Information Notice 1994-30, Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station: Difference between revisions

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| issue date = 08/19/1994
| issue date = 08/19/1994
| title = Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station
| title = Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station
| author name = Grimes B K
| author name = Grimes B
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
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| page count = 9
| page count = 9
}}
}}
{{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555August 19, 1994NRC INFORMATION NOTICE 94-30, SUPPLEMENT 1: LEAKING SHUTDOWN COOLINGISOLATION VALVES ATCOOPER NUCLEAR STATION
{{#Wiki_filter:UNITED STATES
 
NUCLEAR REGULATORY COMMISSION
 
OFFICE OF NUCLEAR REACTOR REGULATION
 
WASHINGTON, D.C. 20555 August 19, 1994 NRC INFORMATION NOTICE 94-30, SUPPLEMENT 1:     LEAKING SHUTDOWN COOLING
 
ISOLATION VALVES AT
 
COOPER NUCLEAR STATION


==Addressees==
==Addressees==
All holders of operating licenses or construction permits for nuclear powerreactors.
All holders of operating licenses or construction permits for nuclear power
 
reactors.


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice (IN) supplement to clarify the type of valve discussed in the originalnotice and to alert recipients to the potential that local leak rate testingof primary containment isolation valves with pressure applied in the directionopposite of the accident direction may not be conservative. It is expectedthat recipients will review the information for applicability to theirfacilities and consider actions, as appropriate, to avoid similar problems.However, suggestions contained in this information notice are not NRCrequirements; therefore, no specific action or written response is required.BackgroundThe NRC issued IN 94-30, "Leaking Shutdown Cooling Isolation Valves at CooperNuclear Station," on April 12, 1994, to alert addressees to a precursor to anunisolable rupture of shutdown cooling piping with the potential for coredamage and release of radioactive material outside the containment. In thatevent, after receiving a high-pressure alarm for the suction piping in theresidual heat removal system, the licensee measured the leakage through theinboard isolation valve, established a bleedoff path into the pressuremaintenance system and continued operations. About 10 months later, thelicensee disassembled the inboard and outboard valves and found cracks in theseating surfaces of both valves.During the preparation of IN 94-30, the staff determined that a concern mayexist regarding the method used for testing of primary containment isolationvalves. This concern is described below. In addition, the NRC has receivedinformation from Anchor/Darling Valve Company that the description of thevalves in IN 94-30, "Anchor-Darling 20-inch nominal, double-disk, flex-wedge,gate valves," is incorrect. The correct description is, "a 20 inch, 900class, flex wedge gate valve," manufactured by the Anchor Valve Company beforethe merger that formed the Anchor/Darling Valve Company. In IN 94-30, the NRCstaff was concerned about the actions of the licensee after the valve leakagewas identified regardless of the valve type or manufacturer.Gs tAiJ4-:&ge q 3 0199408160070illpt- -( IN 94-30, Supplement 1August 19, 1994  
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
 
notice (IN) supplement to clarify the type of valve discussed in the original
 
notice and to alert recipients to the potential that local leak rate testing
 
of primary containment isolation valves with pressure applied in the direction
 
opposite of the accident direction may not be conservative. It is expected
 
that recipients will review the information for applicability to their
 
facilities and consider actions, as appropriate, to avoid similar problems.
 
However, suggestions contained in this information notice are not NRC
 
requirements; therefore, no specific action or written response is required.
 
Background
 
The NRC issued IN 94-30, "Leaking Shutdown Cooling Isolation Valves at Cooper
 
Nuclear Station," on April 12, 1994, to alert addressees to a precursor to an
 
unisolable rupture of shutdown cooling piping with the potential for core
 
damage and release of radioactive material outside the containment. In that
 
event, after receiving a high-pressure alarm for the suction piping in the
 
residual heat removal system, the licensee measured the leakage through the
 
inboard isolation valve, established a bleedoff path into the pressure
 
maintenance system and continued operations. About 10 months later, the
 
licensee disassembled the inboard and outboard valves and found cracks in the
 
seating surfaces of both valves.
 
During the preparation of IN 94-30, the staff determined that a concern may
 
exist regarding the method used for testing of primary containment isolation
 
valves. This concern is described below. In addition, the NRC has received
 
information from Anchor/Darling Valve Company that the description of the
 
valves in IN 94-30, "Anchor-Darling 20-inch nominal, double-disk, flex-wedge, gate valves," is incorrect. The correct description is, "a 20 inch, 900
class, flex wedge gate valve," manufactured by the Anchor Valve Company before
 
the merger that formed the Anchor/Darling Valve Company. In IN 94-30, the NRC
 
staff was concerned about the actions of the licensee after the valve leakage
 
was identified regardless of the valve type or manufacturer.
 
Gs               tAiJ4-:&ge     q 3019
9408160070
    illpt-                                                               -(f.
 
IN 94-30, Supplement 1 August 19, 1994  


==Description of Circumstances==
==Description of Circumstances==
On May 1, 1993, after evaluating the results of local leak rate testing forseveral inboard primary containment isolation valves, the licensee for theCooper Nuclear Station (Cooper) determined that the testing methodology usedfor Appendix J, Type C tests of certain flex-wedge gate valves could not berelied on to be equivalent to or more conservative than testing the valves inthe accident direction. The Type C tests for several such valves had beenperformed with the pressure applied in the direction opposite to the accidentdirection (reverse direction). The licensee began corrective actions andnotified the NRC in Licensee Event Report (LER) 93-019, dated June 1, 1993.In LER 93-019, the licensee reported that the testing of these valves in thereverse direction was based on an incorrect interpretation of information fromthe valve manufacturer. In response to a question from the licensee regardingthe acceptability of valve test methods, the manufacturer had indicated thattesting in the reverse direction would not be expected to affect test results,but an unqualified answer could not be provided. Results of recent tests bythe licensee of some of the primary containment isolation valves with pressureapplied in the accident direction, indicate that testing in the reversedirection may not be equivalent to or more conservative than testing in theaccident direction; therefore earlier test results may not be valid.LER 93-019 indicated that Cooper Nuclear station has 65 inboard primarycontainment valves of various types and from various manufacturers. Thelicensee found that 24 of those valves were of concern. Of the 24 valves,8 could be tested in the accident direction but, before the 1993 refuelingoutage, were not. The other 16 valves could not be tested in the accidentdirection nor had testing in the reverse direction been qualified to beequivalent or more conservative than testing in the accident direction. Formost of these valves, the licensee qualified testing in the reverse directionto be equivalent or more conservative or modified the testing configuration toallow testing the valve in the accident direction. For the remaining valves,the licensee requested exemptions from certain Appendix J requirements toallow leak .rate testing in the reverse' direction.Discussion'Appendix J to Title 10 of the Code of Federal Regulations Part 50 requires aprogram for leak testing the primary reactor containment and related systemsand components penetrating the primary containment pressure boundary.Section III.C.1 of Appendix J specifies that, for Type C tests of valves(local leak rate tests), the pressure shall be applied in the same directionas that when the valve would be required to perform its safety function,unless it can be determined that the results from the tests for a pressureapplied in a different direction will provide equivalent or more conservativeresults. This requirement is intended to ensure that test leak rates arerepresentative of leak rates that would be experienced under actual accidentconditions. As described above, the licensee for Cooper found that, for someof the primary containment isolation valves, testing in the reverse directionwas not equivalent to or more conservative than testing in the accidentdirectio IN 94-30, Supplement 1August 19, 1994 Related Generic Communications* NRC IN 86-16, "Failures to Identify Containment Leakage Due toInadequate Local Leak Rate Testing," March 11, 1986.* NRC IN 92-20, Inadequate Local Leak Rate Testing,' March 3, 1992.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian s, Director QDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact: Jim Pulsipher, NRR(301) 504-2811
On May 1, 1993, after evaluating the results of local leak rate testing for
 
several inboard primary containment isolation valves, the licensee for the
 
Cooper Nuclear Station (Cooper) determined that the testing methodology used
 
for Appendix J, Type C tests of certain flex-wedge gate valves could not be
 
relied on to be equivalent to or more conservative than testing the valves in
 
the accident direction. The Type C tests for several such valves had been
 
performed with the pressure applied in the direction opposite to the accident
 
direction (reverse direction). The licensee began corrective actions and
 
notified the NRC in Licensee Event Report (LER) 93-019, dated June 1, 1993.
 
In LER 93-019, the licensee reported that the testing of these valves in the
 
reverse direction was based on an incorrect interpretation of information from
 
the valve manufacturer. In response to a question from the licensee regarding
 
the acceptability of valve test methods, the manufacturer had indicated that
 
testing in the reverse direction would not be expected to affect test results, but an unqualified answer could not be provided. Results of recent tests by
 
the licensee of some of the primary containment isolation valves with pressure
 
applied in the accident direction, indicate that testing in the reverse
 
direction may not be equivalent to or more conservative than testing in the
 
accident direction; therefore earlier test results may not be valid.
 
LER 93-019 indicated that Cooper Nuclear station has 65 inboard primary
 
containment valves of various types and from various manufacturers. The
 
licensee found that 24 of those valves were of concern. Of the 24 valves,
8 could be tested in the accident direction but, before the 1993 refueling
 
outage, were not. The other 16 valves could not be tested in the accident
 
direction nor had testing in the reverse direction been qualified to be
 
equivalent or more conservative than testing in the accident direction. For
 
most of these valves, the licensee qualified testing in the reverse direction
 
to be equivalent or more conservative or modified the testing configuration to
 
allow testing the valve in the accident direction. For the remaining valves, the licensee requested exemptions from certain Appendix J requirements to
 
allow leak .rate testing in the reverse' direction.
 
Discussion'
Appendix J to Title 10 of the Code of Federal Regulations Part 50 requires a
 
program for leak testing the primary reactor containment and related systems
 
and components penetrating the primary containment pressure boundary.
 
Section III.C.1 of Appendix J specifies that, for Type C tests of valves
 
(local leak rate tests), the pressure shall be applied in the same direction
 
as that when the valve would be required to perform its safety function, unless it can be determined that the results from the tests for a pressure
 
applied in a different direction will provide equivalent or more conservative
 
results. This requirement is intended to ensure that test leak rates are
 
representative of leak rates that would be experienced under actual accident
 
conditions. As described above, the licensee for Cooper found that, for some
 
of the primary containment isolation valves, testing in the reverse direction
 
was not equivalent to or more conservative than testing in the accident
 
direction.
 
IN 94-30, Supplement 1 August 19, 1994 Related Generic Communications
 
*   NRC IN 86-16, "Failures to Identify Containment Leakage Due to
 
Inadequate Local Leak Rate Testing," March 11, 1986.
 
*   NRC IN 92-20,   Inadequate Local Leak Rate Testing,' March 3, 1992.
 
This information notice requires no specific action or written response. If
 
you have any questions about the information in this notice, please contact
 
the technical contact listed below or the appropriate Office of Nuclear
 
Reactor Regulation (NRR) project manager.
 
Brian         s, Director Q
 
Division of Operating Reactor Support
 
Office of Nuclear Reactor Regulation
 
Technical contact:  Jim Pulsipher, NRR
 
(301) 504-2811 Attachment:
 
===List of Recently Issued NRC Information Notices===
        s&C 3Lo
 
Attachment
 
IN 94-30, Supp. 1 August 19, 1994 LIST OF RECENTLY ISSUED
 
NRC INFORMATION NOTICES
 
Information                                  Date of
 
Notice No.            Subject                Issuance  Issued to
 
94-59          Accelerated Dealloying of      08/17/94  All holders of OLs or CPs
 
Cast Aluminum-Bronze                      for nuclear power reactors.
 
Valves Caused by Micro- biologically Induced
 
Corrosion
 
94-58          Reactor Coolant Pump          08/16/94    All holders of OLs or CPs
 
Lube Oil Fire                            for pressurized water
 
reactors.
 
94-57          Debris in Containment        08/12/94    All holders of OLs or CPs
 
and the Residual Heat                    for nuclear power reactors.
 
Removal System
 
94-56          Inaccuracy of Safety Valve    08/11/94    All holders of OLs or CPs
 
Set Pressure Determinations              for nuclear power reactors.
 
Using Assist Devices
 
94-55          Problems with Copes-          08/04/94    All holders of OLs or CPs
 
Vulcan Pressurizer                        for nuclear power reactors.
 
Power-Operated Relief
 
Valves
 
91-79,        Deficiencies Found in        08/04/94    All holders of OLs or CPs
 
Supp. 1        Thermo-Lag Fire Barrier                  for nuclear power reactors.
 
Installation
 
94-54          Failures of General          08/01/94    All holders of OLs or CPs
 
Electric Magne-Blast                      for nuclear power reactors.
 
Circuit Breakers to
 
Latch Closed
 
91-45,        Possible Malfunction of      07/29/94    All holders of OLs or CPs
 
Supp. 1        Westinghouse ARD, BFD,                    for nuclear power reactors.
 
and NBFD Relays, and
 
A200 DC and DPC 250
              Magnetic Contactors
 
94-42,        Cracking in the Lower          07/19/94  All holders of OLs or CPs
 
Supp. 1        Region of the Core Shroud                for boiling water reactors
 
in Boiling-Water Reactors                  (BWRs).
 
OL = Operating License
 
CP = Construction Permit
 
'-30, Supplement 1 V IN
 
August 19, 1994 This information notice requires no specific action or written response. If
 
you have any questions about the information in this notice, please contact
 
the technical contact listed below or the appropriate Office of Nuclear
 
Reactor Regulation (NRR) project manager.
 
orig /s/'d by CIGrimes/for
 
Brian K. Grimes, Director
 
Division of Operating Reactor Support
 
Office of Nuclear Reactor Regulation
 
Technical contact:       Jim Pulsipher, NRR
 
(301) 504-2811 Attachment:
 
===List of Recently Issued NRC Information Notices===
  SPraa Proevintic rnnmirronre
 
OFFICE      SCSB:DSSA:NRR    SCSB:DSSA:NRR  C/SCSB:DSSA:NRR    D/DSSA:NRR
 
NAME      I JPulsifer*        RLobel*        RBarrett*          GHolahan*
  DATE        07/17/94        107/19/94        08/03/94          08/04/94 OFFICE I TECH ED              OGCB:DORS:NRR  AC/OGCB:DORS:NRR  D/DORS:JNI2,a
 
NAME        RSanders*        JBirmingham*    ELDoolittle*      BKGrimes
 
DATE        6/14/94        1 08/03/94        08/04/94        ,08/ t194 UN .-ILALUUU      rptt      A'4u^t- Iit
 
OFFIIAL    UULUMMNI  NAMEL:  Y4-30SH .AN
 
I" 4-30, Supplement 1 August XX, 1994 This information notice requires no specific action or written response. If
 
you have any questions about the information in this notice, please contact
 
the technical contact listed below or the appropriate Office of Nuclear
 
Reactor Regulation (NRR) project manager.
 
Brian K. Grimes, Director
 
Division of Operating Reactor Support
 
Office of Nuclear Reactor Regulation
 
Technical contact:    Jim Pulsipher, NRR
 
(301) 504-2811 Attachment:
 
===List of Recently Issued NRC Information Notices===
* See Previnus Concurrence
 
OFFICE  SCSB:DSSA:NRR    SCSB:DSSA:NRR                  C/SCSB:DSSA:NRR    D/DSSA:NRR
 
NAME    JPulsifer*      RLobel*                        RBarrett*          GHolahan*
    DATE    07/17/94        07/19/94                      , 08/03/94          08/04/94 OFFICE  TECH ED          OGCB:DORS:NRR                  AC/OGCB:DORS:NRR  D/DORS:NRR
 
NAME    RSanders*        JBirmingham*                    ELDoolittle*      BKGrimes
 
DATE
 
v_ -ace---
            06/14/94
            - -..-
                            08/03/94
                              .^ ... _ . -. n...
 
eae      . ..  -
                                                          108/04/94            08/  /94 A
 
OFFICIAL  OUCUMNI  NArt:  U:\1N Y4JUb.LUb
 
IN"4-30, Supplement 1 August XX, 1994 This information notice requires no specific action or written response. If
 
you have any questions about the information in this notice, please contact
 
the technical contact listed below or the appropriate Office of Nuclear
 
Reactor Regulation (NRR) project manager.
 
Brian K. Grimes, Director
 
Division of Operating Reactor Support
 
Office of Nuclear Reactor Regulation
 
Technical contact:    Jim Pulsipher, NRR
 
(301) 504-2811 Attachment:
 
===List of Recently Issued NRC Information Notices===
* See Previnut Cnncurrence                                          A
 
OFFICE  SCSB:DSSA:NRR    SCSB:DSSA:NRR  C/SCSB:DSSA:NRR              RR
 
NAME    JPulsifer*        RLobel*        RBarrett*          GHolahan
 
DATE    07/17/94          07/19/94        08/03/94            08/e/94 OFFICE  TECH ED          OGCB:DORS:NRR    AC  lBODORS:NRR    D/DORS:NRR
 
NAME    RSanders*        JBirmingham*    E6    ttle        BKGrimes
 
DATE    06/14/94          08/03/94
                                      .J 08/4 /94              08/  /94 OICA DO.          ..
 
MN._ NAE      G.. . 4.
 
OFFICIAL DOCUMENT NAME:    6:\IN 9430S.JLB
 
IN44-30, Supplement 1 August XX, 1994 This information notice requires no specific action or written response. If
 
you have any questions about the information in this notice, please contact
 
the technical contact listed below or the appropriate Office of Nuclear
 
Reactor Regulation (NRR) project manager.
 
Brian K. Grimes, Director
 
Division of Operating Reactor Support
 
Office of Nuclear Reactor Regulation
 
Technical contact:                Jim Pulsipher, NRR
 
(301) 504-2811 Attachment:
 
===List of Recently Issued NRC Information Notices===
* See Previous Concurrence                                            A
 
OFFICE lSCSB:DSSA:NRR              SCSB:DSSA:NRR        C/SCS      A:NRR    AD/DSSA:NRR
 
JPulsifer*              RLobel*            l  aWVrgllo
 
NAME
 
lDATE      07/17/94                07/19/94          !08/;7/94            08/ /94 OFFICE    TECH ED                OGCB:DORS:NRR        AC/OGCB:DORS:NRR    D/DORS:NRR
 
NAME      RSanders*              JBirmingham          ELDoolittle        BKGrimes
 
DATE      06/14/94                08/ 3 /94    .      08/  /94          08/  /94 a.-.-.  a. a. anna ... r&*, a.r.      **a A .i  1A
 
1 Do
 
UMLI16AL UUUUMtN1I                `t:  IN Y4JV3 .UL0
 
IN 94-30, Supplement 1 June XX, 1994 This information notice requires no specific action or written response. If
 
you have any questions about the information in this notice, please contact
 
the technical contact listed below or the appropriate Office of Nuclear
 
Reactor Regulation (NRR) project manager.
 
Brian K. Grimes, Director
 
Division of Operating Reactor Support
 
Office of Nuclear Reactor Regulation
 
Technical contact:      Jim Pulsipher, NRR
 
(301) 504-2811 Attachment:


===Attachment:===
===List of Recently Issued NRC Information Notices===
List of Recently Issued NRC Information Noticess&C 3 Lo AttachmentIN 94-30, Supp. 1August 19, 1994 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to94-5994-5894-5794-5694-55Accelerated Dealloying ofCast Aluminum-BronzeValves Caused by Micro-biologically InducedCorrosionReactor Coolant PumpLube Oil FireDebris in Containmentand the Residual HeatRemoval SystemInaccuracy of Safety ValveSet Pressure DeterminationsUsing Assist DevicesProblems with Copes-Vulcan PressurizerPower-Operated ReliefValvesDeficiencies Found inThermo-Lag Fire BarrierInstallationFailures of GeneralElectric Magne-BlastCircuit Breakers toLatch ClosedPossible Malfunction ofWestinghouse ARD, BFD,and NBFD Relays, andA200 DC and DPC 250Magnetic Contactors08/17/9408/16/9408/12/9408/11/9408/04/9408/04/9408/01/9407/29/94All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor pressurized waterreactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.91-79,Supp. 194-5491-45,Supp. 194-42,Supp. 1Cracking in the LowerRegion of the Core Shroudin Boiling-Water Reactors07/19/94All holdersfor boiling(BWRs).of OLs or CPswater reactorsOL = Operating LicenseCP = Construction Permit V IN '-30, Supplement 1August 19, 1994 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.orig /s/'d by CIGrimes/forBrian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact: Jim Pulsipher, NRR(301) 504-2811
* See Previous Concurrence        1i'
  OFFICE  S      5          SCSB:DSSA:NRR   C/SCSB:DSSA:NRR  D/DSSA:NRR


===Attachment:===
NAME    JPulsige          ZtG              RBarrett         MVirgilio
List of Recently Issued NRC Information NoticesSPraa Proevintic rnnmirronreOFFICE SCSB:DSSA:NRR SCSB:DSSA:NRR C/SCSB:DSSA:NRR D/DSSA:NRRNAME I JPulsifer* RLobel* RBarrett* GHolahan*DATE 07/17/94 1 07/19/94 08/03/94 08/04/94OFFICE I TECH ED OGCB:DORS:NRR AC/OGCB:DORS:NRR D/DORS:JNI2,aNAME RSanders* JBirmingham* ELDoolittle* BKGrimesDATE 6/14/94 1 08/03/94 08/04/94 ,08/ t194UN .-ILALUUU A'4 rptt ^t- u IitOFFIIAL UULUMMNI NAMEL:Y4-30SH .AN I " 4-30, Supplement 1August XX, 1994 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact:Jim Pulsipher, NRR(301) 504-2811


===Attachment:===
lDATE    _         i
List of Recently Issued NRC Information Notices* See Previnus ConcurrenceOFFICE SCSB:DSSA:NRR SCSB:DSSA:NRR C/SCSB:DSSA:NRR D/DSSA:NRRNAME JPulsifer* RLobel* RBarrett* GHolahan*DATE 07/17/94 07/19/94 , 08/03/94 08/04/94OFFICE TECH ED OGCB:DORS:NRR AC/OGCB:DORS:NRR D/DORS:NRRNAME RSanders* JBirmingham* ELDoolittle* BKGrimesDATE 06/14/94 08/03/94 1 08/04/94 08/ /94v_ -ace--- --..- .^ ... _ eae .-.n ... ... -AOFFICIAL OUCUMNI NArt:U:\1N Y4JUb.LUb IN"4-30, Supplement 1August XX, 1994 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact:Jim Pulsipher, NRR(301) 504-2811


===Attachment:===
_06/17/94         /94/06/         /94         06/ /94 OFFICE  TECH ED       9  OGCB:DORS:NRR     C/OGCB:DORS:NRR   D/DORS:NRR
List of Recently Issued NRC Information NoticesA* See Previnut CnncurrenceOFFICE SCSB:DSSA:NRR SCSB:DSSA:NRR C/SCSB:DSSA:NRR RRNAME JPulsifer* RLobel* RBarrett* GHolahanDATE 07/17/94 07/19/94 08/03/94 08/e/94OFFICE TECH ED OGCB:DORS:NRR AC lBO DORS:NRR D/DORS:NRRNAME RSanders* JBirmingham* E 6 ttle BKGrimesDATE 06/14/94 08/03/94 08/4 /94 08/ /94OICA DO. MN NAE G.. ._ ..4. ..JOFFICIAL DOCUMENT NAME:6:\IN 9430S.JLB IN 44-30, Supplement 1August XX, 1994 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact:Jim Pulsipher, NRR(301) 504-2811


===Attachment:===
NAME    RSander          JBirmingham       RDennig          BKGrimes
List of Recently Issued NRC Information Notices* See Previous ConcurrenceAOFFICE lSCSB:DSSA:NRR SCSB:DSSA:NRR C/SCS A:NRR AD/DSSA:NRRNAME JPulsifer* RLobel* l aWVrgllolDATE 07/17/94 07/19/94 !08/;7/94 08/ /94OFFICE TECH ED OGCB:DORS:NRR AC/OGCB:DORS:NRR D/DORS:NRRNAME RSanders* JBirmingham ELDoolittle BKGrimesDATE 06/14/94 08/ 3 /94 .08/ /94 08/ /94a.-.-. a. a. anna ...r&*, a.r. **a A 1A .i 1 DoUMLI16AL UUUUMtN1 I `t:IN Y4JV3 .UL0 IN 94-30, Supplement 1June XX, 1994 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact:Jim Pulsipher, NRR(301) 504-2811


===Attachment:===
DATE   06/14/94         I06/   /94         06/ /94         06/ /94 OFF116lAL VULUMtNI NAML      iNr3  JU1.dJLU}}
List of Recently Issued NRC Information Notices* See Previous Concurrence 1i'OFFICE S 5 SCSB:DSSA:NRR C/SCSB:DSSA:NRR D/DSSA:NRRNAME JPulsige ZtG RBarrett MVirgiliol DATE _ _06/17/94 i /94/06/ /94 06/ /94OFFICE TECH ED 9 OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS:NRRNAME RSander JBirmingham RDennig BKGrimesDATE 06/14/94 I06/ /94 06/ /94 06/ /94OFF116lAL VULUMtNI NAMLiNr3 JU1.dJLU}}


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{{Information notice-Nav}}

Latest revision as of 04:28, 24 November 2019

Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station
ML031060492
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant  Entergy icon.png
Issue date: 08/19/1994
From: Grimes B
Office of Nuclear Reactor Regulation
To:
References
IN-94-030, Suppl 1, NUDOCS 9408160070
Download: ML031060492 (9)
v • d • e


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555 August 19, 1994 NRC INFORMATION NOTICE 94-30, SUPPLEMENT 1: LEAKING SHUTDOWN COOLING

ISOLATION VALVES AT

COOPER NUCLEAR STATION

Addressees

All holders of operating licenses or construction permits for nuclear power

reactors.

Purpose

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information

notice (IN) supplement to clarify the type of valve discussed in the original

notice and to alert recipients to the potential that local leak rate testing

of primary containment isolation valves with pressure applied in the direction

opposite of the accident direction may not be conservative. It is expected

that recipients will review the information for applicability to their

facilities and consider actions, as appropriate, to avoid similar problems.

However, suggestions contained in this information notice are not NRC

requirements; therefore, no specific action or written response is required.

Background

The NRC issued IN 94-30, "Leaking Shutdown Cooling Isolation Valves at Cooper

Nuclear Station," on April 12, 1994, to alert addressees to a precursor to an

unisolable rupture of shutdown cooling piping with the potential for core

damage and release of radioactive material outside the containment. In that

event, after receiving a high-pressure alarm for the suction piping in the

residual heat removal system, the licensee measured the leakage through the

inboard isolation valve, established a bleedoff path into the pressure

maintenance system and continued operations. About 10 months later, the

licensee disassembled the inboard and outboard valves and found cracks in the

seating surfaces of both valves.

During the preparation of IN 94-30, the staff determined that a concern may

exist regarding the method used for testing of primary containment isolation

valves. This concern is described below. In addition, the NRC has received

information from Anchor/Darling Valve Company that the description of the

valves in IN 94-30, "Anchor-Darling 20-inch nominal, double-disk, flex-wedge, gate valves," is incorrect. The correct description is, "a 20 inch, 900

class, flex wedge gate valve," manufactured by the Anchor Valve Company before

the merger that formed the Anchor/Darling Valve Company. In IN 94-30, the NRC

staff was concerned about the actions of the licensee after the valve leakage

was identified regardless of the valve type or manufacturer.

Gs tAiJ4-:&ge q 3019

9408160070

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IN 94-30, Supplement 1 August 19, 1994

Description of Circumstances

On May 1, 1993, after evaluating the results of local leak rate testing for

several inboard primary containment isolation valves, the licensee for the

Cooper Nuclear Station (Cooper) determined that the testing methodology used

for Appendix J, Type C tests of certain flex-wedge gate valves could not be

relied on to be equivalent to or more conservative than testing the valves in

the accident direction. The Type C tests for several such valves had been

performed with the pressure applied in the direction opposite to the accident

direction (reverse direction). The licensee began corrective actions and

notified the NRC in Licensee Event Report (LER)93-019, dated June 1, 1993.

In LER 93-019, the licensee reported that the testing of these valves in the

reverse direction was based on an incorrect interpretation of information from

the valve manufacturer. In response to a question from the licensee regarding

the acceptability of valve test methods, the manufacturer had indicated that

testing in the reverse direction would not be expected to affect test results, but an unqualified answer could not be provided. Results of recent tests by

the licensee of some of the primary containment isolation valves with pressure

applied in the accident direction, indicate that testing in the reverse

direction may not be equivalent to or more conservative than testing in the

accident direction; therefore earlier test results may not be valid.

LER 93-019 indicated that Cooper Nuclear station has 65 inboard primary

containment valves of various types and from various manufacturers. The

licensee found that 24 of those valves were of concern. Of the 24 valves,

8 could be tested in the accident direction but, before the 1993 refueling

outage, were not. The other 16 valves could not be tested in the accident

direction nor had testing in the reverse direction been qualified to be

equivalent or more conservative than testing in the accident direction. For

most of these valves, the licensee qualified testing in the reverse direction

to be equivalent or more conservative or modified the testing configuration to

allow testing the valve in the accident direction. For the remaining valves, the licensee requested exemptions from certain Appendix J requirements to

allow leak .rate testing in the reverse' direction.

Discussion'

Appendix J to Title 10 of the Code of Federal Regulations Part 50 requires a

program for leak testing the primary reactor containment and related systems

and components penetrating the primary containment pressure boundary.

Section III.C.1 of Appendix J specifies that, for Type C tests of valves

(local leak rate tests), the pressure shall be applied in the same direction

as that when the valve would be required to perform its safety function, unless it can be determined that the results from the tests for a pressure

applied in a different direction will provide equivalent or more conservative

results. This requirement is intended to ensure that test leak rates are

representative of leak rates that would be experienced under actual accident

conditions. As described above, the licensee for Cooper found that, for some

of the primary containment isolation valves, testing in the reverse direction

was not equivalent to or more conservative than testing in the accident

direction.

IN 94-30, Supplement 1 August 19, 1994 Related Generic Communications

  • NRC IN 86-16, "Failures to Identify Containment Leakage Due to

Inadequate Local Leak Rate Testing," March 11, 1986.

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

the technical contact listed below or the appropriate Office of Nuclear

Reactor Regulation (NRR) project manager.

Brian s, Director Q

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contact: Jim Pulsipher, NRR

(301) 504-2811 Attachment:

List of Recently Issued NRC Information Notices

s&C 3Lo

Attachment

IN 94-30, Supp. 1 August 19, 1994 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

94-59 Accelerated Dealloying of 08/17/94 All holders of OLs or CPs

Cast Aluminum-Bronze for nuclear power reactors.

Valves Caused by Micro- biologically Induced

Corrosion

94-58 Reactor Coolant Pump 08/16/94 All holders of OLs or CPs

Lube Oil Fire for pressurized water

reactors.

94-57 Debris in Containment 08/12/94 All holders of OLs or CPs

and the Residual Heat for nuclear power reactors.

Removal System

94-56 Inaccuracy of Safety Valve 08/11/94 All holders of OLs or CPs

Set Pressure Determinations for nuclear power reactors.

Using Assist Devices

94-55 Problems with Copes- 08/04/94 All holders of OLs or CPs

Vulcan Pressurizer for nuclear power reactors.

Power-Operated Relief

Valves

91-79, Deficiencies Found in 08/04/94 All holders of OLs or CPs

Supp. 1 Thermo-Lag Fire Barrier for nuclear power reactors.

Installation

94-54 Failures of General 08/01/94 All holders of OLs or CPs

Electric Magne-Blast for nuclear power reactors.

Circuit Breakers to

Latch Closed

91-45, Possible Malfunction of 07/29/94 All holders of OLs or CPs

Supp. 1 Westinghouse ARD, BFD, for nuclear power reactors.

and NBFD Relays, and

A200 DC and DPC 250

Magnetic Contactors

94-42, Cracking in the Lower 07/19/94 All holders of OLs or CPs

Supp. 1 Region of the Core Shroud for boiling water reactors

in Boiling-Water Reactors (BWRs).

OL = Operating License

CP = Construction Permit

'-30, Supplement 1 V IN

August 19, 1994 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

the technical contact listed below or the appropriate Office of Nuclear

Reactor Regulation (NRR) project manager.

orig /s/'d by CIGrimes/for

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contact: Jim Pulsipher, NRR

(301) 504-2811 Attachment:

List of Recently Issued NRC Information Notices

SPraa Proevintic rnnmirronre

OFFICE SCSB:DSSA:NRR SCSB:DSSA:NRR C/SCSB:DSSA:NRR D/DSSA:NRR

NAME I JPulsifer* RLobel* RBarrett* GHolahan*

DATE 07/17/94 107/19/94 08/03/94 08/04/94 OFFICE I TECH ED OGCB:DORS:NRR AC/OGCB:DORS:NRR D/DORS:JNI2,a

NAME RSanders* JBirmingham* ELDoolittle* BKGrimes

DATE 6/14/94 1 08/03/94 08/04/94 ,08/ t194 UN .-ILALUUU rptt A'4u^t- Iit

OFFIIAL UULUMMNI NAMEL: Y4-30SH .AN

I" 4-30, Supplement 1 August XX, 1994 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

the technical contact listed below or the appropriate Office of Nuclear

Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contact: Jim Pulsipher, NRR

(301) 504-2811 Attachment:

List of Recently Issued NRC Information Notices

  • See Previnus Concurrence

OFFICE SCSB:DSSA:NRR SCSB:DSSA:NRR C/SCSB:DSSA:NRR D/DSSA:NRR

NAME JPulsifer* RLobel* RBarrett* GHolahan*

DATE 07/17/94 07/19/94 , 08/03/94 08/04/94 OFFICE TECH ED OGCB:DORS:NRR AC/OGCB:DORS:NRR D/DORS:NRR

NAME RSanders* JBirmingham* ELDoolittle* BKGrimes

DATE

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06/14/94

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08/03/94

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108/04/94 08/ /94 A

OFFICIAL OUCUMNI NArt: U:\1N Y4JUb.LUb

IN"4-30, Supplement 1 August XX, 1994 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

the technical contact listed below or the appropriate Office of Nuclear

Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contact: Jim Pulsipher, NRR

(301) 504-2811 Attachment:

List of Recently Issued NRC Information Notices

  • See Previnut Cnncurrence A

OFFICE SCSB:DSSA:NRR SCSB:DSSA:NRR C/SCSB:DSSA:NRR RR

NAME JPulsifer* RLobel* RBarrett* GHolahan

DATE 07/17/94 07/19/94 08/03/94 08/e/94 OFFICE TECH ED OGCB:DORS:NRR AC lBODORS:NRR D/DORS:NRR

NAME RSanders* JBirmingham* E6 ttle BKGrimes

DATE 06/14/94 08/03/94

.J 08/4 /94 08/ /94 OICA DO. ..

MN._ NAE G.. . 4.

OFFICIAL DOCUMENT NAME: 6:\IN 9430S.JLB

IN44-30, Supplement 1 August XX, 1994 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

the technical contact listed below or the appropriate Office of Nuclear

Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contact: Jim Pulsipher, NRR

(301) 504-2811 Attachment:

List of Recently Issued NRC Information Notices

  • See Previous Concurrence A

OFFICE lSCSB:DSSA:NRR SCSB:DSSA:NRR C/SCS A:NRR AD/DSSA:NRR

JPulsifer* RLobel* l aWVrgllo

NAME

lDATE 07/17/94 07/19/94 !08/;7/94 08/ /94 OFFICE TECH ED OGCB:DORS:NRR AC/OGCB:DORS:NRR D/DORS:NRR

NAME RSanders* JBirmingham ELDoolittle BKGrimes

DATE 06/14/94 08/ 3 /94 . 08/ /94 08/ /94 a.-.-. a. a. anna ... r&*, a.r. **a A .i 1A

1 Do

UMLI16AL UUUUMtN1I `t: IN Y4JV3 .UL0

IN 94-30, Supplement 1 June XX, 1994 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

the technical contact listed below or the appropriate Office of Nuclear

Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contact: Jim Pulsipher, NRR

(301) 504-2811 Attachment:

List of Recently Issued NRC Information Notices

  • See Previous Concurrence 1i'

OFFICE S 5 SCSB:DSSA:NRR C/SCSB:DSSA:NRR D/DSSA:NRR

NAME JPulsige ZtG RBarrett MVirgilio

lDATE _ i

_06/17/94 /94/06/ /94 06/ /94 OFFICE TECH ED 9 OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS:NRR

NAME RSander JBirmingham RDennig BKGrimes

DATE 06/14/94 I06/ /94 06/ /94 06/ /94 OFF116lAL VULUMtNI NAML iNr3 JU1.dJLU


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