NRC Generic Letter 1987-06

NRC Generic Letter 1987-006: Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves

ML031150379
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Clinch River
Issue date:	03/13/1987
From:	Denton H R Office of Nuclear Reactor Regulation
To:
References
GL-87-006, NUDOCS 8703160202
Download: ML031150379 (3)

IUNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON. 0. C. 20555.MAR 13 3987TO: All Holders of Operating LicensesGentlemen:.

SUBJECT: PERIODIC VERIFICATION OF LEAK TIGHTAINTEGRITY OF PRESSURE ISOLATIONVALVES (GENERIC LETTER 87-06'Pursuant to 10 CPR 50.54(f), NRC is seeking to verify the methods, if any, bywhich each opetatng reactor licensee is assuring.the leak-tigh.t integrity of'all pressure isolation valves as independent barriers against abnormalleakage, rapidly propagating.,failure, and gross rupture~of the reactor coolantpressure boundary.Pressure isolation valves (PIVs) are defined for each interface as any twovalves in series within the reactor coolant pressure boundary which separatethe high pressure reactor coolant system (RCS) from an attached low pressuresystem. These valves are normally closed during power operation. The reactorcoolant pressure boundary (RCPB) is.defined in 10 CFR 50.2 and generallyincludes all PIVs.Periodic-tests or verifications'Of the leak tight integrity of all pressure _-isolation valves are necessary in'order to assure the integrity of the RCPB inaccordance with 10 CFR 50, Appendices A and B. General Design Criterion (GDC)14 of 10 CFR 50, Appendix A requires that 'The reactor coolant pressure -boundary shall be designed, fabricated, erected and tested so.as to have anextremely low probability of abnormal leakage, of rapidly propagating failureand of gross rupture." GDC 30 requires that "The reactor coolant pressureboundary shall be designed, fabricated, erected, and tested to the highestquality standards practical ..." GDC 32 states that Components which arepart of the reactor coolant pressure boundary shall be designed to permit (1)periodic inspection and testing of important areas and features to assesstheir structural and leak tight integrity ..." Further, as outlined inAppendix B to 10 CFR 50, each licensee's quality assurance program mustinclude planned and systematic actions which will provide adequate confidencethat these components will perform satisfactorily in service.All plants licensed since 1979 have all PIVs listed in the TechnicalSpecifications along with testing intervals, acceptance criteria and limitingconditions for operation. Certain older plants were required to periodicallyleak test, on an individual basis, only those PIVs which were listed in anorder dated April 20, 1981 (Event V Order). That order was sent to 32operating PWR's and 2 operating BWR's. Other older plants have had nospecific requirements imposed to individually leak test any of their PIVs.A number of events have occurred in LWRs involving leakage past pressureisolation valves, failures of the valves, inadvertent actuation of the valves,or mispositioning of the valves. NRC is therefore seeking assurances that theRCPB is being protected.1> ~0150 0O00? 11

-2-Accordingly, you are requested to submit a list of all pressure isolationvalves in your plant. For each valve, describe the periodic tests or othermeasures performed to assure the integrity of the valve as an independentbarrier at the RCPB along with the acceptance criteria for leakage, if any,operational limits, if any, and frequency of test performance. Thisinformation is required to be submitted within 90 days of this letter. Ifcurrent plant Technical Specifications require leak rate testing of all of thePIYs in the plant, your reply to that effect will be sufficient.This request is covered by Office of Management and Budget Clearance Number3150-0111 which expires September 30, 1989. Comments on burden andduplication may be directed to the Office of Management and Budget, Room 3208,New Executive Office Building, Washington, DC 20503.Our review of your submittal of information in response to this letter is notsubject to fees under the provision of 10CFR170.

Sincerely,_ _ R42mFRflid pk Harold enton, irector__ _ _Office of Nuclear Reactor Regulation F"'LIST OF RECENTLY ISSUED GENERI& -ETTERSGeneric ILetter No.Date ofSubject IssuanceIssued ToGL 87-05 REQUEST FOR ADDITIONALINFORMATION-ASSESSMENT OFLICENSEE MEASURES TO MITIGATEAND/OR IDENTIFY POTENTIALDEGRADATION MK103/12/87LICENSEES OFOR S,APPLICANTS FORDL'S, ANDHOLDERS OFCP'S FOR BWRMARK ICONTAINMENTSGL 87-04GL 87-03GL 87-02TEMPORARY EXEMPTION FROMPROVISIONS OF THE FBI CRIMINALHISTORY RULE FOR TEMPORARYWORKERSVERIFICATION OF SEISMICADEQUACY OF MECHANICAL ANDELECTRICAL EQUIPTMENT INOPERATING REACTORS, USI A-46VERIFICATION OF SEISMICADEQUACY OF MECHANICAL ANDELECTRICAL EQUIPMENT INOPERATING REACTORS (USI A-46)03/06/8702/26/8702/19/67ALL POWERREACTORLICENCESALL LICENSEESNOT SUBJECT TOUSI A-46REQUIREMENTSALL HOLDERS OFOPERATINGLICENSES NOTREVIEWED TOCURRENTLICENSING --CRITERIA ONSEISMICQUALIFICATIONOF EQUIPMENTGL 87-01PUBLIC AVAILABILITY OF THE NRC 01/08/87OPERATOR LICENSING EXAMINATIONQUESTION BANKALL POWERREACTORLICENSEES ANDAPPLICANTS FORAN OPERATINGLICENSEGL 86-17AVAILABILITY OF NUREG-1169,"TECHNICAL FINDINGS RELATED TOGENERIC ISSUE C-8BWR MSIC LEAKAGE AND LEAKAGECONTROL SYSTEM10/17/86ALL LICENSEESOF BOILINGWATER REACTORSGL 86-16 WESTINGHOUSE ECCS EVALUATIONMODELS10/22/86ALLPRESSURIZEDWATER REACTORAPPLICANTS ANDLICENSEESGL 86-15INFORMATION RELATING TOCOMPLIANCE WITH 10 CFR 50.49,`EQ OF ELECTRICAL EQUIPMENTIMPORTANT TO SAFETY"09/22/86ALL LICENSEESAND HOLDERS OFAN APPLICATIONFOR ANOPERATINGLICENSE