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{{#Wiki_filter:NRC FORM 366                                                                                                                U.S. NUCLEAR REGULATORY COMMISSION
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LICENSEE EVENT REPORT CONTROL BLOCK: l 1
l    l      l    l    l    lh 6
(PLEASE PRINT oR TYPE ALL REQUIRED INFoRMATION)
VlAlN                                                      0 LICENdE l0 l0NUMBEft l0 l0 l- l0 l0 l@l4 l1                        l1 l1l1 (.                          l@
joltl                                                                                                                                                                l 7        8 9 A l S l 114lgl150 l0 LICENSEE CODE                                                                            25      26      LICENSE TYPE JO            b) CATb8 CON'T l
c    i 8
3{"C l60L l@l61 0 l 5 l DOCKET          o l 0NUMBEH l 0 l 3 l 3 68l8 l@l    69 01EVENT 91DATE 21 81 71 973@l ilREPORT 14 nl 9l    A !79 1l@
D ATE          80 EVENT DESCRIPTION AND PROBA0LE CONSEQUENCES h O  2      10n September 28, 1979, during the performance of the 18 month Containment Depressuri- l o 3        ;zation Actuation test, valves TV-SW101A and B, MOV-SW110A and B, and MOV-SW114A and B l o  4      l failed to close on the first CDA test signal but did close when the second CDA signal l lO ls] lwas initiated. Since all these valves are administrative 1y kept closed and opened                                                                                        l lo is i l only when testing is required, the health and safety of the general public were not                                                                                    I l o l 7 l l af fected by their failure to close. Reportable pursuant to T.S. 6.9.1.9.b.                                                                                          l I
10181 l DE              CODE      SU8C E                  COMPONENT CCDE                    SU8C DE            S      DE O 9                            lW Al@ ] @ ] @                                        Vl Al Ll Vl E            X l@ W@ g @
1d          19                20 7        8                      9        10          11            12            13 SEQUENTIAL                      OCCUR R E NCE        REPORT                        REVISION
_ EVENT YE AR                            REPORT NO.                          CODE                TYPE                            N O.
O e ust "LER/RO  a' 17191
_ 21        22 L--J 2J            24 1 13 14 1 26 M
27 10 31 28        29 LL._J 30 L _-1 31 LO_J 32 TAKEt      A T ON          O . PL T            MET                    HOURS          SB IT D          FO 1 UB.          $ PPLI                MANUFACTURER l X l@[B_j@                    Z l@            [_Zj@          l0 l0 l0 0 l            l41 Y]@          (j1j@              [A_j@            lA l1l8 0l@
J3          34              35                36            31                  40                    42                  43              44              47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i  o lThe cause for the valves not closina has not as yet been determined.                                                                        A maintenance              I i i        l report has been submitted.                            During the Dresent refuelino outaae. tha valves wl11 ha                                                    1 1 2 Ichecked and repaired as necessary.                                                                                                                                    j 11 131 I i 4                                                                                                                                                                            l I
7      8 9                                                                                                                                                                    80 ST      S          % POWER                      OTHER STATUS              iS O RY                              DISCOVERY DESCRIPTION l1 Is l l C l@ l 0l 0l 0l@l                                    NA                        lBl@l Surveillance Test                                                              l ACTIVITY CO TENT RELE ASED OF RELE ASE                      AMOUNT OF ACTIVITY                                                    LOCATION OF RELEASE 1 e        [Z j @ l Zl@l                      NA 44 l          l 45 NA 80 l
7      8 9                  10        11 PERSONNEL EXPOSURES                              s NUMBER            TYPE        DESCRIPTION l i l '7 *l l 0 l 0 ' WhW@l NA PE RSmNE J imu' dies NUMu H              otSCRiPTiON@
NA                                                                                                                              l 1 a 0 l 0 l 0 l@l12                                                                                                                        g 7      8 9                  ft                                                                                                        i e,      f                          80 LOSS OF OR DAVAGE TO FACILITY                                                                                                              /
                                                                                                                                                          ~    (Qj TYPE        DE SC RIP TION 1 9        [_Z_j@l                NA                                                                                                                                          l 7        8 9              10                                                                                                                                                  80 2 O      ISSU LN_j        E l D@DESCRIPNA                      TION                          910310h/f                                      l      llllllllll                ll~*g 7      8 9              10                                                                                                              68 69                              80 5 NAME OF PREPARER                  W. R. Cartwricht                                              p,4oy e        703-894-5151                              2
 
Virginia Electric and Power Comptay North Anna Power Station, Unit #1                  Atta :hment : Page 1 of 1 Docket No. 50-338 Report No. LER 79-134[ .L-0 Description of Event On September 28, 19 79, with      e"  at cold shutdown, service water val  -
TV-SW101A and B, MOV-SW110A a,    B, and MOV-SW114A and B failed to close e    th e first CDA test signal but did close when the second CDA si,w
* was initiated during the performance of the 18 month Containment Depressu-        'on Actuation Functional Test.
Probable Consequences of Occurrence The consequences c' this event were minimal because all six valves, which are located on the sur . y and return lines for the containment recirculation air cooling coils, are administrative 1y kept closed to prevent treated water in the service water system from entering the chilled water system and are opened only when testing on the valves is required. (Normally, chilled water flows through the containment recirculation air cooling coils.) As a result, the health and safety of the general public were not affected by this event. No generic implications exist for this occurrence.
Cause The cause for th. valves not closing on the first CDA signal has not been determined at this time. Further testing and/or maintenance during the outage will be performed to determine the cause.
Immediate Corrective Action A maintenance report has been submitted.
Scheduled Corrective Action The six valves will be checked and repaired as necessary during the present refueling outage.                              ,
Actions Taken to Prevent Recurrence No further actions are required.
4    209}}

Latest revision as of 00:07, 2 February 2020

LER 79-134/03L-0:on 790928,six Valves Failed to Close on First Signal of Containment Depressurization Test But Did So on Second Signal.Cause Undetermined.Valves Will Be Rechecked & Repaired as Necessary
ML19254E286
Person / Time
Site: North Anna Dominion icon.png
Issue date: 10/26/1979
From: Cartwright W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19254E281 List:
References
LER-79-134-03L, LER-79-134-3L, NUDOCS 7910310417
Download: ML19254E286 (2)


Text

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION

(?<7) -

LICENSEE EVENT REPORT CONTROL BLOCK: l 1

l l l l l lh 6

(PLEASE PRINT oR TYPE ALL REQUIRED INFoRMATION)

VlAlN 0 LICENdE l0 l0NUMBEft l0 l0 l- l0 l0 l@l4 l1 l1 l1l1 (. l@

joltl l 7 8 9 A l S l 114lgl150 l0 LICENSEE CODE 25 26 LICENSE TYPE JO b) CATb8 CON'T l

c i 8

3{"C l60L l@l61 0 l 5 l DOCKET o l 0NUMBEH l 0 l 3 l 3 68l8 l@l 69 01EVENT 91DATE 21 81 71 973@l ilREPORT 14 nl 9l A !79 1l@

D ATE 80 EVENT DESCRIPTION AND PROBA0LE CONSEQUENCES h O 2 10n September 28, 1979, during the performance of the 18 month Containment Depressuri- l o 3 ;zation Actuation test, valves TV-SW101A and B, MOV-SW110A and B, and MOV-SW114A and B l o 4 l failed to close on the first CDA test signal but did close when the second CDA signal l lO ls] lwas initiated. Since all these valves are administrative 1y kept closed and opened l lo is i l only when testing is required, the health and safety of the general public were not I l o l 7 l l af fected by their failure to close. Reportable pursuant to T.S. 6.9.1.9.b. l I

10181 l DE CODE SU8C E COMPONENT CCDE SU8C DE S DE O 9 lW Al@ ] @ ] @ Vl Al Ll Vl E X l@ W@ g @

1d 19 20 7 8 9 10 11 12 13 SEQUENTIAL OCCUR R E NCE REPORT REVISION

_ EVENT YE AR REPORT NO. CODE TYPE N O.

O e ust "LER/RO a' 17191

_ 21 22 L--J 2J 24 1 13 14 1 26 M

27 10 31 28 29 LL._J 30 L _-1 31 LO_J 32 TAKEt A T ON O . PL T MET HOURS SB IT D FO 1 UB. $ PPLI MANUFACTURER l X l@[B_j@ Z l@ [_Zj@ l0 l0 l0 0 l l41 Y]@ (j1j@ [A_j@ lA l1l8 0l@

J3 34 35 36 31 40 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i o lThe cause for the valves not closina has not as yet been determined. A maintenance I i i l report has been submitted. During the Dresent refuelino outaae. tha valves wl11 ha 1 1 2 Ichecked and repaired as necessary. j 11 131 I i 4 l I

7 8 9 80 ST S  % POWER OTHER STATUS iS O RY DISCOVERY DESCRIPTION l1 Is l l C l@ l 0l 0l 0l@l NA lBl@l Surveillance Test l ACTIVITY CO TENT RELE ASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE 1 e [Z j @ l Zl@l NA 44 l l 45 NA 80 l

7 8 9 10 11 PERSONNEL EXPOSURES s NUMBER TYPE DESCRIPTION l i l '7 *l l 0 l 0 ' WhW@l NA PE RSmNE J imu' dies NUMu H otSCRiPTiON@

NA l 1 a 0 l 0 l 0 l@l12 g 7 8 9 ft i e, f 80 LOSS OF OR DAVAGE TO FACILITY /

~ (Qj TYPE DE SC RIP TION 1 9 [_Z_j@l NA l 7 8 9 10 80 2 O ISSU LN_j E l D@DESCRIPNA TION 910310h/f l llllllllll ll~*g 7 8 9 10 68 69 80 5 NAME OF PREPARER W. R. Cartwricht p,4oy e 703-894-5151 2

Virginia Electric and Power Comptay North Anna Power Station, Unit #1 Atta :hment : Page 1 of 1 Docket No. 50-338 Report No. LER 79-134[ .L-0 Description of Event On September 28, 19 79, with e" at cold shutdown, service water val -

TV-SW101A and B, MOV-SW110A a, B, and MOV-SW114A and B failed to close e th e first CDA test signal but did close when the second CDA si,w

  • was initiated during the performance of the 18 month Containment Depressu- 'on Actuation Functional Test.

Probable Consequences of Occurrence The consequences c' this event were minimal because all six valves, which are located on the sur . y and return lines for the containment recirculation air cooling coils, are administrative 1y kept closed to prevent treated water in the service water system from entering the chilled water system and are opened only when testing on the valves is required. (Normally, chilled water flows through the containment recirculation air cooling coils.) As a result, the health and safety of the general public were not affected by this event. No generic implications exist for this occurrence.

Cause The cause for th. valves not closing on the first CDA signal has not been determined at this time. Further testing and/or maintenance during the outage will be performed to determine the cause.

Immediate Corrective Action A maintenance report has been submitted.

Scheduled Corrective Action The six valves will be checked and repaired as necessary during the present refueling outage. ,

Actions Taken to Prevent Recurrence No further actions are required.

4 209