ML20126H614
| ML20126H614 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/09/1981 |
| From: | Engle L Office of Nuclear Reactor Regulation |
| To: | Novak T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8104160573 | |
| Download: ML20126H614 (53) | |
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- UNITED STATES f Yn - } NUCLE AR REGULATORY COMMISSION WA$mNGToN, o. C. 20555 l
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MEMORANDUM FOR: T. M. Novak, Assistant Director for Operating Reactors
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THRU: Robert A. Clark, Chief i. '- Operating Reactors Branch d3 g , 7 Divison of Licensing b, ., FROM: Leon Engle, Project Manager Operating Reactors Branch d3 Division of Licensing
SUMMARY
OF MEETING WITH ELECTRIC POWER RESEARCH INSTITUTE,
SUBJECT:
WESTINGHOUSE CCRPORATION, DUKE POWER COMPANY, AND THE VIRGINIA ELECTRIC AND POWER COMPANY REGARDING THE TESTING OF BLOCK VALVES. A meeting was held in Bethesda, Maryland on March 20, 1981 regarding the subject as noted above. A list of attendees is provided in Attachment No.1.
Introduction:
Full scale qualification testing of Power Operated Relief Valves (PORV) is specified in NUREG-0737 " Clarification of TMI Action Plan Requirements". The testing of the PORY is to be ccmpleted by July 1,1981. The requirement for full-scale qualification testing of P9RV block valves is to be completed by July 1,1982. This requirement was first femally indentified in Item II.D.1 of NUREG-0737. The purpose of the block valve testing is to provide empirical evidence that block valves located between the pressurizer and each PORY can be operated, closed and opened for fluid conditions expected under operating and accident conditions. By letter dated December 15, 1980, the PWR Owners Group notified the NRC
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1 that it would not comit to implement a block valve test program until the PORY test program, due July 1,1981, had been completed. Since then, discussions between the NRC staff and the Owners Group have resulted in a verbal coamit:nont from the Group for the establishment of a block valve' test i program. The completion date for this test program is July 1,1982. Et is l presently anticipated that the Owners Group will be submitting a block valve test program to the NRC in May,1981. I Anticipating the requirement for a fornalized block valve testing program, , the Electric Power Research Institute (EPRI) made provisions at the Marshall Test Facility for the installation of block valves between the facility steam source and the PORY's. Since no femal block valve test program was l in place, EPRI obtained seven different block valves which were tested in July,1981 in order to provide base-line data on block valve closure. 810 A 160 57$<
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- 2-As a result of this testing, EPRI notified the NRC that three of the valves tested would not fully close under test conditions. Two of three affected .'
valves were manufactured by the Westinghouse Corporation (W). The third valve was manufactured by Anchor / Darling and was subsequently modified by the manuf acturer and successfully retested. W sent advisory letters ' on the 3 inch gate valve in question to its NSSS customers in late October-early November,1980 and additional advisory letters on the 3 and 4 inch , gate valves to its NSSS customers on February 12, 1981. Two utilities which had installed the W valves in question were Duke Power Company (0conee Units - B&W NSSS) and the Virginia Electric and Power Company (North Anna and Surry Units-W NSSS). A meeting notice was issued by the NRC on March 18, 1981, requesting that EDRI, W, Duke Power and VEPCO convene with the NRC staff on March 20, 1981 to discuss these matters 50 that the chronological order of events and the reporting requirements of 10 CFR Part 21 and 10 CFR Part 50.55(e) could be placed in proper perspective. The agenda for the meeting was specified in the NRC notice (See Attachment 2) and the results of the March 20, 1981 meeting are summarized below.
- 1. Discussion of Block Valve Testing at Marshall Steam Station EPRI proviceo tne cecails of its PWR safety and relief valve test program.
The formation of the test program, the table of organization for the test program, and program output is provided in Attachment 43. As mentioned previously, EPRI anticipated new forthcoming requirements for a block valve test program to be completed by July 1,1982. In order to obtain baseline data for use in evaluating and preparing a block valve test program responsive to NUREG-0737, EPRI tested seven easily obtainable block valves. At the time that the block valves were tested, EPRI did not have access to information regarding the number of nuclear facilities which might have any of the block valves either installed or planned to be installed. The feven block valves tested were Anchor / Darling; Borg Warner; Rockwell; Yelan, Model C 2343 SN-243402; Velan, Model B10-3054 B013M (MO); Westinghouse Model 3GM88 and Westinghouse Model 3GM99. -Initial test indicated that three of the block valves would not fully close against full flow (saturated steam at about 2400 pounds per square inch differential). The three valves in question were the W Model 3GM88 and Model 3GM99 valves and the Anchor / Darling y ,,---- - - -w - . - , , , - . , , - , . . . - . , . --n-w,,, , . , , . - , ., - - - - , - --
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valve. The Anchor / Darling valve was modified and successfully retested. In general the valve failures were caused by too low of a torque capability on the valve operator. The EPRI staff involved in the block valve tests notified the EPRI Safety and Relief Valve Subcommittee and W. ~he EPRI Subcommitee Chairman then notified the NRC staff who in turn contacted the EPRI staff for additional i nformation. Also, as part of the EPRI test program, a va've manufucturer's representative is required on-site during valve testing and the subsequent disassembly and inspection of a tested valve. No violations of 10 CFR Part 21 are applicable regarding EPRI's obligation for reporting requirements. The block valve tests were performed with a valve vender present and the test results were transmitted to the valve vendors. Also, EPRI was neither under contract with vendors nor users and was not aware of specific valve application at facilities either in operation or under construction.
- 2. Discussion of Westinchouse Water Test on 3 and 4 Inch Gate Valves W prov1ded a discussion of recent water valve tests on 3 and 4 inen valves and provided specific data regarding the W valve Models 3GM88 and 3GM99.
W also provided its solution to the 3 and 4 inch gate valve closure problem based on the MarshallThe Testsalient Facilitypoints results ofandthisthe water test discussion are conducted on the gate valves. provided in Attachment No. 4.
- 33. Discussion of Westinghouse letters to Licensees Regarding Valve Testing W previoed a time chronology of its actions from the time it was notified of From the Marshall test results on July 9,1980 regarding the W valve 3GM88.
July to early September,1980, Westinghouse investigated block valve availability for NSSS application and evaluated test results for resolution of valve performance. On September 16, 1980, the W Safety Review Committee (WSRC) convened to assscs block valve failure to completely close at rated torque values. The WSRC determined that the W Safety Analysis Report for the worst case small hot leg break enveloped a stuck open PORY event, and that the WCAP-9600 Report showed no core uncovery assuming all PORVs stuck open (no block valves). The WSRC determined that the present status of the W valves , in auestion was neither a substantial hazard pursuant to 10AtCFR Part 21, the same time, ! nor a significant deficiency under 10 CFR Part 50.55(e). the WSRC decided to expand its investigations to other 3 and 4 inch gate
- valve hpplications.
On September 25,1980, W advised the NRC by telephone of the block valve issue. And, during Septenber,1980, W was advised of the failure of certain 3 inch gate valves to close at two facilities which were undergoing ' pre-ope. rational testing. i [ - . _ ...._.- . - .- _ .- , - ._.. ,, _ ... . _ ,_-..._..,.. _ , _ _..-..~ -.- _ _ _ .
On October '28,1980, the WSRC again convened to discuss 3 inch gate valves and NSSS customers were notified of a potential violation of 10 CFR 50.55(e). On October 30, 1980, W informally notified the NRC on the 3 inch gate valve deficiency. On November 18-20, 1980, the NRC conducted an audit at W, and included in the NRC audit was the September 16, 1980 WSRC findings fer determining that the velve issue was not reportable under 10 CFR Part 21 or 10 CFR Part 50.55(e). During the month of Cacember,1980, W 1aboratory water tests were conducted on 3 and 4 inch gate va'~es. In January,1981, W was notified of Marshall test results for W valve 3GM99, and on January 15, 1981 W provided the NRC with an update on the issue of 3 and 4 inch gate valve deficiency. The NRC conducted an additional audit at W on February 5,1981. And, on February 10, 1981 the WSRC committee met once again to discuss W valve 3GM99 and other 4 inch gate valve applications. And finally, W notified its NSSS customers within 24 hours of the W5RC meeting regsrding a potential violation of 10 CFR Part 50.55(e) (See Attachment No. 5).
- 4. Duke Review of Westinghouse Letters and Actions Taken on Oconee Units Duke Power (tne licensee) received two W advisory letters on October 27, 1990 and November 1,1980 regarding the 3 inch gate valves. The licensee determined that three of the valves discussed in the W 1etters had been installed as PORY block valves on Oconee Units 1, 2 and 3 (See Attactment No. 6).
On November 17, 1980 the licensee performed a safety evaluation in accordance with the requirements of 10 CFR Part 21 and concluded there were no unanalyzed safety problems because, (1) the Oconee units had been analyzed for safe shutdown capability with a stuck open PORY, (2) plant modifications had been made for NRC requirements addressing the TMI-2 accident, and (3) the licensee's confidence that the demands for actuation of a PORY in response to plant transients had been substantially reduced on all three Oconee units. The licensee's confidence regarding PORY actuation is substantiated by plant operations during 1980 when there were no PORY actuations. At the time of the licensee's determination regarding 10 CFR Part 21, Oconee Unit 2 was shutdown and Oconee Units 1 and 3 were operating. .. Prior to restart for Oconee, Unit 2, the licensee made an adjustment in the torque switch setting on the Unit 2 block valve. This torque switch setting increased the valve closure force on the Unit 2 block valve. Oconee, Unit 3 was shutdown for refueling in December,1980 and during this outage, modi-fications recommended by W were implemented. These modifications included changes in the block valve operator control switch and operator gearing. These same modifications were made shortly thereafter on Oconee, Unit 2 when it was again shutdown in December,1980. For Oconee, Unit 1, the licensee iy . .
determined that the Unit 1 block valve would be modified at the first extended Unit 1 outage. In the meantime, the licensee closed the Unit 1 block valve in February,1980. Closure of this block valve is permissible by the plant Technical Specificaitons. Also, the Office of Inspection & Enforcement verified the actions described by the licensee through the resident ILE inspector.
- 5. VEPCO Discussion of W stinghouse Letters and Actions Taken on North Anna Units The Virginia Electric and Power Company (the licensee) received the Westinghouse advisory letters in tne same time period as Duke Power. (These two letters and additional correspondence are provided in Attachment No. 7.).
The licensee made a search of its files to determine whether any of the W block valves in question were installed at either the North Anna or Surry Units. It was determined that one of tne W valves had been installed as a PORY block valve at North Anna, Unit 2. It should be noted that the North Anna design has two PORV's and two block valves per unit. Once the licensee had determined a W block valve was in place at North Anna, Unit 2, the licensee's Safety Review Committee met on March 5,1981 and cetermined that the lack of block valve closure capability was not reportable as a safety issue for either 10 CFR Part 21 or 10 CF Part 50.55(e). This determination by the licensee was based on the recently NRC approved Westinghouse analysis, which demonstrated that the North Anna Units could be safely shutdown with one or both PORV's stack open. The licensee decided to continue full power operations at North Anna, Unit 2 with both block valves ope? and to install the W recommended valve modifications at a mr atenance outage scheduled for May 1981. Also, the Ncrth Anna, Unit 2 - actor operators were cautioned that under certain flow conditions the W b' ek valve might not fully close. In addition, the I&E resident inspector was kept informed of these decisions and has verified that the reactor operators have been alerted to the block valve closure deficiency.
J 4 . a 6-
Conclusion:
The Office of Inspection and Enforcement is in the process of verifying
- that no other applications of the unmodified W valves in question are installed or planned for installation at nuclear facilities. An I&E generic letter will be issued in the near future to all licensee and applicants regarding this matter, bM Leon 3. Eng oject Manager Operating Reactors Branch #3 Divison of Licensing Attachemnts:
i No.1 No. 2 No. 3 , No. A tio. 5 tio. 6 No. 7 cc: See next page e
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SUMMARY
DISTRIBUTION Licensee: Virginia Electric and Power Ccmpsny
- Copies also sent to those people on service (cc) list for subject plant (s).
Docket File NRC PDR L PDR NSIC TERA ORS #3 Rdg 001shinski JHeltemes, AE00 EGrimes RClark Project Manager Licensing Assistant ACRS (10) Mtg Su. mary Dist. NR0 Participants HDenton ECase OEisenhut RVollmer Dross TMurley
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Richard M. Foster, Esquire Mr. Jares Torsen - Musick, Williacson, Schwartz, 501 Leroy ' Leavenworth & Cope, P.C. Socorro, New Mexico 87891 i P. O. Box 4579 Boulder, Colorado ' 80306 Mrs. Margaret Dietrich Route 2, Box 568 Michael W. Maupin, Esquire Gordonsville, Virginia 22042 , Hunton,. Williams, Gay and Gibson Mr. J anes C. Dunstance P. O. Box 1535 Richmond, Virginia 23212 State Corporation Commission i Commonwealth of Virginia , Alderman Library Blandon Building - Manuscripts Department Richmond, Virginia 23209 University of Virginia Charlottesville, Virginia 22901 Director, Criteria and Standards Division Office of Radiation Programs -(ANR-460) > Mr. Edward Kube U.S. Environmental Protection Agency ! Board of Supervisers Washington, D. C. 20460 Louisa County Courthouse P. O. Box 27 U.S. Environmental Protection Agency i Louisa, Virginia 23093 Region III Office ; ATTN: EIS COORDINATOR Curtis Building ! Ellyn R. Weiss, Esquire Sheldon, Harman, Roisman and Weiss 6th and Walnut Streets 1725 I Street, N.W. Suite 506 Philadelphia . Pennsylvania 19106 Washington, D. C. 20006 Mr. Paul W. Purdom - Mr. W. R. Cartwright, Station Manager Environmental Studies Institute ' P. O. Box 402 Drexel- Uni versity Mineral, Virginia 23117 32nd and Chestnut Streets Philadelphia, Pennsylvania 19104 ; I Mr. Anthony Gambardella - Office of the Attorney General Atonde Safety and Licensing 11 South 12th Street - Room 308 Appeal Board Panel Richmond, Virginia 23219 U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. Allan Tattersall Resident Inspector / North Anna .. c/o U.S.N.R.C.- ' P. O. Box 128 , Spotsylvania, Virginia 22553 Commonwealth of Virginia Mrs. June Allen Council of the Environment North Anna Environnental Coalition 903 Ninth Street Office Building 1105-C Olive Street Richmond, Virginia 23129 Greensboro, North Carolina 27401 - s vwe-..- -,,em-, -..w-~,2 ,,_ ,..,, , - . .m,,-y--eve,-r., .,.cw, pe...e.-y.w..e, ,.-.,.-%,,...., ,,,,, ,,-, y .-y.--.-,y+en,. -,%.. , , , -,v-e,,---.-v-~,
9 a ATTACHMENT 1 LIST OF ATTENDEES MEETING ON MARCH 20. 1981 NUCLEAR REGULATORY COMMISSION ELECTRIC POWER RESEARCH INSTITUTE T. Amole OCM J. Carey L. Marsh Il?I to Bradford) . ACRS WESTINGHOUSE CORPORATION D. Bessette J. Drake C. Gottshall < STAFF 0. Ki tch R. Sosnak W. Maelaurin ' E. Brown D. Rawlins F. Cherny R. Clark DUKE POWER COMPANY L. Engle R. Gill B. Forrest S. Hart H. Gregg A. West J. Knignt W. Jensen VIRGINI A ELECTRIC AND POWER COMPANY E. Hemminger E. Smi tn C. Hofmayer B . Syl vi a G. Holahan E. Jordan CONSUMER P0kER COMPANY R. LaGrange D. Hoffman H. Levin J. Ma:etis PACIFIC GAS & ELECTRIC COMPANY T. Novak G. Wu H. Ornstein R. Riggs EGaG (Idaho)
- Z. Rostoczy J. Hunter M. Stolzenberg P. Wagner INTERMOUNTAIN TECHNOLOGY, INCORPORATED
- 5. Kucharski -
NUCLEAR SAFETY OVERSIGHT COMMIittE J. 5tampelos UNION OF CONCERNED SCEINTISTS
- 5. Sholly
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Docket Nc. 50-333 : l I MEMORANDUM FOR: Robert A. Clark, Chief Operating Reacotrs Branch !3, DL FROM: Leon S. Engle, Project Manager Operating Reactors Branch v3, CL SU5 JECT: FORTHCCMING MEETING WITH OUKE POWER COMPANY, VIRGINIA ELECTRIC AND POWER COMPANY, ELECTRIC FOWER RESEARCH INSTITUTE, AND WESTINGHOUSE CORP. Cate & Time: March 20, 1981 1:00 PM, Friday Loca:icn: Rocm P-422, Phillips Suilding Sethesda, Marylanc
Purpose:
To discuss and review block valve :esting. Partici:an:s: NRC
'!EPCO E Novak Q 1via J. Knight D. Spiedel T. Jerdan G. Smith R. Sosnak W. Harrel P. Check R. Clark DUKE POWER J. Stolz R. Glii G. Schwenk P. Wagner EPRI N U . Carey, et al.
F. Cherny WESTINGHOUSE (To ce announced at meeting) Attachrent: .. Meeting Agenda cc: See back of page , , 5~ M'd Leon B. Engle, oject Manager . Operating Reactors Branch #3 Division of Licensing e g,w,- y c p. ,y----,7-, ,yw, , ., , ,w..i,y.. y ,,.y , ,wy, , w--,g,. , _r2 ,,,.. ,_4,-..., - -,--r--- .--
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ATTACHMENT. MEETING AGENDA Discussion of Block Valve Testing at Marshall Steam Statien. j
- 1. .
- 2. Discussion of Westinghouse Water Test en 3 and 4 inch gate valves.
- 3. Discussion of Westinghcuse Letter to all Licensees regarding valve- -
testing. .
- 4. Duke review of-Westing house letter and actions taken en Oconee Units.
- 5. VEPCO discussion of Westinghouse letter and actions taken en North Anna ,
' Units. ;
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SAFETY VALVES UNDER EXPECTED OPERATING CONDITIONS FOR DESIGN-3 ASIS TRAN3IENTS AND ACCIDENTS SY JULY L 1981. : E b UTILIZATION OF PROGRAt1 DATA: i LICENSEES AND APPLICANTS WILL UTILIZE DATA TO SUPPORT ~ PLANT-SPECIFIC SUBMITTALS IN RESPONSE TO SAFETY AND RELIEF VALVE TEST REQUIREMENTS IDENTIFIED IN NUREG 0737, ITEM II.D.1 h e S b h
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l i EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM 9 e PROGRAMINITIATEDINSEPTEMEER,1979BYEPslN'JCLEAR POWER DIVISION AT THE REQUEST OF THE TMI AD HOC NUCLEAR OVERSIGHT COMMITTEE e PROGRAM PLAN DEVELOPED AND SUEMITTED BY UTILITIES TO NRC ON DECEMSER 17,1979 (REVISION 1 SU3MITTED ON ; JULY 8, 1980) e SEPARATE PROGPMMATIC ACTIVITY WITHIN EPRI SAFETY AND ANALYSIS DEPARTMENT . e UTILITY ADVISORY GROUPS: EPRI-RAC-NSAC SUBCOMMITTEE SAFETY AND AllALYSIS DEPARTMENT TASK FORCE SAFETY AND RELIEF VALVE SUBCOMMITTEE TECHNICAL ADVISORY GROUP ..
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SAFETY AND RELIEF VALVE SUECOMMITTEE . DAVID HOFFMAN, CHAIRMAN (CONSUMERS POWER CO.) ROGER NEWTON (WISCONSIN ELECTRIC POWER) JOSEPH TURNAGE (YANKEE ATOMIC) JAMES SCOTT (PU3LIC SERVICE ELECTRIC
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TECHNICAL ' ADVISORY GROUP ; JAMES SCOTT, CHAIRMAN (PUBLIC SERVICE ELECTRIC '
& GAS OF NEW JERSEY)
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KENNETH BERRY (DUKE POWER CO.) - TCRRELL CLIFT (TENNESSEE VALLEY AUTHORITY) 4 WILLI ~AM JONES (YANKEE ATOMIC) 1 TECHNICAL, LICENSING, AND EXECUTIVE CONTACTS FOR EACH PARTICIPATING PWR UTILITY .
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i EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM , UTILIZES THREE TEST FACILITIES TO COMPLETE ALL REQUIRED TESTS BY FRESCRIBED DATE OF JULY L 1981 L MARSHALL STEAM STATION (DUKE POWER) RELIEF VALVE TEST FACILITY RELIEF VALVE STEAM TESTS
- 2. EPRI/WYLE RELIEF VALVE TEST FACILITY ,
RELIEF VALVE SUBC00 LED WATER TESTS i
- 3. EPRI/CE SAFETY AND RELIEF VALVE TEST FACILITY e SAFETY VALVE TESTS; STEAM, SUBC00 LED WATER AND i STEAM TO WATER TRANSITION n..
e SAFETY / RELIEF VALVE DISCHARGE PIPING LOAD DATA . 4 N e e E h i 4
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- 2. PWR SAFETY AND RELIEF VALVE TEST PROGRAM, DESCRIPTION AND STATUS, FEBRUARY 1981 (ISSUED APPR0XDMTELY EVERY SIX WEEKS) ,
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- 1. TEST REPORTS FROM THE MARSHALL, WYLE AND CE VALVt. ;
TEST PROGRAMS l
- 2. A REPORT DOCUMENTING THE SELECTION OF THE RELIEF AND ,
SAFETY VAL.VES TO BE TESTED AND JUSTIFYING THE APPLICA-BILITY OF THE TEST RESULTS TO VALVES UTILIZED IN - OPERATING PLANTS AND PLANTS UNDER CONSTRUCTION i I
- 3. A RE? ORT PROVIDING JUSTIFICATION OF THE SET OF GENERICALLY LIMITING FLUID CONDITIONS UTILIZED TO ESTABLISH THE VALVE ;
TEST CONDITIONS i
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- 4. A REPORT DOCUMENTING A CODE FOR COMPUTING HYDRODYNAMIC i
LOADS FOR RELIEF AND SAFETY VALVE DISCHARGE PIPING ljNDER STEAM AND WATER DISCHARGE CONDITIONS
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i-1.1 PROGRAM COST: SEPTEF.EER, 1979 - DECEM3ER, 1981
~ APPROXIMATELY S18,000,000.
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't e BLOCK VALVE TESTS NOT INCLUDED IN NUREG 0578 RECOMMENDATIONS (JULY, 1979F -
e BLOCK VALVE TEST PROGRAM CURRENTLY NOT A FORMAL PART OF EPRI PWR SAPETY AND RELIEF VALVE TEST PROGRAM : i e BLOCK VALVE TEST REQUIREMENTS IDENTIFIED IN NUREG 0660, i MAY,1980 AND FURTHER CLARIFIED IN NUREG 0737; NOV.,1980: e VERIFICATION OF BLOCK VALVE FUNCTIONABILITY : e TESTS TO BE COMPLETE BY JULY 1, 1982 e LICENSEE TO PROVIDE EVIDENCE SUPPORTED BY TEST : THAT BLOCK VALVE CAN BE OPERATED, CLOSED AND
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OPENED FOR ALL FLUID CONDITIONS EXPECTED UNDER l OPERATING AND ACCIDENT CONDITIONS .. e PWR UTILITIES HAVE REQUESTED EPRI TO PREPARE A BLOCK VALVE TEST PROGRAM RESPONSIVE TO THE REQUIREMENTS OF NUREG 0737 e EPRI IS DEVELOPING A BLOCK. VALVE TEST PROGRAM PLAN FOR SUBMITTAL TO PWR UTILITIES BY JUNE 1,1981 l
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e MARSHALL STEAM STATION TEST LOOP ORIGINALLY (1978-79) SET-UP BY DUKE POWER FOR RELIEF VALVE TESTS
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e MARSHALL TEST LOOP INCLUDES PROVISION FOR RELIEF AND BLOCK VALVES e EPRI CONTRACTED WITH DUKE POWER (EARLY 1980) FOR l UTILIZATION OF THE TEST FACILITY TO PERFORM STEAM TESTS ON POWER OPERATED RELIEF VALVES AS PART OF THE EPRI PWR VALVE TEST PROGRAM IN RESPONSE TO NUREG 0578 , c e IN LIGHT OF THE NEW REQUIREMENT FOR BLOCK VALVE TESTS (NUREG 0660b EPRI RECOMMENDED LIMITED BLOCK VALVE TESTS AT MARSHALL WHICH WOULD NOT INTERFERE WITH THE PRIMARY OBJECTIVE OF RELIEF VALVE TESTS AS REQUIRED BY NUREG' 0578 f a UTILITY ADVISORY GROUP APEROVED RECOMMENDATION AND NRC WAS NOTIFIED OF PLANS TO TEST A LIMITED NUMBER OF BLOCK ' VALVES.AT MARSHALL d
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. 1 MARSHALL BLOCK VALVE TESTS e SEVEN BLOCK VALVES TESTED ,
ANCHOR / DARLING BORG WARNER , ROCKWELL VELAN, MODEL C2345 S/N-243402 VELAN,.MODEL B10-3054B013M (MO) WESTINGHOUSE, MODEL 3GM88 ; WESTINGHOUSE,-MODEL 3GM99 : e VALVE MANUFACTURER TECHNICAL REPRESENTATIVE ON SITE i DURING EPRI BLOCK VALVE TEST (EXCEPT FOR FIRST TEST OF WESTINGHOUSE MODEL 3GM99 ON JANUARY 12, 1981) e CHAIRMAN, SAFETY AND RELIEF VALVE SUBCOMMITTEE NOTIFIED 0F BLOCK VALVE TEST RESULTS e INITIAL TESTS OF THREE BLOCK VALVES INDICATED AN INABILITY i] FULLY CLOSE AGAINST FULL FLOW (SATURATED STEAM, 42400 PSD ANCHOR / DARLING - WESTINGHOUSE MODEL 3GM88 - ' WESTINGHOUSE MODEL 3GM99 e EPRI STAFF NOTIFIED: SUBCOMMITTEE CHAIRMAN WESTINGHOUSE .
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MARSHALL BLOCK VALVE TESTS e SUBCOMMITTEE CHAIRMAN NOTIFIED NRC I e NRC CONTACTED EPRI STAFF AND WERE PROVIDED WITH ADDITIONAL INFORMATION e MARSHALL BLOCK VALVE TEST REPORTS IN PREPARATION; FIRST , l DRAFT OF EACH BLOCK VALVE TEST REPORT WILL BE SUBMITTED T0 ALL PWR UTILITIES'AS THEY BECOME AVAILABLE. ALL SEVEN REPORTS WILL BE COMPLETED AND SENT TO UTILITIES ON OR BEFORE MAY L 1981 1 1 i
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- 1. ANCHOR DARLING e INITIAL TEST, AUGUST 15, 1980 BLCCK VALVE IN-LINE WITH FISHER PORV e BLOCK VALVE WOULD NOT FULLY CLOSE AGAINST FULL FLOW.
(70% CLOSED) e DISASSEMBLY INDICATED SOME SIGNIFICANT WEAR-PATTERNS AT THE DISC / SEAT INTERFACE e VALVE RETURNED'TO MANUFACTURER FOR MODIFICATIONS . e VALVE WAS RETURNED TO MARSHALL FOR FURTHER TESTS e VALVE WAS RETESTED ON SEPTEMBER 25, 1980 IN LINE WITH < FISHER PORV, AND UTILIZED A ROTORK 16NAX1 OPERATOR , e . VALVE WAS CYCLED 21 TIMES AGAINST FULL FLOW (SATURATED STEAM, 42400 PSI, 4195,000 LEM/HR) WITH NO SIGNIFICANT ANOMALIES NOTED. SEAT LEAKAGE AFTER TEST RANGED FROM 0.019.T0 0.066 GPM e ANCHOR DARLING PERSUING. ADDITIONAL MODIFICATIONS TO FURTHER REDUCE SEAT LEAKAGE w v- % s----s= se ms e "ew-+.y-amdv 3.--.-. .*,.-we--sy--w-..s'w w, .e .t w et + + sre4=.ew..y-+ r=,w w. si..w-wase.+..a,um Tre s' es= w w'#f'+" 4'W 1f 7F"f' 9N '%VY "TY'T '+9'*".
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6 MARSHALL BLOCK VALVE TESTS PRELIMINARY
SUMMARY
OF TEST RESULTS
- 3. ROCKWELL e INITIAL TEST (PRESSURIZATION OF LOOP) UNCOVERED A '
BODY TO BONNET SEAL PROBLEM; DESIGN WAS MODIFIED / AND TESTED ON OCTOBER 27, 1980 . e VALVE IN LINE WITH COPES VULCAN PORV AND CYCLED , 21 TIMES AGAINST A FULL FLOW 0F ~230,000 LBM/HR. VALVE WAS ACTUATED WITH A LIMITORQUE OPERATOR MODEL SMB-00-10 e NO ANOMALIES WERE NOTED, SEAT LEAKAGE WAS 0.0 GPM s
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I MARSHALL BLOCK VALVE TESTS PRELIMINARY
SUMMARY
OF TEST RESULTS
- 4. VELAN, MODEL C2345 -S/N-24302 e VALVE WAS ECdIPPED WITH LIMITORCUE ACTUATOR MODEL NO. SM3-00-15 e VALVE WAS CYCLED 21 TIMES ALAINST A FULL FLOW OF
~246,000 LBM/HR ON JANUARY 13, 1981 e SEAT LEAKAGE WAS 0.0 GPM
~
e SOME GALLING INDICATIONS ON ONE OF THE DISC GUIDES " WAS OBSERVED WHEN THE VALVE WAS DISASSEMBLED AND INSPECTED O e
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E ! MARSHALL BLOCK VALVE TESTS
< PRELIMINARY
SUMMARY
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=
- 5. VELAN, MODEL B10-3054B013M (MO) e VALVE WAS EQUIPPED WITH LIMITORCUE OPERATOR J
MODEL NO. SMB-00-10 e VALVE WAS CYCLED 21 TIMES AGAINST FULL FLOW (~245,000 LBM/HR) ON JANUARY 14, 1981
- e NO ANOMALIES WERE NOTED; SEAT LEAKAGE WAS 0.0 GPM .
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SUMMARY
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- 6. WESTINGHOUSE MODEL 3GM88 e INITIAL TESTS PERFORMED IN JULY,19S0 INDICATED THAT THE VALVE WOULD NOT CLOSE AGAINST FULL FLOW e VALVE WAS ACTUATED WITH ROTORK OPERATOR SET AT 110 FT-LB. AND IN-LINE WITH A CONTROL COMPONENTS PORV e FURTHER TESTS INDICATED THAT APPROXIMATELY 175 FT-LBS.
WERE REQUIRED TO CLOSE THE VALVE AGAINST A FULL FLOW 0F +232,000 LBM/HR e VALVE WAS ACTUATED WITH A LIMITORQUE OPERATOR MODEL- NO. djB-00-15 ON AUGUST 13, 1980 e VALVE WAS CYCLED 21 TIMES (FULLY OPEN/ FULLY CLOSED). NO ANOMLIES WERE NOTED. SEAT LEAKAGE WAS 0.0 GPM
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. . FRELIMINARY
SUMMARY
OF TEST RESULTS .
- 7. WESTINGHOUSE MODEL 3GM99
- e. VALVE WAS ORIGINALLY lEQUIFFED WITH A LIMITOROUE OPERATOR MODEL NO. SMB-000-10 f i
e VALVE WAS CYCLED TWICE ON. JANUARY 12, 1981 AND DID i NOT CLOSE FULLY AGAINST FULL FLOW-e VALVE WAS RETURNED.T0 WESTINGHOUSE FOR MODIFICATION . (CHANGE TO VALVE YOKE AND'OPERATORT e MODIFIED VALVE WITH A LIMITOROUE ACTUATOR MODEL NO. SB-00-15 WAS RETURNED TO MARSHALL AND CYCLED 21 TIMES AGAINST FULL FLOW 0F i244,000 LEM/HR ; e SEAT LEAKAGE MEASUREMENTS RANGED FROM 0.0 TO 0.06 GFM i U
. 1 l
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l ATTACHMENT 4 l HISTORY OF CLOSING PROBLEM
. 3Gr38 FIRST FAILED TO CLOSE UNDER HIGH-PRESSURE DIFFERENTIAL STEAM FLOW CONDITIONS DURING AN EPRI TEST PROGRAM AT THE MARSHALL STATION (JULY, 1980).
. SEVERAL 36M88's FAILED TO CLOSE AT T@ PLANT SITES DURING TESTING OF SAFETY INJECTION SYSTEM AT HIGH-PPISSURE DIFFERENTIALS.
. STRAIN GAGES SHOED CLOSING LOADS TO BE APPR0XIMATELY 13,500 POUNDS.
. ::s:r
. FULL FLOW TESTS PERFORMED AT PACIFIC PUMPS RAVE CONFIPED CLOSING LOAD REQUIREMENT OF t 13,500 POUNDS'AT 2700 PSI DIFFERENTIAL. .
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REASON FOR FAILURE T0'CLOSE i
. OPERATOR SIZE BASED ON 9300-POUND CLOSING LOAD (USED IMDUSTRY STANDARD EQUATION)
. OPERATOR SIZE MARGlits MINIMIZED TO REDUCE LOADS AND MINIMlZEPOSSIBILIIYOFVALVEDAMAGEIFANOPERATOR STALLS
. OPERATOR SIZING AND TORQUE SWITCH SETTING DID NOT ACKNOWLEDGE CLOSING LOAD AND OPERATOR DYNAMIC CHARACTERISTICS
, THIS RESULTED IN OPERATOR BEING SET UP TO TRIP AT 9300 POUNDS + SMALL MARGIN AGAINST NO FLOW WHILE THE REQUIRED THRUST LOADS COULD BE AS HIGH AS 13,500 POUNDS e
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VALVE CHARACTERISTICS WITH FLOW d ( ( PEAK LOAD
/
o CLOSING LOAD g RUNNING LOAD x TIME VALVE CHARACTERISTICS WITil00T FLOW P AK-LOAD TOROUE SWITCF SETTING e - ( S p RUNNING LOAD
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~ V/CRDM/25
SUMMARY
OF TESTING ACTIVITIES--VALVE CLOSING PROBLEM
- 1. gter Flow Testing (at Pacific Pump Comp'any)
Condition up to and inc1 ding 600 gpa and 2800 psi 4 valves - 3GM88
+ field modifications . complete 3 valves - 3GM99 3 valves - 4GM88 Field modifications for the 3GM99 and 4GMS8 to be tested in early-May.
2.. EPRI Steam Flow Tests (PORY Block, Steam Flow) 1 valve - 3GM88 complete 1 valve - 3GM99
- 3. Site Testing (Full Flow Water Testing, Safety Injection System)
Almarez: Approximately 10 valves - 3GM88 CGE: Approxisately 10 valves - 3GM88 complete , STP: 3 valves - 3GM88 )
- 4. EdF_ (Steam and Water Flow Testing) 2 valves - 3GM99 --- in process
- 5. Mechanical Fi'xture Testing (At WDO)
~
l Using hydraulic cylinder to duplicate flow loads so force transfer l can be studied in depth. ! 1 I valve - 3GMB8 1 valve - 3GM99 complete l l 1 valve - 4GM88 -
- 6. Seat Friction Factor Tests (At Westinghouse R&D)
To determine stellite on stellite friction factors under water and steam conditions. Test samples are nearing completion at DC. .. 4 - cc: F. R. Bakos J. A. Drake, Mgr. I A. F. Phillips Yalves and CRDM Eng. sk , 3/19/81 l I l i l
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-TORQ. SWITCH SETiliiG 3.25 FLOW = 600 GPM P = 2550 PSI -
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h SOLUTION TO VALVE CLOSURE PROBLEM MODEL 36M88
. REGEAR VALVES TO HAVE 25,000 PCUND STALL CAPABILITY
. USE LIMIT SWITCH RATHER THAN TOR 00E SWITCH - -
CONTROL MODEL 39t99 AND 4-INCH VALVES
. MAY REQUIRE CHANGE 00T OF OPERATOR
. USE LIMIT SWITCH CONTROL
. FINAL DECISION TO BE MADE IN APRIL e
b t i i 5 5
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E 5 5= MMOO 96 W
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, . _ . . . ~ . . . . - - - . _ . _ _ . . _ _ .
BELLEVILLE SPRING < STACK , 1
~
STEM { NORMAL TOROUE 1 I s SWITCH CLG5ING ~m!TH
~
J l
- VRING CWENMTca l & .
4 i ) b e Loads buildup at seat face as motor y %M,I", ) ( - torque increases. L IJlIJ 6 d ul
- Belleville sp' ring stack permits tne NUT stem nut to deflect under stem DEFLECTIC loads.
e knen torque reacnes a preset level VALVr.- , tne torque switch trips tne motor. STE M j e Remaining spring stack deflection provides differential tnermal expansion protection and absores motor inertia. VALVE 4l s DISC
- I I i
i
\ I VALVE SEAT --
+ - -- - -
RtNG \ ! l . h\\N l V ') FIGURE 3 , I
., m, ..,ye % Ap .mm 9VW .
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.6 BELLEVILLE STACK -
\
i n TOROUE SWITCH CLOSI C g
}
AGAIN5T HI6H FL0d CONDITIONS - g -
, g 4 1
- ff nip flow or AP produce nign k
) h .
p L g : stem loads, torque switen may trip ) with valve partially open. Iqgi ipj d 8 lj e When AP reduces, cellevilles will NUT pusn disc toward closed position. DEFLECTICN
- If distance open / nut defection, dix will not reacn closed position.
f
/- s l' l DISTANCE OPEN
~
N _ sW ., { H5H l - - _ s si -- i v
\\hN\. l LEAxAGE
( l d FIGURE 4 _ , =-~ ~ ~ * '
--.w-- . + - - - -- ,r,-+- ., cgs -, -n- ., y m, y n
BELLEvtLLE STACK <' s ,
, I Ul LIMIT CLOSING CONTROL -
i 1 g - thTAcLIhr11NG THE CLOSED
, g LIMI T daiIcM TAIP PO5I TION j g y 5 I )i 3 f
~
e Operator Handwneel is used deflect I :
"l' the stem nut .280*, producing i 11,000 10s o f s ten thrus t . A NUT e Closed limit switch is set at tais DEFLECTION point. 2 .280
- On subsequent electrical closings, the limit switch will trip the g motor with the 11,000 10. Preload stem tnrust present.
/~~s I I N
__ \ + l __
\ .
s\\\N l FIGURE S r ,w y % -----,-o, ,,@y'7r---p y a g -y 3e--yw w y-r- - NwC-wg
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BELLEVILLE STACK s g i 1.IMIT CONTROL - CLOSIC AGAlh5T Fl.,LL FL0st CottDIIIONS U l L J t e If high flow or AP conditions g g product high sters loads, tne ,
) >
operator will produce anatever loaJ !,,, ( is required to reach tne limit switch set position. Y
)
, f' t; i 2
Lu o Of stance , Stemload - 11,000 les
- NfT Open 40,000 ios/in PCFLECTION e Disc closes off the port allowing only normal spec leak rates, i
e Since distance open < the nut
. deflection, the believilles will drive the disc to the seated position if tne AP drops.
/ \
OtSTANCE g} OPEN p .
~
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- ~ ~
n }
\ l ANd kW 1
( J F IGUP.E 6 ar m- e v --'m!---- --ww--- - e- -- T.'e.m - -w-- y *-9 g w n e-e- w-y w m y- r,- -- y ww&7-w-a *,ye-- x- y- y -
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CHRONOLOGY ATTAc wEnT 5-JULY 9, 1980 gADv!SEDOFMARSHALLTESTRESULTS(36M88) JULY - SEPTEMBER d INVESTIGATIONS INTO SLOCK VALVE SUPPLY FOR NSSS SCOPE AND EVALUATION / RESOLUTION OF VALVE PERFORMANCE AT MARSHALL SEPTEMBER 16, 1980 SAFETY REVIEW COMMITTEE MEETING CN BLOCK VALVES W INVES11GATICNS EXPANDED TO OTHER 3" GATE VALVE APPLICATIONS'AND TO 4" VALVES SEPTEMBER 25, 1980 W ADVISED NRC BY TELEPHONE OF BLOCK VALVE ISSUE SEPTEMBER 1980 EADVISEDOFFAILUREOFCERTAIN3"GATEVALVES TO CLOSE DURING PRE-OP TESTING AT TWO PLANTS , OCTOBER 28, 1980 SAFETY REVIEW COMMITTEE MEETING ON 3" GATE VALVES CUSTOMERS NOTIFIED WITHIN 24 HOURS OF POTENTIAL VIOLATION OF 10CFR50.55(E) OCTOBER 30, 1980 NRC INFORMALLY NOTIFIED OF 3" GATE VALVE ISSUE NOVEMBER 18-20, NRCAUDITATE 1980 DECEMBEa 1980 LABORATORY TESTS ON 3" 8 4" GATE VALVES JANUARY 1981 fNOTIFIEDOFMARSHALLTESTRESULTS(3GM99) JANUARY 15, 1981 gVISITEDNRCTOPROVIDEUPDATEOF3" GATE,, VALVE ISSUE FE3RUARY 5, 1981 NRCAUDITATf FEBRUARY 10, 1981 SAFETY REVIEW COMMITTEE ON 3GM99 PLuS 4" GATE VALVES - CUSTOMERS NOTIFIED WITH 24 HOURS OF POTENTI AL VIOLATION OF 10CFR50.55(E) FE3RUARY 11, 1981 NRC INFORMALLY NOTIFIED OF 3GM99 & 4" VALVE ISSUE
- - - - , - - m .e-- y-g e-w..- - -g- g p-g,m.ar , - "
w f v yw+v -' ' M av 4* v'"'n' '-
WESTINGHOUSE SAFETY REVIEW OF PORY SLotx' VALVE - FAILURE TO COMPLETELY CLOSE AT RATED IORQUE SAFETY REVIEW COMMITTEE (SRC) MEETING - SEPTEMBER 16, 1980 e PORV BLOCK VALVES ARE INACTIVE AND ARE NOT SAFETY GRADE ~ e SAR ANALYSIS FOR THE WORST. SMALL HOT LEG BREAK UMBRELLAS > THE STUCK OPEN PORV EVENT e WCAP-9600 SHOWS NO CORE UNCOVERY ASSUMING ALL PORVS STUCK OPEN (NO BLOCK VALVES) WITH MINIMUM SAFEGUARDS : SRC UNANIMOUSLY AGREED THAT IT WAS NOT A SUBSTANTIAL SAFETY HAZARD UNDER 10CFR21 OR A SIGNIFICANT DEFICIENCY UNDER
~
10CFR50.55(E) ! HOWEVER, ALL CUSTOMERS WERE OFFICIALLY NOTIFIED AND NRC WAS INFORMALLY NOTIFIED OF THE ISSUE (SEPTEMBER 25, 1981) - NRC AUDITS ON NOVEMBER 18-20, 1980 AND FESRUARY 5, 1981 DID NOT DISAGREE WITH THE FINDINGS OF THE WESTINGHOUSE SRC ON THI.4 SUBJECT. h e- - w manae.wmr - w---e. e m g. ey + -9 mey -,,9 - e-y g+ --e,- -- - w u- --y- r, e
l
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OPTIONS AVAILABLE TO PLANTS . e: PHYSICAL MODIFI, CATION) OR e EVALUATION OF. SPECIFIC APPLICATION AGAINST GENERIC FUNCTIONAL REQUIREMENTSJ OR e IN SITU TESTING TO CONFIRM-ADEQUACY.IN SELECTED APPLICATION F 1 P e
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%eir.; preoperational testing at the Virgil C. Sumer Station and at a foreig'n s:a-i:n, pr:blems were sn:cun:ered.whea testing the .'Wesitnghouse n, j y i 3 . c. ..., .r.u. e. ., r. .o . =. d. "mir a. e ". . . "o
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failure to ecmple:ely closa j
- n iestingneuse ncncperatin; plants , the subject t j vas ::.sidered repce: nie :n'y en :nese nonoperatin; plants under title 2
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- ..a rus: .:he fun::i:nal recuireren:tsa may beu signifi:an ,.ly i l eless a s.3 than w. l , ,thew.prec;eratic
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ne subject valves may be ser.en:1y, f t is possible :na: c =riete closure Of a::: piished under actual c;erating c nciti:ns even thcugn Ter ec=;1e:e* exa: pie,c!csure the !
.as net ac::=plished under preopera:f =nal :es: conditicas.il C. Sur. er 5:ni:n .
- erating c
- ndi ices uncer whien ene valve at the closa. 'lirgis re:;uirl instead of the pressure c nditi:ns a wnich the valve failed t: .
j Eastinghcuse has insuffician; informatien en the intendec
^
.:r c;arating plants,n:iicati:n, e......is..,
er exten a. y ,. cf,. . . functi:nal g . a. . . .r . testing . . 'or ;erf:r:ed
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l if a pr::ler. exists , you sh: 'd ca. e" ine the foi10 wing: - r i,
- i. Have nese valves been ins: ailed in your plan.? !
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- 2. .
Have these valves been installed in a safety related syste ? \ T,.3,..a.
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- Page 2 August 13, 1980 - Limitation motor operator with torque sw. setting of 3.75+ cycled through full test procedure and valve was successful with :ero seat leakage.
October 27, 1980 - Westinghouse notifies.. Duke of .3GM88 failures. October 28, 1980 - Letter sent to Westinghouse requesting confirmation and resolution of problem. n n November 1,1980 - Westinghcuse requests information on valve function. November 13, 1980 - Steam Production notified by Design Engineering of potential pr0blem. November 17, 1980 - Meeting held between Design / Licensing and C peration and Maintenance to formulate responsibilit: es. Novetter 20,1980 - (Ken Becreft) Limitorque states 275 ft. lbs . avail-able at 3h position. Westinghouse sistes that motor will stall at 80% voltage at much lower foot-pound
,1,, si,/g/ rating - maximum torque sw. to 2.8.
i November 26,1980 - Unit 2's valve torque switch setting is increased
~~
- 0 "/#I from 1.8 to 2.8.
4 n/s, t
. February 9,1980 - Final Westinghouse specification for field modifi-cation of. valves received by Oconee. )
i February 19,1980 - Unit 3 valve modified. 3 /S 8/ C/M 2. /M ~ .. i
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- na: Westin;h. . . . . ,s ice the a::ve cr:er.has. su;;iiec to you F.0. Item No 4 ;
e s .ww .. . b....e.ase ec. a. , ;
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- is e::=encec na you evaluate the impli:ati:ns of this ?::ential c:nci:icn
,.. . j .... . ..
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<.es f r.; vse wi1*. ::ncinue to keep ycu inf rmed as this issue is fur-her cafined.
Sincere'.y.
.~~
s., s.. . W. F. Van D.vke Yalve C:ntracts
/.
- '/.r. C. F.:: ins n, Ouality C:ntr:1 Manager
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4R 4. ,
. ATTACH"ENT 7
*W / nil 0 gy P 'TO'. D,t'.'- j -.,/
Westinghouse Electric Corporation E 466% es i J Mg y ~ anama cena m::: FY S e/H Octeoer 27, 1980
$g QS g4 VPA-80-123 ,
Mr. B. R. Sylvia, Manager Nuclear Operations and Maintenance
#",p8 Virginia Electric and Power Company c P. O. Box 25666 6 Richmond, Virginia 23261
Dear Mr. Sylvia:
Virginia Electric and Power Company Surry Units 1 and 2, Nortn Anna Unit 1 PORV BLOCK VALVE - FAILURE TO CLOSE AT RATED TORCUE In response to NUREG-0578, Item 2.1.2, EPRI is conducting a safety and relief valve test program. As part of the program, EPRI has initiated pressurizer relief valve (PORV) testing at the Marshall Steam Station (Duke Power); tne physical test arrangement at the Marshall Steam Station includes a PORY block valve. However, it should be noted that block valve testing.is not incluced. in the EPRI Safety and Relief Valve Test Program as currently defined. The NRC has recently issued furtner clarification of NUREG-0578 and an aeditional requirement (to be finalized during October) indicating that "... evidence supported by test that the block or isolation valves between the pressuri:er and each power operated relief valve can be operated, closed and opened for all fluid conditions expected under operating and accident conditions" should be provided (by each PWR Licensee) by July 1, 1982. The following information is being provided to advise you of results of tests conducted on the Westinghouse designed gate valve used for the PORV block valve application. It should be noted that plant specific Safety Analysis Report documentation states that the function of the block valve is to seal off leakage through and to provide for maintenance of the PORV and identifies " the PORV block valve as inactive. .. During initial checkout of the test loop at the Marshal
- Steam Station, the
- Westinghouse block valve did not close completely against 240,000 lb/hr steam flow from a 2400 psi source at 600*F. As installed, the valve was able to block 87 percent of the flow area. After the motor operator was modified to provide higher output thrust, the valve was able to close completely during
- repeated cycling against this steam flow. Subsequent inspection showed the _.
valve internals to be in excellent conditi,n. l Ch . _ - - - - .m_ W
"2 October 27, 1980 Page 2 The consecuences of incomplete closure of.the block valve have been reviewed and it has been determined that this situation does not constitute a report-able safety issue. The failure of a PORY to close (and assuming no block valve) is an analyzed condition and as detailed in WCAP-9600, core uncovery will not occur even if all relief lines remain completely open-(i.e., de-pending on plant specific design, two or three stuck open PORVs and assuming no block valves), assuming minimum safeguards.
Westingnouse is currently preparing a valve operator gear modification wnich will provide the higher output thrust required to close the Westingneuse block valve against flow. Very truly yours, fan v
. !bgW .
G. K. Griffiths, Manager Southern Area 0012A . cc: J. T. Rhodes E. A. Baum [ J. L. Wilson L. M. Girvin J. L. Perkins F. M. Alligood W. R. Cartwright V. W. Lockman W
~
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Wy.o.010 Westinghouse Water Rea: tor f *= **nc8' D"*ca
. Electric Corporation Divisions scirir ,
Che5 wet Penezy' vama 15:T24 Cacre WECHESM0K i 1412: 274 0 00 (41213 0 8700 TWI 5104671660 TED B68547 October 27, 1980 Virginia Electric and Power Company General Offidis + P.O. Bcx'26660 - Richmond, Virginia 23261 Attention: Mr. W. R. France
Subject:
Motor Operated Gate Valve for Surry Power Station Your Order No. 52096 Our G.O. RM-64197-EM EMD S.O. H-117
Dear Mr. France:
Our records indicate that Westinghouse has supplied to you two (2) 3GMSSFNB Gate Valves for the subject order. The purpose of this letter is to notify you that 3" gate valves of this type have been tested under conditions of high flow and pressure differences. The small number of valves tested thus far did not completely close. Further tests will be conducted to evaluate the cause and recomended corrective action. It is recomended that you evaluate the implications of this potential condition for your specific application. Westinghouse will continue to keep you informed as this issue is further defined. , Sincerely, Y-W. F. Van Dyke Valve contracts
- /md
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@ WV-0-010 Westinghouse Water Reactor E!c
- Mc8'c8' D***"
Electric Corporation Divisions ee:217 Chaewet Ptecryvan:a 114 Catie WECHESMCK 441D 274 E300 t412) 263 8/00 TWI 5104671E60 # TEII 965547 October 27, 1980 Virginia Electric and Power Company General Offidis P.O. Box 26666 - Richmond, Virginia 23261 Attention: Mr. W. R. France
Subject:
Motor Operated Gate Valve for Surry Power Station Your Order No. 52096 Our G.O. RM-64197-EM Ev3 S.0. H-117
Dear Mr. France:
Our records indicate that Westinghouse has supplied to you two (2) 3G'MSSF'iB Gate Valves for the subject order. The purpose of this letter is to notify you that 3" gate valves of this tyce have been tested under conditions of hlgh flow and pressure differences. The small number of valves tested thus far did not completely close. Further tests will be conducted to evaluate the cause and recommended corrective action. It is recocrnended that you evaluate the implications of this potential condition for your specific application. Westinghouse will continue to keep you informed as this issue is further defined. .. Sincerely, Y . W. F. Van Dyke Valve Contracts - /md
+e.. ,,,e,. m,-.
pjs P /1 C I# o , - yyrr s ' " F W"fC
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- r-msecase seca%rm a m a sain x:x:
gan.
.EIG GDV 5 BBC UL October 31, 1950 VPA-60 126 Mr. B. R. Sylvia, Manager 1
Nuclear Operations and Maintenance * . Virginia Electric and Power Ccasany ' P. O. Box 25666 Richnend, Virginia 22251
Dear Mr. Kylvia:
P
- 6 Virginia Electric add Power Ccapany Surry Units 1 and 2,. North Anna Unit 1 WESTINGHOUSE 3' MTE VALVE Ct.05URE PROBLEM i
The Westinghouse Safety Review Ccanittee met on October 22, 1980 to review a problan of valve preoperational closure failure at Westinghcuse nonope-ating plants during tasting. deficiency and p n were vertally notified on CctooerThe committee detemine forzitlizes that natification persuant to t1tJe 10CFR50.55(E).'
- 23. 1980. This letter Attached are the details of this problem and if me can provide. additional clarifications, ple.ase cantact the undersigned. ,-
Very tru11 sours,
. . . .. ~
G. K. Griff s, Manager Southern Area; [. @N. , .
" - ~
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During preoperational testing at a domestic station and at oreign station,
.' problems were encountered den testing the WestinghoywElectro-Mechanical Division manufactured three inch gate valves, Moder 3GR88,1500 lb. class.
The later redesign version, 3GM99, may be coraidered-te-t(subject to the same - problem. The tested valves failed to completely close under preoperational
~ test conditions (i.e. , approximately 2700 psi as flow approaches zero), these tests were conducted at a condition less severe than the equipme;nt specification -
design conditions (i.e., 2750 psi as flow approaches zero). The valves stroked to significantly restrict flow, but the full stroke was not accomplished to trip the " closed" position indication contacts in the motor operator or to seat the valve disc within the valve body. Westinghouse has reviewed the scope of supply for the subject valves. The
. majority of these valves have been supplied to Westinghouse nonoperating plants as part of the NSSS scope of supply. A smaller number of these valves have been sold directly to several Westinghouse operating plants, as spares or re-placements, as well as to non-Westinghouse plants.
Westinghou:e has reviewed the application of the stbject valves en Westinghouse t nonoperating plants. Westinghouse has detemined that several of these valves are classified as " active" valves (i.e., mechanical operation is required to accomplish a safety function) and are utilized in the Chemical and Volume Control System and the Emergency Core Cooling System. The functional require-ments for ' active" valves include closure under operating pressure / flew conditions. Since the subject valves are utilized in " active" applications - on Westinghouse nonoperating plants, the subject failure to completely close was considered reportable only on these nonoperating plants under title 10 CFR 50.55(e). - As pa'rt cf this review on Westinghouse nonoperating plants, it was determined that'the functional requirement pressure / flow condition under which the valves
. salst close may be significantly less than the preoperational test and equip <
,, , ment specification conditions under which the WP.1ves failed to close. Con-sequently, it is possible that complete closurt SY the subject valves may be
~
. ,. accomplished under actual opersting conditicns even though complete closure was not accomplished under preoperational test conditions,. For examp.le, the -
~ '
- operating conditions onder;which the valve at the domestic station fs required. -
~.[ , pressure ccedit:!cos at which the valve failed to close.
- to func. tion is approximately 1200 psi as . flow approachar. 2sen fastead of the
. .' .. For operating piants,. Ilestinghouse has insuffident inforsation an the intended application, or artant of' functional . testing ruTw.W .an these valves, .
therefore, we cannet make< a complete evalunden. 4n. arder 11er you to evalusta
.- if a.pechlam arists .Jos shouM determinejthe fonowing:
~
. .. - L. Have tinse values beerMascalW.fa 2currplant?
.s '. L. Name these-selves beso fnetened, in.a'safetrretated ini. J
~.f,...i T . .Is.' valve closare. .W4:to. % -Nish a sefsty-related fonct.fon?
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- 4. Under what functional requirement operating conditions "is valve closure ;
required? . ,
- 5. Nas operational testing been per~ormed to verify valve closure. under :
the functional requirment operating conditions? Listed below for your information is a simrnary of typical functional re- i quirement information for various valve applications in nonoperating plants. > Although this information is not available for your plant, it may assist in your evaluation. Westingh;use is continuing its efforts to develop additienal , information concerning thtf problem and to develop appropriate modifications. You will be notified accordingly as this additional infomation becomes available. Maximun AP (psi)
. as Flow Approaches Zero '
. .s Equipnent Functional )
Systan Yalve Function - Specification Requirement CYCS Qarging Line Isolation 2750 2700 , CYCS Og. Pump Miniflow 2750 2700
. I. solation CYCS .
. Latdown Line Contairmient 2750 600 !
Isolation Boron Injection Tank
. ECCS 2750 1200
. Isolation
- ECCS Bot Leg Rectrenlation Iso. ' 2750 . T200
. ~ .
ECS Cold Leg Recirculation Iso. - 2750 1200 i 1 - I
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* . Lh' I */). EL'y.0-O.n Westinghouse Electric Corporation Power Systems se. - mem Sc2 *17 own2 Pynyma 15C24 coewoetra (412)274 63:D *
(412)3E337:0 November 1,1980 Virginia Electric and Power Company General Offices P. O. Box 2566 ' Richmond, Virginia 23261 - - Attention: Mr. W. R. France
Subject:
Motor Operated Gate Valve fer Surry Power Station Your Order No. 52096 Our G.O. RM-64197-EM EMD S.0 H-117
Dear Mr. France:
Further to our subject letter, please refer to Attachment .i and provide the infor nation requested. Very truly yours, W. F. Van Dyke Valve Contracts .
/md Attachment e
V aunas m 4
+- ,m..-=e. w .wa>,. , . . . . . ww .. . ,,
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- a. _r,, aimsi .me9
- ev
f At.Lachment A g operational testing at the Virgil C. Summer Station and at a foreign
.ation, problems were encountered when testing the Wesitnghouse Electro-Mechanical. Division manufactured three inch gate valves, Model 3GM88,1500 lb.
.- class. The.later redesign version, 3GM99, may be considered to be subject.to the same problem. The tested valves failed to completely close under pre-operaticnal test conditions (i.e., approximately 2700 psi' as flow approaches' !
2ero), these tests were conducted at a condition less severe than the equip-
' ment specification design conditions (i.e., 2750 psi as flow. approaches zero).
The valves stroked to significantly restrict flow, but the full stroke was not accomplished to trip the " closed" position indication contacts in the motor operator or to seat the valve disc within the valve body. Westinghouse has reviewed the scope of supply for the subject valves. The majority of these valves have been supplied to Westinghouse nonoperating plants as part of the NSSS scope of supply. A smaller .. umber of these valves ' have been sold directly to several Westinghouse operating plants, as spares or replacements, as well as to non-Westinghouse plants. - Westinghouse has reviewed the application of the subject valves on Westinghouse nonoperating plants. Westinghouse has determined that several of these valves are classif ted as " active" valves (i.e., mechanical oceration is required to accomplish a safety function) and are utilized in tne Chemical and Volume Control System and the Emergency Core Cooling System. The functional require-ments for " active" valves include closure under operating pressure / flow conditions. Since the subject valves are utilized in " active" applications on Westinghouse nonoperating plants, the subject failure to completely cNse was considered reportable only on these nonoperating plants under title 10CFR50.55(e). As part of this review on Westinghouse nonoperating plants, it was determined that the functional requirement pressure / flow condition under which the */ilves must close may be significantly. less than the preoperational test and equip-
. ment specification conditions under which the valves failed to close. Con- ,
sequently, it is possible that complete closure of the subject valves may be accomplished under actual operating cenditions even though complete closure was not accomplished under preoperational test conditions. For example, the r operating conditions under which one valve at the Virgil C. Summer Station n is required to function is approximately 1200 psi as flow approaches zero, .. instead of the pressure conditions at which the valve failed to close. - For operating plants, Westinghouse has insufficient information on* the intended , application, therefore, we cannot or extentmakeofa functional complete evaluation. testing performed In order foron these you to evavalves, , luate ',
,if a problem exists, you should determine the following:
- 1. Have these valves been installed in your plant?
l :
- 2. Have these valves been installed in a safety related system? .
- 3. Is valve closure required to accomplish a safety related function? ?
l i . l ,
,/ .g.
/ ,
/ .
l 4. Under what functional requirement operating conditions is valve closure required?
- 5. ,
Has operational testing been performed to verify valve closure under the functional requirement operating conditions? Attached tion provided for to your. information nonoperating plants.is a copy of the functional requirement informa. - . been reviewed for your plant, it may assist in your evaluation.Although this inf h 3 9 > 9 s , e
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. R 8 . 2; y fi "
as Flow Approaches 2-5 3 T,, h U U 5' "' Location C ( "2 .h 15 % . % 0 Valve Ferction Number x " >
.E 3 E
" 5 % % "g 8 Equipment
' " * " *% S ecification Functio; P
Require; ! Charging Line Iso. . 8105 X X X X X X X X X X X 2750 - - 2M 8106 X X X . X X X X X
" X X X 2750 2M 8107 X X X
" 2750 270(
8108 X X i
" 2750 270( .
i 8146 X 1
- 2750 270('
Chg. Pump Miniflow Iso. 8106 X X X 2750 - 270C l Letdown Line ~ l Containment Iso. B151 ' X 2750 60C Bsron Injection ; Tank Iso. 8801A X X X 2750 1200i . 88018 X X X i'
" 2750 12M ! '
8803A. X X X .
" 2750 1200 88038 X X X -
2750 Hot Leg Recirculation 1200l. Is o.- 88il4 X X 2750 1200' 8086 X X
" 2MO . 1200 8814 X
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2750 1200 8816 X . 2750 1200 Cold 1.eg Recirculation Iso. 8885
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~ . e % 1
[ WV-0-067 Westinghouse Power Systems h m D= Electric Corporation Company em Caswt* Pyrrma1!C4 CuntwEcHEIMCK (41D274 C00 (41DZ38730 i November 14, 1980 Virginia Electric and Power Company General Offices P. O. Box 2666 Richmond, Virginia 23261 Attention: Mr. W. R. France
Subject:
Motor Operated Gage Valve for Surry Power Station Your Order No. o2096 Our G.O. Ed-64197-EM EMD S 0. H-il 7
Dear Mr. France:
By our letter of October 27, 1980, you were informed that 3-inch motor operated valves were tested under conditicis of riigh flow and pressure differences and that a small number of those tested did not close. In this letter, it was reconriended that you evaluate the implications of this potential condition for your specific application, identified in the subject, above. Attachment A to our letter of November 1,1980, further identified [ this condition and in greater detail. Five specific questions were posed to which your answers are required by Westinghouse to make an evaluation. You are requested to provide this infonnation to WEMD by November 19, 1980, er identify by that date when you will provide the infonnation needed. Your assistance in this matter is required so that we can continue to be of service to you. Yery truly yours, - O J. F. Vandyke __ lalve Contracts WFV/gac l
.w < l ,.c6
' -... )r .c s
\j' H~ U~. a .WL. P: .
Vi cir.;: .:: ee ., nama E!::fri: C:t;,0ra:!ca ' ' C I v, .F-I ? / tm"w: . 2/ Ara. 3 C.:rp ::
- a. .- ;. ~ y.
( ?.- *. >. ., ve,p February 12, 1931 VPA-SI- 511
" . 3. %. Syl v i: , li::n g :e
- u:1 ear Cp.raticas & .M nten r.:.:
Virginia Elc:ti f: and Pcwer Corpany P. O. Ecx 25555 P.ic.S:nd, Virgin 4 23251 Cear Mr. Sylvia: VI?,GINIA El.ECTRIC AND FO'JER CCMP/.!'t SURF 1Y U. NITS 1. & 2 - NORTH ANNA UNITS 1 & 2 . WESTi m 0USE O!D VALYE IS UES '
, In October 1950, Westinghcese informed ; 09 that plant preopert.tional tests disclosed that Westinghouse Electro Me:52n4 - ' Division manufactur:.:' t!.rce inch gate valves, medc1 3GiSS,1500 lb. cl0 failed to cc.:pletely cic:a under preoperational test conditions (i.e., proximately 270,J pSIC cs ficw approaches zero). These conditions were less severe th:n the epipment si;,2cification design conditiens (i.e., 2750 PSID as flo'.f epproachc: : era).
A: that tir. Westinghause also reported that the later redasf;nc.i version i of tnis val .e. the codel 2499, may also be subject to the stme probic:: although no testing was , fonned on this codel. Westinghouse instituted an engineering investigation to det'2rmine the cause of the problem, labora tory testing has verified that the mod 213099 will not close when subj;cted to the same preoperational test hydNulic conditions. These tests also show:d that the proble 1 is extended to the !lcstinghouse 4 f r.ch model 4GM87 and 4GMC valves. Th cope of supply for *se valves is similar to that of the model 3 ES. T:' majority have bc.:an st . glim to thestinghouse non0peratirg piants c part of the HSSS scope of supp';y while a smaller number have been s:ld di. .t by the Electro Machanical Division to operatin; plants (both !!estin;;.u n 4.nd non-Westinghou:c) as sparcs ce replace.unts.
- t. :tinghou:a h :s t' 'erm' d that fer n0noperatir.; plants, several of t! :c w.iv. are cle cif: d as " activa" (i.e., cochanical estion B r:g: fred a r c .*ct.a a t Ts y .n eth..) . Yha func>ical rgirt snts @ "cetive" v .- '
...:l " 4 c h. ,u. i u.t. 2. c. Ei".. i . cs u a/ fi t.! r. . : .'i .. : : !M . S. :0 t:2 ".
. , , . , _ ,_. ' = * ~ ~~'
.a Mr. B. R. Sylvia . February 12, igL1 - i VPA-31-511 !
valves.are utilized in " active" applicaticns on Westinghouse non opeed.: " ' plants,. failure tt. completely close was considered repertab1_e only en t..h non operating plants under title 10CF?. 50.55 (e). -Uestinghouse will mka , no femal USNP.C notification of this probicm. l
.It was determined that the functicnal requirement (pressurc/ficW) ccnditica under which the valu. must cics2 may be significantly less than the pec- '
operatio ..:1 test and equip.. ant specification conditiens under t;hich tha valves failed to c1cse. Consequently, it is possible thet complet.: closure ' cf the subject valves may be acec.c.plished under actual cparating c::nditton: ;
. even though ccmplete closure w.as not acceplished 'u:de- test cenlitions. ;
Fcr operating plants, We tinghouse has insufficient. infomation en th: in :nd-ed application, or extent of functional tasting parformed on t'r:n valv.s - , since they were provided on a spare er replacen.ent basis. In order for ycu ! to ccmpletc your can safety evaluation you should detemine the felicaing: ,
- 1) Have these valves bcon installed in your plant?
- 2) Have these valvas been installed in a safety related system?
- 3) Is valve closure required to acccmplish a safety relat:d function?
- 4) Under what functional requirement operating conditions.is valve' closure '
required?
- 5) Has operational testir.g been performed to verify valvo closure unJcr tha functional requirement operating .mditions? ,
Listed below for your information is a sud::ary of'typica_1_ functional requirements for various valva applications in Westinghouse non operating - plants. This information is actual functional conditions.provided to assist you in determining your ' Maximmi AP (psi) as Flow Approaches Zero ,,,_..
. Equipment Functional .,
System . Valve Function . Specifica tion P.equira.w nt CVCS Charging Line Isolation 2750 2700 - CYCS Charging Pump Minific t Isolation 2750 .2700 CYCS Letdown Lin Cone nment 2750 600 Isolation ' ECCS Coron Infection Ti:n!: Isola tion 2750 1200 ECC5 Fot 1.nj . Sci .uktion Isol *.ien 2753 12.N ECCS Cald I.e .r.cciceob: M itch;.icn 7.730 1:C I U. .#5 L d..' . .m '. f in In t ' c " P.M .': $'3 i
+
- . . , , , ~ , - - . - - . , -. . . , - , , , . , , . . - . , . . . - . . , - . . , . - , . . , ~ . , . . , . . - - , . . . - ,
. - . .. . ..~. . - -.- -. _ _ - - -.
{ Mr. B. R. Sylvia- -
- 3- February 12, 1901 ,
i VPA-81-511 The re. air for the 3 inch valves un n r consideration is as fo11cws: 32188 ' l. Change the operator gaar ratio .to insure E0% voltage , closing ca,7 ability. :
- 2. Implen:ent limit closing centrol utilizin] the ccp..bilities of the spring espinsators en the Lhitorqua SB-00 opar.. tors. {
39:99 1. Change the operator fred Limitorque 5"C-CJ to S3-00.
- 2. L.:;i::.,.rt limi t c!c:;r.g con:ral . . l
. Tne repair for the 4 inch valves is still being evaluated.
If we can be of further service to you in this matt:. , pleaca contact us. , Very trul yo rs
/ , s-
, )A G. K. Griffiths, Manager
- Field Service - Southern Area >
Nuclear Service Division . I cc: J. T. Rhedos i E. A.. Bet:n L. M. Girvin
- W. L. Stesart C. W. Pennington J. L. Wilson W. R. Cartwright V. W. Lock :an e
4 e i y e w r w 4-Pwaw*= .+vm4 - *.wi a o.ep g czy-* -iy- st--- up re-we+ww- >-3 y r's-gyg- e - ust + pg *- eswWH pp. y 9-gy-=e:. ==g---yT- m y f- eeN-t*?49-wty -y ?mt-"Mg- m u y
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It i february 13, 1951 VPA-81-11 Mr. 3. P. Sylvia, Managte Nu: lear Operations and Mainter.ar. e
^
' Virginia Electri and Power Co.p2ny a
. D. .:,x .:..>: . .
Ri:necnd, Virginia 23251-i
- -3r M . :yb;i a: ,
n W:.. S . .p. p s. , , u- o. .. ~. .k,,- .. u...: 6, , .h v , c.,2 ,.,. .- -- _ 3. -.
. s The bestin;,cuse Safety Reviu Co ci tee re en :abruary 10 -El sc r . Y .
l th: tr:oitr.. of valve -lesure fai h re ef Medel 23"Ji', tams 7 ar. 42."E3. Tre 0--ittee ce:ided tna all utilities freuld be no:ifie cf tha probie . inc i atta:h.en: am;:lifies end formali:es the ve .,a1 notifi : ion ef. U.S. pia .;.s en ! Fe:r.;ary 11, 1?^1. *
' Fc a:diti:nal clarification please ::ntact the un:ersigned. ?
Ve y truly y:urs, i
/ f'i/ //,. Jti 'o M
JM54- ** V99 = := G.K.GrIffiths,Haasser Scutnern Area Atta:n=ent
- J. T. Rhodes E. A. Baum J. L. Wilson L. M. 7irvin J. L. Perkins F. M. 411:gced '
W. F. Cartwright G. E. Williams : V. W. Lock. man W _ i 0 l-
.e >
0 P l i i W& 1 i
. i t
v '.Wp
- tw + my g gw,$ M ys
+- m .,,,.-w,euw..g, .=- -y.m -f-- , y- ,,,.p.,-- - - - ,.n,.,.-,m,-.,.,%,, .,.--w,,.--,-&-,-- -w.---.. . . , - . - -- ,-
s t t i t In 0::::er 1930, Westingneuse infor=ec the affe::cd plants tha . plan: pre- ; [ cperathm1 *ests eisclosed. :na: Westinghouse Eiertro " c hani:21 Divisi:n q
=ancft: ured :nree inch ;ste valves, M: del 2GM5. ' 00 lb. lass, faile:
to ::::letely 01:se under pre::erati:nal test c nditi:ns (i.e. , a::r:xira:ely i 2700 psid as f1:s approaches :er:). These c:nditiens a re less severe : nan l
- r.e er i:mer.: ::e:ifi:s-icn :ssi;r ::.diti:n2 s (i.e. , 275 psi: as #1:.. i
- a::r:s:nes :er:). A: ths:' time, Westingnces.e also rep rted :na: :nc la:er recesi;re: verst:n Of :nis valve, tne Mcdel 3GM99, cay also ce su:je:: to :ne ;
sare pr:blem, al:n:ugn no. testing was perf:-=ed en :nis macel.
. t Westin;. use ins-ita:ec an engineerin; inve:: iga:1:n :: ce:e-:ine th: :s;s-Of :ne pr:blam. Laterat:ry testing has verifie: :na; :ne tb:e1 22"?? .111 ;
n:: class anen subjects: :D - same pre:perati:cai tes: hydrauli: : n:itic s. Tnese tests also sn:wed that a problem is extenced :: the '.lestin;n:;.se f:ur in:h M: del 4GM57 and 4GE .. , The !. ?e of supply f:r these valves is similar to na: cf the M::e1 r<II. J The me rity have been supplied to Westin;heuse ncn:pera:ing plants as par , t of the MISS s:cpe of supply while a smaller number have been sold dire:tly - } by the Ele: re Mechanical Division to operating pland (botn Westinghn. s t and non-Westinghouse) as spares er replacements.
-- i Westingt.: :e has deter =ined tnat, for nonc;erating plants, several of these valves are classified as " active" (i.e. , m.echanical moti:n is re::uir:d..:: '
per'or: a safety fun :icn). The functicnal requirements for " active" valves i include closure under operating pressure / flow conditi ns. Since the subje:: l velvea are utili:ed in " active" applica:icas on Westinghcuse nonoperating plants, f ailure to c:npletely close,was censidered reportable only cn-th2se non perating plants under title 10CFp.50.55(e). Wes-inghouse will me!:e r.3 . formal MP.C n::f ficati:n of this problem. E s 1 a f mpy--y- = = > , , ,.--.
-n 9 -. sr -go. 4.pnm.,,,*es.=wg yg py 9--,,9-vy-yag,yg.--e-sy. g -s.m,y g,...g.-- ma. --@e*dv'-dS'"TwerW**M"D" TT'-1= wW m' e- s' 94-,'7 "*- '*,e-**"we-e- w-iw*e'*--e'-
'96
. . i 1
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' n a. ". , v" .3 'Aa..e ..1 ;.
. . h.. u s 2. ' r. .
. *. . .= . d. .a. ,-
1a..e, * ..=..
,, . . .. ...a. #. ~. a. . . . '.. .a. .a 'i re:vi reme' Oressure/ flow) c:ncition under wnich tne va!ves mus : lese may be' sis 'i :n:1y less than :ne pre:pera:icnal t2s: and e::vi:=en: spe:ifi.
ca:icn ::nci:icns uncer wnich :ne valves failed t: 1cte. Conse:;;e":1y, it is' pcs:ible tha: c:mplete ' closure Of the subje:: valves :y bs at:..;1isne under a::ual 0;.erating cnciti:ns even tn:vGn cc :leta c1:sure wa: n:: #
. . s . c , .a. .L.. ,
a . . ._. l i a. . . s......s. Tre affe: e: valves :en be ':e . ified by :ne y:L ":.nte: name:I ' e. These r name:la es are star:ed "'JEITI.E%'IE" and incl. 7 ALVE I:E*.T." an: " VALVE
..]." num:ers as sh:w1 in Table I. All name;1a have "VA'.VI IDE ;7."
nut:e-s, but :.no:e s:1d as spares er re;iacements may not have "V"LVE !.D." r.ur: e r s . Tna " VALVE IDE:.'~." n.;::er . includes the manufs: urers c: del referen:e an :te " VALVE I.C." num:er is a referen:o : the valve system a; li:stic: . The " VALVE !.D." num:er also ap; ears en Westingh:ase valve incexe: ar.d syste's flew :iagrams. There is no reference ::. he "Vk.VI !:Il7." nutter en these indexe: Or flew diagracs. Table I indicates the cifferential pressures for the various valves above wnich pr:per o:eration cann:: be assured. , For c;erating plants, Westingneuse has irsufficien; information on the inten 'e: applica .i:n or extent Of fun::icnal testing perfc-med on these valves since- , they were provided as spares or repla:erents. Therefore, in order for you :s perform y:ur own safety evalua:icn you sheuld consider :ne following: i
- 1. Have these valves been installed in your plant?
- 2. Have these valves been installed in a safety related system?
- 3. Is valve closure required to perform a safety related function?
f 4 Ur.d e: what functional re;uirement cper: ting c nditiens is valve
- lesure re:'., ired?
E. Ha 0;er::imi usting buen perf r.nco te vkrify valv:. cic7ur; f
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h Liste: : ei:.. fo your ir.f:rmeti:n is a su- e y Of ty;i:al fun:-i:ral e:uire- ' ren; infor .iti:n for varicus valve a;oli: :iens in Westingn:vse n:n:; era ing f 1 plants. 'i nis infer:na icn is provice: to assis; you in ce:emining your I actual fun::i..11 :entitiens: .
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cs. Isolatien Hot Leg Recirculation Isc. 2750 1203 ECCS 2750 1200 ECC5 Cold Les Re:ir:ulation Isc. . I i The engineering valve tes program was cc ;rised of a series of flo.; tes:s performed in a hydraulic test lab:r ::ry using a centrifugal :na ;ing pu ; ; to provice flew and pressure. These tests :ensisted of 75 to 100 closing and coening cycles as: inst flews and pressures as high as 600 g;m and
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2600 psid, respectively. These cycles provi:ed the expe::ed valve seat, to disk wear wnich.resulted in stabili:ed valve closing leads Once One s abili:ed level was reached, closing tests were run at Icwer flows and ; differential pressures to determine One extent of the closure problem. . i Modifi:stiens for the three inch valves have been c;u:lf fied by testing. Thess re:ifi:ations arc as follows:
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