ML19210C433: Difference between revisions

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{{#Wiki_filter:uCEisSdd Ev EN i nErOrii
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uCEisSdd Ev EN i nErOrii CONTROL BLOCK:                     l  l    l      l  l                      (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 7 o  i 8 9 lVlA              l N l A l S 14l1 l@l LICENSEE CODE                    13 0l 0l -l 0 lLICEtJSE0 l 0NUMBEH l 0 l 0 l- l 0 l 025l@l4     26 l1LICENSE 1
lllll(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) l V l A l N l A l S l1 l@l 0l 0l -l 0 l 0 l 0 l 0 l 0 l- l 0 l 0 l@l4 l1 1 1 l1 l@lll@o i 7 8 9 LICENSEE CODE 14 13 LICEtJSE NUMBEH 25 26 LICENSE TYPE JO bl LAI 58 CON'T ,"j]"y l L l@l 0 l 5 l0 l0 l0 l3 l3 l8 l@l1 011 l3 l 719 l@l i i li l9 17 h l@
1TYPE l1JOl@lbl LAIl 58 l@
o i 7 3 60 61 DOCKET NUMSER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h
CON'T 7
&LLJ l After the condensate and feedwater pumps were secured for refueling, containment i isolation check valve 1-FW-ill was observed to be partially stuck open as evidenced lO 3lby back leakage from "C" steam generator to the feedwater heaters. The health and I 0.,; safety of the general public were not affected by this event.
o i 3
Reportable pursur.. to lo 3;T.S. 6.9.1.9.b.
                        ,"j]"y l L l@l 0 l 5 l0 l0 l0 l3 l3 l8 68l@l1 60          61                                              69 011     l3 l 71974l@l75 i i REPORT EVENT DATE li l9DATE 17 h 80l@
lO 3 0 7ll0 8ll80 7 8 9 bE CC E S3 0 E COVPONE NT CODE SUSCODE SU El c l H l@ lE l@ l R l@ IV l A lL IV IE lX l@ LC_j@ (Lj @
DOCKET NUMSER EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h
o 9 7 8 9 10 11 12 13 18 19 20'SEQUE NTI AL OCCURRENCE REPORT REVISION LE R RO EVENT YEAR REPORT NO.
&LLJ l After the condensate and feedwater pumps were secured for refueling, containment                                                                                     i O  3            isolation check valve 1-FW-ill was observed to be partially stuck open as evidenced                                                                     l 0    .,      lby back leakage from "C" steam generator to the feedwater heaters. The health and                                                                         I o    3      ; safety of the general public were not affected by this event.                                                         Reportable pursur.. to             l O  3       ;T.S. 6.9.1.9.b.                                                                                                                                             l 0    7      l                                                                                                                                                          l 0 8        l                                                                                                                                                          l 7         8 9                                                                                                                                                           80 bE           CC E         S3 0 E                 COVPONE NT CODE                 SUSCODE         SU     E o  9                                l c l H l@ lE l@ l R l@ IV l A lL IV IE lX l@ LC_j@ (Lj @
CCCE TYPE NO.O17 ,RElgl217l 9ll-ll11410j 1/il 013 lLl[ --jl0 lu 22 23 24 26 27 28 23 30 31 32 T K N A T ON O PL NT.t TH HOURS 22 S B IT D FOf 1 B.5 PPLIE VAN FA TURER I X l@lD l@
7         8                           9         10         11             12             13                         18         19             20
l Z]@l Z l@l 0 l 0 l 010 l lY l@l N ]@[Al@lC 2l5[5l@
                      '                                                         SEQUE NTI AL                   OCCURRENCE         REPORT                   REVISION LE R RO       EVENT YEAR                             REPORT NO.                         CCCE             TYPE                       NO.
33 34 35 36 3/40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l The cause for the check valve stit'<ing open is not known at this time. The valve was li O[i li l l radiographed but tne results were unsuccessful due to the thickness of the valve body.
O17 ,RElg                                    l-l            l11410j              1/i          l 013 l                Ll          [ --j    l0 l u
I The valve will be disassembled and repaired as determined necessary during the current l i 2l outage.l, 3 i 4 1 1 7 8 9 80 ST 5% POWER OTHER STATUS ISCOV RY DISCOVERY DESCRIPTION LtLj@ l 0101 nl@l ral[L.j@l onaratnr nhwrvatinn li s' JTIVITY''""''CC TNT WOUNTOhCTIVITY @ I LOCATION OF RELEASE @
l217l229l          23             24             26     27           28       23         30             31       32 T K N A T ON                     O PL NT           .t TH                     HOURS 22     S B IT D       FOf 1     B. 5 PPLIE           VAN FA TURER I33X l@lD     34 l@         l35 Z]@           l36Z l@         l 0 l 0 l 010 l 3/                40 lY 41 l@         l42N ]@         [Al@
RELEASED OF RELEASE fi e LLl@ Lzl@l I rm I rm 7 8 9 10 11 44 45 So PERSCNNEL EXPCSURES NUVBER.YPE DE SCRIPTION
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'1010 Ol@lzl@lNA li 2 2"*'' ',ERSONNabu'R,ES oESCR,PTiON@
44             47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i  O        l The cause for the check valve stit'<ing open is not known at this time. The valve was                                                                     l
7%-/pg NUven 7 1010101@lNAli a 7 8 9 11 12 80 LOSS OF OR OAMAGE TO FACILITY Q TYPE DESCRIPTION N/[i 9l Z l@lNAl7 8 9 10 80 PTiON O 7911140 g Q
[i li l l radiographed but tne results were unsuccessful due to the thickness of the valve body.                                                                           I i  2 The valve will be disassembled and repaired as determined necessary during the current l
' ' ' *NRC usE CNa iSSU OESCR: 17 I o l [ Jds81 NA I IIIIIi III i lI 7 8 9 10 68 69 S0 5 W. R. Cartwright 701-894-5151 psoye.N A*.1E CF PPE P AP E R  
    ,  3      l outage.                                                                                                                                                   l i 4       1                                                                                                                                                           1 7         8 9                                                                                                                                                           80 ST       5             % POWER                     OTHER STATUS               ISCOV RY                         DISCOVERY DESCRIPTION i  s      LtLj@ l 0101 nl@l                                 ra                        l  [L.j@l         onaratnr nhwrvatinn                                         l
.Virginia Electric and Pcwer Company fiorth Anna Power Station, Unit #1
'                                 '               '     "                               "               '
          ' JTIVITY          CC TNT RELEASED OF RELEASE                                                                                                LOCATION OF RELEASE @
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e 8 9 LLl@ Lzl@l         10           11 rmWOUNTOhCTIVITY                  44 I
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                                                                                                              @I rm So I
PERSCNNEL EXPCSURES
                                            '
NUVBER                 .YPE       DE SCRIPTION
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          ' '
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                    ,ERSONNabu'R,ES                                                                                                 -
7%
i NUven                  oESCR,PTiON@
7     /pg 7
a 8 9 1010101@l12          11 NA 80 l
LOSS TYPE OF OR OAMAGE TO FACILITY Q DESCRIPTION                 N/
[i     9 l Z l@l10                            NA                                                                                                                    l 7          8 9                                                                                                                                                           80
                              '''*
iSSU            OESCR:    PTiON O                                                   7911140 g Q                                         NRC usE CNa 17 I o l [ Jds81                                     NA                                                                                     I 68 69 IIIIIi         III   iS0lI5 7         8 9                 10 N A*.1E CF PPE P AP E R W. R. Cartwright                                        psoye.          701-894-5151
 
.
Virginia Electric and Pcwer Company fiorth Anna Power Station, Unit #1                  


==Attachment:==
==Attachment:==
Page 1 of 1 Docket tio. 50-338 Report flo. LER 79-140/03L-0 Description of Event On October 13, 1979, with the unit in refueling mode, containment isolation check valve 1-FN-lll was observed to be partially stuck open as evidenced by back leakaSe from "C" steam generator to the feedwater heaters when the condensate and feedwater pumps were secured. The inoperability of containment isolation valve 1-FW-lll is contrary to T.S. 3.6.3.1 and reportable pursuant to T.S. 6.9.1.9.b.
Page 1 of 1 Docket tio. 50-338 Report flo. LER 79-140/03L-0 Description of Event On October 13, 1979, with the unit in refueling mode, containment isolation check valve 1-FN-lll was observed to be partially stuck open as evidenced by back leakaSe from "C" steam generator to the feedwater heaters when the condensate and feedwater pumps were secured. The inoperability of containment isolation valve 1-FW-lll is contrary to T.S. 3.6.3.1 and reportable pursuant to T.S. 6.9.1.9.b.
Probable Consequences of Occurrence The health and safety of the general public were not affected because the check valve was found inoperable while the unit was in a safe shutdown condition and will be restored to operable status prior to resuming operation.
Probable Consequences of Occurrence The health and safety of the general public were not affected because the check valve was found inoperable while the unit was in a safe shutdown condition and will be restored to operable status prior to resuming operation.
Line 44: Line 68:
Scheduled Corrective Action The check valve will be disassembled and repaired as necessary during the current refueling outage.
Scheduled Corrective Action The check valve will be disassembled and repaired as necessary during the current refueling outage.
Actions Taken to Prevent Recurrence flo further actions are required.
Actions Taken to Prevent Recurrence flo further actions are required.
' " 9 280}}
                                                        '"9     280}}

Revision as of 12:53, 19 October 2019

LER 79-140/03L-0:on 791013,after Condensate & Feedwater Pumps Secured for Refueling,Containment Isolation Check Valve 1-FW-111 Be Stuck Open.Cause Unknown.Valve Will Be Disassembled & Repaired During Current Outage
ML19210C433
Person / Time
Site: North Anna Dominion icon.png
Issue date: 11/12/1979
From: Cartwright W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19210C432 List:
References
LER-79-140-03L, LER-79-140-3L, NUDOCS 7911140243
Download: ML19210C433 (2)


Text

,

uCEisSdd Ev EN i nErOrii CONTROL BLOCK: l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 7 o i 8 9 lVlA l N l A l S 14l1 l@l LICENSEE CODE 13 0l 0l -l 0 lLICEtJSE0 l 0NUMBEH l 0 l 0 l- l 0 l 025l@l4 26 l1LICENSE 1

1TYPE l1JOl@lbl LAIl 58 l@

CON'T 7

o i 3

,"j]"y l L l@l 0 l 5 l0 l0 l0 l3 l3 l8 68l@l1 60 61 69 011 l3 l 71974l@l75 i i REPORT EVENT DATE li l9DATE 17 h 80l@

DOCKET NUMSER EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h

&LLJ l After the condensate and feedwater pumps were secured for refueling, containment i O 3 isolation check valve 1-FW-ill was observed to be partially stuck open as evidenced l 0 ., lby back leakage from "C" steam generator to the feedwater heaters. The health and I o 3  ; safety of the general public were not affected by this event. Reportable pursur.. to l O 3 ;T.S. 6.9.1.9.b. l 0 7 l l 0 8 l l 7 8 9 80 bE CC E S3 0 E COVPONE NT CODE SUSCODE SU E o 9 l c l H l@ lE l@ l R l@ IV l A lL IV IE lX l@ LC_j@ (Lj @

7 8 9 10 11 12 13 18 19 20

' SEQUE NTI AL OCCURRENCE REPORT REVISION LE R RO EVENT YEAR REPORT NO. CCCE TYPE NO.

O17 ,RElg l-l l11410j 1/i l 013 l Ll [ --j l0 l u

l217l229l 23 24 26 27 28 23 30 31 32 T K N A T ON O PL NT .t TH HOURS 22 S B IT D FOf 1 B. 5 PPLIE VAN FA TURER I33X l@lD 34 l@ l35 Z]@ l36Z l@ l 0 l 0 l 010 l 3/ 40 lY 41 l@ l42N ]@ [Al@

43 lC 2l5[5l@

44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i O l The cause for the check valve stit'<ing open is not known at this time. The valve was l

[i li l l radiographed but tne results were unsuccessful due to the thickness of the valve body. I i 2 The valve will be disassembled and repaired as determined necessary during the current l

, 3 l outage. l i 4 1 1 7 8 9 80 ST 5  % POWER OTHER STATUS ISCOV RY DISCOVERY DESCRIPTION i s LtLj@ l 0101 nl@l ra l [L.j@l onaratnr nhwrvatinn l

' ' ' " " '

' JTIVITY CC TNT RELEASED OF RELEASE LOCATION OF RELEASE @

fi 7

e 8 9 LLl@ Lzl@l 10 11 rmWOUNTOhCTIVITY 44 I

45

@I rm So I

PERSCNNEL EXPCSURES

'

NUVBER .YPE DE SCRIPTION

'

i 2

' '

1010 Ol@lzl@lNA 2 "

  • l

,ERSONNabu'R,ES -

7%

i NUven oESCR,PTiON@

7 /pg 7

a 8 9 1010101@l12 11 NA 80 l

LOSS TYPE OF OR OAMAGE TO FACILITY Q DESCRIPTION N/

[i 9 l Z l@l10 NA l 7 8 9 80

*

iSSU OESCR: PTiON O 7911140 g Q NRC usE CNa 17 I o l [ Jds81 NA I 68 69 IIIIIi III iS0lI5 7 8 9 10 N A*.1E CF PPE P AP E R W. R. Cartwright psoye. 701-894-5151

.

Virginia Electric and Pcwer Company fiorth Anna Power Station, Unit #1

Attachment:

Page 1 of 1 Docket tio. 50-338 Report flo. LER 79-140/03L-0 Description of Event On October 13, 1979, with the unit in refueling mode, containment isolation check valve 1-FN-lll was observed to be partially stuck open as evidenced by back leakaSe from "C" steam generator to the feedwater heaters when the condensate and feedwater pumps were secured. The inoperability of containment isolation valve 1-FW-lll is contrary to T.S. 3.6.3.1 and reportable pursuant to T.S. 6.9.1.9.b.

Probable Consequences of Occurrence The health and safety of the general public were not affected because the check valve was found inoperable while the unit was in a safe shutdown condition and will be restored to operable status prior to resuming operation.

There are no generic implications associated with this event.

Cause of Occurrence The exact cc.use for 1-FW-lli sticking open is not known at this time.

Immediate Corrective Action The valve was radiographed but the results of the examination were unsuccessful because of the thickness of the valve body.

Scheduled Corrective Action The check valve will be disassembled and repaired as necessary during the current refueling outage.

Actions Taken to Prevent Recurrence flo further actions are required.

'"9 280