NRC Generic Letter 1987-06: Difference between revisions

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{{#Wiki_filter:I UNITED STATES NUCLEAR REGULATORY  
{{#Wiki_filter:I
COMMISSION
                                  UNITED STATES
WASHINGTON.
                      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.


0. C. 20555.MAR 13 3987 TO: All Holders of Operating Licenses Gentlemen:.
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.
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  
Periodic-tests or verifications'Of the leak tight integrity of all pressure               _-
..." 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  
  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)
..." 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.
  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.


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.
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.


1> ~0150 0O00? 11
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.
-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.
1>  ~0150              0O00?11


This request is covered by Office of Management and Budget Clearance Number 3150-0111 which expires September  
-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.
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  
This request is covered by Office of Management and Budget Clearance Number
OF LICENSEE MEASURES TO MITIGATE AND/OR IDENTIFY POTENTIAL DEGRADATION
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.
MK1 03/12/87 LICENSEES
 
OF OR S, APPLICANTS
Our review of your submittal of information in response to this letter is not subject to fees under the provision of 10CFR170.
FOR DL'S, AND HOLDERS OF CP'S FOR BWR MARK I CONTAINMENTS
 
GL 87-04 GL 87-03 GL 87-02 TEMPORARY
Sincerely, R4 2mFRflid             p k
EXEMPTION
            _    _
FROM PROVISIONS  
                                    Harold     enton, irector
OF THE FBI CRIMINAL HISTORY RULE FOR TEMPORARY WORKERS VERIFICATION  
                              __ _ _Office of Nuclear Reactor Regulation
OF SEISMIC ADEQUACY OF MECHANICAL  
 
AND ELECTRICAL  
F"'
EQUIPTMENT  
                  LIST OF RECENTLY ISSUED GENERI& -ETTERS
IN OPERATING  
Generic I                                   Date of Letter No. Subject                         Issuance     Issued To GL   87-05 REQUEST FOR ADDITIONAL         03/12/87      LICENSEES OF
REACTORS, USI A-46 VERIFICATION  
            INFORMATION-ASSESSMENT OF                    OR S,
OF SEISMIC ADEQUACY OF MECHANICAL  
            LICENSEE MEASURES TO MITIGATE                 APPLICANTS FOR
AND ELECTRICAL  
            AND/OR IDENTIFY POTENTIAL                     DL'S, AND
EQUIPMENT  
            DEGRADATION MK1                              HOLDERS OF
IN OPERATING  
                                                          CP'S FOR BWR
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
                                                          MARK I
ALL HOLDERS OF OPERATING LICENSES NOT REVIEWED TO CURRENT LICENSING  
                                                          CONTAINMENTS
--CRITERIA ON SEISMIC QUALIFICATION
GL   87-04 TEMPORARY EXEMPTION FROM        03/06/87     ALL POWER
OF EQUIPMENT GL 87-01 PUBLIC AVAILABILITY  
            PROVISIONS OF THE FBI CRIMINAL               REACTOR
OF THE NRC 01/08/87 OPERATOR LICENSING  
            HISTORY RULE FOR TEMPORARY                   LICENCES
EXAMINATION
            WORKERS
QUESTION BANK ALL POWER REACTOR LICENSEES  
GL    87-03 VERIFICATION OF SEISMIC         02/26/87      ALL LICENSEES
AND APPLICANTS  
            ADEQUACY OF MECHANICAL AND                    NOT SUBJECT TO
FOR AN OPERATING LICENSE GL 86-17 AVAILABILITY  
            ELECTRICAL EQUIPTMENT IN                     USI A-46 OPERATING REACTORS, USI A-46                 REQUIREMENTS
OF NUREG-1169,"TECHNICAL  
GL    87-02 VERIFICATION OF SEISMIC         02/19/67      ALL HOLDERS OF
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  
            ADEQUACY OF MECHANICAL AND                    OPERATING
ECCS EVALUATION
            ELECTRICAL EQUIPMENT IN                      LICENSES NOT
MODELS 10/22/86 ALL PRESSURIZED
            OPERATING REACTORS (USI A-46)                 REVIEWED TO
WATER REACTOR APPLICANTS  
                                                          CURRENT
AND LICENSEES GL 86-15 INFORMATION  
                                                          LICENSING   --
RELATING TO COMPLIANCE  
                                                          CRITERIA ON
WITH 10 CFR 50.49,`EQ OF ELECTRICAL  
                                                          SEISMIC
EQUIPMENT IMPORTANT  
                                                          QUALIFICATION
TO SAFETY" 09/22/86 ALL LICENSEES AND HOLDERS OF AN APPLICATION
                                                          OF EQUIPMENT
FOR AN OPERATING LICENSE}}
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}}


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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

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