ML093440859
| ML093440859 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 02/02/1989 |
| From: | Brons J Power Authority of the State of New York |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML093440860 | List: |
| References | |
| IPN-89-009, NUDOCS 8902130103 | |
| Download: ML093440859 (3) | |
Text
123 Main Street White Plains, New Yor001 914 681.6240
^NewYorkPower 4
Authority February 2, 1989 IPN-89-009 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Mail Station Pl-137 Washington, D.C.
20555
Subject:
Reference 1.
John C. Brons Executive Vice President Nuclear Generation Indian Point 3 Nuclear Power Plant Docket No. 50-286 RTD Bypass Manifold Elimination Modification Details JLetter dated, January 20, 1989, from J. C. Brons to NRC "Proposed Changes To Technical
.Specifications Regarding The Transition To Westinghouse 15 x 15 Vantage 5 Fuel and RTD Bypass Manifold Elimination Modification."
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 hot and cold leg temperature measurement system that will replace the existing RTD bypass manifold temperature measurement system.
The new system will employ thermowell mounted RTDs installed directly into the hot and cold leg loop piping. The complexity of the bypass manifold piping has been a concern of the Authority for some time. Excessive maintenance and housekeeping activities are necessary as a result of system leakage.
These maintenance and housekeeping activities are a significant source of occupational radiaiton exposure. Experience at other Westinghouse plants indicates that using thermowell mounted RTDs minimizes leakage and; therefore, maintenance and housekeeping activities.
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In Reference 15 the Authority committed to provide details of the RTD bypass manifold elimination modification for staff review in a subsequent submittal. Accordingly, transmitted as Attachment A and B to this letter, respectively, are:
Four (4) copies of WCAP-12009, Revision 1. "RTD Bypass Elimination Licensing Report for Indian Point Unit 3" (Proprietary), dated January. 1989.
Four (4) copies of WCAP-12037, "RTD Bypass Elimination Licensing Report for Indian Point Unit 3" (non-proprietary), dated January, 1989.
Attachment C is a Westinghouse authorization letter (CAW-89-001). 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 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 Commission's regulations. Correspondence with respect to the proprietary aspects of the Application for Withholding or the supporting Westinghouse affidavit should refer to CAW-89-0O01 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.
Attachments D and E consist of clarifying information typical of that which the staff has requested from other licensees that have undertaken the RTD bypass manifold elimination modification.
The Authority believes that the RTD modification does not involve an unreviewed safety question or a Technical Specification change. The details of the RTD modification contained in the attachments to this letter are provided to support the license amendment and Technical Specification changes for the Cycle 6/7 reload transmitted in Reference 1.
Should you or your staff have any questions regarding this matter, please contact Mr. P. Kokolakis of my staff.
Very truly yours, onC. Brons ecutive Vice President Nuclear Generation cc: Mr. Jospeh D. Neighbors, Senior Poject Manager Project Directorate I-i 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