ML20203C473
| ML20203C473 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/05/1999 |
| From: | Ewing E ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20203C478 | List: |
| References | |
| W3F1-99-0021, W3F1-99-21, NUDOCS 9902120075 | |
| Download: ML20203C473 (3) | |
Text
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=Entergy w:n,_
Entergy Operations, Inc.
Tel 504 739 6242 Early C. Ewing, lil L. e Safety & Regulatory Attwrs W3F1-99-0021 A4.05 PR February 5,1999 1
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Technical Specification Change Request NPF-38-174, Revision 2 I
Reactor Trip Circuit Breaker Surveillance Interval Extension Gentlemen:
Entergy submitted to the NRC Staff Technical Specification Change Request (TSCR)
NPF-38-174 by Letter W3F1-96-0004 dated July 17,1996 for Waterford 3. This request constituted a lead plant submittal, proposed by Entergy on behalf of the Combustion Engineering Owners Group (CEOG). CE NPSD-951,' Reactor Trip Circuit Breakers Surveillance Frequency Extension," was submitted to the Staff for review by the CEOG. The Staff requested additionalinformation by Letter dated September 8,1998. Letter W3F1-98-0174, dated October 22,1998 provided j
answers to these questions. Based on conversations with Mr. Iqbal Ahmed of the NRC Staff, Entergy submitted the revised pages to replace the original TSCR in its entirety. These were provided by Letter W3F1-99-0001, dated January 12,1999.
On January 25,1999, Mr Ahmed recommended editorial changes to Note 11 and the Bases. Based on this conversation, Entergy is submitting the attached revised pages to replace the two affected pages (page 3/4 3-12a and B 3/4 3-1a). The other pages in the January 12,1999 submittal remain unchanged.
Entergy has concluded that this change is bounded by the No Significant Hazards Evaluation submitted in the July 17,1996 license amendment request. Therefore, the original No Significant Hazards Evaluation continues to be applicable.
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Technical Specification Change Request NPF-38-174, Revision 2 Reactor Trip Circuit Breaker Surveillance Interval Extension W3F1-99-0021
- Page 2 February 5,1999 Should you have any questions or comments concerning this request, please contact Cud Taylor at (504) 739-6725.
Very truly yours, k.
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,,c E.C. Ewing Director Nuclear Safety & Regulatory Affairs ECE/ CWT /ssf Attachments:
NPF-38-174, Revision 2, Replacement Pages
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cc:
E.W. Merschoff, NRC Region IV l
C.P. Patel, NRC-NRR J. Smith N.S. Reynolds NRC Resident inspectors Office Administrator Radiation Protection Division (State of Louisiana)
American Nuclear Insurers l
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i NPF-38-174, Revision 2 i
ATTACHMENT A j
REPLACEMENT PAGES i
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