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Report No. 240046-R.001 SEISMIC VERIFICATION REVIEW OF AUXILIARY STEAM SYSTEM PIPING THREE MILE ISLAND UNIT I REVISION I June 5, 1998 Prepared for: GPU NUCLEAR ' F I ADC00 F22 EQE INTERNATjONAL .. I
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Page 1: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

Report No. 240046-R.001

SEISMIC VERIFICATION REVIEW OF AUXILIARYSTEAM SYSTEM PIPINGTHREE MILE ISLAND UNIT I

REVISION I

June 5, 1998

Prepared for:

GPU NUCLEAR

' F I ADC00 F22

EQE INTERNATjONAL.. I

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SEISMIC VERIFICATION REVIEW OF AUXILIARYSTEAM SYSTEM PIPINGTHREE MILE ISLAND UNIT I

REVISION I

June 5, 1998

Prepared by:

EQE ENGINEERING CONSULTANTS

Prepared for

GPU NUCLEAR

THREE MILE ISLAND

Route 441

Middletown, PA 17057

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i) 1998 by EQE InternationalALL RIGHTS RESERVED

The information contained in this document isconfidential and proprietary data. No part of thisdocument may be reproduced or transmitted in anyform or by any means, electronic or mechanical,including photo-copying, recording, or by anyinformation storage and retrieval system, withoutpermission in writing from EQE Incorporated.

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2q�.

240046-R-01Revision 1June 5, 1998Page 4

TABLE OF REVISIONS

Revision

0

1

Description of Revision

Original Issue

Minor clarifications onpages 6, 8, 9, 13 &14

Date Anoroved

April 30, 1998

June 5, 1998

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'K-'

L

240046-R-001Revision 1June 5, 1998Page 5

APPROVAL COVER SHEET

TITLE: SEISMIC VERIFICATION REVIEW OF AUXILIARY STEAM

SYSTEM PIPING -THREE MILE ISLAND UNIT I

REPORT NUMBER:

CLIENT:

PROJECT NO.:

240046-R-001

GPU NUCLEAR

240046

REVISION RECORD

REV. NO. DATE PREPARED REVIEWED APPROVED

0 4130/98 @ibLi / Ia)

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SUMMARY

EQE International has performed a seismic verification review of the Three MileIsland Unit 1 auxiliary steam piping which could adversely affect safety relatedequipment if pressure integrity is not maintained.

The review used acceptance criteria derived from earthquake experience data. Aseismic verification walkdown was performed by senior engineers familiar withearthquake experience data, seismic verification techniques developed by theSeismic Qualification Utility Group, and seismic margin assessment procedures.The walkdown was supplemented by a confirmatory analysis of a portion of thesystem. The analysis used seismic margin assessment criteria with the seismicmargin earthquake set to the plant SSE.

The results of the walkdown and the confirmatory analysis are that the systemmeets the seismic criteria in the applicable areas of the plant. It is concluded thatthe system has sufficient seismic margin to maintain pressure integrity during andfollowing a seismic event equal to the plant SSE.

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TABLE OF CONTENTS

PageL SUMMARY . . 61.0 PURPOSE .8

| 2.0 SCOPE ... 92.1 PIPING REVIEWED .: 92.2 SCOPE OF REVIEW .10

3.0 CRITERIA .. 113.1 WALKDOWN SCREENING CRITERIA .11

3.2 SEISMIC MARGIN CRITERIA .13

L 4.0 WALKDOWN .15

5.0 ANALYSIS .16

6.0 CONCLUSIONS .18

7.0 REFERENCES .19

ATTACHMENTS

Page

1_ A. WALKDOWN DATA SHEETS .................................................. A1-A13

B. WALKDOWN PROCEDURE 240046-P-OO1 ........................................... B1-B30

C. TRAINING AND QUALIFICATIONS .................................................. C1-C4

D. ANALYSIS RESULTS - EQE CALCULATION 240046-C4001 .................. D1-D81

E. WALKDOWN PHOTOGRAPHS ................................................... E1-E12

L

14

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1.0 PURPOSE

The purpose of this project was to provide a seismic verification review of theThree Mile Island Unit 1 auxiliary steam system piping in certain areas of the plant.There are safety related equipment located in these areas which could be adverselyaffected by a steam line break.

The system is not safety related and was not designed to plant seismic design basisrequirements. The seismic verification review uses the results of research into theeffects of past strong earthquakes on similar piping to assess if the auxiliary steampiping will maintain pressure integrity during an earthquake equal to the plant safeshutdown earthquake. The review technique is similar to that used to verifyseismic adequacy of equipment using earthquake experience data. This wassupplemented by a seismic margin assessment of a portion of the system.

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2.0 SCOPE

2.1 PIPING REVIEWED

[ The piping that requires seismic verification includes those portions of the auxiliary* steam system which run through the control building, fuel building and auxiliary

building. Isometric drawings of the extent of the main 8-inch diameter header ineach building are included in the walkdown notes in Attachment A. Branch linesfrom the main run were included up to their termination points or where they exitthe building. The piping layout is shown on Gilbert drawing E-304-751 Revision 10.

_ The auxiliary steam piping in the control building consists of an 8-inch diameterheader which runs along the H3 column line. The piping enters the control building(from the intermediate building) through wall penetration 1847 south of the 8bcolumn line. The pipe runs south along the H3 line at approximately elevation 362'-

X 6w. The piping then drops down to elevation 329'-0 at the 1 la column line,continues south approximately 9-feet, and turns west through a wall penetrationinto the fuel handling building.

The auxiliary steam piping in the fuel handling building includes the 8-inch diameterheader and a 2-inch diameter branch line which runs to three manual valves at threeelevations in the decontamination pit. The header enters the fuel building throughthe wall penetration south of the H3 line, and runs to anchor AS-1 55 in thereceiving and shipping area. The header then runs from the anchor to a loop whichturns west and crosses the J column line into the auxiliary building below theelevation 305' floor slab.

The in-scope auxiliary steam piping in the auxiliary building includes the 8-inchdiameter header west of the J column line, and east of the K column line to anchorAS-1 56 at elevation 294'IO. The piping includes branch lines at steam trap AS-ST-31 (as shown in section B-B on drawing E-304-751). piping and steam trapsattached to the L line wall (as shown in isometric view B on Drawing E-304-751),and condensate lines running to the auxiliary steam condensate return unit AS-P-2A/2B. Branch line piping beyond manual valve AS-V-102 is included to the extent

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required for structural boundary only since this valve is normally closed. Auxiliarysteam piping west of the L line wall is not included in the scope since this piping isisolated in the A and B miscellaneous waste evaporator rooms, and in theconcentrated waste storage tank room.

2.2 SCOPE OF REVIEW

The scope of the review is analogous to that used for seismic verification ofmechanical equipment under the USI A-46 program. This methodology is describedin detail in References 3 and 4. The NRC has approved the methodology inReference 5. The extension of the methodology to piping is described inReference 6.

The scope of review consisted of a comparison to the piping in the earthquakeexperience database, a spectral comparison per Reference 4 to verify applicabilityof the database, and a walkdown by a qualified seismic review team to assure thatthe caveats of Reference 6 are met. A representative portion of the piping wasselected for a margin analysis as a benchmark for the walkdown screeningverification.

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3.0 CRITERIA

3.1 WALKDOWN SCREENING CRITERIA

In recent years, a great deal of field data has been collected on the performance ofpiping in earthquakes. EQE International has assembled an earthquake experiencedatabase on structures, equipment, and piping from more than 20 strong motionearthquakes. The database contains a very diverse and robust set of groundmotions, structures, and piping configurations.

Reference 8 contains an analysis of the piping failures (leaks, breaks, collapse, orloss of flow control) observed in the earthquake experience data. Reference 9contains a detailed study of the piping at 20 power plant units in the database inaddition to a literature review of the effects of 29 earthquakes from 1923 to 1985.For above ground welded steel piping, failures were found to be caused only byseismic anchor motion (terminal end equipment movement, header movements atsmall branch connections, or differential movements between buildings), excessivedeterioration of the wall thickness, progressive hanger failure, and seismic inter-action. Failures resulting from seismic inertia stresses were not observed.

These results are further supported by the results of full scale testing. Reference10 states:

Experience data collected by SQUG and others and high-level seismic tests onpiping conducted in foreign countries and in the U.S. show that piping is notsusceptible to failure resulting from seismic inertia loads. The only observedinstances of piping failure during the SQUG program to collect seismicexperience data were due to relative motion of anchor points and inadequate ornonexistent anchorage of tanks or equipment for sites with zero periodacceleration between 0.25g and 0.60g.f

Reference 6 contains guidelines for visually evaluating piping against the failuremodes observed in the earthquake experience data. The evaluation is performed bya seismic review team using procedures similar to those used for equipment under

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the USI A-46 program (Reference 4) and for piping under the EPRI seismic marginassessment guidelines (Reference 7). The detailed inspection procedures arecontained in EQE procedure 240046-P-001, included as Attachment B of thisreport.

A key element in the criteria is the experience and qualifications of the seismicreview team members. References 3 and 7 give qualifications for seismic reviewteam members. In summary, these are:

* Knowledge of earthquake experience data

* Knowledge of nuclear design standards and practice

* Ability to perform fragility/margins type evaluations

* General understanding of SPRA conclusions

* General knowledge of plant systems

* Minimum of five years applicable experience

* Professional Engineer registration

The experience data must be shown to be applicable to the piping underconsideration. As shown in Reference 9, the database contains an enormousamount of steam piping of size, construction, operating temperature and pressure,and support (primarily rod hung) similar to the auxiliary steam system piping at TMI.

The experience data must also be applicable in terms of level of excitation.Reference 4 gives criteria for this in the form of a generic bounding ground responsespectrum which must envelop the site design basis response spectrum at 5%damping. TMI-1 was determined to meet this criterion from USI A-46documentation.

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3.2 SEISMIC MARGIN CRITERIA

A portion of the piping which includes the 8-inch diameter header from anchor AS-155 in the fuel handling building to anchor AS-1 56 in the auxiliary building wasselected for confirmatory analysis. This portion of the piping was selected becauseit contains branch lines which were judged to have the potential to restrain freemovement of the 8-inch header, resulting in high stresses at the branch lineconnection to the header, and which contain threaded connections susceptible tobrittle failures. The analysis was a seismic margin analysis using the conservativedeterministic failure margin (CDFM) approach as described in Reference 7. Thisapproach is summarized in Table 3-1.

For this project, the seismic margin earthquake (SME) was taken as the TMI-1 safeshutdown earthquake (SSE). Broadened floor response spectra from the TMI-1 USIA-46 review were conservatively used for seismic demand determination rather

than the unbroadened, median centered floor response spectra with frequencyshifting called for in Reference 7. The piping was linearly analyzed using 56

L; damping per Reference 7. Resulting stresses were compared to ANSI B31.1allowables equivalent to ASME Service Level D (comparing Equation 12 stresses to3.0 Sh). The 0.8 factor to account for inelastic energy'absorption wasconservatively not applied.

The analysis used the floor response spectra in the vertical and two horizontaldirections with stresses combined by SRSS.

L-L

0 X -46R~vtvl .oc

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TABLE 3-1

SUMMARY OF CONSERVATIVE DETERMINISTIC FAILURE MARGIN APPROACH(From Reference 7)

Load Combination: Normal + SMEGround Response Spectrum: Conservatively specified (84% Non-Exceedance

Probability)DConservative estimate of median dampingStructural Model: Best Estimate (Median) + Uncertainty Variation In

FrequencySoil-Structure-Interaction Best Estimate (Median + Parameter VariationMaterial Strength: Code specified minimum strength or 95%

exceedance actual strength if test data are available.Static Capacity Equations: Code ultimate strength (ACI), maximum strength(AISC), Service Level D (ASME), or functional limits.If test data are available to demonstrate excessiveconservatism of code equations, then use 84%exceedance of test data for capacity equation.

Inelastic Energy Absorption: For non-brittle failure modes and linear analysis, use80% of computed seismic stress in capacityevaluation to account for ductility benefits, or performnonlinear analysis and go to 95% exceedanceductility levels.*

In-Structure (Floor) Spectra Use frequency shifting* rather than peak broadeningGeneration: to use account for uncertainty plus use mediandamping.

*Conservatively not used in this evaluation

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4.0 WALKDOWN

The walkdown covered the areas described in Section 2. The walkdownrequirements were specified in EQE Procedure 240046-P-001, which is included asAttachment B to this report. The seismic review team (SRT) was made up of twosenior EQE personnel who meet the SRT requirements of References 4 and 7. TheSRT qualification sheets are included as Attachment C.

The results were documented on screening and evaluation worksheets. Thecompleted worksheets are included as Attachment A to this report.

Hanger anchorages were visually inspected by the SRT and found to be acceptableper Procedure 240046-P-001. For anchorage using expansion anchors, the base.plate and anchor bolt arrangement was compared to standard industrial designpractice per the experience of the SRT members. Anchor bolts were inspected forsigns of looseness, lack of washers, oversize bolt holes, gaps under the base plate,and improper bolt spacing and edge distance. Welded anchorages were visuallyinspected for normal workmanship and thickness.

Since the main run piping is supported on rod and spring hangers without lateralrestraint capability, special attention was given to potentially damaging seismicinteractions between the piping and its supports, and the nearby structures,systems and components. Seismic movements of up to six inches in any horizontaldirection were assumed.

The results of the SRT walkdown were that the piping and supports met thewalkdown criteria, with one exception, and were judged by the SRT to be able tomaintain pressure integrity during the safe shutdown earthquake (SSE). The oneexception was the branch piping at steam trap AS-ST-31, which contained threadedconnections and had a rigid restraint in close proximity to the flexible main run.This piping was selected as the bounding case for further analysis.

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5.0 ANALYSIS

A portion of the in-scope piping was analyzed by the conservative deterministicfailure margin (CDFM) method as described in Section 3. The portion of the piping

L analyzed was selected because it contained the only area of concern from thewalkdown. The seismic margin earthquake (SME) was set equal to the plant safe

L shutdown earthquake (SSE). The stresses were compared to 3.0 Sh, which is theASME Class 3 Level D service limit divided by 0.8 to account for inelastic energyabsorption.

The piping analyzed included the 8-inch diameter piping from anchor MK-AS-1 55 inL the fuel handling building to anchor MK-AS-1 56 in the auxiliary building. This piping

is shown on Gilbert Associates drawing E-304-751. The model also included theL branch piping to and from steam trap AS-ST-31. This piping is shown in section B-

B on drawing E-304-751. The two 1-inch diameter lines were modeled sufficientlyfrom the steam trap that the effects on the area of concern (the piping between the8-inch main run and the guide support on the 3/4 inch threaded piping) would be

L included.

The analysis included deadweight and thermal conditions, as well as two horizontalL and one vertical components of earthquake. The earthquake excitation consisted of

N-S, E-W, and vertical floor response spectra at 5% damping. Vertical responsespectra were taken as 2/3 of the horizontal.

The results were that the highest stress occurred in the 1-inch diameter branch atL the 2x1x3/4 inch tee immediately adjacent to the 8-inch main run piping. The

maximum stress was 35 ksi, or 83% of the CDFM capacity. Stresses in the 8-inchmain run were less than 10 ksi. Forces in the hangers on the main piping werecompared to the design loads on hanger drawings, and the hangers were judged tobe acceptable. Anchorage loads for the guide support on the branch piping werecomputed and found to be small.

L The maximum horizontal displacements were computed to be approximately four- inches. This compares favorably with the six inches assumed during the walkdown.

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240046-R-001Revision 1June 5, 1998!- -Page 17

The analysis results are contained in Attachment D to this report. The analysis wasperformed in accordance with 1 OCFR 50 Appendix B Quality Assurance

L requirements under the EQE Engineering Quality Assurance Program.

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6.0 CONCLUSIONS

EQE International has performed a seismic verification walkdown of the applicableportions of the auxiliary steam supply system by a qualified seismic review team. Ithas also performed a confirmatory seismic margin analysis of a bounding portion ofthe system.

The results show that there is sufficient seismic margin inherent in the as-builtpiping to conclude that the probability of a pipe break occurring during a safeshutdown earthquake is extremely low. Therefore, it is concluded that this systemwill not adversely affect the operability of safety related equipment in the plant.

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!

7.0 REFERENCES

L 1. USNRC. February1997. GenericLetter87-02,VerificationofSeismicAdequacyof Mechanical and Electrical Equipment in Operating Reactors, Unresolved SafetyIssue (USI) A-46.m

2. EQE Incorporated, Piping Seismic Adequacy Criteria Recommendation Based onPerformance During and After Earthquakes,* 2 Volumes. Prepared for the ElectricPower Research Institute, RP-2635-1, February 1987.

3. SSRAP Report, "Use of Seismic Experience Data to Show Ruggedness ofEquipment in Nuclear Power Plants," Senior Seismic Review and Advisory Panel,

L Revision 4.0, February 28, 1991.

4. Bishop, Cook, Purcell and Reynolds; EQE Incorporated; MPR Associates, Inc.;Stevenson & Associates; URS Corporation/John A. Blume and Associates.December 1988. "Generic Implementation Procedure (GIP) for Seismic Verification

- of Nuclear Plant Equipment," Revision 2 corrected 2/28/91.

5. USNRC, "Supplemental Safety Evaluation Report No. 1 on SQUG GenericImplementation Procedure, Revision 1," June 29, 1990.

6. P.D. Baughman, et al., "Seismic Evaluation of Piping Using Experience Data,"Second Symposium on Current Issues Related to Nuclear Plant Structures,L Equipment and Piping, December, 1988.

7. EPRI NP-6041, Revision 1, uA Methodology for Assessment of Nuclear Power PlantSeismic Margin,", Electric Power Research Institute, Palo Alto, CA, prepared byL NTS Engineering, Long Beach, CA, and RPK Consulting, Yorba Unda CA, July1991.

L 8. P.D. Smith, et al., "Experience Data on the Performance of Piping Systems inEarthquakes," Proceedings of the 1985 ASME Pressure Vessels and PipingConference, June, 1985.

9. M.S. Silver, et al., "Piping Seismic Adequacy Criteria Recommendations Based onPiping Performance During and After Earthquakes," EPRI RP-2635-1, February,1987.

10. USNRC, "Regulatory Analysis for Resolution of Unresolved Safety Issue A-46,Seismic Qualification of Equipment in Operating Plants." NUREG-121 1, February,1987.

11. Senior Seismic Review and Advisory Panel (SSRAP), "Review Procedure to AssessK> Seismic Ruggedness of Cantilever Bracket Cable Tray Supports," Prepared forSeismic Qualification Utility Group, October, 1988.

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240046-R-M1Revision IJune 5, 1998

- Page A I

ATTACHMENT A:

WALKDOWN DATA SHEETS

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.L I

stem Name

L Equip. ID No.

I Une Identifier

Bldg. C

SCREENING AND EVALUATION WORKSHEET (SEWS)

Aj4V$tG1Adf Srq 1V s, moM . Az/L,&4%-

V1/4 Equip. Class 23-Piolna System Without Dynamic Analysis/IA CDAV,7AS'L 4WuL

?#I SOQ,'y 6SWi47/- LI4', 5tC . N Iv0-1

I, Floor Elevation(s) 55•' 2

Drawing No. 64I ar x -3W- -75i "V 10

e..~-iA A~i0~f'd JJcdar - . ... 44. ~.I1 '~- 6--- w' -rII UWW411W V 0JJC:. INW. - - -If!:

L- Operating Pressure/Temperature

. -1 - �- . I � -� - W- I

PSIG °F___

' Pioina System Boundar

Description AUX -57tv41/ llA4/ 41iiWIW Mg( CO477AOL.. 6(1fL ,LO/W6, 1 P

/01,AI f1J1As -5 AS r 4P7X, 9.L- 34Z'-164 FIZeNl ITf I- COw,~ ,

ulvAzj. Jl('3 r Af ,/3 P/P ( f gL, '- 0 k T7 S

L or sketch (attach sheets as necessary)v,5!9£r 7Y!du1w 1qLL ,AFvYr/?40,'V.'J (7A*,F&CC 4(aLOV6r-.

nctionalitv Reauirement

-1J DuringSeismic~vn } ,4~~c 7-~^K J

L 2. After Seismic Event AMSo r /%OUz4.AY

Evaluation by -/4.d -

DatN U9 N U

Date #qZ/

L The piping system boundary Includes the piping configuration from component to component (or other anchorpoints). Other interconnections to the subject piping are included from the connection to the first anchor point

I or component. An anchor Is defined as a point at which the pipe Is restrained In 3 directions and 3 rotations ori through a series of supports which provide equivalent restraint of the pipe.

Caveats- Pi2ina

L 1. Does the piping configuration appear to have adequate flexibi-lity to accommodate the thermal loading?

2. No visible damage?L 3. No significant visible rust/corrosion deterioration?

4. Are all fittings standard?5. No potentially brittle connections (threaded joints, cast Iron

fittings, etc.)?6. Does the piping configuration appear to have adequate flexibil-

lity to accommodate differential movement of vibrating components?7. IDo the support spans appear to follow ANSI 631.1 requirements?

No unreinforced main/branch connections?No unusual pipe attachments?

U N/A

NNNN

U NfAU N/AU NfAU NJA

Y N U )

Y N$N

U N/AU N/A'U N/A

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i tL SCREENING AND

I L~1p. ID No. AmU c5X4Gf /4/e COA'7oc. 6C//f4,,v6-

) EVALUATION WORKSHEET (SEWS)

Equip. Class 23-Pioina System Without Dynamic Analysis

10. No heavy valves supported by small bore vent and/or drain pipes11. Does the piping configuration at building joints appear to have

L adequate flexibility to accommodate seismic Induced differentialmovement?

12. No in-line components which can be subject to impact due to seismicInduced movements?

13. No fittings (bellow, flexible hoses, etc.) which can be adverselyaffected by seismic Induced differential movements?

14. Free of piping attached to poorly anchored equipment?A' 15. No stiff piping attached to flexible equipment?

16. No stiff branch piping attached to the main line with potentiallysignificant movements?

17. No other concerns (if no, comment on separate sheets and attach)?

N UN U

NfAN/A

0 N U N/A

() N U N/A

() N U NIA9 N U N/AO) * N U NfA

(I N UAre the caveats met?

L ( N U

Date - */i'4Evaluation by __ _ _ _ _

Caveats - Suimorts

1 No visible damage?No visible rust/corrosion deterioration?L iNo unusual design?No customized parts used in place of catalog parts, whichappear Inadequate?

D . Are the support settings (spring hangers, etc.) adequate?L 6. Free of any sliding surfaces which appear not to be performing

their intended function?7. No one-way guide support with the potential for the piping toL slide off during a seismic event8. Free of support details which appear to have been altered to

accommodate Interferences or other problems?9. Do nuts have full thread engagement?10. No friction beam clamps?11. Do concrete expansion bolts appear to have adequate

| Bolt centerline to plate edge distanceL Bolt centerline to bolt distance

Bolt centerline to concrete edge distanceBolt centerline to empty hole

Lx 12. Does the anchorage appear adequate (attach SEWS 25A through25.F, as required)?

13. No additional concerns (f no, document comments on separatesheet and attach).

Are the above caveats met?

Evaluation by__ __ __ __

N UN UN UN U

& N U

& N U

) N UN U

N/AN/AN/ANIA

N/AN/A

N/A

N/A

N/AN/A

I;) N U NYAUY N U NfA

O N N/A

O N U

Date 5.-U -Z9-f

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SCREENING AND EVALUATIL, tC/ j. 57zm

I-~uip. ID No. Py' CONML 6'- Equip.Class

ION WORKSHEET (SEWS)

23-Pidno System Without Dynamic Analysis

Interaction EffectsI

1. Soft targets free from impact by nearby equipment or structures? 6 N U NWA2. Distribution branch lines have adequate flexibility? Alo 6Atfv' (,4rXs & N U3. No collapse of overhead equipment, distribution systems, or (& N U w

I masonry walls?4. No other concerns? (9 N U NIA

I ~Is equipment free of Interaction effects?

Evaluation by_ _ _ __ _ _

Is the piping system seismically adequate?

@) N U

Date ~-VZ-7ff

P N U

L Comments P/Pf4'6- INa.vO4S 7ME AOWLcN,,W- S-r.os/4,r:

ASIVY. hts-'q. '4's-1509 A-/S-

#511.3 AMxS-g

I All aspects of the equipment's seismic adequacy have been addressed.

L Evaluated by: J / (44

(ll team members) 6.-cAy?t . iI

Date: q-2 -i-f

-- 141.)k

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[ JOB rA / ir / JOB NO. Z° '

SUBJECT AUXYIC44Y acEtI /A CON77ML eW& CALC NO.

! 9 J-2DATE3'as CHD _ DATE _______ SHEET NO. _OF

I 7 L~ 41

I A

co)p

1*0131

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SCREENING AND EVALUATION WORKSHEET (SEWS)

R?14M4,/Z SA H4 IA] 'V4EL (4410AU1V6-- 3,uA1C-Kl-4sterm Name

- Equip. ID No. 4'14 EnUinU-.1 as 23-PiDIn_ System Without Dynamic Analvsis, "r _. _

Une Identifier

Bldg. F'

?' $5//#*'dY NR4D I,,. / LV f5(11L0'v-.-A, It A'6AcqICoV 'rlav 7a

f ta 77AVch, 64 V Floor Elevation(s) 9o;So'P.C#OVT4f/1(d4i7o&Al'pr

Drawing No. 6-iC-szr A- 3 o - 7S e, lo

Drawina SDec. No. W14o41L SA4.C. 54-5sYCA q 5596Operating PressurerTemperature PSIG °F

--------- -

Pioina System Boundary*

Description A jG 5 A4P ','kW6- WINH mA- Ae M40 moV& 4We6k

(Isuy /plo.) i9r X4 3i5z$ -~O#3 ofieA W ACvd~-f2:.S j'sC sv 0 ,: 11.t w s, 3z'reg 4fs 0>5 ors omox 7touw(tMAS- 4.r- 4L'A'S Fvoi'r AC/44. 101wr Ir A. y~'¶OA4Moo dM.1 21'} A#O WEsr 440,C. -&" 7D cOWS-S

_ or sketch (attach sheets as necessary) j tpjvC vtrM 4/y. e06t, #Ctd'WS ZA# 4dA41

-qlncionality Recuirernen UwP4;qPNWA7 A/W",-M1 0r

During Seismic Event? IYp, ,n r A0,nlf

2. After Seismic Event J

Evaluation by V I/C(

DtN UT) N U

Date V-Z4--!f

*Te piping system boundary Includes the piping configuration from component to component (or other anchorpoints). Other interconnections to the subject piping are included from the connection to the first anchor pointor component An anchor Is defined as a point at which the pipe Is restrained In 3 directions and 3 rotations orthrough a series of supports which provide equivalent restraint of the pipe.

Caveats - PipLna

1. Does the piping configuration appear to have adequate flexdbi-lity to accommodate the thermal loading?

2. No visible damage?3. No significant visible rustlcorroslon deterioration?4. Are all fittings standard?5. No potentially brittle connections (threaded joints, cast Iron

fitings, etc.)?6. Does the piping configuration appear to have adequate flexibil-

lity to accommodate differential movement of vibrating components?7. Do the support spans appear to follow ANSI B31.1 requirements?

No unreinforced main/branch connections?y No unusual pipe attachments?

0 N U N/A

N U N/AN U N/AN U N/AN U N/A

N U )

N U NJAN U NIAN U N/A

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SCREENING AND EVALUATION WORKSHEET (SEWS)

> ID No. A? )e 5J4M4 IA/ Equip. Classm 23-Pioina Svstem Without Dvnamic AnalvsisFVFL% H4)Vf s i5L/ V6-

10. No heavy valves supported by small bore vent and/or drain pipes11. Does the piping configuration at building joints appear to have

adequate flexibility to accommodate seismic Induced differentialmovement?

12. No In-line components which can be subject to Impact due to seismicinduced movements?

13. No fittings (bellow, flexible hoses, etc.) which can be adverselyaffected by seismic induced differential movements?

14. Free of piping attached to poorly anchored equipment?15. No stiff piping attached to flexible equipment?16. No stiff branch piping attached to the main fine with potentially

significant movements?17. No other concerns (ff no, comment on separate sheets and attach)?

Are the caveats met?

N UN U

NZANIA

N U NWA

N U N/A

N U NWAN U NIAN U NMA

N U

N U

Evaluation by ' WC/ ( Date q -Z/-j(

Caveats - Suncorts

1. No visible damage?2. No visible rust/corrosion deterioration?

'No unusual design?_Jo customized parts used In place of catalog parts, which

appear Inadequate?;. Are the support settings (spring hangers. etc.) adequate?W. Free of any sliding surfaces which appear not to be performing

their Intended function?No one-way guide support with the potential for the piping toslide off during a seismic event.Free of support details which appear to have been altered toaccommodate Interferences or other problems?Do nuts have full thread engagement?

). No friction beam damps?Do concrete expansion bolts appear to have adequate

Bolt centerline to plate edge distanceBolt centerline to bolt distanceBolt centerline to concrete edge distanceSBolt centerline to empty hole

Does the anchorage appear adequate (attach SEWS 25A through26.F, as required)?No additional concerns (If no, document comments on separatesheet and attach).

the above caveats met?

NNNN

U N/AU N/AU NWAU N/A

N U WtAN U N/A

N U N/A

N U .NA

N U . NfAN U (E!3Y

NN

U N/AU NWA

N/A

U

Evaluation by Dew - .. Date My Z/

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SCREENING AND EVALUATION WORKSHEET (SEWS)K> 14' 31SMA~f //V pU-1-L..

Equip. ID No. /4A'/IA'U (/LOW Equip. Class 23-Pilina System Without Dynamic Analvsis

Interaction Effects

- 1. Soft targets free from Impact by nearby equipment or structures? N U2. Distribution branch lines have adequate flexibility? N U3. No collapse of overhead equipment, distribution systems, or N U

masonmy walls?4. No other concerns? @j N U

L Is equipment free of Interaction effects? ( N U

Evaluation by -tI ( - - Date j

Is the piping system seismically adequate? ()N U

NIANWAN/A

NJA

Comments fk',shf- I4/LC . gage4Cwol, SimAgvr-

L4AS 4''-J/, S- fS7 4-/g3 s-J AS-/3

z9 Asv L : /N-37 /LW-yo1 ?v A/o rYwsmu~s s OVA6VINC- 71 7)MC O jos7Zrjn' Ar

_ All aspects of the equipment's seismic adequacy have been addressed. PAfOs "Li ,

Evaluated by: _

(All team members)

Vtm/(ny

jrAf4E5 7 -* //Date: Yg /w-f

/V h/s-

L-

f :I

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JOB TAf £'er / JOB NO. 2Uoy6V SUBJECT i' tmdy s7EA MI >a/tL BC06-D CALC NO.

Y / DATE '4 'St CHK'D DATE. _______ SHEET NO. OF__

_ U- SA

fairlyvil, 301

4/

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lI..ystem Name

Equip. ID No.

SCREENING AND EVALUATION WORKSHEET (SEWS)41VXRLzYf 5Xf INV AUXAay gofdl-

Equip. Class 23-Pimina System Without Dynamic AnalysisUne Identifier 9" f 51MY Me9Ahe -JW 4OXrLI4C ' 61I/LO/A- 7W WL 4gudi2. 4S-/S6

/F "src OlUAW W.V S ~ V f,Bld. Ah)I</4A Floor Elevation(s) W'-" 17 70 AVK, Sf4ADrawing No. 6-I L64.7- N1O, £ -0Y V -7/ /ifxV, /a C47/ZgTV*4 rcDrawing Sm No.n M14)J1AL 5B.r, SP - qcsuq v ci- < (A t5 -p2A )

-r,--. ---- - - - -.- ---- -1 -- I I -F -- W I

Operating PressuremTemperature PSIG

MPlina Svstem Boundary'

Description Wk 5T7AA P//bv P 1I1h7Yrf/ : VCY/tIoAl2, a '44'6-,0 *VAoYf~d4.E'x ),,,ws wiS-w 4/7wjvol l.J, AP,te. 7~3~M L1VT m Q

6 "~v- Q 7LVS T* 4v 1w,%g wrfr iv 4@o'Cjmoz/PN- Rz-rf 1W.41 F(g ,Lfwgz.sbus a a

or sketch (attach sheets as necessary) 1,r ( 4r @ (7 CJ PfAC 4k'/.qnctionalith Reguirement

- During Seismic Event7 MP4'- M1hf' 'Y#fAM/IW

2. After Seismic Event JEvaluation by __ _

Dat N U@ N U

Date Ys-U-tv

'The piping system boundary Includes the piping configuration from component to component (or other anchor- points). Other interconnections to the subject piping are Included from the connection to the first anchor pointor component. An anchor Is defined as a point at which the pipe Is restrained In 3 directions and 3 rotations orthrough a series of supports which provide equivalent restraint of the pipe.

Caveats - Pipina

L 1. Does the piping configuration appear to have adequate flexibi-lity to accommodate the thermal loading?

2. No visible damage?3. No significant visible rust/corosion deterioration?4. Are all fittings standard?5. No potentially brittle connections (threaded joints, cast Iron

fittings, etc.)?L 6. Does the piping configuration appear to have adequate flexibil-

Miy to accommodate differential movement of vibrating components?7. Do the support spans appear to follow ANSI B31.1 requirements?

U_ ' No unreinforced main/branch connections?y ~ No unusual pipe attachments?

N U NIA

U NIAU NJAU NfA r3/'4i ' erel#J4U N/A 1.4r SMW

U N/AU N/AU NfA

NNN

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SCREENING AND EVALUATION WORKSHEET (SEWS)i I . W ux S ap r4/4' ES

i "uip.ID No. gme i yd&,% 114W6 Equip.Class -23-Pidna System Wdhout Dv'namic Analysis

10. No heavy valves supported by small bore vent and/or drain pipes11. Does the piping configuration at building joints appear to have

adequate flexibility to accommodate seismic induced differentialmovement?

12. No in-line components which can be subject to Impact due to seismicInduced movements?

L 13. No fittings (bellow, flexible hoses, etc.) which can be adverselyaffected by seismic Induced differential movements?

14. Free of piping attached to poorly anchored equipment?L 15. No stiff piping attached to flexible equipment?

16. No stiff branch piping attached to the main line with potentiallysignificant movements?

17. No other concerns (if no, comment on separate sheets and attach)?

Are the caveats met?

N(5N

(g N

M N

a6

Pi N

Date - 2 f-f

U N/AU N/A

U N/A

U N/A

U NIAU N/A a*c'e6wj AU NMA Ar %7, Y&V

(a~s 4t-106U CAG4o tb

U

Evaluation by 'ICt 4A'vk CI

Caveats - SUDDOrtS

1. No visible damage?No visible rust/corrosion deterioration?No unusual design?No customized parts used In place of catalog parts, whichappear Inadequate?! 5. Are the support settings (spring hangers, etc.) adequate?

L 6. Free of any sliding surfaces which appear not to be performingtheir Intended function?

7. No one-way guide support with the potential for the piping toL 8 slide off during a seismic event.8. Free of support details which appearto have been altered to

accommodate Interferences or other problems?9. Do nuts have full thread engagement?

L 10. No friction beam damps?11. Do concrete expansion bolts appear to have adequate

- Bolt centerdine to plate edge distanceL Bolt centerline to bolt distance

Bolt centerline to concrete edge distanceS Bolt centerline to empty hole

12. Does the anchorage appear adequate (attach SEWS 25A through25.F, as required)?

13. No additional concerns (If no, document comments on separatesheet and attach).

Are the above caveats met?

NNNN

U N/AU N/AU NIAU NIA

N UN U

N/AN/A

V

N U N/A

U N/AN

N U N/AN U __

U NIAU NIA

N/A

O N U

Date -ZEvaluation by .=

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L SCREENING AND EVALUATION WORKSHEET (SEWS)L)p U) S 1-49AI 141

Equip. ID No. 140XU4'ty 4A11vi4 Equip. Class 23-Piping System Without Dynamic Analysis

Interaction Effects

I

L!

L

I. Sou wrlijs iree from Impac by nearby equipment or structures?2. DistrIbution branch lines have adequate flexibility?3. No collapse of overhead equipment, distribution systems, or

masonry walls?4. No other concerns?

Is equipment free of interaction effects?

Evaluation by_ ___ _

Is the piping system seismically adequate?

(3 N Ur2 N UDt N U.

& j N U

. D- N U

Date y Wl

oe' U

WANtANfA

NIA

Comments PAi06- /A'C(L'41ZS MeX rOc W 6 £ Mowqs.

L A : /ZSWvs-lg. , -?S-i/ q , 6s-,qb,45-,sfg SS/y-tPs&AM

I 'O'' ,2 L/ 6* es /Z 2L All aspects of the equipments seismic adequacy have been addressed.

Evaluated by: _ L t 1 .,/ Date: Y/

(All team members) _ 4/Li/f t

L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Li

L

il

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LI YJBY Jv~W_

I-

JOB Jew £4tvr ' JOB NO. Z_ _____

SUBJECr 4VXIL,4.4 0 1Y A AUK CALC NO.

DATE a- 1Z'f CKD (7s DATE /Z 3/ ^ SHEET NO. OF

4-1

t*g'l

ei;b

~~4,"tni

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I i

L'

240046-R-001Revision IJune 5, 1998Page B I of 30

ATTACHMENT B:

WALKDOWN PROCEDURE 240046-P-001

COVER SHEET AND 29 PAGES

Il

,I

6-I

: _46R1 revI .doc

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EQE PROCEDURE TO PERFORM DATA GATHERING AND SCREENINGWALKDOWN FOR THE AUXILIARY STEAM SYSTEM PIPING

AT THREE MILE ISLAND UNIT 1

Project Performed For:

GPU Nuclear Corp.

K>PROCEDURE NO.:

REVISION NO.:

DATE:

240046-P-001

0

April 29, 1998

PREPARED BYIDATE:

- REVIEWED BY/DATE_

APPROVED BYIDATE_

.r/ A 9 4- 7-1go.. I d-7"9

�-!q f

- ,

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IK)

Procedure 240046-P-001Revision 0April 30, 1998Page 3

TABLE OF REVISIONS

Revision Description of Revision Date Aporoved

0 Original Issue April 29, 1998

K>

24046PRO.DOC

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Procedure 240046-P-001Revision 0April 30, 1998Page 4

L TABLE OF CONTENTS

PageLi1.0 SCOPE ......... 5

2.0 RESPONSIBILITIES .................. 6

LL 3.0 DEFINITIONS ......... '7

L 4.0 METHODOLOGY ......... 95.0 PROCEDURE ............................ 12

5.1 PIPING AND PIPE SUPPORTS .125.2 ANCHORAGE .16

L 6.0 SEISMIC INTERACTION REVIEW .19

7.0 REQUIRED DOCUMENTATION. 208.0 QUALIlY ASSURANCE .21

L 9.0 REFERENCES .22i

ATTACHMENTS

lA. TRAINING VERIFICATION SHEET .A-1 TO A-2

B. SEISMIC REVIEW TEAM MEMBER QUALIFICATION SHEET ...... B-1 TO B-2

L C. SCREENING AND EVALUATION WORKSHEETS .................................... C-1 TO C-4

24046PRO.DOC

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Procedure 240046-P-001Revision 0April 30, 1998Page 5

1.0 SCOPE

This procedure describes the activities and required procedures for implementationof a data gathering and screening walkdown for seismic verification of the awdliarysteam piping system at Three Mile Island Unit 1.

The purpose of this activity is to gather and document the information required forverification of the seismic adequacy of this system.

All work performed for this project will be done in accordance with the latestrevision of the EQE Quality Assurance Manual (Reference 4).

24046PRO.doc

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Procedure 240046-P-p01Revision 0April 30, 1998Page 6I

2.0 RESPONSIBILITIES

The project manager shall be responsible for ensuring the implementation of thisprocedure.

The project manager shall be responsible for ensuring that the seismic review teammembers are trained in accordance with this procedure prior to performing thewalkdown. This will be documented on training verification forms included asAttachment A to this procedure.

The project manager shall be responsible for organizing and directing thewalkdowns in accordance with this procedure. The individual seismic review teammembers shall be responsible for the. actual performance of the walkdowns anddocumentation of the results.

L24046PRO.doc

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Procedure 240046-P-001Revision 0April 30, 1998

L Page 7L

3.0 DEFINITIONS

LA. SEISMIC REVIEW TEAM

L The Seismic Review Team (SRT) engineers performing the evaluation must bedegreed engineers, with considerable experience in structural and/or earthquake

L engineering applicable to nuclear power plants. SRT engineers shall meet therequirements for seismic capability engineers as defined in References 3 and 8.I.The SRT engineers shall successfully complete a training course on the backgroundfor, the philosophy behind, and the use of these seismic evaluation guidelines. At

L least two SRT engineers shall comprise a team of which at least one shall be alicensed professional engineer.

L. As a group, the SRT shall possess knowledge in the performance of equipment,systems, and structures during strong-motion earthquakes in industrial process andpower plants. They shall also understand conduct of nuclear plant walkdowns;nuclear design codes and standards; and seismic design, analysis, and test

L qualification practices for nuclear power plants.

The core SRT may be supplemented by additional personnel for the purpose ofL documenting field conditions not shown on plant drawings. The qualifications forthese personnel will be determined by the project manager.

Each engineer involved in the walkdown or evaluation shall submit a resume ofqualifications and experience per Attachment B. In addition, documentation of

L having completed the required training shall also be on file.

B. EVALUATION

L An assessment of the seismic adequacy of the as-installed piping and pipe supportsusing the Screening and Evaluation Worksheets included as Attachment C. Theseworksheets were developed based on predicted failure modes as defined in

., Reference 9.

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Procedure 240046-P-001Revision 0April 30, 1998Page 8

C. OUTUER

As-installed piping that does not meet the guidelines of this procedure. Outliers aredispositioned by office based review using analysis or other accepted means.

L

1.

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Procedure 240046-P-001Revision 0April 30, 1998

L -Page 9

4.0 METHODOLOGY

Very few components of nuclear plant systems are unique to nuclear facilities.Nuclear plant systems include electrical panels and switchgear, air compressors,

- tanks, piping, conduit, and many other' items that are common components ofconventional power plants and industrial facilities. The seismic experience database was developed to address the problem of seismic qualification for equipmentwhich was purchased as common "off the shelf" items or for commodities whichrequire an upgrade in seismic classification. By reviewing the performance offacilities that contain equipment similar to that found in nuclear plant, conclusionscan be drawn about the performance of nuclear plant equipment during and after adesign basis earthquake. Typical sources of seismic damage for different classes ofequipment and piping have been obtained and are explained in detail in References

L and 9.

Visual and design document review examination of piping systems are to beperformed to assess valve vulnerabilities and potential for pipe failure. SeismicL inertial effects in welded steel piping systems are not considered to be primaryfailure initiators. Inadequate piping system flexibility and excessive relative supportdeflections are the more likely contributors to seismically-induced failures thandynamic shaking effects for welded steel pipe. Impact of valve operators onadjacent structures or equipment are the only credible valve failure modes of

L concern. Items to be observed in the walkdown are:

1. Preferably, the piping systems should not be fabricated with threaded orvictaulic or other mechanical friction-type of connections. These detailsproduce a non-ductile system that is sensitive to inertia loads and supportconfigurations for strong motion earthquakes. When observed, these detailsneed to receive special attention.

2. The use of cast iron pipe is a potential problem since it does not have thestrength or ductility of steel, and usually has low capacity connections.

> 3. Branch lines out to their first support could be a potential concern if they donot have adequate flexibility. The necessary flexibility can come fromeither the supports or the pipe routing. Short, straight branch lines that are

| ~24046PRO~doe

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Procedure 240046-P-001Revision 0L 0April 30, 1998Page 10

L..

connected to relatively rigid anchor points are candidates for failure if themajor run pipe is not restrained from motion close to the branch.

4. The connection of pipe into vessels, heat exchangers, and other equipmentanchor points could be of concern if the details used could transmitexcessive loads to the nozzles. This situation could result from:

a. Flexibility in the equipment support with the pipe system being rigidlysupported near the equipment.

b. Long unsupported runs of pipe adjacent to the equipment, particularly ifiJ heavy in-line components are mounted near the equipment.

L c. Pipe support failure near the equipment. Any indication of potentialweak links in these supports should be noted for further evaluation.

5. Proximity of valve operators to structures, components, or other subsystemsshould be examined. The principal concern for active valves is that theoperator support may be bent so that the valve will not change position ordemand. For passive valves, the only concern is fracture of the top worksL that could breach the pressure boundary.

6. Multiple failure of threaded rod supports (unzipping) on non-seismic pipingcould, in instances of potentially long runs of pipe, result in piping failure andsubsequent flooding problems.

7. The use of vibration or shock isolation systems on equipment to which pipingattaches could adversely affect the seismic performance if the piping system

L if the pipe segments to the first support on either side of this component areL not flexible enough to accommodate the equipment motion.

8. The piping details across seismic gaps or between two buildings should be* reviewed. Insufficient flexibilities in the routing detail could affect the pipeintegrity for seismic differential building motions.

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Procedure 240046-P-001Revision 0April 30, 1998Page 11

9. The increased pipe seismic responses may produce seismic interactionconcerns. The following conditions should be reviewed during thewalkdowns:

a. That supports can accommodate motions in directions other than theprimary load path. This concern is applicable to the clevis ends ofstruts and snubbers, and is not a concern unless there exists follow-onconsequences, as seismic missiles or seismic interaction.

b. Relatively flexible spans that could have seismic interactionramifications.

c. Supports that only restrain dead weight loads and do not restrict theL pipe from sliding off.

24046PR0.doc

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Procedure 240046-P-001Revision 0April 30, 1998Page 12

5.0 PROCEDURE

5.1 PIPING AND PIPE SUPPORTS

Piping systems in the seismic experience database have performed very well inearthquakes, even though they were typically designed for dead and operating loadsonly, with little or no consideration for seismic loads (Reference 7). Databasepiping and selective analytical review are the basis for review of the auxiliary steamsystem piping.

In order to use experience data to evaluate piping the following must bedemonstrated: (1) database representation, and (2) known seismic vulnerabilities ofpiping must be addressed. Instances of seismic damage to database piping havebeen the result of seismic anchor movement (SAM), seismic systems interaction(and impact), and corrosion. The database has demonstrated that inertial failures ofpiping are not credible as long as standard industrial or better design practices areemployed.

5.1.1 Database Revresentation of Piging

In order to assure database representation of piping systems, the followingconditions must be met:

1. The design basis ground spectra for the nuclear facility are less than thebounding spectrum per Reference 2.

2. Piping installations must follow industry-standard practices (e.g., ANSIB31.1 spans and supports).

3. The piping system does not display known seismic vulnerabilities or employL. seismically sensitive characteristics, such as brittle joints or mechanicalcouplings which could be adversely affected by differential movement.

24046PRO~doc

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Procedure 240046-P-001Revision 0April 30, 1998Page 13

KJ

Piping and pipe supports should be reviewed for the following to assure databaserepresentation:

The piping configuration must have adequate flexibility to accommodate itsthermal loading. The concern is that piping which appears highly stresseddue to normal operating loads may perform poorly under an additionalseismic load.

* Visible damage to piping or supports (e.g., broken supports, loose U-bolts)_ may adversely affect piping seismic performance.

* Unusual conditions (non-standard fittings, unusual pipe attachments,'.. unusual support design, customized parts used in place of catalog parts,

i pipe supports that have been modified) should be considered as potentialoutliers: judgement should be used to evaluate if these conditions representa deviation from piping systems in the experience database.

a Brittle connections (e.g., threaded joints, cast iron fittings) should beconsidered as potential outliers. The experience database has demonstrated

-: the seismic vulnerability of these connections. Unreinforced branchconnections should be reviewed as they may represent deviation fromnormal industrial installation practices.

* The adequacy of pipe support installation (e.g., spring hanger settings,sliding supports which may have been restrained to preclude pipe sliding,one-way guide supports which may not restrain the pipe from sliding off

|- under lateral seismic loads) should be reviewed by the SRT.

L Friction clamps should not be oriented in such a way that gravity loads areresisted only by the clamping or frictional forces developed by the clamps.

24046PRO.doc

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Procedure 240046-P-001Revision 0April 30, 1998Page 14

5.1.2 Seismic Anchor Movement

The experience database includes several instances of seismic damage to pipingand supports that were attributed to seismic anchor movement. Damage was theresult of excessive movement of terminal end equipment, differential movementbetween pipe supports in adjacent buildings, and excessive movements imposed onbranch lines by flexible headers.

As a result of these instances of damage, the following attributes must beevaluated by the seismic review team during their piping walkdown.

* Piping configurations at building joints and between buildings should haveadequate flexibility to accommodate seismically-induced differential buildingmovement.

* Fittings which can be adversely affected by seismically-induced differentialmovement (e.g., bellows, flexible hoses) should be evaluated for adequateflexible.

* Piping attached to unanchored or poorly anchored equipment should beconsidered an outlier. Stiff piping attached to flexible equipment should beevaluated to verify that the piping will not act as an equipment anchorage.In addition, the piping configuration should have adequate flexibility toaccommodate vibrating components.

* Conditions where stiffly supported branch lines are attached to flexibly-supported (e.g., rod-hung) mainlines or headers should be considered aspotential outliers. The seismic review team should evaluate thisconfiguration for potential damage due to seismically-induced differentialmovement.

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Procedure 240046-P-001Revision 0April 30, 1998

_ Page 15

.KJ

5.1.3 Seismic Interaction Concerns for Pinina

Guidelines for evaluating potential interaction hazards to items, including pipingsystems, are presented in Section 6. Particular attention should be given tohazardous interactions to piping with threaded or bolted connections for possiblebreach of pressure boundary. In addition, interactions involving impact of valveoperators, vents and drains, and fragile appurtenances, should be evaluated indetail.

5.1.4 Pine Corrosion

The experience database includes instances of seismic damage to piping andsupports that were attributed to excessive corrosion. Therefore, the seismic reviewteam should evaluate both piping and pipe supports for rust or corrosion

Ldeterioration.

5.1.5 Selective Analytical Review

A sampling of the piping configurations and pipe supports shall be selected foranalytical review if it is considered appropriate by the SRT.

The sample size shall be determined by the SRT, based on the diversity, complexityand extent of the systems or areas being evaluated. Supports which are heavilyloaded or which appear to have marginal anchorages shall be selected.

Detailed sketches of the sample piping and supports shall be included in the fieldwalkdown notes. Sketches shall include the location, support configuration,dimensions, connection details, anchorage attributes, member sizes, and tributarylengths. The data sheet shall include notes describing the basis for selection ofeach sample. Any additional information that may be considered relevant to theseismic ruggedness of the sample support shall be noted.

_-

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Procedure 240046-P-001Revision 0April 30, 1998Page 16

5.2 ANCHORAGE

Anchorage of pipe supports shall be visually inspected in accordance with theguidelines of Reference 3. The extent of tightness testing to be performed forexpansion anchor bolts shall be determined by the SRT based on accessibility ofequipment and the extent of estimated loadings.

5.2.1 Exnansion Anchor Bolts

5.2.1.1 Inspection Guidelines Expansion anchors shall be evaluated in the plant toensure that proper installation has been obtained. The sample size of thisevaluation shall be of sufficient quantity to satisfy the SRT engineers that properinstallation has been achieved. This visual inspection shall include the following:

* A washer is installed between the equipment base and the bolt head or nut.If the equipment base is made of structural steel plate, then a washer is notneeded if the bolt-hole diameter in the structural steel plate appears to beno greater that the nominal bolt diameter plus 1/16 inch.

* The concrete is sound with no significant cracks in the vicinity of the anchorLy bolt.

* The gap between the equipment base and the concrete surface is less thanL or equal to 1/4 inch.

L The bolt spacing is greater than about 10 times the bolt diameter.

* The distance between the bolt and any free concrete surface is greater thanapproximately 10 times the bolt diameter.

* The bolt is installed with at least the minimum embedment.

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Procedure 240046-P-001Revision 0April 30, 1998Page 17

For shell type anchors, the minimum embedment is ensured if the shell does notprotrude above the surface of the concrete. For non-shell type anchors, theminimum embedment is ensured if the projection of the bolt above the surfaceL conforms with the following:

Bolt Allow. BoltDiameter Projection(Inches) (Inches)

3/8 1/2

1/2 5/8

5I8 7/8

314 1-1/2

1 *1-1/25.2.2 Cast-In-Place Anchor Bolts

5.2.2.1 Insoection Guidelines. Cast-in-place bolts shall be evaluated to ensure thatproper installation has been obtained. This visual inspection shall include thefollowing:

A washer is installed between the equipment base and the bolt head or nut. If theequipment base is made of structural steel plate, then a washer is not needed if thebolt-hole diameter in the structural steel plate appears to be no greater than thenominal bolt diameter plus 1/16 inch.

The concrete is sound with no significant cracks in the vicinity of the anchor bolt.

The gap between the equipment base and the concrete surface is less than or equalto 1/4 inch.

The bolt spacing is greater than about 10 times the bolt diameter.

The distance between the bolt and any free concrete surface is greater thanL. approximately 10 times the bolt diameter.

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L Procedure 240046-P-001Revision 0April 30,1998Page 18

5.2.3 Welded Anchoraces

5.2.3.1 Inspection Guides Welded anchorages shall be evaluated to ensure thatproper installation has been obtained. This visual inspection shall include the

L following:

L . Check for weld bum-through on thin sections.

* Limit weld thickness, t, to thickness of thinner part being connected.

* If plug welds are found and required to take tension loads, they are to beconsidered as an outlier.

5.2.4 Allowable Values

L Realistic capacity estimates should be used when performing the vertical andhorizontal load capability checks. Realistic capacity values, shear-tensioninteraction formulas, and reduction factors for edge distance and center to centerspacing for anchors and welds are defined in EPRI report "Seismic AnchorageGuidelines for Nuclear Plant Equipment* (Reference 5).

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Procedure 240046-P-001Revision 0April 30, 1998Page 19

6.0 SEISMIC INTERACTION REVIEW

L The seismic interaction review is a visual inspection of structures, piping, orequipment adjacent to the equipment under evaluation. The seismic interactionreview also includes the identification of all seismically induced failures ordisplacements of any adjacent structures, piping, or equipment that could adverselyaffect the capability of the equipment under consideration. Particular attentionshould be given to adjacent non-safety-related structures, piping, and equipment.

- The review team should identify and evaluate all credible and significant interactionhazards in the immediate vicinity of the equipment being evaluated. Evaluation ofinteraction effects shall consider detrimental effects on the capability of equipmentand systems to function, taking into account equipment attributes such as mass,size, support configuration, and material hardness in conjunction with the physicalrelationships of interacting equipment, systems, and structures. In the evaluation ofproximity effects and overhead or adjacent equipment failure and interactions, theeffects of intervening structures and equipment which would preclude impact

! should be considered.

Damage from interaction in earthquakes results from unusual circumstances or fromL. generic, simple details such as open hooks on suspended lights. In the interaction

review, the SRT should look for (1) unusual impact situations, and (2) lack of properanchorage or bracing of adjacent equipment.

L

L

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Procedure 240046-P-001Revision 0April 30, 1998Page 20

L7.0 REQUIRED DOCUMENTATION

The walkdown shall be documented by notes and observations recorded on theSEWS sheets from Attachment C. The SEWS sheets shall be signed and dated byall members of the SRT.

The qualification and training of the individual seismic review team members shallbe documented on Attachments A and B.

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Procedure 240046-P-001Revision 0April 30, 1998Page 21

1:- 8.0 QUALITY ASSURANCE

This walkdown shall be performed in accordance with the latest revision of the EQE

Quality Assurance Manual (Reference 4).

24046PROAd0o

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Procedure 240046-P-001Revision 0April 30,1998Page22

9.0 REFERENCES

1. USNRC. February 1987. "Generic Letter 87-02, Verification of Seismic Adequacyof Mechanical and Electrical Equipment in Operating Reactors, Unresolved SafetyIssue (USI) A-46."

2. SSRAP Report, OUse of Seismic Experience Data to Show Ruggedness ofEquipment in Nuclear Power Plants," Senior Seismic Review and Advisory Panel,Revision 4.0, February 28, 1991.

3. Bishop, Cook, Purcell, and Reynolds; EQE Incorporated; MPR Associates, Inc.;L Stevenson and Associates; URS Corporation/John A. Blume and Associates:December 1988." Generic Implementation Procedure (GIP) for Seismic Verificationof Nuclear Plant Equipment," Revision 2 corrected 2/28/91

4. EQE Engineering. November 15, 1991. "Quality Assurance Manual," Revision 2.

L 5. EPRI Report NP-5228, Revision 1, "Seismic Verification of Nuclear Plant EquipmentAnchorage," Electric Power Research Institute, Palo Alto, CA, prepared by URSCorporation/John A. Blume & Associates, Engineers, June 1991.

L 6. EPRI Report NP-7149, "Summary of the Seismic Adequacy of Twenty Classes ofEquipment Required for Safe Shutdown of Nuclear Plants," Electric PowerResearch Institute, Palo Alto, CA, prepared by EQE, Inc., March 1991

- 7. EQE Incorporated, "Piping Seismic Adequacy Criteria Recommendation Based onPerformance during and after Earthquakes", 2 Volumes. Prepared for the Electric

U Power Research Institute, RP-2635-1, February 1987.

8. EPRI NP-6041, Revision 1, "A Methodology for Assessment of Nuclear Power PlantSeismic Margin," Electric Power Research Institute, Palo Alto, CA, prepared by NTSEngineering, Long Beach, California, and RPK Consulting, Yorba Unda, CA, July1991.

9. EQE Incorporated. 1986. "Power Piping During and After Earthquakes." Vol. 1.Prepared for the Electric Power Research Institute. San Francisco, CA.

LL

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Procedure 240046-P-001Revision 0April 29, 1998Page Al of 2L

ATTACHMENT A:

TRAINING VERIFICATION SHEET

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Procedure 240046-P-001Revision 0April 29, 1998Page A2 of 2

l EXHIBIT 1L TRAINING SESSION RECORDS

Description of Session Topic(s): _

LInstructor:-

Designated Attendees:

Print or Tvne Name Initial Sinaturel at

!

*My signatumreinitials attest to mypresenice during the prescribed training session and generalunderstanding of the subject matter. As of now, anry questions I might have had regarding sessionL subject matter have been answered to my satisfaction.

L

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Procedure 240046-P-001Revision 0April 29, 1998Page BI of 2

ATTACHMENT B:

SEISMIC REVIEW TEAM MEMBERS

QUALIFICATION SHEET

LI U

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LI :I

L

L

LUl

i

"I

Procedure 240046-P-001Revision 0April 29, 1998Page B2 of 2

SEISMIC REVIEW TEAM QUALIFICATION SHEET

1.0 Name:

2.0 Company:

3.0 Position:

4.0 Education:

5.0 Professional engineers registration:

6.0 Engineering discipline:

7.0 Areas of expertise_

L-,-

L 7.1

1 7.2L

+ .7.3

7.4

L

L7.5

!

L 8.0

L 9.0

LSign

L

Experience

Knowledge of failure modes

Knowledge of nuclear design STDs & nuclearseismic design practice

Seismic capability evaluations

Knowledge of equipment- Nuclear- Heavy industrial process plants- Fossil fuel power plants

Conduit/Cable tray evaluations

Training Courses

Other qualifications

Years Experience

-

ature nave-&LOua__ _

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Procedure 240046-P-001Revision 0April 29, 1998Page C1 of 4

ATTACHMENT C

SCREENING AND EVALUATION WORKSHEETS

IiIL7� 11--7�1�

1 iIL�

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Procedure 240046-P-001Revision 0April 29, 1998Page C2 of 4

SCREENING AND EVALUATION WORKSHEET (SEWS)System Name

Equip. ID No.

Une Identifier

Equip. Class 23-Pining System Without Dynamic Analysis

Bldg. Floor Elevation(s)_

Drawing No.

Drawing Spec. No.

Operating Pressure/remperature _ __ PSIG

Pining System Boundary'

Description

, or sketch (attach sheets as necessary)

Functionality Recuirement

1. During Seismic Event

2. After Seismic EventY N UY N U

Evaluation by Date

*The piping system boundary Includes the piping configuration from component to component (or other anchor points)L Other Interconnections to the subject piping are Included from the connection to the first anchor point or componentanchor is defined as a point at which the pipe Is restrained In 3 directions and 3 rotations or through a series of supporwhich provide equivalent restraint of the pipe.

Caveats - Piping

L1. Does the piping configuration appear to have adequate flexAbi-lity to accommodate the therTnal loading?

2. No visible damage?3. No significant visible rust/corrosion deterioration?4. Are afl fittings standard?5. No potentially brittle connections (threaded joints, cast Ion

fittings, etc.)?6. Does the piping configuration appear to have adequate flexibil-

L7 lity to accommodate differential movement of vibrating components?\ -~7. Do the support spans appear to follow ANSI 831.1 requirements?

8. No unreinforced main/branch connections?9. No unusual pipe attachments?

Y N U N/A

Y N U N/AY N U N/AY N U N/AY N U NIA

Y N U N/A

Y N U N/AY N U N/AY N U N/A

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Procedure 240046-P-001Revision 0April 29, 1998Page C3 of 4

SCREENING AND EVALUATION WORKSHEET (SEWS)

Equip. ID No. Equip. Class -2-Pl-ino System Without Dynamic Analysis

10. No heavy valves supported by small bore vent andlor drain pipesL t1. Does the piping configuration at building joints appear to haveadequate flexibility to accommodate seismic Induced differentialmovement?

12. No in-line components which can be subject to Impact due to seismicInduced movements?

L 13. No fittings (bellow, flexible hoses, etc.) which can be adverselyaffected by seismic Induced differential movernerits?L 14. Free of piping attached to poorly anchored equipment?

15. No stiff piping attached to flexible equipment?16. No stiff branch piping attached to the main line with potentially

significant movements?17. No other concerns (if no, comment on separate sheets and attach)?LAre the caveats met?

Evaluation by

; aveats - SuPDoils

1. No visible damage?2. No visible rust/corrosion deterioration?3. No unusual design?4. No customized parts used in place of catalog parts, which

appear Inadequate?L0 5. Are the support settings (spring hangers, etc.) adequate?L 6. Free of any sliding surfaces which appear not to be performingtheir intended function?

7. No one-way guide support with the potential for the piping toslide off during a seismic event

8. Free of support details which appear to have been altered toaccommodate Interferences or other problems?

9. Do nuts have full thread engagement?L 10. No friction beam clamps?

11. Do concrete expansion bolts appear to have adequateS Bolt centerline to plate edge distance

L Bolt centerline to bolt distanceBolt centerline to concrete edge distanceBolt centerline to empty hole

12. Does the anchorage appear adequate (attach SEWS 25A through25.F, as required)?

13. No additional concerns (If no, document comments on separate

L sheet and attach).K Are the above caveats met?

Y N UY N U

Y N U

Y N U

Y N UY N UY N U

N/ANIA

N/A

NWA

NIANfANfA

Y N U

Y N U

Date

Y N UY N UY N UY N U

Y N UY N U

Y N U

Y N U

Y N UY N U

N/AN/AN/AN/A

N/AN/A

N/A

N/A

NIAN/A

Y N U N/AY N U NA.

Y N N/A

Y N U

Evaluation by Date

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Procedure 240046-P-001Revision 0April 29, 1998Page C4 of 4

SCREENING AND EVALUATION WORKSHEET (SEWS)

Equip. ID No. Equip. Class 23-Pipinc, System Without Dynamic Analysis

Interaction Effects

L 1. Soft targets free from Impact by nearby equipment or structures?2. Distribution branch lines have adequate fleibilty?3. No collapse of overhead equipment, distribution systems, or

masonry walls?L 4. No other concerns?

| Is equipment free of Interaction effects?

Evaluation by _

Y N U N/AY N U N/AY N U N/A

Y N U N/A

Y N U

Date

Is the piping system seismically adequate? Y N U

Comments

L All aspects of the equipment's seismic adequacy have been addressed.Li Evaluated by Date:

(AM team members)

LIIL

L

A,

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240048-R-001Revision IJune 5, 1998Page C 1

ATTACHMENT C:

TRAINING AND QUALIFICATIONS

j,

LLK-

46R1 revl .doc

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I-

-L

L

*l

L.,1

I

-I1

Procedure 240046-P-00tRevision 0April 29, 1998Page B2 of 2

SEISMIC REVIEW TEAM QUALIFICATION SHEET

1.0 Name: t49AS L W/7.

2.0 Company:

3.0 Position: G odV1p/ C4WjL/scTJ7Wi.-

4.0 Education:

5.0 Professional engineers registration: A4(SS/ 5A4'e/. Flour

6.0 Engineering discipline: C0 V/L. Sfnl1 C7Ly

7.0 Areas of expertise: C-V1 C S7VIC,- 7J7dL M&VAL f 6'127N4VWCA f

Lu~1 7.1

7.2

7.3

L 7.4

_

.L 7.5

L 8.0

L 9.0

L signatu.

Experience

Knowledge of failure modes

Knowledge of nuclear design STDs & nuclearseismic design practice

Seismic capability evaluations

Knowledge of equipment- Nuclear- Heavy industrial process plants- Fossil fuel power plants

Years Experience

/0 Usabl- Slap

20*e

Conduit/Cable tray evaluations 20

Training Courses 6Q(C A4LXOICW /i'gC . ao sJ nzc

Other qualifications AMIWC /Atl em0 57XS.S AMAC JV#APOJ-reC /9044 L D ate±6z

rW, D /Gate 'j-s

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Procedure 240046-P-001Revision 0April 29, 1998L Page A2 of 2

EXHIBIT I

TRAINING SESSION RECORDS

Description of Session Topic(s): "DZi LIV1L" VA/I 0Vo IV1A5 ZVO4'7W-,--001A4V~, 0, -f0ag os #V SC.C.A oG -1tfV1(-141zs

P4=Zq/1&- 47r Mrz/ &.56b M4r-r- Ag 0 NVor- Wfr 51f.Ajk OFpeL

L Instructor: A 0, 0e 0)CA8lL Dsnated6+ yfesDesiqnated Attendees:

L Print or Tvoe Name Initial Sianature* Da

L A e1. X9dvMAd ._ _ __ _ _ _ _ _ 'f/71

i_ £ C. WN(? . 24/ - 94716

LL-

L *My signatureirnitials attest to my presence during the prescribed training session and generalunderstanding of the subject matter. As of now, ary questions I might have had regarding session

| subject matter have been answered to my satisfaction.

A

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f

L

1.0

2.0

iL" 3.0

L 4.0

L-

5.0

. 6.0

7.0

Procedure 240046-P-OltRevision 0April 29, 1998Page 82 of 2

SEISMIC REVIEW TEAM QUALIFICATION SHEET

Name: PAVL b Z.AfJ

Company:

Position: 54. J~LcfTJ4

Education: BscE, s

Professional engineers registration: 5 tJ /

Engineering discipline: 6 IViiLf 57ZverueC?-L

Areas of expertise: 61/VIL. 377ZUsRA-. "&CtM*Jj/CAL. •i le-5- /

Experience

L 7.1 Knowledge of failure mode

7.2 Knowledge of nuclear desi!L seismic design practice

7.3 Seismic capability evaluatih

7.4 Knowledge of equipment- Nuclear- Heavy industrial process

- - Fossil fuel power plants

L 7.5 Conduit/Cable tray evaluati

8.0 Training Courses..$ U

9.0 Other qualifications Stp'JZ

L Signature

L

es

gn STDs & nuclear

ins

plants

Years Experience

2-5-4-

_25T4(Ioi US SJ4J 30U

/0 i-

ions - /0 f,-

WDky&AIMJF /IEf A&2A-oaJ

-A0 5?1E, I~~t MAf"1fj!

-DateSZS5

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240046-R-01Revision IJune 5, 1998Page D I

ATTACHMENT D:

ANALYSIS RESULTS - EQE CALCULATION 240046C-"O1

46R1 rov .doc

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lI

IUI

Calculation No.

Project

Calculation Title

References

Attachments

240046-C-001

TMJ-1 Auxiliary Steam Piping

TMI-1 Auxiliary Steam Pininn Evaunaionn…- -. . p - *

As Noted

As Noted

,

Total Number of Pages (including Cover Sheet): I/z 3,-51 a-0 2 4 5 7,

R evion Apprval Description of Revision Originator Checker Approver

0 4-30 - fX Initial Issue

l £/7tt. ke dC RSi By

LLI-I

K>;

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EQE INTERNATIONAL-MNO. 240046 JOB TMI-1 Auxliary Steam Piping BY

mLC. NO. C-001 SUBJECT TMI-1 Auxiliary Steam Pipina Evaluation Cl

TABLE OF REVISIONS

SHEET NO. -.

P: DATE: 4-7049HK D: /.2DATE: 4 0 -fC'

ApprovedDate )Revision Description of Revision

0

i

Initial Issue

6'o Jf.fo-4. e"44L ,A/..t5, 7, A, bP 3S,40 hvortor4t . ZAL *vv

4 - Sxo- 9 is

L

2448001.DOC Pae 2

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i EQE INTERNATIONAL

' 0XJ . 240046 JOB TMI-1 Auxiliary Steam Pining E.NO. C-001 SUBJECT TMI-1 Auxiliary Steam Piping Evaluation

TABLE OF CONTENTS

SECTION

L Table of Revisions.

L 1.0 Purpose.

2.0 M ethodology ............................................................................

3.0 Calculations.

4.0 Conclusions.

5.0 References.

ATTACHMENTS

A. Walkdown Sketches.

B. AutoPIPE Computer Output.

L C. TMI-1 5% Damped Response Spectra.

D. Checking Criteria Checklist.

SHEET NO. 3BYKD:.1ZDATE: 4-jo 4e,CHICD: eJ DATE:.- 4)0 f I

PAGE

..........................2

.........................4

..........................4

...........................4 ,.

.......................... /

.......................... / /

No. Paaes

......................... . 4........................ ss

.........................3 2

.............................. 3

L

L-I -, )

L 244DC-O1 DC Page 3

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EQE INTERNATIONAL

SHEET NO.7NO. 240046 JOB TMI-1 Auxiliary Steam Pining BY: DATE- '/4'/V |

NO. C-001 SUBJECT TMI-1 Auxiliary Steam Pipina Evaluation CHICD: .g DATE |

1.0 PURPOSE

The purpose of this calculation Is to provide a seismic verification review of the TMI-1 AuxiliarySteam Piping in certain areas of the plant. There is equipment located In these areas thatcould be adversely affected by a steam line break.

The system is not safety related and was not designed to plant seismic design basisrequirements. This seismic verification review uses the results of research into the effects ofpast strong motion earthquakes on similar piping to assess if the TMI-1 Auxiliary Steam Pipingwill maintain pressure boundary integrity during and following an earthquake equal to the TMI-1SSE. The review technique is similar to that used to verify seismic adequacy of equipmentusing earthquake experience data.

2.0 METHODOLOGY

The piping was walked down in the field to determine actual piping and support configuration.The walkdown was performed per the guIdelines of Reference 3.

L: Using the walkdown information, the piping is analyzed using the REBIS AutoPIPE computerprogram (Reference 4). This program has been certified for use on QA projects (Reference 5).

This calculation is a seismic margin analysis using the conservative deterministic failure margin(CDFM) approach as described in Reference 6. This approach is summarized in Table 1. Forthis project the seismic margin earthquake (SME) was taken as the TMI-1 safe shutdownearthquake (SSE). Broadened USI A-46 floor response spectra was used rather than the lessconservative unbroadened, median-centered floor response spectra with frequency shiftingcalled for in Reference 6. The piping was linearly analyzed using 5% damping per Reference-6. Resulting stresses were compared to ANSI B31.1 allowables equivalent to ASME ServiceLevel D (comparing Equation 12 stresse to 3.OSh.)The 0.8 factor to account for inelastic energyabsoption was conservatively not applied.

L The response spectra used will be the 5% damped SSE values for Elevation 305' of the TMI-iAuxiliary Building as found in Reference 2. The Auxiliary Building spectra envelopes the FuelHandling Building spectra over the entire frequency range. The N-S and the E-W spectra are

* 244&COt1.(DOC Page 4

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EQE INTERNATIONAL

SHEET NO._ _t JNO. 240046 JOB TMI-1 Auxiliary Steam Piping BY: DATE: 41Yt

;'u C. NO. C-001 SUBJECT TMI-1 Auxiliary Steam Piping Evaluation CHICD: -dk' DATE: 4J3t4L A(z6/h

used in the X and Z directions. The vertical spectra is defined as 213 the maximum of the N-L S or E-W spectra and is input in the Y direction.

L

-7hLiEL

SUMMARY OF CONSERVATIVE DETERMINISTIC FAILURE MARGIN APPROACH

Load Combination:

Ground Response Spectrum:

Damping:

Structural Model:

Soil-Structure-Interaction:

Normal + SME

- Conservatively specifiedability)

(84% Non-Exceedance Prob-

Conservative estimate of median damping

Best Estimate (Median) + Uncertainty Variation in* Frequency .

Best Estimate (Median) + Parameter Variation

III

I

Material Strength: Code specified minimum strength or 95% exceedanceactual strength if test data are available.

Static Capacity Equations: Code ultimate strength (ACI), maximum strength(AISC), Service Level 0 (ASME), or functionallimits. If test data are available to demonstrateexcessive conservatism of code equations, then use84% exceedance of test data for capacity equation.

Inelastic Energy Absorption: For non-brittle failure modes and linear analysis,use 80% of computed seismic stress in capacityevaluation to account for ductility benefits, orperform nonlinear analysis and go to 95% ex-ceedance ductility levels

In-Structure (Floor) Spectra Use frequency shiftitn'rather than peak broadeningGeneration: to account for uncertainty plus use median damp-

I ng.

IA

2446C-O1.DOC Pa9p 5

Page 73: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

EQE INTERNATIONAL

SHEET NO. L9

,BNO. _ JOB_______________________ BY___ DATE ______

CALC. NO. O1) I SUBJECT PIEPid4 / FVlr4(-LiuS7iJA CHK'DVW DATE -O4

L. o " C)-1j

dcc jcn 4c4,&. A AC.9-4 ccc..

* - _________s

P PiL -A-il p4pi'-yps A s/ O Ao.kI - Spci c. fsr~vJyo! ccs - a ° 74s 1

l_ -/0a..z 4t I^ 15 ce4I4u, s^Cv ,/,c~e. Js+/e

L - 3/D/" p';p; r~z s ftire, a ,1e / M/Vser spe-ciApee Sf2, ,

- -/Jpe. Sspor jklls am i n R4e 7.-\-2. p wpi^ k/^s Ae4' 740 L Ce Iev, '42) 1 e 7e4r #4k.

I 3 Pro_-' 7g ,q 6 4 5 zy (Itt~17LI drss sI/rZ 5;f'5 vc 5;n ss 1 P/,P 3fj

I - 71VI a f 3 c z5' 6eoe F- 3 i

L - 7%yp /p " 3fhss5 725ft I k L le-I Tre'Ss /4v bf i= 4c -or- P4L'

e / Ar p 5 k4, tv- 4- a4 S/ I 0

Page 74: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

1l

to-

EQE INTERNATONAL

i L%1U%ATVAL

NO. 2*04o JOB T4X- I Aix, w rqa 1, p&iQ

j CALC. NO. .00QL SUBJECT PI/ PJA1? PVA(,4 77-6J

L _ _ _ _ _ _ _ _ _

SHEET NO. 7BY DATE 4- _-

CHK'D1 DATE 4! 37-ff

7 pot> (0-4-19

*i rao 1, ;!.9z psCti A,4,wP's~r e 4~I-c(

fs 133%&e 4, eewvo;e- oSl, - 4 z9 3 ' se -

7-4 w,4417 / £(/x exc!- ca #4 i 4 4k n0 1~is,~ /4&IS ~ ~ ect A,-sws 7'wsc r4~sae rid hcprf, 4irko.s4e f-stp. As s nA 'vre noJ cefzLL of IL tH

J2p/E'd ,i4-OecC6Ie bL*pJE7HD 'sM~.+j ,esi\g~t

3 q3es g3't r7 /336 Qg 4none o/44<J<2,5 hva se<Me 0,-- r Sp-Ss{ vfq

J~r-e'ew&v 4 e c4ArL/4s) +Y4 V'f /1 6 V4 bLf'-7

15 ce- pw'de, ( An ckpiq4 ,t S62Th o r 4 sVt vr s A>p ,go-:S q An4 csse

Cs o D ,v eetPO4/s

1A

COMPwv7CE LoAb..&4- t7r+ sca Ak.

L-oAb ad41MUC 1iil

WDSF - , - 'i -,- - - - - .1 , �- -i

L 4o3Ao4

L AllAlz

L- A15

IA I qL--- 1f 05

I Ie soeAj c q.

5757

7&C "1O5 ofs

5,13i

T/3s .j4.9(.BIC-'J oo

4liM

A$-13 i

4.s-iu-iAs-144

ks- J40AS-147A's'-14 1

II coD

q9o4-

99N4-7-04+

I.,,

0.771. 1+

1.. I i

I1fA1

~, I~t~r1% 95e.

Page 75: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

_ EQE INTERNATIONAL

I

yJ NO. 404b JOB -77A>5- / ,4 pW-PP)

j CALC. NO. 00) SUBJECT __P_____ ev____ _A__Vi

SHEET NO. -_5

BY DATE______

CHK'D 1 tft/ DATE _____

pit 6 1t -1

L

L

ttQ Svfpor+ Ufl'SB vtirmel CLlelaeLic- lu"Ls ;2 hs rS S.Ry imsgec~b7-5 4e- Weock lbk pI all A_ eppOrk +'s

I e r- c (S01-11 c v r i iY% S 9c, &W-. . -

�31

1 _ .:3 VA

L

L

A5 a-it cW -A it4er-,c~vs are- kss " '/3 -55 4~'As +s aJezr4ep 4-7t sets Ars 7L4 1 <g IQ flihs z4 6 .v- J/~

L

7 5p s a. pp4 er 4. 7Z+t litqz 4y pi, el J(oQ) re2 SOppor At oe'P'/t}s q -C 4

,( AZ 1 Cf/0 ') +Z 4e r' iecs, HA/csmzo ll'w 5; w+,7 1 +L. vet por4 a4 .A h0g t; S-_190 cfplW 11 ',

•fRA W A 66

L *(Do

Li -416

re -fram Lo A-qL+ TT SSE

3,i2 4f

5 ZTU5ZoI

A S-142.A s-I4 3AS-) +S

LoCMf oJS~fMV_-7v"A

5i9 4DII o All IupF O

-0j .L. TkLor-l awmtL -5ruf" o^Ax f-1 svftO atrwles , & d-roJ W @t fi {<Kt' s 4%

Page 76: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

EQEINERAONAL

084NO._24__ JOB-I CALC. NO. OnL SUBJECT.

kY't7-/ SL/ •174P,P,g4Pr PJ A Li 1

SHEET NO.

BY DATE __-__CHKD t1l DATE _-___

t VA b-4-fIL' Lt,6 5 PPoR7

There.. I' !~-: 5die L'pv4 1 c44 aJnt J3Le314- 11 ov 3ite- -,5-ueap or4 u -m- nodez Co3 -- <,4Pip' ^S

,& p S, F3SA S SUM I 4 r4

4-Ad 4-o -hs 5011 qy 97 0-a

&- 67"1 "

t t - 4 .71 (; ) -_g 2 51IF t

t 4pvn.:L2+ - N Z e l 4 12 /2z

4 2s4 114

6ros . 4- u.e- ""L )uE.

A6 0I !AJtS a /

t?

L TZ !5Lrfp~+ is sb 4 Q4. L.A1 II (2V) 4 5"sL41

WA-LAL-

Th ecLr ' ppac4s e p,4_5 hje Jeed 4I 4Lj 7 4! K

4, ry 4orJt^-la p.t irSoee-Ve d

L T 5 i TA se4 3 34 k IE

Page 77: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

EQE INTERNATIONAL

SHEET NO. / °NO. 240046 JOB TMI-1 Auxiliary Steam Piping BY: PQnf D

i uC. NO. C-001 SUBJECT TMI-1 Auxiliary Steam Piding Evaluation CHK'D:- DATE :J-g

4.0 CONCLUSIONS

The TMI-1 Auxiliary Steam Piping from anchor MK-AS-155 in the Fuel Handling Building toanchor MK-AS-156 in the Auxiliary Building has been evaluated in accordance with the CDFMmethodology as detailed in Reference 6. The piping and supports have been found adequateto ensure there will not be a breach of the piping pressure boundary during and/or following aL- SSEeventatTMI. in e 4oy ID CL +5 I rd V164-ev* ii peo- 5 aWI Sts ga^l se, Cves I14cufs 5 X

LL pipi 4 do-SAd 4Wfi 5iT- 3/-? A's Sr

t o?>g5aJSo aoe- 4Vule.

2C4481DOC Pages

Page 78: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

EQE INTERNATIONAL

SHEET NO. /1a- NO. 240046 JOB TMI-1 Auxiliary Steam Pipina BY:._._DATE _-30-f! C. NO. C-001 SUBJECT TMI-1 Auxiliary Steam Piping Evaluation CHICD: _DATE: 2ad

5.0 REFERENCES

L 1. aGeneric Implementation Procedure (GIP) for Seismic Verification of Nuclear PlantEquipment', Prepared for the Seismic Qualification Utility Group (SQUG), Revision 2 dated6-28-91.

2. EQE Report No. 42105-R-001, "Summary of Conservative, Design In-Structure ResponseL Spectra for Resolution of Unresolved Safety Issue A-46 for the Three Mile Island Nuclear

Generating Station, Unit 1-. Revision 0 dated July 1993.

3. EQE Procedure 240046-P-001, Revision 0.

4. AutoPIPE User Reference Manual D/N QA26API-4.7, Volume 1, Revision 0, C/N 104

L 5. Memorandum from J.L. White, "Certification of AutoPIPE*, February 12, 1996, File3.19.5Q, Log No. 004.

L 6. EPRI NP-6041, "A Methodology for Assessment of Nuclear Power Plant Seismic Margin*,Prepared for the Electric Power Research Institute (EPRI), , Final Report dated October1988.

L 7. Basic Engineers Support Drawings:

Support No.AS-120AS-121AS-122AS-123AS-124AS-125AS-126AS-127AS-128AS-129AS-130AS-131AS-132AS-133AS-134AS-135AS-136AS-137AS-138AS139

S.O.8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS

Sheet No.GA-1 663 and 1664GA-1665GA-1666GA-1667GA-1668GA-1669GA-1670GA-1671GA-1672GA-1673GA-1674GA-1675GA-1676GA-1677GA-1679GA-1680GA-1681GA-1682GA-1684GA-1686

2448C-O1.O Page 7

Page 79: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

M EQE INTERNATIONAL

0Y. 240046 JOB TMI-1 Auxliary Steam PiPina BYI C. NO. C-001 SUBJECT TMI-1 Auxiliary Steam Piping Evaluation Cl

B/! 7. Basic EngineersSupport Drawings:

SHEET NO. / Z

-IKD: -J*DATE: 430f

TL M4 & _'d-I ISUDDOrt No.AS-140AS-141AS-142AS-143AS-144AS-145AS-146AS-147AS-148AS-149AS-154AS-155AS-156AS-157

S.O.8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS8563-AS

Sheet No.GA-1687GA-1688GA-1689GA-1690 and 1691GA-1692GA-1693GA-1694 and 1694-AGA-1695 and 1696GA-1697 and 1698GA-1699GA-1706 and 1707GA-1708GA-1709GA-1710

8. T Power Piping, ASME Code for Pressure Piping, B31*,ASMEB31.1-1995 Edition

q9 67iLSEAT ASS0C-,*7.Cs Tb~*WI14XZ-54-Sg. " pi D .- #1

3 3 ~ 'I- ~-

VtC)

/0 G I oTE7 65Cv-iA'7r_5 'Lb .,#4e - 4--7 5Z2 LP. " D,_

by ScPAzLti a 5 A-I-/ ~l~Jk e ~ t,7 T-em, A cowe -Fc I .C- to

11, I.5;c £,e-orr Le.'t1-e-r 4o 6(' sod'o 0*1 , 5

Wit v5 a{ -,rto' f, Irb, 11,Po 'i

I Praof f.ett Ft( (,I/Q, to 00/.5-/- V/sg,2yodet

2440.1.MC Pap$S

Page 80: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

JOB Trf, £'/r / JOB NO.

-- SUBJECT -VW /CAl~y smw zov Fimt '64, CLC NO.

DATE 4 !'LCHKD E SHE NO. OF__

o-4.

Ii d

No A.2

VI

* X\;v......................... . ss<.___

Page 81: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

)7A-4r E a-. =-FA, T A -At t~~~~~ Len Brow}{!Ao/{

JOB 7Xyl vlrT / JOB NO. Z Voa I/

SUBJECT 4VXILA-MY Sg -/- 4&'x/wzO At-' - CALC NO. I

DATA # 1' o HKD_ AE SHEE NO. - OF___

i

.12*i4 C

'I-,-o -P

4.,

1LO)

4~ V-

L

Li ALI 1 X r/pe.y1

i

I t

Page 82: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

A -1A: Cj/f4A17 A,JOB 7r7 13v T~- -

SUBJECT* i MV'J441A ;72-t 1% IA/

\DATE _______ c. ,c A.- DATE ______

--- . N<>- _ _ S A

,_ , *.-

>-, -4o~ -

L-k--- - - - 6 AQ - __ O-

-~~- - . - tt:-- - - -.- --- ----

_ --- . . .... . ... - .. _ .. _ .

= 6_ \ - .%- . -\. _

$A/7 4 3_JOB NO. c=4c{_CALC NO. ° C.>

SHEET NO. . OF___

'. - -4.

*~-,--;g-O------

i_-- _.... _.2 ... __ .....__ :

i - _ -

'- ,.. ...

,~- , -. 1 I- , - - - ~,! ~ : , _,- -- . 4 :4

'S. .'-- . .. - . '*4. " . .x xS x. , .**

<xo- - --- - -- ; ~. --.- < <-----.-

- -- -o s -. -. _ s . . -

L .------ :------ - -. -- s ---- - - --

.4- -'.zl t 44. S "4. . 6 a o -

h4ff2.r 1$ .. I~tS. inAy A{~ ~~~~~~~~'d7~Ji ; ei 9.D~§ :Sev t.J5+Sk

Page 83: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

IL-rr7L,- I PAsAz;I/--r -A A W/I 7f1 r r 'W /7 -5//7'7 I~t 94

JOB J77 z r ..7 JOB NO.,>4x4v

SUBJECT A.JwL-IAiy 5-r~r-tl Pj e/A//p CALC NO._____

rLDATE ii'~ CHICD ~ DATE_.L FL_ 9SHEET NO. -OF I- -. r-- r----~----r--- .,

..... l8 * __

__ I ~7 - 7 -- 4. .c

N.0

-- - - - *.A

YJ . -. 4

-r -Z

fl- .,L N.-- 7

H - _IJ

Page 84: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

ALCULATION 240046-C-001 ATTACHMENT B PAGE BE…__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _

AUXSTM1 240046 EQE International! 04/30/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 MODEL PAGE 1_- - - -_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

*

** **

** **

** **

** **

****1

**

'***** ** *******

** ** ** **

** ** ** **.***** ** ********* ** ** ***** **i

** ** ** ** ** .**

** ** ** ** ** **

***** ** ***** **

**

**

**

**

**

**

**

**

r**

**

Pipe Stress Analysis and Design Program

Version: 4.70.06

Edition: Plus-DOS

Developed and Maintained by

REBIS Industrial Workgroup Software1600 Riviera Ave., Suite 300

Walnut Creek, CA 94596

A

Page 85: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

ALCULATION 240046-C-001 ATTACHMENT B PAGE B2

________________________________________________________________________________

!ATTKSTM1 240046 EQE International_ '0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 MODEL PAGE 2

F ** ~AUTOPIPE SYSTEM DATA LISTING .*

Ii

in

i .

ji j,6\-

SYSTEM NAME : AUXSTM1

PROJECT ID :

PREPARED BY :

CHECKED BY :

240046TMI-1 AUX STEAM LINE-

Je 4- In a e

%e- pulpit lysWA> "a t+ re-65ee,04

CPaw Atk L

PIPING CODE : B31.1

AMBIENT TEMP. ( deg F )

COMPONENT LIBRARY

MATERIAL LIBRARY

MODEL REVISION NUMBER

:70.0

: AUTOPIPE

: AUTOB311

:33

Page 86: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

(JLCULATION 240046-C-001 ATTACHMENT B PAGE B3

…_-__-___________________________________-____-________-___-___________________| UXSTM1 240046 EQE International' 0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 MODEL PAGE 3

…-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

O I N T D A T A

i'OINT ----- OFFSETS (ft )…_AME TYPE X Y Z PIP]

…____ - - - - ____ __ - - - - -- - - - --** SEGMENT A.00 Run 0 0 0 8"-I

XA01 Run 0 0 8.000,ao2 Bend 0 0 1.500

L I S T I N G

3 ID DESCRIPTION…_________________________________

AS

00

Long Elbow, RadiusBend angle change -SIF 2.44Flex - 7.360

- 12.000 inch90.00 deg

i 3A04

, i

1

Run 10.750Bend 11.500

00 Long Elbow, Radius - 12.000 inch

Bend angle change = 90.00 degMid point at 50.00 percentSIF - 2.44Flex - 7.360

Bend 0 -10.000 0 Long Elbow, RadiusBend angle change -SIF - 2.44Flex - 7.360

= 12.000 inch90.00 deg

L~JA06

I.io7

A.09-

_ 10

Alli 12_13

RunBend

RunBend

Bend

RunRunBend

3.9171.500

00

00

00 Long Elbow, Radius = 12.000 inch

Bend angle change - 90.00 degSIF = 2.44Flex - 7.360

0 -8.2500 -1.500

0 -2.000 0

Long Elbow, RadiusBend angle change -SIF = 2.44Flex - 7.360

Long Elbow, RadiusBend angle change =SIF = 2.44Flex = 7.360

Long Elbow, RadiusBend angle change -SIF - 2.44Flex - 7.360

- 12.000 inch90.00 deg

= 12.000 inch90.00 deg

= 12.000 inch45.00 deg

000

0 -16.4170 -11.0830 -1.250

Bend 13.000 0 -13.000 Long Elbow, Radius = 12.000 inchBend angle change - 45.00 degMid point at 50.00 percentSIF - 2.44Flex = 7.360

Page 87: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

EJLCULATION 240046-C-001 ATTACHMENT B PAGE B4

______________________________________________________ -------------------------

'iUXSTM1 240046 EQE International. '0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 MODEL PAGE 4

-------- __________f

P O I N T D A T A L I S T I N G

! ?OINT*%AME TYPE

I1 U5 Runi t16 RunA17 Tee,18 Bend

.1.

----- OFFSETS (ft )-----X Y Z PIPE ID

…______ ------- ------- --------13.500 0 017.417 0 05.917 0 0

0 5.365 0

~'A1 9A2 0

DESCRIPTION…____________________-____________

Long Elbow, Radius - 12.000 inchBend angle change = 90.00 degSIF = 2.44Flex = 7.360

Long Elbow, Radius = 12.000 inchBend angle change = 45.00 degSIF = 2.44Flex = 7.360

Long Elbow, Radius = 12.000 inchBend angle change = 45.00 degSIF = 2.44Flex = 7.360

RunBend 0

2.083

0 -3.0000 -1.000

0 -2.083Bend

Run 0 0 -9.417

I k**

"A17B01302

* 303

SEGMENTTeeReduRunBend

B77.501

000

-12.000-1.250-0.500-1.250

-42.000 8"-AS0.0 2"-AS0

Cone angle = 27.51 deg, SIF = 2.00

Long Elbow, Radius - 3.000 inchBend angle change = 45.00 degSIF - 1.73Flex = 4.404

B04 Bend 0 -0.500

0 -1.000

0.500 Long Elbow, Radius = 3.000 inchBend angle change = 45.00 degSIF = 1.73Flex = 4.404

305

i 305C 17Co1

Tee 0

SEGMENT CTee 77.501 -16.500 -41.500 3/4"-ASTee 0 -0.833 0Valv 0 -0.667 0 Weight - 5 lb

Surface factor - 1.00Non-standard joint, SIF = 1.00

RunI v RunII I Bend

0 -0.2500 -0.2500 -0.500

00

Long Elbow, Radius - 1.125 inchBend angle change - 90.00 degSIF = 1.30

Page 88: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

PkLCULATION 240046-C-001 ATTACHMENT B PAGE BS

kUXSTM1 240046 EQE International- 0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 MODEL PAGE 5

LP O I N T D A T A L I S T I N G

' ?OINT'-AME

C05

TYPE_end

Bend

----- OFFSETS (ft )-----X Y Z PIPE ID

…__ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - -DESCRIPTION

…__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _Flex - 2.849

-1.500 0

Bend 0 -1. 000

0

0

0

Long Elbow, RadiusBend angle change -SIF = 1.30Flex - 2.849

Long Elbow, RadiusBend angle change =SIF - 1.30Flex - 2.849

Long Elbow, RadiusBend angle change =SIF - 1.30Flex - 2.849

= 1.125 inch90.00 deg

= 1.125 inch90.00 deg

= 1.125 inch90.00 deg

Bend -0.500 0

- Valv 0 1.750 0 Weight - 5 lbSurface factorSocket welded,

' 1.00SIF = 2.10

I O09WsZ18C10

I 4** 4

C17; G011 71 8

RunTeeJunc

0 0.2500 0.6670 0.833

G77.501 -17.333-1.500 0-0.500 0

000

1 "-AS

SEGMENTTeeRunTee

-41.500 3/4"-AS00

I :10_ 01

SEGMENTJuncBend

H75.501

0-16.500 -41.500 1"-AS

2.000 0 Long Elbow, RadiusBend angle change =SIF - 1.31Flex - 2.889

= 1.500 inch45.00 deg

H02 Bend 0 0.750 0.750 Long Elbow, RadiusBend angle change =SIF = 1.31Flex - 2.889

= 1.500 inch45.00 deg

Bend 0 1.000 0 Long Elbow, RadiusBend angle change =SIF = 1.31Flex = 2.889

= 1.500 inch45.00 deg

I J--H-0H04 Bend 0 0.500 0.500 Long Elbow, Radius = 1.500 inch

Bend angle change = 90.00 deg

Page 89: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

; ALCULATION 240046-C-001 ATTACHMENT B PAGE B6

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

; AUXSTM1 240046s 30/98 TMI-1 AUX STEAM LINE

…-- - - - - - - - - - - - - - - - - - - - - - - --

._____________________________________________EQE International

: AutoPIPE+4.70 MODEL PAGE 6._________________________________________________

~ P O I N T D A

| POINT ----- OFFSETS (ft )-----,-NAME TYPE X Y Z

.T A L I S T I N G

PIPE ID DESCRIPTION_ _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

__________________________________

SIF =1.31Flex - 2.889

H05 Run -0.500H06 Run -8.000

0 00

I, B05

I02

SEGMENT ITee 77.501 -16.500 -41.500 1"-ASRun -0.-667 0 0Bend -0.500 0 0 Long Elbow, Radius

Bend angle change-SIF = 1.31Flex -2.889

- 1.500 inch90.00 deg

! 103 Bend 0 0.500 0.500 Long Elbow, RadiusBend angle change-SIF = 1.31Flex -2.889

. tut Bend

- 1. 500 inch45.00 deg

= 1.500 inch90.00 deg

0 0. 667 0 Long Elbow, RadiusBend angle change -SIF - 1.31Flex - 2.889

II05IL

Run -4.000 0 0

,Total weight of empty pipes : 5617 lb

Page 90: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

AALCULATION 240046-C-001 ATTACHMENT B PAGE B7

1 AUXSTM1 240046_. 0/98 TMI-1 AUX STEAM LINE

---------------------------

EQE InternationalAutoPIPE+4.70 MODEL PAGE 7

._________________________________________________

C O M P O N E N T D A T A L

|POINT --- COORDINATE(ft )--- DATA--NAME X Y Z TYPE DESCRIPTION

…____ - - - - - - - - - -- - - - -- - -- - - - -- - - - _ _ _ _ _ _ _ _ _ _ _

I S T I N G

,_______________________________-

A#** SEGMENT AA00 0.000 0.000 0.000 ANCHOR Rigid

Thermal movements : None

! o01A02 NA02

I &02 Fjk03

P .04 N

L-A04 MA04 F

, P05 N'A05-AOS F

.I

I 07 NLA07A07 F

, 08

|09 NLsosA09 Fi110 N

,10A10 F~1 1

-A12A13 N

Lkl3 FA14 N\14e 14 MLA14 FI I

Ls;>

0.0000.0000.0001.000

10.750

21.25022.25021.95722.25022.25022.25023.25026.167

26. 66727.66727. 66727.667

27. 66727.66727. 66727.66727.66727.66727.667

27.66727.66727.66727.96040.37440.66740.69941.08154.167

0.0000.0000.0000.0000.000

0.0000.000

-0.293-1.000-9.000

-10.000-10.000-10.000

-10.000-10. 000-10.000-10.000

-10. 000-10.000-11.000-11.002-12.000-12.000-12.000

-12.000-12.000-12.000

4 mass point(s)9.5009.5009.5009.5009.5009.5009.5009.500

TIY-STOP ID : AS-141, Connected to Ground

3 mass point(s)

TI1 mass point(s)

SPRING ID : AS-142, Connected to Ground1 hanger(s)Stiffness = 91 lb/inPreload - 288 lb

3 mass point(s)8.000 Y-STOP ID : AS-139, Connected to Ground8.5009.500 TI - -9.500 4 mass point(s)9.500 Y-STOP ID : AS-140, Connected to Ground

9.5009.500 TI8.5001.250 SPRING

-0.750-0.250 TI-0.250-0.250-0.250. TI-1.250

-16.667 Y-STOP

-27.750 Y-STOP-28.586-29.000 TI

3 mass point(s)ID : AS-143, Connected to Ground1 hanger(s)Stiffness - 107 lb/inPreload = 496 lb

6 mass point(s)ID : AS-144, Connected to Ground4 mass point(s)ID : AS-145, Connected to Ground

7 mass point(s)

ID : AS-146, Connected to Ground5 mass point(s)ID : AS-147, Connected to Ground7 mass point(s)ID : AS-148, Connected to Ground1 hanger(s)Stiffness - 107 lb/in

-12.000 -29.293-12.000 -41.707-12.000 -42.000 TI-12.000 -41.924 Y-STOP-12.000 -42.000-12.000 -42.000 Y-STOP

71.584 -12.000 -42.000 SPRING

Page 91: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

I.LLCULATION 240046-C-001 ATTACHMENT B PAGE B8

! tt e ¶, t - A e% n A _UAJA% LCML

'0/98 TMI-1 AUX STEAM LINEEQE InternationalAutoPIPE+4.70 MODEL PAGE 8

--------------------------------------------------------------------- PAGE-8

C 0 M P 0 N E N T D A T A L I S T I N G

I?OINT ---COO]IX-_4AME X

_ _ _ _ _ - - - - - - -

RDINATE(ftY

)--- DATAZ TYPE DESCRIPTION

…____ ------ ------------------------------------------

Preload = 505 lb

77.501 -12.000 -42.000 TEE2 mass point(s)Welded-on fittingSIF - In - 2.23, Out - 2.231 mass point(s)

A18I 8 F

A20 N\20

1 i20 Fhi21 NA21

I 2l FLi22

77. 50177.50177.50177.50177.50177.50177.79479.29179.58479.58479.584

-7.635-6.635-6.635-6.635-6.635-6.635-6. 635-6.635-6.635-6.635-6.635

-42.000-42.000-43.000-45.000-45.586-46.000-46.293-47.790-48.083-48.497-57.500

TI

Y-STOP ID : AS-149, Connected to Ground

TI

TI4 mass point(s)

ANCHOR RigidThermal movements : None

TEE Welded-on fittingSIF - In = 2.23, Out - 2.23

t EGMENT B<S 77.501 -12.000 -42.000

301UJ02

1503

1'-031303-

LS04

t404__04

N

F

77.501 -13.250 -42.00077.501 -13.750 -42.000

77.501 -14.896 -42.000

USRFLX In = 2.10, Out = 2.10, FlexOverride all other values =

USRFLX In = 2.10, Out = 2.10, Flex

77.50177.501

-15.000 -42.000 TI-15.073 -41.927 USRFLX

Override all other values =

In - 2.10, Out = 2.10, FlexOverride all other values =In - 2.10, Out - 2.10, FlexOverride all other values -

- AutomaticYes= AutomaticYes

= AutomaticYes= AutomaticYes

N 77.501 -15.427 -41.573

77.501 -15.500 -41.500F 77.501 -15.604 -41.500

77.501 -16.500 -41.500

USRFLX

TIUSRFLX In = 2.10, Out - 2.10, Flex = A

Override all other values = YesTEE Welded-on fitting

SIF - In = 1.52, Out - 1.52USRFLX In - 2.10, Out = 2.10, Flex = A

Override all other values = Yes

utomatic

utomatic

k **

B05SEGMENT C

77.501 -16.500 -41.500

77.501 -17.333 -41.500

77.501 -18.000 -41.500

TEE Welded-on fittingSIF - In - 1.52, Out - 1.52

USRFLX In - 2.30, Out - 2.30, FlexOverride all other values -

TEE B16.9 welding teeSIF - In - 1.00, Out = 1.00

USRFLX In - 2.30, Out = 2.30, FlexOverride all other values

USRFLX In - 2.30, Out - 2.30, Flex

- AutomaticYes

- AutomaticYes,Automatic

Page 92: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

t LCULATION 240046-C-001 ATTACHMENT B PAGE B9

: DXSTM11/98

_L ,_ _

240046TMI-1 AUX STEAM LINE

EQE InternationalAutoPIPE+4.70 MODEL PAGE 9

._______________________________________________________________________

C O M P O N E N T D A T A L I S T I N G

I _ _- _! 'OINT --- COORDINATE(ft )--- DATA%.EAME X Y Z TYPE

i 02 77.501 -18.250 -41.500 USRFLX

,r03 77.501 -18.500 -41.500 GUIDE

Y04 N 77.501 -18.906 -41.500 USRFLX

i04 77.501 -19.000 -41.500 TI&04 F 77.407 -19.000 -41.500 USRFLX

:-05 N 76.095 -19.000 -41.500 WEIGHT

DESCRIPTION____________________________________-____

Override all other values = YesIn = 2.30, Out = 2.30, Flex - AutomaticOverride all other values = YesID : C03 1, Connected to GroundStiffness = RIGIDIn = 2.30, Out = 2.30, FlexOverride all other values -

- AutomaticYes

In - 2.30, Out - 2.30, Flex - AiOverride all other values = Yes50 lb , No offsetsIn - 2.30, Out = 2.30, Flex = AiOverride all other values = Yes

automatic

I ,

C05j 05 F

C06 N

i'

I '07 N

C07. 07 F

t08

L09C18

L

USRFLX atomatic

76.001 -19.00076.001 -19.094

76.001 -19.906

76.001 -20.00075.907 -20.000

75.595 -20.000

-41.500 TI-41.500 USRFLX In = 2.30, Out = 2.30, Flex

Override all other values --41.500 USRFLX In - 2.30, Out - 2.30, Flex

Override all other values =-41.500-41.500

-41.500

75.501 -20.000 -41.50075.501 -19.906 -41.500

75.501 -18.250 -41.500

75.501 -18.000 -41.500

75.501 -17.333 -41.500

75.501 -16.500 -41.500

TIUSRFLX In - 2.30, Out = 2.30, Flex

Override all other values =USRFLX In = 2.30, Out - 2.30, Flex

Override all other values =TIUSRFLX In = 2.30, Out = 2.30, Flex

Override all other values =USRFLX In - 2.30, Out = 2.30, Flex

Override all other values =USRFLX In - 2.30, Out = 2.30, Flex

Override all other values -TEE B16.9 welding tee

SIF - In - 1.00, Out = 1.00USRFLX In = 2.30, Out = 2.30, Flex

Override all other values =

= AutomaticYes= AutomaticYes -

= AutomaticYes= AutomaticYes

= AutomaticYes= AutomaticYes= AutomaticYes

= AutomaticYes

SEGMENT G77.501 -17.333 -41.500

76.001 -17.333 -41.500

75.501 -17.333 -41.500

TEE B16.9 welding teeSIF - In - 1.00, Out - 1.00

USRFLX In = 2.30, Out - 2.30, Flex IOverride all other values = No

WEIGHT 5 lb , No offsetsUSRFLX In = 2.30, Out = 2.30, Flex =I

Override all other values = NoTEE B16.9 welding tee

SIF - In = 1.00, Out = 1.00

Automatic

kutomatic

SEGMENT H75.501 -16.500 -41.500

Page 93: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

LCULATION 240046-C-001 ATTACHMEN

-_______________________________________

1,UXSTM1 2400460/98 TMI-1 AUX STEAM LINE

-------- --------------------------

[T B PAGE B10

________________- ---------------------- _

EQE InternationalAutoPIPE+4.70 MODEL PAGE 10

…_______________________________________

C O M P O N E N T D A T A L I S T I N G

I'OI]. oil

i 01

H01901

hdi02

t02L102

*1 03

'i03H03

.S04

H05

L06

E05

I .

LIO

102

102'02

0 3

I03I 0 3

'I04

ET --- COORDINATE (ftX Y

N 75.501

75.501F 75.501

N 75.501

75.501F 75.501

N 75.501

75.501F 75.501

N 75.501

75.50175.376

75.001

67.001

SEGMENT I77.501

76.834

N 76.459

76.334F 76.334

N 76.334

76.334F 76.334

N 76.334

/ 76.334F 76.209

-14.552

-14.500-14.463

-13.787

-13.750-13. 698

-12.802

-12.750-12.713

-12.338

-12.250-12.250

-12.250

-12.250

-41

-41-41

-40

-40-40

-40

-40-40

-40

-40-40

-40

-40

)--- DATAZ TYPEI---- ------

_.500 USRFLX

L.500 TI.463 USRFLX

.787 USRFLX

.750 TI

.750 USRFLX

.750 USRFLX

.750 TI

.713 USRFLX

.338 USRFLX

.250 TI

.250 USRFLX

.250 Y-STOP

.250 ANCHOR

DESCRIPTION…-----------------------------------------

In = 2.10, Out = 2.10, Flex - AutomaticOverride all other values - Yes

In = 2.10, Out - 2.10, Flex = AutomaticOverride all other values - YesIn = 2.10, Out - 2.10, Flex = AutomaticOverride all other values Yes

In - 2.10, Out - 2.10, Flex = AutomaticOverride all other values = YesIn = 2.10, Out = 2.10, Flex = AutomaticOverride all other values = Yes

In - 2.10, Out - 2.10, Flex - AutomaticOverride all other values = YesIn - 2.10, Out - 2.10, Flex AutomaticOverride all other values = Yes

In - 2.10, Out = 2.10, Flex - AutomaticOverride all other values = YesID : H05 1, Connected to Ground3 mass point(s)RigidThermal movements : None

-16.500 -41.500

-16.500 -41.500

-16.500

-16.500-16.412

-16.037

-16.000-15. 948

-15.458

-15.333-15.333

-41.500

-41.500-41.412

-41.037

-41.000-41.000

-41.000

-41.000-41.000

TEE

USRFLX

WEIGHTUSRFLX

USRFLX

TIUSRFLX

USRFLX

TIUSRFLX

USRFLX

TI

USRFLX

Welded-on fittingSIF - In = 1.52, Out - 1.52In - 2.10, Out = 2.10, FlexOverride all other values -5 lb , No offsetsIn - 2.10, Out - 2.10, FlexOverride all other values -In - 2.10, Out - 2.10, FlexOverride all other values -

In - 2.10, Out = 2.10, FlexOverride all other values =In - 2.10, Out - 2.10, FlexOverride all other values -

In - 2.10, Out 2.10, FlexOverride all other values =In - 2.10, Out = 2.10, FlexOverride all other values =

1 mass point(s)In - 2.10, Out - 2.10, FlexOverride all other values =

- AutomaticYes

= AutomaticYes= AutomaticYes

= AutomaticYes= AutomaticYes

= AutomaticYes= AutomaticYes

= AutomaticYes

Page 94: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

C LCULATION 240046-C-001 ATTACHMENT B PAGE BlI

1 JXSTM1 240046 EQE International.1/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 MODEL PAGE 11

-L ----.- . m .- - m - - _ A m - --C I rLU N lE4 N T D A T A L I S T I N G

i OINT.AME

05

Lm

f 'ume

--- COORDINATE(ft )---x Y z

72.334 -15.333 -41.000

DATATYPE DESCRIPTION

…_____ ------------------------------------------

ANCHOR RigidThermal movements : None

of points in the system : 166

Page 95: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

I ALCULATION 240046-C-001 ATTACHMENT B PAGE B12

________________________________________________________________________________

AXUXSTMl 240046 EQE International' 0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 MODEL PAGE 12

LP I P E D AT A L I S T I N G

i Pipe ID/Lj4aterial

____________

ISm-ASI -S

Nom/ O.D.Sch inch____ -----

8 8.625STD

-----Thickness(inch)-----W.Th.

0.322

Corr Mill Insu0___ 0.04 2-00

0 0.04 2.00

Ling____

0

SpecGrav

0

Weight(lb/ft )Pipe Other Total

…____ ----- -----28.52 5.10 33.62

ZL/zC

1.001.00

2 "-ASI 'S

3/4"-AS

, "-ASi C

2.000STD

0.750STD

1.000STD

2.375 0.154

1.050 0.113

1.315 0.133

0 0.02 2.00

0 0.01 2.00

0 0.02 2.00

0 0 3.65 2.10 5.75 1.001.00

0 0 1.13 1.46 2.59 1.001.00

0 0 1.68 1.59 3.27 1.001.00

Page 96: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

LLCULATION 240046-C-001 ATTACHMENT B PAGE B13

i UXSTM1 240046 EQE Internationall '0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 MODEL PAGE 13

LM A T E R I A L D A T A L I S T I N G

1 Material. Name Pipe ID

8"-AS

Density Pois.lb/cu.ft Ratio

489.0___ 0.30-

489.0 0.30

Temper.deg F_______

70.0300.0

ModulusE6 psi____.50_

29.50

Expans. Allow.in/lOOft psi

14100.01.8200 14100.0

CS

Cs

CS

2"-AS

3/4 "-AS

489.0 0.30 70.0300.0

489.0 0.30 70.0300.0

489.0 0.30 70.0300.0

29.50

29.50

29.50

14100.01.8200 14100.0

14100.01.8200 14100.0

14100.01.8200 14100.0

1" -AS

Lu'-II 7

i

L

L

L -

L_LL_

Page 97: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

JALCULATION 240046-C-001 ATTACHMENT B PAGE B14

_______________________________.

AUXSTM1 240046, ' 0/98 TMI-1 AUX STEAM LINE

.______________________-__________________________

EQE InternationalAutoPIPE+4.70 MODEL PAGE 14

I- -- - --- -- - -- - -- - -- ---- ----- ------ --- -- ---- ---

| POINTIIAME

----- CPRESS.psi______

A S ETEMPERdeg F______

TEMPERATURE AND PRESSURE DATA1------ -----C A S E 2------EXPAN. PRESS. TEMPER EXPAN.

in/lOOft psi deg F in/lO.Oft-_______ ------ ---- -- --------

-----C A S EPRESS. TEMPERpsi deg F_ _ _ _ _ _ - - - - - -

3…--___EXPAN.

in/lOOft________

,I j

i k** SEGMENT ALAOO 25.00A22 25.00

300 1.820300 1.820

A17, 302305

SEGMENT B25.0025.0025.00

300300300

1.8201.8201.820

SEGMENT C25.0025.00

300 1.820300 1.820

i ***

L:17

C18

SEGMENT G25.0025.00

LI 'EGMENT H25.00

H06 25.00

300 1.820300 1.820

300 1.820300 1.820

300 1.820300 1.820

Ilkt**L.B

B05* 105

SEGMENT I25.0025.00

Page 98: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

:ALCULATION 240046-C-001 ATTACHMENT B PAGE B15

_-_____________________________ ________-_______________________________________

l AUXSTM1 240046 EQE International1 30/98 TMI-1 AUX STEAM LINE AutoPIPE14.70 RESULT PAGE

----------------------------------------------------------------------

A N A L Y S I S SUMMARY

Current model revision number : 33

Static - Date and Time of analysis .............Model Revision Number.Number of load cases ..................Load cases analyzed ...................Gaps/Friction/Yielding considered ....Hanger design run .....................Cut short included ....................Weight of contents included ...........Number of mass points per span ........Pressure stiffening case ..............Water elevation for buoyancy loads ....

April 30, 1998333GR T1 P1NoNoNoYesAutomatic0Not considered

10:18 AM

Modal - Date and Time of analysis .Model Revision Number .Number of modes .Cutoff frequency (Hz).Weight of contents included .Number of mass points per span ..Pressure stiffening case .Water elevation for buoyancy loads ....

April 30, 1998333033.0YesAutomatic0Not considered

10:18 AM

Response Date and Time of analysis ............. A]Model Revision Number ................. 3Number of load cases ........... 3Load cases analyzed .... .............. RDate and time of modal analysis ....... ANumber of modes .................. 3Cutoff frequency (Hz) ... .............. 3Model revision of modal analysis -.... 3:Weight of contents included ........... YeNumber of mass points per span ........ AlPressure stiffening case ............. . 0Water elevation for buoyancy loads .... Ni

pril 30, 19983

1 R2 R3pril 30,03.03esatomatic

10:19 AM

10:18 AM1998

ot considered

Page 99: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

NkLCULATION 240046-C-001 ATTACHMENT B PAGE B16

________________________________________________________________________________-

I UXSTM1 240046 EQE Internationalg '0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 2

CODE COMPLIANCE COMBINATIONS

i Combination Category Method Load-

Factor M/S Allowable Remarks

GR + Max P Sustain Sum GravityMax Long

1.001.00

Automatic Default

Cold to Ti

Sus. + Ri

Sus. + R2

Sus. + R3

Expansion

Occasion

Occasion

Occasion

Sum Thermal 1

Abs sum Response 1Max Sus

Abs sum Response 2Max Sus

Abs sum Response 3Max Sus

1.00

1.001.00

1.001.00

1.001.00

Automatic

Automatic

Automatic

Automatic

Default

Default

Default

Default

Max P

L* SSE-SEISMC

IL-..+P+SSE

Hoop Max Hoop

Occasion

Occasion

SRSS Response 1Response 2Response 3

1.00

1.001.001.00

1.00 M1.00 M

Automatic

Automatic

Default

User

UserAbs sum GR + Max PSSE-SEISMC

Automatic

Page 100: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

6 XLCULATION 240046-C-001 ATTACHMENT B PAGE B17

________________________________________________________________________________

.UXSTM1 240046 EQE InternationalL 0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 3

L OTHER USER COMBINATIONS

Combination___________

GR

Method Load

Sum Gravity

Factor1.00__

1.00

RemarksDefault

Default

Ti Sum Thermal 1

Press 1

1.00 Default

1.00 DefaultP1 Sum

RI Sum

R2

R3

Sum

Sum

Response 1 1.00

Response 2 1.00

Response 3 1.00

Default

Default

Default

SSE-SEISMC SRSS Response 1Response 2Response 3

1.001.001.00

User

l-

Page 101: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

ALLCULATION 240046-C-001 ATTACHMENT B PAGE B18

…_______________________________________________________________________________AUXSTM1 240046 EQE International

'0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 4

CODE COMPLIANCE

-Y - Factor ..................... 0.40Weld efficiency factor ................ 1.00Range reduction factor ........ * ....... 1.00Design Pressure Factor ...... .......... 1.00Minimum stress ratio used in reports.... 0.00

| Include corrosion in stress calcs. YInclude axial force in code stress .... NSet sustained SIF to 1.00 .... ......... NLongitudinal pressure calculation ..... PD/4t

L Include rigorous pressure .... ......... N

i

U-

Page 102: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

I ALCULATION 240046-C-001 ATTACHMENT E PAGE B19

___________ ___________________.

IAUXSTM1 240046L' '0/98 TMI-1 AUX STEAM LINE

___-

REPNESETRMLA AE

._________________________________________________

EQE InternationalAutoPIPE+4.70 RESULT PAGE 5s

-_________________________________________________

RESPONSE SPECTRUM LOAD CASES :-

Number of load cases analysed : 3

Load case 1 - R1

Missing mass : YesZPA : Yes

Combination method : SRSS

X- Spectrum : 305NSMultiplier : 1.00

305NS

Freq (Hz)

U. 0.1500.300

t 0.450g p.600

1.1002.500L 4.1008.600

i 15.000L 27.000

Grav(-___________

0.010.050.080.130.160.200.310.370.430.360.17

Freq (Hz)

0.2000.3500.5000.6500.9001.3003.0005.000

10.00020.00033.000

Grav(_____________

0.030.050.090.150.170.250.340.400.480.200.15

Freq (Hz)________

0.2500.4000.5500.7001.0002.0003.6006.900

11.00021.000

Grav(_____________

0.040.060.100.150.180.280.370.410.480.17

i.i-

Page 103: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

T, ALCULATION 240046-C-001 ATTACHMENT B PAGE B20

| 'UXSTM1 240046 EQE International0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 6

r

Load case 2 - R2

Missing mass : YesZPA : Yes

Combination method : SRSS

Y- Spectrum : 305NSMultiplier : 0.67

305NS

L Freq(Hz)________

L 0.150L 0.3000.4500.600

I' 0.800L 1.100

2.500

1 4.100.600

L-A5 . 00027.000

Grav(_____________

0.010.050.080.130.160.200.310.370.430.360.17

Freq(Hz)________

0.2000.3500.5000.6500.9001.3003.0005.000

10.00020.00033.000

Grav(_____________

0.030.050.090.150.170.250.340.400.480.200.15

Freq (Hz)________

0.2500.4000.5500.7001.0002.0003.6006.900

11.00021.000

Grav( )

0.040.060.100.150.180.280.370.410.480.17

Page 104: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

iLCULATION 240046-C-001 ATTACHMENT B PAGE B21

________________________________________________________________________________

1 LUXSTM1 240046 EQE Internationalt- l)/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 7

Load case 3 - R3

Missing mass : YesZPA : Yes

Combination method : SRSS

Z- Spectrum : 305EW- Multiplier : 1.00

305EW

l- Freq(Hz)________

I 1 0.1500.320

a 0.5601.0501.950

L 4.7007.1003.000

A, .000

Grav(_____________

0.020.050.110.190.290.410.460.360.14

Freq(Hz) Grav(

0.210 0.030.420 0.070.620 0.141.070 0.222.950 0.355.100 0.449.000 0.37

20.500 0.25

Freq(Hz) Grav(

0.280 0.030.510 0.110.810 0.171.100 0.263.700 0.386.050 0.46

11.500 0.3827.000 0.15

Page 105: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

C JCULATION 240046-C-001 ATTACHMENT B PAGE B22

L.UXSTM1 240046 EQE International* 0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 8

~F R E Q U E N C I E S

lode Frequency Frequency Period Participation factorsLumber (Rads/sec) (Hertz) (Sec) X Y Z

…_____ ----------- ---------- ------ --- ----- ---- - --- - -------

1

2

3

4

S

! 6C-

7

l_ 8

1 11

12

13

, 14

15

t 16

17

18

19

L 20

21

L 22

24

4.0612

13.3305

17.9294

22.5992

28. 6141

29.6625

31.5866

39.0302

48.0421

52.2803

61.3152

69.8966

73.3366

86.4064

96.1673

103.5508

110.9562

114.5139

120.1983

128.7373

131.5620

138.4425

141.9278

146.8770

0.6464

2.1216

2.8535

3.5968

4.5541

4.7209

5.0272

6.2119

7.6461

8.3207

9.7586

11.1244

11.6719

13.7520

15.3055

16.4806

17.6592

18.2255

19.1301

20.4892

20. 9387

22.0338

22.5885

23.3762

1.547

0.471

0.350

0.278

0.220

0.212

0.199

0.161

0.131

0.120

0.102

0.090

0.086

0.073

0.065

0.061

0.057

0.055

0.052

0.049

0.048

0.045

0.044

0.043

-0.380

2.329

2.115

-0.085

-0.066

-0.462

-0.161

1.061

1.024

-0.122

-0.768

-0.251

0.054

-0.196

-0.062

0.054

-0.010

-0.182

0.064

-0.139

-0.139

-0.245

-0.172

-0.037

-0.003

0.134

0.047

-0.262

0.025

0.319

-0.646

0.061

-0.826

0.929

-0.339

-0.461

-0.511

-0.831

-0.217

-0.074

0.206

-0.599

-0.698

-0.223

0.372

0.632

-0.111

0.104

-3.020

-0.746

0.338

-0.398

-0.535

0.329

-0.571

-0.495

0.510

0.381

0.236

-0.346

* -0.111

0.209

-0.080

-0.160

-0.033

-0.139

0.160

-0.325

-0'.387

-0.240

-0.065

-0.040

Page 106: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

ALCULATION 240046-C-001 ATTACHMENT B PAGE B23

…-------------------------------------------------------------------------------AUXSTM1 240046 EQE International

L" 10/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 9------------------------------------------------------------------ ____________

9 F R E Q U E N C I E S

~,Mode Frequency Frequency Period Participation factors,1u ber (Rads/sec) (Hertz) (Sec) X Y Z

25 159.3507 25.3615 0.039 0.016 0.115 -0.101

26 171.1813 27.2444 0.037 -0.115 0.122 -0.009

27 176.0196 28.0144 0.036 0.199 0.143 -0.135A-

28 186.5147 29.6847 0.034 -0.117 -0.270 0.180

29 200.5212 31.9139 0.031 -0.049 -0.080 -0.026

30 203.3268 32.3605 0.031 -0.17-AQ n ion- - - - - - -

L-J

U

L

I'

-.,

I .,

6.-

L-

Page 107: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

, LCULATION 240046-C-001, X T 1 2 0 4 ATTACHMENT B PAGE B24

_______________________________.

, UXSTM1 240046'I- '0/98 TMI-1 AUX STEAM LINE_ - -S_ -__-__-__-__-__-__-__-__-__-__-__-.

r

~D I'S I

.____________________________________-____________

EQE .InternationalAutoPIPE+4.70 RESULT PAGE 10

._________________________________________________

P L A C E M E N T S

'oint Load1-?am'e combination

i'~tr** Segment A begin

TRANSLATIONS (in )

_ _ _ _Y Z

_ _ _ _ _ _ - - - - - -

ROTATIONS (deg ). X Y Z_ _ _ _ _ _ - - - - - - - - - - - -

GRT1P1SSE-SEISMC

GR -T1P1SSE-SEISMC

GRT1P1SSE-SEISMC

O .000O. 000O. 000O .000

O .001-0.034

O .0000.175

O .001-0.038

O .0000.197

O .000O .000O. 000O .000

O. 000O .000O. 000O. 000

O. 000O .000O .000O .001

A02 N

!

A0

1 t

U,,

.1 GRT1P1SSE-SEISMC

>3 GRT1P1SSE-SEISMC

14 N GRT1 -PiSSE-SEISMC

4 M GRT1P1SSE-SEISMC

4 F GRT1P1SSE-SEISMC

O .001-0.030

O .0000.262

O .0010.147O .0000.262

O .0010.338O .0000.262

O .0010.351O .0000.262

0.0020.354O .0000.264

-O.001O .001O .0000.008

O .000: . 000O .000O .000

-O.0010.006O .0000.008

O .000O .000O .000O .000

0.000,-0.014

O 0.0000.007

O .000O .000O .000O. 000

O. 0000.146O .000O. 000

O .0000.155O . 000O .000

O .0000.186O. 0000.082

-0.0030.350O .0001.260

-0.0070.518O0.0012.739

-0.0070.527O. 0012.849

-0.0070.532O .0012. 919

O. 000O. 000O .000O .000

O .000--O.001

O .000O .011

O .000-O .001

O .0000.014

0 . 000 . 000 . 000.000

O .001-0.037

O .0000.203

O .001-0.038

O .0000.215

O .000O .000O .000O. 000

-0.002-0.002

O .000O .010

-0.003-0.002

O .000O. 011

O .001-O .005

O . 0000.048

O. 000-0.014

O .0000.118

-0.002-0.024

O .0000.192

-0.003-0.019

O .0000.197

-0. 003-0.016

O .0000.214

O. 001-0.072

O. 0000.487

0.002-0. 084, O .0000.645

0.002-0.063

O. 0000.677

-0.002-O.001

O .0000.004

O .0000.002O .0000.012

0.004-O.001

O .0000.028

'A0 0.001 0.004-0.047 -0.008

O.000, 0.0000. 665 0.089

IL~O .001

-0.040O .0000.664

0.005-0.016

O .000O .150

Page 108: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

ALCULATION 240046-C-001 ATTACHMENT B PAGE B25

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

I AUXSTM1 240046> 30/98 TMI-1 AUX STEAM LINE

% J ,

EQE InternationalAutoPIPE+4.70 RESULT PAGE 11

…______________________________________________

D I S P L A C E M E N T S

, Pointname______

-A05 N

bI-.

1l0N F

i

,A06

|A07 N

Loadcombination___________

GRTIP1SSE-SEISMC

GRTiP1SSE-SEISMC

GRT1P1SSE-SEISMC

GRT1P1SSE-SEISMC

TRANSLATIONS (in' )x y

0.012 0.0000.324 -0.1590.000 0.0000.414 0.007

0.0140.3400.0000.444

0.0140.3930.0010.444

0.0140.4020.0010.444

.0.002-0.179

0.0000.047

0.008-0.1790.0000.162

0.009-0.1800.0000.182

z______

0.0000.5560.0013.268

0.0010.5520.0013.428

0.0000.5280.0013.765

0.0000.5230.0013.822

-0.0060.0170.0000.163

-0.0070.0260.0000.141

-0.0070.0280.0000.138

-C-cCC

ROTATIONS (deg )X Y Z

.005 0.001 0.0071.009 -0.001 -0.016.000 0.000 0.0001.211 0.618 0.190

0.0000.0330.0000.570

0.0000.0470.0000.551

0.0000.0490.0000.547

0.0'09-0.0020.0000.190

0.008-0.0010.0000.188

0.008-0.0010.0000.188

A07 F

L

A09 N

L

l k09 F

. >

A-10 N

L

GRT1P1SSE-SEISMC

GRTiP1SSE-SEISMC

GRTiP1SSE-SEISMC

GRT1P1SSE-SEISMC

GRT1P1SSE-SEISMC

0.0140.4020.001.0.446

0.0150.2110.0000.841

0.0150.1960.0000.875

0.0140.1640.0000.967

0.0140.1640.0000. 967

0.008-0.1720.0000.204

-0.005-0.1010.0000.137

-0.006-0.0960.0000.135

-0.009-0.1040.0000.132

-0.009-0.1040.0000.132

0.0010.4900.0013.926

0.0010.3580.0003.926

0.0010.3490.0003.926

0.0040.3210.0003.934

0.0040.3210.0003.934

-0.0090.0420.0000.105

-0.0100.0490.0000.080

-0.0110.0490.0000.078

-0.0150.0460.0000.053

-0.0150.0460.0000.053-

0.0000.1100.0000.447

-0.0010.1390.0000.374

-0.0010.1410.0000.369

0.0010.1600.0000.288

0.0010.1600.0000.288

0.0020.0050.0000.190

-0.0030.0010.0000.182

-0.0040.0010.0000.181

-0.007-0.008

0.0000.146

-0.007-0.0080.0000.146

Page 109: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

.ILCULATION 240046-C-001 ATTACHMENT B PAGE B26

11UXSTM1 240046 EQE International_ '0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 12

-D I S P L A C E M E N T S

i?oint Load TRANSLATIONS (in ) ROTATIONS (deg )&,ame combination X Y Z X Y Z

…_____ - --- - - ----- - --- -- - ----- _ ____ - --- -- - -- - - -,110 F GR 0.012 -0.012 0.007 -0.012 0.003 -0.011* T1 0.126 -0.112 0.293 0.045 0.175 -0.015

P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 1.037 0.126 3.937 0.043 0.205 0.109

;11 GR 0.004 0.000 0.007 0.008 0.003 -0.023Ti -0.456 0.000 0.013 0.014 0.173 -0.010P1 -0.001 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 1.307 0.000 3.937 0.019 0.071 0.067

A12 GR -0.003 0.000 0.007 -0.005 0.003 -0.031T1 -0.812 0.000 -0.189 -0.006 0.127 -0.007P1 -0.001 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 1.105 0.000 3.938 0.007 0.176 0.037

)13 N GR -0.003 -0.001 0.007 -0.006 0.003 -0.032Ti -0.834 -0.001 -0.204 -0.005 0.122 -0.007P1 -0.001 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 1.078 0.001 3.938 0.007 0.184 0.035

A13 F GR -0.004 -0.004 0.006 -0.007 0.003 -0.033T1 -0.844 -0.002 -0.223 -0.002 0.087 -0.006

L P1 -0.001 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 1.051 0.002 3.928 0.011 0.241 0.030

1,14 N GR -0.014 -0.002 -0.003 0.039 0.004 0.001T1 -0.703 -0.001 -0.534 0.010 -0.022 0.001P1 -0.001 0.000 -0.001 0.000 0.000 0.000SSE-SEISMC 0.410 0.001 3.286 0.021 0.361 0.007

A14 M GR -0.014 0.000 -0.004 0.038 0.004 -0.001T1 -0.696 0.000 -0.536 0.012 -0.039 0.003P1 -0.001 0.000 -0.001 0.000 0.000 0.000SSE-SEISMC 0.402 0.000 3.263 0.023 0.373 0.005

,.14 F GR -0.014 0.000 -0.004 0.038 0.004 -0.003T1 -0.688 0.001 -0.533 0.012 -0.057 0.005P1 -0.001 0.000 -0.001 0.000 0.000 0.000

F SSE-SEISMC 0.399 0.000 3.235 0.024 0.388 0.004

\I15 GR -0.014 0.000 -0.016 0.036 0.005 -0.003T1 -0.450 0.000 -0.292 0.026 -0.110 -0.013.P1 -0.001 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.399 0.000 2.154 0.043 0.439 0.008

Page 110: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

; ALCULATION 240046-C-001 ATTACHMENT B PAGE B27

.______________________________________________________________________

I PUXSTM1_i-r 0/98

x---.240046TMI-1 AUX STEAM LINE

EQE InternationalAutoPIPE+4.70 RESULT PAGE 13

,_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

D I S P L A C E M E N T S

i PointB1ame

, 1

Loadcombination___________

GRT1P1SSE-SEISMC

-TRANSLATIONS (in )x y z

…__ _ _ _ - - - - - - - - - - - -

ROTATIONS (des

-0.014-0.1330.0000.399

-0.010-0.0920.0000.038

-0.0320.1210.0000.616

x______

0.0330.0440.0000.073

0.004-0.1010.0000.408

g )z

-0.002-0.0220.0000.009

A18 N

Lj18 F

A19

j _

i20NLi~

A20 F

tiL

f 21 N

GRT1P1SSE-SEISMC

GRT1P1SSE-SEISMC

GRT1P1SSE-SEISMC

GRTIP1SSE-SEISMC

GRT1P1SSE-SEISMC

GRT1P1SSE-SEISMC

GRT1P1SSE-SEISMC

GRTiP1SSE-SEISMC

-0.014-0.0260.0000.399

-0.004-0.0270.0000.397

-0.001-0.0210.0000.345

-0.001-0.0140.0000.253

-0.001-0.0130.0000.227

-0.001-0.0070 . 0000.199

-0.0010.0190.0000.147

-0.0010.0230.0000.127

-0.019-0. 1090.0000.027

-0.019-0.0290.0000.027

-0.012-0.0060.0000.015

0.0000.0000.0000.000

0.0030.0010.0000.004

0.0040.0030.0000.008

0.0000.0060.0000.016

-0.0010.0060.0000.017

-0.0360.2320.0000.158

-0.0070.2760.0000.087

0.0000.2650.0000.076

0.0000.2290.0000.076

0.0000.2180.0000.076

0.0000.2050.0000.064

0.0000.1770.0000.009

0.0000.1640.0000.000

0.0320.0500. 0000.083

0.0320.0450.0000.081

0.0300.0160.0000.040

0.0260.0120.0000.032

0.0230.0110.0000.030

0.0090.0040.0000.014

0.0040.0010.0000.009

0.001-0.0030.0000.011

0.003-0.0760.0000.354

0.002-0.0490. 0000.296

0.000-0.0200.0000.242

0. 000-0.0130.0000.227

0.000.-0. 0120.0000.223

0.0000.0010.0000.182

0. 0000.0050.0000.166

-0.0010.0150.0000.117

-0.010-0.0030.0000.029

-0.0120.0030.0000.035

-0.0140.0140.0000.056

-0.0150.0120.0000.048

-0.0150.0110.0000.046

-0.0200.0070.0000.040

-0.0180.0060.0000.033

-0.0170.0040.0000.029

Page 111: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

kLCIUT.ArThn 9dnnDsz-r,-nn1 ,I7 W MMtxy -

PAGE B28

__-_____________________________________________________________________________

i kUXSTM1 240046 EQE InternationalI *. 0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 14

-KJ-

D I S P L A C E M E N T S

Doint Load TRANSLATIONS (in ) ROTATIONS (deg_iame combination X Y Z X Y Z

…__ _ _ _ - - - - - -- - - -- - -- - -- -- - - -- - - - - - - - - - - - - - - - - - - - - - - - -122 GR 0.000 0.000 0.000 0.000 0.000 0.000

Ti 0.000 0.000 0.000 0.000 0.000 0.000P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.000 0.000 0.000 0.000 0.000 0.000

2** Segment A end ***

;** Segment B begin ***

A17 GR -0.014 -0.019 -0.036 0.032 0.003 -0.010Ti -0.026 -0.109 0.232 0.050 -0.076 -0.003

, P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.399 0.027 0.158 0.083 0.354 0.029

,301 GR -0.017 -0.019 -0.045 0.032 0.003 -0.011T1 -0.026 -0.131 0.219 0.051 -0.076 -0.001P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.397 0.027 0.178 0.083 0.353 0.030

GR -0.018 -0.019 -0.048 0.032 0.004 -0.011T1 -0.026 -0.141 0.213 0.053 -0.076 0.001P1 0.000 0.000 0.000 0.000 0.000 0.000

L SSE-SEISMC 0.396 0.027 0.187 0.081 0.350 0.033

.03 N GR -0.021 -0.019 -0.055 0.030 0.014 -0.015Ti -0.017 -0.161 0.193 0.108 -0.052 0.064P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.357 0.027 0.199 0.042 0.242 0.276

j03 F GR -0.021 -0.020 -0.056 0.032 0.017 -0.014T1 -0.015 -0.167 0.190 0.137 -0.042 0.087P1 0.000 0.000 0.000 0.000 0.000 0.000

i SSE-SEISMC 0.346 0.027 0.200 0.048 0.217 0.400

B04 N GR -0.021 -0.022 -0.059 0.029 0.021 -0.015Ti -0.011 -0.184 0.186 0.153 -0.040 0.095P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.315 0.027 0.199 0.056 0.204 0.454

L04 F GR -0.021 -0.022 -0.059 0.016 0.025 -0.013Ti -0.008 -0.189 0.181 0.176 -0.041 0.098P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.297 0.026 0.198 0.072 0.200 0.514

Page 112: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

'ALCULATION 240046-C-001 ATTACHMENT B- PAGE B29

AUXSTM1 240046 EQE International30/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 15

-- - - - - - - - - -- - - - - - - - - - -- - - - - - - - - - --------------- _! - -

D I S PLA CE ME NTS

i Points..,,name

B05

Loadcombination___________

GRTiP1SSE-SEISMC

TRANSLATIONS (in )x y z

… _____ ------ _____-0.023 -0.022 -0.0610.010 -0.206 0.1460.000 -0.000 0.0000.199 0.026 0.187

ROTATIONS (deg )x y z

0.005 0.035 -0.0100.190 -0.047 0.0820.000 0.000 0.0000.092 0.194 0.512

**Segment B end

1 *** Segment C begin ***

B05 GR -0T1 0P1 0SSE-SEISMC 0

l C17 GR -0Ti 0P1 0SSE-SEISMC 0

.023

.010

.000

.199

.019

.014

.000

.112

-0.022-0.2060.0000.026

-0.022-0.2210.0000.026

-0.0610.1460.0000.187

-0.0470.0970.0000.139

(<C 02

L

_ 03

I

, C04 N

l

,_704 -F

GRTiP1SSE-SEISMC

GRTiP1SSE-SEISMC

GRT1P1SSE-SEISMC

GRTiP1SSE-SEISMC

GRT1P1SSE-SEISMC

-0.0080.0070.0000.047

-0.0050.0040.0000.023

0.0000.0000.0000.000

0.012-0.0090.0000.035

0.015-0.0130.0000.043

-0.022-0.2330.0000.026

-0.022-0.2380.0000.026

-0.022-0.2420.0000.026

-0.022-0.2500.0000.026

-0.027-0.2490.0000.033

-0.0220.0430.0000.063

-0.0110.0210.0000.032

0.0000.0000.0000.000

0.018-0.0330.0000.052.

0.026-0.0390.0000.069

0.0050.1900.0000.092

-0.1520.3450.0000.452

-0.2070.4110.0010.602

-0.2070.4110.0010.603

-0.2140.4010.0010.613

-0.2190.3780.0000.615

-0.2240.3610.0000.620

0.1500.0130.0000.614

0.1500.0130.0000.615

0.1600.0320.0000.668

0.1750.0640.0000.756

0.1850.0840.0000.809

0.035-0.0470.0000.194

0.123-0.0380.0000.480

-0.0100.0820.0000.512

0.091-0.0480.0000.472

0.073-0.0630.0000.451

0.073-0.0630.0000.451

0.106-0.0840.0000.431

0.169-0.1160.0000.408

0.231-0.1420.0000.400

f

i-.�

Page 113: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

; ALCULATION 240046-C-001 ATTACHMENT B PAGE B30

AUXSTM1 240046 EQE International_ '0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 16

V-----------------------------------------------i-------------__-----

~D I S e L A C E M E N T S

I Point-ame

Z C05 N

X05 F

Loadcombination___________

GRT1P1SSE-SEISMC

GRT1P1SSE-SEISMC

TRANSLATIONS (in )x

______

0.015-0.0370.0000.043

0.020-0.0420.0000.050

y

-0.100-0.2020.0000.134

-0.104-0.2000.0000.141

z

0.081-0.0100.0000.286

0.090-0.0130.0000.311

ROTATIONS (deg )X y z

-0.237 0.209 0.2460.291 0.114 -0.1920.000 0.000 0.0000.632 0.865 0.371

-0.2400.2800.0000.637

0.2120.1130.0000.847

0.208-0.1980.0000.355

-C06 N

I 06 F

LJC07 N

_

GRT1P1SSE-SEISMC

GRT1P1SSE-SEISMC

GRT1P1SSE-SEISMC

GRT1P1SSE-SEISMC

GRT1P1SSE-SEISMC

0.049-0.0760.0000.108

0.051-0.0810.0000.115

0.051-0.0860.0000.115

0.050-0.0860.0000.107

0.011-0.0490.0000.050

-0.104-0.2140.0000.141

-0.106-0.2130.0000.148

-0.112-0.2020.0000.172

-0.114-0.1980.0000.180

-0.114-0.1680.0000.180

0.131-0.0590.0000.401

0.140-0.0620.0000.426

0.154-0.0560.0000.473

0.154-0.0490.0000.475

0.0730.0380.0000.277

-0.2400.2660.0000.661

-0.2380.2690.0000.669

-0.2350.2720.0000.685

-0.2330.2710.0000.699

-0.2440.2090.0000.725

0.2190.0990.0000.778

0.2200.0940.0000.763

0.2210.0850.0000.746

0.2210.0750.0000.728

0.218-0.0070.0000.638

0.134-0.1850.0000,354

0.097-0.1660.0000.371

0.085-0.1490.0000.390

0.090-0.1240.0000.419

0.140-0.1190.0000.385

F

; I

C08j :

GRT1P1SSE-SEISMC

0.003-0.0420.0000.068

-0.114-0.1630.0000.180

-0.114-0.1510.0000.180

0.0600.0490.0000.255

0.0240.0730.0000.223

-0.2440.2090.0000.725

-0.2640.1380.0000.709

0.218-0.0070.0000.638

0.141-0.1190.0000.385

GRT1P1SSE-SEISMC

-0.019-0.0220.0000.112

0.216-0.0400.0000.607

0.171-0.1780.0000.279

I t2l�

Page 114: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

LLCULATION 240046-C-001 ATTACHMENT B PAGE B31

________________________________________________________________________________

jUXSTM1 240046 EQE InternationalL- 0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 17-------- - - - - - - - - - - - - --

D I S P L A C E M E N T S

Point Loade-~ame combination

10 GRTiP1

,~ SSE-SEISMC

tk** Segment C end

TRANSLATIONS (in )X Y z

-0.044 -0.113 -0.0240.009 -0.136 0.0910.000 0.000 0.0000.147 0.180 0.249

ROTATIONS (deg ). X y z______

-0.2940.0670.0000.739

0.235_0.235

-0.0350.0000.580

0.122-0.1810.0000.175

*** Segment G begin ***

C17 GR -0.019Ti 0.014

: P1 0.000SSE-SEISMC 0.112

-0.022-0.2210.0000.026

-0.0470.0970.0000.139

-0.1520.3450.0000.452

0.123-0.0380.0000.480

0.091-0.0480.0000.472

L�-�

GRTiP1SSE-SEISMC

GRTiP1SSE-SEISMC

-0.019-0.0130.0000.112

-0.019-0.0220.0000.112

-0.091-0.1710.0000.147

-0.114-0.1510.0000.180

0.0030.0790.0000.175

0.0240.0730.0000.223

-0.236 0.1950.190 -0.0590.000 0.0000.622 0.616

0.245-0.2050.0000.353

0.171-0.1780.0000.279

-0.2640.1380. 0000.709

0.216-0.0400.0000.607

Segment G end ***

Segment H begin ***

:

H01 N

L- F

H0d1 F

GRTiP1SSE-SEISMC

GRTiP1SSE-SEISMC

GRTiP1SSE-SEISMC

-0.0440.0090.0000.147

-0.0760.0830.0000.176

-0.0740.0860.0000.172

-0.113-0.1360.0000.180

-0.113-0.1000.0000.180

-0.110-0.0980.0000.175

-0.0240.0910.0000.249

-0.1630.0850.0000.475

-0.1700.0840.0000.486

-0.2940.0670.0000.739

-0.390-0.0970.0000.730

-0.406-0.121

0..0000.722

0.235-0.0350.0000.580

0.277-0.0240.0000.565

0.281-0.0230.0000.568

0.122-0.181

O.'0000.175

0.041-0.1770.0000.058

0.033-0.1750.0000.063

Page 115: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

L2ALCULATION 240046-C-001 ATTACHMENT B PAGE B32

____________________.

1,AUXSTM1 240046L 30/98 TMt-1 AUX

.____________________________________________________________

STEAM LINEEQE InternationalAutoPIPE+4.70 RESULT PAGE 18

r----------------------------- ------------------- --------------------------

D I S P L A C E M E N T S

X Point'~name

______

i H02 NI'

Loadcombination___________

GRTiP1SSE-SEISMC

TRANSLATIONS (in )x

______

-0.0360.1070.0000.090

y

-0.050-0.0640.0000.076

H02 F GR -0.034Ti 0.110P1 0.000SSE-SEISMC 0.085

,IH03 N GR -0.033Ti 0.140P1 0.000SSE-SEISMC 0.069

t H03 F GR -0.031Ti 0.142P1 0.000SSE-SEISMC 0.063

H04 N GR -0.006Ti 0.152P1 0.000SSE-SEISMC 0.012

LH04 F GR 0.000T1 0.152P1 0.000SSE-SEISMC 0.000

H05 GR 0.000Ti 0.146Pi 0.000SSE-SEISMC 0.000

H06 GR 0.000L Ti 0.000

P1 0.000SSE-SEISMC 0.000

Segment H end ***

L~ **Segment I begin ***

-0.047-0.0610.0000.070

-0.047-0.0450.0000.070

-0.043-0.0420.0000.066

-0.009-0.0190.0000.019

0.000-0.0100.0000.008

0.0000.0000.0000.000

0.0000.0000.0000.000

z

-0.2300.0740.0000.577

-0.2380.0720.0000.588

-0.3200.0360.0000.703

-0.3280.0330.0000.714

-0.3630.0240.0000.759

-0.3630.0210.0000.755

-0.3390.0200.0000.711

0.0000.0000.0000.000

ROTATIONS (deg )x y z

…_____ ------ -------0.435 0.291 0.008-0.172 -0.019 -0.1660.000 0.000 0.0000.690 0.567 0.088

-0.435-0.1790.0000.679

-0.440-0.199-0.0010.641

-0.442-0.205-0.0010.627

-0.436-0.207-0.0010.600

-0.421-0.2000.0000.577

-0.403-0.1910.0000.552

0.000*0. 0000.0000.000

0.293-0.0190.0000.568

0.302-0.0170.0000.571

0.304-0.0180.0000.572

0.306-0.0160.0000.575

0.310-0.0170.0000.576

0.309-0.0170.0000.576

0.0000.0000.0000.000

0.003-0.1630.0000.096

-0.009-0.1530.0000. 110

-0.011-0.1490.0000.112

-0.014-0.1400.0000.111

-0.010-0.1290.0000.105

0.003-0.1130.0000.095

0.0000.0000.0000.000

Page 116: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

'ALCULATION 240046-C-001 ATTACHMENT B PAGE B33

-AUXSTM1 240046 EQE International. 10/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 19

D I S P L A C E M E N T S

Point Load TRANSLATIONS (in ) ROTATIONS (deg ),-name combination X Y Z X Y Z

…___ _ _ - -- - - - - - - - - - - - - - - - -- -- - - - - - -- - - - - - - - - - - - - -- - - - -iB05 GR -0.023 -0.022 -0.061 0.005 0.035 -0.010

Ti 0.010 -0.206 0.146 0.190 -0.047 0.082P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.199 0.026 0.187 0.092 0.194 0.512

GR -0.020 -0.021 -0.055 0.019 0.055 -0.014TI -0.002 -0.206 0.138 0.121 -0.062 -0.075P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.199 0.068 0.176 0.060 0.266 0.159

,02 N GR -0.023 -0.019 -0.050 0.028 0.065 -0.027Ti -0.009 -0.197 0.133 0.083 -0.057 -0.160P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.199 0.071 0.162 0.051 0.351 0.085

t I02 F GR -0.021 -0.019 -0.048 0.033 0.081 -0.047Ti -0.008 -0.191 0.135 0.038 -0.034 -0.274P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.185 0.066 0.155 0.056 0.514 0.393

103 N GR -0.010 -0.022 -0.045 0.036 0.083 -0.063T1 0.014 -0.186 0.143 0.007 -0.069 -0.371P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.103 0.065 0.154 0.058 0.506 0.634

LI03 F GR -0.008 -0.022 -0.044 0.036 0.083 -0.066Ti 0.021 -0.184 0.144 -0.004 -0.078 -0.392P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.086 0.065 0.154 0.062 0.495 0.677

I04 N GR -0.002 -0.022 -0.041 0.034 0.079 -0.063T1 0.062 -0.175 0.143 -0.014 -0.137 -0.403P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.016 0.065 0.153 0.062 0.408 0.646

I04 F GR 0.000 -0.021 -0.038 0.031 0.076 -0.050Ti 0.070 -0.163 0.138 -0.023 -0.173 -0.370P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.001 0.052 0.144 0.070 0.357 0.450

I05 GR 0.000 0.000 0.000 0.000 0.000 0.000Ti 0.000 0.000 0.000 0.000 0.000 0.000

L P1 0.000 0.000 0.000 0.000 0.000 0.000SSE-SEISMC 0.000 0.000 0.000 0.000 0.000 0.000

J Segment I end ***

Page 117: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

PALCULATION 240046-C-O01 ATTACHMENT B PAGE B34

_________.

I AUXSTM1L' '0/98

1

._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _240046TMI-1 AUX STEAM LINE

EQE InternationalAutoPIPE+4.70 RESULT PAGE 20

._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - -

R E S T R A I N T R E A-C T I O N S

1 Point-name

______

Loadcombination X

FORCES (lb ) MiY Z Result X

…__ _ _ _ -- - - - - - - - - - - - - - - - - -

DMENTS (ft-lbY Z

---- ----- ___

)Result

…-- - -

AnchorGRTiP1SSE-SEISMC

1-78

0454

-133-26

0259

-i79

0442

133114

0684

175690

669

22-1505

-27277

-59-51

0259

1861508

27312

A03

4I M

L.

I A06

Y - StopGRT1P1SSE-SEISMC

Y - StopGRTiP1SSE-SEISMC

Y - StopGRT1P1SSE-SEISMC

SpringGRT1P1SSE-SEISMC

SpringGRT1P1SSE-SEISMC

Y - StopGR .T1P1SSE-SEISMC

0 -3120 3o 00 260

0 -45331-,70 76 ' 70 00 401

0 -436 '0 400 00 370

0 -2870 -160 00 15

O -497O -110 00. 15

*0 -557O -1690 00 299

0 3120 30 00 260

5750

0000~

0000

0 4530 760 0o 401 V

-9** 7 7,M1

0 4360 400 00 370

76*

0 2870 160 00 15

5/b 4

0 4970 110 00 -'

0 5570 1690 00 299

/0 z

0000

0000

0000

0000

0000

0000

0000

0

00

0

000

0

000O

0000

0

00in0

00

0

00

0

000

° 10000

0000

0000

0000

0000

0000

0000

Page 118: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

C LCULATION 240046-C-001 ATTACHMENT B PAGE B35

s^.UVSTM1 240046 EQE International1 /98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 21

R E S T R A I N T R E A C T I O N S

I 'oint-name

; 12L

A14 M

L _

Loadcombination

FORCES (lb ) MOMENTS (ft-lb )X y Z Result X Y Z Result

…__ _ - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - -Y - StopGRTiP1SSE-SEISMC

Y - StopGRTiP1SSE-SEISMC

Y - StopGRT1P1SSE-SEISMC

SpringGRT1P1SSE-SEISMC

Y - StopGRTiP1SSE-SEISMC

o -490O-3/o 97 430 00 190

0 -4951 -10 780 00 98

0 -5650 -1520 \ 00 151

0 4900 970 00 190

0 4950 780 00 98 V

sis 515

0000

0000

0000

0000

0000

5651520151

0000

0000

0000

0000

0000

0000

0000

0000

00.

00

-372960

639

0K0

0 &

0006

00000t0

4541281

15039

0000

-506-10

04

0 5060 100 00 4

51i0

0 -7070 590 00 188

0000

A2',

i

707590

188 -

45f+ 83 C.

0000

0000

2 AnchorGRTiP1SSE-SEISMC

-9178

0449

-154590

154

14-132

0375

1552290

605

254-357

0930

-591227

14911

'U03 GuideGRTiP1SSE-SEISMC

31-19

047

91 *

0 -80 320 00 47

g7I

32380

67i

I1V1

0000

0000

0000

0000

Page 119: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

ALCULATION 240046-C-001 ATTACHMENT B PAGE B36

.^AUXSTM1 240046 EQE International'% '30/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 22

- ---

,-Point Load| name combination X

H05 Y - StopGRT-P1

-_ SSE-SEISMC

-H06 AnchorGRT1P1SSE-SEISMC

105 Anchor- GR

Tl

SSE-SEISMC 2

R E S T R A I

FORCES (lby z

0 -480 -280 00 34

N T

Res

0000

R E A C T I O N S

MOMENTS (ft-lb )cult X Y Z

…__ _ -- -- -- - - - - - -- - - - - -- - -

48 0 0 028 0 0 0

0 0 0 034 0 0 0

-13304

-6-40

42

/r4

-3 14-0 40 0

13 18

-2 2021 820 019 282

-12-60

17

2-104

23-10

62

10-540O40

-18909

-8-37

046

Result_______

0000

32110

65

1366061

Page 120: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

PLCULATION 240046-C-001 ATTACHMENT B PAGE B37

…_______________________________________________________________________________-AWXSTM1 240046 EQE International

0 '30/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 23

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

, Point Load Ma-lame combination (Sus.)

1 -- - - - - - - - - - - - - - - - - - - - - - -

B31.1 (1992) CODE COMPL3mients in ft-lb )

Mb Mc(Occ.) (Exp.) S.I.F

-_ _ _ _ _ _ - - - - - - - -

(Stress in psi )Eq. Load Code Codeno. type Stress Allow.

…_ _ - - - - - - - - - - - - - - - -

Segment A begin ***

AOO Max PGR + Max P 186L Cold to TiSSE-SEISMC 0 7312GR+P+SSE 0 7355

L,01 Max PGR + Max P 198Cold to TiSSE-SEISMC 0 6507GR+P+SSE 0 6569

1.001508 1.00

1.001.00

1.00891 1.00

1.001.00

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

372300

107652205251

372309636

46454690

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

t 02 N- Max PGR + Max PCold to T1SSE-SEISMC

J GR+P+SSE

121

0 65140 6556

1.00854 1.00

1.001.00

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

372254610 -

46504680

A02

LI 2i

N+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

F- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

F+ Max P.GR + Max PCold to T1SSE-SEISMCGR+P+SSE

121

0 65140 6556

77

0 62190 6244

77

0 62190 6244

2.44854 2.44

2.442.44

2.44705 2.44

2.442.44

1.00705 1.00

1.001.00

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

372325

148785058560

372268122881208153

372223503

44404458

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

Lj02 ( 3) HOOP(11) SUST(13) DISP(12) OCC(12) OCC

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

495

0 31190 3295

1.00286 1.00

1.00'1.00

( 3) HOOP(11) SUST(13) DISP(12) OCC(12) OCC

372521204

22272352

1410014100211504230042300

Page 121: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

iALCULATION 240046-C-001U-

ATTACHMENT B PAGE B38

m-AUXSTM1 240046 EQE International'1P"'30/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 24

_ ---------------------------------------------------- _I---------------------__

ASME B31.1 (1992) CODE COMPLIANCE(Moments in ft-lb )

,,Point Load! name combination

------ -----------

A04 N- Max P1 GR + Max P

L Cold to TiSSE-SEISMC

1 * GR+P+SSE

Ma Mb Mc(Sus.) (Occ.) (Exp.) S.I.F

-_____ ---- --- -------

-A04 N+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

88

0 33410 3423

88

0 33410 3423

40

D 34620 3492

1.00989 1.00

1.001.00

2.44,989 2.44

2.442,44

2.441041 2.44

2.442.44

Eq.no.

( 3)(11)(13)(12)(12)

(Stress in psiLoad Codetype Stress

HOOP 372SUST 230DISP 706OCC 2385OCC 2444

L )

\ A04 M

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

372282

172143634470

372219

181245204560

CodeAllow.14100_

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

F- Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

76

0 32530 3322

2.441046 2.44

2.442.44

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

372267182242484337

1410014100211504230042300

A04

Li ;z-A05

F+ Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

N- Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

76

0 32530 3322

* 76

0 22370 2288

1.001046 1.00

1.001.00

1.001162 1.00

1.001.00

( 3) HOOP(11) SUST(13) DISP(12) oCC(12) OCC

( 3) HOOP(11) SUST(13) DISP(12) OCC(12) OCC

372222747

23232371

372222829

15971633

14100141002115042300.42300

1410014100211504230042300

N+ Max PGR + Max PCold to TISSE-SEISMCGR+P+SSE

76

0 22370 2288

2.441162 2.44

2. 442. 44

( 3) HOOP(11) SUST(13) DISP(12) OCC(12) OCC

372266

202229202988

1410014100211504230042300

Page 122: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

PkLCULATION 240046-C-001 ATTACHMENT B PAGE B39

…__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _,-AUXSTM1 240046 EQE International

0s" 1'0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 25

…---------------------------------------------------_ I- ------------------ __

L ASME B31.1 (1992) CODE COMPLIANCE

,?oint Load! iame combination

A05 F- Max PGR + Max P

L Cold to TiSSE-SEISMC

I GR+P+SSE

(Moments in ft-lb )Ma Mb Mc Eq. I

(Sus.) (Occ.) (Exp.) S.I.F no. I…__ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - _ _ _ _

50

0 25410 2580

2.441262 2.44

2.442.44

( 3)(11)(13)(12)(12)

I

I

(Stress in psiLoad Codetype Stress A____ ------ -

HOOP 372SUST 233)ISP 2197OCC 3317OCC 3369

Codeilow.

1410014100211504230042300

F+ Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

50

0 25410 2580

1.001262 1.00

1.001.00

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

372203901

18141842

1410014100211504230042300

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

ST- Max PGR + Max PCold to T1SSE-SETSMC

306

0 29530 3032

247

0 30430 3108

247

0 30430 3108

1.001433 1.00

1.001.00

-1.001468 1.00

1.001.00

2.441468 2.44

2.442.44

GR+P+SSE

A07 N+ Max PGR + Max P

L Cold to TiSSE-SEISMCGR+P+SSE

kr7 F- Max PGR + Max P

; Cold to TiL SSE-SEISMC

GR+P+SSE

07 F+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

372386

102321082165

372344

104821722219

372490

255639734058

372368

251040894145

372277

102922362266

141001A4100211504230042300

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

154 2.441442 2.44

0 3132 2.440 3175 2.44

154

0 31320 3175

1.001442 1.00

1.001.00

I I

Page 123: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

!LLCULATION 240046-C-001 ATTACHMENT B PAGE B40

________________________________________________________________________________

ttUXSTM1 240046 EQE Internationalje '0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 26

W J ---------------------------------------------------- --------------- -------

ASME B31.1 (1992) CODE COMPLIANC:(Moments in ft-lb )

I'oint! tame

A08

I!

Loadcombination___________

Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

Ma(Sus.)

_ _ _ _ _ _

Mb Mc(Occ.) (Exp.)

_ _ _ _ _ _ _ - - - - - - -

Eq.S.I.F no.

_ _ _ _ _ _ _ - - - -

E(Stress in psiLoad Codetype Stress J

HOOP 372SUST 490DISP 553OCC 2195OCC 2310

sA09Il

452

0 30750 3236

313

0 31070 3209

N- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

1.00775 1.00

1.001.00

1.00737 1.00

1.001.00

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

oCCOCC

CodeAllow.

1410014100211504230042300

1410014100211504230042300

372391526

22182291

09 N+ Max PGR + Max PCold to Ti

t: SSE-SEISMCL GR+P+SSE

313

0 31070 3209

2.44-737 2.44

2.442.44

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

372576

128440574191

1410014100211504230042300

I

L-

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

151

0* O

2.44652 2.44

2.442.44

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

372364

113542124249

1410014100211504230042300

32263254

A09

LF+ Max P

GR + Max PCold to TiSSE-SEISMCGR+P+SSE

151

0 32260 3254

1.00652 1.00

1.001.00

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

372275466

23032323

1410014100211504230042300

N- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

N+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

151

0 32260 3254

151

0 32260 3254

1.00652 1.00

1.001.00

2.44652 2.44

2.442.44

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCoCC

372275466

23032323

372364

1135.42134249

1410014100211504230042300

1410014100211504230042300

Page 124: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

PILCULATION 240046-C-001 ATTACHMENT B PAGE B41I

, WUXSTM1 240046 EQE International'C 0'"0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 27L I- - - -- - -- - -- - -- -- -- ---- - ------ ----- --- --- ---- -- --- ---- ---.- --- - -- -- - -- --- ---

'Point Loadi name combination

A10 F- Max P

|; GR + Max PCold to TiSSE-SEISMC

, - GR+P+SSE

ASME B31.1 (1992) CODE COMPLIANCI(Moments in ft-lb )

Ma Mb Mc Eq.(Sus.) (Occ.) (Exp.) S.I.F no.

…______ - - -- - -- - - - - - -- - -- -- - - -- - -

256

0 33500 3445

256

0 33500 3445

( 3)2.44 (11)

576 2.44 (13)2.44 (12)2.44 (12)

( 3)1.00 (11)

576 1.00 (13)1.00 (12)1.00 (12)

(Stress in psi )Load Code Codetype Stress Allow.

…___ - -- --- _____HOOP 372 14100SUST 502 14100DISP 1003 21150OCC 4374 42300OCC 4499 42300

HOOP. 372 14100SUST 351 14100DISP 411 21150OCC 2391 42300OCC 2460 42300

'-10 F+ Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

887

0 40150 4424

1.001215 1.00

1.001.00

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

372801867

28663158

1410014100211504230042300

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

A13 N- Max PGR + Max PL Cold to TiSSE-SEISMCGR+P+SSE

'A13 N+ Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

441

0 31320 3247

205

0 30780 3139

205

0 30780 3139

1.001512 1.00

1.001.00

1.001578 1.00

1.001.00

2.441578 2.44

2.442.44

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

372483

107922362318

372314

112621972241

372435

274640194099

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

I 13 F- Max PGR + Max PCold to T1

. SSE-SEISMCLGR+P+SSE

101

00

30233047

2.441610 2.44

2.442.44

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

372300

280339483979

1410014100211504230042300

v-I

Page 125: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

, LCULATION 240046-C-001 ATTACHMENT B PAGE B42

,AUXSTM1 240046 EQE InternationalLt '00/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 28--

?oint Loadiame combination

----- -----------

A13 F+ Max PGR + Max P

L Cold to TiSSE-SEISMCGR+P+SSE

"'A14 N- Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

ASME B31.1 (1992) CODE COMPLIANCE(Moments in ft-lb )

Ma Mb Mc Eq. 3(Sus.) (Occ.) (Exp.) S.I.F no. I

…____ ______ ------- -------… ---- -

( 3) 1101 1.00 rll * c

(Stress in psiLoad Codetype Stress ;____ ------ -lOOP 372SUST 240)ISP 1150OCC 2158OCC 2175

1610 1.000 3023 1.000 3047 1.00

' ~,(13)(12)(12)

I

CodeAllow.

1410014100211504230042300

1410014100211504230042300

124

0 30290 3057

1.001621 1.00

1.001.00

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

372256115821622182

1i 4 N+ Max PGR + Max P

I 1 Cold to TiSSE-SEISMCGR+P+SSE

T Max PI, > GR + Max P

Cold to Tif, SSE-SEISMCi GR+P+SSE

124

0 30290 3057

2.441621 2.44

2.442.44

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

372329

282339543992

1410014100211504230042300

227 2.441613 2.44

0 3049 2.440 3096 2.44

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

372464

280939824043

1410014100211504230042300

A14 F- Max P! , GR + Max P

L Cold to TiSSE-SEISMC

i .GR+P+SSE

k

,14 F+ Max PGR + Max PCold to TiL SSE-SEISMCGR+P+SSE

159

0 30430 3072

159

0 30430 3072

2.441587 2.44

2.442.44

1.001587 1.00

1.001.00

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

372375

27623974.4012

372281

113321732193

1410014100211504230042300

1410014100211504230042300

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

833

00

1.001005 1.00

2466 1.002783 1.00

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

372762717

17611987

1410014100211504230042300

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ALCULATION 240046-C-001 ATTACHMENT B PAGE B43

________________________________________________________________________________

;AUXSTM1 240046 EQE InternationalIr '0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 29K1-

ASME B31.1 (1992) CC(Moments in ft-lb )

iPoint Loadi iame combination

.A16 Max P1. GR + Max PL_ Cold to TI

Ma(Sus.)

_______

Mb(Occ.)

_ _ _ _ _ _

Mc(Exp.)

_______

)DE COMPLIANCE(Stress in psi

Eq. Load CodeS.I.Fr no. type Stress i

…__ _ _ _ _ - - - - - - - - - - - - - - -

SSE-SEISMCGR+P+SSE

'I,

AJ17. i;

- Max PGR + Max. PCold to TiSSE-SEISMCGR+P+SSE

819

0 26430 3026

147

0 37500 3827

1.001026 1.00

1.001.00

2.231710 2.23

2.232.23

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

oCCoCC

HOOPSUSTDISP

oCCoCC

372752732

18872160

372343

272544824575

)CodeAllow.

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

122

0 37550 3841

2.231458 2.23

2.232.23

( 3) HOOP(11) SUST(13) DISP(12) OCC(12) OCC

372313

232344894591

KJ7 Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

Al8 N+ Max PLI GR + Max PL Cold to Ti

SSE-SEISMCGR+P+SSE

LA18 F- Max PGR + Max PCold to Ti

L SSE-SEISMCGR+P+SSE

L18 F+ Max PGR + Max PCold to Ti

- SSE-SEISMCGR+P+SSE

108

0 35350 3602

108

0 35350 3602

263

0 33640 3499

263

0 33640 3499

1.001398 1.00

1.001.00

2.441398 2.44

2.442.44

2.441265 2.44

2.442.44

1.001265 1.00

1.001.00

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

372244998

25232571

372308

243446154703

372511

220343934568

372355903

24022498

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

( 3) HOOP(11) SUST(13) DISP(12) OCC(12) OCC

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

Page 127: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

I ALCULATION 240046-C-001 ATTACHMENT 3 PAGE B44

________________________________________________________________________________

AUXSTM1 240046r/130/98 TMI-1 AUX STEAM LINE

EQE InternationalAutoPIPE+4.70 RESULT PAGE 30

I- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Point Loadname combination~____ ----- _---------

ASME B31.1 (1992) CODE COMPLIANCE(Moments in ft-lb ) (Stress in psi

-Ma Mb Mc Eq. Load Code(Sus.) (Occ.) (Exp.) S.I.F no. type Stress J

…__ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ _ _ _ _ _

CodeAllow.______

Al 9L 1

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

N- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

1016

0 28400 3366

851

0 27020 3122

1.00849 1.00

1.001.00

1.00745 1.00

1.001.00

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISPoCcOCC

HOOPSUSTDISP

OCCOCC

372893606

20282403

372775532

19292229

1410014100211504230042300

14100* 14100211504230042300

LA20 N+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

F- Max PLx GR + Max P

Cold to TiSSE-SEISMCGR+P+SSE

A20 F+ Max PGR + Max P

L Cold to TiSSE-SEISMC

851

0 27020 3122

664

0 26200 2973

664

0 26200 2973

475

0 27840 2950

475

0 27840 2950

2.44745 2.44

2.442.44

2.44647 2.44

- 2.44

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISPoCc

2.44 (12) OCC

A

'A21

GR+P+SSE

N- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

1.00647 1.00

1.001.00

1.00525 1.00

1.001.00

2.44525 2.44

2.442.44

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

oCCOCC

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

3721278129735284076

372* 103411273421* 3881

372641462

18712122

37250737519872106

372788914

36353852

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

LA21 N+ Max PGR + Max P

I Cold to TiL SSE-SEISMC~GR+P+SSE

LL

L

Page 128: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

kLCULATION 240046-C-001 ATTACHMENT B PAGE B45

KAUXSTM1 240046 EQE International'0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 31

------------ ----- ---- ---- ---- --- ---- ---- ---- ----------------------

i-oint Loadiame combination

-A21 F- Max P'i GR + Max P

Cold to TiSSE-SEISMC

- GR+P+SSE

ASME B31.1 (1992) CODE COMPLIANCE(Moments in ft-lb )

Ma Mb Mc Eq.(Sus.) (Occ.) (Exp.) S.I.F no.

…__ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - -

439

0 28130 2985

2.44427 2.44

2.442.44

( 3)(11)(13)(12)(12)

(Stress in psi )Load Code Codetype Stress Allow.

…__ ------ ------HOOP 372 14100SUST 741 14100DISP 743 21150OCC 3673 42300OCC 3898 42300

*.22

F+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

439

0 28130 2985

454

0 50390 5208

*

46

0 12910 1325

1.00427 1.00

1.001.00

1.001281 1.00

1.001.00

2.23435 2.23

2.232.23

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

( 3) HOOP(11) SUST(13) DISP(12) OCC(12) OCC

k jegment A end

*** Segment B begin

I k17 Max PL GR + Max P.Cold to T1

I SSE-SEISMCL GR+P+SSE

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

372481305

20082131

372492915

35973718

372222693

15431584

372198

422985

1010

210884

107912600626650

210709

52871513415594

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

.1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

p301 Max PGR + Max PCold to T1

- SSE-SEISMC| GR+P+SSELB02 Max P

GR + Max P1 Cold to'T1

SSE-SEISMC- GR+P+SSE

403 N- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

29

0 9200 943

23

0 7710 791

18

0 4490 463

2.00295 2.00

2.002.00

2 2.10240 .2.10

2.102.10

2.10118 2.10

2.102.10

( 3) HOOP(11) SUST(13) DISP(12) OCC(12) OCC

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

Page 129: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

ALCULATION 240046-C-001 ATTACHMENT B PAGE B46

AUXSTM1 240046 EQE Internationalt 30/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 32

-- --,_ _ _ _ - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Point Load, name combination

B03 N+ Max P| GR + Max PL Cold to T1

SSE-SEISMC! GR+P+SSE

ASME B31.1 (1992) CODE COMPLIANCE(Moments in ft-lb )

Ma Mb Mc Eq. ](Sus.) (Occ.) (Exp.) S.I.F no. I

…__ _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - - - - - - -- - -

(Stress in psi )Loadtype

18

0 4490 463

2.10118 2.10

2.102.10

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

CodeStress______

210709

528715134-15594

CodeAllow.14100_

1410014100211504230042300

! B03

F- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

F+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

18

0 3910 405

18

0 3910 405

2.10100 2.10

2.102.10

2.10100 2.10

2.102.10

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

oCCOCC

HOOPSUSTDISP

oCCOCC

210694

44741319313638.

210694

44741319313638

1410014100211504230042300

1410014100211504230042300

L -Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

5 B04

L:

LB0 4

N+ Max PGR + Max PCold to T1iSSE-SEISMCGR+P+SSE

F- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

37

0 2450 274

37

0 2450 274

42

0 1910 222

42

0 1910 222

2.1072 2.10

2.102.10

2.1072 2.10

2.102.10

2.1063 2.10

2.102.10

2.1063 2.10

2.102.10

( 3) HOOP(11) SUST(13) DISP(12) OCC(12) OCC

( 3) HOOP'(11) SUST(13) DISP(12) OCC(12) OCC

( 3) HOOP(11) SUST(13) DISP(12) OCC(12) OCC

2101353322182559250

2101353322182559250

2101508281464387477

2101508281464387477

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

I

LB04 F+ Max PGR + Max PCold to Ti

II SSE-SEISMCL- - GR+P+SSE

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

Page 130: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

.ALCULATION 240046-C-001 ATTACHMENT B PAGE B47

,AUXSTM1 240046 EQE International'30/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 33K - -------------------------------

L~ ASME B31.1 (1992) CODE COMPLIANCE(Moments in ft-lb )

I Point Load Ma Mb Mc Eq. :_name combination (Sus.) (Occ.) (Exp.) S.I.F no. 1

B05 Max P ( 3) IGR + Max P 33 2.10 (11) '

L. Cold to Ti 8A ' in ,i i

(Stress in psiLoad Codetype Stress A

HOOP 210SUST 1220DISP 3987OCC 6343OCC 7265

Codehlow.

1410014100211504230042300

SSE-SEISMC

L GR+P+SSE

*** Segment B end ***

' *** Segment C begin ***

0 1880 215

. 1w

2.102.10

1J2 I

(12)(12)

LC17

Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

32

0 880 119

36

2.3040 2.30

2.302.30

2.3031 2.30

2.302.30

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

1239405

156752571234911

12310521122732285532648

1410014100211504230042300

1410014100211504230042300

00

78* 111

+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

20

00

4967

lC02

II

10

0 330 43

15

0 340 47

2.3023 2.30

2.302.30

2.3011 2.30

2.302.30

2.3012 2.30

2.302.30

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

12359549001

1448219776

123313943799738

12570

123445248839968

13709

1410014100211504230042300

14100-14100211504230042300

1410014100211504230042300

5 IJ

Max PGR + Max PCold to TISSE-SEISMCGR+P+SSE

21 1.00* 17 1.00

1.001.00

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

oCCOCC

1233708287464659529

1410014100211504230042300

00

3856

Page 131: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

PILCULATION 240046-C-001 ATTACHMENT B PAGE B48

________________________________________________________________________________

! UXSTM1 240046 EQE International,' '0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 34

ILASME, B31.1 (1992) CODE COMPLITANCEr

1?oint LoadIlame combination

_ _ _ _ _ _ - - - - - - - - - - -

(Moments in ft-lb ) (StriMa Mb Mc Eq. Load

(Sus.) (0cc.) (Exp.) S.I.F no. type…__ _ _ _ _,_ _ _ _ _ _ _ - -- - - -- - - - - - - - - -- - - - --

C04

C04

0

L 0 4

N- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

N+ Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

F- Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

00

3047

21

21

00

2.3013 2.30

2.302.30

2.3013 2.30

2.302.30

2.3012 2.30

2.302.30

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

3047

ess in psiCode

Stress______

1236166.5168891113863

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

123616651688911

13863

12354134621787412216

i )Code

Allow.14100_

1410014100211504230042300

1410014100.211504230042300

1410014100211504230042300

18

00

2742

'+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

C05 N- Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

tO5 N+ Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

18

00

2742

14

00

1425

2.3012 2.30

2.302.30

2.306 2.30

2.302.30

2.306 2.30

2.302.30

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

oCCOCC

HOOPSUSTDISP

OCCOCC

123541346217874

12216

1234155239842307399

1234155239842307399

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

14

00

1425

F- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

11

0 130 21

2.305 2.30

2.302.30

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

1233428209439076264

1410014100211504230042300

Page 132: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

,tALCULATION 240046-C-001 ATTACHMENT B PAGE B49

eAUXSTM1 240046P '30/98 TMI-1 AUX STEAM LINE

EQE InternationalAutoPIPE+4.70 RESULT PAGE 35

r…_________________ _-

-Point LoadIname combination

C05 F+ Max PGR + Max PL Cold to T1SSE-SEISMCL GR+P+SSE

C06 N- Max PGR + Max P

I ~ Cold to T1L SSE-SEISMC

GR+P+SSE

ASME B31.1 (1992) CODE COMPLIANCE(Moments in ft-lb )

Ma Mb Mc Eq. I(Sus.) (Occ.) (Exp.) S.I.F no. I

…______ ------- ------- ------- ---- -

11

00

1321

13

0 180 28

13

2.305 2.30

2.302.30

2.306 2.30

2.302.30

2.306 2.30

2.302.30

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

I

(Stress in psiLoad Codetype Stress____ ------

HOOP 123SUST 3428DISP 2094OCC 3907OCC 6264

i

LC06 N+

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

1233771228452418314

1233771228452418314

)Code

Allow.

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

00

1828

i F-

LCO- F

C06 F+

Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

10

0 190 28

10

2.307 2.30

2.302.30

2.307 2.30

2.302.30

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

1232983281255998086

1232983281255998086

1410014100211504230042300

1410014100211504230042300

00

1928

-C07 N- Max PGR + Max PCold to Ti

* SSE-SEISMCGR+P+SSE

' z07 N+ Max PGR + Max PCold to T1

|i SSE-SEISMCLGR+P+SSE

1

00

1920

2.309 2.30

2.302.30

2.309 2.30

2.302.30

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

123372

356456465862

123372

356456465862

1410014100211504230042300

1410014100211504230042300

1

00

1920

Page 133: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

ELCULATION 240046-C-001 ATTACHMENT E PAGE B50

, UXSTM1 240046 EQE InternationalL' "0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 36L r------------------------------------------------------------------------

ASME B31.1 11992) CODE COMPLITANCE(Moments in ft-lb )

?oint Load Ma Mb Mc Eq. ]Iame combination (Sus.) (Occ.) (Exp.) S.I.F no. I

______ ----------- --------------- ------- ------- ---- -

C07 F- Max P ( 3) 1L GR + Max P 3 2.30 (11) 'Co-l d to T1l a i an r1w %

(Stress in psi )Load Code Codetype Stress Allow.____ ------ ------

ROOPSUSTDISP

OCCOCC

SSE-SEISMCGR+P+SSE

00L-

C07

L

1821

F+ Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

2.30

2.302.30

2.309 2.30

2.302.30

( 1 2

(12)(12)

A

123923

352552606031

123923

352552606031

1410014100211504230042300

1410014100211504230042300

3( 3) HOOP(11) SUST(13) DISP(12) OCC(12) OCC

00

1821

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

Max PGR + Max PCold to TiSS&-SEISMCGR+P+SSE

6

00

2127

6

00

2632

8

2.3013 2.30

2.302.30

2.3016 2.30

2.302.30

2.3022 2.30

2.302.30

2.3027 2.30

2.302.30

1.0027 1.00

1.001.00

( 3)(11)(13)(12)(12)

( 3). (11)(13)(12)(12)

( 3)(11)(13)(12)(12)

( 3)'(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

oCCOCC

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCoCC

1231774517861587781

1231940610875219338

12323998716

11470137-74

132364855739028

12554

1322011240442936159

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

00

3947L

.Cie23

00

5881

22

00

4868

Ir** Segment C end

, Segment G begin

L,~

Page 134: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

C LCULATION 240046-C-001 ATTACHMENT B PAGE B51

_____________-__________________________________________________________________

.UXSTM1 240046 EQE InternationalL/ 1/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 37_ - I , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

L oint LoadLame combination

.,17 Max PII GR + Max P

Cold to T1SSE-SEISMC

I GR+P+SSE

ASME B31.1 (1992) CODE COMPLIANCE(Moments in ft-lb )

Ma Mb Mc Eq. ](Sus.) (Occ.) (Exp.) S.I.F no. 1

…______ ------- ------- ------- ---- -

(Stress in psi )Loadtype____

42

00

5998

2.3032 2.30

2.302.30

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

Code CodeStress Allow.

123___ 14100-

123 1410012278 1410012692 2115017246 4230028623 42300

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

15 2.3011 2.30

2.302.30

( 3)(11)(13)(12)(12)

HOOP*SUSTDISP

OCCOCC

123443843859060

13152

1410014100211504230042300

00

3145

L18 Max PGR + Max PCold to Ti

I1 SSE-SEISMCL- GR+P+SSE

28

00

18

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

123475330187377

11627

14100- 141002115042300

423004368

i egment G end ***

*** Segment H begin ***

L10 Max PGR + Max PCold to TiSSE-SEISMC

L GR+P+SSE

01 N- Max PL GR + Max P

Cold to TiSSE-SEISMCL GR+P+SSE

H01 N+ Max PI GR + Max PL Cold to T1

SSE-SEISMCj GR+P+SSE

..

'D -,->e~l~( 3) HOOP

r 1 09 11)SUST27 1.00 (13)DISP

1.00 (12) OCC1.00 (12) OCC

1162.7 (z. I)S zd4,07ts

Z*41'7 , O. sf & I.4?W132 14100

2011 141002404 211504293 423006159 42300

22

00

21

00

4868

3958

2.1026 2.10

2.102.10

2.1026 2.10

2.102.10

( 3) HOOP(11) SUST(13) DISP(12) OCC(12) OCC

1323037498755308305

1323037498755308305

1410014100211504230042300

1410014100211504230042300

21

0 390 58

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

'101 F- Max PGR + Max P

I Cold to T1SSE-SEISMC

I > GR+P+SSE

I-

20

00

3857

2.1025 2.10

2.102.10

( 3) HOOP(11) SUST(13) DISP(12) OCC(12) OCC

1322928481154398143

1410014100211504230042300

Page 135: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

* :ALCULATION 240046-C-001 ATTACHMENT.B PAGE B52

AUXSTM1 240046 EQE International_' 30/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 38

L -.<

I Point LoadL-name combination

: HO1 F+ Max PI GR + Max P

Cold to TiSSE-SEISMC

| GR+P+SSE

* ASME B31.1 (1992) CODE COMPLIANCE(Moments in ft-lb )

Ma Mb Mc Eq.(Sus.) (Occ.) (Exp.) S.I.F no.

…______ ------- ------- ------- ----

20

00

3857

2.1025 2.10

2.102.10

( 3)(11)(13)(12)(12)

(Stress in psi )Load Code Codetype Stress Allow.

…___ -- --- - ---- --HOOP 132 14100SUST 2928 14100DISP 4811 21150OCC 5439 42300OCC 8143 42300

H02 N- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

7 2.109 2.10

2.102.10

( 3) HOOP(11) SUST(13) DISP(12) OCC(12) OCC

1321036163938924771

1410014100211504230042300

00

2734

-H02 N+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

7

00

2734

2.109 2.10

2.102.10

( 3) HOOP(11) SUST(13) DISP(12) OCC(12) OCC

1321036163938924771

1410014100211504230042300

_ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

6

0 270 32

2.108 2.10

2.102.10

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

132972

148238374493

1410014100211504230042300

IH02 F+ Max PL - GR + Max P

Cold to TiSSE-SEISMC

| GR+P+SSE

6

00

2732

H03 N- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

4

2.108 2.10

2.102.10

2.108 2.10

2.102.10

2.108 2.10

2.102.10

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

132972

148238374493

132694

155941274714

132694

155941274714

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

00

2933

N+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

4

00

2933

Page 136: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

t LCULATION 240046-C-001 ATTACHMENT B- PAGE B53

________________________________________________________________________________

IkUXSTM1 240046 EQE International'0/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 39

--- - - - - - - - - - - - - - - - - - - - - - - -__

|oint_L3ame

______

'103 F-I '

, _t

Loadcombination

JuAmr, Z).)1.1 k z C COLIk uukeLANCE(Moments in ft-lb )

Ma Mb Mc Eq. 3(Sus.) (Occ.) (Exp.) S.I.F no. I

…______ ------- ------- ------- ---- -Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

4

00

H03

i :

2932

F+ Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

2.108 2.10

2.102.10

2.108 2.10

2.102.10

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

I

I

(Stress in psiLoad Codetype Stress

iOOP 1323UST 579)ISP 1424OCC 4102OCC 4498

4

0 290 32

CodeAPllow.

1410014100211504230042300

1410014100211504230042300

HOOPSUSTDISP

OCCOCC

132579142441024498

L.-04 N- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

9

00

2734

k 1+ Max PGR + Max PCold to T1SSE-SEISMC

L GR+P+SSE

9

00

2734

2w04

:i~

H04t.VF- Max P

GR + Max PCold to TiSSE-SEISMCGR+P+SSE

F+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

13

( 3)2.10 (11)

6 2.10 (13)2.10 (12)2.10 (12)

( 3)2.10 (11)

6 2.10 (13)2.10 (12)2.10 (12)

( 3)2.10 (11)

10 2.10 (13)2.10 (12)2.10 (12)

( 3)2.10 (11)

10 2.10 (13)2.10 (12)2.10 (12)

3)1.00 (11)

19 1.00 (13)1.00 (12)1.00 (12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP- OCC

OCC

HOOPSUSTDISP

oCCoCC

1321399115138504842

1321399115138504842

1321869190338165409

1321869190338165224

1321946167725974202

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

14100141002115042300.42300

00

13

00

2738

2737

21

00

2947

Page 137: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

.LCULATION 240046-C-001 ATTACHMENT B PAGE B54

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

I ;tUXSTM1 2400461 )''10/98 TMI-1 AUX STEAM LINE- I_>--------------------------

EQE InternationalAutoPIPE+4.70 RESULT PAGE 40

…________________________________________________

I- ASME B31.1 (1992) CODE COMPLIANCE(Moments in ft-lb )

! ?oint Load Ma Mb Mc Eq. :Laame combination (Sus.) (Occ.) (Exp.) S.I.F no. I

…____ ----------- ------- ------- ------- ------- ---- -H06 Max P

I 1 ~GR + Max PL- Cold to T1

SSE-SEISMCGR+P+SSE

*** Segment H end

32

00

1.0011 1.00

1.001.00

( 3)(11)(13)(12)(12)

IIII

(Stress in psiLoad Codetype Stress____ ------

HOOP 132SUST 2913DISP 959OCC 5865OCC 8482

CodeAllow.

.1410014100211504230042300

6594

i;:** Segment I begin ***

B05I

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

12

0 1760 185

13

0 2030 214

2.1080 2.10

2.102.10

2.1076 2.10

2.102.10

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

1321811151722504626387

1321907

144752881730447

1410014100211504230042300

1410014100211504230042300

[:02 N- Max PGR + Max P

, I Cold to TiIi SSE-SEISMC%. GR+P+SSE

At02 N+ Max P

L GR + Max PCold to T1

;1 SSE-SEISMCI GR+P+SSE

16

0 2180 233

16

0 2170 232

2.1075 2.10

2.102.10

2.1075 2.10

2.102.10

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

1322285

142903096733093

1322285

142903084632966

1410014100211504230042300

1410014100211504230042300

I02 F- Max Pj' GR + Max Pj- Cold to Ti

SSE-SEISMC

1 GR+P+SSE

9I02 F+ Max P-GR + Max P

PI Cold to T1L- SSE-SEISMC

GR+P+SSEK,

14

0 1900 204

14

0 1900 204

2.1067 2.10

2.102.10

2.1067 2.10

2.102.10

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

1322064

127582706229000

1322064127582706229000

1410014100211504230042300

1410014100211504230042300

Page 138: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

ALCULATION 240046-C-001 ATTACHMENT B PAGE BSS

AUXSTM1 240046r' '0/98 TMI-1 AUX STEAM LINEt r---------------------------------___________

EQE InternationalAutoPIPE+4.70 RESULT PAGE 41

…_____________________________

PointL -ame

Loadcombination (S

ASME B31.1 (1992) CODE COMPLIANCE(Moments in ft-lb )

Ma Mb Mc Eq. ];us.) (Occ.) (Exp.) S.I.F no. I

…___ ------- ------- ------- ---- -

(Stress in psi )Loadtype

103 N- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

5

00

8893

45

( 3). HOOP2.10 (11) SUST2.10 (13) DISP2.10 (12) OCC2.10 (12) OCC

N+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

5 2.1045 2.10

2.102.10

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

00

-8893

"Zo3 F- Max PGR + Max PCold to T1SSE-SEISMCGR+P+SSE

j + Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

!T04 N- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

4

00

7477

4

0 740 77

7

0 1040 110

2.1041 2.10

2.102.10

2.1041 2.10

2.102.10

2.1031 2.10

2.102.10

( 3)(11)(13)(12)(12)

( 3)(11)(13)(12)(12)

3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

oCCOCC

CodeStress______

132767

84661248113174

132767

84661248113174

132587

77761049910999

132587

77761049910999

132101859361475715659

1410014100211504230042300

1410014100211504230042300

1410014100211504230042300

CodeAllow.14100_

1410014100211504230042300

1410014100211504230042300

Lo04

N+ Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

F- Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

7

0 1040 110

8

0 1290 137

2.1031 2.10

2.102.10

2.1034 2.10

2.10

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

HOOPSUSTDISP

OCC

13210185936

1475715659

13212476541

1834019489

1410014100211504230042300

1410014100211504230042300

( 3)(11)(13)(12)

2.10 (12) OCC

Page 139: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

, kLCULATION 240046-C-001 ATTACHMENT B PAGE B56

________________________________________________________________________________

,XSTM1 240046 EQE International1'30/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 42

t y__- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -_

PointIiame

______

104 F+

I05

Loadcombination___________

Max PGR + Max PCold to T1SSE-SE ISMCGR+P+SSE

Max PGR + Max PCold to TiSSE-SEISMCGR+P+SSE

ASME B31.1 (1992) CODE COMPLIANCE(Moments in ft-lb ) (Stress in psi

Ma Mb Mc Eq. Load Code(Sus.) (Occ.) (Exp.) S.I.F no. type Stress J

_______ ------- ------- ------- ---- ---- ------ -

( 3) HOOP 1328 2.10 (11) SUST 1247

34 2.10 (13) DISP 65410 129 2.10 (12) OCC 183400 137 2.10 (12) OCC 19489

CodeAllow.

1410014100211504230042300

1410014100211504230042300

13 1.0066 1.00

1.001.00

( 3)(11)(13)(12)(12)

HOOPSUSTDISP

OCCOCC

1321266595355146702.

00

6174

1

L.*** Segment I end

Page 140: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

( LCULATION 240046-C-001_k

ATTACHMENT B PAGE B57

________________________________________________________________________________

!.UXSTM1 240046 EQE International_ii'10/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 43

S Y S T E M S U M M A R Y

aximum displacements (in)I-._______________________

Maximum X :Maximum Y :Maximum Z :Max. total:

"Maximum rotations (deg)_______________________

L- ~ - Maximum X :Maximum Y :Maximum Z :

I Max. total:

1.307-0.2503.9384.149

0.7390.8650.6771.134

PointPointPointPoint

PointPointPointPoint

: All: C04 N: A13 N: All

: C10: C05 N:I03 F: C05 N

Load Comb.: SSE-SEISMCLoad Comb.: T1Load Comb.: SSE-SEISMCLoad Comb.: SSE-SEISMC

Load Comb.: SSE-SEISMCLoad Comb.: SSE-SEISMCLoad Comb.: SSE-SEISMCLoad Comb.: SSE-SEISMC

L jumrestraint forces (lb)_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Maximum X :Maximum Y :Maximum Z :Max. total:

454-707442707

Maximum restraint moments (ft-lb)

I - - - --- --- --- - ---------------- ____

Point : ADOPoint : A19Point : AOOPoint : A19

Point : A22Point : AOOPoint : A22Point : AOO

Load Comb.:Load Comb.:Load Comb.:Load Comb.:

Load Comb.:Load Comb.:Load Comb.,:Load Comb.:

SSE-SEISMCGRSSE-SEISMCGR

SSE-SEISMCSSE-SEISMCSSE-SEISMCSSE-SEISMC

Maximum X :Maximum Y :Maximum Z :Max. total:

9307277639

7312

L-

Page 141: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

ALCULATION 240046-C-001 ATTACHMENT B PAGE B58

________________-_______________________________________________________________

1,AUXSTM1 240046 EQE International; '30/98 TMI-1 AUX STEAM LINE AutoPIPE+4.70 RESULT PAGE 44

S Y S T E M S U M M A R Y

Maximum sustained stress

PointStress psiAllowable psiRatioLoad combination

: C17: 12278: 14100: 0.87: GR + Max P

Maximum displacement stress

PointStress psiAllowable psiRatioLoad combination-:

B0515675211500.74Cold to T1

Maximum occasional stress

PointStress psiAllowable psiRatioLoad combination

: B05: 34911: 42300: 0.83: GR+P+SSE

Maximum hoop stress

PointStress psiAllowable psiRatioLoad combination

: AQO: 372: 14100: 0.03: Max P

!-.

Page 142: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

ikLCULATION 240046-C-001 ATTACHMENT B PAGE B59

_________-______________________________________________________________________

WUXSTM1 2400465'',X 0/98 TMI-1 AUX STEAM LINE

tK __ …

EQE InternationalAutoPIPE+4.70 RESULT PAGE 45

._______________________________________________-

S Y S T E M SUMMARY

Maximum sustained stress ratio

PointStress psiAllowable psiRatioLoad combination

: C17: 12278: 14100: 0.87: GR + Max P

Maximum displacement stress ratio

PointStress psiAllowable psiRatioLoad combination :

B0515675211500.74Cold to T1

Maximum occasional stress ratioIL-,--� Point

Stress psiAllowable psiRatioLoad combination :

B0534911423000.83GR+P+SSE

Maximum hoop stress ratio

PointStress psiAllowable psiRatioLoad combination

: AOO: 372: 14100: 0.03: Max P

l1 * * * The system satisfies ASME B31.1 code requirements * * ** * ** for the selected options * * *

Page 143: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

-"I. / - t- . ( -~ [-;

a

UM

: "I,

IX,i

Frequency (Hz)

\ILegend:

Envelope of LB, BEUB Spectra1.5 x SQUG BoundingSpectrum

C'7

v

Notes:

Enveloped In-Structure ResponsLB & UB Broadened 10%BE Broadened 15%5.0 % Spectral DampingAccelerations in gos

_ _ _- _-

Page 144: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

.__ II - I

Ii

(I

I tI

I 2 2I0

0

C)i

l

.o

4.II0

NI

IFrequency (Hz)

.

I

Ii|- -.?

1 ? i ! E

%S1

Legend:

Envelope of LB, BEUB Spectra .

1.5 x SQUG BoundingSpectrum

, . .

Notes:

Enveloped In-StructureLB & UB Broadened 10%BE Broadened 15%5.0 % Spectral DampingAccelerations in g's

_ _- -_-

a _ I

Page 145: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

A4 77Adr ",I; J7 <,*7 r> )

1.

L

Li

L

L

L

LI

L

CHECKING CRITERIA CHECKLIST

Client (ZPd/ Project A In P/F^S

Job No. 2 4 o4 Calc. No. 0 /

Revision No.

Criteria Yes No N/A Comment No.

1. Originator followed defined procedures.

2. Title, purpose and function of the workchecked are adequately described.

3. Work method clearly stated and appropriate.

4. Assumptions identified. Open items flaggedfor subsequent verification where necessary..

5. Technical bases and references current,correctly selected, and incorporated.

6. Technical input properly selected andadequately identified. Any specific input tobe excluded are adequately identified.

7. Applicable codes, standards and regulatoryrequirements identified and properly used.

8. Analytical steps can be verified withoutrecourse to originator.

9. Each page of the work identified and trace-able to originator, date and job or equivalent 3control number.

1 O.All markings legible and identifiable.

Page bi of 3

PD6)"2KLW

Page 146: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

A- 7A'14A>,J-y7 >)

4-

4.-

I.

L

i

k--

l'1

LI

CHECKING CRITERIA CHECKLIST

_ __

Client

Job No.

61-11) PUIA./

2-4V O 4 &Project

Calc. No.

Revision No.

Avy--572*m P Pl

A3�A, 4 P, Pdd,

t0

0

Criteria Yes No N/A Comment No.

11.Work clearly references any final supportingcomputer runs.

1 2. Final computer runs include input listing andoutput.

13.Final computer runs contain unique numberidentifier.

14.Results consistent with inputs, technicalprocedures, and other project criteria.

1 5.Results are reasonable.

1 6.Revisions are clearly documented. _

1 7.Technical interface requirements in theProject Plan have been satisfied.

1 8.AII documentation available to checker.

19.Computer program version identified.

20.Computer program version certified andapplication valid.

I.

Checked by: IA k7 A.

4 30-fmDate:

' #4-f6Page P2- of .3

#"MWe2Lw

Page 147: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

A AriA . Pi>-I-_~~ 7 , *A frg-c 11R.

CHECKING CRITERIA CHECKLIST

Client 67pL1 Project 57-CAM P,16

Job No. ___ _ _ _ _ _ Calc. No.

Revision No.

CHECKING CRITERIA CHECKLIST

Comment No. Comment Resolved by:

Date:

l_ . /h 4-?o-

___ A/rt ____v ? 1;-

.. I

Page t3 of 3'

Page 148: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

N4�

II

ii Ii

240046-R-001Revision 1June 5, 1998Page E I

_

LNJI I

L-LII

ATTACHMENT E:

WALKDOWN PHOTOGRAPHS

I.

L

Page 149: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

240046-R-001Revision 0April 30, 1998Page E 2

Photo 1: Auxiliary Steam Piping from header. Turbine Bldg. El. 355'.

Photo 2: Auxiliary Steam Piping from header. Turbine Bldg. El. 355'.

III...

Page 150: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

240046-R-001Revision 0April 30, 1998Page E 3

Photo 3: Auxiliary Steam piping at Control Building Penetration #1 847. ControlBldg. El. 355'.

Photo 4: Auxiliary Steam Piping support no. MK-AS-1 29. Control Bldg. El. 355'.This support is located approx. 5'-0 south of penetration 1847. Thepenetration will limit E-W (lateral) deflection of the pipe. The short rodhanger is judged acceptable based on deflection being limited by thepenetration.

Page 151: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

240046-R-001Revision 0April 30,1998Page E 4

Photo 5: Auxiliary Steam Piping support no. MK-AS-1 30. This photo is lookingup at rod penetrating cutout in grating. Above grating is flexible plateand carpeting for an office area. The SRT judged the rod will not bedamaged by movement of piping and the resulting interaction with theplate and carpet.

Photo 6: Auxiliary Steam Piping in wall penetration near support no. MK-AS-134.

L

Page 152: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

240046-R-001Revision 0April 30, 1998Page E 5

Photo 7: Auxiliary SteamPiping Truck Bay-Fuel Building pipepenetration andsupport no. MK-AS-1 35.

Photo 8: 2" branch line off 85 diameter Auxiliary Steam Pipe header in theTruck Bay.

Page 153: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

240046-R-001Revision 0April 30, 1998Page E 6

Photo 9: Anchor support no. MK-AS-1 55 for the Auxiliary Steam Piping in theTruck Say.

L

Photo 10: Typical wall mounted U-bolt support for the 2 diameter AuxiliarySteam Piping going to the Decontamination Pit.

Page 154: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

240046-R-001Revision 0April 30, 1998Page E 7

Photo 1 1: Auxiliary Steam Piping support no. MK-AS-1 42.

Photo 1 2: Auxiliary Steam Piping support no. MK-AS-1 46.

Page 155: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

240046-R-001Revision 0April 30, 1998Page E 8

Photo 13: Auxiliary Steam Piping support no. MK-AS-147.

Photo 14: Looking east at steam trap AS-ST-31.

Page 156: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

240046-R-001Revision 0April 30, 1998Page E 9

Photo 15: Wall mounted support near steam trap AS-ST-31. Calculations showsupport is acceptable.

Photo 16: Close-up of wall mounted support near steam trap AS-ST-31.

Page 157: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

240046-R-001Revision 0April 30, 1998Page E 10LL

L

LLLLI>

Photo 17: 1" diameter branch piping from valve AS-V-102 running to decant andslurry pump and make up tank room.

Photo 1 8: Auxiliary Steam Condensate Return piping.; \_-/8

Page 158: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

240046-R-001Revision 0April 30, 1998Page E 11

i I1

Photo 19: Auxiliary Steam Conde Lte Return piping.

I

Photo 20: 1 " diameter condensate return to condensate return tank/pumps AS-P2A/B.

V

Page 159: Report No. 240046-R-001, 'Seismic Verification Review of Auxiliary ... · EQE International has performed a seismic verification review of the Three Mile Island Unit 1 auxiliary steam

240046-R-001Revision 0April 30, 1998Page E 12

Photo 21: 1 diameter condensate return to condensate return tank/pumps AS-P2A/B.

LL.


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