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Q1 Record _22 '89 0228 01 8 . .- y , ,, _ m ,0 , . . . . . . . . -- . - t ~ _Ve TENNESSEE VALLEY AUTHORITY' g __ i Va w Division of Nuclear ens,ineering < \ % |S't; _ ,/ j i hka10$37 _ z - DESIGN CRITERIA f ~ - 590'89 0222 007 . NO._BFN-50-C-7302 . . __ BROWNS FERRY NUCLEAR PLANT . TITLE: _ OPERABILITY CRITERIA FOR EVALUATION OF LOWER DRYWELL ACCESS PLATFORMS I (SSUE DATE: JULY 19, 1988 . UNLON%~.04_g._ . . g Copy < - . 4= \ REVISION RO R1 R2 R3 R4 RS _ i i D ATE 7-19-88 gyg PREPARED R. H. /s[.e du-,,eY 'EIN Hollinesworth CHECXED R'Gaines L -. |$ N'"'' | | | gf, qi,,,e ., REVIEWED J a, 6.L. D w o j | | Rupert % gureg | | | APPROVED J- K- | ,tr#co,mg | | | McCall sellk'Nebu I L | | t 8903200342 890315 ( PDR ADOCK 0500 9 p g, - ! [. _ . _ ! L _ _ _ _ --__
Transcript
Page 1: UNLON%~.04 g. g

Q1 Record_22 '89 0228 01 8

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y , ,, _ m ,0, . . . . . . . . --

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~ _Ve TENNESSEE VALLEY AUTHORITY'g - __ i

Va w Division of Nuclear ens,ineering<

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hka10$37_ z

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DESIGN CRITERIAf

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590'89 0222 007.

NO._BFN-50-C-7302.

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__ BROWNS FERRY NUCLEAR PLANT

.

TITLE: _OPERABILITY CRITERIA FOR EVALUATION OF

LOWER DRYWELL ACCESS PLATFORMS.

I

(SSUE DATE: JULY 19, 1988.

UNLON%~.04_g._.

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gCopy<-

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REVISION RO R1 R2 R3 R4 RS_

i iD ATE 7-19-88 gygPREPARED R. H.

/s[.e du-,,eY 'EINHollinesworthCHECXED R'Gaines

L -.

|$ N'"'' | | |gf, qi,,,e .,

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REVIEWED J a, 6.L. D w o j| |Rupert % gureg| |

| APPROVED J- K- | ,tr#co,mg| | |McCall sellk'Nebu I L | |

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8903200342 890315 (PDR ADOCK 0500 9p g,

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7302.. '

GABILITY CRITERIA FOR EVALUATION OF REVISION. LO GITER DRWELL ACCESS PLATFORMS

BFN-50-C-7302 "^i 30pf 0 Val /,

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DESCRIPTION OF REVISION' App ved

. R3 vision to . incorporate DIM BFN-50-C-7302-1, reviseTable 3.2.1 R I A

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* i $PERABILITY CRITERIA FOR EVALUATION.q,

ROF LOWER.DRYWELL^ ACCESS PLATFORMS |,.

BFN-50-C-7302ap. -

.iTABLE OF CONTENTS:m

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F 1.0INTRODUCTION .........................'...............oi

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1.1.. Description ........._.......................... t

j 11.2 Pu rp o s e 1. . . . . . . . . . . . ., , . " -:: '1.3 Scope............~...;.......................... 11

.......................... 1-..

2.0, DESIGN' SPECIFICATIONS '

.............................. 1,

3.0LOADS AND LOADING COMBINATIONS ..................... 2

3.1 _ Loading' Definitions ........................... '\ 23.2 Loading Combinations and-Allowable Stresses ...\?5

-3

4.0DESIGN AND ANALYSIS PROCEDURES ..................... 5

5.0REFERENCES .. ............'.........................-Y

' .

5,

-Figure 3.1 Combination'of Dyn'amic' Reactions from'

'

Attached' Systems ........................ f 6. !

i

-TABLES:1

8 .. '

' Table 3.2.1 ' Loading Combinations'and1 Allowable Stresses7 *

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Table:3.2.2 Loading Combinations For. Uplift' Evaluations 8

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' OPERABILITY CRITERIA FOR EVALUATION-

OF LOWER DRYWELL ACCESS PLATFORMSBFN-50-C-7302

1.0 INTROD'UCTION

1.1 Description

The lower drywell access platforms include two main platforms, oneat elevation 584 feet 11 inches, and one at elevation 563 feet 2inches. The flooring is standard grating, with 1-1/2-inch by 3/16-inch load bars. The grating and support steel extend from thereactor pedestal to the drywell shell at elevation 563 feet 2 inchesand from the sacrificial shield wall to the drywell shell at

- elevation 584 feet 11 inches.

The platforms are supported by 24-inch-deep, wide-flange beamsradiating from the reactor pedestal and sacrificial shield wall tothe drywell shell. The radial support beams for elevation 584 feet11 inches are field-welded to header beams in the sacrificial shieldwall. The radial support beams for elevation 563 feet 2 inches arefield-bolted to embedded plates in the outside face of the reactorpedestal. All radial beams are supported by beam seats welded tothe drywell shell. Lubrite pads under the radial beams allowdrywell shell expansion. Shear bars welded to the bottom flange ofthe radial beams on both sides of the beam seat prevent lateralmovement of the beams. Intermediate grating support beams at 6 feet6 inches maximum spacing are framed between the radial beams.Additional support beams are framed between both the radial andgrating support beams for equipmer.t. HVAC, cable tray, and pipingsystem attachments. For remainder of drywell platforms, seeBFN-50-C-7100. Attachment G.

1.2 Purpose

.

The purpose of these criteria is to establish the requirements foroperability evaluation of the lower drywell access platforms..

1.3 Scope

1.3.1 The requirements of this document shall apply to the lowerplatform structural steel inside the drywell at elevation 584 feet11 inches and elevation 563 feet 2 inches as denoted inreference 5.2.

2.0 DESICN SPECIFICATIONS-

For this structural design or evaluation. AISC specifications(reference 5.1) shall be used. ,

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. Op'ERABILITY CRITERIA FOR EVALUATION ,.

f

OF LOWER DRYWELL ACCESS PLATFORMS |BFN-50-C-7302 )3.0 -LOADS'AND LOADING COMBINATIONS

3.1 Loading Definitionst

3.1.1 D - Deadload,including structural steel, permanent equipment, andattached systems, e.g., piping, HVAC, cable trays, etc., shall be

)a minimum of 40 psf.|3.1.2 L

o - Outage and maintenance loads, including any moveable I

equipment loads and other loads which vary with intensity and !

occurrence during an outage, i.e., these loads shall not be 1.

present while the plant is operating. An L of 100 psf applied!

to the loadable open arear shall be evaluated as a baseline outageo

and maintenance live load for the initial analysis using thesecriteria.As concentrated live loads due to outage or maintenance

procedures are identified, these loads shall be evaluated against .

If the results of the concentrated loads fthe baseline case.exceed the baseline case, '

per these criteria. the concentrated loads must be evaluated !

!3.1.3E - Loads due to effects of OBE on structural steel and permanentfloor-mounted equipment. This excludes support loads from iattached piping. HVAC ducts, and cable trays (these loads are i

defined in section 3.1.9).!

3.1.4E' - Loads due to effects of DBE on structural steel and permanentfloor-mounted equipment. This excludes support loads fromattached piping. HVAC ducts, and cable trays (these loads aredefined in section 3.1.9).

<

3.1 5 Y i

r - Equivalent static load on the structure generated by thepipe whip reaction from pipe rupture restraints attached to the v

drywell steel..

The application of pipe rupture loads only at those locationswhere mitigation exists is consistent with the baseline approachto pipe rupture design inside the drywell. Only those locations j

where GE and/or TVA negotiated pipe rupture mitigation as part of'

the original design need be considered.BFN-50-C-7105, section 4.2 for further information.See design criteria,

3.1.6 To -Thermal ef fects and loads during startup, normal operating,

or shutdown conditions, based on the most critical transient orsteady-stato condition. ?

Y

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. OFRRABILITY CRITERIA FOR EVALUATION,

OF LOWER DRYWELL ACCESS PtATFORMSBFN-50-C-7302 I

'

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3.1.7Ta - Thermal loads under thermal conditions generated by thepostulated pipe break accident and including T . .

o3.1.8

RFE - Restraint of free end displacement loads due to thermalreactions from attached piping systems, based on the most criticalthermal condition.*

RFE loads can be subdivided as follows:3.1.8.1 RFE

~

ul - RFE reactions which contribute to uplift.3.1.8.2 RFEs - All other RFE reactions, i.e., reactions which do notcontribrte to uplift.

*If reduced conservatism is needed, RFE loads may be defined for upsetemergency, and faulted conditions corresponding to the associated dynamic

,

loading conditions (DYNB DYNC & DYND).

3.1.9 DYNB,DYNC, and DYND - Dynamic Reaction of attached systems, e.g.,

piping..HVAC, cable trays, etc., due to upset (service level B),emergency (service level C),events, respectively. and faulted (service level D) dynamic

Note: Not all attached systems are analyzed for the faultedcondition; therefore, some reaction points on the floor steel willonly have upset and emergency loading.

( 3.1.9.1 Dynamic Reaction Phasing

Dynamic reactions from attached systems are transmitted to thefloor steel through rigid restraints and snubbers.,

Based on thelocation and orientation of these restraints, differentassumptions can be made regarding the phasing of these dynamicloads. These assumptions shall be grouped into three general

.

categories as follows and they must be coordinated with theorganization responsible for the system dynamic analysis.Group A - Phasing Known

When two or more dynamic restraints act together to restrain aparticular motion or mode of vibration of an attached system,in-phase reaction loads can be assumed. For example, reactionsresulting from a matched pair of vertical snubbers on a pipingsystem would fall into this group. -

Group B - Random Phasing ~.''

When a dynamic restraint acts independently to restrain aparticular motion or mode of vibration of an attached system,this reaction can be considered randomly phased with otherdynamic reactions.

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I OPERABILITY CRITERIA'FOR EVALUATION. . .

'0F LOWER DRYWELL' ACCESS PLATFORMSBFN-50-C-7302

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Group'C'- Worst Case phasing

When two or more dynamic restraints act to restrain a particularlocation of an' attached system in more than~one direction, as 'r

phasing relationship for these restraints cannot be assume'd.For example, two snubbers which restrain essentially the samepoint on a piping system and whose lines of action 'are skewed to

.

each other would fall into this group. The'results of these j

reactions.must be summed absolutely to determine an enveloping,

t

. condition.[!

If further justification or additional analysis can show aphasing relationship between group C restraint loads, these.restraints can be treated as group'A' restraints, .

l.'3.1.9.2Procedure for Determining DYNB, DYNC, and DYND

3.1.9.2.1As a minimum, the following procedure shall be used .todetermine the dynamic reaction load cases.,

A. Assign each dynamic reaction to one of the groups definedin section 3.1.9.1. This requires engineering judgment. i

- Justification for:these groupings shall be included as part .|of the analysis calculation in accordance with section 4.0-of these criteria.. ,

B. Group A reactions shall be arranged into load sets'per the-

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phasing assumed. Each load set shall be evaluated j

separately with the results of each evaluation constituting )a dynamic load step. 1

.

C. Each group B reaction shall be evaluated separately withthe results of each evaluation constituting a dynamic loadstep. i

D. Group C reactions shall be arranged into load sets pertheir potential for phasing.shall be evaluated separately. Each reaction in the load set

The absolute summation ofthe results of each reaction in the load set shall- )constitute a dynamic load step.

E. Combine all dynamic load steps using the square root of the.

sum of the squares (SRSS) method to form DYNB, DYNC, or .

DYND.'..

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-3.1.9.2.2Figure 3.1 provides a graphic summary of this procedure. i

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' OPERABILITY GRITERZA'FOR EUALUATION"- '

10F LOWER. DRYWELL ACCESS PLATFORMS BFN-50-C-7302

13.1.10' DYBD'- Larger.of DYNB or.DYND. To determine DYBD, screen eachL'jDYMB' load step against the corresponding DYND load step. (Note '

that in some instances no DYND load step exists. In these cases,use the DYNB load step.) 'Combino the' screened load steps using,the SRSS method to form.DYBD.

3.1.11 DYCD - Larger of- DYNC or DYND. Use the procedure outlined in3.1.10 above substituting DYNC for DYNB.

3.2 Loadinn Combinations and' Allowable Stresses'

As stated in section 1.1, all radial platform support beams are,

supported on one end by beam seats welded to the drywell shell'.Since the beam seats do not have hold down capability, the potential:for. lifting off the beam seats as well,as the. beam stress must be' evaluated. Loading combinations and allowable stresses for. stressand uplift evaluations are specified in Table 3.2.1 and' Table 3.2.2.

.14.0 DESIGN AND ANALYSIS PROCEDURES.

The. design and analysis procedures utilized for the drywell steelstructures'shall be in accordance with reference 5.1. ,

|,.

A summary of analysis procedures as well.as justification for assumptions_ shall be documented in a DNE Calculation package.

|;

5.0 REFERENCESi.

5.1 American Institute of Steel Construction (AISC), Specification for. the Design, Fabrication and - Erection of Structural Steel for

Buildings, Eighth Edition, 1978.. . .

5.2 .TVA drawings 48N442, 48N443, 48N444, 48N1015-series, 48t11016-series,*

4CN1028, and 48N1115 or successor configuration control DocumentDrawings.

.TVA,' Civil Desiga Standard, DS-C1.7.1, " General Anchorage Concretc," f5.3May 1983.

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OPERABILITY CRITERIA FOR EVALUATION- *

OF LOWER DRYWELL ACCESS PLATFORMSBFN-50-C-7302

~

GROUP A Phasinn Known

K1+K2 -----------------------g\\n

\i.K3+E4 ~~~~~~~~~~~~~~~~ '

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\KN + E +1N ~~~~~ ~~~ s

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s\

g \ IGROUP B Random Phasing 's ' I

ss 1\g % I% \ ,t

a | DYNB1 ---------------------- SRSS-_--------------I DYNC/

| DYNDs' / /| |,

o'/ I,

s / /' /Is /Rg ---------- | | / | /

/ / / |'/ /' I,/ |/

t | |/'

/R / / |n ---------/

/f

/ / *

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/ /y

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GROUP C Worst Case Phasinn i / // *

|//

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lu 1 + |u 1 ----------- ' # ;1 2

, f' //

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/ Ilu 1 + lu4l - - - - - - - - - - - - - - '

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|u i + lu 1 1 ------------------- /n n

Ki = Individual group A reactionRi = Individual group B reactionUi = Individual group C reaction

Figure 3.1

Combination of Dynamic Reactions from Attached Systems-6-

DHE2 - 6859C

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0PERABILITY CRITERIA FOR EVALUATION-- *

OF LOWER DRYWELL ACCESS PLATFORMS ;BFN-50-C-7302

TABLE 3.2.1,

LOADING COMBINATIONS AND ALLOWABLE STRESSES' Combination-

No. Combination -

. Allowable' Stress (l)A. D+L Io 1.0 SB. D + E + DYNB

1.0 SC.. 'D+L F E + DYNBa 1.0 SD.

D + E + DYNB + To + RFE s 1.5 SE. 'D+Lo + E' + DYNC

1.6 S. F. ./ D + E' + DYNC + To + RFEs ' 1. 6 ' SC. D + E' + DYCD + Y (2)e 1.6 SH. D + DYND + T + RFEa s. 1.6-SI.

D + E + DYBD + T '+ RFEs + Y (2)~

_

a r 1.6 S'~

J.

D + E' + DYCD + Ta + RFEs + Y (2)p l'. 6 SNotes: I:

(1) S - For ' structural steel.. S is the all'owable stress based on elasticdesign methods. defined in AISC (reference 5.1). The one-third increase in .

-

allowable stresses AISC Code (reference 5.1) due to Seismic loadings is !not permitted.

/

In the abore factored load combinations, thermal loads (To and Ta) can be*

neglected when it can be shown that they are secondary-and self-limitingin nature and where the material is ductile.

1

The requirements of TVA Civil Design Standard (DS-C1.7.1, as applicable(references 5.3) shall be applied for evaluation and design of concret .f

I,

anchorages for supports. ]e

i

(2) only one pipe whip reaction should be considered at any given time; tI

however, all postulated breaks for which pipe rupture mitigationstructures exist and are attached to drywell steel must be considered

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*-OPERABILITY CRITERIA FOR EVALUATIONs

' ' . - 0F. LOWER DRYWELL' ACCESS PLATFORMS.

!

BFN-50-C-7302; '..

' TABLE '3.'2. 2I;~ n

LOADINC COMBINATIONS'FOR UPLIFT EVALUATION (1) I

L ,i

Combination Static Loading1

Dynam e'LoadinnA'

.9D + To + RFEul. --

!B '

.9D '

4DYNB'+ E

. '1..~

C ,

.9D + To + RFEul DYNB + E.D .9D -i

DYNC.+ E''E

.9D + T ,+ RFEul' DYNC + E' - In

|F *

.9D + T ..+ RFEul 'DYND + E'+ Ya ~

rC. a

.9D + T. a + RFEul DYND + E' + Y'i

rNote, :

, (1)In each combination, it must be shown that the magnitude of the beam

. seat reaction.due to static loading is greater ~ than the reaction due to !

dynamic-loading, unless an adequate tiedown exists or the' magnitude of !

uplift is within acceptable--limits of 0.05. inches. 1

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