05000354/LER-1996-028, Forwards LER 96-028-00,submitted Pursuant to Requirements of 10CFR50.73(a)(2)(v).Commitments Listed: Difference between revisions

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| Title = Forwards LER 96-028-00,submitted Pursuant to Requirements of 10CFR50.73(a)(2)(v).Commitments Listed
| Title = Forwards LER 96-028-00,submitted Pursuant to Requirements of 10CFR50.73(a)(2)(v).Commitments Listed
| Plant =  
| Plant =  
| Reporting criterion =  
| Reporting criterion = 10 CFR 50.73(a)(2)(v)
| Power level =  
| Power level =  
| Mode =  
| Mode =  
| Docket = 05000354
| Docket = 05000354
| LER year = 2096
| LER year = 1996
| LER number = 28
| LER number = 28
| LER revision =  
| LER revision = 0
| Event date =  
| Event date =  
| Report date =  
| Report date =  
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    .> 'O PSEG                                                                                                     l Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit                                                                                     i JAN 201997                                             i LR-N97023 l
~
U.S. Nuclear Regulatory Commission                                                                         I Document Control Desk                                                                                       i Washington, DC 20555
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit JAN 201997 i
LR-N97023 U.S. Nuclear Regulatory Commission I
Document Control Desk i
Washington, DC 20555


==Dear Sir:==
==Dear Sir:==
HOPE CREEK GENERATING STATION DOCKET NO. 50-354 UNIT NO. 1 I
HOPE CREEK GENERATING STATION DOCKET NO. 50-354 UNIT NO. 1 I
LICENSEE EVENT REPORT NO. 96-028-00 This Licensee Event Report entitled, " Potential Loss of Containment Integrity Due to Water Hammer in Drywell Cooler Piping," is being submitted pursuant to the requirements of 10CFR50.73 (a) (2) (v) .
LICENSEE EVENT REPORT NO. 96-028-00 This Licensee Event Report entitled, " Potential Loss of Containment Integrity Due to Water Hammer in Drywell Cooler Piping," is being submitted pursuant to the requirements of 10CFR50.73 (a) (2) (v).
T Si   erely, d
T Si
pMM r   Bezilla Ge eral Manager -
: erely, d
Hope Creek Operations Attachment JPP SORC Mtg. 97-003 C           Distribution h
pMM r
LER File
Bezilla Ge eral Manager -
                                                                                                          't 6b
Hope Creek Operations Attachment JPP SORC Mtg. 97-003 C
                                                                                                    /
Distribution LER File h
240079 9701240300 970120 PDR     ADOCK 05000354 S                         PDR     ,..
't 6b
The rwerisin >uurlunds.
/
240079 9701240300 970120 PDR ADOCK 05000354 S
PDR The rwerisin >uurlunds.
95?168 REV M4
95?168 REV M4


JAN 201997 Document Control Desk                   LR-N97023 Attachment A The following items represent commitments that Public Service Electric & Gas (PSE&G) made to the Nuclear Regulatory Commission (NRC) relative to this LER (354/96-028-00). The commitments are as follows:
JAN 201997 Document Control Desk LR-N97023 Attachment A The following items represent commitments that Public Service Electric & Gas (PSE&G) made to the Nuclear Regulatory Commission (NRC) relative to this LER (354/96-028-00).
On 12/20/96, administrative controls were implemented to prevent the defeating of the drywell cooler isolation interlocks in post LOCA conditions. To addrecs the water hammer issue, aither:   1) revisions to the Hope Creek EOPs will be made to address overriding of the containment isolation interlocks of the chilled water system; or 2) the affected containment penetrations will be reanalyzed or modified to accommodate the water hammer loads. Final implementation of corrective actions to resolve this issue will be completed by the end of the next refueling outage (RF07).
The commitments are as follows:
On 12/20/96, administrative controls were implemented to prevent the defeating of the drywell cooler isolation interlocks in post LOCA conditions.
To addrecs the water hammer issue, aither:
: 1) revisions to the Hope Creek EOPs will be made to address overriding of the containment isolation interlocks of the chilled water system; or 2) the affected containment penetrations will be reanalyzed or modified to accommodate the water hammer loads.
Final implementation of corrective actions to resolve this issue will be completed by the end of the next refueling outage (RF07).
Engineering evaluations of the impact on Hope Creek of the water hammer, two-phase flow and over-pressurization issues discussed in Generic Letter 96-06 have been completed and the results will be transmitted to the NRC (in the response to Generic Letter 96-06) by 1/28/97.
Engineering evaluations of the impact on Hope Creek of the water hammer, two-phase flow and over-pressurization issues discussed in Generic Letter 96-06 have been completed and the results will be transmitted to the NRC (in the response to Generic Letter 96-06) by 1/28/97.
}
}

Latest revision as of 07:13, 12 December 2024

Forwards LER 96-028-00,submitted Pursuant to Requirements of 10CFR50.73(a)(2)(v).Commitments Listed
ML20133P504
Person / Time
Site: Hope Creek 
Issue date: 01/20/1997
From: Bezilla M
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20133P508 List:
References
LR-N97023, NUDOCS 9701240300
Download: ML20133P504 (2)
v • d • e


LER-1996-028, Forwards LER 96-028-00,submitted Pursuant to Requirements of 10CFR50.73(a)(2)(v).Commitments Listed
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(v), Loss of Safety Function
3541996028R00 - NRC Website
v • d • e

text

-

.> 'O PSEG

~

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit JAN 201997 i

LR-N97023 U.S. Nuclear Regulatory Commission I

Document Control Desk i

Washington, DC 20555

Dear Sir:

HOPE CREEK GENERATING STATION DOCKET NO. 50-354 UNIT NO. 1 I

LICENSEE EVENT REPORT NO. 96-028-00 This Licensee Event Report entitled, " Potential Loss of Containment Integrity Due to Water Hammer in Drywell Cooler Piping," is being submitted pursuant to the requirements of 10CFR50.73 (a) (2) (v).

T Si

erely, d

pMM r

Bezilla Ge eral Manager -

Hope Creek Operations Attachment JPP SORC Mtg.97-003 C

Distribution LER File h

't 6b

/

240079 9701240300 970120 PDR ADOCK 05000354 S

PDR The rwerisin >uurlunds.

95?168 REV M4

JAN 201997 Document Control Desk LR-N97023 Attachment A The following items represent commitments that Public Service Electric & Gas (PSE&G) made to the Nuclear Regulatory Commission (NRC) relative to this LER (354/96-028-00).

The commitments are as follows:

On 12/20/96, administrative controls were implemented to prevent the defeating of the drywell cooler isolation interlocks in post LOCA conditions.

To addrecs the water hammer issue, aither:

1) revisions to the Hope Creek EOPs will be made to address overriding of the containment isolation interlocks of the chilled water system; or 2) the affected containment penetrations will be reanalyzed or modified to accommodate the water hammer loads.

Final implementation of corrective actions to resolve this issue will be completed by the end of the next refueling outage (RF07).

Engineering evaluations of the impact on Hope Creek of the water hammer, two-phase flow and over-pressurization issues discussed in Generic Letter 96-06 have been completed and the results will be transmitted to the NRC (in the response to Generic Letter 96-06) by 1/28/97.

}

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