ML18101A912

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Difference Between Containment Design Parameters & Accident Analysis
ML18101A912
Person / Time
Site: Salem PSEG icon.png
Issue date: 08/18/1995
From: Warren C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18101A914 List:
References
NUDOCS 9508280010
Download: ML18101A912 (2)


Text

e OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk SALEM GENERATING STATION LICENSE NO.

DPR-70 DOCKET NO.

50-272 UNIT NO.

1 LICENSEE EVENT REPORT NO. 95-016-0 August 18, 1995 This Licensee Event Report entitled "Difference Between Containment Design Parameters and Accident Analysis," is being submitted pursuant to the requirements of the Code of Federal Regulations IOCFR50.73(a)(2)(ii). Attachment A contains those commitments which are currently outstanding related to this issue.

Attachment A SORC Mtg.95-092 MNNtcp C

Distribution LERFile

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Sincerely,

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Clay C. Warren General Manager -

Salem Operations The ~'O\\\\*er is in ~\\mr ltmds.

9508280010 950818 PDR ADOCK 05000272 S

PDR jeJd I 95-2168 RE. 6/94

ATTACHMENT A PSE&G Commitments forLER 272/95-016-0 The following items represent PSE&G's commitments made to the Nuclear Regulatory Commission related to LER 272/95-016-0. The commitments are as follows:

One Time Actions

1.

Corrective actions, as necessary, will be developed after completion of a root cause determination and analysis of this issue on plant equipment and design basis.

2.

The plant will not transition from mode 5 to mode 4 until the issues associated with this LER are resolved.

3.

Provide a supplement to this LER on or before December 15, 1995.