Text

Responds to RAI Re GL 95-07, Pressure Locking and Thermal Binding of Safety-Related Power Operated Gate Valves
	ML20116G254
Person / Time
Site:	Summer
Issue date:	08/02/1996
From:	Gabe Taylor; SOUTH CAROLINA ELECTRIC & GAS CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	GL-95-07, GL-95-7, RC-96-0182, RC-96-182, NUDOCS 9608080036
	Download: ML20116G254 (127)
	v • d • e

4 South Carolina Eltetric & GIs Comp:ny Gary J. Taylor Jenkinsville, SC 29065 Nuclear Operations (803) 345-4344 j SCEArG escence August 2,1996 RC-96-0182 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Gentlemen:

Subject:

VIRGIL C. SU MMER NUCLEAR STATION (VCSNS)

DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 REQUEST FOR ADDITIONALINFr ATION - GENERIC LETTER j 95-07," PRESSURE LOCKING AN ;.ERMAL BINDING OF SAFETY-RELATED POWER OPERAi ED GATC VALVES" OF JULY 3, 1996 Pursuantio the NRC's request for additional information on the subject Generic Letter, South Carolina Electric & Gas Company (SCE &G) is submitting the attached documentation under oath of affirmation.

, Should you have any questions, please call Mr. Jeffrey W. Pease, at (803) 345-4124.

Very truly yours, 4

GaryJ.Ta or JWP/GJT/ews Enclosures (5) c: J. L. Skolds NRC Resident Inspector J. B. Knotts, Jr.

W.F. Conway(w/o enclosures)

R. R. Mahan NSRC l R. J. White File (815.14) '

A. R. Johnson RTS (LTR950007) i S. D. Ebneter DMS (RC-96-0182) l 4

9608080036 960802 PDR ADOCK 05000395 P PDR

Docum:nt Contrcl Desk LTR 950007 RC-96-0182 Page 2 of 2 STATE OF SOUTHCAROLINA :

TO WIT :

COUNTY OF FAIRFIELD :

Ihereby certify that on the N day of 4. /7 19 f[,before me, the subscriber, personally appeared Thomas H. Taylor, beidduly sworn, states that he is acting for j the Vice President, Nuclear Operations of the South Carolina Electric & Gas <

Company, a corporation of the State ofSouth Carolina, that he provides the foregoing response for the purposes therein set forth, that the statements made are true and correct to the best of his knowledge, information, and belief, and that he was authorized to provide the response on behalf of said Corporation.

I WITNESS my Hand and Notarial Seal ca. A"--

yublic for South Carolina My Commission Expires 7- 2/-200 f ,

Date !

I NUCLEAR EXCELLENCE- A SUMMER TRADITION!

Enclosure 1 Rc-96-0182 Page 1 VCSNS RESPONSE TO THE REQUEST FOR ADDITIONAL INFORMATION CONCERNING THE STATIONS INITIAL GENERIC i LETTER 95-07 " PRESSURE LOCKING AND THERMAL BINDING l

OF SAFETY-RELATED POWER-OPERATED GATE VALVES" SUBMITTAL.

PURPOSE:

This enclosure provides the additional information requested in part 1 of the enclosure to the NRC letter to Mr. Taylor, dated July 3, 1996 (REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER 95-07,

" PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER OPERATED GATE VALVES," VIRGIL C. SUMMER NUCLEAR STATION (TAC NO.

M93525).

ADDITIONAL INFORMATION REQUESTED:

1. "Regarding the following valves:

1 8000 A/B/C Pres.surizer PORV Block !

8801 A/B High Head Injection to RCS Cold Legs !

8884 High Head Safety Injection to RCS Hot Legs 8885 Alternate HHSI to RCS Cold Legs 8886 HHSI to RCS Hot Leg =

l the licensee's submittal states that a hydraulic pressure locking analysis consistent with the Commonwealth Edison methodology has shown that these valves have sufficient opening thrust capability to overcome the postulated pressure locking forces. Please provide these thrust requirement and actuator capability calculations for our review".

VCSNS ADDITIONAL INFORMATION:

The requested pressure locking (PL) thrust requirement and the applicable portions of the actuator capability calculations are attached as follows:

8000 A/B/C Actuator capability calculation - Attachment #I 8000 A/B/C PL thrust requirement calculation - Attachment # III 8801 A/B Actuator capability calculation - Attachment # II 8801 A/B PL thrust requirement calculation - Attachment # IV 8884 Actuator capability calculation - Attachment # II

Enclosure 1 RC-96-0182 Page 2 8884 PL thrust requirement calculation - Attachment # V 8885 Actuator capability calculation - Attachment # II 8885 PL thrust requirement calculation - Attachment # VI 8886 Actuator capability calculation - Attachment # II 8886 PL thrust requirement calculation - Attachment # V '

l 1

1 Enclosure 1, Attachment I RC-96-0182, Page 1 of 15 ES-412 ATTACHMENT I REVISION 1 PAGE 1 OF 2 SUBJECT CODE 15':L SOUTH CAROLINA ELEC6 tdC AND GAS COMPANY PAGE CALCULATION RECORD 1 OF CALC TITLE; Dedicyo,3ediew o, vel CALC NO REV

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ME SCE+G -DF :f-I-% V/A A. CALCULATION INFORMATION CONTENT DESCRIPTION: Wisim %> CC, EF, VS, VW, MS, 'EC,59 + SW 5ys4 - 5 H0V Sehe Wi

An cucu COMPONENTS /ANALYS!S: \ jai!.xus %\Krsp~d %VKs/fje arga}yse3

'trnpcud.ed CONTAINS PRELIMINARY DATA /ASSUM3TIONS:

E NO O YES,PAGES COMPLTi'ER PRO 3ilAM USED: 8 ND D YES, VALIDATION NOT REO'D IREF.3.5) D YES, VAUDATED [OTHERS]

O YES. vAuoATED TES-412) O PRO 3 RAM VALIDATION CALCULATION E. VERI:tCATIDN O CONilNUED, ATTACHMENT VERI:lOATION SOO?Ey\JWS per FS- H D repe-4.5 a ~ d h e.

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VER1RER: Vlabr,TfE .. O '/ '

ASSIGN BY: Escs, B.T- tb b I ,u w 6-/-95 LEAD EN31NEER (DESl3N==)/DATE VERlRER/DATE A?PROV ' - TE N/ #

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C. RECORDS REEL NUMBEPc FRAME NUMBER:

TO PRS:

ORl31NAL MAINTAINED EY:

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PDE /SYdi:M EN3 Ew:2/e.::r_~rnex tr,eaan : DE RLE 20.6602 ATTACH.1 ONLY. CO?Y)

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Enclosure 1, Attachment I RC-96-0182, Page 2 of 15 i

ES-412 l ATTACHMENT l i

REVISION 1 PAGE2OF2 SOUTH CAROLINA ELEGI MIC & GAS COMPANY PAGE REVISION

SUMMARY

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SUMMARY

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ES4:2/ATTACHM9fiVREVIS10N 1 O CONTINUES ON PAGE

1

. . 1 Enclosure 1, Attachment I l RC-96-0182, Paga 3 of 15 1.0 PURPOSE This calculation will determine the motor operator capability in botl the open and close directions, provide torque bands, thrust bands anc control switch setpoint recommendations for rising stem GL 89-10 MOVs as well as additional important to safety MOVs per ref. 2.32 in the following systems:

Component Cooling (CC) Reactor Coolant (RC) i Emergency Feedwater (EF) Reactor Building Spray (SP) I Fire Service (FS) Service Water (SW) !

Feedwater (FW)

Main Steam (MS)

?

Valves tag numbers in section 2.6 marked with an asterisk are not within the scope of GL-89-10.

Motor operator capability determination can serve several purposes:

1. Determine motor operator capability - Minimum operator capability is defined as the output torque and thrust the operator is capable of producing under design basis conditions independent of control switch setting.

2. Determine the limiting thrus and torque values for the MOV to protect it from overthrust, overtorque and locked rotor conditions.

3. To indicate overall MOV adequacy to operate at design basis conditions prior to diagnostic testing.

4. Recommend the configuration of control switches based on minimum required thrust calcula ions and most limiting stress and/or thrust

value of the MDV in both the opening and closing directions without compromising MDV iritegrity.

5. Can be used as a basis for recommanding motor operator reconfiguration where thrast/:orque capability is determined to be -

less than adequate to overcome design basis thrust requirements.

2.O REFERENCES 2.1 Limitorque correspondence:

id 2.1 1 mitorque letter from Dominick Giangua]ano to Mr. E.N.

Goldstein of Gilber- Commonwealth regarding P.O. 233617, including corrected Limitorque data sheets, dated 6/9/EE 4.1.9 gm'. torque letter from .3. Drab to E.N. Goldstein !

c: Gi.wert Commonwealth regarding P.O. 23054*?,

incluc:.ng Limitorgae data sheets, dated 5/20/E7 2.1.;

simitorque letter from Mr. M. Bailey to Mr. Barry I Norcutt of SCE&G regarding Limitorque Actuator Torque and Thrust Ratings, dated 10/2/91 2 DC01520-065

Enclosure 1, Attachmsnt I RC-96-0182, Pags 4 of 15

- 2.2 Limitorque Documents 2.2.1 SEL-1, dated 5/21/79 2.2.2 SEL-2, dated 7/1/77 2.2.3 SEL-3, page 1 of 4, dated 5/21/79 SEL-3, page 2 of 4, dated 12/15/75 SEL-3, page 3 of 4, dated 2/26/79 SEL-3, page 4 of 4, dated 7/1/77 2.2.4 SEL-4, dated 7/1/77 2.2.5 SEI-5, dated 11/9/88 2.2.6 SEL-7, dated 11/89 2.2.7 SEL-9, dated 6/2/75 2.2.8 900-00003, dated 3/88 2.2.9 900-00004, dated 3/88 2.2.10 Technical Update 92-02, dated 10/9/92 2.2.11 Technical Update 93-01, dated 6/8/93 2.2.12 Potential 10CFR21 Condition Reliance 3 Phase Limitorque Corporation Actuator Motors, dated' 5/13/93 and Technical Update 93-03, dated 11/93 2.2.13 Technical Update 92-01, dated 2/28/92 2.2.14 Maintenance Update 92-01, dated 2/27/92 2.3 EPRI Documents 2.3.1 EPRI Application Guide for Motor Operated Valves in Nuclear Power Plants NP-6660-d, Final Report, dated March 1990 2.3.2 EPRI MOV PPP MOV Margin Improvement Guide TR-100449,

. Dated February 1992 2.4 Le .ter CGE-91-104 8 from J.C. Snelson to R.J. Waselus, Motor Operated Valve Data Sheets for V.C. Summer including attachment 2.5 Westinghouse E-Spec. 678852, Rev. 2, dated 3/14/77 2.6 Valve assembly dradings: Valve to drawing traceability confirmed through references 2.4 and 2.9.

Valve Vendor Dwc. VCSNS Dwc. Elementary 1 XVG-9568-CC 3316-3, Rev. C 1F3-25-222-3 E-208-011 CC-18 R6A i XVG-9600-CC 3299-3, Rev. D IMS-25-206-4 E-208-011 CC-24 R63 l XVG-9605-CC 3319-3, Rev. C 1MS-25-225-3 E-208-011 CC-25 R6A XVG-9606-CC 3320-3, Rev. C l 1MS-25-226-3 E-208-011 CC-26 R6 i XVG-9625-CC 3318-3, Rev. C IMS-25-224-3 E-208-011 CC-29 R3A !

XVG-9626-CC 3318-3, Rev. C iMS-25-224-3 E-208-011 CC-29 R3A XVG-1001A-EF 3316-3, Rev. C 1MS-25-222-3 E-208-032 EF-03 R7 XVG-10015-EF 3316-3, Rev. C 1MS-25-222-3 E-208-032 EF-04 E7 XVG-1002-EF 3318-3, Rev. C 1MS-25-224-3 E-208-032 EF-05 R7 XVG-1008-EF 3318-3, Rev. C 1MS-25-224-3 E-208-032 EF-06 R7 XVG-1037A-EF 3318-3, Rev. C 1MS-25-224-3 E-208-032 EF-07 E9 XVG-10375-EF 3318-3, Rev. C 1MS-25-224-3 E-208-032 EF-OS E9A XVG-679~-FS 3558-3, Rev. C 1MS-25-498-3 E-208-044 FS-01 R5 XVK-1633A-FW ACD-31602315, R 1G 1MS-25-647-1 E-208-045 FW-41 R5 XVK-16333-FW ACD-31602315, R 1G IMS-25-647-1 E-208-045 FW-42 R5 XVK-1633C-FW ACD-31602315, R 1G 1MS-25-647-1 3-208-045 FW-43 R5 4 DC01520-065

1.

Enclosure 1, Attachm:nt I RC-96-0182, Page 5 of 15 l Valve Vendor Dwc. VCSNS Dwo. Elementarv XVG-2802A-MS 93-14372, Rev. 0 1MS-25-618-0 l

XVG-2802B-MS 93-14372, Rev. 0 B-208-067 MS-01 R10A 1MS-25-618-0 B-208-067 MS-02 R9A XVT-2813-MS* ACD-31602299, R.1 1MS-25-552-1 B-208-067 MS-04 R13 XVG-8000A-RC 115E075, Rev. 7 1P3-25-115-3 XVG-8000B-RC 115E075, Rev. 7 3-208-082 RC-10 R7A 1MS-25-115-3 B-208-082 RC-11 R7A XVG-8000C-RC 115E075, Rev. 7 1MS-25-115-3 XVT-8095A-RC* E-191790, Rev. 3 B-208-082 RC-12 R7A 1MS-25-793-2 B-208-082 RC-14 R4 XVT-8095B-RC* E-191790, Rev. 3 1MS-25-793-2 XVT-8096A-RC* E-191790, Rev. 3 B-208-082 RC-15 R4 1MS-25-793-2 B-208-082 RC-17 R3 XVT-80963-RC* E-191790, Rev. 3 1MS-25-793-2 B-208-082 RC-16 R4 XVG-3001A-SP 3329-3, Rev. D IMS-25-233-2 XVG-30013-SP 3329-3, Rev. D 3-208-097 SP-03 RSA IMS-25-233-2 3-208-097 SP-04 R8A XVG-3002A-SP 3304-3, Rev. E 1MS-25-211-3 XVG-3002B-SP 3304-3, Rev. E B-208-097 SP-05 R9A 1MS-25-211-3 3-208-097 SP-06 R9A XVG-3003A-SP 3336-3, Rev. C 1MS-25-237-3 XVG-30033-SP 3336-3, Rev. C 3-208-097 SP-07 R9A 1MS-25-237-3 3-208-097 SP-08 R9A XVG-3004A-SP 3328-3, Rev. I 1MS-25-232-5 XVG-30043-SP 3328-3, Rev. E 3-208-097 SP-09 R8 IMS-25-232-5 3-208-097 SP-10 R8 XVG-3005A-SP 3330-3, Rev. D IMS-25-233-2 XVG-30053-SP 3330-3, Rev. D 3-208-097 SP-11 R9 IMS-25-233-2 3-208-097 SP-12 R7 XVG-3103A-SW 3331-3, Rev. 3 iMS-25-291-2 XVG-31033-SW 3331-3, Rev. 3 3-208-101 SW-23 R6A 1MS-25-291-2 3-208-101 SW-24 R6A XVG-3107A-SW .3332-3, Rev. 3 1MS-25-292-2 XVG-31073-SW 3332-3, Rev. 3 3-208-101 SW-27 R73 1MS-25-292-2 3-208-101 SW-28 R7C !

XVG-3108A-SW 3325-3, Rev. D IMS-25-230-4 XVG-31083-SW 3325-3, Rev. D 3-208-101 SW-29 R4A IMS-25-230-4 3-208-101 SW-30 R4A i XVG-3108C-SW 3325-3, Rev. D IMS-25-230-4 XVG-310BD-SW 3325-3, Rev. D 3-208-101 SW-31 R4A 1MS-25-230-4 3-208-101 SW-32 R4A l XVG-3109A-SW 3 325-3, Rev. D IMS-25-230-4 XVG-31093-SW 3325-3, Rev. D 3-208-101 SW-33 R5A I IMS-25-230-4 3-208-101 SW-34 R5A i XVG-3109C-SW 3325-3, Rev. D IMS-25-230-4 XVG-3109D-SW 3325-3, Rev. D 3-208-101 SW-35 R5A :

IMS-25-230-4 3-208-101 SW-36 RSA {

XVG-3111A-SW 3327-3, Rev. 3 1MS-25-290-2 XVG-31113-SW 3327-3, Rev. 3 3-208-101 SW-39 R5A 1MS-25-290-2 3-208-101 SW-40 RSA XVG-3112A-SW 3327-3, Rev. 3 1MS-25-290-2 XVG-31123-SW 2327-3, Rev. 3 3-208-101 SW-41 R63 1MS-25-290-2 3-208-101 SW-42 R6A

2.7 Correspondence

Gilbert / Commonwealth letter CGGW-1896 to Westinghouse, datad 3/17/83

2.8 Correspondence

Westinghouse letter CGE-83-678 to G.J. Braddick i of Gilbert / Commonwealth, dated 5/13/83 2.9 Minimum Required Thrust Calculations 2.9.1 DC01520-060 Rev. 3, Minimum Required Thrust For GL 89-10 MDVs in the CC System 2.9.2 DC01520-057 Rev. 3, Minimum Required Thrust For GL 89-10 MDVs in the ET System 5 DC01520-065

Enclosurs 1, Attachmtnt I RC-96-0182, Pagn 6 of 15 2.9.3 DC01520-064 Rev. 2, Minimum Required Thrust For GL 89-10

'MOVs in the FS System 2.9.4 DC01520-055 Rev. 2, Minimum Required Thrust For GL 89-10 MOVs in the FW System ,

I 2.9.5 DC01520-056 Rev. 4, Minimum Required Thrust For GL 89-10 !

MOVs in the MS System !

ji 2.9.6 DC01520-062 Rev. 4, Minimum Required Thrust For GL 89-10 l

MOVs in the RC System :

2.9.7 DC01520-063 Rev. 3, Minimum Required Thrust For GL 89-10 MOVs in the SP System I

2.9.8 DC01520-058 Rev. 4, Minimum Required Thrust For GL 89-10 I MOVs in the SW System 2.10 specification for Electric Motor Valve Actuators, V.C. Summer Nuclear Station, (SP-3 09-22 61-00) , dated 10/1/71 2.11 Correspondence: Westinghouse letter from R.J. Faix to Mr.

C.A. Price of SCE&G, CGWS-1184, dated 5/7/81 2.12 USNRC IE3 81-02, dated 4/9/81 and IE3 81-02 Supplement 1, dated 8/18/81; " Failure of Gate Valves to Close Under Differential Pressure" 2.13 Correspondence: Westinghouse letter from R.J. Faix to Mr.

C.A. Price of SCE&G, CGWS-2013, dated 6/11/81 1

2.14 Correspondence: Westinghouse letter from R.J. Faix to Mr.

C.A. Price of SCE&G, CGWS-2125, dated 11/12/81 2.15 Correspondence: SCE&G 1etter from T.C. Nichols to NRC Director James P. Reilly, dated 7/7/81 2.16 Correspondence: Westinghouse letter to R.B. Clary of SCE&G, CGE- 90-1061, dated 4/4/90. Valve allowables and new limitorque thrust rating for SE-00 and SSD-00 actuators provided with Westinghouse valves 2.17 DC0820-003, Rev. 4, Class 1E 460V MDV Starting Voltages at Degraded Voltage Conditions 2.18 Correspondence: Westinghouse letter from R.J. Faix to Mr.

C.A. Price of SCE&G, CGWS-2371, dated 12/15/82 Field Change Notice FCN-CGE-10634 l l

2.19 V.C. Summer Nuclear Station Equipment Qualification Data Base 2.20 S-021-018, Environmental Zone Information 2.21 EEL 3/MSLB Evaluation, Report 2616, Rev. 7 2.22 V.C. Summer Nuclear Station Surveillance Test Procedures 6 DC01520-065

I

. Enclosure 1, Attachment I 2.23 MOV Weak Link Calculations 2.23.1 DC01520-050, Rev. 1, MOV Weak Link Analyses 2.23.2 DC01520-070, Rev. O, Maximum Allowable Thrust Analysis i Report B.O.M. RNn4 (XVG09605-CC) l 2.23.3 DC01520-071, Rev. O, Maximum Allowable Thrust Analysis Report B.O.M. RNn16 (XVG03003A, B-SP) 2.23.4 DC01520-072, Rev. O, Maximum Allowable Thrust Analysis Report B.O.M. RNn17 (XVG03005A,B-SP) 2.23.5 DC01520-073, Rev. O, Maximum Allowable Thrust Analysis Report B.O.M. RNn18 (XVG03001A,B-SP) 2.23.6 DC01520-074, Rev. O, Maximum Allowable Thrust Analysis. .

Report B.O.M. RNn30 (XVG09568-CC, XVG09606-CC) 2.23.7 DC01520-075, Rev. O, Maximum Allowable Thrust Analysis Report 3.0.M. RNg25 (XVG09625-CC, XVG09626-CC, XVG01002-EF, XVG01008-EF, XVG01037A-EF, XVG010373-EF) 2.23.8 DC01520-076, Rev. 1, Maximum Allowable Thrust Analysis Report B.O.M. RNg19 (XVG03111A, B-SW, XVG03112A, B-SW) 2.23.9 DC01520-077, Rev. O, Maximum Allowable Thrust Analysis Report 3.0.M. RNn14 (XVG03103A, B-SW) 2.23.10 DC01520-078, Rev. O, Maximum Allowable Thrust Analysis

,. Report 3.0.M. RNg20 (XVG03107A,3-SW) 2.23.11 DC01520-079, Rev. O, Maximum Allowab2e Thrust Analysis Report 3.0.M. RNg21 (XVG03 002A,3-SP ',

2.23.12 D001520-080, Rev. O, Maximum Allowable Thrust Analysis Report 3.O.M. RNg24 (XVG01001A, E-EF) 2.23.13 DC01520-081, Rev. 1, Max. Allowable Thrust Analysis I:

Report B.O.M. RNn13 (XVG0310 BA, E, C, D-SW, XVG03109A,3, C, D-SW) 2.23.14 DC01520-082, Rev. O, Maximum Allowable Thrust Analysis Report 3.0.M. RNn5 (XVG09600-CC) 2.23.15 DC01520-083, Rev. O, Maximum Allowable Thrust Analysis Report 3.0.M. RNn21 (>NG 03 004A, E-SP )

2.23.16 DC01520-084, Rev. O, Maximum Allowable Thrust Analysis Report 3.0.M. RNn40 (XVG067 97-FS) 2.23.17 DC01520-085, Rev. 1, Maximum Allowable Thrust Analysis Report E.O.M. RNn7 (XVG02802A, E-MS )

2.23.18 DC01520-087, Rev. O, Maximum Allowable Thrust Analysis Report E.O.M. RNn8 & RNg10 (XVK01633A,3,C-FW, XVT02813-MS) 2.23.19 DC01520-088, Rev. 1, Maximum Allowable Thrust Analysis Report 3.O.M. RNul (XVT08 095A, E-RC, XVT08096A,E-RC) 7 DC01520-065

1 Enclosure 1 Attachment I RC-96-0182., Pege 8 of 15 l 2.24 VCSNS GL 89-10 Actuator Refurbishment Packages

~

2.25 MRF 21745 MCN C \

2.26 MRF 21745 MCN G I l

2.27 Reactor Building Design Basis Document, Rev. 4 2.28 MRF 21745 MCN H 2.29 MRF 22362 2.30 MRF 21745 MCN I 2.31 Kalsi Engineering Inc. Documents 2.31.1 :,

Thrust Rating Increase of Limitorque SB-00 Through i SS-2 Spring Compensator Assemblies and SB-00 through 2.31.2 SE-1 Actuators, Document No. 1707C, Rev. O, dated 11-25-91 Thrust Rating Increase of Limitorque SMS-000, SMB-00, SMB-0 and SMB-1 Actuators, Document No. 1707C, Rev. O, dated 11-25-91 2.31.3 Fastener Analysis: Limitorque Operator Mount and Housing Cover, Document No. 1759C, Rev. O, dated 12-7-93 2.32 DC01520-089, Rev. 2, Justifications GL 89-10 MOV Scope, Grouping and Engineering ;

3.0 ASSUMPTIONS 3.1 Spring pac'k limitations will not be considered as an operator limiting component.

3.2 The maximum ambient temperature for which operation of XVG08000A,3,C-RC is required is the Reactor Building design I

temperature of 283*F (140*C) (ref. 2.27) . This is considered reasonable as the design function of these MDvs is to isolate a !

stuck open pressurizer PORV. From a Reactor Building peak I temperature perspective, the most limiting high energy line break for which PORV actuation is reasonable (i.e., RCS pressure ;

increase) is a Feedwater Line Break Inside Containment (FWLBIC) .

The R3 pressure and temperature analysis do not specifically address the FWLEIC as it results in less energy input to the F3 than a Main Steam Line Break (i . e . , the feedwater is subcooled).

As there are no post-FWISIC R3 temperature profiles, the design temperature of 283*F will be used.

Please note that these MOVs' EQ protective category of C1,C2 indicates that their operation in a steam environment is not required.

3.3 The maximum stem to stem nut coefficient of friction during maximum MDV DP loads is less than or equal to 0.15 based on VCSNS l experience, unless otherwise specified.

4.O METHODOLOGY This calculation will determine the mininum MDV capability. These limitations can be based on degraded voltage actuator capability, actuator thrust ratings, actuator torque ratings and/or valve structural l

limitations (reference 2.23) .

8 DC01520-065 1

Enclosure 1, Attachmant I RC-96-0182, Page 9 of 15 4.1 The basic actuator degraded voltage capability equation and methodolcgy are given below.

l ACTUATOR NOM.

OPEN =

MOTOR

MTT

OCR

PULLOUT ETr .

APP. TACTCR * (%DT TULL VOLTAGE /100)'

TOROUE TOROUE ACTUATOR l OPEN =

ACTUATOR OPEN TORDUE/ STEM TACTOR f 0.15 (Unless otherwise specified)

TERUST l ACTUATOR NOM.

CLosE =

HOTOR

M'"T

OCR

RUN ETT.

APP. TACTOR * (% OT TULL VOLTACE/100)' l TORQUE TORQUE l ACTUATOR CLOSE =

AC*UATOR CLOSE TOROUI/ STIM TACTOR t 0.15 (Unless otherwise specified)

TERUST ACTUATOR NOM.

STALL = MOTOR

0;R

STALL ITT.

1.1 TOROUI TORQUE */

Both the motor torque factor and undervoltage factor are affected by temperature as discussed in reference 2.2.12. The maximum allowable stroke time (MU S.T.) for each MOV was determined by a review of reference 2.22. This information is then used to determine the !

temperature increase internal to the motor per the guidance of ref.

2.2.12. The maximum ambient temperature for which MOV operation is required is determined by a review of references 2.19, 2. 2 0 and 2. 21. l Once this data has been acquired, the internal temperature rise due to I MOV operation is added to the worst case ambient temp. (MAOT) for which MOV operation is required. Note that for position changeable MOVs, the motor torque loss from internal heat generation due to 'two MOV strokes l (mispositioning and recovery) is used rather than the heat generation for one stroke.. This total temperature is then used a determination of the overall temperature effect on motor torque reauction and motor locked rotor current reduction per Ref. 2.2.12. The locked rotor current reduction (MCF) is an input to ref. 2.17. The motor torque '

reduction (MTF) is used in the overall actuator capability calculation as shown above. The general equations for MCF and MTF are given below (ref. 2.2.12). Note thct the % Current Loss (MCM) and % Torque Loss

(!CM) from 25'C to 180*C are motor sire and speed specific per reference 2.2.12.

l MI'F = 1 - (MAOT + 2 * (0.1 sec.

75 C/10 sec. + MAX S.T. 75*CS00 sec.)- 40 C)

MTM/155 MCF = 1 - (MAOT + 0.1 sec.

75*C/10 sec. + MAX S.T.

75 CB00 sec. - 40 C)

MCM/155 i

The Unit Efficiency is a function of actuator sire, actuator overall ratio, closure control method, and stroke direction. Pullout efficiency is used for the valve opening per references 2.2.6 and 2.2.10. MOV closure control method is based on a review of reference 2.6 elementary l

diagrams. Running efficiency is used for the closing stroke per ref.

2.3.2. Running efficiency is justified in the closing direction as the initial loads are small enough to allow the entire drive train to reach rated speed per ref. 2.3.2. Stall efficiency is from reference 2.2.6.

The Application Factor (AF) is a function of minimum motor terminal voltage per ref. 2.2.12. For minimum motor terminal voltage of less than 90%, the AF is 1.0. For cases where the minimum motor terminal voltage is greater than or equal to 90%, the AF is 0.9.

9 DC01520-065

i Enclosure 1, Attachment I RC-96-0182, Page 10 of 15 Note that all MOV applications are for temperatures considerably less than 900*F and per ref. 2.2.5 do not require an AF of 0.8.

The Undervoltage Factor is also a function of minimum motor terminal voltage as stated in references 2.2.10 and 2.2.12. For minimum motor terminal voltage of less than 90%, the Undervoltage Factor is the actual percentage of rated motor voltage (4 60VAC) squared. For cases where the minimum motor terminal voltage is greater than or equal to 90%,

the Undervoltage Factor is 1.0. The motor terminal voltage values are from reference 2.17.

Stem factors are from reference 2.2.9 based on reference 2.6 data.

An MOV is considered position changeable unless it cannot be mispositioned from the Main Control Board, has a power lockout switch '

which allows MOV electrical operation for specific operations only or has its circuit breaker locked in the open position.

4.2 Standard actuator thrust ratings are from reference 2.2.7 with the exception of Westinghouse supplied SE-00 and SBD-00 actuators which have a maximum thrust rating of 16,000 lbf. (ref. 2.16) . The standard thrust rating for SMB-000, SME-00, SMS-0 and SMB-1 actuators may be increased to 140% of the standard thrust rating per reference 2.2.13 with the number of cycles at this increased thrust rating not to exceed 2000. Trarust values greater than 140%

of the standard rating are allowed pe: Ref. 2.31 testing only as stated throughout this calculation.

4.3 Standard a'ctuator torque ratings are from reference 2.2.7 and are dependent on OGR for a given size actua*or. The standard torque ratings may be exceeded by as much as 2D5 for a limited number of cycles (100) per reference 2.1.3. The standard actuator torque ratings may be exceeded by 100% for one cycle per reference 2.2.14.

4.4 Valve open and close thrust limitations are from reference 2.23.

4.5 Valve minimum recuired thrust values are from reference 2.9.

4.6 The limiting torque and thrust values in this calculation do not include diagnostic test equipment accuracy allowances.

4.7 This calculation does not evaluate torque switch / spring pack capabilities and/or limitations. Full spring pack compression must be avoided for torque controlled MOVs. Torque switch settings must be below the lesser of the actuator torque rating, actuator degraded voltage capability, and spring pack limitations.

4.8 Results of the minimum actuator torque and thrust capabilities are compared to the actuatcr torque and thrust ratings to determine which is more limiting.

10 DC01520-065 l

l

Enclosure 1, Attachmsnt I RC-96-0182, Page 11 of 15 4.9 The most limiting of the minimum actuator capabilities and ratings are then compared to the valve allowables to verify that the valve will not be damaged due to improper actuator configuration.

4.10 Thrust and torque bands are then developed as follows; Minimum Required Thrust = Min. Required Thrust per ref. 2.9.

Maximum Thrust at CST = Minimum of the actu'ator capability determination. Total thrust cannot exceed valve allowable or actuator ratino (includinc inertia)

Maximum Torque at CST = Minimum of the actuator capability .

determination. Total torcue cannot exceed actuator ratino (includinc inertia)

NOTE: Diacncstic equipment error is not factored into the torcue and thrust band values above.

4.11 Where it is determined that actuator capability is less than the minimum required thrust or if the minimum required thrust is greater than the actuator rating, recommendations are made to reconfigure the actuator to overcome limitations and provide an adequate margin to overcome minimum required thrust without compromising the MOV integrity.

4.12 Control Switch Recommendations Control switch configuration is determined only when an acceptable torque and thrust band is available. Minimum torque and thrust capabilities should be greater than minimum required torque and thrust with diagnostic equipment error included. Recommendations are based on calculated results.

Control Switch Trip (CST) is considered to be the torque switch actuation in the open direction with the open limit providing primary valve control.

CST for the closing stroke is either close limit or close torque switch actuation depending on the design of the individual MDV.

4.13 Limit Svitch Control Open The open limit switch will be adjusted to prevent backseating.

Typically, this setting approximates 90 to 95% of stroke from the fully c1csed position but may be varied due to inertia of the M3V, motor design, and contactor drop-out time.

11 DC01520-065

1 Enclosure 1, Attachmant I RC-96-0182, Page 12 of 15 4.14 Limit Switch Control Close In cases where minimum required thrust is very close to maximum rating or allowable, and/or high inertia is present, the MOV may be set for limit closure. Actuator will be configured to trip the 4 motor on limit and coast the disk into the seat to achieve an I acceptable thrust. I 4.15 Torque Switch Control Open Primary torque switch control in the opening direction is not recommended. Backup torque switch protection is provided in case of limit failure.

4.16 Torque Switch Control Close i

Recommendation for torque switch control in the closing direction {

is based on the torque and thrust bands established in the body of the calculation. Torque switch trip must be set at a value greater than the minimum required torque and thrust (including equipment ;

error) and less than the lesser of the actuator rating, valve '

allowable or actuator degraded voltage capability. This will assure the disk is properly seated and that the torque developed is great enough to trip the motor prior to overthrust conditions.

4.17 Close to Open Torque Switch Bypass Close to 0 pen (C/0) torque switch bypass will be set to bypass a minimum of 20 to 25% of disk travel time with the torque switch in the open circuit. This will ensure the open torque switch is l

bypassed for the highest M3V loads in the open direction.

I 4.18 Open to Close Torque, Switch Bypass

(

i Open to Close (0/C) torque switch bypass will be set to bypass the' close torque switch sufficiently to assure flow cutoff l (i . e . , disc over seat rings) while having the close torque switch in the control circuit prior to hard seat contact.

This will ensure the valve cuts off flow while limitinc the l total seating thrust, including inertial effects. This setup i

is not recommended for valves which are required to be leak tight.

4.19 The use of the tested stem factor, tested packing load and 2004 actuator torque rating is required only to address recovery from inadvertent mispositioning which is expected to no longer be an issue for PWRs with the issue of Supplement 7 to GL 8 9-10.

, This applies to valves XVG03103A-SW and XVG031033-SW.

12 DC01520-065

Enclosure 1, Attachment I XVG-8000A-RC RC-96-0182, Page 13 of 15 VALVE MFG. WESTINGHOUSE STEM DIA. 1.250 in.

VALVE TYPE FLEX WEDGE GATE STEM PITCH 0.333 in.

VALVE SIZE 3. 00 in. STEM LEAD 0.333 in.

STEM FACTOR @ 0.20 0.0140' DWG. NO. 1MS-25-115-3 STEM FACTOR @ 0.15 0.0116' MAX. S.T. 10 sec.

VALVE OPEN ALL. 23995 lbf. VALVE ID 3GM88FNH t VALVE CLOSE ALL. 24922 lbf. MAOT 14 0*C POSITION CHANGEABLE YES 90* OTS BYPASS YES !

ACTUATOR INFORMATION

MODEL SB-00 SERIAL NO. 188642-ORDER No. 370315B OGR 34.1 NOM. MOTOR TORQUE 15 ft-lbf APP. FACTOR 1.0 MOTOR RPM 3400 MOTOR VOLTAGE 460 VAC i i

DEGRADED VOLTAGE 40~ (88.48%) CLOSE CONTROL LIMIT '

ALLOWASLE THRUST 16000 lbf. PULLOUT EFF. 0.40 f MOTOR TORQUE MULT. 0.214 RUN EFF. 0.60 MOTOR CURRENT MULT. 0.192 STALL EFF. 0.65

' f ALLOWAELE TORQUE 250 ft-lbf. STALL TORQUE 365.*7 ft-lbf i MOTOR CAPASILITY @ DEGRADED VOLTAGE !

CI=.- ts;; - 2 *

(L.a sec. ' w;< .0 se . .%. A.;. -

4 ;,6 0 sec.) - 40'e)

Mr.w.< . ,:,

L M*T = 1 - (;4 C*0 - 2 * (0.1 sec.

7:*0/10 sec. * ;0 se:.

75*0/90C sec. ) - 4 C*0) '

O.214/155 !

MT= C.2576 MOT =;- (MAO * - C . ; sec . * *'E*0/; C s'e:.

YAX !.~.

7:*0/900 sec. - 4C*0)

MOM /*I! I MOT = 1 - (14 0*C + C.1 sec.

7 *0/* C sec. - IC se:. * *!*0/ 90C sec. - 4 0*0)

C.;f2/135 M~T = C.Ei42 A070A70E NOM.

OPEN =

MO*0E ' M*T ' 00E

POLLOO7 ETT. ' APP . TAC *0E ' (t 07 TOLL V0;7AOI/;00)'

0RDOI 70E00I I

AO*0A70R OPEE =

! f: -lbf

0. 85 7 f

34. 2

C . 4 0

1. C * (0.8648)' = ;27.4 f:-ibf. I 707:05 l

AO'*7A70E '

OPEK =

AO'"UATOF. OPIE 70R077./I*EM TA070E t C.*.5 = 13 7.4/0.C;;( = '

1*641 lbf.

TER0!!

A~~0ATOE NOM.

0* 03I =

M070E

M*T

00E

RON ETT.

APP TA070R * (t OF TOLL VO* 7 AGE /100)'

i 70EO : .OE00I

)

A0"0A70E 010!I =

! f: -lbf ' C.B 7f

34.1 ' C.6C

1.0 * (C. 864 2 )' = 206. C f -lbf. l l

0R;0I A0~;ATOR CLOSI = A070A70E 0* 03I 70E00I/Em TACTOR t C.;! = 200.C/C.C1;f a li7C* It!.

7EEOSO n DC01520-065

Enclosure 1, Attachment I RC-96-0182, Page 14 of 15 XVG-8000B-RC VALVE MFG. WESTINGHOUSE STEM DIA. 1.250 in.

VALVE TYPE FLEX WEDGE GATE STEM PITCH 0.333 in.

VALVE SIZE 3.00 in. STEM LEAD 0.333 in.

t STEM FACTOR @ 0.20' O.0140' DWG. NO. 1MS-25-115-3 STEM FACTOR @ 0.15 0.0116' MAX. S.T. 10 sec.

VALVE OPEN ALL. 23995 lbf. VALVE ID 3GM88FNH VALVE CLOSE ALL. 24922 lbf. MAOT 14 0*C POSITION CHANGEABLE YES 90% OTS BYFASS YES ACTUATOR INFORMATION ,

MODEL SB-00 SERIAL NO. 188645 ORDER NO. 370317B OGR 34.1 NOM. MOTOR TORQUE 15 ft-lbf APP. FACTOR 0.9 MOTOR RPM 3400 MOTOR VOLTAGE 460 VAC !

DEGRADED VOLTAGE 411 (89.35%) CLOSE CONTROL LIMIT ALLOWABLE THRUST 16000 lbf. PULLOUT EFF. 0.40 I MOTOR TORQUE MULT. 0.214 RUN EFF. 0.60 MOTOR CURRENT MULT. 0.192 STALL EFF. O.65 ALLOWABLE TOROU,E 250 ft-lbf. STALL TORQUE 365.~1 ft-lbf MOTOR CAPABILITY @ DEGRADED VOLTAGE m=4 - euc;

2 -

4c.. .ec. awic sec. - m s.;. um.,m sec.) - w a M:M/.:,:

M*T = 1 - (14 C*

2* (c.1 se .

75**/IC sec. + 10 sec.

71*0/900 sec. ) - 4 C*0)

C.2*4/1

M*T = C.2576 MOT = 1 - (MA07 - C.1 se:. *

*C/10' se: . - MAX S . T. * *0/ 90 0 s ec. - 4 C'0)

MOM /1'5 MOT = 1 - (14 0*C - C .1 se:.

7:*0/1C sec.

1C se:.

75*0/900 sec. - 4 C'0)

C.192/1**

MOT = C.E742 AOC A*0R NOM.

OPIE = NOTOP.

MTT

00E

P%1,0*'T ITT.

APP . TACTOE * (% OT TULL V01.TAOI/100)'

TOROUI TORQUI

'AO*0ATOR OPIN =

15 f -lbf

C.E!7f ' 34.1

C.4C ' 1.C * (C.E f 25)' = 140.1 f -lbf.

70 EQUI A0"l"UATOE OPIK = ACTUA*0E OPD; 70RDUT/E*IM TAO *0E 6 0.15 = 14 0.* /C. 01*.( = 12C7E lbf.

IR0!"

AO*0ATOE NOM.

CLOSI = M0707.

MTT

00E

RT!; ITT.

APP. TA0 TOE * (4 OT TEL V01.TA07/100)'

70 EQUI TOROTI AC*UA*0E CLOSI = **

. f:-lbf ' C.E!7(

34.1

C . 6C

1. C * ( C . E E251' = 21 C .1 f:-Itf .

TOROUI A0"'OA*0P 0001I = ACTUATOE 0105I TORDUI/2*Iv. TA0"'OE t C .;! = 2* C.1/ C.C';f = 1Elif Ibf.

TIEUS-i' E DC01520-065

Enclosure 1, Attachmant I RC-96-0182, Page 15 of 15 XVG-8000C-RC

.. VALVE MFG. WESTINGHOUSE STEM DIA. 1.250 in.

VALVE TYPE FLEX WEDGE GATE STEM PITCH 0.333 in.

VALVE SIZE 3.00 in. STEM LEla 0.333 in.

STEM FACTOR @ 0.20 0.0140' DWG. NO. 1MS-25-115-3 STEM FACTOR @ 0.15 0.0116' 1%X. S.T. 10 sec.

VALVE OPEN ALL. 23995 lbf. VALVE ID 3GM88FNH VALVE CLOSE ALL. 24922 lbf. MAOT 14 0*C POSITION CHANGEABLE YES 90% OTS BYPASS YES ACTUATOR INFORMATION MODEL SE-00 SERIAL NO. 188644 OPOER NO. 3703153 OGR 34.1 NOM. MOTOR TORQUE 15 ft-lbf APP. FACTOR 1.0 MOTOR RPM 3400 MOTOR VOLTAGE 460 VAC DEGMDED VOLTAGE 415 (90.2%) CLOSE CONTROL LIMIT ALLOWAELE THRUST 16000 lbf. PULLOUT EFF. O.40 MDTOR TORQUE IfET. 0.214 RUN EFF. 0.60 MDTOR CUPRENT IfET. 0.192 STALL EFF. O.65 ALLOWASLE TORQUE 250 ft-lbf. STALL TORQUE 365.7 ft-lbf

MOTOR CAPA32LITY @ DEGRADED VOLTAGE .

1 MIT = . - (G ;; - i

6.. sec. * ;;';/;L s e c . - E). s .. . * ;LL WD sec. s - 4c;)

MIL 1;;

MOT = 1 - (14 0* -2* (0.1 se .

7 *C/10 sec. - 10 sec.

75*0/900 sec. ) - 4 C*0)

C.2;4/155 )

.CT = C.E*M l MOT = 1 - (n07 - C . ; s e c . ' ?!*0/; C; se c. - nX S . " . '

75*C/900 sec. - 40* )

M M/155 M*T = ; - ( *. 4 C*O = C . ; se c . ' 7!*0/10 se c . = 1 C se : .

7:*0/ 900 sec. - 4 C'~) ' O.;P2/155 M*.T = 0.6742 A*'*"OATCE NOM.

OPIK = MOTCE .CT

007.

PC* ;.007 ITT.

APP . TACTO7. * (% 07 TUL" VOLTAOI/100)*

TOR 00I TDR00I AO*UATOE 0?IE = 15 f -1:f

C.t!7f ' 34.1 ' C.4C ' C.E * (1)' = 157.9 f -;bf.

TDRDLT ACTOATCE OFIK = A"*"UATDE OPIS 70RO*;I/$7EM TACTOE 6 C . ;5 = 157. 9 / C . Cl

f = 13 f ;2 lbf .

TIEOST A O*"OATOE EDM.

CLO!I = MO*DT.

MTT

CGI ' EUN ITT.

AF7. TACTDE * (% CT T!L;. VOLTAOI/;00)'

TCRDTI TCE;UI A 70ATDE OLOSI = ;5 f:-;tf

C . 25M

34.;

C . 6C

C . t * (1)* = 23 6. 5 f:-;bf.

TLROUI AC 0ATOT.

CLOSI = A0"'UATOF. CLOSI TDRQUT /ITIM TACTOE 6 C.;I = 23 f. 9/C. C;*. f = 2C4;E lbf.

TIr:r!

a cm DOO1520-065

Enclosure 1, Attachment II RC-96-0182, Page 1 of 16 ES-412 ATTACHMENT 1 REVISION 1 PAGE 1 OF 2 SUBJECT CODE SDtJTH CARDLINA ELEu tilC AND GAS COMPANY PAGE 151 CALCULAT10N RECORD 1 OF CALC TITLE DesigbuW and CALC NO REV STARJS Cur 4:th For b 5% Hoos i~ 'DCo 152 o-0 67 we C5,fM a4 52 3 srsb,-,. - $ -

A PARENT DOCUMENT SYsitM SAr-J- Y CLASS NJA \/usou s DNN O OR E SR ORIGINATOR D!SC ORGANIZATION Alte,v H. EDNo,o D DATE XREF NO.

ME SC E+G-- D E S-l- % V/A A. CALCULATION INFORMATION '

CONTENT DESCRIPTION:

'R%) $6 CS, RH a J 52. Sy M5 MDt/

5:he Wi~doios K\/7 Aimind.ed r=CTED COMDONENTS/ANALYS!S:llar;ows

. se t O ce 2.6 4 a h , aWd LCtk/ hle a, val"

Ktf(.k aq.qkejgtm, CONTAINS PRELIMINARY DATAfASSUMOTIONS:

R NO . O YES, PAGES

- COMPUTER PRO 3 RAM USED: E NO O YES, val [DATION NOT REQ'D IREF.3.5) D T=S, VALID Aizu [OTHERS]

D YES. VALIDATED TES 412) D PRO 3 RAM VALIDATION CALCULATION E. VERtFICAT1DN O CONTINUED, ATTACHMENT VERIFICATION SCOPE Vev" pec E5-110 H queed.s AM MC M ~' MT*ad s,we qw_4 a Es 'n2 .

VERIFIER- N=4"3,N- 1

^

M[

ASSl3N BY: E$cs' B.E ~ -

N1b LEAD EM3tN:::i(DESGNEEVD ATE VERlrt:H/D TE ADP VALDATE Y Y f &" 5lIlH- u 2 9(,.

v- a C. RECORDS R ' NUMBER-FRAME NUMBER-TO PRS:

ORGINAL lAAINTAINED BY:

INiTCATE D SCE&G DE D SCELG D VENDOR D!s a rilBUTION: CALC FILE (ORGINAL)

PDE ISYd s:M EN3 59wea rne r is,e.sm 1 DE FILE 20.53::2 ATTACH.1 ONLY, CO?Y)

Enclosure 1, Attachmsnt II l RC-96-0182, Page 2 of 16' ES-412 ATTACHMENT I REVISION 1 PAGE 2 OF 2 SOUTH CAROLINA ELECTRIC & GAS COMPANY PAGE 1 REVISION

SUMMARY

2 OF CALCULATION NO.

D Co157 o - D 6~l l' REV NO.

SUMMARY

DESCRIPTION 5 Tk;3 mag ~ wdudes %e %uoa. c63 5.

1,Ltorpocaks %e 9b*lo Opm Lg ueSekh i Type wb h co~0ph

CA\ sut.w

~Keguleeds 5.dte b % Vdues ideJhed by %:s veu:36. t 2 %MoePord's/tL*S*5 Me 907. 675 $ gass 1

O SdYES 1.oOe 1/alve Lbdt ~

Sc h a ~ 4 % oa\o es t Q .qted b h a huh. 3 3, Fy%.4ej %e. tbd~$ bgue capV.h'hb

%qMew Cup &.\;h atVeped Vebt*

Sech_ g,J iecepaenklINb h%ctue hJ a J Cu4 %%.S -G"Cm.6\ Se:M leque=Jr Seh b %vLDBbzA-RB.

c This is abw,A Per t eReuce 2 4.

I O CONTINUES ON PAGE EM12]ATTACHMENTVREVISON1

Enclosure 1, Attachment II 1.0 PURPOSE RC-96-0182, Page 3 of 16 This calculation will determine the motor operator capability in both the open and close directions, provide thrust bands and control switch setpoint recommendations for GL 89-10 MOVs as well as other safety-related MOVs in the Chemical Volume and Control System, Residual Heat i

Removal System, and Safety Injection System. Valve tag numbers in section 2.6 marked with an asterisk are D21 within the GL 89-10 scope i per reference 2.29.

Motor operator capability determination can serve several purposes: )1

1. Determine motor operator capability - Minimum operator capability is defined as the output thrust and torque the operator is capable of producing under design basis conditions '

independent of control switch setting.

2. Determine the limiting thrust and torque values for the valve / actuator to protect the MDV from overthrust, overtorque and locked rotor conditions.

3. To indicate overall MOV adequacy to operate at design basis ,

conditions prior to diagnostic testing. l

4. Recommend the configuration of control switches based on minimum required thrust calculations and most limiting stress and/or thrust value of the MOV in both the opening and closing directions without compromising M3V integrity.

l 5. Can be used as a basis for recommending motor operator l reconfiguration where thrust / torque capability is determined to be less than adequate to overcome design basis thrust requirements.

2.O REFERENCES 1

2.1 Limitorque "as-shipped" data sheets:

l l 2.1.1 Limitorque letter from Dominick Giangualano to Mr.

l E.N. Gcidstein of Gilbert Commonwealth regarding P.O. 233617, including corrected Limitorque data sheets, dated 6/9/88 2.1.2 Limitorque letter from J.E. Drab to E.N. Goldstein cf Gilbert Commonwealth regarding P.O. 230547, including Limitorque data sheets, dated 5/20/87 2.2 Limitorque Documents 2.2.1 SEL-1, dated 5/21/79 2.2.2 SEL-2, dated 7/1/77 2.2.3 SEL-3, page 1 of 4, dated 5/21/79 SEL-3, page 2 of 4, dated 12/15/75 SEL-3, page 3 of 4, dated 2/26/79 SEL-3, page 4 of 4, dated 7/1/77 2.2.4 SEL-4, dated 7/1/77 2.2.5 SEL-5, dated 11/9/BE 2.2.6 SEL-7, dated 11/89 DOO1520-067

Enclosure 1, Attachmsnt II RC-96-0182, Page 4 of 16.

2.2.7 SEL-9, dated 6/2/75 2.2.8 900-00003, dated 3/88 2.2.9 900-00004, dated 3/88 2.2.10 Technical Update 92-02, dated 10/9/92 -

2.2.11 Technical Update 93-01, dated 6/8/93 2.2.12 Potential 10CFR21 Condition Reliance 3 Phase Limitorque Corporation Actuator Motors, dated j 5/13/93 and Technical Update 93-03, dated 11/93 2.2.13 Limitorque letter to Barry Norcutt of SCE&G dated 10-2-91, Actuator Torque and Thrust. Ratings 2.2.14 Technical Update 92-01, dated 2/28/92 l

EPRI Documents -

i 2.3 2.3.1EPRI Application Guide for Motor Operated Valves in Nuclear Power Plants NP-6660-D, Final Report, dated March 1990

2. 3.2EPRI 'HOV PPP, MOV Margin Improvement Guide, TR-100449, dated February 1992 2.4 Kalsi Engineering Inc. Documents 2.4.1 Thrust Rating Increase of Limitorque S3-00 Through SB-2 Spring Compensator Assemblies and SB-00 Through SB-1 Operators, Document No. 1799C, Rev. O, dated 10-7-94 2.4.2 Thrust Rating Increase of Limitorque SMB-000, SM3-00, SMB-0 and SMB-1 Actuators, Document No.1707C, Rev. O, dated 11-25-91 2.4.3 Fastener Analysis: Limitorque Operator Mount and Housing Cover, Document No. 1759C, Rev. O,

~

dated 12-7-93 2.4.4 SB-2-60 Limitorque Actuator Cycle Tesring Results, Document No.1790, dated 3-20-93 2.5 Westinghouse E-Spec. 678852, Rev. 2, dated 3/14/77 2.6 Valve Essy dw;s: Valve to dwg traceability confirmed via Ref. 2.9 yh Was . Dwc. VCSNS Dwc. U e'nerra-v LCV-01155-CS 115E064 RB iMS-25-069-7 E-208-021-33 R9 LOV-0115D-CS 115E064 RB 1MS-25-069-7 E-208-021-35 R 11A XVG-B130A-CS 115E064 RB IM5-25-069-7 3-208-021-22 R 10 XVG-B130E-CS 115E064 RB 1MS-25-069-7 B-208-021-23 R 10A XVG-B131A-CS 115E064 RB 1MS-25-069-7 E-208-021-24 R SA XVG-81315-CS 115E064 RB 1MS-25-069-7 E-208-021-25 R 10A I.CV-0115C-OS 115E062 R5 1MS-25-067-5 3-208-021-34 R 9 LOV-0115E-CS 115E062 R5 1MS-25-067-5 B-208-021-36 R 10 XVG-B106-CS 115I071 R5 1MS-25-066-1-6 B-208-021-16 R 13 XVG-B107-CS 115E071 R5 IMS-25-066-1-6 E-208-021-19 R 10A XVG-B105-CS 115E071 R5 1MS-25-066-1-6 3-208-021-20 R 11A XVG-B132A-CS 115E271 R6 1MS-25-176-1 3-208-021-26 R BA XVG-B1323-CS 115E271 R6 1MS-25-176-1 E-20B-021-27 R 10A XVG-B133A-CS 115E271 R6 *MS-25-176-1

_ E-208-021-28 R 10A l XVG-B1333-CS 115E271 R6 F.S-25-17 6-1 3-208-021-29 R 10A i XVG-BB01A-SI 115E071 R5 IMS-25-066-1-6 3-208-095-09 R 13A XVG-BB015-SI 115E071 R5 1MS-25-066-1-6 E-209-095-10 R 13A XVG-BBOBA-SI

1*5E079 RB 1MS-25-117-4 3-208-095-16 R 12 XVG-BBOB3-SI ' 115E079 RB IM5-25-117-4 3-208-095-17 E'11 XVG-BBOBC-SI

115E079 RB 1MS-25-117-4 3-208-095-1B R 11 XVG-BBOSA-SI 1164 EBB R4 1MS-25-520-0 3-208-095-19R 113 XVG-BB09B-SI 1164 EBB R4 IMS-25-520-0 3-208-095-20 R 113 XVG-BB11A-SI 115E070 R5 1MS-25-118-3 E-208-095-21 R 9 XVG-BB115-5: 115E070 R$ 1MS-25-118-3 E-208-095-22 R 9 DC01520-067 l

4 !

l l

Enclosure 1, Attachm:nt 11 RC-96-0182, Page 5 of 16 yf,1g= west. Dwm VCSNs num ria e- t= v XVC-8812A-SI 115E069 R5 1MS-25-075-2 XVG-8812B-SI 115E069 R5 3-208-095-23 R 10 IMS-25-075-2 3-208-095-24 R 10 XVG-8884-SI 115E071 R5 1MS-25-066-1-6 ,

XVG-8885-SI 3-208-095-13 R 12A 115E071 R5 1MS-25-066-1-6 B-208-095-14 R 14A XVG-8886-SI- 115E071 R5 1MS-25-066-1-5 XVG-8887A-SI 3-208-095-15 R 14A 115E067 R5 1MS-25-120-2 3-208-095-25 R 10A XVG-8887B-SI 115E067 R5 1MS-25-120-2 B-208-095-26 R 9A XVG-8888A-SI 115E273 R7 1MS-25-175-1 3-208-095-27 R 10 XVG-88883-SI 115E273 R7 1MS-25-175-1 3-208-095-28 R 11 XVG-8889-SI 115E273 R7 iMS-25-1~5-1 3-208-095-29 R 11 XVG-8701A-RE

115E274 R5 1MS-25-160-1 3-208-084-03 R 11 XVG-8701B-RE

1164E89 R5 IMS-25-519-1 XVC-8702A-RH

3-208-084-04 R 12A 1164E89 R5 1MS-25-519-1 3-208-084-05 R 12 XVG-87023-RE

115E274 R5 1MS-25-160-1 B-208-084-06 R 12 XVG-8706A-Rs 115E272 R6 1MS-25-174-1 B-208-084-09 R 11 XVG-87063-RE 115E272 R6 1MS-25-174-1 FCV-0602A-RH 3-208-084-10 R 11 8372D26 R1 1MS-25-B11-1 B-208-084-07 R 6

FCV-06023-R5 8372D26 R1 IMS-25-811-1 3-208-084-08 R 6 .

Valve Val =n Dwm VCSNS N . Eleant _

XVT-8100-CS E-73-020 RD IMS-25-172-3 XVT-8104-CS 3-208-021-17 a 103 E-73-020 RD IMS-25-172-3 3-208-021-09 R 4 XV*-8109A-CS E-73-020 RD IMS-25-172-3 XV*-81093-CS 3-208-021-13 R 10A I-73-020 RD 1MS-25-172-3 E-208-021-14 R los XV*-8109C-CS E-73-020 RD 1MS-25-172-3 XV*-8102A-CS 3-208-011-15 R 10A E-73-018 RC 1MS-25-800-0 8-208-021-10 R 7A XV*-81023-CS I-73-018 E-208-021-11 R 7A XV"-8102C-CS E-73-018, RC RC 1MS-25-800-0 iMS-25-800-0 XC-8112-tS E'-208-021-12 R 7A I-73-024fRC 1MS-25-173-2 3-208-021-18 R 93

2.7 Correspondence

Gilbert / Commonwealth letter CGGN-1896 to

-Westinghouse, dated 3/17/83

2.8 Correspondence

Westinghouse letter CGE-53-678 to G.J.

Braddick of Gilbert / Commonwealth, dated 5/13/83

? c

-imum Reg; ired Th=st Calculat:.cns 2.9.1 DC01520-066 Rev. 3, Minimum Regaired "hrust For Rising Stem GI, 89-10 MOVs in the CVCS System 2.9.2 DC01520-053 Rev. 4, Minimum Regaired *hrust For Rising Stem MOVs in the RER System 2.9.3 DC01520-059 Rev. 3, Minimum Regaired Thrus For Rising Stem MOVs in the SI System 2.10 Specification for Electric Motor Valve Actuators, V.C. St=mer Nuclear Station, (SP-3 09-22 61-00) , dated 10/1/71 l

2.11 Correspondence: Westinghouse letter from R.J. Faix to Mr. l C.A. Price of SCE&G, CGWS-1184, dated 5/7/61 l 2.12 USNRC IES 81-02, dated 4/9/S1 and IE3 81-02 Supplement 1, i dated 8/18/81; " Failure of Gate Valves to Close Under Differential ?ressure" DC01520-067 S

Enclosure 1, Attachm:nt II RC-96-0182, Pege 6 of 16 1

2.13 Correspondence: Westinghouse letter from R.J. Faix to Mr. !

C.A. Price of SCE&G, CGWS-2013, dated 6/11/81 !

l - l l -

2.14 Correspondence: Westinghouse letter from R.J. Faix to Mr. )

C.A. Price of SCE&G, CGWS-2125, dated 11/12/81 l I

2.15 Correspondence: SCE&G 1etter from T.C. Nichols to NRC Director !

l James P. Reilly, dated 7/7/81 2.16 Correspondence: Westinghouse letter to R.B. Clary of SCE&G, CGE-90-1061, dated 4/4/90. Valve allowables and new Limitorque thrust rating for SB-00 and SBD-00 actuators provided with Westinghouse valves 2.17 DC0820-003, Rev. 4, Class 1E 460V MOV Starting Voltages at Degraded Voltage Conditions .-

2.18 Correspondence: Westinghouse letter from R.J. Faix to Mr.

C.A. Price of SCE&G, CGWS-2371, dated 12/15/82 Field Change Notice FCN-CGE-10634 2.19 V.C. Summer Nuclear Station E=uipment Qualification Data Base ,

1 i

2.20 S-021-018, Environmental Zone Information 2.21 HELB/MSLB Evaluation, Report 2616, Rev. 7 2.22 V.C. Summer Nuclear Station Surveillance Test Procedures 2.23 DC01520-050, Rev. O, MDV Weak Link Analyses 2.24 VCSNS GL 89-10 Actuator Refurbishment Packages 2.25 MRF 21745 MON C

2. 26 MRF 21745 MON G 2.27 MRF 21745 MON H 2.28 IEE 21745 MON IS 2.29 DC01520-089, Rev. 2, GL 89-10 MDV Scope, Grouping and Engineering Justificaions 3.0 ASSUMPTIONS 3.1 Spring pack limitations will not be considered as an operator limiting component.

DC01520-067

1 Enclosure 1, Attachmant II j RC-96-0182, Page 7 of 16 4.0 ' METHODOLOGY l

This calculation will determine the minimum MOV capability. These l 4

limitations can be based on degraded voltage actuator capability, '

actuator thrust ratings, actuator torque ratings and/or valve structural limitations (reference 2.23) . ;

4.1 The basic actuator degraded voltage capability equation and methodology are given below.

l ACTUATOR NOM.

OPEN =

TOROOE ~ MOTOR

MTT

OGR ' PULLOUT ETT.

APP. FACTOR * (4 OF TULL VOL* AGE /100)' '

TOROUE ACTUATOR OPEN =

ACTUATOR OPEN TORQUE / STEM FACTOR 6 0.15 TERUST l ACTUATOR NDP..

CLOSE =

TOROUE MOTOR

MTT

OCR

RUN ETT.

APP. FAC*0R * (4 OF TULL VOLTAGE /100)'

TOROUE i

ACTUATOR CLOSE =

ACTUATOR CLOSE TORQUE / STEM FACTOR 0 0.15 TERUST '

i i

AC"'UATOR NOM.

i STALL =

MOTOR

OGR

STALL EFF.

1.1 j TORQUE TORQUE '

Both the motor torque factor and degraded voltage factor are affected by '

temperature as discussed in reference 2.2.12. The maximum allowable stroke time (MAX S.T.) for each MOV was determined by a review of reference 2.22. This infonnation is then used to determine the :

temperature increase internal to the motor per the guidance of ref. l 2.2.12. The maximum ambient temperature for which MOV operation is '

required is determined by a review cf references 2.19, 2.20 and 2.21.

Once this data has been acquired, the internal temperature rise due to MOV operation is added to the worst case ambient temp. (MAOT) for which ;

MOV operation is required. Note that for position changeable MOVS, the

-internal heat generation due to two MOV strokes (mispositioning and recovery) is used rather than the heat generation for one stroke. This total temperature is then used in determination of the overall temperature effect on motor torque reduction and motor locked rotor current reduction per Ref. 2.2.12. The locked rotor current reduction (MCF) is an input to ref. 2 . I'l . The motor torque reduction (MTF) is used in the overall actuator capability calculation as shown above. The general equations for MCF and MTF are given below (ref. 2.2.12). Note that the % Current Loss (MCM) and % Torque Loss (MTM) from 25'C to 180*C are motor size and speed specific per reference 2.2.12.

MTF =1. (MAOT + 2 * (0.1 sec.

75 C/10 sec. + MAX S.T.

75 C/900 sec.)- 40 C)

MTM/155q,osican sann.bk Movi)

MTF =1 - (MAOT + (0.1 sec.

75*C/]O sec. + MAX S.T.

75'C/900 sec.) - 40 C)

MTM/155(nonpuan esopabh Movs)

MCF = 1 -(MAOT + (0.1 sec.

75 C/10 sec. + MAX S.T.

75 C/900 sec.)- 40 C)

MCM/155 {

i DC01520-067

4 Enclosure 1, Attachment II RC-96-0182, Page 8 of 16 The Unit Efficiency is a function of actuator size, actuator overall ratio (OGR) , motor speed, closure control method, and stroke direction.

Pullout efficiency is used for the valve opening per references 2.2. 6 and 2.2.10. MOV closure control method is based on a review of l'

reference 2.6 elementary diagrams. Running efficiency is used for the closing stroke per ref. 2.2.6. Running efficiency is justified in the closing direction as the initial loads are small enough to allow the entire drive train to reach rated speed per Ref. 2.3.2. Stall efficiency is from reference 2.2.6.

The Application Factor (AF) is a function of minimum motor terminal voltage per ref. 2.2.12. For minimum motor terminal voltage of less than 90%, the AF is 1.0.

For cases where the minimum motor terminal voltage is greater than or equal to 90%, the AF is 0.9. Note that all l MOV applications are for temperatures considerably less than 900*F and I per ref. 2.2.5 do not require an AF of 0.8.

i l

l The Degraded Voltage Factor is also a function of minimum motor terminal voltage as stated in references 2.2.10 and 2.2.12. For minimum motor terminal voltage of less than 90%, the Degraded Voltage Factor is the actual percentage of rated motor voltage (4 60VAC) squared. For cases where the minimum motor terminal voltage is greater than or equal to 90%, the Degraded Voltage Factor is 1.0. The motor terminal voltage values are from reference 2.17 i

Stem factors are from reference 2.2.9 based on reference 2.6 data.

VCSNS MOV dynamic performance for the MOVs addressed within this i

calculation supports use of a 0.15 coefficient of friction, unless otherwise listed in this calculation.

t j An MOV is considered position changeable

' unless it cannot be mispositioned from the Main Control Board, has a power lockout switch which allows MOV electrical operation for specific operations only or has its circuit breaker locked in the open position.

4.2 Actuator thrust ratings are from reference 2.2 with the exception of Westinghouse supplied S3-00 and SED-00 actuators which have a i

maximum thrust rating of 16,000 lbf. (ref. 2.16) . The standard thrust rating of SMB-00, SMB-00, S3-00, SBD-00, SM -0, SMB-1 and SB-1 actuators may be increased to greater than 140% of the standard thrust rating based on Ref 2.4 test data only as stated throughout this calculation.

4.3 Actuator torque ratings are from reference 2.2.7 and are dependent on OGR for a given size actuator. Exceedance of the standard torque ratings are allowed for a limited number of cycles per i

l reference 2.2 and 2.4 data. Torque rating exceedances are addressed on a valve by valve basis.

, 4.4 Valve open and close th ust limitations are frotn reference 2.23.

4.5 Valve minimum required th=st values are from reference 2. 9.

i l

l DC01520-067

. I a .

Enclosure 1, Attachmsnt II i RC-96-0182, Page 9 of 16 1-i 4.6 The limiting torque and thrust values in this calculation do not i

include diagnostic test equipment accuracy allowances.

4.7 This calculation' does not evaluate torque switch / spring pack

capabilities and/or limitations. Full spring pack compression must be avoided. Torque switch settings must be below the lesser 1

of the actuator torque rating, actuator degraded voltage capability, and spring pack limitations.

l 4.8 Results of the minimum actuator torque and thrust capabilities are i compared to the actuator torque and thrust ratings to determine

. which is more limiting.

4.9 The most limiting of the minimum actuator capabilities and ratings' l

}; are then compared to the valve allowables to verify that the valve ]

will not be damaged due to improper actuator configuration.

i 4

4.10 Thrust and torque bands are then developed for minimum and maximum

! limits as follows; i Minimum Required Thrust = Min. Required Thrust per ref. 2.9.

s Maximum Thrust = Minimum of the MOV structural capability

, determination. Total thrust cannot exceed valve allowable or actuator ratinc (includino inertia) r Maximum T6rque at CST = Minimum of the actuator capabilty

, determination. Total torcue cannot exceed actuator ratinc (includino inertia) unless otherwise stated.

. NOTE: Diacnostic ecuirment error is not factored into the torcue and thrust band values above.

3 4.11 Where it is determined that actuator capability is less than the minimum -required thrust or if the minimum required thrust is

greater than the actuator rating, recommendations are made to reconfigure the actuator to overcome-limitations and provide an adequate margin to overcome minimum required thrust without compromising the MDV integrity.

4 4.12 Control Switch Recommendations Control switch configuration is determined only when an acceptable torque and thrust band is available. Minimum thrust capabilities should be greater than minimum required thrust with diagnostic i equipment error included. Recommendations are based on calculated j results.

4

, Control Switch Trip (CST) is considered to be the torque switch

actuation in the open direction with the open limit providing j primary valve control.

4 CST for the closing stroke is either close limit or close torque switch actuation depending on the design of the individual MDV.

DC01520-067

Enclosure 1, Attachment II RC-96-0182, Page 10 of 16 l

! 4.13 Limit Switch Control Open The open limit switch will be adjusted to prevent backseating.

Typically, this setting approximates 90 to 95% of stroke from the l

fully closed position but may be varied due to inertia of the MOV, l

motor design, and contactor drop-out time.

4.14 Limit Switch Control Close In cases where minimum required thrust is very close to maximum i rating or allowable, and/or high inertia is present, the MOV may be set for limit closure. Actuator will be configured to trip the motor on limit and coast the disk into the seat to achieve an acceptable thrust.

4.15 Torque Switch Control Open Primary torque' switch control in the opening direction is not recommended. Backup torque switch protection is provided in case of limit failure.

4.16 Torque Switch Control close Recommendation for torque switch control in the closing direction is based on the torque and thrust bands established in the body of 1 the calculation. Torque switch trip must be set at a value greater than the minimum required thrust (including equipment error) and l 1ess than the lesser of the actuator torque and thrust ratings, valve allowable thrust or actuator degraded voltage torque capability. This will assure the disk is properly seated and that the torque developed is great enough to trip the motor prior to overtorque or overthrust conditions.

4.17 Close to Open Torque Switch Bypass Close to Open (C/0) torque switch bypass will be set to bypass a minimum of 20 to 25% of disk travel time with the torque switch in the open circuit. This will ensure the open torque switch is bypassed for the highest MOV loads in the open direction.

DC01520-067

- - . - ~. - . - - _ - _ _ _ - _ _ - - -

1 i

XVG-8801A-SI Enclosure 1, Attachment II !

RC-96-0182, Page 11 of 16 VALVE MFG. , WESTINGHOUSE STEM DIA. 1.250 in. ;

'-~

VALVE TYPE FLEX WEDGE GATE STEM PITCH 0.333 in.

e VALVE SIZE 3.00 in. STEM LEAD 0.333 in. -

STEM FACTOR @ 0.20 0.0140' DWG. NO. 1MS-25-066-1-6 i STEM FACTOR @ 0.15 0.0116' MAX. S.T. 10 sec. i i

VALVE OPEN ALL. 23995 lbf. VALVE ID 3GM7BFN !

VALVE CLOSE ALL. 24922 lbf. MAOT 3 9*C i l POSITION CHANGEABLE YES 90% OTS BYPASS YES l !

ACTUATOR INFORMATION ,

MODEL SB-00 SERIAL NO. 179527 I l ORDER NO. 370315A OGR 38.60 !

NOM. MOTOR TORQUE 15 ft-lbf APP. FACTOR 1.0 !

i MOTOR RPM 3400 MOTOR VOLTAGE 4 60 VAC !

DEGRADED VOLTAGE 412 (89.56%) CLOSE CONTROL LIMIT :

ALLOWA3LE THRUST 16000 lbf.** PULLOUT EFF. 0.40 I

-l MOTOR TORQUE MULT. 0.214 RUN EFF. 0.60 l MOTOR CURRENT MULT. 0.192 STALL EFF. 0.65 ;

ALLOWASLE TORQUE 250 ft-lbf. STALL TORQUE 414 ft-lbf i i

i MOTOR CAPABILITY.@ DEGRADED VOLTAGs ,

t

.M;i = a - (mas; - a

t L . a sec. * .L'Giac sec. + Mid, J.;.

e?';/ m se:. ) - n'cs

M;.% ; t '

M"'T = 1 - (39*C - 2 * (0.1 sec.

75*0/10 sec. - 10 se:.

75*0/900 sec. ) - 4 C*0)

0.214/155 CT = C . 9 9"IC .

MCT = 1 - (MACO - (0.1 sec.

75*0/10 sec. + MAX S .T.

75*0/900 sec. ) - 4 C*0)

MOM /155 M"i = 1 - (2 9'O = (0.1 sec.

75*0/10 se=. + 10 sec.

75*0/900 sec. ) - 4 0*0)

C.192/155 MOT = C.9992 I i

ACTUATOF. NOM.

OPEN =

CTOR

M*T

OCR

PU1,*007 ITT

APP. TACTOR * (% OF FO*1 V01.TA0E/100)'

TORQUE TOROUE AO*UATOR OPEN 70RDUE

=

'5 f:-lbf ' C.9970 ' 3E.(

C.4C

1.0 * (0.895C)' = 125.2 f -lbf.

ACTUATOR OPEN = A0"'UATOR OPEN "0RQUE/ ITEM TA0 TOR t C.15 = 125.2 /0. 01;( = 15 968 lbf. 4

!?. RUST ACTUATOR NOM.

0~,03E

. =

C 0E

CT

00R

RUN ETT.

A?F. TAO *0R * (t 07 TU';. V00TAGE/100)'

TORQUE TORQUE ACTUATOR OLOSI =

15 f:-lbf

C. 9970

3E. 0 ' t . 60

1. 0 * (0. 2 95 6 )' = 277.25 f:-lbf.

TORDUE 01,0$E TF. RUST

= AC*UATOR 0* 03E TORDUE/!!EM TACTOR t C.15 - 277.25/C.C116 = 22952 lbf.

DC01520-067 r

-, , . , . - ~ .

sdnosure 6. munWEnt n XVG-8801B-SI RC-96-0182, Page 12 of 16 VALVE MFG. WESTINGHOUSE STEM DIA. 1.250 in.

VALVE TYPE FLEX WEDGE GATE STEM PITCH 0.333 in.

VALVE SIZE 3. 00 in. STEM LEAD 0.333 in.

STEM FACTOR @ 0.20 0.0140' DWG. NO. 1MS-25-066-1-6 1 STEM FACTOR @ 0.15 0.0116' MAX. S.T. 10 sec.

l i

VALVE OPEN ALL. 23995 lbf. VALVE ID 3GM78FN VALVE CLOSE ALL. 24922 lbf. MAOT 39'C POSITION CHANGEASLE YES 90% OTS BYPASS YES ACTUATOR INFORMATION 1 .=

MODEL SE-00 SERIAL NO. 229637 OF, DER NO. 370315A OGR 38.60 NOM. MOTOR TORQUE 15 ft-lbf APP. FACTOR 1.0 MOTOR RPM 3400 MOTOR VOLTAGE 460 VAC DEGRADED VOLTAGE 410 (89.13%) CLOSE CONTROL LIMIT l

l ALLOWAELE THRUST 16000 lbf.-- PULLOUT EFF. 0.40 l MDTOR TOP'QUE MULT. 0.214 RUN EFF. 0.60 l

l l

MOTOR CURRENT ICLT. 0.192 STALL EFF. 0.65 i l ALLOWABLE TORQUE 250 fr-lbf. STALL TORQUE 414 ft-lbf MOTOR CAPABILITY @ DEGRADED VOLTAGE I

l j M;F =.- (.w . - 2

G.. sec.

r;e . c s ec. 9J. s . . .

r;/ N L se c. ) - 4c ;)

CM/it?

, CT=;- ( 2 9'O - 2 * (C.*. see.

71*0/10 se:. + ;C sec.

75*0/90C sec. ) - 4CT)

C.214/125 f MT= C . 9 E*lt i

MOT = * - (MA07 - (C.1 se:.

75*0/10 see. - MD: 5.7.

75*C/900 sec. ) - 40*0)

MOM /;15 MOT = 1 - (297 - (C.1 se:.

7:T/* C see. - 10 sec. * 5*C/900 sec. ) - 4C*-)

C.192/;55 i MT= C.9993 A070ATOE EOM.

OPIN = MOTOE

M*"?

00E * ??: LOOT ITT

APP. TA070E * (4 07 TULL VO*. 7AGI/100)' !

TCEQUI 7;EOUI l j

AO*0A70E l 0?D = ;* f:-lbf

C.957C

2E.f

C.40

1.C * (C .6 9;3)' = ;E2.4 : itf.

70R00I AC-~ATLE OPIN = AC"0ATLE OPIN TOEDCI/S*IM TACTLE 6 C.15 = 123.4/C.C116 *.5E14 itf.

TEECIT A0"';A* CE E**: .

C*,0SI - MOTOE

P~T

O*E

RON ITT

APP. TACTCE ' (t OT TO;; VO TA3I/100)'

707.*CI 70E0!I A070A7DF 0!I 3..R,a

= * ! f:

ti

C. f E7 0

3 E . f

C . 6 C

1. C * (C.Ef*2)'

. = 275.;6 f -lbf. l j

A0~01707 C* 051 = A0""JA707 OLOSI TOR;/0I/ STIM TAO CE 6 C ..* ! = 271 ; f /C . C *

f = 2 372; lbf. !

TEEUI! .

l I

DC01520-067

_7 7

Enclosure 1, Attachmsnt II XVG-8884-SI RC-96-0182, Page 13 of 16 VALVE MFG. WESTINGHOUSE STEM DIA. 1.250 in.

VALVE TYPE FLEX WEDGE GATE STEM PITCH 0.333 in.

VALVE SIZE 3.00 in. STEM LEAD 0.333 in.

STEM FACTOR @ 0.20 0.0140' DWG. NO. 1MS-25-066-1-6 STEM FACTOR @ 0.15 0.0116' MAX. S.T. 10 sec.

VALVE OPEN ALL. 23995 lbf. VALVE ID 3GM78FN VALVE CLOSE ALL. 24922 lbf. MAOT 4 8'C POSITION CHANGEASLE NO 90% OTS EYPASS YES ACTUATOR INFORMATION MODEL SE-00 SERIAL NO. 229642 ORDER NO. 370319A OGR 31.90 NOM. MOTOR TORQUE 15 ft-lbf APP. FACTOR 0.9 MOTOR RPM 3400 MOTOR VOLTAGE 460 VAC DEGRADED VOLTAGE 419 (91.1%) CLOSE CONTROL LIMIT ALLOWAELE THRUST 16000 lbf. " PULLOUT EFF. 0.40 MOTOR TORQUE MULT. 0.214 RUN EFF. 0.60 MOTOR CU? MENT MULT. 0.192 STALL EFF. 0.65 ALLOWAELE TORQUE 250 fr-lbf. STALL TORQUE 342.1 ft-lbf MOTOR CAPAEILITY @ DEGRADED VOLTAGE Fa. 4 - (MO. - ts.. sec.

c's, L, sec. - M.x s.".

W;/ M sec.) - 6 ci * .CM/. :

MTT = 1 - (4 E*C + (C.; as:. *

?!*0/;C sec. + 10 see.

7 *C/90C sec. ) - 4 C*0)

C.214/1 5

.CT = C.956E M~T = 1 - (n 07 + ( C .1 s e:. '

75*0/10 sec. + MAX S.*. ' 75*0/90C sec. ) - 4 C'0)

MOM /;*5 MOT = 1 - (4 C*O * (0.1 se:. ' 7:*0/10 sec. - 10 se:.

75*0/90C se:. ) - 4 C'0)

C.192/;55 MOT = 0.92E; A0"'OATOR NOM.

OFIN = MOTOE *

M*T

O~E * ?O*.,1,007 I. T.

A??. TAO *0E * (% OF TT.*.* V01.TAOI/10 0)'

0EOss . .,r ,0I ACTUATOE OPIN = ;! f:-it!

C.926E

21.9

C.4C

C.t * (1)' = 17C.C ::-itf.

70EOCI AC CATOE OPIN = ACTUA707 0?IK TCE00I/57EM TACTOE ( C.;5 = 17*.C/C.C*.*( = 14654 1.-f.

TERO37 ACTTA707. NOM.

C*,0SI = MOT *r ' M"'T

00E

ETE ITT.

A??. TA0707.* (% OF T~~.~. V00"'AOI/100 )8 .

0EC-'I "'0 EQUI I I

A0*0AT07 i 0003I = 15 f -itf

C.986E

2;.9

C. 6C

C. t * (* l' = 21* . C f

t

. f ,

TOROTI AO*0 ATOP

'.".*.,0 $ I = A0~0AT07 0*,0!I TOE 00I/S IM TACTOE 6 C.;5 = 255. C/C . C' .( = 2.9E; lbf.

TEIO!!

DC01520-067

Enclosure 1, Attachmtnt II XVG-8885-ST RC-96-0182, Page 14 of 16 VALVE MFG. WESTINGHOUSE STEM DIA. 1.250 in.

VALVE TYPE FLEX WEDGE GATE STEM PITCH 0.333 in.

VALVE SIZE 3.00 in. STEM LEAD 0.333 in.

STEM FACTOR @ 0.20 0.0140' DWG. NO. 1MS-25-066-1-6 STEM FACTOR @ 0.15 0.0116' MAX. S.T. 10 sec.

VALVE OPEN ALL. 23995 lbf. VALVE ID 3GM7SFN VALVE CLOSE ALL. 24922 lbf. MAOT 105'C POSITION CHANGEABLE YES 90% OTS BYPASS YES ACTUATOR INFORMATION MODEL SE-00 SERIAL NO. 179524 ORDER NO. 370315A OGR 31.90 NOM. MOTOR TORQUE 15 ft-lbf APP. FACTOR 1.0 MOTOR RPM 3400 MOTOR VOLTAGE 460 VAC DEGRADID VOLTAGE 407 (88.48%) CLOSE CONTROL LIMIT ALLOWASLE TERUST 16000 lbf.'* PULLOUT EFF. 0.40 MOTOR TORQUE MULT. 0.214 RUN IFF. 0.60 MOTOR CURRENT MULT. 0.192 STALL EFF. 0.65 ALLOWAELE TORQU.I 250 ft-lbf. STALL TORQUE 342.1 ft-lbf MOTOR CAPAEILITY @ DEGRADED VOLTAGE M;f = 1 - MA0; a *

- si ti.. sec. . r;s i L s e c . - MAJ. s . ; .

ers/tas sec.) - 4L'Gi

r.T.%. . : s CT = 1 - I CE*O - (2 * (C.; sec.

75*C/10 see. - 10 sec.

7:*C/900 sec. ) - 4 C** )

C.214/15:

CT = C . 9C: 9 CT=1- (MA0" - (C.* se:.

75*0 /10 s e c .

PAX S . T .

75*0/90C sec. ) - 4 C*") ' CM/;55 MOT = 1 - (10 *~ - (C.; sec.

75'0/* 0 sec. - 10 se:. ' 7 *0/900 sec.) - 4C*0)

C.192/*55 CT = C.9175 A0~0ATOE NOM.

0?IN = C"'OE

CT

00E

FO*

00* ITT '

A?F. TACTOR * (% 07 TOLL VOLTAOI/10C)'

70EOCI 70E00I AO CATOR OPEN = * ! f:-lbf

C. 9Ci f

2 *. 9

C . 4 C

1. C * (C. E E4 2 )' = ;25.7 ::-itf.

"'OROUI AC 0 ATOP O?IN = AC".*AT"E OPIN *0E00I/57EM TACTOL 6 C .15 = *.3! .7 /C .C* 16 = 1170; lbf.

"IE05*

A~~0ATOE NOM.

01,0!I - CTOE

CT ' O~E ' E'~N ETT.

APF . TAO 07 * (4 or TOL VOLTAOI/;0C)'

~0E;;I 70E00I A0".;ATOE OLOSI = *i f:-lbf ' C.9039

2*.9 ' C.0C ' 1.C * (C.2648)'

. = 2C3.( f: *lf. l

"'OE00I l A0"'UATOE I l

OLO3I - AC-CATOE 0* 0$I TORO **I/ STEM TAC *07 ! C.15 = 2C2. (/C. Cl* ( = ;?!!2 ;hf.

TIE 0!! ,

1 DC01520-067 y

I Enclosure 1, Attachment II XVG-8886-SI RC-96-0182, Page 15 of 16 VALVE MFG. WESTINGHOUSE STEM DIA. 1.250 in.

l VALVE TYPE FLEX WEDGE GATE STEM PITCH 0.333 in.

l l

i VALVE SIZE 3.00 in. STEM LEAD 0.333 in.

STEM FACTOR @ 0.20 0.0140' DWG. NO. 1MS-25-066-1-6 STEM FACTOR @ 0.15 0.0116' MAX. S.T. 10 sec.

VALVE OPEN ALL. 23995 lbf. VALVE ID 3GM78FN VALVE CLOSE ALL. 24922 lbf. MAOT 4 8'C POSITION CHANGEABLE NO 90% OTS BYPASS YES l

ACTUATOR INFORMATION l MODEL SB-00 SERIAL NO. 229643 ORDER NO. 370319A OGR 31.90 l NOM. MOTOR TORQUE 15 ft-lbf APP. FACTOR 0.9 MOTOR RPM 3400 MOTOR VOLTAGE 460 VAC l

DEGRADED VOLTAGE 419 (91.1%) CLOSE CONTROL LIMIT ALLOWAELE THRUST 16000 lbf. " PULLOUT EFF. O.40 MOTOR TORQUE MULT. 0.214 RUN EFF. O.60 MOTOR CURRENT MULT. 0.192 STALL EFF. 0.65 ALLOWASLE TORQUI 250 ft-lbf. STALL TORQUE 342.1 fr-lbf MOTOR CAPAEILITY @ DEGRADED VOLTAGE M;I = 1 - (rm; - ( c . s e c.

W;/ ; O s e c . + MAA s.;

W;/ m sec. ) - 4c';)

M0y./.::

M*T = 1 - (4 E*C = (0.1 sec. ' 7'*0/10 sec. + 1C se:.

75*0/900 sec. ) - 4 C'0)

C.2*4/155 M*T = C.Se6E NOT = 1 - (FA0" + ( 0.1 s e c . * ~'5*0 /10 s e c . - MAX S . T .

75*0/ 900 sec. ) - 40*0)

M M/155 MOT = 1 - (4 E*C + (0.1 sec.

75*0/10 sec. - 10 se .

75*0/900 se:. ) - 4 C'0)

C.192/155 M~T = 0.96E1 A0"OATOE EOM.

CP;E = M0"'0E * .CT

DOE

TOLLOO* ITT

APP. TACTOR * (4 07 TOLi. V00TA~I/100)'

TOR 00I 70E00I AO*0ATOE OPIN = '5 f:- 3 f

C.986E

51.9

C.4C

0.9 * (ll' = 17 0. 0 f:-lbf .

0R00I AO*0ATOE OPIE = AC 0ATOE OFIN TOE 00I/!m TA0"'OE i C .15 = 17 0. 0/C . 01* 6 = 14 E54 ".bf .

I?OS:

A0""JATOE NOM. '

OLOSI = MOTOE * .WT

O~E

EON ITT.

APP. TA070E * (4 07 TOL* V00TAOI/100)' l TOR 00I 70E00I ,

a A0':"JAT07.

OLosI = ** f:-lbf

0.9E6E

51.9

C.6C

C.9 * (1)' = 255.C ::-lbf.

70R00I

! AC~tATOE

[

0~.05I = ACTOATOE OLOSI TOROOT/ STIM TA070E 6 C.15 = 255.0/0.C*.1f = 21985 lbf. ,

TEROST I l l 1

DC01520-067

Enclosure 1, Attachment II XvG-8889-sI RC-96-0182, Page 16 of 16 VALVE MFG. WESTINGHOUSE STEM DIA. 2.500 in.

VALVE TYPE FLEX WEDGE GATE STEM PITCH 0.333 in.

VALVE SIZE 10.00 in. STEM LEAD 0.667 in.

STEM FACTOR 0 0.20 0.0295' - DWG. NO. 1MS-25-175-1 STEM FACTOR @ 0.15 0.0242' MAX. S.T. 15 sec.

VALVE OPEN ALL. 166339 lbf. VALVE ID 10GM78FN VALVE CLOSE ALL. 100000 lbf. MAOT 4 8'C POSITION CHANGEAELE NO 90% OTS EYPASS NO ACTUATOR INFORMATION MODEL SBD-3 SERIAL NO. 200797 ORDER NO. 370317G OGR 38.34 OM. MOTOR TORQUE 150 ft-lbf APP. FACTOR 0.9 MOTOR RPM 3400 MDTOR VOLTAGE 460 VAC DEGRADED VOLTAGE 417 (90.6%) C",OSE CONTROL TORQUE

~

AL*,0WAELE TERUST 140000 lbf. PULLOUT IFF. 0.45 MOTOR TORQUE MULT. O.100 RUN IFF. O.60 MOTOR CURRENT MULT. OfI39 STALL EFF. O.60 ALLOWAELE TORQUE 4200 fr-lbf. STALL TORQUE 3796 fr-lbf MOTOR CAPAEILITY @ DEGRADED VOLTAGE

.GE = a - stu.7. w se.a sec.

i4GoaG sec. +t% b.;.

i~;t m sec.o - a no

t.' . i a MN = 1 - (4 8'O + (0.; sec.

75'0/1: sec. - 15 sec.

75t/9CC sec.) - 40%)

C.100/*55 M'"T = 0.9S36 i

M7 = 1 - (MAC* + (0.1 sec.

15*0/1C sec.

MAX 5.7.

7:*0/900 sec. ) - 4 0*0)

M Y./1 5 M T = 1 - (4 6*O + (c.1 sec.

75*0/1C sec. + 15 sec.

75t/9CC sec.) - CCT)

C.139/1 5 MOT - C.9910 A0"0A*0K NOM.

oPIN =

MMOR

M*T

OOK

PT*.:.00T. ITT.

A?P. TA COR * (4 CT M1, V0".*AOL/1CC)* i TORDOI TORO *I ACTOATOR OPIN =

15 0 f:-lbf

C . 9 9 3 6

2 2. 34

C . 4 5

C . S * (1)' = 2314 2

hf.

TOR 002 AO*;ATOE OPEN = AC TATOR OPIN 00RO';'I./STry. TACOR t C.20 = 2314/C. C295 = ";t44* lbf.

TEROST i

ACTOATOR NOM. i C1.0EI =

MOTOR

M*T

001

RON T.TT.

AFF. TACTOR * (4 CT G* VOi,*A::T./1CC)'

TORO 7Z 70R00Z l k=:3. "OR 1 0* Ost =

1st St-lbf

c.9936

32.34 *.60*C.f* (1)' = 308f f:-it!.

CR00I A0"OATOR C:,0SI "IROST

= A0"TA 02 C*.0SI 7020'TI/5"IM TACOR E C.ic = 3086/C.C295 = 104592 lbf.

DC01520-067

Enclosure 1. Attachmtnt III RC-96-0182, Page 1 of 12

. ES-412 ATTACHMENT 1 REVISION 1 PAGE 1 OF 2 SUBJECT CODE SolJrH CARDLINA ELECTRIC AND GAS COMPANY PAGE I52_ CALCULATION RECORD 1 OF //A CALCTIRE F.et e. 'R eg o;nd CALC NO REV STATUS u Caen..mt.~p,*n at kla:3

.G XNC- o s eco A .~r5 ,C - R e DCO / S20-/02 O A E PARENT DOCUMENT SY.dlEM SArts Y CLASS A/ l A T C, ONN O OR @ SR l ORIGINATOR DISC ORGANIZATION DATE XREF NO.

Ro ,(O d oree mE 5 + C. E 2 % 3/ fA '-

A. CALCULATION INFORMATION CONTENT DESCRIPTION: % a c. It -I-4:*- oltif 's %e F -c rw mins !

-to o v t< Lo me. "po 6bla bM 'pec55 u<t l o c b!-4, a . c/ a 5 5 e ,, r.h/ mq,g,*sg, X \IG O B ooo d.3,C. - R C,,

Art cCTED COMPONENTS ANALYS!S: '4 gfC o e o oo A - R.c, x VC.o e ooo ~4. -Q

')( d C- O 9 0 co c - Q C COffrAINS PRELIMINARY DATA / ASSUMPTIONS: .

t B NO O YES,PAGES COMPUTER PROGRAM USED: 9 NO C AbOc =/ us O YES, VALIDATION NOT REQ'D [REF. 3.5] O YES, VAUDATED [OTHERS]

O YES. VALIDATED TES412] O PROGRAM VALIDATION CALCULATION B. VERIFICATION O CONTINUED, ATTACHMENT VERIFICATION SCOPE N)er : G:ec % 45 s u e p rop e,.

a, .-ib cf N et e o a die g,j3g dL J e 3 es -pfia*5 a-d e 4 -05 7 '-* *' i' N ~ * 'ib-st% dela ay.

VERIFIER: ALuN H.Emo~o ASSIGN BY: k./pm/c S Nac T 8 h /'2 'z - %

LEAD ENG1NEER (DESIGNEEVDATE VERIFIER /DATE

APPROVAUDATE

n. M.B--

S 1/zi %

W z e-,c C. RECORDS REEL NUMBER:

FRAME NUMBER:

TO PRS: ORIGINAL MAINTAINED BY:

INIT/DATE O SCE&G DE D SCE&G O VENDOR DISTRIBUTION: CALC FILE (ORK31NAL) g PDE / SYSTEM ENG DE FILE 20.6602 AHACH.1 ONLY, COPY) 1 ES412/At:a.-tenert URevocr11,

. *i Enclosure 1, Attachmant III RC-96-0182, Page 2 of 12 ES 412 ATTACHMENT I REVISION 1 PAGE 2 OF 2 SOUTH CAROLINA ELECinic & GAS COMPANY PAGE REVISION

SUMMARY

CALCULATION NO. 2 OF ff tt o tsz o - 10 2. .

REV NO.

SUMMARY

DESCRIPTION O %.-4;.I . s s u e l

9 i

1 ES412fATTACHMENT VREVISION 1 0 CONTINUES ON PAGE

Enclosure 1, Attachmant III RC-96-0182, Page 3 of 12 Purnose: This calculation will determine the force required to overcome postulated pressure locking conditions (Fw) for the following Power Operated Gate Valves (POGVs); XVG08000A, B, C-RC The methodology used is consistent with the Commonwealth Edison method to predict the force required to overcome postulated pressure locking conditions.

This calculation will then compare Fw to the opening structural limit (MAOT) and capability limit (MPOT) for the POGVs to determine if the valves are capable of opening under the postulated pressure locking condition.

Assumotions: 1. As stated in reference 1,

2. The use of the opening valve factor will yield more representative results than the closing valve factor. VCSNS dynamic MOV testing has shown that the two are not usually the same.

3. Others as stated throughout this calculation.

References:

1. USER'S GUIDE FOR PRESLOK, A GATE VALVE PRESSURE LOCKING ANALYS!S PROGRAM USING THE COMMONWEALTH EDISON MODEL, REVISION 0,1-2-96

2. - USNRC Generic Letter 95-07, Pressue Locking of Safety-Related Power-Operated Gate Valves

3. USNRC letter from Mr. Paul E. Fredrickson, Chief Special inspection Branch Division of Reactor Safety to Mr. Gary Taylor, Vice President Nuclear Opera.tions,

SUMMARY

OF PUBLIC WORKSHOPS TO DISCUSS GENERIC LETTER 95-07, " Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves", dated 13-96

4. TWR 13157 Tab 957-RC, GL 95-07 Review for the RC System, dated 1-30-96

5. Engineering Report G/C 3097, NRC Generic Letter 89-10 MOV Setup, Test and Performance Validation Summary Report, Rev. 0, dated 7-26-95 t

t

6. DC01520-065, Design Review and Capability for Rising Stem MOVs in the CC, EF, FS, FW, MS, RC, SP and SW Systems, Rev. 3

7. Fax from ike Ezekoye (West.) to Ron Osborne, VCSNS MOV Data for PL Analysis, dated 1-25-96

8. DC01520-050, GL 89-10 MOV Weak Link Calculations, Rev. 0

9. Enoineerino Properties of Steel. American Society for Metals.1982 DC01520-102 PA 2 3 0~ 11 i

l

Enclosure 1, Attachmsnt III RC-96-0182, Page 4 of 12 Methodoloov: The methodology used for the determination of Fw is per pages 11 l

through 19 of ref.1 except this calculation will use the opening valve factor rather than the closing valve factor, as discussed in assumption 2.

The opening valve factor (VFJ will be corrected to account for the difference in the mean seat diameter versus the effective seat port dia.

(seat port diameter plus the 1/16" seat chamfer) used in the determination l of the tested opening valve factor (VF). This is necessary because the ,

I Westinghouse valves use the effective seat port area rather than mean ,#

seat area in the calculation of required operating thrust within the minimum required thrust calculations of reference 6. As such, the valve factor (VFy used within this calculation is determined as fo!!ows; VF, = VF * (effective seat port radius /mean seat radius)2 The opening structural margin evaluation will be based on a comparison of Fw and MAOT as follows; MARGIN, = (MAOT-Fw)/Fw A positive value shows stmetural margin.

The opening capability margin evaluation will be based on a comparison of Fw and MPOT as follows; MARGIN, = (MPOT- Fw)/Fw A positive value shows capability margin.

Review of reference 6 shows that 8000A has the lowest opening capability of the three valves (11844 lbf.) while the 8000C valve has the highest unseating load of the three valves (6129 lbf.). Therefore, this calculation will use a MPOT of 11844 and an unseating load of 6129 lbf.to bound all three valves.

Note that review of reference 8 shows the disk material to be SA.182 F316.

Comouter Calculations: N/A (This calculation is done in Mathcad.)

l l

l 0001520-102 PACE 4 0' 11 1

l

Enclosure 1, Attachment III RC-96-0182, Page 5 of 12 This section of the program reads the sixteen items of input data from the plinput1.dat file.

i:= 0 15 I input, := READ (phnputl) pbonnet :=inpurgpst t v := input, ;

i Pup:= input3 psi E := input, psi

'i !

Pg,n ::inPutgpsi Dm:= input g in 3 I

t :=inputg in Fpo ':= input 33 Ef I

a :=inputg in VF := input ,

3 b :=inputgin MOT := input 3f Bf MPOT:= input3 gl bf .

Hubjeg := inputg in l . .

c .:= 2nputg gm 0 := input. deg l

I l

1 I

I I

4 4

DC01520-102 PAE 5 0 11 l

l , _

- - i Enclosure 1, Attachment III '

3 1-RC-96-0182, Page 6 of 12 3

1 Program PRESLOK, Version 1

INPUTS:

Bonnet Pressure Pbonnet = 2485 psi (ref. 4)

Upstream Pressure (ref. 4)

Pup =1700 psi 3 Downstream Pressure (ref. 4) Pdown = 0 psi Disk Thickness (ref.7) t = 1.01 in 1 (taken at centerline of the hub vertically) '

Seat Radius (ref.7) a = 1.62-in (corresponding to mean seat diameter)

. Hub Radius (ref.7)(taken at plane of symmetry, b = 1.056 in perpendicular to the hub, radius of circle of equivalent area for non-circular hubs) c = 134375 in Effective Seat Port Radius (ref. 6 thrust calc.)

1 .

Seat Angle (ref.8) e = 7 deg Poisson's Ratio (ref. 8) (disk material at temperature) v = 03 Modulus of Elasticity (ref. 9) (disk material at temperature) 7 E = 2.8 10 psi Static Pullout Force (ref. 5) Fpo = 6129 Ibf ;

(measured value from diagnostic test) !

Valve Factor (ref. 6 VF = 0.6 thrust calc.)

Stem Diameter (ref. 6)

D 3a = 1.25 in l Hub Length (ref.7)

Hub 14 = 0.61 -in (from inside face of disk to inside face of disk)

Open Structural Limit (ref. 6) MAOT = 226801bf Open Capability (ref. 6) MPOT = 11844 Ibf DC01520-102 PACE 6 0; 11

. 3 Enclosure 1, Attachment III RC-96-0182, Page 7 of 12 "

Program PRESLOK, Version 1 PRESSURE FORCE CALCULATIONS t

Open valve factor corrected for mean seat dia, f

c)2 VF co := VF. 1 rja ype0 0,413 I Coefficient of friction between disk and seat:

cos(0) n:=VF co p = 0.39 I t VF co sin (0) '

~

Average DP across disks: !

Pup + Pdown DPavg := Pbonnet-2 DPavg =1635 pci Disk Stiffness Constants D :=

E-(t)'

6 D =2.64210 Ibf b 12-(1 - v")

E

.-. G := 7 2-(1 + v) - G =1.07710 osi i Geometry Factors: l l

1 Ii f a' C

2 := 4 1.b*I1 1 + 2 b 1 (a) i ibj), .

C2 =0.0529 b (b' 2 fl Ib'2 C3 -

+1 ba , -

-1 4a ,

(a j (b) taj C3 =0.0057 C 1 + v + (1 - v)-

8: 2- ta ,

C g =0.7987 1 b 1+v l l b'*.

C9 := -- -b a';+ 1-v 1-a 2 tjb 4 taj C9 =0.2469 i

a faI

fI faI

L ;:

3

+1 ha + -

-1 4a ,taj taj taj L3=0 DC01520-102 PC2 7 0' 11

t <

Enclosura 1, Attachment III RC-96-0182, Page 8 of 12

{

l l

Program PRESLOK, Version 1 '

Geometry Factors:(continued) a f a) 1-v fa i*

L9 :=-- 1+v In l+ 1- 1 L 9 =0 ;

a 2 taj 4 taj ,

I tht2 fl#

b . Ii b* Il L

13 := 64 1+4 taj

-5 taj

- 4. 2+b* -In I a L11 = 5.181 10 '

taj iaj (bj, S

t 1 1-v Il#.

b Ii*'

b aI fi L 1 1- i - -

1 + (1 + v) In I 37 := 4- 4 taj iaj (bj j, L17 =0.0488 Moment '

, - i

-DPavg a- C9 f ,' p Mrb :=

Cg 2ab ta - b )- L17 Mrb =-322.9 Ibf L

Q b:= DPavg (/ aa* - b')\

2b Q b=1168.4 Ibf l in i i

Deflection due to pressure and bending:

5 a* a DPavg a#

ybq Mrb - C 2+ Q -L ~

b3 C 3 p ybq =-8.532310 ' in it Deflection due to pressure and shear stress:

fI a Il Kg := 2 in b

-1+b*. l Kg =-0.0842 lj a ij, i

K gDPavg a

y3q:=

yq =-33231 10~5 *in Deflection due to hub stretch:

Pf := n-(a*- b*) DPavg Pf , Hub 34 ymd 2 nb (2 E) 7 d = 2.4104 10~8 -in DC01520-102 PEE 8 711

Enclosure 1, Attachmtnt III RC-96-0182, Paga 9 of 12 Program PRESLOK, Version 1 Total deflection due to pressure forces (per Ibfiin.):

Yq

Y bq + Y sq - YM y q=-6.586710'8 in Deflection due to seat contact force and shear stress (per Ibf/in.):

fta f 1.2- :b a1 a yy :=. '*l A .

[, tG y 3, =-7.6 8 10~8 -

Ibf i .m j Deflection due to seat contact force and bending (per Ibflin.):

(331 fC2I fa-C 91 'Ial ybw ~

bj -19 C3 +L3 Y bw =-2.63910-s , in (Dj ;C ;

g g ,(b) fIbf) 1 l

tmj Deflection due to hub compression:

- I2na Hub legh y cmF :=. yC*F =-3.165 10' -

g, 2 ~ 2E .j IIbf) t in j Total deflection due to seat contact force (per Ibilin.):

in y , := y 3, + 93, + y cmg Y w =-1.345 10' 1

(in }

Seat Contact Force for which deflection is equal to previously calculated deflection from pressure forces:

Ps :=2 naYq F, =4984 !bf Yw 0C01520-102 PE 9 0~ 11

. 9 l

.- . Enclosure 1, Attachmant III i RC-96-0182, Page 10 of 12 j UNSEATING FORCES Fpacking si included in measured static pullout Force n 2 Fpiston := D mPbonnet Fg = 3049.6 *Ibf F

vert :=n a sin (0)-(2 P% -Pup -Pg.n) Fvm = 3285.7 Ibf F prM := 2 F -(s cos(0)- sin (0)) 'I FNd = 2644.9 Ibf Ftod : -Fpiston + Fym+Ppreslock+ Fpo Fpo =6129 Ibf Ftod = 9010 Ibf MARGIN EVALUATION MAOT- Ftod MARGLNg :=

F iog MARGIN ,t = 151.72 *%

MPOT- F tod MARGINeap p total MARGINcap = 31.454 % -

CONCLUSION: Based on the methods used throughout this calculation, it can be !

concluded that XVG08000A, B & C-RC are capable of overcoming the postulated pressure locking forces.

DC01520-102 PME 10 0 11

Enclosure 1, Attachm:nt III

, RC-96-0182, Page 11 of 12 l

l ENGINEERS SERIAL NO. _10625 1

ENGINEER AME l TECHNICAL WORK RECORD DATE 2-2-96 PROJECTTITLE ES-412 VERIFICATION '

TAB 102 PAGE_Lof_

THE VERIFICATION OF CALCULATION NO. DC01520-102,REV. 0 l

Verified calculation DC01520-102, Rev.0 per the vedfication scope listed on the cover sheet of the ; 1 calculation and per ES-416, Rev.11 Section 6.7.3.A. ^

Verification per the cover sheet of the calculation The inputs are correct based on the references identified in this calculation and are inaccordance with 11 User's Guide to determine the force to overcome pressure locking. Allinputs were verified by the reference listed.

1 The methodology is in accordance with the User's Guide For Preslok, A Gate Valve Pressure Locking Analysis Program Using the Commonwealth Edison Model, Rev. O for determmmg the force required overcome pressure locking.

i The assumptions are inaccordance with the assumptions listed in the User's Guide. All assumptions are reasonable.

The outputs and arithmetic are reasonable and correct based on the inputs and the methodology used in 1 this calculation.

Therefore, this calculation is acceptable per the requirements of ES-412. l i

Verification per ES-416, Rev.11, Section 6.7.3.A

1. Technical concept verification- Not Applicable, this calculation is not the result of a design change, l the calculation was performed as a result of addressing GL-95-07, Thermal Binding and Pressure Locking evaluation.

2. Design basis check- Not Applicable, this calculation is not the result of a design change, the calculation was performed as a result of addressing GI 95-07, Thermal Binding and Pressure Locking evaluation. However, the design inputs utihzed in this calculation satsify the intent and purpose of the Calculation as identified in the purpose section of the calculation

3. Check of calculation accuracy- Not Applicable, this calculation is not the result of a design change, the calculation was performed as a result of addressing GL-95-07, Tnermal Binding and Pressure Locking evaluation. See Verification per the cover sheet of the calculation.

DC01520102 Page 11 of 11

Enclosure 1, Attachmsnt III RC-96-0182, Page 12 of 12 ENGINEERS SERIAL NO.10625 ENGINEER AME TECHNICAL WORK RECORD DATE 2-2-96 PROJECT'1 TILE ES-412 VERIFICATION TAB 102 PAGE_1.of_:

4. Interface considerations- Not Applicable, this calculation is not the result of a design change, . . ,

the calculation was performed as a result of addressing GL-95-07, Thermal Binding and Pressure Locking evaluation.

5. Systems interaction consideration- Not Applicable, this calculation is not the result of a design chan; the calculation was performed as a result of addressing GL-95-07, Thermal Binding and Pressure Locking evaluation.

This calculation is acceptable per the requirements of ES-416, Rev.11, Section 6.7.3.A.

M.

2/t[ %

DC01520-102 Page 11 of 11A j

j

Enclosura 1, Attachmtnt IV RC-.96-0182, Pags 1 of 12 ES-412

-. . ATTACHMENT 1 REVISION 1 PAGE 1 OF 2 SUBJECT CODE SOUTH CARDLINA ELECTRIC AND GAS COMPANY PAGE

/ 5 2. CALCULATION RECORD 1 OF flA CALC TITLE F r R ty.:ed 4. CALC NO REV STATUS o verc.. s '" Pre.w - e Loc k:-. ~

.P w u c_ o e co#4 ,B . s :. D C O /520- o 4 7 O A I PARENT DOCUMENT SYsit:M sat-ei Y CLASS stA <& r CNN O OR E SR ORIGINATOR DISC ORGANIZATION DATE XREF NO.

\ % Od:, o , s. In E % -C.E l-z *1-% N/A '

A. CALCULATION INFORMATION .

CONTENT DESCRIPTION:"T%;5 c.,,,fc. ,[.f;m de$er~;.a3 f Le Fone. <c4 ,l el b>

o+s a-e poskIJ d y< ewe e IoeL13 c oJ:+tess , a ~d -ss.ru.4sd ~r::~s ,%-

YJGo bSotA .1-sy.

AFFECTED COMPONENTS ANALYSIS: X VCO eM/A-5.r Y U c c s eo s t - s.1-CONTAINS PRELIMINARY DATA / ASSUMPTIONS:

@ NO O YES,PAGES COMPUTER PROGRAM USED: E NO thA.r elc 4 'b us ed D YES, VALID'ATION NOT REQ'D [REF. 3.5] O YES, VALIDATED [OTHERS]

O YES.VALIDATEDIES-4121 0 PROGRAM VAUDATION CALCULATION B. VERIFICATION O CONTINUED, ATTACHMEfff VERIFICATION SCOPE: Ver: G: e. +o a% e. p ,,p e ,. ; ,p.jn, , g, g,, , , ,, , a., .

4ss..q% J . 3.p.is e-ea st.f r.:f -r A -fi,4Qy, VERIFIER ALLEv H.ChWD N. .. ~

2. e-..

. ASSIGN BY: W4 Vive SNs.T Nk. kh//-at- -r(,

LEAD ENGINEER (DESIGNEE)/DATE VERIFIER /DATE APPROVAUDATE 0 hw Y$a ll~5iI96 , m < f- 1 1-.'m C. RECORDS REEL NUMBER-FRAME NUMBER:

TO PRS: ORIGINAL MAINTAINED BY:

INIT/DATE O SCE&G DE D SCE&G O VENDOR DISTRIBUTION: CALC FILE (ORIGINAL)

PDE / SYSTEM ENG DE FILE 20.6602 ATTACH.1 ONLY, COPY) !

ES.412]Acactarnerst 17Ae& 1

, , Enclosure 1, Attachment IV RC-96-0182, Page 2 of 12

, ES-412 ATTACHMENT I l REVISION 1 i PAGE 2 OF 2 SOLITH CAROLINA ELECTRIC & GAS COMPANY PAGE

,' REVISION

SUMMARY

2 OF ll ,

CALCULATION NO. '

4tois20- o9 7 b . ; j

, REV NO.

SUMMARY

DESCRIPTION ;

N O Z ,:%I rssue i a

I I

l l

l 0 CONTINUES ON PAGE ES-412l ATTACHMENT 2REYlSION 1

Enclosure 1. Attachmtnt IV RC-96-0182, Page 3 of 12 Purnose: This calculation will determine the required force required to overcome postulated pressure locking conditions (Fw) for the following Power Operated Gate Valves (POGVs); XVG08801A-SI XVG08801B-Si The methodology used is consistent with the Commonwealth Edison method to predict the force required to overcome postulated pressure locking conditions.

This calculation will then compare Fw to the opening structural limit (MAOT) and capability limit (MPOT) for the POGVs to determine if the valves are

{

capable of opening under the postulated pressure locking condition. ..,

Assumotions: 1. As stated in reference 1.

2. The use of the opening valve factor will yield more representative results than the closing valve factor. VCSNS dynamic MOV testing has shown that the two are not usually the same.

3. Others as stated throughout this calculation.

References:

1. USER'S GUIDE FOR PRESLOK, A GATE VALVE PRESSURE LOCKING AN ALYS!S PROGRAM USING THE COMMONWEALTH EDISON MODEL, REVISION 0,1-2-96

2. U

' SNRC Generic Letter 9%07, Pressue Locking of Safety-Related Power-Operated Gate Valves

3. USNRC letter from Mr. Paul E. Fredrickson, Chief Special Inspection Branch Division of Reactor Safety to Mr. Gary Taylor, Vice President Nuclear Operations,

SUMMARY

OF PUBLIC WORKSHOPS TO DISCUSS GENERIC LETTER 95-07," Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves", dated 1-3-96

4. TWR 13157 Tab 957-Si GL 95-07 Review for the SI System, dated 1-19-96

5. Engineering Report G/C 3097, NRC Generic Letter 89-10 MOV Setup, Test and Performance Validation Summary Report, Rev. O, dated 7-26-95

6. DC01520-067, Design Review and Capability for Rising Stem MOVs in the RH, CS and SI Systems, Rev. 4

7. Fax from ike Ezekoye (West.) to Ron Osborne, VCSNS MOV Data for PL Analysis, dated 1-25-96

8. DC01520-050, GL 89-10 MOV Weak Link Calculations, Rev. O

9. Engineering Properties of Steel, American Society for Metals,1982 0001520-097 Pcce 3 of 11

Enclosure 1, Attachment IV RC-96-0182, Page 4 of 12 ;

i I

Methodology: The methodology used for the determination of Fw is per pages 11 ;

through 19 of ref.1 except this calculation will use the opening va!ve i factor rather than the closing valve factor, as discussed in assumption 2. i The opening valve factor (VFJ will be corrected to account for the I difference in the mean seat diameter versus the effective seat port dia. ;

(seat port diameter plus the 1/16" seat chamfor) used in the determination j

of the tested opening valve factor (VF). This is necessary because the Westinghouse valves use the effective seat port area rather than mean seat area in the calculation of required operating thrust within the .; i minimum required thrust calculations of reference 6. As such, the valve I factor (VFy used within this calculation is determined as follows; VF, = VF * (effective seat port radius /mean seat radius)2 The opening structural margin evaluation will be based on a comparison of Fw and MAOT as follows; s

MARGIN, = (MAOT-Fw)/Fw A positive value shows margin.

~

The opening capability margin evaluation will be based on a comparison of Fw and MPOT as follows; MARGIN, = (MPOT - Fw)/Fw l

A positive value shows margin. 1 Review of reference 5 shows that XVG088018 S! has both a lower opening capability and a higher unseating thrust than XVG08801 A-St. Therfore, use of the XVG08801B-SI data will result in a limiting analysis.

Note that review of ref. 8 reveals the disk material to be SA-182 F316.

Computer Calculations: N/A (This calculation is done in Mathcad.) j DC01520-097 Pete 4 of 11

[ ,

, , Enclosure.1, Attachment IV RC-96-0182, Page 5 of 12

' i nis section of the program reads the sixteen items of input data from the plinput1.dat file.

i := 0 15 l input,:= READ (plinputl) l l P9,:=inputgpsi v := input, P9 := input3 psi E :=inputgpsi l

Pdown :=in;mt, psi D m:= input,g in l

1:=inputg in Fpo := input 33 Ibf l

a := saputgin VF := input,3 l

l b := input in f

OT:=5t gbf i MPOT:= input y lbf Hub 34 :=inputg in g ._ ,g 6 := input deg f ,

1 l

l i

t 3

i 1

4 i '

. D001520-097 Pcce 5 of 11 !

1 i 4

i

Enclosure 1, Attachmtnt IV g

RC-96-0182, Page 6 of 12 Program PRESLOK, Version 1

INPUTS:

Bonnet Pressure bonnet = 2826 psi

(ref. 4)

Upstream Pressure (ref. 4) p,p . 0. psi Downstream Pressure (ref. 4) Pdown = 0 psi T .

Disk Thickness (ref.7) t = 1.01 *in (taken at centerline of the hub vertically)

! Seat Radius (ref. 7) a = 1.62 in j (corresponding to mean seat diameter) i i

Hub Radius (ref.7)(taken at plane of symmetry, b = 1.056 in j perpendicular to the hub, radius of circle of equivalent area for non-circular hubs)

Effective Seat Port Radius (ref. 6 thrust calc.) c = 134 *

Seat Angle (ref.8) 0 = 7 deg i

) Poisson's Ratio (ref. 8) (disk material at temperature) v = 03 Modulus of Elasticity (ref. 9) (disk material at temperature) 7 E = 2.8* 10

psi 1

5 Static Pullout Force (ref.5)

(measured value from diagnostic test)

Fg = 2890tf i

Valve Factor (ref. 6 VF = 0.6 thrust calc.)

Stem Diameter (ref. 6)

D m = 1.25 in Hub Length (ref.7)

Hubjg = 0.61-in (from inside face of disk to ina,:de face of disk)

Open Structural Limit (ref. 6) MAOT=22680 Ibf Open Capability (ref. 6) MPOT = 15810 tf DC01520-097 Pcge 6 of 11

- - Enclosure 1, Attachment IV RC-96-0182, Page 7 of 12 1

Program PRESLOK, Version 1 l PRESSURE FORCE CALCULATIONS Open valve factor corrected for mean se'at dia.

f el l VF co:=VF VFco = 0.413 i (aj Coefficient of friction between disk and seat:

cos(0) 1 p:=VF co y = 0.39 .

1 e VF co sin (0) .-

Average DP across disks:

]

DPavg SP ht-P9+Pdown DPavg =2826 psi 1 2

Disk Stiffness Constants l l

E-(t)* l 6

D := D = 2.64210 Ibf in '

i 12-(1 - v ) ;

E 7 G :=

G =1.07710 psi ]

2-(1 + v)

Geometry Factors:

1 tib* fI a I C 1- f1+2 b l C2 =0.0529 2 := 4- laj ( (b j, 3

~

b Ibi* fl u Ibi*

C -

-1+1 b .+ -

'-1 C3 =0.0057 3 := 4 a ,taj ,

(bj gaj ,

1 Ii b *.

C g := 2-1 + v e (1 - v) (aj C g =0.7987 fi b 1+v f ai 1-v 1-b* !

C b .+ -

C9 = 0.2469 i

9 := a- 2 (bj 4 taj l

a faI* fi a faI*

L .+1 h + -

1-1 L3=0 3 := 4 a taj

, (a3 (aj 0001520-097 Pcge 7 of 11 i

I

.... . - = .

Enclosure 1, Attachmant IV I

RC-96-0182, Page 8 of 12 l

Program PRESLOK, Version 1 r

Geometry Factors:(continued) a Irv f al 1-v f aI

L -In ;+ 1- -

L 9 =0 i 9 := a- 2 (aj _ 4 (aj ,

1 IIb Ii#

b Il fi fl L

11 := 64 1+4 - 5. .-4ib 1- 2+b* -la, a

1 Lit =5.181 10 4

(aj (aj (aj taj , (bj, , ;

e ,

L 1 1-v b'

'I ll*'

b fI a'

1 1 -

1 + (1 + v) In L17 = 0.0488 17 := 4 4 taj (aj (bj, Moment I l

2

-DPavg a C9 ,

Mrb := - a - b") - L17 Mrb =-558 Ibf Cg 2ab Q := DPavg- a2 - b: Qb=2019.5 lbf l

b 2b in Deflection due to pressure and bending:

3 4 a' DPavg a y bq := M rb- C 2+ Qba C 3 D II N Deflection due to pressure and shear stress:

f al fbi*. ~

Kn:=-0.3- 2 In -1ri -

Kg =-0.0842 i

(bj (aj ,

l l

Ku DPavg a*

y sq

2 g Y q =-5.7437 10-8 in Deflection due to hub stretch:

P gm := n-(a - b*) DPavg l

, Pf Hubgg Y stretch 2 nb (2.E) y = 4.1663 10 8 in DC01520-097 Pege 8 of 11 l

1 Enclosure 1, Attachment IV RC-96-0182, Page 9 of 12 Program PRESLOK, Version 1 Total deflection due to pressure forces (per Ibflin.):

Yq Ybq+ Ysq- Ysuetch y q =-1.138510' in Deflection due to seat contact force and shear stress (per Ibflin.):

f l 1.2 ail Ini aia .'

I y gw :=- - I y 3, =-7.648 10' -

4 (mj Deflection due to seat contact force and bending (per Ibflin.):

f 31 ' fC 21 fa C9) 'ti y g. - -L 9

" )

(Dj (C gj ,( b)

,(bj C3 +l3 Ybw =-2.63910' <

'Ibf) I i

l nj ,

Deflection due to hub compression: I I

2na Hubj g l

~

b Y cmpr ;*' -

2E Y cmpr =-3.165 10 7 -

(mj Total deflection due to seat contact force (per Ibf/In.):

in y w := y 3,- y sw + Y cmpr , Yw =-1.34510' i

i nj )

Seat Contact Force for which deflection is equal to previously calculated deflection from pressure forces:

Y F, := 2 n a 4 F s= 8614.6tf Yw DC01520-097 Fegt 9 of 11

'. l Enclosure 1, Attachmsnt IV l RC-96-0182. Page 10 of 12 l

UNSEATING FORCES l l

Fpacking is included in measured static pullout Force l Fp gm := D *P m h Fpiston =3468 bf F -P Fyen = 5679.1 Ef ven :=n a sin (0)-(2 Pw- Pup down)

Fpresid := 2 F,-(n cos(0)- sin (0)) Fpndd = 4571.6 bf Ftod :=-Fpiston + Fyen + Ppid + Fpo Fpo =2890 bf i l

Ftod = 9672.6*bf l

MARGIN EVALUATION j MAOT- Ftod MARGIN st :

F tod l

MARGINst =134.477 To MPOT- Ftod MARGINeap

p !

total MARGINcap = 63.452 *To l

CONCLUSION: Based on the methods used throughout this calculation,it can be ,

concluded that XVG08801 A Si and XVG08801B-Si are capable of overcoming the postulated pressure locking forces.

DC01520-097 Pcge 10 of 11 I

Enclosure 1, Attachment IV RC-96-0182, Page 11 of 12 ENGINEERS SERIAL NO.10625 ENGINEER AME TECHNICAL WORK RECORD DATE l-30-96 PROJECT TITLE ES-412 VERIFICATION TAB 097 PAGE_1 of _1 ,

i THE VERIFICATION OF CALCULATION NO. DC01520-097,REV. O Verified calculation DC01520-097, Rev.0 per the verification scope listed on the cover sheet of the '

calculation and per ES-416, Rev.11 Section 6.7.3.A.

Verification per the cover sheet of the calculation The inputs are correct based on the references identified in this calculation and are inaccordance with the User's Guide to determine the force to overcome pressure locking. All inputs were ve:ined by the reference listed.

The methodology is in accordance with the User's Guide For Preslok, A Gate Valve Pressure Locking Analysis Program Using the Commonwealth Edison Model, Rev. O for determming the force required to overcome pressurelocking.

The assumptions are inaccordance with the assumptions listed in the User's Guide. All assumptions are reasonable.

The outputs are reasonable and carrect based on the inputs and the methodology used in this calculation Therefore, this calculation is acceptable per the requirements of n,S-412.

Verification per ES-416, Rev.11, Section 6.7.3.A

1. Technical concept verification- Not Applicable, this calculation is not the result of a design change, the calculation was performed as a result of Addressing GL-95-07, Thermal Binding and Pressure Locking evaluation.

2. Design basis check- Not Applicable, this calculation is not the result of a design change, the calculation was performed as a result of Addressing GL-95-07, Thermal Binding and Pressure Locking evaluation. However, the design inputs utihzed in this calculation satsify the intent and purpose of the Calculation as identified in the purpose section of the calculation

3. Check of calculation accuracy- Not Applicable, this calculation is not the result of a design change, the calculation was performed as a result of Addressing GL-95-07 Thermal Binding and Pressure Locking evaluation. See Verification per the cover sheet of the calculation.

DC01520-097 Page 11 of 11 4

I

- - - 1 I

Enclosure 1, Attachment IV I RC-96-0182, Page 12 of 12 1

ENGINEERS SERIAL NO.10625 ENGINEER AME TECHNJCAL WORK RECORD DATE l-30-96 PROJECT TITLE ES-412 VERIFICATION TAB 097 PAGE_l_of_1 i

4. Interface considerations- Not Applicable, this calculation is not the result of a design change, .,

the calculation was performed as a result of Addressing GL-95-07, Thermal Binding and Pressure Locking evaluanon. l l 5. Systems interaction consideration- Not Applicable, this calculation is not the result of a design chang the calculation was performed as a result of Addressing GL-95-07, Thermal Binding and Pressure l

, Locking evaluation.

l l

) This calculation is acceptable per the recuirements of ES-416, Rev.11, Section 6.7.3.A.

l 1 l

l l

l l lh M. ;

s/ < l %

I i

4 i

i l

l I

l DC01520-097 Page 11 of 11A m , -

l Enclosure 1, Attachmtnt V RC-96-0182, Page 1 of 12 ES-412 ATTACHMENT I REVISION 1 PAGE 1 OF 2 SUBJECT CODE SOUTH CAROLINA ELEvi tilC AND GAS COMPANY PAGE 15 Z. CALCULATION RECORD 1 OF 1/A CALC TITLE F,rs.c. L, :nd +=> CALC NO REV STATUS over ... "Wasw Lo Lig , F DJGoeee4 4 wc o s e e c, . s z- b/520 - o98 O A B PARENTpOCUMENT SYSTEM sat-ti Y CLASS N lA '~o 3- DNN D OR O SR ORIG;NATOR DISC ORGANIZATION DATE XREF NO.

%,m O ,6me tw E $4CE / .7. 4 -9c, ,py 4 A. CALCULATlON INFORMATION <

CONTENT DESCRIPTION.Tki , c.alc ul 4 t.- eleffr~s-es +ke bar e refs,.;, c/ b ouen.*~e pos+ I.hd P< c..swe. lac Lt2 < =~d:is c ~s, a,d a ssoc.:.4ed ma rg;.,,

C X \1 C-o 060 4 + K VGo e eG G 52.

AFFECTED COMPONENTS ANALYSIS:

Y V G o 9 6 G 4 - 5.;: , X vGoeeeG. g7 CONTAINS PRELIMINARY DATA / ASSUMPTIONS:

8 NO O YES,PAGES COMPUTER PROGRAM USED: @ NO Q gl.f[c./ md

-Ata. i . <-n O YES, VALIDdTION NOT REQ'D [REF. 3.51 O YES, VALIDATED [OTHERS]

D YES. VALIDATED TES-4121 0 PROGRAM VALIDATION CALCULATION B. VERIFICATION O CONTINUED, ATTACHMENT VERIFICATION SCOPE: \ler:C: er 4o cy, ,e. p,p., an y, 42, mett,.ls, rcas. .kle. =s-ptr%

a d

51> +s J: e.amr,4e.& w. -ik u+LJokay.

Ay e 1 < -s. '

VERIFIER ALW M. E' dmo.vP m't ?E ASSIGN BY: Wa*>e"S N cf N . @ w //- h -9(,

LEAD ENGINEER (DESIGNEE)/DATE VERIFIER /DATE APPROVAUDATE M$ Il3al4 b W ~Z-T-7C-C. RECORDS REEL NUMBER:

FRAME NUMBER:

TO PRS: ORIGINAL MAINTAINED BY:

INTT/DATE O SCESG DE O SCE&G O VENDOR DISTRIBUTION: CALC FILE (ORIGINAL) i PDE / SYSTEM ENG DE FILE 20.6602 ATTACH.1 ONLY, COPY) I es42=a:t,-t me=,= 1

Enclosure 1. Attachmtnt V 1

RC-96-0182, Page 2 of 12 i

1 ES-412 1 ATTACHMENT I REVISION 1 PAGE 2 OF 2 SOUTH CAROLINA ELECTRIC & GAS COMPANY PAGE l REVISION

SUMMARY

2 OF ll CALCULATION NO.

i

%c.osszo - 098 ,

- 1 I

REV NO.

SUMMARY

DESCRIPTION

! O A ,-4. . / r s s c.

l l

l l ,

l 1

l i

1 l

l l

e ewarrrscnusurvnEWSCN1 O CONTINUES ON PAGE l

l

I l e l , Enclosure 1, Attachment V RC-96-0182, Page 3 of 12

(

Puroose: This calculation will determine the force required to overcome postulated pressure locking conditions (Fw) for the following Power Operated -

Gate Valves (POGVs); XVG08884-SI XVG08886-Si The methodology used is consistent with the Commonwealth Edison method to predict the force required to overcome postulated pressure locking conditions.

This calculation will then compare Fw to the opening structural limit (MAOT) and capability limit (MPOD for the POGVs to determine if the valves are capable of opening under the postulated pressure locking condition.

Assumotions: 1. As stated in reference 1.

l- 2. The use of the opening valve factor will yield more representative l results than the closing valve factor. VCSNS dynamic MOV testing has shown that the two are not usually the same.

3. Others as stated throughout this calculation.

References:

1. USER'S GUIDE FOR PRESLOK, A GATE VALVE PRESSURE LOCKING ANALYSIS PROGRAM USING THE COMMONWEALTH EDtSON MODEL, REVISION 0,1-2-96

2. USNRC Generic Letter 95-07, Pressue Locking of Safety-Related j Power-Operated Gate Valves

! 3. USNRC letter from Mr. Paul E. Fredrickson, Chief Special inspection Branch Division of Reactor Safety to Mr. Gary Taylor, Vice President Nuclear Operations,

SUMMARY

OF PUBLIC WORKSHOPS TO DISCUSS GENERIC LETTER 95-07," Pressure Locking and Thermal Binding of l Safety-Related Power-Operated Gate Valves", dated 1-3-96

4. TWR 13157 Tab 957-SI, GL 95-07 Review for the SI System, dated 1-19-96

5. Engineering Report G/C 3097, NRC Generic Letter 89-10 MOV Setup, Test and Performance Validation Summary Report, Rev. 0, dated 7-26-95

6. DC01520-067, Design Review and Capability for Rising Stem MOVs in the i

RH, CS and SI Systems, Rev. 4

7. Fax from lke Ezekoye (West.) to Ron Osborne, VCSNS MOV Data for PL Analysis, dated 1-25-96

8. DC01520-050, GL 89-10 MOV Weak Link Calculations, Rev. 0

9. Engineering Properties of Steel, American Society for Metals,1982 D001520-098 PE 3 (F 11 1

Enclosure 1, Attachmsnt V RC-96-0182, Page 4 of 12 Methodolocy: The methodology used for the determination of F,g si per pages 11 through 19 of ref.1 except this calculation will use the opening valve factor rather than the closing valve factor, as discussed in assumption 2.

The opening valve factor (VFy will be corrected to account for the difference in the mean seat diameter versus the effective seat port dia.

(seat port diameter plus the 1/16" seat chamfer) used in the determination of the tested opening valve factor (VF). This is necessary because the WestingF.cuse valves use the effective seat port area rather than mean seat arta in the calculation of required operating thrust within the ..

minimum required thrust calculations of reference 6. As such, the valve factor (VFy used within this calculation is determined as follows; VF, = VF * (effective seat port radius /mean seat radius)2 The opening structural margin evaluation will be based on a comparison of Fw e and MAOT as follows; MARGIN, = (MAOT-Few)!Fuw A positive value shows structural margin.

The opening capability margin evaluation will be based on a comparison of Fug and MPOT as follows; MARGIN, = (MPOT - Fas)/Fe w A positive value shows capability margin.

Review of reference 5 shows that the opening capability for the 8884 and 8886 valves are the same, with the 8884 valve have the highest unseating load of 6720 lbf. Therefore,this calculation will use an unseating load of 6720 lbf.

Note that review of reference 6 shows the disk material to be SA-182 F316.

Comouter Calculations: N/A (This calculation is done in Mathcad.)

DC01520-095 F/CE 4 D~ 11

I

.. I Enclosure 1. Attachmsnt V !

RC-96-0182, Page 5 of 12 This section of the program reads the sixteen items of input data from the plinputi.dat file.

i:= 0 15 inputy:= READ (plinputl) l P% := inputgpsi v := input, i

Pup:: input3 psi E :=inpurgpsi ,

i Pdown:= input2 Psi Dm:= input gin 3 I

t := input3 in l Fg := input33 Ibf a :=inputg in VF := input 3 l MAOT := input Ibf j b := inputgsn 13 MPOT: input3 gIbf Hubg g:=inputg in c := input 3fin 0 := inputfdeg ,

r i

i i

l l

l

\

l 1

I DC01520-098 PE 5 0 11

Enclosure 1, Attachmtnt V RC-96-0182, Page 6 of 12 Program PRESLOK, Version 1 INPUTS:

Bonnet Pressure Pbannet = 1854 psi (ref.4)

Upstream Pressure (ref. 4)

P,p =0 psi Downstream Pressure (ref. 4) p .o.ps; l

l 3 l

Disk Thickness (ref.7) t = 1.01 in l (taken at centerline of the hub vertically)

Seat Radius (ref.7) a = 1.62 in (corresponding to mean seat diameter) i Hub Radius (ref.7)(taken at plane of symmetry, b = 1.056 in perpendicular to the hub, radius of circle of equivalent area for non-circular hubs) ;

)

c = 1M in Effective Seat Port Radius (ref. 6 thrust calc.)

Seat Angle (ref.8) 0 = 7 deg Poisson's Ratio (ref. 8) (disk material at temperature) v = 03 1

7 Modulus of Elasticity (ref. 9) (disk material at temperature) E = 2.8 10 psi j i

Static Pullout Force (ref. 5) Fpo =6720 lbf (measured value from diagnostic test)

Valve Factor (ref. 6 VF=0.6 thrust calc.) !

l Stem Diameter (ref. 6) D m = 1.25 in Hub Length (ref.7) l Hub 34 =0.61 in l (from inside face of disk to inside face of disk) ,

i Open Structural Limit (ref. 6) MAOT=22680 Ibf Open Capability (ref. 6) MPOT=14655 Ibf l DC01520-098 PACE 6 0711 )

4 j Enclosure 1, Attachmsnt V RC-96-0182, Page 7 of 12 '

i l

I Program PRESLOK, Version 1 i I

PRESSURE FORCE CALCULATIONS l

. Open valve factor corrected for mean seat dia. l k t ch

VF co := VF. -

VFco = 0.413 (aj i Coefficient of friction between disk and seat:

1 cos(0) i i :=VF co =039 I 1 1+VF co sin (0) .? i i Average DP across disks:

1 i P,p + Pde .

DPavg := Pbonnet- DPavg =1854 psi

, 2 Disk Stiffness Constants e

4 E-(t)3 i D := D = 2.6421@ -Ibf b

! 12-(1 - v )

G := G = 1.07710'

psi 3 2-(1 t v) i l Geometry Factors:

1 I\b* '

I1 -2 bln\Y q C 1- C 3 =0.0529 l

2 := 4- la j ( \bjj, b fbl* lfi a fbl*

, C ' -

+ 1 'h + -

-1 C3 =0.0057 3*4a ,taj (b3 (aj 4 .

I f\

b*

- 1,. y + (1 - v) C g =0.7987 C g := 2 (aj 3

l b 1+v fi a 1-v b *,

Il C -b - -

1- i C9 = 0.2469 9 := a- 2 (bj 4 (aj a fa\* ' ai fa i*

L -

l-l+1 'h 't - -I L3=0 j 3 4a , (aj taj (aj J

, DC01520-098 PACE 7 0; 11 4

Enclosure 1, Attachment V RC-96-0182, Page 8 of 12 Program PRESLOK, Version 1 Geometry Factors:(continued) f faI

L a

Itv-h al + 1-v -

1- 1 L 9 =0 9 := a- 2 ta; 4 (aj ,

1 Ii 'i I bl

Ii f Lgi := 64- 1+4b*-5b'i - 4 -

2+b* h aI Lig =5.181+10 '

(a3 (aj (a) (aj , (bj, ,

?

L 1 1-v b*

fl 'bl

a' fi g7 := 4-1 4

1 '1 + (1 + v) b L '7

= 0.0488 i taj (aj (bj, i

4 Moment 1

-DPavg a 2

C9 : l Mtb 2ab

~ a)~17 rb "-E I *M C8 I

\

Q b:= DPavg / 2qa - b') Q b=1324.9 Ibf 2b b Deflection due to pressure and bending:

a* DPavg a# -

ybq M rb - C2+ Qb a C 3 L 11 Ybq =-9.675210 ' b D

Deflection due to pressure and shear stress:

I\ t y\ 2.

K33 :=. 03- 2ha ,-1+;

K33 =-0.0842

\jb (a; K saDPavg a*

y sq ' g Y sq =-3.7682 10_3 b Deflection due to hub stretch:

2 P fm::n-(a - b ) DPavg Pf Hub 34 Ysmch ,

(2,E) n b- y = 2.7333 10-5 b DC01520-098 PG B 0711

._. . ~ _ _ _ -_ _ _ _ _ .

l . \

l Enclosure 1, Attachmsnt V l RC-96-0182, Page 9 of 12 l

l Program PRESLOK, Version 1 Total deflection due to pressure forces (per Ibf/in.): ,

l Yq Y bq+ Y sq- Y smuch yq =-7.46910~8 in l

Deflection due to seat contact force and shear stress (per Ibf/*m.):

l f ai f ai 1.2 In a .

y ,, := .

'"I A y 3. =-7.648 10' tG '

,Ibf 7

xmj Deflection due to seat contact force and bending (per Ibf/in.):

~

f3) a IC2) fa C9) rf al -

ybw - -L 9 8- "

iC3 +L3 Ybw =-2.63910 (Dj C8 ).{ b j , .(b3 'Ibfi t i nj Deflection due to hub compression:

I 2na Hub 14) g Ycmpr - cmpr" E H *

(.: 2E j fIbf) 6i nj Total deflection due to seat contact force (par Ibf/in.):

y w ::y bw+ Y sw t Y cmpr Y w =-1.345 10' - i imj Seat Contact Force for which deflection is equal to previously calculated deflection from pressure forces:

7 F,::2 n a 9 F 3=5651.6 Ibf Yw l DC01520-098 PG 9 0~ 11

Enclosure 1, Attachment V RC-96-0182, Page 10 of 12 UNSEATING FORCES Fpacking is included in measured static pullout Force Fpiston := D m 2,p bonnet Fp =2275.2 Ibf F

ven :=n a sin (0)-(2 Pbonnet- up -P P w) Fym = 3725.8 Ibf Feld :=2 F -(p3 cos(0)- sin (0)) FFesid = 2999.2 Ibf Fto d -Fpiston + Fym+FF eS g + Fpo 2

Fpo =6720 lbf Ftod =11169.7 Ibf MARGIN EVALUATION MAOT- Ftod MAP. GIN st F tod MARGINst =103.049 %

MPOT- Ftod MARGINeap ,

ptotal MARGINcap = 31.203 %

CONCLUSION: Based on the methods used throughout this calculation, it can be concluded that both XVG08884-SI and XVG08886-SI are capable of overcoming the postulated pressure locking forces.

l DC01520-098 PCE 10 Or 11

\

, Enclosure 1, Attachmant V RC-96-0182, Page 11 of 12 ENGINEERS SERIAL NO.10625 :

ENGINEER AME TECHNICAL WORK RECORD DATE l-30-96 PROJECTTITLE ES-412 VERIFICATION TAB 098 PAGE_1_of_1 THE VERIFICATION OF CALCULATION NO. DC01520-098,REV. 0 Verified calculation DC01520-098, Rev.0 per the verification scope listed on the cover sheet of the calculation and per ES-416, Rev.11 Section 6.7.3.A.

. Verification per the cover sheet of the calculation 1

The inputs are correct based on the references identified in this calculation and are inaccordance with the User's Guide to determine the force to overcome pressure locking. All inputs were verified by the reference listed.

The methodology is in accordance with the User's Guide For Preslok, A Gate Valve Pressure Locking Analysis Program Using the Commonwealth Edison Model, Rev. O for determining the force required to j overcome pressure. locking.

The assumptions are inaccordance with the assumptions listed in the User's Guide. All assumptions are

reasonable.

l The outputs are reasonable and correct based on the inputs and the methodology used in this calculation I

Therefore, this calculation is acceptable per the requirements of ES-412.

Verification per ES-416, Rev.11, Section 6.7.3.A I l

1. Technical concept verification- Not Applicable, this calculation is not the result of a design change, the calculation was perfonned as a result of Addressing GL-95-07, Thermal Binding and Pressure l Locking evaluation. !

2. Design basis check- Not Applicable, this calculation is not the result of a design change, the calculation was performed as a result of Addressing GI-95-07, Thennal Binding and Pressure Locking evaluation. However, the design inputs utilized in this calculation satsify the intent and purpose of the Calculation as identified in the purpose section of the calculation

3. Check of calculation accuracy- Not Applicable, this calculation is not the result of a design change, the calculation was performed as a result of Addressing GI-95-07 Thermal Binding and Pressure Locking evaluation. See Verification per the cover sheet of the calculation.

DC01520-098 Page 11 of 11 1

Enclosure 1, Attachment V j RC-96-0182, Page 12 of 12 i

ENGINEERS SERIAL NO.10625 ENGINEER AME TECHNICAL WORK RECORD DATE 1-30-96 PROJECT TITLE ES-412 VERIFICATION 8 TAB _02_8_PAGE_J_of_1

4. Interface considerations- Not Applicable, this calculation is not the result of a design change, .,

l the calculation was performed as a result of Addressing GL-95-07, Thermal Binding and Pressure Locking evaluation.

5. Systems interaction consideration- Not Applicable, this calculation is not the result of a design change.

the calculation was performed as a result of Addressing GL-95-07, Thermal Binding and Pressure Locking evaluation. l This calculation is acceptable per the requirements of ES-416, Rev.11, Section 6.7.3.A.

N.

I{ih l

l l

DC01520-098 Page 11 of 11A

- m_ ,:. a

- . ...__s._

Enclosure 1, Attecluntnt VI RC-96-0182, Page 1 of 12 ES-412

.. ATTACHMENT l REVISION 1

! PAGE 1 OF 2 SUBJECT CODE SOUTH CAROLINA ELECTRIC AND GAS COMPANY PAGE l /.5' 2_ CALCULATION RECORD 1 OF //A i

CALC iiILE Fome he <d +o CALC NO REV STATUS l mer . P e.w .c. L . Li .s A X w osa6s -ir DCOt52.0-C19 O B PARENT DOCUMENT SYsitM sat-ci Y CLASS l

i

id sr DNN O QR @ SR ORIGINATOR DISC ORGANIZATION DATE XREF NO.

7 Osbo < rn e 5 v-c r / ze -m .4 /A '

A. CALCULATION INFORMATION -

CONTENT DESCRIPTJON:T % ts c. h l O-* de-/er-l es th- f. e- re4 1-el /o

,<ce

<. pbl 4*/ p c,s ,c !.cLe a c .arit -s, . d an ,c=/ c/ . .. g; s, f;>,-

RUGO960s-W AFFEC ED COMPONENTS ANALYSIS: 4v4.os egy_gy CONTAINS PRELIMINARY DATA / ASSUMPTIONS:

@ NO O YES,PAGES COMPLKER PROGRAM USED: @ NO M c.e4.../

O YES, VALID'ATION NOT REQ'D [REF. 3.5] O YES, VALIDATED [OTHERS]

O YES. VALIDATED [ES-4121 0 PROGRAM VALIDATION CALCULATION B. VERIFICATION O CONTINUED, ATTACHMENT VERIFICATION SCOPE: \/c-:E:er 4e % c p .Per- r-pch,,ot Q ,,m . .{,fe,

% .eyf re o . J e 4p -fs e-eew /c it A. e-Na'./.sy.

VERIFIER All.eo H. E"omo.op -

ASSIGN BY: W Avror S N acT k /~M ~9(o LEAD ENGINEER (DESIGNEE)/DATE VERIFIER /DATE APPROVAL /DATE m

%. m ,,/ l) 3 r /96 ,

f t_ z-9G, C. RECORDS REEL NUMBER:

FRAME NUMBER:

TO PRS: ORIGINAL MAINTAINED BY:

INIT/DATE D SCE&G DE O SCE&G O VENDOR l DISTRIBUTION: CALC FILE (ORIGINAL)

PDE / SYSTEM ENG DE FILE 20.6602 ATTACH.1 ONLY, COPY) I i Es 4mAnactrnene s/neiaion f I

. - = . __. . . .. .. -- . . ~ - = . _.

" Enclosure 1, Attachmznt VI RC-96-0182, Page 2 of 12 ES-412 ATTACHMENT I REVISION 1 '

1 PAGE 2 OF 2 I

l l

SOUTH CAROLINA ELECinlC & GAS COMPANY PAGE -

REVISION

SUMMARY

2OFl/

CALCULATION NO.

%C Ots20 -oq 7 REV NO.

SUMMARY

DESCRIPTION o L;hl Tsswe.

i O CONTINUES ON PAGE ES412/ ATTACHMENT VREVISION 1

Enclosure 1 Attachmant VI i RC-96-0182, Page 3 of 12 l

Purpose:

This calculation will determine the force required to overcome postulated pressure locking conditions (Fw) for the following Power Operated Gate Valve (POGV); XVG08885-Si The meihodology used is consistent with the Commonwealth Edison method to predict the force required to overcome postulated pressure locking conditions.

This calculation will then compare Fw to the opening structural limit (MAOT) and capability limit (MPOT) for the POGVs to determine if the valves are capable of opening under the postulated pressure locking condition.

Assumptions: 1. As stated in reference 1.

2. The use of the opening valve factor will yield more representative results than the closing valve factor. VCSNS dynamic MOV testing has shown that the two are not usually the same.

3. Others as stated throughout this calculation.

References:

1. USER'S GUIDE FOR PRESLOK, A GATE VALVE PRESSURE LOCKING ANALYSIS PROGRAM USING THE COMMONWEALTH EDISON MODEL, REVISION 0,1-2-96

2. USNRC Generic Letter 95-07, Pressue Locking of Safety-Related Power-Operated Gate Valves

3. USNRC letter from Mr. Paul E. Fredrickson, Chief Special inspection Branch Division of Reactor Safety to Mr. Gary Taylor, Vice President Nuclear Operations,

SUMMARY

OF PUBLIC WORKSHOPS TO DISCUSS GENERIC LETTER 9507, " Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves", dated 1-3-96

4. TWR 13157 Tab 957-SI, GL 95-07 Review for the SI System, dated 1-19-96 l S. Engineering Report G/C 3097, NRC Generic Letter 89-10 MOV Setup, Test and Performance Validation Summary Report, Rev. O, dated 7-26-95

6. DC01520-067, Design Review and Capability for Rising Stem MOVs in the RH, CS and SI Systems, Rev. 4

7. Fax from Ike Ezekoye (West.) to Ron Osborne, VCSNS MOV Data for PL Analysis, dated 1-25-96

8. DC01520-050, GL 89-10 MOV Weak Link Calculations, Rev. 0

9. Engineering Properties of Steel, American Society for Metals,1982 DC01520-099 Pcge 3 of 11

f Enclosure 1, Attachmznt VI RC-96-0182, Page 4 of 12 l '

l _

Methodology: The methodology used for the determination of Fw is per pages 11 l through 19 of ref.1 except this calculation will use the opening valve l factor rather than the closing valve factor, as discussed in assumption 2.

The opening valve factor (VFJ will be corrected to account for the difference in the mean seat diameter versus the effective seat port dia.

(seat port diameter plus the 1/16" seat chamfor) used in the determination of the tested opening valve factor (VF). This is necessary because the Westinghouse valves use the effective seat post area rather than mean seat area in the caiculation of required operating thrust within the ,

minimum required thrust calculations of reference 6. As such, the valve factor (VFy used within this calculation is determined as follows; VF, = VF * (effective seat port radius /mean seat radius)2 The MPOT value will be based on the reference 6 opening torque capability divided by the reference 5 static unseating stem factor.

The opening structural margin evaluation will be based on a comparison of Fw and MAOT as follows; MARGIN, = (MAOT-FJ/Fw A positive value shows structural margin, j

\

lhe opening capability margin evaluation will be based on a comparison of Fw and MPOTas follows; MARGIN, = (M' POT- Fw)/Fw A positive value shows capability margin.

Comnuter Calculations: N/A (This calculation is done in Mathcad)

DC01520-099 Pege 4 of 11

Enclosure 1, Attachmsnt VI RC-96-0182, Pags 5 of 12 1

i i This section of the program roads the seventeer P ms of input data from the plinput1.dat file.

i := 0 16 j input,:= READ (plinputl)

P% := input opsi y := input, P,p := input, psi E :=inputgpsi Pdown:= input2 Psi D a := input, gin i

j 1:=inputgin Fpo := input,, Ibf 1,

a := inputf in VF := input g MAOT := input n Ibf b :=inputgin OTQC := input,gIbf Hublength: inPutgin ,

,g

=

6 := input f eg d t, 3

l l

4 I

0C01520-099 Fege 5 of 11

-- .-.- . . . - . -- _ _ - _ . ~ . - . .- . ..

.- l Enclosure 1, Attachment VI

{ RC-96-0182, Page 6 of 12

}

Program PRESLOK, Version 1 INPUTS:

Bonnet Pressure Pw =1854 psi

~

(ref. 4)

Upstream Pressure (ref. 4) P,p =0 psi

[ Downstream Pressure (ref. 4) Pdown = 0 psi I

Disk Thickness (ref.7) t = 1.01 in (taken at centerline of the hub vertically)

Seat Radius (ref.7) a = 1.62 in (corresponding to mean seat diameter)

Hub Radius (ref.7)(taken at plane of symmetry, b = 1.056 in perpendicular to the hub, radius of circle of equivalent area for non-circular hubs)

"I # *E Effective Seat Port Radius (ref. 6 thrust cale) l Seat Angle (ref.8) 0 = 7 deg Poisson's Ratio (ref. 8) (disk material at temperature) v=0.3 1

Modulus of Elasticity (ref. 9) (disk' material at tamperature) E = 2.8 10' psi j Static Pullout Force (ref. 5) Fpo =7877 Ibf (measured value from diagnostic test)

Valve Factor (ref. 6 VF = 0.6 thrust calc.)

Stem Diameter (ref. 6) D m = 1.25 in Hub Length (ref.7)

Hub 4 = 0.61 in (from inside face of disk to inside face of disk)

Open Structural Limit (ref. 6) MAOT = 22680 Ibf Open Torque Capability (ref. 6) OTQC = 135.7 Ibf SF = 0.00624 Stem Factor (ref. 5)

DC01520-099 Pcge 6 of 11

Enclosure 1, Attachmsnt VI RC-96-0182, Page 7 of 12 Program PRESLOK, Version 1 PRESSURE FORCE CALCULATIONS Open valve factor corrected for mean seat dia.

W co := W ci

I Wco = 0.413 Laj Coefficient of triction between disk and seat:

cos(6) k := Wco- p =0.39 1+W co sin (0) /

Average DP across disks:

Pup +P%

DPavg := Pbannet- DPavg = 1854

psi 2

Disk Stiffness Constants D :: E-(t)'

D =2.6421(f *Ibfin 12-(1 - v*)

G := G =1.07710'

psi i 2-(1 + v) -

Geometry Factors: l 1

I b f f aM C -

1- 1+2 b C2 = 0.0529 2 := 4 la ( (ba ,

fb\* ' a\ Ib\*

C3 - b +1 b t -

i-1 C3 =0.0057 4a ,

(a j (bj (aj l

1 I bI C g := 2- 1 + v t (1 - v) (aj C8 =0.7987 1

b fl 1- v fl C Itv-b 9 := a - 2 a

+ - - - -

4 1-b* C9 = 0.2469 (bj (aj a fa\* ' ni fa\*

L3 71 'h l+ -

-I L3=0

~4a ,(aj , (a) (aj DC01520-099 Pcge 7 of 11 i

Enclosure 1, Attachmant VI RC-96-0182, Page 8 of 12 Program PRESLOK, Version 1 Geometry Factors:(continued) f ai f 1+v 1-v ai*

L 9:= a- h + 1- L 9 =0 a 2 (aj 4 (aj

'\ i '

1+4b*i - 5 bi'l - 4.'b

2+ bi* k ai 1 I f -

L -

11 := 64- (aj (aj taj ,

l (bj, L11 = 5.181 10 '

(a3 1 1-v b Ii ' Ibi* '

f ai' L 1 1- ' --

1 + (1 + v) h Lg7 = 0.0488 g7:=4- 4 (aj (aj gbj, Moment 2

-DPavg a C9 ,

Mrb := a - b')- L 17 Mtb =-366.1 Ibf Cg ,2ab DPavg 2 Q b:: a - b*) Qb=1324.9 Ibf 2b in Deflection due to pressure and bending:

2 '

a a DPavg a y bq

M tb- 'L 11 C 2+ Qbg C 3 p Ybq =-9.675210' in Deflection due to pressure and shear stress:

Ii2 b

K , := - 03 2 h(a)i- 1 r : Ku =-0.0842

\b/ Laj ,

K sa DPavg a y sq := y sq =-3.7682 10-8 *in Deflection due to hub stretch:

2 Pf :=n-(a*- b ) DPavg P fm Hub 34 Ysuetch ,

n b- (2 E) y = 2.7333 10~8 *in DC01520-099 Pege B of 11

Enclosure 1. Attachment VI RC-96-0182, Pega 9 of 12 Program PRESLOK, Version 1 Total deflection due to pressure forces (per Ibflin.):

Y q

Y bq+ Y sq- Y sd yq =-7.46910' b Deflection due to seat contact force and shear stress (per Ibflin.):

f ai t ai i 1.2 h a A'l Ab y 3, :=. y ,, =-7.648 10' tG ,Ibf i T

im3 Deflection due to seat contact force and bending (per Ibflin.):

' ~

f,0 fC2) aC9I 'fl a s , in ybw ~ -L 9 - -

C3 +L3 Ybw =-2.63910 (Dj b ,Ibfl (C8) . I D l . .i3 (in t Deflection due to hub compression:

I2na Hubj g I in Ycmpr*~ yemp7 -3.165 10 ,

-2E j i

tn3 Total deflection due to seat contact force (per Ibflin.): .

y w ::Y bwt Y sw + Y cmpr Y w =-1.345 10' + , "

7 1 (3Di Seat Contact Force for which deflection is equal to previously calculated deflection from pressure forces:

Y F,:=2 n a 4 F, = 5651.6 Ibf Yw I

i i

DC01520-099 Pcge 9 of 11 l

l i

l

, Enclosure 1, Attachment VI l RC-96-0182, Page 10 of 12 ;

l l l

1 UNSEATING FORCES ,

1 Fpacking is included in measured static pullout Force !

1

)

75 2 i Fp :: D m Pbonnet Fpism =2275.2 Ibf I I

F vert ::n a sin (0)-(2 Pbonnet- Pup- Pdown)' Fyen = 3725.8+1bf l . 1 Fpreslock := 2 F,-(g cos(0)- sin (0)) FWock = 2999.2 Ibf l

Fmg :=-Fpinon + Fven+ Fpreslock+ Fpo Fpo = 7877 Ibf Fgg = 12326.7 Ibf MPOT DETERMINATION MPOT::OTQC SF MPOT=21750.28 lbf MARGIN EVALUAT10N MAOT- Ftod MARGINg :=

Ftod MARGINg = 83.991 %

MPOT- Ftod MARGINcap

ptotal MARGINcap = 76.448 +%

CONCLUSION: Based on the methods used throughout this calculation,it can be concluded that XVG08885-SIis capable of overcoming the postulated pressure locking forces.

1 DC01520-099 Pcge 10 of 11

-s Enclosure 1. Attachm:nt VI RC-96-0182, Page 11 of 12 ENGINEERS SERIAL NO.10625 ENGINEER AME TECHNICAL WORK RECORD

, DATE 1-30-96 j

j PROJECT TITLE ES-412 VERIFICATION TAB 099 PAGE_1 of_1 l

J I

THE VERIFICATION OF CALCULATION NO. DC01520-099,REV. 0 Verified calculation DC01520-099, Rev.0 per the verification scope listed on the cover sheet of the calculation and per ES-416, Rev.11 Section 6.7.3.A. i i

Verification per the cover sheet of the calculation The inputs are correct based on the references identified in this calculation and are inaccordance with the User's Guide to determme the force to overcome pressure locking. Allinputs were verified by the reference listed.

I j The methodology is in accordance with the User's Guide For Preslok, A Gate Valve Pressure Lockmg l

4 Analysis Program Using the Commonwealth Edison Model, Rev. O for determming the force required to !

overcome pressure locking.

1 The assumptions are inaccordance with the assumptions listed in the User's Guide. All assumptions are reasonable.

The outputs are reasonable and conect based on the inputs and the methodology used in this calculation Therefore, this calculation is acceptable per the requirements of ES-412.

Verification per ES-416, Rev.11, Section 6.7.3.A

1. Technical concept verification- Not Applicable, this calculation is not the result of a design change, the calculation was performed as a result of Addressing GL 95-07, Thermal Binding and Pressure Locking evaluation.

2. Design basis check- Not Applicable, this calculation is not the result of a design change, the calculation was performed as a result of Addressing GI 95-07, Thermal Binding and Pressure Locking evaluation. However, the design inputs utihzed in this calculation satsify the intent and purpose of the Calculation as identified in the purpose section of the calculation

3. Check of calculation accuracy- Not Applicable, this calculation is not the result of a design change, the calculation was performed as a result of Addressing GI 95-07, Thermal Binding and Pressure Locking evaluation. See Verification per the cover sheet of the calculation.

DC01520-099 Page 11 of 11

.s .

Enclosure 1, Attachment VI RC-96-0182, Page 12 of 12 l

ENGINEERS SERIAL NO.10625 ENGINEER AME l

TECHNICAL WORK RECORD l DATE l-30-96 h .

PROJECT TITLE ES-412 VERIFICATION TAB 099 PAGE_1 of_1 l

l

4. Interface considerations- Not Applicable, this calculation is not the result of a design change, .,

the calculation was performed as a result of Addressing GI 95-07, Thermal Binding and Pressure l Locking evaluation.

5. Systems interaction consideration- Not Applicable, this calculation is not the result of a design change, the calculation was performed as a result of Addressing GI-95-07, Thermal Binding and Pressure j Locking evaluation.

This calculation is acceptable per the requirements of ES-416, Rev.11, Section 6.7.3.A.

l 1

V.

2/ 19 6 i

l-4 DC01520-099 Page 11 of 11A

Enclosure 2 RC-96-0182 Page1 1

VCSNS RESPONSE TO THE REQUEST FOR ADDITIONAL INFORMATION CONCERNING THE STATIONS INITIAL GENERIC LETTER 95-07 " PRESSURE LOCKING AND THERMAL !

BINDING OF SAFETY-RELATED POWER-OPERATED GATE l 4 VALVES" SUBMITTAL.

i l PURPOSE:

i This enclosure provides the additional information requested in part 2 of the enclosure to the NRC letter to Mr. Taylor, dated July

3, 1996 (REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER 95-0~7, j

" PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER OPERATED GATE VALVES," VIRGIL C. SUMMER NUCLEAR STATION (TAC NO.

M93525).

ADDITIONAL INFORMATION REQUESTED:

2. "The licensee's submittal discusses the susceptibility of valves

' 8000A/B/C, Pressurizer PORV Block Valves, to thermal binding. The licensee's submittal states that these valves have spring compensators which help mitigate the potential thermal binding 4

condition. In addition, the licensee's submittal states that these i valves have been closed numerous times during various modes of j i

plant operation and subsequently reopened at ambient temperatures. l Does the licensee have diagnostic test data that demonstrate that the spring compensators prevent excessive closing forces on the valve disk? Please discuss this issue and provide the results of

! the diagnostic tests, if applicable.

The licensee's submittal states that these valves are not used for cold over pressure protection. If these valves are shut to isolate a leaking PORV, would they remain shut as the plant cools down, and l potentially have a requirement to open later for cold over pressure

protection? Please address this scenario".

VCSNS ADDITIONAL INFORMATION:

The Pressurizer PORV Block Valves (XVG08000A,B,C-RC) are fast acting valves that have Limitorque SB-00 actuators which are equipped with spring cc.mpensators. The spring compensator, which is a Belleville spring assembly mounted on top of the actuator, l supports the stem nut instead of the stem nut being held rigidly in I place by a lock nut as is the case for Limitorque actuators that are not equipped with spring compensators. The Belleville washers compress in response to the reactive upward force on the stem nut during the closing stoke which results in the Belleville washers

Enclosure 2 RC-%4182 Page 2 I

absorbing most of the additional thrust due to inertia. The Belleville washers will also absorb loads caused by thermal expansion, thereby keeping the valve disc from becoming too tightly wedged into the valve seat. In order for the Belleville washers to absorb the loads caused by thermal expansion the Belleville washers must not be in full compression as a result of the closing force.

The static test as-left full stroke diagnostic traces for the PORV l Block Valves indicate that the Belleville washers are not fully compressed during the closing stroke and the closing forces on the valve disk are not excessive (see attached traces).

The PORV Block Valves are not required to be opened for cold over pressure protection. Cold over pressure protection at VCSNS is provided by the RER (Residual Heat Removal) suction relief valves.

If one of the PORV Block Valves were shut to isolate a leaking PORV, and remained shut as the plant cooled down, the valve would not have a requirement to reopen.

1

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Enclosure 3 RC-96-0182 Page 1 VCSNS RESPONSE TO THE REQUEST FOR ADDITIONAL INFORMATION CONCERNING THE STATIONS INITIAL GENERIC LETTER 95-07 " PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES" SUBMITTAL.

PURPOSE:

This enclosure provides the additional information requested in part 3 of the enclosure to the NRC letter to Mr. Taylor, dated July 3, 1996 (REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER 95-07,

" PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER OPERATED GATE VALVES," VIRGIL C. SUMMER NUCLEAR STATION (TAC NO. 1 M93525). '

ADDITIONAL INFORMATION REQUESTED:

3. "The licensee's submittal discusses the susceptibility of valves 8887A/B, A/B Train Low Head Safety Injection (LHSI) Cross-Connect Valves, to pressure locking. The licensee's submittal states that the valves are closed to align the LHSI pumps for cold leg recirculation I

and are reopened to align the LHSI pumps for hot leg recirculation at a lower temperature. Based on a review of system diagrams, it appears that, during the time these valves are shut for cold leg recirculation, they may experience heat transfer from the LHSI system, causing thermally-induced pressure locking. Please address this issue. If the licensee has completed heat transfer, thrust requirement and actuator capability calculations, please provide them for our review".

i l 1 VCSNS ADDITIONAL INFORMATION:

The A/B Train Low Head Safety Injection (LHSI) Cross-Connect Valves (XVG8887A,B-SI) are not susceptible to thermally induced pressure locking. The valves are normally open and are closed to align the LHSI pumps for Cold Leg recirculation after the LHSI pump suction is aligned to the recirculation sumps. Closing the valves after the LHSI pump suction is aligned to the sumps results in the valves being closed at the time of the highest system temperature. The fluid temperature at the time of valve closure is approximately 145 degrees F. The valves are reopened to align the pumps for Hot Leg recirculation at a fluid temperature of approximately 125 degrees F (the Residual Heat Removal Heat Exchangers are cooling the recirculating water). Since the fluid temperature is highest when the valves are first closed and the system cools during the time the valves are closed the valves are not susceptible to thermally-induced pressure locking.

Enclosure 4 RC-96-0182 Page 1 1

VCSNS RESPONSE TO THE REQUEST FOR ADDITIONAL INFORMATION CONCERNING THE STATIONS INITIAL GENERIC LETTER 95-07 " PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES" SUBMITTAL.

PURPOSE:

This enclosure provides the additional information requested in part 4 of the enclosure to the NRC letter to Mr. Taylor, dated July 3, 1996 (REQUEST FOR ADDITIONAL INFORMA"' ION - GENERIC LETTER 95-07,

" PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER OPERATED GATE VALVES," VIRGIL C. SUMMER NUCLEAR STATION (TAC NO.

M93525).

ADDITIONAL INFORMATION REQUESTED:

4. "Regarding valve 8889, LHSI to RCS Hot Legs, the licensee's submittal states that this valve is not susceptible to pressure locking because 1) the downstream check valves must pass stringent leakage and testing requirements, 2) the valve is stroked quarterly without any problems to date, 3) the valve would not be required to open until hours after the LOCA which would allow the bonnet pressure to decrease and 4) all valve operations occur with the LHSI pumps running. Please address the following issues:

a. Over time, swing check valves may transmit high pressure even though they pass leak tightness criteria. The NRC staff notes that the licensee's submittal states, on page 6 of Enclosure 1, that even though check valves may prevent gross backleakage, they may not prevent pressure from increasing in the pipe between the check valve (s) and the gate valve under evaluation. Please discuss assurance that the check 1

valves downstream of valve 8889 will not transmit pressure over the entire operating cycle,

b. The quarterly stroke testing may not be conducted under the same conditions as that during a design basis accident.

Please discuss the correlation of past quarterly stroke testing to the potential pressure locking condition.

c. Through operating experience feedback discussed in NUREG-1275 Volume 9, Appendix A, Example A, the NRC staff is aware that gate valves can maintain bonnet pressure over a significant period of time. Please provide information to support the assertion that valve 8889 will not continue to maintain bonnet pressure when called upon to open.

Enclosure 4 3C-96-0182 Pap 2

d. Please provide more detailed information regarding the timing of the LHSI pump operation relative to the time at which the valve would be required to open".

VCSNS ADDITIONAL INFORNATION:

4. a. The two in-series check valves that isolate the LHSI to RCS Hot Legs valve (XVG08889-SI) from the RCS could leak by and ,

allow the RCS to pressurize the LHSI to RCS Hot Leg valve to RCS pressure prior to it being required to open (8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after a large break loss of coolant accident (LOCA)) to align the LHSI pumps for Hot Leg Recirculation. The likelihood of the check valves leaking by and pressurizing the valve during the operating cycle is reduced since the valve is stroked quarterly and the Residual Heat Removal system pressure would increase when the valve was opened alerting Operations that the check valves were leaking by.

For conservatism we will assume the LHSI to RCS Hot Legs valve is susceptible to hydraulic pressure locking and tne in-series check valves transmit the full RCS pressure to the valve (8889) just prior to a large break LOCA (see the attached pressure locking thrust calculation, DC01520-134) .

Based on the actuator capability (See Enclosure 1, Attachment II) and the pressure locking thrust requirement, this valve has sufficient thrust capability to overcome the postulated pressure locking forces.

b. If the in-series check valves were to transmit pressure during the operating ~ cycle, the quarterly stroke testing of valve 8889 would result in the valve being required to open against whatever pressure was transmitted by the check valves. The potential pressure locking conditions occurring during the time the valve is required to be opened (approximately 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after a large break LOCA) would be less severe than surveillance test conditions due to the valve depressurization that would take place over the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months time period following the RCS depressurization as a result of the accident (See item c. for more details). The valve !

actuator torque / thrust capability is essentially the same !

for both the surveillance test and the LOCA conditions since the motor terminal voltage remains above 90% for both cases and the LOCA does not result in a significant reduction in actuator output torque / thrust due to elevated ambient temperatures. i

c. Westinghouse has performed an analysis of the bonnet depressurization rates of gate valves tested by Commonwealth Edison Company (

Reference:

WOG-96-073, Final Program Verification Letter Report, "V-EC-1619 Bonnet Depressurization Rate"). The analysis determined the following bonnet depressurization rates:

Enclosure 4 RC-96-0182 Page 3 Differential Pressure Bonnet Depressurization Rance Rance Below 500 psid 1.0 psi / minute 500 - 1,000 psid 2.5 psi / minute ;

1,000 - 1,500 psid 4.0 psi / minute -

> 1,500 psid 5.5 psi / minute Assuming the initial bonnet pressure for valve 8889 was 2235 psig (RCS normal operating pressure) the bonnet pressure I would be 479 psig when called upon to open, 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the LOCA, to provide LHSI to the RCS Hot Legs.

d. The LHSI pumps run continuously during the injection, cold leg and hot leg recirculation phases. The pumps are not secured when swapping back and forth between cold leg and hot leg recirculation as is the case for the HHSI pumps. The quarterly surveillance test of XVG08889-SI is performed with I the pumps. secured. Even though the LHSI pumps are running during the time valve 8889 is required to open to establish ;

Hot Leg Recirculation the valve may be isolated from the l pumps by the closure of valves XVG08887A,B-SI. Since the valve may be isolated from the LHSI pumps when it is required to open no credit is taken for the head of the pumps in the pressur.e locking thrust calculation (See attached pressure locking thrust calculation, DC01520-134).

Enclosura 4 RC-96-0182 Page 4 ES-412

-,,' ATTACHMENTI REVISION 1 PAGE 1 OF 2 SUBJECT CODE SOUTH CAROUNA ELECTRIC AND GAS COMPANY PAGE 162. CALCULATION RECORD 1 OF t 1 CALCTITLE Farcc. R g.sr</ fo CALC NO REV STATUS OutcsonstTrL vuGoseB9-5,

%are I os.Is:^s of MOISto - t 5 4 o A B

PARENT DOCUMENT SYsiEM SAtti Y CLASS NiA Sr DNN O OR @ SR SRIGINATOR DISC ORGANIZATION DATE XREF NO.

Kon Osbo<o n ms 6 +c s 7-/9-5c m4 A. CALCULATION INFORMATION '

CONTENT DESCRIPTION:Tkr> calcold:.~ ddermhe overt..me, yeshlai<J yrtewe 1.d tag ad assoc .s -fat. F.,,e etqa:rti iohl **<sfas AFFECTED COMPONENTS ANALYSIS: M C.o 8 6 8 T- 5 J CONTAINS PRELIMINARY DATA / ASSUMPTIONS:

B NO O YES,PAGES COMPUTER PROGRAM USED: E NO (p).&c d %,1)

O YES, VALIDATlON NOT REQ'D [REF. 3.5] O YES, VALIDATED [OTHERS]

O YES. VALIDATED [ES4121 0 PROGRAM VAUDATION CALCULATION B. VERIFICATION O CONTINUED, ATTACHMENT VERIFICATION SCOPE: \le<:

G:e< % assa,e. pe.yer hy,ts, mend =J aertkd;q vtason* Lit aww+ ns ad od p.6 c ensided wid ***/d=u.

VERIFIER:'Roloert Ldt e.

ASSIGN BY: AI "P.,h* /7'/9-9(,

LEAD ENGINEER (DESIGNEE)/DATE VERIFIER /DATE APPROVAUDATE

/Minjrp /b* h. A . 7l24l9 L U' G C. RECORDS REEL NUMBER:

FRAME NUMBER:

TO PRS: ORIGINAL MAINTAINED BY:

INIT/DATE O SCE&GDE O SCE&G O VENDOR DISTRIBUTION: CALC FILE (ORIGINAL) .

PDE / SYSTEM ENG ES 4ft/Aftaowerrt 1/ Revision 1 DE FILE 20.6602 ATTACH.1 ONLY, COPY) lB

Enclosure 4 RC-96-0182 Page 5 ES-412 ATTACHMENTI REV'.SION 1 PAGU 2 OF 2 l

SOUTH CAROLINA ELECTRIC & GAS COMPANY PAGE .

REVISION

SUMMARY

2 OF // i CALCULATION NO. )

1

% col 520 -134 \

l REV NO.

SUMMARY

DESCRIPTION O Z-:+;. ) in a e .

J O CONTINUES ON PAGE ES41PJATTACHMENT WREVISION 1

Enclosure 4'

] RC-96-0182

] Page 6 i

i

Purpose:

This calculation will determine the force required to overcome postulated hydraulic pressure locking conditions (Fw) for the following Power j Operated Gate Valve (POGV); XVG08889-SI i

The methodology used is consistent with the Commonwealth Edison method to

predict the force required to overcome postulated pressure locking conditions. '

! This calculation will then compare Fw to the opening structural limit (MAOT)

{ and capability limit (MPOT) for the POGVs to determine if the valve is

capable of opening under the postulated hydraulic pressure locking condition.

i Assumptions: 1. As stated in reference 1.

l i

i 2. The use of the opening valve factor will yiald more representative .

l results than the closing valve factor. VCSNS dynamic MOV testing has (

, shown that the two are not usually the same. '

4 j 3. Others as stated throughout this calculation.

i i

References:

1. USER'S GUIDE FOR PRESLOK, A GATE VALVE PRESSURE LOCKING

ANALYSIS PROGRAM USING THE COMMONWEALTH EDISON MODEL, i REVISION 0,1-2-96

. 2. USNRC Generic Letter 95-07, Pressue Locking of Safety-Related Power-Operated Gate Valves i

3. USNRC letter from Mr. Paul E. Fredrickson, Chief Special inspection l Branch Division of Reactor Safety to Mr. Gary Taylor, Vice President Nuclear Operations,

SUMMARY

OF PUBLIC WORKSHOPS TO DISCUSS GENERIC LETTER 95-07," Pressure Locking and Thermal Binding of j Safety-Related Power-Operated Gate Valves", dated 1-3-96 I

3

4. TWR 13157 Tab 95-7R1, GL 95-07 Additional Info. SI System, dated 7 19-96 l 5. Diagnostic test traces and associated Engineering Evaluation for MWR j 9603392, dated 4 28-96 i

j 6. DC01520-067, Design Review and Capability for Rising Stem MOVs in the RH, CS and SI Systems, Revision 6 l

f 7. Fax from lke Ezekoye (West.) to Ron Osborne, GEOMETRIC

PARAMETERS FOR VALVE PRESSURE LOCK'NG ANALYSIS, dated 7-19-96 I

j 8. DC01520-050, GL 8910 MOV Weak Link Calculations J

j 9. Engineering Properties of Steel, American Society for Metals,1982 1

i j 0001520-134 Page 3 of 11

)

i i

- . - . - . __ - . - - - ~ . _ _ _ .

Enclosure 4 i RC-96-0182

Page 7 l

l i

Methodoloav: The methodology used for the determination of Ftotal is per pages 11 j through 19 of ref.1 except this calculation will use the opening valve factor rather than the closing valve factor, as discussed in assumption 2.

The opening valve factor (VFeo) will be corrected to account for the difference in the mean seat diameter versus the effective seat port dia.

l (seat port diameter plus the 1/16" seat chamfer) used in the determination of the tested opening valve factor (VF). This is necessary because the Westinghouse valves use the effective seat port area rather than mean

. seat area in the calculation of required operating thrust within the

! minimum required thrust calculations of reference 6. As such, the valve '

factor (VFeo) used within this calculat!on is determined as follows; VFeo= VF * (effective seat port radius /mean seat radius)2 j The opening structural margin evaluation will be based on a comparison of Ftotal and MAOT as follows; MARGINst = (MAOT-Ftotal)/ Feat,, l l

A positive value shows structural margin.

The opening capability margin evaluation will be based on a comparison of F,ot,i and MPOT as follows; MARGIN e,p = (MPOT - Ftotal)/Ftotal A positive value shows capability margin.

Computer Calculations: N/A (This calculation is done in Mathcad) l l

l

! 0001520-134 Page 4 of 11

l Enclosura 4 RC-96-0182 Pags 8 l This section of the program reads the sixteen items of input data from the plinput1.dat file.

l-l

[

I i .= 0.15 input := READ (plinputl)

P bonnet = inputo psi y .= inputs P up = input, psi E := inputypsi P down = input 2' Psi Dstem := input 10'I" t = input3 in Fpo := input 3lbf a .= inputgin VF = input l2 b .= inputs 'I" " " ' 13 MPOT := inputi gibf Hublength := inputgin c = mput .

i s'"

0 = inputydeg -

i 3

l l

t i

DC01520-1M Page 5 of 11

i 1 l

Enclosure 4 RC-96-0182 Page 9 i

l Program PRESLOK, Version 1 l

INPUTS:

Bonnet Pressure P bonnet " 479 ' Psi (ref. 4)

Upstream Pressure (ref. 4) P up = 0 psi i

Downstream Pressure (ref. 4) P don =0 psi Disk Thickness (ref. 7) t =2.744 in *

(taken at centerline of the hub vertically) l 4

Seat Radius (ref. 7) a v 5.011 in (corresponding to mean seat diameter)

Hub Radius (ref. 7) (taken at plane of symmetry, b = 2.694 in perpendicular to the hub, radius of circle of equivalent area for non-circular hubs) c = 4.409 in Effective Seat Port Radius (ref. 6)

~

Seat Angle (ref. 8) 0 =7 deg Poisson's Ratio (ref. 8) (disk material at temperature) v = 0.3 7

Modulus of Elasticity (ref. 9) (disk material at temperature) E = 2.8 10 psi Static Pullout Force (ref. 5) Fpo =22833 lbf .

(measured value from diagnostic test) l I

Valve Factor (ref. 6 VF = 0.65 l thrust calc.) j Stem Diameter (ref. 6) Dstem =2.5 in Hub Length (ref. 7) Hublength = 0.82 in (from inside face of disk to inside face of disk)

Open Structural Limit (ref. 6) MAOT = 140000 lbf Open Thrust Capability (ref. 6) MPOT =78445 Ibf l

! D^C'520-19 Page 6 of 11 l

l l

Enclosure 4 l RC-96-0182 i Page 10 l Program PRESLOK, Version 1 PRESSURE FORCE CALCULATIONS Open valve factor corrected for mean seat dia.

VF co := VF- { VFco = 0.503 Coefficient of friction between disk and seat:

cos(0) p = VF -

co 3 yp co,;(g),

pem Average DP across disks:

P up + P down !

DPavg .= P bonnet - DPavg =479 psi 2

Disk Stiffness Constants ,

E-(t)3 D= 2 D = 5.298 10 7 lbfin 12-(1 - v ) l E

7 G = 1.07710 psi j G = 2-(l + v) .

Geometry Factors:

C2= - 1- 1 + 2 in C2 = 0.0881 l

C3= -

+1 In + -1 C3 = 0.012 C8= - 1 + v + (1 - v)- C 8 = 0.7512 b 1+v /a\ 1-v /b\2 '

C 9=- 2 'l"lh

4 1-h C 9 = 0.2838 L 3= -

+1 In + -1 L3=0 I

0001520-134 Page 7 of 11 l l

j i

Enclosure 4 RC-96-0182 Pags 11 l

Program PRESLOK, Version 1 Geometry Factors:(continued) 2' a 1+v I-v L 9 := - ' l"

1- L9=0 2 4 L j j .= -

1 + 4- -

2+ In L j ] = 0.002

~

L 37 = - 1- 1- - -

1 + (1 + v) in L 17 = 0.0793 Moment 2

-DPavg a C9 2 M tb

Cg 2 a b (a - b ) - 17L Mtb =-1733.8 lbf l

2 Q b := 2b -(a - b ) Q b = 1587.1 -

Deflection due to pressure and bending:

2 ,3 a DPavg a#

Y bq = Mtb'3 C2 + Q b'5 C 3- D 'l 11 Y bq =-3.581710-5 g, Deflection due to pressure and shear stress:

K sa = - 0.3 - 2in -1+ Ksa "41591 DPavg a 2 K sa y sq

tG Y Sq = .4 104 in Deflection due to hub stretch:

2 2 P force = x-(a - b ) DPavg P force Hub length 5 Y stretch

Y stretch = 1.7253 10 in

,2 (2 E)

DC01520-134 Page 8 of 11 i

i

! Enclosure 4 RC-96-0182 Page 12 i

l Program PRESLOK, Version 1 l

Total deflection due to pressure forces (per Ibflin.): I Y q Y bq + Y sq - Y stretch d y q = -1.1782 10 in Deflection due to seat contact force and shear stress (per Ibflin.):

7 in -

ysw '~ tG Y sw =-1.263 10 Ibf Deflection due to seat contact force and bending (per Ibflin.):

l aM ' fC2) aC9 _a in

-L 9 -

C3 *L 3 Y bw =-9.41 10 Ybw* M b Deflection due to hub compression:

l fna 2 Hub lengthI ~g in Y cmpr - 2 2E Y cmpr =-2.022 10 -

\n b j l Total deflection due to seat contact force (per Ibflin.):

-7 y w :" Y bw + Y sw + Y cmpr Y w =-2.406 10 -

! Seat Contact Force for which deflection is equal to previously calculated deflection from pressure forces:

i Y

! F s=2na q F s = 15417.3 lbf l 1w l

l l

l 4

i 0C01520-134 Page 9 of 11

Enclosure 4 RC-96-0182 Page 13 UNSEATING FORCES F packing is included in measured static pullout Force K 2 F piston T Dstem P bonnet F piston =2351.3 Ibf 2

F vert = x a sin (0)-(2 P bonnet - P up - Pdown) F vert = 9210 lbf F preslock = 2 Fs -(pcos(0)- sin (0))

F preslock = 10644.6 lbf F total '= -F piston + F vert + F preslock + F po F po =22833 lbf F total =40336.3 lbf MARGIN EVALUATION MAOT - Ftotal MARGINst

F total MARGINst =247.1 %

MPOT F total MARGIN cap

p total MARGINcap = 94.48 %

CONCLUSION: Based on the methods used throughout this calculation,it can be concluded that XVG08889-SI is capable of overcoming the postulated pressure locking forces.

D^0*520-134 Page 10 of 11

i l Enclosure 4 i

RC-96-0182 Page 14 l

ENGINEERS Serial 13157 TECHNICAL WORK RECORD Engineer RLJ ?$k Date 7/24/96/

l I

Project Title DC01520-134 VERIFICATION Tab 95-7R1 Page i 1

l THIS IS A VERIFICATION IN ACCORDANCE WITH ES - 412 & 110.

l DESIGN CALCULATION DC0152-134 REV.0 " Force Required to Overcome

! Pressure Locking of XVG08889-SI" meets all of the requirements of !

ES-412 And ES-110.

j CALCUIATION EVALUATION :

1, Calculation DC0152-134 REV.0 includes all necessary information. '

Inputs are correctly incorporated into the calculation.

l 2, Assumptions are reasonable, are adequately described and are

! justifiable.

l i

3, The Methodology is consistent with industry pressure locking ;

thrust calculations. The Commonwealth Edision methodology is !

recognized by the industry and the NRC as one of the best.

l 4, All references are adequately defined.

5, All other design verification questions listed on attachment II of ES-110 are not applicable to this design calculation.

6, The calculation, which was performed in MATHCAD, was verified l

by perfoming the sample problem given in Westinghouse letter ESBU/WOG-96-050, dated February 13, 1996 and verifying the l proper MATHCAD outputs.

i I

CONCLUSION: CALCULATION DC0152-134 IS CORRECT AS IT IS WRITTEN l PER ES-412 AND 110.

1 ROBERT L JUSTI ~

Systems Engineering W

k l

l

4 e

l j Enclosure 5

RC-96-0182

Page1 VCSNS RESPONSE TO THE REQUEST FOR ADDITIOREAL INFORMATION CONCERNING i

THE STATIONS INITIAL GENERIC LETTER 95-07 " PRESSURE LOCKING AND l TaunuaL EINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES"

SUENITTAL.

i i

PURPOSE

! This enclosure provides the additional information requested in part

!- 5 of the enclosure to the NRC letter to Mr. Taylor, dated July 3, i 1996-(REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER 95-07,

" PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER j OPERATED GATE VALVES," VIRGIL C. SUMMER NUCLEAR STATION (TAC NO.

! M93525).

1 ADDITIO3thL INFORMATION REQUESTED l 5. "Through review of operational experience feedback, the staff is j aware of instances where licensees have completed design or procedural modifications to preclude pressure locking or thermal j binding which may have had an adverse impact on plant safety due to i incomplete or incorrect evaluation of the potential effects of these j modifications. Please describe evaluations and training for plant i personnel that have been conducted for each design or procedural I

modification completed to address potential pressure locking or thermal binding concerns".

VCSNS ADDITIONAL INFORMATION:

5. The Recirculation Sump to RHR/LHSI Pump A/B valves (XVG08811A,B-SI and XVG08812A,B-SI) had holes drilled in their discs to mitigate potential pressure locking conditions. The valve discs were modified per MRF 22765B. The 10CFR50.59 screening evaluation is attached (See Attachment I). Plant personnel were trained on MRF 22765B as it relates to plant operation during licensed operator requal training (See Attachment II).

The following surveillance test procedures were modified to address potential pressure locking concerns:

Surveillance test procedure STP-220.001A " Motor Driven Emergency Feedwater Pump and Valve Test" was revised to require monitoring the opposite train's pressure during the test. The 10CFR50.59 screening evaluation is attached (See Attachment III).

Surveillance test procedure STP-205.004 "RHR Pump and Valve Operability Test" was revised to eliminate the requirement for closing the valves XVG0888A,B-SI (LHSI to RCS Cold Legs) during the performance of the test, in operational modes 1 through 3. The 10CFR50.59 screening evaluation is attached (See Attachment IV). I i

I

1 Enclosure 5 Rc-96-0182 Page 2 Surveillance test procedure STP-212.002 " Reactor Building Spray Pump Test" was revised to require monitoring the opposite train's pressure during the test and to require manually opening the valve (XVG03003A(B)-SP) on the tested train, after performing the pump test, to ensure the valve's bonnet cavity is vented. The 10CFR50.59 screening evaluation is attached (See Attachment V).

Surveillance test procedure STP-223.002A " Service Water System Pump Test" was revised to require that valves XVG03109A,B,C,D-SW be placed in the open position during the pump test. The 10CFR50.59 screening evaluation is attached (See Attachment VI).

The discipline supervisor responsible for the procedure changes determined that the changes did not require special training.

l

Enclosure 5 Attachment I RC-96-0182 Page 1 of 7 10CFR50.59 SCREENING PROCESS WORKSHEET PARENT DOCUMENT MRF 22765 REV. MCN B Activity Description Pressure Lockina of SI Sumo Recirc Valves Screening Ouestions:

Yes No A. Does the activity represent a change to the procedures described O E in the FSAR or FPER?

Discussion of the basis for the answer. De base MRF was a temoorary decian chance that did address orocedures described in the FSAR with respect to an added surveillance and valve strokina after RHR operation.

MCN B will be a permanent chance that will no lonaer recuire the added surveillance or the valve strokina.

N 5 +

B. Does the activity represent a change to the facility as descr; bed E O in the FSAR or FPER?

Discussion of the basis for the answer: MRF 22765 MCN B will be a permanent desian chanae to XVG08811 A. XVG08811B. XVG08812 A.

and XVG08812B. These valves are described in FSAR sections :

6.2.4.2.2 and 6.3.2.2.6.1 and are listed in FSAR Tables 6.2-53a and 6.2-54. l Yes No !

C. Does the activity represent a test or experiment not described in O E the FSAR or FPER?

Discussion of the basis for the answer: The activity is neither a test nor an experiment. Drillina a hole in the hiah oressure side flexible wedae cate valve discs is a commonly accepted means of orecludina oressure lockina and is recommended by INPO and NRC. ~

Yes No D. Does the activity represent a change to the Technical Specifications? O E Discussion of the basis for the answer The proposed activity will not affect the desian function of the valves with respect to containment isol- l ation or RHR operation: therefore. Tech Soec ooerability of these valves will be unaffected bv this chance. No chanae to Tech Specs is reauired.

NAL /T %lV- ? V /J. JD . !l l, Ih3h3 I'reparers Signatup Date Independent Revhiwers Signi Date cso armr Approval Signature

&&r' D' ate

l Enclosure 5 Attachmant I RC-96-0.18 2 Page 2 of 7 VIRGIL C. SUMMER NUCLEAR STATION 10CFR50.59 SAFETY EVALUATION WORKSHEET l Check Applicable Yes [ ] and No ( ) Indications PARENTDOCUMENT MtF 2 Does this evaluation change the Final Safety Analysis Report ACA/ 6 i or Fire Protection Evaluation Report?

l I TECH. SPEC. REFERENCE FSAR/FPER REFERENCE Section Page Yes (( No[ ] Chapter Section Page 3- b ~

[p

, 6.2.Y.2.E ~'-"

.+

3.S.3 is a change in Tech. (g 6. 3. L 2.6.1 -

g , g, y Specification involved? l g ray a-m !

.n W ,

Not aodressed in

' Tsf sle ( 2 - 714 Tecn Specs. [ ] Yes[ ] No(( Not addressed in !

u F5AR/FPER [ ]

u l l

UNREVIEWED SAFETY QUESTION DETERMINATION: i l

Answer the seven questions on pages 2 and 3. Provide specific reasons

/ justifying the decision for the "yes" or "no" answers.

Nuc. U c. Reviewer Date NOTE:

u j l PSRC/NSRC Restatement of the question in a negative sense or making a simple Review statement of conclusion is not sufficient and shall be avoided. It is recognized, however, that for certain very simple activities, a statement of the conclusion with identification of references consulted to support the conclusion will be adequate.

Recuest and Receive l Nuclear Regulatory Commission Authorization Complete the items below after the questions on pages 2 and 3 have l For Change Prior been addressed.

l To implementation -

l ' Of the Subject Change 1

l U

Authorization '

Denied Any Answer Yes [ ] All Answers No [@

"3 y v Abort _

Authorization Initiate

~

The Change Received The Change l *lf answer (1)is "yes" but answers (2) and (3) are "no", hh / T Date ad Engm.eer/Weppr l then the change is reportable under 10CFR50.59b and a description of the change will be included in the Annual '

jp p*

Report. If answer (2)is "yes" then 10CFR50.59 is not D' applicable. Proceed to 10CFR50.90.

In epen ent Review ate t

1 c)nM ApproiTai signature

/70[dc Dhte l

1

Enclosure 5 Attachm2nt I RC-96 .0182 Page 3.of 7 10CFR50.59 SAFETY EVALUATION QUESTIONS PARENT DOCUMENT ///E22767 AM/$

.Y.E.S_ N0

1. May the proposed activity increase the probability I of occurrence of an accident previously evaluated in the FSAR or FPER?

Basis: 6@ O oe Th./

YES NO

2. May the proposed activity increase the X consequences of an accident previously evaluated in the FSAR or FPER?

Basis: boa 4 ebc b s YE5 NO

3. May the proposed activity increase the probability Y 1 of occurrence of a malfunction of equipment I important to safety previously evaluated in the FSAR or FPER?

Basis: 50" 0 7b r Dl TUk -

YES NO 4 May the proposed activity increase the consequences X of a malfunction of equipment important to safety previously evaluated in the FSAR or FPER?

Basis: $N 4 Ch [f*T

Enclosure 5 Attachm:nt I RC-96-0182 Page 4 of 7.

PARENT DOCUMENT g//1/7gf //(#/J YES g

5. May the proposef activity create the possibility of an y" accident of a different type than any previously evaluated ~

in the FSAR or FPER?

Basis: he o c[/ TL4/[

YES g

6. May the proposed activity create the possibility of a [

different type of malfunction of equipment important to safety than any previously evaluated in the FSAR or FPER?

Basis: Sea o c[ c/ ft~7M YES NO

7. Does the proposed activity reduce the margin of safety X as defined in the basis for any technical specification?

Basis: See a7%cl,/ 7 t d /f NOTE: Attach additional supportive documentation to this form.

1 l

e

Enclosure 5 Attechm:nt I l RC-96-0182 1 Page 5 of 7 l

t l

ENGINEERS Serial 11917 TECHNICAL WORK RECORD Fngineer M.Dantzler Date 9-15-95 ,

1 1

Project Title 10CFR50.59 Evaluation for MRF 22765. MCN B Tab _14. Page_i_of

1. May the proposed activity increase the probability of oceturence of an accident pmviously evaluated in the FSAR orFPER? NO Basis: The proposed change will result in a hole being drilled on the RB side of the discs of the ;

XVG08811 valves, and a hole on the RHR side of the XVG08812 valves. This activity will not mcrease I the probability of occurrence of accidents as described in chapters 6 and 15 of the FSAR nor willit affect #

the evaluations of the FPER. Supporung factors are:

Although the design of the valves will be altered by the hole, the structural integrity of the discs l

will be unaffected (see Wesunghouse letter #CGE-95-030).

Re overall system performance will be =6cted by the modification. The valves will become l unidirectional as a result of this modification, but this will not affect the function for which these l valves am designed. The XVG08811 valves will still seal against RB pressure. and the XVG08812 valves will still seal against RER system pmssure. Individually, these valves will l provide uni-ducc:ionalisolation; however. in tandem, they will provide bi-ducctionalisolation. )

l

These valves provide isolation between the SI Recuculation Sump and the RBR system. They l automatically open during an SI when the RWST rnh its Lo-lo level in order to place the plant in the niuculation mode for accident mitigation. These valves. and their interfaces with I

other equipment / systems, have no effect on the probability of the initiation of accidents described l in the FSAR or FPER. i 1

2. May the proposed activity increase the consequences of an accident previously evaluated in the FSAR j orFPER? NO l

Basis: The XVG08811 valves and the XVG08812 valves function to provide a path for low head and high head post-LOCA recirculation. The XVG08811 valves also function as containment isolation valves. The prtposed modification to these valves will not adversely affect these functions, and. therefore. it will not increase the consequences of accidents previously evaluated in the FS AR or FPER. Supporang factors am:

He purpose of the proposed modification is to provide additional assurance that the valves will not become pressure-locked, and will open when na-dedto provide a post-LOCA recirculation path, thereby mitigating the radiological consequences of a LOCA.

Le modification to the XVG08811 valves will not degrade the function of these valves as containment isolation valves. Flexible wedge gate valves utilize a difference in system pressure to wedge the disc against the seat opposite the higher system pressme. This seat, then,is the sealing boundary for the valve disc. Since the XVG08811 valves must seal against RB design pressure in their function as containment isolation valves, seahng must occur at the seat opposite to the RB. Drilhng the hole on the RB side of the disc willnot affect the capability of this valve to isolate against RB pressure since sealing will occur at the seat opposite to the RB.

Enclosure.5 Attachatnt I RC-96-0182 Page 6 of 7

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1

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ENGINEERS Scrial 11917 TECHNICAL WORK RECORD

~

Engineer M.Dantzler Date 9-15-95 i Project Tille 10CFR50.59 Evaluation for MRF 22765. MCN B Tab _14., Page.2_of

3. May the proposed actisity increase the probability of occurrence of a malfunction of equipment imponant to safety previousi) cvaluated in the FSAR or FPER? NO l

Basis: The XVGG881 halves and the XVG08812 vah es arc safe shutdown components (SSC); however. y l the proposed modification will have negligible effects on the structural integrity of the valves' discs and will. in fact. increase the reliability of the vah es by ensuring that they will not be susceptible to pressure locking. No other important to safety ( ITS) equipment will be affected, either directly or indirectly. by this modification. Supponing factors are: .

. The proposed size and location of the hole will not affect the structural integrity of the discs irefer to Westinghouse letter CGE-95-030).

The hole will provide a drain path from the bonnet to the high pressure side of the valve thereby providing assurance against pressure locking.

. Although. individually the valves will provide uni-directional isolation. in tandem they will maintain bi-directional isolation capability; therefore. interfaces with other ITS equipment will be unaffected by this modification. ,

4. May the proposed activity increase the consequenecs of a malfunction of equipment imponam to safety previously evaluated in the FSAR or FPER? NO Basis: The proposed change will not result in a different response of the ECCS or safety related systems and components to accidem scenarios tfian that postulaicd in the FSAR or FPER. No new equipment malfunctions will be introduced that will affect fission product barrier integrity. Therefore. it is concluded that the proposed changes will not inercase the consequences of a malfunction of equipment imponant to safet) previously evaluated in the FSAR or FPER. -

5. May the proposed activity create the possibility of an accident of a different type than any previously evaluated in the FSAR or FPER? NO Basis: The proposed change will not cause the initiation of an accident. create any new limiting single failure. or resuh in any event previously deemed incredible being made credible. As such. the change will not crease the possibility of an accident different than any evaluated in the FSAR or FPER.

6 May the proposed activity create the possibility of a different type of nalfunction of equipmem imponant to safety than any previously evaluated in the FSAR or FPER? NO Basis The proposed change will not adversci) affect the operation of the Reactor Protection System.

Engineering Safety Features. or other sysicms. components. or devices required for accident mitigation.

Thes: 53 sicms. including the ECCS. will remain qualified and capable to perform their design function F

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I'~ 4 Enclosure 5

,Attachutnt I RC-96-0182 Page 7 of 7 i

ENGINEERS Scrial 11917 TECHNICAL WORK RECORD Engineer M.Dantzler i

Date 9-15-95 Project Title 10CFR50.59 Evaluation for MRF 22765. MCN B Tab _]ff. Pagelof for the proposed change. Therefore. the proposed chanyc will not create the possibility of a malfunction

) of equipment imponant to safety different than previously evaluated in the FSAR or FPER.

i

7. Does the proposed activity reduce the margin of safety as defined in the basis for any Technical .;p Specification? NO Ba is: The proposed modification will not afTect any margin of safety as described in the Tech. S'pecs..

FSAR. FPER. or SER. The modification will affect containment isolation valves. XVG08Sil A.B; .

however. the modification will not affcci the side of the disc (RHR side) which is utilized for isolating containment. therefore, the type C Icsting leak raics for Ihese valves will be unalTected.

i k

l

. Enclosure 5 Attcchmtnt II RC-96-0182 Page 1 of 5 NUCLEAR OPERATION TRAINING PLANT MODIFICATIONS CYCLE 9 MRFs REFUEL MRFs REFUEL MRFs MRF-22305 MRF-90109 MRF-90112 .

MCN-90009D MRF-22737 MRF-22755 l l

MRF-22291 MRF-90107 MRF-90109A l MRF-22467 MRF-22177G MRF-90102 MRF-22741 MRF-22765B MRF-21042B l

MRF-22769 MRF-22771 MRF-22769B, C, &D l MRF-22766 ETBT 411 MRF-22742 MRF-22410 MRF-90102D MRF-22766B MRF-22764 MRF-90102A MRF-22657D MRF-22553 MRF-22293 MRF-22654 LESSON PLAN REVISION 0

~

TIME: 1.0 HOUR 9

Recommended W f. / L Date YhMU j S

0 Approved SW C- h Date Ihf NG A

SemorInstructor, Development

Enclosure 5

- - Attechmsnt II 4 RC-96-0182 l Page 2 of 5 )

L _ OBJECTIVES

3. .

A. TERMINAL OBJECTIVE The student shall be able to relate the plant

, modification to the operation of the V.C. Summer Station.

B.

ENABLING OBJECTIVES: The student shall be able to:

I

\

1.

OUTLINE the background that necessitated the need to change plant eqtupment.

I

2. STATE the purpose (s) for the modification.

3. DESCRIBE the system / component changes.

l

4. RELATE the changes of the modification to the operation of the V.C.

Summer Station, including System Operating Procedure, Technical Specifications, gc.

i D;WCSl\LPWORD\MRFMCNLP. DOC 1

Encloaure 5 Attachmtnt 11 RC-96-0182 Page 3 of 5 H. DETAILED DESCRIPTION A. Cvele 9 MRFs

1. MRF-22305 RMA0005A(B) Removal j

a. Removed RMA0005A(B), Auxiliary Building Charcoal Plenum ;

radiation monitors.

b. Had a poor operating history and had been inoperable for several years. >

c. No regulatory requirements for these monitors.

2. MCN-90009D MSR Tube Bundle Replacement '

a. Replaced the MSR tube bundle in 1993.

b. MCN D made minor changes to the forth stage drain valve logic. ;

c. The base MRF had the drain valve to heater 1 A(B) open when I

1) power was greater then 40 percent,

2) heater level was not at the Hi-Hi setpoint

3) Reheater Drain Tank dump valve to the condenser was not l

opened.

'a) Once the forth stage drain to the heater is opened, the drain valve to the condenser closes.

d. MCN D added an additionalinput '

e. In summary, when the following conditions are met, the forth stage drain valve to number I heater, XVT02068A(B) will open:

1. XVG02859A-MS, main steam line to MSR drain valve, is closed

2. Power level is greater than 40 percent (IPS05636)

3. Heater I A(B) level is less than its HI-HI level setpoint

4. ILV03704 (ILV03714) Reheater Drain Tank Condenser Dump Valve,is closed i

D:WCSl\LPWORD\MRFMCNLP. DOC 2

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_- . . _ . - . _ _ . _ . _ ~ _ _ _ _ . _ - _ _ . _ _ . _ _ _ _ _ _ . . ._ _ _ . - _ _ . - ___ ._ _

Enclosure 5 ,

j',' .

Attachmznt II ;

l , RC-96-0182 -t Pegs 4 of 5 I

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4.- MRF- 22177GCHANGE TO LOW FLOW SETPOINT ON RML-8 m

., a. MCN G of MRF 22177 changes the low flow setpoint of RML-8 from 1.9 gpm to 4.0 gpm decreasing

b. Requires RML-8 to be manually reset after sufficient flow is re-l established from a low flow condition. i l l l

5. MRF 22765B Press Lock of SI Sump Recire Valves i

a. IN 95-14 ,

b. Pressure locking of the containment sump isolation valves l MVG08811 A(B)-SI and MVG08812A(B)-SI due to high l

temperature sump water following a LOCA.

c. Fluid becomes pressurized within the valve bonnet and that this pressurization creates a differential pressure across the valve disc

d. Preventing the actuator from overcoming the added thrust requirements. j

e. Valves would therefore fail in the closed direction, resulting in a loss of all SI flow following RWST depletion.

f. MRF 22765 provided a temporary solution

g. Established 10 foot water seal between the SI sumps and the valves.

h. Limit the temperature rise in the valve bonnet during' post LOCA j conditions. !

i. Limit the pressurization within the disc to within the capability of the valve actuato'r.

j. The MRF also required that the valves be stroked following decay l heat removalwith the RHR system.

k. Relieve any pressure that built up within the disc during the cooldown operation.

l

1. RWST maximum allowed level was reduced by 1%.

m. The level in the sump was limited to the 408' elevation

n. Sump water had to be at a boron concentration equal to the RWST.

D:WCS)'i.PWORD\MRFMCNLP. DOC 6

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. .- Enclosure 5 Attachmtnt II RC-96-0182 Page 5 of 5 l

o. A quarterly sun eillance was implemented to verify that the water m

leg was still there

p. Permanent fix is holes drilled through valve discs

6. MRF 22771 RC SYSTEM VENTING

a. Each outage, PVC piping is installed in the Reactor Building (RB)

, from the PRT and RCDT to the top of the pressurizer and then to the RB purge exhaust manifold

b. Purge gases from the tanks without contaminating the RB.

c. Cost ofinstallation and removalis $12,500.00 per outage.

d. Replace the PVC piping will steel pipe and tube.

7. ETBT 411 Loose Parts Monitoring System

a. Siemens Loose Parts Monitoring System (LPMS)

b. Detects loose parts in the Reactor Coolant System (RCS)

c. Structure-borne acoustic signals that originate from pans hitting against the walls orinternals.

d. Accomplished by using piezoelectric accelerometers with sensitivity in the audible frequency range.

e. Components are located in the same location as the old system.

f. Once the system is in place and is in automatic,' there are no operational procedures for the actual monitoring process.

g. Observation of the system entails the following:

1) Periodically check system switches set to normal.

2) Watch for LED indication of trouble in Signal Conditioning Unit of the LPMS.

3) Check the Main Computer Monitor for error messages.

4) Periodically listen to the audiochannels to detect differences l

in sound.

5) Acknowledge event alarm or system failure alarm.

i i

D:WCSl\LPWORD\MRFMCNLP. DOC 7

Enclosura 5 Attachment III SAP .107 RC-96-0182 REVISION O

8 10 CFR 50.59 SCREENING PROCESS WORKSHEET PARENT DOCUMENT STP-220.001 A REV. 4 CHANGE B Activity

Description:

The proposed activity is Change B to Revision 4 of STP-220.001 A. The purpose of this change was to incorporate the following:

Steps 6.6,6.7,6.8 and 6.9, added CO2i n accordance with RC-96-0032, Response to GL 95-07, Pressure Locking and Thermal Binding of SR Power Operated Gate Valves.

Renumbered Step 8.3.4 to 8.3.6 and added Not Pcap per NCN-4099, Suction Piping Over - Pressure Concem,2-7-91. ,

Added Step 9.9, RC-96-0032, Response to GL 95-07, Pressure Locking and Thermal i Binding of SR Power Operated Gate Valves l Added Steps 8.3.4 and 8.3.5 and associated C02 Peap in accordance with RC-96-0032, Response to GL 95-07 Pressure Locking and Thermal Binding of SR Power Operated Gate Valves.

Attachment IVA, corrected step number from 5.5.3 to 5.1.3 to correct typo.

Attachment IVA and VA, Steps 6.6.2.C and 6.8.5, added CO2 and changed the peak suction header pressure limit from <275 psig to 100 psig in accordance.with the commitment requirements of the \EC. Summer $ response to GL 95-07, Pressurs Locking and Thermal Binding of SR Power Operated Gate Valves.

~

Attachment IVB, corrected step number from 5.5.3 to 5.1.3 to correct typo.

Attachment IVB and VB, Steps 6.7.2.C and 6.9.5, added CO2 and changed the peak suction header pressure limit from 5275 psig to 100 asig in accordance with RC-96-0032, Response to GL 95-07, Pressure Locking $and Wermal Binding of SR Power Operated Gate Valves.

Updated procedure format as suggested during the procedure review process.

The original intent of this procedure was to perform periodic surveillance testing of Emergen,cy Feedwater System components in accordance with GTP-301 and GTP-302 as required by FSAR Section 5.7.7 and Technical Specification Sunreillance Requirements 4.0.5,4.7.1.2.a.1 and 4.3.2.1 Table 4.3-2 Items 6a and 6b. This original intent remains unchanged.

i Page 1 of 3

Enclosure 5 l Attachment III SAP-107 RC'96-0182 REVISION O Page 2 of 3 .

10 CFR 50.59 SCREENING PROCESS WORKSHEET-PARENT DOCUMENT STP-220.001 A REV. 4 CHANGE B Screening Ouestions:

YES NO A. Does the activity represent a change to the procedures described in X the FSAR or FPER?

FSAR Section 5.7.7 states the rec ulrements to perform the surveillance test activities performed by STP-220.001 A. FSA9 Section 13.5.8 describes the general content of a Surveillance Test Procedure. However no system or component specific details are presented by these FSAR Sections. .

FSAR Section 7.3.2.2.5 describes in general the testing methodology of the Engineered Safety Features Actuation System but does not provide specific detail into the testing of each associated component.

FSAR Section 10.4.9 states that testing of the Emergency Feedwater Pumps will be conducted in accordance with ASME Section XI but does not provide any specific details as to the test methodology or procedure to be used.

Based on the above statements, the description of the proposed activity, and the review of FSAR Sections 5.7.7,7.3.2,10.4.9 and 13.5, the proposed activity does not represent a change to procedures as described in the FSAR or FPER.

' YES NO B. Does the activity represent a change to the facility as described X in the FSAR or FPER7 STP-220.001A is designed to perform surveillance testing of the Motor Driven Emergency Feedwater Pumps utiiizing existing plant components, controls, test connections, process instruments and the installed testing capabilities of the Engineered Safety Features Actuation System. No modifications or changes to the plant are represented by this surveillance test procedure.

Based on the above statements, the description of the proposed activity, and the review of FSAR Sections 5.7.7, 7.3.2, and 10.4.9, the proposed activity does not ,

represent a change to the facility as described in the FSAR or FPER.

l Page 2 of 3

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Enclosure 5 Attachant III SAP-107 RC-96-0182 REVISION 0 Page 3 of 3 10 CFR 50.59 SCREENING PROCESS WORKSHEET PARENT DOCUMENT STP-220.001 A REV. 4 CHANGE B 4

YES NO C. Does the activity represent a test or experiment not described in X 2

the FSAR or FPER?

STP-220.001 A is designed to perform surveillance testing of the Motor Driven

. Emergency Feedwater Pumps utilizing existing plant components, controls, test

connections, process instruments and the installed testing capabilities of the Engineered Safety Features Actuation System. This testing is performed as required by FSAR Sections 5.7.7,7.3.2.2.5 and 10.4.9.

, Based on the above statements, the review of FSAR Sections 5.7.7,7.3.2, and 10.4.9, t rop activity does not represent a test or experiment not described in the YES NO D. Does the activity represent a change to the Technical X

Specifications?

in addition to "C" above STP-220.001A is designed to perform surveillance testing of the Motor Driven Emergency Feedwater Pumps in accordance with Technical Specification Surveillance Requirements 4.0.5, 4.7.1.2.a.1, and 4.3.2.1 Table 4.3-2 Items 6a and 6b. The proposed change has not altered this requirement.

Based on the above statements, the description of the proposed activity, and the review of Technical Specification Surveillance Requirements 4.0.5, 4.7.1.2.a.1, and 4.3.2.1 Table 4.3-2 Items 6a and 6b and Technical Specifications 3.3.2 and 3.7.1.2, the proposed activity does not represent a change to Technical Specifications.

'hk 2. u-9 c w .1..u - %

Preparer's Signature Date independent Reviewer's Signature /Date

>b M LLh b Approbl Signature Date Page 3 of 3

, Enc 1,osure 5 Attachm:nt IV SAP-107 RC-96-0182 REVISION O Page 1 of 3 10 CFR 50.59 SCREENING PROCESS WORKSHEET

! PARENT DOCUMENT STP-205.004 REV. 2 CHANGE B l

Activity

Description:

The pro aosed actMty is Change B to Revision 2 of STP-205.004. The purpose of th!s change s to incorporate the following:

, 1. Address'the requirements of RTS# LTR950007. This was accomplished by adding Ste as 6.1.4 and 6.2.4, in which XVG08888A-Si and XVG088888-Si are closed only in Modes 4, 5 or 6. Attachments llA and IIB were changed to ensure that XVG08888A-SI and XVG08888B-SI remain open in modes 1,2 and 3. Maintaining XVG08888A-Si and XVG08888B-S1 open during testing while in Modes 1,2 or 3 will have no effect on the performance of the required testing.

2. Address the recommendation of RTS# ONO 950204. This was accomplished by addinas Steps 6.1.9.C and 6 2.9.C, which provide guidance for depressurization of RHR Tieader A or B if the pressure indicated on the associated Field Standard is greater than 60 psig. The depressurization is accomplished using the local sample connections installed on each RHR header. Attachments llA and IIB were updated to include the valves manipulated during Steps 6.1.9.C and 6.2.9.C.

The original intent of this procedure was to perform inservice testing of the Residual i Heat Removal System / Safety injection System components in accordance with the requirements of FSAR Section 5.7.7 and Technical Specification 4.0.5. This intent remains unchanged.

Screening Questions:- '

YES NO A. Does the activity represent a change to the procedures described in X the FSAR or FPER?

FSAR Section 5.7.7 states the requirements to perform the surveillance test activities performed by STP-205.004. FSAR Section 13.5.8 describes the general content of a Surveillance Test Procedure. However,' no system or component specific details are presented by these FSAR Sections.

FSAR Section 6.3.4 describes in general the test activities that are performed during testing of the RHR and Safety injection System components but does not provide specific detall into the testing of each associated component. FSAR Section 6.3.4.4 states testing of RHR and Safety injection System components will be conducted in accordance with ASME Section Xi but does not provide any specific details as to the test methodology or procedure to be used.

Based on the above statements, the description of the proposed activity, and the review of FSAR Sections 5.7.7,6.3 and 13.5, the proposed activity does not represent a change to procedures as described in the FSAR or FPER.

I Page 1 of 3 l

Attachunt IV SAP-107 RC-96-0182 REVISION O Page 2 of 3 l 10 CFR 50.59 SCREENING PROCESS WORKSHEET PARENT DOCUMENT STP-205.004 REV. 2 CHANGE B YES NO B. Does the activity represent a change to the facility as described X in the FSAR or FPER?

The purpose of this procedure is to perform inservice testing of Residual Heat Removal System / Safety injection System components in accordance with the requirements of FSAR Section 5.7.7. I i

FSAR Section 6.3.4 describes in general the test activities that are performed during !

testing of the RHR and Safety injection System components but does not provide l specific detall into the testing of each associated component. FSAR Section 6.3.4.4 I states testing of RHR and Safety injection System components will be conducted in :

accordance with ASME Section XI but does not provide any specific details as to the j test methodology or procedure to be used.

The test activities performed by STP-205.004 are conducted using installed plant components, controls and test connections. No modifications to the facility are l performed or required by the performance of STP-205.004.

Based on the above statements, the description of the pro 3osed activity, and the review of FSAR Sections 5.7.7, 6.3 and 13.5, the proposed ac ivity does not represent a change to the facility as described in the FSAR or FPER.

YES NO C. Does the activity represent a test or experiment not described in X i the FSAR or FPER? i The purpose of this procedure is to perform inservice testing of Residual Heat l Removal System / Safety injection System components in accordance with the requirements of FSAR Section 5.7.7.

FSAR Section 6.3.4 describes in g testing of the RHR and Safety Inj,eneral the components ection System test activities butthat doesare notperformed provide during specific detail into the testing of each associated component. FSAR Section 6.3.4.4 states testing of RHR and Safety injection System components will be conducted in accordance with ASME Section XI but does not provide any specific details as to the test methodology or procedure to be used.

Based on the above statements, the description of the proposed activity, and the review of FSAR Sections 5.7.7,6.3 and 13.5, the proposed activity does not represent a test or experiment not described in the FSAR or FPER.

Page 2of 3

Enclosure 5 Attachm:nt IV SAP-107 REVISION 0 RC-96-0182 Pa*ge 3 of 3 10 CFR 50.59 SCREENING PROCESS WORKSHEET .

PARENT DOCUMENT STP-205.004 REV. 2 CHANGE B-YES NO D. Does the activity represent a change to the Technical X Specifications?

In addition to !C" ab6ve, STP-205.004 is designed to perforrn surveillance testing of RHR and Safety injection System components in accordance with Technical Specification Surveillance Requirements 4.0.5, 4.5.2.f.2 and 4.5.3.1. The proposed change has not altered this intent.

Based on the above statements, the description of the proposed activity, and the review of Technical Specification Surveillance Requirements 4.0.5, 4.5.2.f.2 and 4.5.3.1 and Technical Specifications 3.4.1.3, 3.4.1.4.1, 3.4.1.4.2, 3.5.2, 3.5.3, 3.9.7.1, and 3.9.7.2, the proposed activity does not represent a change o echni 1 Specifications.

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% 2-27-fg Preparer's Signature Date independent RevEwer's Signature /Date 2lh}%

Approval Signature Date ,

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i b,l 1-Page 3 of 3 )

Enclosura 5 Attachm:nt y SAP-107 RC-96-0182 REVISION 0 8

10 CFR 50.59 SCREENING PROCESS WORKSHEET PARENT DOCUMENT STP-212.002 REV.,2_ CHANGE C Activity

Description:

The proposed activity is Change C to Revision 2 of STP-212.002. The purpose of this change was to incorporate the following:

1. Steps 6.1.4.G, 6.1.4.J, 6.1.5.D, 6.2.4.G, 6.2.4.J and 6.2.5.D, added to monitor the opposite train of Reactor Building Spray for any increase in system pressure dunng testing. Attachments lilA and lilB, added data blocks to record opposite train pressures.

2. Steps 6.1.6.A and 6.2.6.A, added steps to manually verify that XVG03003A/B-SP were not pressure locked following the completion of pump testing. This also included the performance of a complete valve stroke cycle for XVG03003A/B-SP following closure of the power suoply breaker to ensure that the MOV will operate satisfactorily following manua operation.

3. Steps 8.3.4 and 8.3.5, added to incorporate the limit of 80 psig for the pressure increase of the opposite train during pump testing.

4. Step 9.7, incorporated reference to RC-96-0032, response to GL 95-07,

5. Added Coi Pcap as required to preserve the responses to GL 95-07 as recorded in RC-96-0032.

The original intent of this procedure was to perform periodic surveillance testing of Reactor Building Spray System components in accordance with GTP-301 and GTP-302 as required by FSAR Section 5.7.7 and Technical Specification Surveillance Requirements 4.0.5, 4.6.2.1.b, 4.3.2.1 Table 4.3-2 Item 2.b, and 4.8.4.2.a. This original intent remains unchanged.

Screening Ouestions:

YES NO A. Does the activity represent a change to the procedures described in X the FSAR or FPER7 FSAR Section 5.7.7 states the requirements to perform the surveillance test activities performed by STP-212.002. FSAR Section 13.5.8 describes the general content of a Surveillance Test Procedure. However no system or component specific details are presented by these FSAR Sections.

FSAR Section 7.3.2.2.5 describes in general the testing methodology of the Engineered Safety Features Actuation System but does not provide specific detail into the testing of each associated component.

FSAR Section 6.2.2.4.1.1, System Actuation Tests, describes the testing methodology incorporated by this procedure for the testing of K644, Spray Actuation Relays.

Page 1 of 3

Enclosure 5 <

Attachm:nt V SAP-107 !

- RC-96-0182 REVISION 0 age 2 d 3 10 CFR 50.59 SCREENING PROCESS WORKSHEET PARENT DOCUMENT STP-212.002 REV. 2_. CHANGE C FSAR Section 6.2.2.4.1 states that testing of the Reactor Building Spray System will be conducted in accordance with ASME Section XI but does not provide any specific ;

details as to the test methodology or procedure to be used.

Based on the above statements, the description of the proposed activity, and the review of FSAR Sections 5.7.7,6.2.2, 7.3.2, and 13.5, the proposed activity does not represent a change to procedures as described in the FSAR or FPER.

YES NO i

B. Does the activity represent a change to the facility as described X in the FSAR or FPER?

4 STP-212.002 is designed to perform survelliance testing of Reactor Building Spray System components utilizing existing plant components, controls, test connections, 3rocess instruments and the installed testing capabilities of the Engineered Safety eatures Actuation System. No modifications or changes to the plant are I represented by this surveillance test procedure.

i Based on the above statements, the description of the proposed activity, and the review of FSAR Sections 5.7.7, 6.2.2, and 7.3.2, the proposed activity does not

. represent a change to the facility as described in the FSAR or FPER. l YES NO C. Does the activity represent a test or experiment not described in X the FSAR or FPER7 STP-212.002 is designed to perform surveillance testing of Reactor Building Spray System components utilizing existing plant components, controls, test connections, .

process instnJments and the installed testing capabliities of the Engineered Safety -

Features Actuation System. This testing is performed as required by FSAR Section 5.7.7, 6.2.2.4.1, 6.2.2.4.1.1 and 7.3.2.2.5.1.

Based on the above statements, the description of the proposed activity, and the review of FSAR Sections 5.7.7, 6.2.2, and 7.3.2, the proposed activity does not 4 represent a test or experiment not described in the FSAR or FPER. l YES NO D. Does the activity represent a change to the Technical X Specifications?

In addition to "C" above STP-212.002 is designed to perform surveillance testing of Reactor Building Spray System components in accordance with Technical Specification Surveillance Requirements 4.0.5, 4.6.2.1.b, 4.3.2.1 Table 4.3-2 Item 2.b, and 4.B.4.2.a. The proposed changes have not altered this requirement.

Page 2 of 3

o ;

Enclosure 5 Attachmsnt V SAP-107

- R'c t)6-0182 REVISION O Page 3 of 3 10 CFR 50.59 SCREENING PROCESS WORKSHEET PARENT DOCUMENT STP-212.002 REV._2_ CHANGE C Based on the above statements, the descripti6n of the proposed activity, and the review of Technical Specification Surveillance Requirements 4.0.5, 4.6.2.1.b, 4.3.2.1 Table 4.3-2 Item 2.b, and 4.8.4.2.a, and Technical Specifications 3.3.2,3.6.2.1, 3.6.2.2, and 3.8.4.2, the proposed activity does not represent a change to Technical Specifications.

1 l

h/l 3-?-76 fb 3 , 9 97, Preparer's Signature Date Independent Reviewer's Signature /Date ,

. 'M14\9 h Approv0 Signature bate I

i 1

Page 3 of 3

1 Ericiosura 5 Attachment VI SAP-107 RC-96-0182 REVISION 0

. Page 1 of 3 10 CFR 50.59 SCREENING PROCESS WORKSHEET PARENT DOCUMENT STP-223.002A REV. _ 5 CHANGE A j Activity

Description:

The proposed activity is Change A to Revision 5 of STP-223.002A. This revision was i

performed to implement the following:

1. Added Step 9.6.8, reference to RC-96-0032, Response to GL 95-07, Pressure

. Locking and Themial Binding of SR Power Operated Valves.

2. Enclosure 10.1 Page 2, corrected line spacing.

3. Attachment VIA, deleted Notes 1 and 2, changed the Test Position for MVG-3109A and B to OPEN and added C02 Peap. This was performed in !

response to RC-96-0032.

4. Attachment VIB, deleted Notes 1 and 2, changed the Test Position for MVG-3109C and D to OPEN and added CO2 Pcap. This was performed in response to RC-96-0032.

Prior to this change, the Service Water Booster Pumps were tested with a flow aath through either XVG03109A-SW or XVG03109D-SW for the A Pump and throug i either XVG031090-SW or XVG03109D-SW for the B Pump. The following is an evaluation of the change in test flowpath and the impact this will have on the

, Service Water Booster Pumps and associated components during the perfonnance of

the required testing.

FSAR Section 9.2.1.2', System Description, states that the reactor building cooling units receive water from the service water booster pumps and the digital rod position indication system cooling unit is isolated from tne reactor building cooling units by closing the Isolation valves under safety injection, loss of non-Class 1E power, or test conditions. Upon receipt of a safety injection signal, the ESFLS starts the inactive loop at high speed. The service water booster pumps, with the throttling orifices in the discharge piping, maintain system pressure inside the reactor building above peak post accident pressure when service water flow is maintained to two reactor building cooling units.

FSAR Section 9.2.1.3, Safety Evaluation, states that during a postulated LOCA, the two service water booster pumps supplying service water to the reactor building cooling units are started. Throttling onfices in the return lines control back pressure to maintain service water pressure above long term post accident reactor building ambient pressure.

The Service Water System DBD lists the capacity of the Service Water Booster Pumps as a rated capacity of 4,000 gpm.

Page 1 of 3

Enclosure 5 SAP-107 Attachment VI REVISION 0 RC-96-0182

. Page 2 of 3 10 CFR 50.59 SCREENING PROCESS WORKSHEET PARENT DOCUMENT STP-223.002A REV. 5 CHANGE A MRF-21022 Post Mod Test Review as documented by TWR Serial 13867, Tab 11, Dated 1-9-89, showed that the operation of the Sewice Water Booster Pumps with two RBCUs in service resulted in the following flowrates.

1 RBCU 2 RBCU XPP0045A 171 psi / 2450 gpm 168 psi / 2670 gpm XPP0045B 161 psi / 2500 gpm 168 psi /2750 gpm ,

Design Calculation DC-433-0428-16, Service Water RBCU Disch. Orifice Size, was performed to determine the required pressure drop for sizing orifice XPS-29, XPS-99

)

or FE-4468/98 to yield 2000+ gpm thru a single RBCU 70 sec. after diesel start signal l and less than 3500 gpm at 85 sec after diesel start signal, all valves fully stroked at 85 sec. This was performed to support MRF-21022. The results of which are shown 4 above.

It is concluded that the performance of Service Water Booster Pump testing with two RBCUs in service will not operate the system outside its asbuilt configuration and maximum flow parameters during testing performed by STP-223.002A as proposed by Change A to Revision 5 of this procedure.

The original intent of this procedure was to perform surveillance testing of Service Water System pung' cind valves as required by FSAR Section 5.7.7 and Technical i

Specifications 4.0.5 and 4.6.2.3.b.2. This intent remains unchanged by the proposed activity.

Screening Questions:

YES NO A. Does the activity represent a change to the procedures described X in the FSAR or FPER7 FSAR Section 5.7.7 states the requirements to perform the surveillance test activities ;

performed by STP-223.002A. FSAR Section 13.5.8 describes the general content of a l Surveillance Test Procedure. However no system or component specific details are presented by these FSAR Sections.

FSAR Section 9.2.1.4 states that normal operation verifies the operability and performance of the Service Water pumps, therefore no periodic testing is necessary.

FSAR Section 5.7.7.1 states that Code Class 2 and 3 pumps will be tested in accordance with ASME Section XI. The Service Water Pumps will be tested by STP-223.002A to satisfy the requirements of FSAR Section 5.7.7.

Based on the above statements, the description of the proposed activity, and the review of FSAR Sections 5.7.7, 9.2.1 and 13.5, the proposed activity does not represent a change to procedures as described in the FSAR or FPER.

Page 2 of 3

l Enc'losure 5 Attachm nt VI SAP-107 RC-96-0182 REVISION 0 Page 3 of 3 10 CFR 50.59 SCREENING PROCESS WORKSHEET PARENT DOCUMENT STP-223.002A REV. 5 CHANGE A YES NO B. Does the activity represent a change to the facility as described X in the FSAR or FPER? ;

STP-223.002A is designed to perform surveillance testing of Service Water System components ut!!izing existing plant components, controls, test connections and l process Instruments. This testing is performed as required by FSAR Sections 5.7.7. The changes made to this procedure by Revision 5 do not alter this intent.

Based on the above statements, the description of the proposed activity, and the review of FSAR Sections 5.7.7 and 9.2.1, the proposed activity does not represent a i change to the facility as described in the FSAR or FPER. l YES NO I C. Does the activity represent a test or experiment not described in X the FSAR or FPER?

STP-223.002A is designed to perform surveillance testing of Service Water System components utilizing existing plant components, controls, test connections and l process instruments. This testing is aerformed as required by FSAR Sections 5.7.7. The I changes made to this procedure by Revision 5 do not alter this intent.

Based on the above statements, the description of the proposed activity, and the review of FSAR Sections 5.7.7 and 9.2.1, the proposed activity does not represent a test or experiment not described in the FSAR or FPER.

YES NO I D. Does the activity represent a change to the Technical X Specifications?

In addition to "C" above STP-223.002A is designed to perform surveillance testing of Service Water System components in accordance with Technical Specificatloa Surveillance Requirements 4.0.5 and 4.6.2.3.b.2.

Based on the above statements, the description of the proposed activity, and the review of Technical Specification Surveillance Requirements 4.0.5, and 4.6.2.3.b.2 and Technical Specifications 3.5.2, 3.5.3, 3.6.2.3, 3.7.1.3, 3.7.3, 3.7.4, 3.9.7.1, and 3.9.7.2, the proposed activity does not represent a change to Technical Specifications.

BML 3 7 74 Preparer's Signature Date

/tr00e/4$

independent ReviewMs Signature /Date b> Ax NM '

Approval Sigha'ture Date Page 3 of 3

RC-96-0182, Responds to RAI Re GL 95-07, Pressure Locking and Thermal Binding of Safety-Related Power Operated Gate Valves

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RC-96-0182, Responds to RAI Re GL 95-07, Pressure Locking and Thermal Binding of Safety-Related Power Operated Gate Valves

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