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Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2....

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~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~- Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY [ NON QUALITY [ PROJECT ER/CTN NO. 402288 DESIGN ACT!VITY/PMR NUMBER PAGE I OF TITLEIOESCRIPTIOII MDII Data Detail, Linit S«retc Settings and Ectgne Sre.tch Settings for: Y /55 Fd03 SYSTEMS AFFECTED Generic Letter 89-10 required establishment of a program to provide for the testing, inspection and maintenance of safety-related motoroperated valves. This calculation provides the data details for the valve identified above which will be used to prepare the Data Detail Dra~ring which will support the testing, inspection and maintenance activities. See Section 2.0 for! methodology. This calculation serves as the design inputs for draTring N A - Ig7q See Section 3.0 foi Inputs/References. See Section 6.0 for Results/Conclusions. R(v I ~lc E Pyt 4 I4 . Aya.4+a HekIh. S4e+ <orqse = C 8-I (RaF.Iaj f.FTA) RINnru. arFFrmnv.t' YES-If yes enter: Binder g 9i10i00067 9'ii004 PDR ADOCK 05000387 0 PDR Calc. File NO Vol. Pgs. REV. NO. DATE PREPARED BY REVIEWED/CHECKED BY DATE APPROVED BY DATE I ~F 2 st II-- D ~9- - r TI ml s/frb006i (12) c-z w/ &J (O]4 'll 0'0 </
Transcript
Page 1: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

~ ~ ~ CALCULATION COVER SHEET

CALC. No.!~-~~- Zq2.

FILE NO. R2 +~

SUPERSEDED BY

SAFETY-RELATED f)cASME III OR XI fOTHER QUALITY [NON QUALITY [

PROJECT ER/CTN NO. 402288

DESIGN ACT!VITY/PMR NUMBER PAGE I OF

TITLEIOESCRIPTIOII MDII Data Detail, Linit S«retc Settings and Ectgne Sre.tch Settings

for: Y /55 Fd03

SYSTEMS AFFECTED

Generic Letter 89-10 required establishment of a program to provide for the testing,inspection and maintenance of safety-related motoroperated valves. This calculationprovides the data details for the valve identified above which will be used to preparethe Data Detail Dra~ring which will support the testing, inspection and maintenanceactivities.

See Section 2.0 for!methodology.

This calculation serves as the design inputs for draTring N A - Ig7q

See Section 3.0 foi Inputs/References.

See Section 6.0 for Results/Conclusions.

R(v I ~lc E Pyt 4 I4 .

Aya.4+a HekIh. S4e+<orqse = C 8-I

(RaF.Iaj

f.FTA) RINnru. arFFrmnv.t' YES-If yes enter: Binder g9i10i00067 9'ii004PDR ADOCK 050003870 PDR

Calc. FileNO

Vol.

Pgs.

REV. NO. DATE PREPARED BY REVIEWED/CHECKED BY DATE APPROVED BY DATE

I ~F 2 st II--D ~9- - r TI

ml s/frb006i (12)

c-z w/ &J (O]4 'll0'0 </

Page 2: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

DESIGN INPUTS CHPXXIJSTTitle 6, No. 4-V'LV'- 277 R ~ O

INPUTSPage 2. of 8<File R35

lN 1.ib.qt~ ~t i/eg

h. DESIGN INPUTS

l. APPLICABLE CODES

Codes: ASME, ASIA, AISI. Standards: ANSI, IEEE, AWS, ANS Regulatory Requirements.

2. PERFORMANCE REQUIREMENXS

A. Input Requirements - For services such as air, water, electricity,lube oil, etc.

B. Output Requirements - Physical output such as: capacity, pressure,temperature, voltage, velocities of fluids, pressure drops separationand isolation both system and unit, and redundancy requirements ofstructures systems and components.

C. Operational requirements under various conditions, such as plant startup,normal plant operation, plant shutdown, plant emergency operation, specialor infrequent operation and system abnormal or emergency operation. Thisincludes the overall effect on the plant (i.e., the potential loss of generation).

D. Failure effects requirements of structures, systems and components,including a definition of those events and accidents which they mustbe designed to withstand.

3. COMPATIBILITY

h. Compatibility and suitability of material selection, such as chemical andphysical characteristics, radiation and heat resistance protectivecoatings and corrosion resistance.

B. Operational interface requirements including definition of thefunctional interface involving structures, systems and components.

4. INSTALLATION (ITEMS MAY APPLY TO ANY DISCIPLINE)

A. Transporting and Storing - Includes environmental conditions anticipatedduring storage, construction and operation and handling storage andshipping requirements.

B. Civil - Plant layout and arrangement requirements, escape fromenclosures, anchor bolts, penetrations, equipment foundations.

C. Piping - Thermal expansion or heat restriction requirements, vibration ordynamic loading considerations, stress, shock, reaction forces and pipe supports.

D. Electrical - Voltage, source, grounding conduit(raceway requirements.

E. Instrumentation - Instrumentation and control requirements includingindicating instruments, control and alarms required for operation,testing and maintenance and calibration.

F. Chemistry - Water chemistry considerations, including sampling provisions.

5. MAINTAINABILITY

h. Accessibility - Maintenance, ISI and ALARA accessibility requirements.

6. TEST REQUIREMENTS - Including pre-OPS, ISI and LLRT tests.

7. SAFETY - Personnel and public safety including special blocking, radiationexposures, ALARA environmental concerns, effluents and noise.

8. SECURITY - Physical security plant considerations.

9. DESIGN CONSIDERATIONS - Form EPM/h-20882 and B3.

10. OTHER-

APPLICABLEYES NO

bC) t )

%) t )

[X) t )

h(.) [ 1

t 1 bc)

t 1 baal

[ ) bc)

[ I bc)

[1 M

t ) bc)

b<) t 1

bc) t )

t 1 b<)

t 1 lx)

t 1 tx)

t )

t ) b<)

b<) t 1

t) R)

dhc/lie007i(ll)Form EPM+h»208B, Rev. 5 (1 of 3)

Page 3: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

0

Page 4: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

DESIGH INPOXS CICXLXSZ

a.tie 6 No. 6- VLV- 2 /2 6~ (7

B. DESIGN CONSIDERAXIONS

INPUTSPage 3 o f {~>

File R35

QN <f.(C ch

Py q-zi-e/

SUBJ'ECE

1. Dynamic Qual ification"

2. Environmental Qualification2.1 Relay Qualified Life

APPLICABLEYES NO

t l IX)

N ( I

() M

REFERENCEPROCEDURE

EPM+A-222

EPM+h-222

CIVVernarr

CIVDerkacsELCNudge

ISSUEDGUIDANCE

GDG-03

SEA-EE-170SEA-EE-171

3. Electrical Separation

4. II over I, Safety Impact

5 ~ Fire Protection

6. Appendix R-6.1 Safe Shutdmm Analysis6.2 Combustible Loading Anal.

( l bt)

( l bc)

t l X)

[l tRtl fA

EPM+h"211 CIVRose

NDI+h-15+ 3o 1 EPEPM+h-440 Kohn

ELCBackenstoeCIVDelgado

E 1012

Fire ProrectionManual

EDS-01

CDS-03 6Dug. C-1929

7 ~ Flooding Protection

8. Jet Impingement

10. Radiation Exposure, ALARA

11. Physical Separation

12. HVAC Requirements

13. ElectricalLoad/Voltage Study

14. Human Factors Engineering

15. Inservice InspeccionRequirements

16. Materials Compatibility

17. ASME Code Compliance(See Note 1)

18. Design Assessment

19. Fuel/Core Effects

( l M

( l Xl

bcl

t l

[ ) (X)

lK) t )

t I bc)

t )

t ) bc)

t l M

t ) M

tl K)

NDI-6.4. 2

NDI-15.3. 12

NDI+h 15.3.7

NDI+h-7.2. 2

CIVReinsmith

CIVMatchick

CIVRose

ELCSleva/Nudge

EPPatnaude

EPLindberg

EPWillertx

MCBSetter

SEDetamore

NFEKulick

Memo AM-151DG-G-100

htg. C-1804

EDG-02EDS-02

Human FactorsSpecifications6 GuidelinesManual

ISI Manuals

PLI-59437 dated3/31/89

Form EPM+A-208B, Rcv. 5 (2 of 3)

Page 5: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY
Page 6: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

DESIGN INPUTS QKCELIST

Litle & No. A-YLV-271 IZ<v 0

B. DESIGN CONSIDERATIONS

INPUTSPage 9 of

9'ile

R35

Okll 1.lg-ql

EUEIECI

20. Heavy Loads

APPLICABLEYES NO

( ) fx) M"1435 MCHKostelnick

ISSUEDGUIDANCE

21. RadMaste Minimization

22. Approved Materials

23. Secondary Containment,Control Structure,Ventilation ZoneBoundary Penetrations

24. Electrical Load Tracking

t 1'cL( 1 bc)

[1 b4

NDI+A-15.3.9 EPMorgan

MCHAgnev

ELCSieve/Nudge

NDPL85-003

Susq. Approved Matl'sPLI.37573 of 1/10/85PLI 45673 of 5/22/86

EDS 02

25. Computer Program Changeincluding Display Formats

W) EPM~A-401 CPU

26. Environmental Protection

27. Station Blackout

yl NDI-QA-6.3.2

(] bO

(Nuc. Svcs.-J. S. Fields)

ELCSleva

GDS 08

NOTE 1: For modifications to ASME III systems/components (both paperwork only and physical changes)request in the installation instructions that Plant Staff prepare the required documentationpackage per NDI-QA-5.3.4 and AD-QA-522.

dc/a186i(11)

Form EPM-QA-208B, Rev. 5 (3 of 3)

Page 7: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

~ ~ QEctj:GN INI LlTS ( con ')

2. T/TI p W-YLV- 2.72. t4 0

hu

I ~ PAGE ~ OF l~

FILE NO. R35

a. r rEW 5. DISCUSSION 3.NQ

Ap li&lt Q Jtr.'c~lAie< slall /tlJ~plfvPg vert t'ai'f /O'Cc Aaf/li. 4Jfg/ Q /g

A,8/CPtJ6'I'teat ~Ct Rt/Vl&m\~C t

8tclric tj t /tj vt7ct'rt ter art perte Q 4 '>$«Mi /ltl7rr ling AS -217

was'-or 7igw mg 'Tl

tttt//t< rt~

rt~'dr N tlat aa/aa/t art g/irt Cj C rttllf-trl

+(f/41 MJ tft/t~t ttA tc/he< At MW7Sr j rCyl Sr <J )4

err gt~ ~ ~EA Wg g?7,

CJCOOCV

I

CO

I

XCL

Page 8: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

Calc 0 M-VLV-272 4v 0

Page < of 'l~

Calculation Contents

1.0 Purpose/Scope

2.0 Methodology

2.1 Actuator Sizing Calculation2.2 VOTES Diagnostic Thrust Acceptance Criteria2.3 Limit Switch Settings2.4 Other Items

3.0 Inputs/References

4.0 Assumptions

5.0 Calculations

5.1 Actuator Sizing Calculation5.2 VOTES Diagnostic Thrust Acceptance Criteria5.3 Limit Switch Settings5.'4 Other Items

6.0 Results/Conclusions

Page 9: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

Calc 4 M-VLV-27'. 6v g

Page 7 of gc

%Peg ePpf v-w-r>

1.0 Pur ose Sco e

The purpose of this calculation is to develope all ofthe information necessary to create a Motor OperatedValve Data Detail Drawing for the subject MOV. In orderto meet this end the following specific activities willbe performed in this calculation to complete the MOVDetail Drawing for the subject MOV:

1.1 Research existing design documents and records forthe MOV to determine best available configurationdata. This data will be used as input to the MOVData Detail Drawing as well as to the calculationsto be performed herein.

1.2 An actuator sizing calculation will be performedto determine the required actuator parameters(e.g.actuator size, motor size, spring pack,torque switch settings, etc.).

1.3 Using the results of Item 1.2, diagnostic testacceptance criteria will be established.

1.4 Based on the design function of the MOV, gearedlimit switch settings will be determined. For thepurposes of this calculation, the limit switchfunctions to be considered will be limited to:

a.) Torque switch bypass (open and closedirection)

b.) Full open limit switch

c.) Valve position indication

1.5 A review of previously approved spring packReplacement Item Equivalency Evaluations (RIEE'sor RIE's) will be performed for the particular MOVbeing evaluated. Changes to these RIE's will beprocessed as necessary based on the results ofthis calculation.

Page 10: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

Calc I M-VLV-Z72. k~v oPage g of q~»~e iL.e

p7Pp 1-~I.wt

Existing design documents, modifications and fieldwork authorizing documents will be reviewed toidentify required inputs to the MOV Data DetailDrawing. Lists of the required inputs „as well as across reference to the data source are provided inSection 3.0 of this calculation.2.1 Actuator Sizinc[ Calculations: These will be

performed usinq the software version ofMechanical Design Standard (MDS) Number 01 (Inputa. ). The following methods will be used tocompliment the techniques used in the softwarepackage:

a.) The active valve stroke length is arequired program input which allows theprogram to calculate a design valvestroke time. The active stroke lengthwill be calculated based on the followingexpression:ACTIVESTROKE = Z * FSLLENGTH

Where:

Z = The setpoint of the full openlimit switch in percent open(typically 97%)

FSL = Full Valve Stroke Length fromthe closed position to the fullyopen (backseated) position. IfFSL is not specifically known itcan be calculated using thefollowing expression:

HWT * SLFSL

HGR

Where:

HWT = The number of handwheelturns required for thevalve to travel fromfully closed to fully

Page 11: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

open.

Calc I M-VLV-272. g,~ gPage y of q~>4 e.tc.e

pp f->I-+I

SL = The valve stem lead.

HGR = The overall handwheelgear ratio.

b.) Program overrides will be used to allowthe calculation to reflect the currentconfiguration of the MOV.

c.) Once an expected motor run torque iscalculated, a typical motor curve will beconsulted to determine an estimatedmidstroke loaded motor speed (RPM). Thecalculation will be rerun using thisvalue as an override, the result being amore representative design stroke time.

d.) For gate valves the calculation will berun using a valve factor of .3.

e.) The calculation will be run with variousacceptable spring packs to allow forflexibilty in future replacement. Onlyspring packs approved on spring packequivalencies wall be included on the MOVData Detail Drawing.

the actuator sizing has been completed diagnostictest thrust acceptance criteria will beestablished using the following methodology:

a.) The Minimum Allowable Thrust will beestablished as 1154 of the desiqncalculated required thrust. Thxs allowsfor at least 10% error in the diagnostictest results and 54 variation in torqueswitch repeatability.

b.) The Maximum Allowable Running Thrust willbe established as the Stuffing BoxFriction load used in the actuator sizingcalculations.

c.) The Maximum Allowable Thrust will beestablished as the thrust correspondingto the minimum of the following:

Page 12: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

Calc N M-VLV-g72~gPage go ofAN 4-Il'1> ~ f/w/4A

1.) Actuator thrust rating,2.) 1204 of the equivalent thrust

at maximum allowable actuatoroutput torque,

3.) Maximum allowed valve thrust(if available).d.) The acceptance criteria at each torque

switch setting will be specified as theexpected thrust +/- 204

e.) In all cases items a.) and c.) shall takeprecedence over item d.).

calculation will determine the appropriate gearedlimit switch settings for valve control andposition indication. The limit switch settingswill be established per the requirements of MDS-03 (Input b.). The switch settings will bespecified in percentages of physical stem travelfrom either full open or full closed.

2.4 Other Items

Page 13: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

3.0 Xn uts References

Calc I M-VLV-47K R~~ oPage // of QwWl't (l tr gVpt V/ii/f(

3..1 The principle design inputs for this calculation are:

a.) MDS-01 "Design Standard for the Sizing ofLimitorque Actuators Including ThrustCalculation, Actuator Sizing, Spring PackSelection and Torque Switch SettingDetermination." Revision l.

b.) MDS-03 "Design Standard for Determining andSetting Valve Motor Actuator Limit Switches."Revision 0.

3.2 Information required for entry on the MOU Data DetailDrawing and as input to this calculation is providedon pages i2 through Ip of this calculation.Reference Numbers are provided for each of theentries. A listing of all references is provided onPage /4 (Note: Copies of references not readilyavailable are provided as attachment to thiscalculation).

Page 14: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

General Valve DesignData Value

Calc 4 M-VLV-Z72. Qzt:Page R- of towIANNA-g.e py 9-P-9I

Reference No

Valve Manufacturer A>Vendor Drawing Number

Valve Serial Number

Valve Quality Class

93- >J'So 2

Valve ASME Section IIIEdition and Class j97/ 'NW M'72- 8/~u I

Valve Location (Inside/Outside Containment)

Valve Type

Valve Pressure Class

OuTfioj=

Q7E

Valve Size (Inches)

Valve Seat Area (Inches Squared)

Stem Information:Stem Diameter (Inches):

At Stuffing Box Location /,g75't

Threaded Portion /.f75'hread

Pitch/Lead o.D3 oc47

Stem Material A 274- v/0

Original Design Stroke Time (Seconds)

Page 15: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

Calc 4 M-vLv-Z7gPage u of cfz-

General Valve Design (Cont.) '"""'"W'«Process Parameters:

Flow Medium

Data Value Reference No.

Q(Design/Maximum Pressure (PSIG)

Design/Maximum Temperature ( F)

Design/Maximum Flow (GPM or LB/HR)

Throttled Flow (GPM or LB/HR)

/2 5o j /35'0

2I6 OOo /tlc/FaOO LE/A. QI(

Max, Operating Differential Press. (PSID):

Opening Direction

Closing Direction

Additional Physical Parameters:

Valve Max. Thrust Capability (LBS) NP7 AvAILAQC2

End Connections/RatingI

Body Material

Disc Trim Material

/34/ - J'Ch'

Jg gled -Mt g

STE, I Z i 7-Z

Body Seat Trim Material

Guide Rib Facing (Gate Valves Only)

Drain/Bypass Required (Y/N)

Srz~im

J g g t t'. - uc 8

Page 16: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

General:

Actuator Quality Class

Safety Function (Open/Close)

Actuator Manufacturer

Actuator DesignData Value

Ig l~iiar)Vt

Page lf of 'f2-

Reference No. ltltN't-t5-qiPEP' -iI-t

Calc g M-VLV-272- 6v o

Main Unit ( e.g. SMB):

Actuator Order Number 3S.I~Cy g

Actuator Serial Number los'$ /5

Actuator Size JAG-~ - gg

Gearing Information:

Motor Pinion Number of Teeth Os.

Worm Gear Number of Teeth

Worm to Worm Gear Ratio

Overall Actuator Ratio 77.P: I

Lost Motion Drive Sleeve (Y/N)

AuxilaryWorm/Bevel Gear Unit:

Unit Order Number 8/A

Unit Serial Number

Unit Type/Size

Unit Gear Ratio p'A

Overall Handwheel Ratio ~'+ 9f:/

Handwheel Orientation (Top or Side Mount)

Handwheel Efficiency

Page 17: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

Electrical/Motor Design InformationData Value

Motor Class (1E/Non1E)

Calc 4 M-VLV-27iPage IS of gl. <

~ Power Supply Type (AC/DC)

Power Source

Voltage Supply/Phase/Frequency

Motor Manufacturer

25O/ I / n/4

Motor Serial Number

Design Motor Speed (RPM)

Motor Start/Run Torque (ft-lbs)

Motor Horsepower

Service Factor

/boa

Motor Type/Frame Size

Motor Frame Design/Enclosure Type

Winding Type (DC Motors)

Motor Duty Rating

Insulation Class

/ 4/zd'R

Temp. Rise/Ambient Temp. ( C)

Full Load/Locked Rotor Current (Amps) orKVACode (LRIC) at Supply Voltage (See Note 3)

r

DC Motor Field Current (Amps)1

LimitSwitch Comp/Motor Spaceheaters (Y/N)

Page 18: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY
Page 19: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

References:

1. Anchor Darling Valve Drawing 93-13802(FF 110100 6101), Rev 8

Calc 4 M-VLV-272 gqy 0Page /g of ~~

beak e-g-eg7py f-w

2. Anchor Darling Letter dated 2/20/90 (copyattached)3. Valve Specification Data Sheet P10 Sh 9 (copyattached)4. Work Authorization S70796 (copy attached)5. Motor Operator Information Sheet for 381264H (copyattached)6. SEL-ll, Limitorgue Standard Handwheel Ratios (copyattached)7. SEIS'Pipeline Index, dated 8/9/888. Anchor Darling Design Report E5853-21-D

(FF 110101 1401), Rev 1 (copy of referenced pageattached)9. P & I D M-155 RCIC Sht 1 Rev 32

1 0 PIPT'Jl'1.

SEA-ME-238 Design Basis Development Priority 2Motor Operated V ives, Rev 0 (copy of data sheetattached) (g((g(g(

12. Electrical Schematic Dwg. E- i'h (J Rev /'/

13 ~ f/or

14. Anchor Darling Telecopy dated 3/28/91 (copyattached)

P~cg. g$ o% 100 Rev, 5

Page 20: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

Assum tions

Calc 0 M-VLV-2.1+ Ize bPage ~y o f y~

'l l/-etf-w-~f

1. For the purposes of this calculation, attempts havebeen made to verify design information againstactual as-installed information as documented inPlant Work Authorizations. Where actual as-installed information is unavailable the originaldesign information will be used. Upon completion offield as-built verification, any'iscrepencies willbe reconciled and this calculation shall be revisedas appropriate.

2. Stuffing box friction values will be consistent withthe empirical values listed in MDS-01 unlessotherwI.se noted herein.

3. Unless noted otherwise, the stem factor used hereinwill be based on a coefficient of friction of 0.15(Reference (0- ). This is consistent with theoriginal design seismic analysis. The SSES MOVpreventative maintenance and trending program willensure the valve stems/stem nuts are maintained in amanner which supports this assumption.

4. The minimum voltage available will be assumed to be804 unless noted otherwise. If the electricalvoltage drop calculations show this to beunconservatzve a lower value will be used. If theuse of 80% initially produces unacceptable resultsthe electrical voltage drop calcs will be consultedin an attempt to remove some of the conservatism.

5. Gate valve sizing calculations will be run using avalve factor of .3.

6. During the initial preparation of this calculation,the valve maximum thrust capability may not yet beavailable. In these cases, the maximumthrust/torque shall be based on the following:

~Maximu Torque

The maximum allowed torque shall be the lesserof the maximum torque calculated by the MDS01software or the torque corresponding to theoriginal design maximum torque switch setting.g~gE ~%stThe maximum allowed thrust. shall be the lesserof the actuator thrust ratinq or 120% of theequivalent thrust at the max>mum allowableactuator output torque.

Page 21: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

Calc g M-VLV-Z72 4~ 0Page /P of qzbled 9-]l-qi

PP 9-w-ql

5.1 Actuator Sizing CalculationThe results of the actuator sizing calculations areprovided as follows:

Run g Conditions Calc. Pacaes

1 ~SPRUNG P~ oao7,VALV6 RtcPA,2

ZZ-23

2. SPeHP PA<aug'ACVePAc~ -"(- -'5

3 ~

4.

5.2 VOTES Diagnostic Thrust Acceptance Criteria,The calculation of the thrust acceptance criteria wasperformed per the method outlined in 2.2.

~</tb5.3 Limit Smitch Settings

~«py 27 gr neer

Page 22: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

~ ~ ~

I I

~ ~ ~ ~

Page 23: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

CALCULATIONSHEETACTUATOR SIZING

PPSL CALC NO. W-wv-pe, g,yPAGE zg OF ~~ g]<.is.z

9 Q '0/MDSA1%3 Rev.1 f6'OI- 7]Valve tag number

4V- I5$F o p3

Select APPLICATION FACTORS [APPENDIX E]

Selected APPLICATION FACTORS

0, I

Resultant Application Factor

Calculated MOTOR START TorqueStem Tor ue

Overall Actuator Ratio x Unit Pullout Efficiencyx Application Factor

7F'x -25m . I

FT-LBS

[eqn. 13 ~;

Calculated MOTOR RUN TorqueTrun x FS

Overall Actuator Ratio x Unit Run Efficiency

S6'/gal(oughz.g

7g ~+5

FT-LBS

[ eqn 151 i

I

Reduced Voltage Requirements {ifapplicable);

Revised MOTOR START Torque (AC)Calculated Motor Start Torque

% Volta e Available ) FT-LBS

[eqn. <((

Revised MOTOR START Torque {DC)Calculated Motor Start Tor ue

% Volta e Available

g7,5.F

FT-LBS

[ eqn.

Page 24: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

CALCULATIONSHEETSPRING PAC SELECTIONMOTOR SIZE SELECTION

PP&L CALC NO. pf-t/Lv'-gpy g~ oPAGE <i OF '|~ ~~- 4o

q grip/MDS-01-03 Rev.1 P OF 7]Valve tag number

//v'5'5 /- 003

MOTOR SIZE SELECTION:

Select MOTOR SIZE based on criteria stated in MDS-01 section 5.2.8.2AS /u/. Aus P

Selected MOTOR SIZE/f-/J3

MOTOR SIZE CHECK:

Selected Motor Size

FT-LBS

FT-LBS

FT-LBS'riteriaZ3.5'alc.

MOTOR START torque

2f, '/Revised MOTOR START torque

5~33 = /f 5

5 x Gale. MOTOR RUN torque

MOTOR STALL:Stall Torque (ft-Ibs)= Selected Motor Size (ft-Ibs) x Overall actuator

ratio x Stall Efficiency x1.1 /EVY,'/ FT-LBS

[eqn. 19]'/o "7f~,'/5 x /./

Stall Thrust (Tstall) Ibs= Stall Tor ue/FS

/5'/c9 [eqn. 18]74o 7'f

, @Zoic LBS

MOTOR STALLCHECK:Stall Thrust (Tstall).

74 o79

LBS

CRITERIA

//2.5 oo

2.5 x Actuator Thrust Ratin

LBS

Page 25: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

PPGL REVISION 1. 90226 DATED 08-14-90 — TODAY IS

g vga-z72 g,~ gPage 2z~F ~L

08-19-1991 12 46: 53 09lb'ALVEInfo (Input)t Calculated by:

(TABLE 4 1 )— FILE: 155F003

Page 1 of 2

Checked by:ValveValveValveValveValveValveValveValveValveValve

MANUFACTURERTYPE (GATE or GLOBE):SIZE:TAG Number:VENDOR DRAWING number:PP&L Drawing number:LOCATION:SYSTEMLINE (ie. PIPE LINE I.D.):MAXIMUM Design THRUST:

ANCHOR DARLINGGATE

10HV155F00393-13802

VALVE Data (Input) (TABLE g 2 ) — FILE: 155F003

ANCHOR DARLING GATE Tag: HV155F003Valve STEM DIAMETER (Inches):Valve STEM PITCH:Valve STEM LEAD (Inches):Valve SEAT AREA (Sq-Inches):Valve STEM AREA (Default = 0 Sq-Inches):Req'd STEM SPEED (0 or 3-6=Globe or 12-14=Gate):Valve STROKE LENGTH (Inches):Req'd STROKE TIME (Seconds):Valve INLET PRESSURE (PSIG):Valve PRESSURE DROP (PSIG):Valve Factor (.2 or .3=Gate 1.1=Globe):

ve STUFFING BOX FRICTION (Default = 0 Lbs):ve STEM/NUT Coeff. FRICTION (0 .15 or .2):Manual ACTUATOR RATIO Selected: 92.4 : 1

Manual ACTUATOR Selected: 18Manual SPRING PAC CURVE Selected: 27

MOTOR Data (Input) (TABLE 5 3 )— FILE: 155F003

1. 875.333.66766.332 '61172000 ( 0 Min.)11461146~ 32500.15

ANCHOR DARLING GATE Tag: HV155F003Motor TYPE (AC or DC):Motor RPM (900 1800 or 3600):Motor REDUCED VOLTAGES Percent (Default=0.8):HIgh TEMPerature application (Y or N):COMPound motor GEAR application (Y or N):AIR MoToRs (Y or N):MODULTRONIC MoToRs (Y or N):HILO Applications (Y or N):Non-Rising Stem — OPERator thrust (Y or N):Non-Rising Stem — VaLVe thrust (Y or N):

Manual MOTOR Selected: 16

DC1800.8

NNNNNNN

Page 26: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

PP&L REVISION 1.90226 DATED 08-14-90

lculation RESULTS (TABLE 4 4 )

Calculated by:

<- +4'- Z72 Revg

NQ I (k9iTODAY IS 08-19-1991 12:46:54 Pyjy g.gp-og

FILE: 155F003Page 2 of 2

Checked by:ANCHOR DARLING GATE Tag: HV155F003

Valve STEM FACTOR: 0.0203STUFFING BOX FRICTION: 2500 Lbs

THRUST: 28468.56 LbsSTEM TORQUE: 576.943 Ft-Lbs

STEM SPEED: 13.71537 Inches/Min.UNIT RPM: 20.56277 RPM

Design STROKE TIME: 0 SecondsOVERALL ACTUATOR RATIO: ~2 ' gcrvgc IS'8'.

* SMB-1 ACTUATOR selected having a 92.4 — 171.6 Ratio RANGE (IACT= 18 )* SMB-1 92.4 — 171.6 UNIT Efficiencies: PULLOUT= 35 RUN= 45 STALL= 45* * USER Selected ACTUATOR* * USER Selected ACTUATOR Ratioused 1800 Rpm 'DC'otor

APPLICATION FACTOR:Calc. MOTOR START TORQUE:

MIDSTROKE RUN THRUST:Calc. MOTOR RUN TORQUE:

* 40 Ft-Lbs SMB-1 MOTOR with* * USER Selected MOTOR

vised MOTOR START TORQUE:STALL TORQUE:STALL THRUST:* * USER Selected Motor SIZE

0 RATI at 1900 Rpm.919.8 13 Ft-Lhs566 . 3 Lbs2 60765 Ft-Lbs (5 X RUN= 13.80382 )

106 Maximum Ratio Selected (IMTR= 16 )

24. 77 7 Ft-Lbs1829 2 Ft-Lbs902 . 6 Lbs (2.5 X Rated= 112500 )

* SPRING PAC Curve: SMB-1 OBSOL Selected (ISPG= 27 )* * USER Selected SPRING PAC CurveSPRING PAC No: 60-600-0007-1

BILL of Materials No: NONE

* Calc. SPRING PAC SETTING: 2.764496* Set SPRING PAC to: 3Max. SPRING PAC SETTING: 3.75

Normal TORQUE: 641 Ft-LbsMax. TORQUE: 845 Ft-Lbs

MOTOR SIZE Checks: 40 Ft-Lhs vs 19.82213 Ft-Lbs Calc. Start TORQUE40 Ft-Lbs vs 24.77767 Ft-Lhs Revised Start TORQUE40 Ft-Lbs vs 13.80382 Ft-Lhs 5 X RUN TORQUE

MOTOR STALL Check: 90275.46 Lbs vs 112500 Lbs 2.5 X Actuator THRUST

TORQUE SWITCH Checks: 845 Ft-lbs vs 850 Ft-Lbs Actuator RATING41695 Lbs vs 45000 Lbs Max. Actuator THRUST845 Ft-Lbs vs 1829 Ft-Lbs Stall TORQUE3.75 SETTING vs 5 Max. SPRING PAC Setting

* CAUTION — Check MDS-01 if this application operates at 340 DEG.F

Page 27: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY
Page 28: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

PP&L REVISXON 1.90226 DATED

tVALVE Info (Input) (TABLE

Calculated by:

Pl- vs- g7g + gP~c ~q.F~~

08-14-90 — TODAY IS 08-19-1991 12: 45: 14 ~W 9 ti-eipg/ f~) /~'tl

1 )— FILE: 155F003

Page 1 of 2

Checked by:ValveValveValveValveValveValveValveValveValveValve

MANUFACTURER:TYPE (GATE or GLOBE):SIZE:TAG Number:VENDOR DRAWING number:PP&L Drawing number:LOCATION:SYSTEM:LINE (ie. PIPE LINE I.D.):MAXIMUM Design THRUST:

ANCHOR DARLINGGATE

10HV155F00393-13802

VALVE Data (Input) (TABLE 4 2 )— FILE: 155F003

ANCHOR DARLING GATE Tag: HV155F003Valve STEM DIAMETER (Inches):Valve STEM PITCH:Valve STEM LEAD (Inches):Valve SEAT AREA (Sq-Inches):Valve STEM AREA (Default = 0 Sq-Inches):Req'd STEM SPEED (0 or 3-6=Globe or 12-14=Gate):Valve STROKE LENGTH (Inches):Req'd STROKE TIME (Seconds):Valve INLET PRESSURE (PSIG):Valve PRESSURE DROP (PSIG):V lve Factor (.2 or .3=Gate 1.1=Globe):

ve STUFFXNG BOX FRICTION (Default = 0 Lbs):ve STEM/NUT Coeff. FRICTION (0 .15 or .2):Manual ACTUATOR RATIO Selected: 92.4 : 1

Manual ACTUATOR Selected: 18

MOTOR Data (Input) (TABLE g 3 )— FXLE: 155F003

1.875.333.66766.332.761172000 ( 0 Min.)11461146~ 32500~ 15

ANCHOR DARLING GATE Tag: HV155F003Motor TYPE (AC or DC):Motor RPM (900 1800 or 3600):Motor REDUCED VOLTAGE Percent (Default=0.8):HIgh TEMPerature application (Y or N):COMPound motor GEAR application (Y or N):AIR MoToRs (Y or N):MODULTRONIC MoToRs (Y or N):HILO Applications (Y or N):Non-Rising Stem — OPERator thrust (Y or N):Non-Rising Stem — VaLVe thrust (Y or N):

Manual MOTOR Selected: 16

DC1800.8

NNNNNNN

Page 29: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

8-ULU-z72 /4w g

PP&L REVISION 1 ~ 90226 DATED 08-14-90 — TODAY IS 08 19 1991 12 '45'5g ~i g

lculation RESULTS (TABLE 4 4 ) — FILE: 155F003Page 2 of 2

Calculated by: Checked by:ANCHOR DARLING GATE Tag: HV155F003

Valve STEM FACTOR: 0.0203STUFFING BOX FRICTION: 2500 Lbs

THRUST: 28468.56 LbsSTEM TORQUE: 576.943 Ft-Lbs

STEM SPEED: 13.71537 Inches/Min.UNIT RPM: 20.56277 RPM

Design STROKE TIME: 0 SecondsOVERALL ACTUATOR RATIO: 92. 4 gcyvgc. py 7g:u

* SMB-1 ACTUATOR selected having a 92.4 — 171.6 Ratio RANGE (IACT= 18 )* SMB-1 92.4 — 171.6 UNIT Efficiencies: PULLOUT= 35 RUN= 45 STALL= 45* * USER Selected ACTUATOR* * USER Selected ACTUATOR Ratioused 1800 Rpm 'DC'otor

APPLICATION FACTOR:Calc. MOTOR START TORQUE:

MIDSTROKE RUN THRUST:Calc. MOTOR RUN TORQUE:

0 RATI.919. 135664 032 ' 0 5

at 1900 Rpm

Ft-LbsLbsFt-Lbs (5 X RUN= 13.80382 )

* 40 Ft-Lbs SMB-1 MOTOR with 106 Maximum Ratio Selected (IMTR= 16 )* * USER Selected MOTOR

evised MOTOR START TORQUE: 24. 77 7 Ft-LbsSTALL TORQUE: 1829 2 Ft-LbsSTALL THRUST: 902 5. 6 Lbs (2.5 X Rated= 112500 )* * USER Selected Motor SIZE

* SPRING PAC Curve: SMB-1 HEAVY Selected (ISPG= 12 )SPRING PAC No: 60-600-0068-1

BILL of Materials No: 0701-212* Calc. SPRING PAC SETTING: 2.076543* Set SPRING PAC to: 2.25

Max. SPRING PAC SETTING: 2.75Normal TORQUE: 638 Ft-Lbs

Max. TORQUE: 838 Ft-LbsMOTOR SIZE Checks: 40 Ft-Lbs vs 19.82213 Ft-Lbs Calc. Start TORQUE

40 Ft-Lbs vs 24.77767 Ft-Lbs Revised Start TORQUE40 Ft-Lbs vs 13.80382 Ft-Lbs 5 X RUN TORQUE

MOTOR STALL Check: 90275.46 Lbs,vs 112500 Lbs 2.5 X Actuator THRUST

TORQUE SWITCH Checks: 838 Ft-lbs vs 850 Ft-Lbs Actuator RATING41350 Lbs vs 45000 Lbs Max. Actuator THRUST838 Ft-Lbs vs 1829 Ft-Lbs Stall TORQUE2.75 SETTING vs 2.75 Max. SPRING PAC Setting

* CAUTION — Check MDS-01 if this application operates at 340 DEG.F

Page 30: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

9D)~ c9tfet jaS4 116(gtat e91)401

Dept.

Date ~ 19 '9t

Designed by

Approved by

PENNSYLVANIAPOWER 8I LIGHT COMPANYCALCULATIONSHEET

PROJECT MOV Data Detail,

Limit Switch Settings, and

Torque Switch Settings for HV- /SS l-DD3

ER No.M-VLV-2.72. gt9 g

Sht. No. ~4 of <~

PULLOUT TORQUE CALCULATION:(100% Voltage)

Pullout Torque (ft-Ibs)

Pullout Torque (ft-Ibs)

Motor Start Torque x Overall Actuator Ratio xPullout Efficiency x Application Factor

Qg py

x.3S'ullout

Torque (ft-Ibs) 9g z.

3'quivalent

Thrust (Ibs) = "~~ ~q I q~y

ohoJ

TORQUE SWITCH SETt'ING CHECK (cont'd):

Torque (ft-Ibs) at MaxTorque Switch Setting

vs. Voltage PulloutTorque (ft-lbs)

vs.

Page 31: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

isssLL Co(m 2454 esD'NlCe;, eg7340s

Dept. PENNSYLVANIAPOWER & LIGHT COMPANYCALCULATIONSHEET

Designed by ~ PROJECT

Approved byIy'IS'5

Foo3'RNo.

Sht. No. ~~ A of

Q~,~.z~ I

yl.c F~jzvw =

Zvr.Pu p (w, p)

+p

ADA-o( 6v~+. zz

F = Zoo4~= z.;CAt< "- +4.27

li!Ca P= IIPS R 2c>l Yeller

= (>~)

4eyre( yer Jyccrf*rirt ='t/<:"-. „c set'cicci cc<Qc (@'g)

4 JVCtl Yr'ligt gal Hipster- <t~tsl Vilest Attn fNf7~E a OAR Jc Un j'fatf ER".

A+), Merv4 x. 7F x.. I5

I'/53

7/574 - ~QO 0 - (2 7d d ItV-')

6'IgE7

Page 32: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

Geared LimitSwitch SettingsData Value

Calc 4 M-VLV-272. @ra.Page 1g of tinbow 1-rl fr

Pyr 0-g-IlReference

No.

Electrical Schematic & Connection Diagram No. E- l52. Slr. 13rc'- 379-I y XR E

Full Stroke Length & Number of Handwheel Turns 7/0

Limit SwitchNumber

ZS-1

Function SetpointSee Note 4

Equivalent No. ofHandwheel Turns

ZS-2

ZS-3 CLOSE LICA1'fC

ZS-4

ZS-S

ZS-6

~ ZS-7

ZS-8

OPm urer

CW 8$PAXS'ap

0

'l75 t-

ZS-9

ZS-10

ZS-11

ZS-12

ZS-13

ZS-14

ZS-15

ZS-16

Page 33: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

~ ~ ~

~ ~ ~ ~ ~

~ ~ e

~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~

~ 0 0 ~ ~

~ ~ ~ ~

~ t ~ ~ ~ ~

Page 34: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

~ ~

~ ~ ~ ~

I I

~ ~ . ~

~ ~ ~~

~ ~ ~

~ s Il

~ ~

Page 35: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

6.0 Results Conclusions

Calc I M-VLV-%72. ~~~ 0

Page 3o of q~74I e.a-ePy q ii f-l

6.1 All available MOV Data Detail Drawing input, hasbeen researched and documented herein. Where itwas determined that information was unavailablefrom existing records, the field has been leftblank. This information will be determined duringthe as-built walkdown.

6.2 The results of the actuator sizing calculations,VOTES diagnostic acceptance criteria calculationsand limit switch setting determination are providedwithin the body of the calculation.

6.3 The following anomolies have been identifiedthrough the performance of this calculation:

Page 36: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

AnchorioarlingValve Company

701 FIRST STREETP O. BOX 3428WILLIAMSPOAT. PA 177014428(717) 327.4800TELEX; 759953

Rf z.

8- YLY- 2.72 Rtv g

P~( 3(

February 20, 1990

PENNSYLVANIA POWER & LIGHT COMPANYTwo North Ninth StreetAllentown, PA 18101

Attn: Mr. Ken Anderson, Engineering

SUBJECT: YALYE DATA

Dear Ken,

The valve data you requested at our recent meeting is enclosed,

Please advise if you need further information.

Yours sincerely,

ANCHOR/OARLIH6 VALVE COMPANY

rra vgjg(»

J V

R. W. DommersDirector - Marketing & Sales

/cll

CC:

encl.

J, J. GhappellR. J. Siout

Page 37: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

RCf 2. R-PLY-272, Ct 0 P~ c 3Z, of

eI

I )e

'I F007ll vFbc~

i rt II

II

II I

'et(r=t.'6'

I

-oW

e'I III

I~ I«

I e j-

i ltI

I

Ie t

I

llI

I'

«

I Ie

mmes

)cl I I i

e

~ il

( = eI

eg tr

19

I 37cf II ~

I~ I

«looo«rococo oo«ra«t oTooT 0%tete OTTOTC COVCO(.ttt ecaOC e« tt to

Page 38: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY
Page 39: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

~E7

JEEKMESKWRBM~ll&MRRM~REEEW~ERE~RRERREFER<R RERREFER FIRIREFER am a IElmSRREEa REF

rmnanm

lZHRF'-.

REERF~~~ER~/ 4RRRR~RIIF~

Ki

r'rr - P

RRI~~RREEF~RR~WEEW~IRtERIIFS EEL RRREaW

~ ~~

~ ~

IPEIR~~llaKRR~EEeRRRERIRR

r ~'MMXMWMI5RREEER KRRW - =

sfta~r

~ '

~

Page 40: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

I- PROSLEN OfCRIPTICNg5'w9

UNf I~I

RE8fONILSLEWORK GROUP

1 5. /Itstrs u-

/ors. /hj&E.ce3

P1-VLV-27K (sv Cl

LABAN

aC ace Oht.IaoRLISad Ip/IIILI Dao

MOOIFlCATION RELATED 0 YES Jk NO HARN

II. WORK CLASSIFICATION QUALITY +YES ASME OOOE ~ YES

0 NO ~7 ~M-EOUIPOVAL.

TECHSPEC

YESO NO

RELIABILITY CI

RELATEO

Oate

INITIAL.INPUTIII. WOAK PLANNING sTATUs iAF

A. IN'LltESTIQATION

PLANT STATUSCOOE

Oate

OItaewlone Atattonaatton Oate

B, WORK PLAN

Q~AyTAr LIES DICER,K A&klERFREO

Qvss

HPREssrIEW

YESNO

RWPMan Hra.

~D Itg~ e/Orris'7/7 fg S7+ZS'P

4 777aS

C. POST MAI TENANCE TESTING REQUIREMENTS~mI52, QQARTe6% QADI QLV Q(HQ;lQQQ~t--tqq-OZq t t Pt ILPCI STAN SutPPLX TBJQ-II

IV. ACTION TAKEN -EQUIPMENT HISTORY SUMMARY

i 56' 003

d~...|,-f .- ~I-~l-~~«-<'.~

s4:IL i 4~ ~ ~'" qLdQu shak.l ~.~c,-ss~t~rt"

Date

'7- a I.% tOate

0 a Autnonxatron Oat ~

R- 0 0 I 7 ~ 18 g g'?

HEALTH PHYSICS

C3 No HP0 HP CK.D RSVP REQUI DQ R

tII(fog7

Com pret

Wo Grou

aaty Controt Review

l0

Da e

V PROBLEM CODEcooy Yea PR08 EM 'cAUsE AcTICN PMIs

hid r" F.Operations Review Date

FORM A~02 1. Rev. 4 PART t —ORIGINAL PART 2 COPY PART 3 COPY

Page 41: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

R~g qAM%ASES WORK AIITHORIZA~~-v~v ~7z ~,'

00~ATlOH SHKKT

SWITCH VERIFICATION DATA SHEET

)Qc ~~ ef Qw

52.

VALVE TAG NO.

LIMITORQUE '"~ROPERATOR SIZE

SERIAL NO. ggggygMOTOR SIZE (FT-LBS)

OPERATOR FULL STROKE ( TURNS) 7fg 3l STROKE (4TURNS)

DESIGN T. S. SETTING: BIN. HAX.

)DESIGN) )AS FOUND) )AS LEFT)

FULL OPEN L.S. SETTING:

OPENING DIRECTION TORQUE

SMITCH BYPASS SETTING: A

LOSING DIRECTION TORQUE

SMITCH BYPASS SETTING:

T. S. SETTING (Of'):T. S. SETTING (CLOSE):

LIHITER PLATE SETTING:

CAL. CHART

NORMAL SETTING:

GAL. CHART

MAX. SETTING: ~WCQPr Hg

F onn A~A.502.2 Aer. 0 PART I ORIGINAL PART 2 COPYPD of

Page 42: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

/2~ f'5'

~-YLlf-27k J5v 0 Attachment A-Page-4-0WH-

MQTOR OPERATOR INFORMATION SHEET

LIMITQROUK ORDER NO.:

OPERATOR SERIAL NQS.:

ITEM:

-~4~95 ~ 5'f4

OPERATOR TYPE: pi~,5 OPERATOR S I ZE:

DESISN UNIT RPH <AS DEFINED IN LINITQRQUE SEL-. >: Q< 3Q

SPRINS PACK NURSER: (D~ $03- OQ 07 jNORMAL TORQUE SWITCH SETTING:

CORRESPOND ING INPUT TORQUE (LB-FT):(SEE NOTE i)

CORRESPQNDING OPERATOR OUTPUT TORQUE (LB-.-T): 5/~ r . ISS

CORRESPONDING OPERATOR OUTPUT THRUST (LBS): gg g /0 „rg.

MAXIMUM TORQUE SWITCH SETTING:

CORRESPOND ING INPUT TORQUF (LB-FT):(SEE NOTE 1)

CORRESPONDING OPERATOR OUTPUT TORQUE (LB-FT):

iVFg. ~os.

78L> FW Z!i'<

CORRESPONDING OPERATOR OUTPU~ THRUST <LBS>, ~8 f 26 ~i~ ~

GEAR RATIO INFORMATION

gROTOR PINION NUMBER OF TEETH: 3~ MORN SHAFT SEAR NQ. OF TEETI~9

g / ~ IMORN TQ MORN SEAR RATIO: 8<B L

OVERALL ACTUATOR RATIO. < > ~ j 'J

NOTE 1: INPUT TORQUE IS TORQUEHANDWHEEL ON SMB-0 AND

~LIM ITORQUE

0" <le/SS @U~O

FROM WORMSHAFT ON SMB-00 5 000 ANDFRQI'ARGER.

SIGNATURE:

Page 43: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

r6j <&-VXV-2H. <S~ g

P . 31.<

LIMITORQUE MOTOR NAMEPI ATE

ORDER NUMBER: BQ ~ 0 f ig

DATA SHEET

0.~ Q(z.lC ~ l/f'ERIALNUMBER: ~0 ~ z

MOTOR NAME PLATE DATA

IDENT IF ICATION NUMBER:

START TORQUE (LS-F.): HORSEPONERt

RUN TORQUE <LB-FT>: i.o

TYPE: FRAME: AMASS: ~~ „~ .

~OTDR BREED <RPM>: l 9'00

<>OLTS: g gQ coos

p.~.A.AMFS> ~t 85. 9

AMB C: 'fo'NSULATION CLASS: g DUTY: + tY>ZIU i

LIMITORG|UE SIGNATURE:

Q8'9/lP It] (a<>fSEg

Page 44: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

~ ~pic Z „ha7 du( il

gglll [~g ( H6fg WwK

STANDARD IIANDHIIEEL RATIOS FOR SHB a IIHB UNITS

UNITSIZE

SHB-000

II ANDNI EEL

RATIO

1$ lUNIT RATIO

hllEFF.%

100

UNITSIZE

HHB-00

HANMHEELRATIO

19 $ 1

45$ 1

UNIT RATIO

9.7-22.02 3. 0-109. 0

-EFF.a

6030

SHB-00

SHB-0SB-Q

SHB- lSs-l

SHB-2SB"2

SHB-3SB-3

SHB-4SHB-4TSB-4

SHB-5SHB-5T

1$ 1ii.38$ 1

8.93$ 121. 1$ 1

33$ 154. 1$ 1

10.75$ 125. 3$ 149.0$ 166.7$ 1

9$ 1

22. 3$ 140.5$ 157.4$ 1

7. 15$ 111.07$ 128. 37 $ 1

39.4$ 155. 36 $ 1

8. 7$ 1

13.06$ 1

33.69$ 1

39.87$ 159.13$ 1

86 $ 1)163. 5 $ 1)

142.0$ 1)269.8$ 1)

hllhll

11.2-26.126.4-96.2

102.6-150.8158.3-247

11.6-25.627.2-88.4

92.4-171.6191. 7-234

10.6-25.526.2-82.5

Si. 8-150153-212.5

11. 1-24. 125. 7-37. 343. 9-95. 598.6-132.8

138.4-186.4

13.4-32.333.6-48.451.8-124-9

131.8-147.9152.1-219-3

61.4-93.4

101.4-230.2

10095

60302525

60302525

6Q302525

6060302525

60603Q2525

25

25

NHB-0

HHB-2

IIHB-3

IIHB-4IIHB-4T

15.7$ 1

37$ 158$ 1

95$ 1

14.5$ 1

34$ 166 190$ 1

13.3$ 1

33$ 1

60 $ 1

85$ 1

10.3$ 1

16$ 141$ 1

57$ 1

80$ 1

12.7$ 1

50$ 1

58$ 1

11.2-26.126.4-96.2

102.6-150.8158. 3-247

11.6-25.627.2-88.4

92. 4-171.6191. 7-234

10.6-27.226.2-82.5

84.8-150.0153-212.5

11.1-24.125.7-37.335.9-95.5

98. 6-132. 8138. 4-186-4

10. 1-32. 340.0-124.9

131.8-147 9

«This ratio supplied when torque requiredexceeds 65 ft/lbs.

Q For SHB-5 and SllB-5T unit, this ratioprovided as standard. Alternate ratioshcwn provided only on request.

60302525

60302525

60302525

6060302525

603025

I

a

?"

O

SEL llSection 9Page 2 of 2

Page 45: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY
Page 46: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

Cg z8 vs-27z g,~ gpQ{ j j gf Cf

.Anchor/Darling Valve Company .

Williamsport, Pa.

Class 1 Valve Design Calculations1971 ASME Section III, Thru Winter 1972 Addendum

Valve Size: IO'00 L b & 7 8

Design Report No.: E 5 ~5 ~

Customer: Bechtel Power CorporationPurchase Order:Design Specification: $'F5 6- t

Valve No.: I o- E 8p - c T- @no- F oo 2 -F'o-zBR-c,>-+0-Fo03-T

Bechtel Item No.: s,l4.2

3

DATE: « Prepared By:

Checked By:

Page 47: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

Ola~p

SE

0 R

Customer:

Prepared by:

S.Q. No.

Vlv.Size, Press. 8 Type

No.Req'd 8 (Item No.)

Ref. hing. No.

ANCHOR/DARLING VALVE CO.

MOTOR OPERATOR DATA SHEET

P.O. No.

Approved

by'/3-

)3 0I 93- 19 8'OQ.

~eF F4-YLV- Z7Z Rrv'

Pge qo .Pq

ShtZ kf

Seat Hean Dia.In. 8 Area In. ~ A .7854 x4 =.7FSM H.I9 g g.332 System Design Press. PSI

3 Design Diff. Press. PSI

4 Disc Thrust LBS

5 Stem Thrust Tent. LBS

6 Stem End Thrust

7 Stuff Box Load LBS

8 Total Stem Thrust LBS

= Line Pressure ~ g= nP

Td = A x P (Line 1 x Line 3)

Use

= T = T x f (Line 4 x Coeff Friction)*2= T = .7854 x 0 x Pl (stem area x Line 2e s

= Ts

= F = Tt + Te + T (Sum of Lines 5,6 & 7)s

/ Goo

I 6/2 5'

500

9

S"VS'Coefficient

of Friction: Double Disc

Flex Medge

.2

.3V

Globe Valve 1.1

Page 48: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

4-VLY-272. Rc/ oPgc ~1 Z~>

PENNSYLVANIA POWER & . LIGHTSusauehana Steam Eleqtric $ tation

MOV - Design Bases ReviewVALVE TAG NUMBER:HV-155F003 UNIT 1 PRIORITY: 2

VALVE DWG NO.FF110100-6101 MFG. ANCHOR DARLING

DESIGN DATA

Valve Type GT

REF NO MATERIAL DIMENSIONAL DATA

Stroke Length (in) 10 '25REF NO

22Valve Size 10. 00 Stroke Time (sec)

50'ressureClassValve CodeArea/RoomElevation

600SR

28/I-202708

'',16 Stem Diameter (in)Stem Pitch (in)Stem Lead (in)

1 ~ 8750 '30.66

Orifice Diameter (in) 9.187 22

Line No. DBA-102 Stem Material A276-410T

Actuator SizeValve Oiientation

SMB-1-40

Stem Orientation RPower Supply 1D264031

Normal Valve Pos 0 Stem Mod of Elasticity 29.200Stem Mod of Rigidity 11.300Valve Thrust CapabilityDsk Guide Fac Mat SA2 16-WCBDsk Seat Surf Mat STELLZTE

2121

Rework Window OC-1, 2 & 3 - 14 DAYS (3 ~ 5 ~ 1)

DEFINITION OF SAFETY RELATED FUNCTIONHV-155F003 A NORMACONTAZNMENC'SOLATIISOLATE HPCI ON A SOVERPRESSURE AND 0ISOLATION. RC'COVERYIS NOT CLASSIFIED AS

LLY OPEN VALVE, IS THE HPCI STEAM SUPPLY LINE INBOARDON VALVE. THIS VALVES SAFETY FUNCTION IS TO CLOSE TOTEAM LINE BREAK TO PREVENT TURBINE EXHAUSTN LOW STEAM LINR PRESSURE AND PROVIDES CONTAINMENT

FROM MISPOSITIONING IS NOT REQUIRED SINCE THE VALVEPOSITION CHANGEABLE.

VALVE OPERATIONAL DATA

Max Diff PressDir Diff PressFlow RateLine Press(psigFluidProcess Temp(F)Duty CycleTime Line (sec)Envr Profile(F)Initiate SignalValve Cycle

Lrpe Brk

1030

216K1040

551

139P4

Smal BrkLOCA

1030

216K1040

551

139P4

O,C

BlackoutNA

NA

NA

NA

NA

NA

NA

NA

NA

NA

NA

HELB

1146

648K1146

563

130DP1

LOOP

NA

NA

NA

NA

NA

NA

NA

NA

NA

NA

NA

FireNA

NA

NA

NA

NA

NA

NA

NA

NA

NA

NA

InadvertOper

NA

NA

NA

NA

NA

NA

NA

NA

NA

NA

NA

Page 49: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

SNT 8Y:Xerox Telecopier 7020 : 3-2~7 : 10:55

Anchor/DarlingVatw Company

701 FIRST STAggt.O. ICN 4444WILUAQIKNT,fA 1770144%P1Q 447~TRAX'. 7QN43

FAX: (717) 327MOS

7$ 700000~ 27f 770 7d30 lN T

LV-Z7> Rcv oRcP. 1$

P~~q M2.~P ~>

Date 3 zr ~

Fax 2 ~5'- v v - 7 s s

TQ: oC peal

SUBJ: JO9

War ~oWor 0 a%

or S B

Signed:

Page 50: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

Close

lose Stroke Time 35.558 seconds

Tag Nuaber:%155FIt3.Test thawer '5

Test Date .'8/3/98

Open

Open Stroke The 34.Mi seconds

Close &pass Time 33. i96 seconds Open 8gess TiIe

tax Running Force -2639 lbs

Avg Running Force -2229 lbs

Thrust at CSI'3287 lbs

tax Ihnning Force 2K?A lbs

Avg Running Force 2286 lbs

Thrust At Disc Pullout 24863 lbs

thxiea Thrust -&75 lbs

Disc-To-Seat Thrust at (Zl'-3959i lbs Torque %itch Setting (0/C) 3,II/38

high packing load on opening stroke. Thrust target Iet.

Torque Switch Settinq Open/Close.....Limit Switch Rotor Adjustment (Y/N). ~

Flow (gpm) Start/Finish..............Upst'ream Pressure (psi) St@1 t/Fi11ish.Downstream Pressure (psi) Start/finisGeneral Comments:hxgh packing load on opening stroke.

3. 888/3. 888~ ~ ~ ~ 0 0 ~ ~ ~

8/ 88/ 88/ 8

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0

~ ~ ~ ~ ~ ~ ~

h ~ ~ ~ ~ ~ ~

~ ~ ~

~ ~ ~ ~

Th'rust ta'rget met.

Va 1 ve In fo'rma t ion Valve Actuato'r Actuator RotorPlant SUSQUEHANNAUnit 1

Tag Number HV155F883GATE

Size 18Target Thrust 36829 lbsOrientation HORZLocation EL/683 RHI-282Stem blate'rial A276-418Stem Diameter 1.875 inchesThreads ne'r in. 3.88Elasticity(1.8E6) 29.288 psiPoissons Ratio 8.388LeadVOTES Serial ¹ A3857

eValve Calibration 1.548E-8882 pv/v/lb

Actuator Type LIPllSize SPlB/2Wax Thrust Rate. 78888 lbsSe.rial ¹0'rde'r ¹¹ Worm Gear TeethGear RatioSpring Pack ¹ 8887

Voltage (AC/DC) DCVolts 258Amp 'rating 11.88 ampsNominal Speed 1988.88 rpSta'rt torque 25 '8 ft-IRun Torque 5.88 ft-IHorse Powe1 2.98 h.p.

Signal Conditione1 Calibration Due Date 9/29/98Votes Fo'rce Offset: -2151 lbs

Page 51: Nuclear Regulatory Commission · 2018. 1. 30. · ~ ~ ~ CALCULATION COVER SHEET CALC. No.!~-~~-Zq2. FILE NO. R2 +~ SUPERSEDED BY SAFETY-RELATED f)c ASME III OR XI f OTHER QUALITY

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