ML093440863
| ML093440863 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 02/15/1989 |
| From: | Brons J Power Authority of the State of New York |
| To: | NRC/IRM |
| Shared Package | |
| ML093440864 | List: |
| References | |
| IPN-89-011, IPN-89-11, NUDOCS 8902220529 | |
| Download: ML093440863 (6) | |
Text
123 Main Street i
White Plains, New Yo8601 914 681.6240 O
NewYorkPower 4
Authorily February 15, 1989 IPN-89-011 John C. Brons Executive Vice President Nuclear Generation U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Mail Station P1-137 Washington, D.C.
20555
Subject:
References:
Indian Point 3 Nuclear Power Plant Docket No. 50-286 Plant Specific Improved Thermal Design Procedure (ITDP) Instrument Uncertainty Methodology In Support Of Transition To Westinghouse 15 x 15 Vantage 5 Fuel and RTD Bypass Manifold Elimination - Cycle 7
- 1. Letter IPN-89-007, dated January 20, 1989, from J. C. Brons to the NRC, "Proposed Changes To Technical Specfications Regarding The Transition To Westinghouse 15 x 15 Vantage 5 Fuel and RTD Bypass Manifold Elimination Modification."
- 2. Letter IPN-89-009, dated February 8, 1989, from J. C. Brons to the NRC "RTD Bypass Manifold Elimination Modification Details."
Dear Sir:
The Authority proposed Technical Specification changes associated with the transition to Vantage 5 fuel commencing with the Cycle 7 reload in Reference 1. Those proposed Technical Specification changes, as well as the transient and accident analyses supporting the changes, were developed anticipating installation of the new temperature measurement system that will replace the existing RTD bypass manifold temperature measurement system. Details of this modification were provided for staff review in Reference 2.
The Safety Assessment and supporting documentation included in Reference 1 employ Westinghouse's ITDP instrument uncertainty methodology.
This methodology has been generically approved by the NRC via the staff's concurrence with WCAP-9500-A "Reference Core Report - 17 x 17 Optimized Fuel Assembly," as transmitted in a letter, dated May 22, 1981 from Robert L. Todesco of the NRC to T. M. Anderson of Westinghouse.
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The transition to Vantage 5 fuel and the RTD bypass manifold elimination modification are supported by the ITDP instrument uncertainty methodology. Accordingly, transmitted as Attachments A and B to this letter are:
Four (4) copies of WCAP-12128, "Westinghouse Improved Thermal Design Procedure Instrument Uncertainty Methodology for New York Power Authority -
Indian Point Unit 3" (proprietary), January, 1989.
Four (4) copies of WCAP - 12129, "Westinghouse Improved Thermal Design Procedure Instrument Uncertainty Methodology for New York Power Authority - Indian Point - Unit 3 (non-proprietary), January, 1989.
Attachment C is a Westinghouse authorization letter (CAW-89-013), a Proprietary Information Notice, and an accompanying affidavit.
Since proprietary claims as to Attachment A are asserted by Westinghouse Electric Corporation, those claims are supported by an affidavit signed by Westinghouse.
The affidavit sets forth the basis on which the claim is made that the information may be withheld from public disclosure by the Commission, and addresses the considerations listed in 10 CFR Section 2.790(b)(4).
Accordingly, it is respectfully requested that Attachment A, or in the alternative such portions of Attachment A as the Commission determines to be protected by 10 CFR Section 2.790 as proprietary to Westinghouse, be withheld from public disclosure in accordance with the Commmssion's regulations.
Correspondence with respect to the proprietary aspects of the Application for Withholding or the supporting Westinghouse affidavit should refer to CAW-89-013 and should be addressed to R. A. Wiesemann, Manager, Regulatory and Legislative Affairs, Westinghouse Electric Corporation, P.O.
Box 255, Pittsburgh, PA 15230, with a copy to the undersigned.
Should you or your staff have any questions regarding this matter, please contact Mr. P. Kokolakis of my staff.
Very truly yours, J ohn C. Brons Executive Vice President Nuclear Generation
-3 cc:
Mr. Joseph D. Neighbors, Sr. Proj. Mgr.
Project Directorate I-1 Division of Reactor Projects -
I/II U.S. Nuclear Regulatory Commission Mail Stop 14B2 Washington, D.C.
20555 Resident Inspector's office Indian Point Unit 3 U.S. Nuclear Regulatory Commission P.O. Box 337 Buchanan, NY 10511 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
ATTACHMENT A
.WCAP-12128 "WESTINGHOUSE IMPROVED THERMAL DESIGN PROCEDURE INSTRUMENT UNCERTAINTY METHODOLOGY FOR NEW YORK POWER AUTHORITY -
INDIAN POINT 3,"
(PROPRIETARY), JANUARY, 1989 NEW YORK POWER AUTHORITY INDIAN POINT 3 NUCLEAR POWER PLANT
ATTACHMENT B WCAP-12129 "WESTINGHOUSE IMPROVED THERMAL DESIGN PROCEDURE INSTRUMENT UNCERTAINTY METHODOLOGY FOR NEW YORK POWER AUTHORITY -
INDIAN POINT 3,"
(NON-PROPRIETARY), JANUARY, 1989 NEW YORK POWER AUTHORITY INDIAN POINT 3 NUCLEAR POWER PLANT
ATTACHMENT C MATERIAL RELATING TO PROPRIETARY ASPECTS NEW-YORK POWER AUTHORITY INDIAN POINT 3 NUCLEAR POWER PLANT