NRC Generic Letter 1987-06: Difference between revisions

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{{#Wiki_filter: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  
{{#Wiki_filter:I UNITED STATES NUCLEAR REGULATORY  
-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
COMMISSION
}}
WASHINGTON.
 
0. C. 20555.MAR 13 3987 TO: All Holders of Operating Licenses Gentlemen:.
SUBJECT: PERIODIC VERIFICATION  
OF LEAK TIGHTAINTEGRITY  
OF PRESSURE ISOLATION VALVES (GENERIC LETTER 87-06'Pursuant to 10 CPR 50.54(f), NRC is seeking to verify the methods, if any, by which each opetatng reactor licensee is assuring.the leak-tigh.t integrity of'all pressure isolation valves as independent barriers against abnormal leakage, rapidly propagating.,failure, and gross rupture~of the reactor coolant pressure boundary.Pressure isolation valves (PIVs) are defined for each interface as any two valves in series within the reactor coolant pressure boundary which separate the high pressure reactor coolant system (RCS) from an attached low pressure system. These valves are normally closed during power operation.
 
The reactor coolant pressure boundary (RCPB) is.defined in 10 CFR 50.2 and generally includes 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 in accordance 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 an extremely low probability of abnormal leakage, of rapidly propagating failure and of gross rupture." GDC 30 requires that "The reactor coolant pressure boundary shall be designed, fabricated, erected, and tested to the highest quality standards practical  
..." GDC 32 states that Components which are part of the reactor coolant pressure boundary shall be designed to permit (1)periodic inspection and testing of important areas and features to assess their structural and leak tight integrity  
..." Further, as outlined in Appendix B to 10 CFR 50, each licensee's quality assurance program must include planned and systematic actions which will provide adequate confidence that these components will perform satisfactorily in service.All plants licensed since 1979 have all PIVs listed in the Technical Specifications along with testing intervals, acceptance criteria and limiting conditions for operation.
 
Certain older plants were required to periodically leak test, on an individual basis, only those PIVs which were listed in an order dated April 20, 1981 (Event V Order). That order was sent to 32 operating PWR's and 2 operating BWR's. Other older plants have had no specific requirements imposed to individually leak test any of their PIVs.A number of events have occurred in LWRs involving leakage past pressure isolation valves, failures of the valves, inadvertent actuation of the valves, or mispositioning of the valves. NRC is therefore seeking assurances that the RCPB is being protected.
 
1> ~0150 0O00? 11  
-2-Accordingly, you are requested to submit a list of all pressure isolation valves in your plant. For each valve, describe the periodic tests or other measures performed to assure the integrity of the valve as an independent barrier at the RCPB along with the acceptance criteria for leakage, if any, operational limits, if any, and frequency of test performance.
 
This information is required to be submitted within 90 days of this letter. If current plant Technical Specifications require leak rate testing of all of the PIYs in the plant, your reply to that effect will be sufficient.
 
This request is covered by Office of Management and Budget Clearance Number 3150-0111 which expires September  
30, 1989. Comments on burden and duplication 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 not subject to fees under the provision of 10CFR170.Sincerely,_ _ R 4 2mFRflid p k Harold enton, irector__ _ _Office of Nuclear Reactor Regulation F"'LIST OF RECENTLY ISSUED GENERI& -ETTERS Generic I Letter No.Date of Subject Issuance Issued To GL 87-05 REQUEST FOR ADDITIONAL
INFORMATION-ASSESSMENT  
OF LICENSEE MEASURES TO MITIGATE AND/OR IDENTIFY POTENTIAL DEGRADATION
MK1 03/12/87 LICENSEES
OF OR S, APPLICANTS  
FOR DL'S, AND HOLDERS OF CP'S FOR BWR MARK I CONTAINMENTS
GL 87-04 GL 87-03 GL 87-02 TEMPORARY
EXEMPTION  
FROM PROVISIONS
OF THE FBI CRIMINAL HISTORY RULE FOR TEMPORARY WORKERS VERIFICATION
OF SEISMIC ADEQUACY OF MECHANICAL  
AND ELECTRICAL
EQUIPTMENT  
IN OPERATING
REACTORS, USI A-46 VERIFICATION
OF SEISMIC ADEQUACY OF MECHANICAL  
AND ELECTRICAL
EQUIPMENT  
IN OPERATING
REACTORS (USI A-46)03/06/87 02/26/87 02/19/67 ALL POWER REACTOR LICENCES ALL LICENSEES NOT SUBJECT TO USI A-46 REQUIREMENTS
ALL HOLDERS OF OPERATING LICENSES NOT REVIEWED TO CURRENT LICENSING
--CRITERIA ON SEISMIC QUALIFICATION
OF EQUIPMENT GL 87-01 PUBLIC AVAILABILITY  
OF THE NRC 01/08/87 OPERATOR LICENSING  
EXAMINATION
QUESTION BANK ALL POWER REACTOR LICENSEES
AND APPLICANTS
FOR AN OPERATING LICENSE GL 86-17 AVAILABILITY
OF NUREG-1169,"TECHNICAL  
FINDINGS RELATED TO GENERIC ISSUE C-8 BWR MSIC LEAKAGE AND LEAKAGE CONTROL SYSTEM 10/17/86 ALL LICENSEES OF BOILING WATER REACTORS GL 86-16 WESTINGHOUSE  
ECCS EVALUATION
MODELS 10/22/86 ALL PRESSURIZED
WATER REACTOR APPLICANTS
AND LICENSEES GL 86-15 INFORMATION
RELATING TO COMPLIANCE
WITH 10 CFR 50.49,`EQ OF ELECTRICAL  
EQUIPMENT IMPORTANT
TO SAFETY" 09/22/86 ALL LICENSEES AND HOLDERS OF AN APPLICATION
FOR AN OPERATING LICENSE}}


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Revision as of 12:31, 31 August 2018

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, Washington Public Power Supply System, 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)
v • d • e


I UNITED STATES NUCLEAR REGULATORY

COMMISSION

WASHINGTON.

0. C. 20555.MAR 13 3987 TO: All Holders of Operating Licenses Gentlemen:.

SUBJECT: PERIODIC VERIFICATION

OF LEAK TIGHTAINTEGRITY

OF PRESSURE ISOLATION VALVES (GENERIC LETTER 87-06'Pursuant to 10 CPR 50.54(f), NRC is seeking to verify the methods, if any, by which each opetatng reactor licensee is assuring.the leak-tigh.t integrity of'all pressure isolation valves as independent barriers against abnormal leakage, rapidly propagating.,failure, and gross rupture~of the reactor coolant pressure boundary.Pressure isolation valves (PIVs) are defined for each interface as any two valves in series within the reactor coolant pressure boundary which separate the high pressure reactor coolant system (RCS) from an attached low pressure system. These valves are normally closed during power operation.

The reactor coolant pressure boundary (RCPB) is.defined in 10 CFR 50.2 and generally includes 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 in accordance 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 an extremely low probability of abnormal leakage, of rapidly propagating failure and of gross rupture." GDC 30 requires that "The reactor coolant pressure boundary shall be designed, fabricated, erected, and tested to the highest quality standards practical

..." GDC 32 states that Components which are part of the reactor coolant pressure boundary shall be designed to permit (1)periodic inspection and testing of important areas and features to assess their structural and leak tight integrity

..." Further, as outlined in Appendix B to 10 CFR 50, each licensee's quality assurance program must include planned and systematic actions which will provide adequate confidence that these components will perform satisfactorily in service.All plants licensed since 1979 have all PIVs listed in the Technical Specifications along with testing intervals, acceptance criteria and limiting conditions for operation.

Certain older plants were required to periodically leak test, on an individual basis, only those PIVs which were listed in an order dated April 20, 1981 (Event V Order). That order was sent to 32 operating PWR's and 2 operating BWR's. Other older plants have had no specific requirements imposed to individually leak test any of their PIVs.A number of events have occurred in LWRs involving leakage past pressure isolation valves, failures of the valves, inadvertent actuation of the valves, or mispositioning of the valves. NRC is therefore seeking assurances that the RCPB is being protected.

1> ~0150 0O00? 11

-2-Accordingly, you are requested to submit a list of all pressure isolation valves in your plant. For each valve, describe the periodic tests or other measures performed to assure the integrity of the valve as an independent barrier at the RCPB along with the acceptance criteria for leakage, if any, operational limits, if any, and frequency of test performance.

This information is required to be submitted within 90 days of this letter. If current plant Technical Specifications require leak rate testing of all of the PIYs in the plant, your reply to that effect will be sufficient.

This request is covered by Office of Management and Budget Clearance Number 3150-0111 which expires September

30, 1989. Comments on burden and duplication 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 not subject to fees under the provision of 10CFR170.Sincerely,_ _ R 4 2mFRflid p k Harold enton, irector__ _ _Office of Nuclear Reactor Regulation F"'LIST OF RECENTLY ISSUED GENERI& -ETTERS Generic I Letter No.Date of Subject Issuance Issued To GL 87-05 REQUEST FOR ADDITIONAL

INFORMATION-ASSESSMENT

OF LICENSEE MEASURES TO MITIGATE AND/OR IDENTIFY POTENTIAL DEGRADATION

MK1 03/12/87 LICENSEES

OF OR S, APPLICANTS

FOR DL'S, AND HOLDERS OF CP'S FOR BWR MARK I CONTAINMENTS

GL 87-04 GL 87-03 GL 87-02 TEMPORARY

EXEMPTION

FROM PROVISIONS

OF THE FBI CRIMINAL HISTORY RULE FOR TEMPORARY WORKERS VERIFICATION

OF SEISMIC ADEQUACY OF MECHANICAL

AND ELECTRICAL

EQUIPTMENT

IN OPERATING

REACTORS, USI A-46 VERIFICATION

OF SEISMIC ADEQUACY OF MECHANICAL

AND ELECTRICAL

EQUIPMENT

IN OPERATING

REACTORS (USI A-46)03/06/87 02/26/87 02/19/67 ALL POWER REACTOR LICENCES ALL LICENSEES NOT SUBJECT TO USI A-46 REQUIREMENTS

ALL HOLDERS OF OPERATING LICENSES NOT REVIEWED TO CURRENT LICENSING

--CRITERIA ON SEISMIC QUALIFICATION

OF EQUIPMENT GL 87-01 PUBLIC AVAILABILITY

OF THE NRC 01/08/87 OPERATOR LICENSING

EXAMINATION

QUESTION BANK ALL POWER REACTOR LICENSEES

AND APPLICANTS

FOR AN OPERATING LICENSE GL 86-17 AVAILABILITY

OF NUREG-1169,"TECHNICAL

FINDINGS RELATED TO GENERIC ISSUE C-8 BWR MSIC LEAKAGE AND LEAKAGE CONTROL SYSTEM 10/17/86 ALL LICENSEES OF BOILING WATER REACTORS GL 86-16 WESTINGHOUSE

ECCS EVALUATION

MODELS 10/22/86 ALL PRESSURIZED

WATER REACTOR APPLICANTS

AND LICENSEES GL 86-15 INFORMATION

RELATING TO COMPLIANCE

WITH 10 CFR 50.49,`EQ OF ELECTRICAL

EQUIPMENT IMPORTANT

TO SAFETY" 09/22/86 ALL LICENSEES AND HOLDERS OF AN APPLICATION

FOR AN OPERATING LICENSE

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