NRC Generic Letter 1987-06: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
 
(3 intermediate revisions by the same user not shown)
Line 3: Line 3:
| issue date = 03/13/1987
| issue date = 03/13/1987
| title = NRC Generic Letter 1987-006: Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves
| title = NRC Generic Letter 1987-006: Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves
| author name = Denton H R
| author name = Denton H
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
Line 14: Line 14:
| page count = 3
| page count = 3
}}
}}
{{#Wiki_filter:IUNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON. 0. C. 20555.MAR 13 3987TO: All Holders of Operating LicensesGentlemen:.
{{#Wiki_filter: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,integrity    if any, by which each opetatng reactor    licensee  is  assuring.the    leak-tigh.t              of'
  all pressure isolation valves  as  independent      barriers  against  abnormal leakage, rapidly propagating.,failure, and gross rupture~of the reactor coolant pressure boundary.


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
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.
-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}}
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, R4 2mFRflid              p k
            _     _
                                    Harold     enton, irector
                              __ _ _Office of Nuclear Reactor Regulation
 
F"'
                  LIST OF RECENTLY ISSUED GENERI& -ETTERS
Generic I                                  Date of Letter No. Subject                        Issuance      Issued To GL    87-05 REQUEST FOR ADDITIONAL          03/12/87      LICENSEES OF
            INFORMATION-ASSESSMENT OF                    OR S,
            LICENSEE MEASURES TO MITIGATE                APPLICANTS FOR
            AND/OR IDENTIFY POTENTIAL                      DL'S, AND
            DEGRADATION MK1                              HOLDERS OF
                                                          CP'S FOR BWR
                                                          MARK I
                                                          CONTAINMENTS
GL    87-04 TEMPORARY EXEMPTION FROM        03/06/87     ALL POWER
            PROVISIONS OF THE FBI CRIMINAL                REACTOR
            HISTORY RULE FOR TEMPORARY                    LICENCES
            WORKERS
GL    87-03 VERIFICATION OF SEISMIC        02/26/87      ALL LICENSEES
            ADEQUACY OF MECHANICAL AND                    NOT SUBJECT TO
            ELECTRICAL EQUIPTMENT IN                      USI A-46 OPERATING REACTORS, USI A-46                  REQUIREMENTS
GL    87-02 VERIFICATION OF SEISMIC        02/19/67      ALL HOLDERS OF
            ADEQUACY OF MECHANICAL AND                    OPERATING
            ELECTRICAL EQUIPMENT IN                      LICENSES NOT
            OPERATING REACTORS (USI A-46)                 REVIEWED TO
                                                          CURRENT
                                                          LICENSING  --
                                                          CRITERIA ON
                                                          SEISMIC
                                                          QUALIFICATION
                                                          OF EQUIPMENT
GL    87-01 PUBLIC AVAILABILITY OF THE NRC 01/08/87      ALL POWER
            OPERATOR LICENSING EXAMINATION                REACTOR
            QUESTION BANK                                LICENSEES AND
                                                          APPLICANTS FOR
                                                          AN OPERATING
                                                          LICENSE
GL    86-17 AVAILABILITY OF NUREG-1169,     10/17/86      ALL LICENSEES
            "TECHNICAL FINDINGS RELATED TO                OF BOILING
            GENERIC ISSUE C-8                            WATER REACTORS
            BWR MSIC LEAKAGE AND LEAKAGE
            CONTROL SYSTEM
GL  86-16 WESTINGHOUSE ECCS EVALUATION    10/22/86      ALL
            MODELS                                        PRESSURIZED
                                                          WATER REACTOR
                                                          APPLICANTS AND
                                                          LICENSEES
GL  86-15  INFORMATION RELATING TO        09/22/86      ALL LICENSEES
            COMPLIANCE WITH 10 CFR 50.49,                 AND HOLDERS OF
            `EQ OF ELECTRICAL EQUIPMENT                  AN APPLICATION
            IMPORTANT TO SAFETY"                         FOR AN
                                                          OPERATING
                                                          LICENSE}}


{{GL-Nav}}
{{GL-Nav}}

Latest revision as of 02:47, 24 November 2019

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: Harold Denton
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,integrity if any, by which each opetatng reactor licensee is assuring.the leak-tigh.t 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, R4 2mFRflid p k

_ _

Harold enton, irector

__ _ _Office of Nuclear Reactor Regulation

F"'

LIST OF RECENTLY ISSUED GENERI& -ETTERS

Generic I Date of Letter No. Subject Issuance Issued To GL 87-05 REQUEST FOR ADDITIONAL 03/12/87 LICENSEES OF

INFORMATION-ASSESSMENT OF OR S,

LICENSEE MEASURES TO MITIGATE APPLICANTS FOR

AND/OR IDENTIFY POTENTIAL DL'S, AND

DEGRADATION MK1 HOLDERS OF

CP'S FOR BWR

MARK I

CONTAINMENTS

GL 87-04 TEMPORARY EXEMPTION FROM 03/06/87 ALL POWER

PROVISIONS OF THE FBI CRIMINAL REACTOR

HISTORY RULE FOR TEMPORARY LICENCES

WORKERS

GL 87-03 VERIFICATION OF SEISMIC 02/26/87 ALL LICENSEES

ADEQUACY OF MECHANICAL AND NOT SUBJECT TO

ELECTRICAL EQUIPTMENT IN USI A-46 OPERATING REACTORS, USI A-46 REQUIREMENTS

GL 87-02 VERIFICATION OF SEISMIC 02/19/67 ALL HOLDERS OF

ADEQUACY OF MECHANICAL AND OPERATING

ELECTRICAL EQUIPMENT IN LICENSES NOT

OPERATING REACTORS (USI A-46) REVIEWED TO

CURRENT

LICENSING --

CRITERIA ON

SEISMIC

QUALIFICATION

OF EQUIPMENT

GL 87-01 PUBLIC AVAILABILITY OF THE NRC 01/08/87 ALL POWER

OPERATOR LICENSING EXAMINATION REACTOR

QUESTION BANK LICENSEES AND

APPLICANTS FOR

AN OPERATING

LICENSE

GL 86-17 AVAILABILITY OF NUREG-1169, 10/17/86 ALL LICENSEES

"TECHNICAL FINDINGS RELATED TO OF BOILING

GENERIC ISSUE C-8 WATER REACTORS

BWR MSIC LEAKAGE AND LEAKAGE

CONTROL SYSTEM

GL 86-16 WESTINGHOUSE ECCS EVALUATION 10/22/86 ALL

MODELS PRESSURIZED

WATER REACTOR

APPLICANTS AND

LICENSEES

GL 86-15 INFORMATION RELATING TO 09/22/86 ALL LICENSEES

COMPLIANCE WITH 10 CFR 50.49, AND HOLDERS OF

`EQ OF ELECTRICAL EQUIPMENT AN APPLICATION

IMPORTANT TO SAFETY" FOR AN

OPERATING

LICENSE

Template:GL-Nav

Retrieved from "https://kanterella.com/w/index.php?title=NRC_Generic_Letter_1987-06&oldid=2200676"