05000354/LER-1996-015, Forwards LER 96-015-00 Re Potential to Operate in Unanalyzed Condition Due to Design Deficiency in Overboard Discharge Line.Commitments Listed as Submitted

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Forwards LER 96-015-00 Re Potential to Operate in Unanalyzed Condition Due to Design Deficiency in Overboard Discharge Line.Commitments Listed as Submitted
ML20111C500
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 05/10/1996
From: Reddemann M
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20111C502 List:
References
LR-N96129, NUDOCS 9605160209
Download: ML20111C500 (2)


LER-2096-015, Forwards LER 96-015-00 Re Potential to Operate in Unanalyzed Condition Due to Design Deficiency in Overboard Discharge Line.Commitments Listed as Submitted
Event date:
Report date:
3542096015R00 - NRC Website

text

f Q PSEG Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit MAY101996 l LR-N96129 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 .

Dear Sir:

HOPE CREEK GENERATING STATION DOCKET NO. 50-354 UNIT 1 LICENSEE EVENT REPORT 96-015-00 This Licensee Event Report entitled " Potential to Operate in an Unanalyzed condition due to a Design Deficiency in the Overboard Discharge Line" is being submitted pursuant to the requirements of 10CFR50.73 (a) (2) (ii) and 10CFR50.73 (a) (2) (v) .

l Sincerely,

! I h (b frA Mark E. Reddemann General Manager -

Hope Creek Operations RAR/tcp Attachment LER SORC Mtg.96-050 i

l' l

9605160209 960510 l- PDR ADOCK 05000354 l 8 PDR 2 gj 160018 jp I Thepowerisinyourlunds. l 95-2168 REV ES4 i

bocumentControlDesk LR-N96129 Attachment A The following item represents the commitments that Public Service Electric & Gas (PSE&G) made to the Nuclear Regulatory Commission (NRC) relative to this LER (354/96-015-00). The commitments are as follows:

1. A design review and configuration baseline documentation  ;

validation of the Service Water system design basis will l be completed by 6/6/96. Action items will be assigned as appropriate following the completion of the Service Water system design basis review. These action items will be tracked via the Corrective Action Program. Upon completion of the design basis review, the appropriate maximum UHS temperature will be re-evaluated. Technical Specification changes will be applied for if appropriate.

2. As an interim action, the Technical Specification maximum UHS temperature limit has been administratively I lowered to 75 degrees. The limit is imposed as though I l it were the Limiting Condition for Operation. The '

administrative limit will remain in place until the l

appropriate design modifications are complete and/or Technical Specification changes are implemented.

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