ML20078N434
| ML20078N434 | |
| Person / Time | |
|---|---|
| Site: | Waterford |
| Issue date: | 12/02/1994 |
| From: | Burski R ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20078N436 | List: |
| References | |
| W3F1-94-0195, W3F1-94-195, NUDOCS 9412060281 | |
| Download: ML20078N434 (2) | |
Text
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R. F. Burski r.
I W3F1-94-0195 A4.05 PR December 2,1994 U.S. Nuclear Regulatory Commission Attn: Document Control Desk l
Washington, D.C.
20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Supplemental Information to Technical Specification Change Request NPF-38-155 Gentlemen:
By letter dated August 11, 1994, Waterford 3 proposed a change that would remove cycle-specific variables from the Technical Specifications (TS) and control them under a new document called the Core Operating Limits Report (COLR).
The proposed change was consistent with the technical specification line-item improvement guidelines provided by the NRC in Generic Letter (GL) 88-16, " Removal of Cycle-Specific Parameter Limits From Technical Specifications," dated October 3, 1988.
However, for reasons described in the initial request, the proposed change took exception to the generic guidance provided in the revised Combustion Engineering Standard Technical Specifications (STS) NUREG 1432.
Specifically, NUREG 1432 requires the Administrative Controls section of the TS to include a listing of the analytical methods used to determine the core operating limits (i.e., the NRC approved methodologies).
The Waterford 3 proposed TS 6.9.1.11, included the requirement to use only NRC approved j
analytical methods, but the methods were listed in Section IV of the COLR and j
not listed in the TS.
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Supplemental Information to Technical Specification Change Request NPF-38-155 W3F1-94-0195 j
Page 2 December 2, 1994 Waterford 3 has reconsidered and formally withdraws the exception to the above stated requirement. Any future change regarding this exception will be-
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pursued through the Combustion Engineering Owners Group on a generic basis.
Thus, the NRC analytical methods in Section IV of the COLR will be duplicated in the proposed change as indicated on the attached.
i The withdrawal of the previously requested exception will have no impact on the safety and significant hazards determination provided with the original 3.
submittal.
I Should you have any questions or comments concerning this request, please contact Paul Caropino at (504)739-6692.
Very truly yours, 9
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l lH R.F. Burski Director Nuclear Safety RFB/PLC/ssf Attachment cc:
L.J. Callan, NRC Region IV C.P. Patel, NRC-NRR R.B. McGehee N.S. Reynolds NRC Resident inspectors Office Administrator Radiation Protection Division (State of Louisiana)
American Nuclear Insurers 1
.