ML20071E686
| ML20071E686 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/03/1983 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 091, 91, NUDOCS 8303100342 | |
| Download: ML20071E686 (5) | |
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a VinorwrA ELECTRIC AND POWER COMPANY Ricnwoxn,VinorwrA 20261 1
W.L,StewAmr wuI.".S",".1'7...
March 3, 1983 Mr. Harold R. Denton, Director Serial No. 091 Office of Nuclear Reactor Regulation GLD:cdk:0325C l
-Attn: Mr. Robert A. Clark, Chief Docket No. 50-339 Operating Reactors Branch No. 3 Division of Licensing Licence No. NPF-7 U. S. Nuclear Regulatory Commission Washin9 on, D.C.
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Gentlemen:
RELOAD INFORMATION FOR CYCLE 3 NORTH ANNA NUCLEAR POWER STATION UNIT NO. 2 i
North Anna Unit No. 2 is scheduled to couplete its second cycle of operation on March 31, 1983, and will go into an outage for refueling. The l
purpose of this letter is to advise you of our plans for the Cycle 3 reload core and to transmit to you the Core Surveillance Report containing specific nower distribution limits applicable for Cycle 3 operation.
The Cycle 3 reload core was analyzed in accordance with the methodology documented in Westinghouse Topical Report WCAP-9272 catitled " Westinghouse Reload Safety Evaluation Methodology". The results of this analysis indicated i
that no key analysis parameters would become more limiting during Cycle 3 operations than the values assumed in the currently applicable safety analysis. Further, the analysis demonstrated that the current Technical Specifications, as approved through Operating License Amendment No. 28, are l
appropriate and rcquire no additional changes.
l The analyses necessary to support Cycle 3 operation have been performed and reviewed by our technical staff, using the Westinshouse methodology anu analysis. techniques.
In addition, a review has been performed by both the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control staff.
It has been determined that no unreviewed safety questions as defined in 10 CFR 50.59 will exist as a result of the Cycle 3 reload core. provides the Core Surveillance Report containing the specific f
Cycle 3 values for Fxy and the axial power distribution surveillance limit, Pm. This report is being provided as required by North Anna Unit No. 2 Technical Specification 6.9.1.10 and is based on the recently approved total l
peaking factor (Fq) limit of 2.20.
l 8303100342 830303 PDR ADOCK 05000339 P
w OiWii st.BCMC AND POWEB COMMY TO Mr. Harold R. Denton, Director Verification of the reload core will be perforned through a start-up physics testing program. Unless otherwise indicated, this prograra will be consistent with the program proposed for North Anna Unit No. 2 in the Vepco letter from Mr. R. H. Leasburg to you dated April 8,1982, Serial No. 204.
This letter is provided for your information. However, should you have questions, please contact us at your earliest convenience.
Very truly yours, n
\\h W. L. Stewart Attachraent (1) ' Core Surveillance Report for North Anna 2, Cycle 3 cc: Mr. Jaraes P. O'Reilly, Regional Administrator Region II 1
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ATTACHMENT 1 Core Surveillance Report North Anna 2, Cycle 3
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1 of 2 TABLE 1 2.20 NORTH AMMA UNIT 2, CYCLE 3 CORE SURVEILLANCE LIMITS, TS =
I. The T-xy limits for RATED THERMAL POWER within specific core planes shall bei 1.
Txy-RTP S 1.71 for all core planes containing bank "D" control rods, and 2.
Txy-RTP 5 1.65 for all unrodded core planes between 15 % and 25 % of core height, or 3.
Txy-RTP S 1.60 for all unrodded core planes between 25 % and 55 % of core height, or 4.
Txy-RTP 5 1.65 for all unrodded core planes between 55 % and 85 % of core height.
II. The axial power distribution surveillance threshold power level shall bei 1.
Pm = 100% of RATED THERMAL POWER.
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