ML19270E896: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 21: | Line 21: | ||
lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORNIATION) 7 oji 8 9 lUlElFlClSl1l@l0lol0l0lolol0l0lo o l o l@l hl 1l ll ll 1l@l LICENSEE CODE 14 15 LICENSE NUMBER 25 ;8 LICENSE TYPE JO l | lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORNIATION) 7 oji 8 9 lUlElFlClSl1l@l0lol0l0lolol0l0lo o l o l@l hl 1l ll ll 1l@l LICENSEE CODE 14 15 LICENSE NUMBER 25 ;8 LICENSE TYPE JO l | ||
57 CATid l@ | 57 CATid l@ | ||
CON'T | CON'T o11 5a7RCE I L @l 0 l 5 l 0 j 0 l 0 l 2 l 8 l 5 }gl1 l 210 l 5 [ 7 l 8 @l1 l 2 l2 l 217 l8 l@ | ||
o11 5a7RCE I L @l 0 l 5 l 0 j 0 l 0 l 2 l 8 l 5 }gl1 l 210 l 5 [ 7 l 8 @l1 l 2 l2 l 217 l8 l@ | |||
7 4 60 61 CCCXET NUM8ER 68 69 EVENT CATE 74 75 REPCRT CATE 80 | 7 4 60 61 CCCXET NUM8ER 68 69 EVENT CATE 74 75 REPCRT CATE 80 | ||
_ EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h o 2 l During the performance of the type B and C containment leak rate tests during the l o a l 1978 refueling outage, it was noted that the total leakage exceeded the 0.6 La limit l 0 44 lof 62,951 sces. I o s ! l 0 6 l 017 l l ata l I 7 $ 9 SO SYSTEM CAUSE CAUSE COMP. VALVE CCDE CCOE SU8CCDE COMPONENT CCDE SUSCCOE SUSCCCE 7 | _ EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h o 2 l During the performance of the type B and C containment leak rate tests during the l o a l 1978 refueling outage, it was noted that the total leakage exceeded the 0.6 La limit l 0 44 lof 62,951 sces. I o s ! l 0 6 l 017 l l ata l I 7 $ 9 SO SYSTEM CAUSE CAUSE COMP. VALVE CCDE CCOE SU8CCDE COMPONENT CCDE SUSCCOE SUSCCCE 7 | ||
oI9 8 | oI9 8 | ||
| Line 32: | Line 29: | ||
@ aEPoat 17 18 I l-l lo lh lo i I/l l 01, I ILI l-1 I ol | @ aEPoat 17 18 I l-l lo lh lo i I/l l 01, I ILI l-1 I ol | ||
_ 21 22 23 24 26 27 28 23 30 31 J2 ACTION . FUTURE EFFECT SHUTOOWN ATTACHMENT NPR O-4 PRIME COMP, COMPONENT TAKEN ACTICN ON PLANT METHOO HOURS d SUSMITTED PCRM bu8. SUPPLIE R MANUFACTURER lo 3J l@lz l@34 W@ - Iz l@ Io lo l0 lo l lY@ l42N I@ l Alh l Xl 9l ol Olh 35 36 3 e. 40 41 43 44 47 CAuSE cESCRIPTION AND CORRECTIVE ACTIONS 1 eo lThe penetrations that exhibited excess leakage were recaired and the total containmentI ii1 l leakage was reduced to below the 0.6 La (62.oS1 seem) limit. A modifientic, +n W -4 | _ 21 22 23 24 26 27 28 23 30 31 J2 ACTION . FUTURE EFFECT SHUTOOWN ATTACHMENT NPR O-4 PRIME COMP, COMPONENT TAKEN ACTICN ON PLANT METHOO HOURS d SUSMITTED PCRM bu8. SUPPLIE R MANUFACTURER lo 3J l@lz l@34 W@ - Iz l@ Io lo l0 lo l lY@ l42N I@ l Alh l Xl 9l ol Olh 35 36 3 e. 40 41 43 44 47 CAuSE cESCRIPTION AND CORRECTIVE ACTIONS 1 eo lThe penetrations that exhibited excess leakage were recaired and the total containmentI ii1 l leakage was reduced to below the 0.6 La (62.oS1 seem) limit. A modifientic, +n W -4 | ||
, ;tainment purge valves was completed this refueling outage which should reduce the leak + | , ;tainment purge valves was completed this refueling outage which should reduce the leak + | ||
,3 l age attributable to these valves, even if after repeated cycling. Quarterly leakage I g,, ; tests will continue to be performed on the containment purge valve penetrations. I 7 8 9 so | ,3 l age attributable to these valves, even if after repeated cycling. Quarterly leakage I g,, ; tests will continue to be performed on the containment purge valve penetrations. I 7 8 9 so "YE | ||
$ sPowER oTHER STATUS @ ciSCoNRv ciScovERY cESCRiPrioN h lt !5 l H l@ l 0l ol ol@lRefueline Shutdevd l Bl@l Refueline leak rate test l ACTIVITY CO TENT mELEASEC CFRELEASE AMOUNT C8 ACTtVITY LOCATICN CF RELEASE l l NA l 164 I3 l Z l h lZ l@l NA 1 | $ sPowER oTHER STATUS @ ciSCoNRv ciScovERY cESCRiPrioN h lt !5 l H l@ l 0l ol ol@lRefueline Shutdevd l Bl@l Refueline leak rate test l ACTIVITY CO TENT mELEASEC CFRELEASE AMOUNT C8 ACTtVITY LOCATICN CF RELEASE l l NA l 164 I3 l Z l h lZ l@l NA 1 | ||
7 10 11 44 45 30 ageSCNNEL EXPCSURES NUV8Ea ypg O ESCRIPTICN | 7 10 11 44 45 30 ageSCNNEL EXPCSURES NUV8Ea ypg O ESCRIPTICN | ||
| Line 42: | Line 36: | ||
PERSCNNEL N; BRIES , | PERSCNNEL N; BRIES , | ||
NLV6Em OESCR:PT:C N ',' | NLV6Em OESCR:PT:C N ',' | ||
& ilololol@l u | & ilololol@l u i | ||
790103o\\o | |||
:S$ cP :R = " .Ca , CmTv ra TV'E 05 SCRwTION V | :S$ cP :R = " .Ca , CmTv ra TV'E 05 SCRwTION V | ||
? | ? | ||
I9!l2i NA 7 3, 3 'C 40 PU B LICITv ygcggggggv | I9!l2i NA 7 3, 3 'C 40 PU B LICITv ygcggggggv 1 SUED OESCP6PTION | ||
* 3l W @l n M3/ ! !I i ' IIII i ''' | |||
1 SUED OESCP6PTION | |||
3l W @l n M3/ ! !I i ' IIII i ''' | |||
7 3 9 10 /M 93 59 ' % | 7 3 9 10 /M 93 59 ' % | ||
NAME OF PRi? ARER J. Connolley/G. Petersen 7wCNE: | NAME OF PRi? ARER J. Connolley/G. Petersen 7wCNE: | ||
Lo2 h26 holl | Lo2 h26 holl | ||
LER 78-Oh0 Omaha Public Power District Fort Calhoun Station Unit No. 1 Docket Ilo. 05000285 Attachment Ilo.1 Safety Analysis The air leakage tests performed during the 1978 refueling outage indicated a total leaka ge rate of h81,30h.27 seen of this leakage. However, only 183,288.07 scem can be attributed to direct containment atmosphere leakage. | |||
LER 78-Oh0 Omaha Public Power District Fort Calhoun Station Unit No. 1 Docket Ilo. 05000285 | |||
Attachment Ilo.1 Safety Analysis The air leakage tests performed during the 1978 refueling outage indicated a total leaka ge rate of h81,30h.27 seen of this leakage. However, only 183,288.07 scem can be attributed to direct containment atmosphere leakage. | |||
Since the containment purge valves were the largest contributors to this leak-age, 1h3,002.17 seem and the leakage of the purge valves was verified to be 8,h10 seem on September lb, 1978, prior to cycling to purge containment after the shutdown. It can, therefore, be concluded that centainment integrity was not violated during plant operation since the total leak rate to atmosphere would have been h8,695.9 scem. The purge valves were repaired during the 1978 refueling outage as were other valves and mechanical seals to bring the total leak rate within the 0.6 La limit. A special report (as required by Technical Specification 5 9.3.e) vill be submitted within 90 days of the leak test comple-tion date. | Since the containment purge valves were the largest contributors to this leak-age, 1h3,002.17 seem and the leakage of the purge valves was verified to be 8,h10 seem on September lb, 1978, prior to cycling to purge containment after the shutdown. It can, therefore, be concluded that centainment integrity was not violated during plant operation since the total leak rate to atmosphere would have been h8,695.9 scem. The purge valves were repaired during the 1978 refueling outage as were other valves and mechanical seals to bring the total leak rate within the 0.6 La limit. A special report (as required by Technical Specification 5 9.3.e) vill be submitted within 90 days of the leak test comple-tion date. | ||
o y}} | o y}} | ||
Revision as of 19:45, 1 February 2020
| ML19270E896 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/22/1978 |
| From: | Connolley J, Gordon Peterson OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML19270E890 | List: |
| References | |
| LER-78-040-03L, LER-78-40-3L, NUDOCS 7901030110 | |
| Download: ML19270E896 (2) | |
Text
Nf4C PORM 066 U.S. NUCLEAR REGULATORY COMMISSION (7, 77)' ,, \. LICENSEE EVENT REPORT g CONTROL BLOCX; l 1
l l I l 1 6
lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORNIATION) 7 oji 8 9 lUlElFlClSl1l@l0lol0l0lolol0l0lo o l o l@l hl 1l ll ll 1l@l LICENSEE CODE 14 15 LICENSE NUMBER 25 ;8 LICENSE TYPE JO l
57 CATid l@
CON'T o11 5a7RCE I L @l 0 l 5 l 0 j 0 l 0 l 2 l 8 l 5 }gl1 l 210 l 5 [ 7 l 8 @l1 l 2 l2 l 217 l8 l@
7 4 60 61 CCCXET NUM8ER 68 69 EVENT CATE 74 75 REPCRT CATE 80
_ EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h o 2 l During the performance of the type B and C containment leak rate tests during the l o a l 1978 refueling outage, it was noted that the total leakage exceeded the 0.6 La limit l 0 44 lof 62,951 sces. I o s ! l 0 6 l 017 l l ata l I 7 $ 9 SO SYSTEM CAUSE CAUSE COMP. VALVE CCDE CCOE SU8CCDE COMPONENT CCDE SUSCCOE SUSCCCE 7
oI9 8
i S l Djh Wh IB lh l Vl Al Ll VI 'l XIh Wh l DIh 9 10 11 12 13 18 19 20
,_ SECUENTIAL OCCURRENCE REPORT REVislCN LE R. Ro EVENT YE AR REPORT NC. CODE ~YPE NO.
@ aEPoat 17 18 I l-l lo lh lo i I/l l 01, I ILI l-1 I ol
_ 21 22 23 24 26 27 28 23 30 31 J2 ACTION . FUTURE EFFECT SHUTOOWN ATTACHMENT NPR O-4 PRIME COMP, COMPONENT TAKEN ACTICN ON PLANT METHOO HOURS d SUSMITTED PCRM bu8. SUPPLIE R MANUFACTURER lo 3J l@lz l@34 W@ - Iz l@ Io lo l0 lo l lY@ l42N I@ l Alh l Xl 9l ol Olh 35 36 3 e. 40 41 43 44 47 CAuSE cESCRIPTION AND CORRECTIVE ACTIONS 1 eo lThe penetrations that exhibited excess leakage were recaired and the total containmentI ii1 l leakage was reduced to below the 0.6 La (62.oS1 seem) limit. A modifientic, +n W -4
, ;tainment purge valves was completed this refueling outage which should reduce the leak +
,3 l age attributable to these valves, even if after repeated cycling. Quarterly leakage I g,, ; tests will continue to be performed on the containment purge valve penetrations. I 7 8 9 so "YE
$ sPowER oTHER STATUS @ ciSCoNRv ciScovERY cESCRiPrioN h lt !5 l H l@ l 0l ol ol@lRefueline Shutdevd l Bl@l Refueline leak rate test l ACTIVITY CO TENT mELEASEC CFRELEASE AMOUNT C8 ACTtVITY LOCATICN CF RELEASE l l NA l 164 I3 l Z l h lZ l@l NA 1
7 10 11 44 45 30 ageSCNNEL EXPCSURES NUV8Ea ypg O ESCRIPTICN
- 7 ii7 8 9 loIolol@lzl@l n 11 1: 13 BC i
PERSCNNEL N; BRIES ,
NLV6Em OESCR:PT:C N ','
& ilololol@l u i
790103o\\o
- S$ cP :R = " .Ca , CmTv ra TV'E 05 SCRwTION V
?
I9!l2i NA 7 3, 3 'C 40 PU B LICITv ygcggggggv 1 SUED OESCP6PTION
- 3l W @l n M3/ ! !I i ' IIII i
7 3 9 10 /M 93 59 ' %
NAME OF PRi? ARER J. Connolley/G. Petersen 7wCNE:
Lo2 h26 holl
LER 78-Oh0 Omaha Public Power District Fort Calhoun Station Unit No. 1 Docket Ilo. 05000285 Attachment Ilo.1 Safety Analysis The air leakage tests performed during the 1978 refueling outage indicated a total leaka ge rate of h81,30h.27 seen of this leakage. However, only 183,288.07 scem can be attributed to direct containment atmosphere leakage.
Since the containment purge valves were the largest contributors to this leak-age, 1h3,002.17 seem and the leakage of the purge valves was verified to be 8,h10 seem on September lb, 1978, prior to cycling to purge containment after the shutdown. It can, therefore, be concluded that centainment integrity was not violated during plant operation since the total leak rate to atmosphere would have been h8,695.9 scem. The purge valves were repaired during the 1978 refueling outage as were other valves and mechanical seals to bring the total leak rate within the 0.6 La limit. A special report (as required by Technical Specification 5 9.3.e) vill be submitted within 90 days of the leak test comple-tion date.
o y