ML20248B267
| ML20248B267 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/25/1989 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20248B273 | List: |
| References | |
| IPN-89-059, IPN-89-59, TAC-71938, NUDOCS 8910030148 | |
| Download: ML20248B267 (4) | |
Text
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September 25,1989 IPN-89-059 U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C. 20555 Attn: Document Control Desk
Subject:
in_dian Point 3 Nuclear Power Plant Docket No. 50-286 Cycle 7 Startup Report e
References:
1.
Letter from Mr. J. D. Neighbors to Mr. J. C. Brons, dated June 22, 1989, entitled: " Corrections To Amendment No. 86 For Indian Point 3 (TAC No. 71938)."
2.
Letter from Mr. J. D. Neighbcts to Mr. J. C. Brons, dated June 6, 1989, entitled: " Issuance of Amendment No. 86 (TAC No.
71938)."
3.
Letter from Mr. J. C. Brons to the NRC, dated May 23,1989, entitled: " Proposed Changes to Technical Specifications Regarding the Transition to Westinghouse 15 x 15 Vantage 5 Fuel.
4.
Letter from Mr. J. C. Brons to the NRC, dated May 5,1989, entitled: Proposed Changes to Technical Specifications Regarding the Transition to Westinghouse 15 x 15 Vantage 5 Fuel."
5.
Letter from Mr. J. C. Brons to the NRC, dated February 15,1989, entitled: " 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."
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6.
Letter from Mr. J. C. Brons to the NRC, dated February 2,1989,
. entitled: " Proposed Changes to Technical Specifications -
Regarding the Transition to Westinghouse 15 x 15 Vantage 5 Fuel =
and RTD Bypass Manifold Elimination Modification."
7.
Letter from Mr. J. C. Brons to the NRC, dated January 20,1989, entitled: " Proposed Changes to Technical Specifications Regarding the Transition to Westinghouse 15 x 15. Vantage 5 Fuel and RTD Bypass Manifold Elimination Modification."
Dear Sir:
During the. Cycle 6/7 Refueling Outage the Authority started the transition from the 15 x 15
~ optimized fuel assembly (OFA) design to a 15 x 15 Vantage 5 fuel design. References (3),' (4), (5),
l (6) and (7) provided the NRC the proposed technical specifications and supplemental information -
L regarding the transition to Vantage 5 fuel. In References (1)' and (2) the NRC issued Amendment 86 to the Indian Point 3 (IP-3) Technical Specifications reflecting this transition in fuel design. In accordance with IP-3 Technical Specification 6.9.1.1, "Startup Report," Attachment I contains the Cycle 7 startup physics test r6pM.-
Information concerning two other modifications performed during the Cycle 6/7 Refueling Outage is also attached. Attachment ll providesinformation concerning the replacement of the four (4) steam generators. Attachment til contains a discussion of the of the High Pressure Turbine Optimization Program.
If you have any questions regarding this matter, please contact Mr. P. Kokolakis of my staff.
l Very truly yours, m
. XL
'd John C. Brons Executive Vice President Nuclear Generation
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cc: U. S. Nuclear Regulatory Com. mission 475 Allendale Road King of Prussia, PA 19406 Resident inspector's Office l
Indian Point 3 l'
U.S. Nuclear Regulatory Commission -
P.O. Box 337 Buchanan, New York 10511 Mr. J. D. Neighbors, Sr. Project Manager Project Directorate 1-1 Division of Reactor Projects-l/II U.S. Nuclear Regulatory Commission Mail Stop 14B2 Washington, D.C. 20555
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8 ATTACHMENT ITO lPN-89-059 CYCLE 7 STARTUP PHYSICS TEST REPORT -
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NEW YORK POWER AUTHORITY INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 DPR - 64
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