ML18101A912

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Forwards LER 95-016 Re 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 August 18, 1995 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 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.

Sincerely,

~c~

Clay C. Warren General Manager -

Salem Operations Attachment A SORC Mtg.95-092 MNNtcp C Distribution LERFile

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The ~'O\\*er is in ~\mr ltmds. 9508280010 950818 PDR ADOCK 05000272 jeJd I S PDR 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.