ML20093H709
| ML20093H709 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/18/1984 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, John Miller Office of Nuclear Reactor Regulation |
| References | |
| 415, NUDOCS 8407250248 | |
| Download: ML20093H709 (5) | |
Text
I
.m VIRGINIA ELECTHIC AND Powen CO>iPANY Ittennoxn,VInorx1A uneGI W.L. STEWART 3[c,,,1,'7,",',""',,n, July 18, 1984 Mr. Harold R. Denton, Director Serial No. 415 Office of Nuclear Reactor Regulation PSE/J0E:k1h:2005N Attn: Mr. James R. Miller, Chief Docket No. 50-339 Operating Reactors Branch No. 3 License No. NPF-7 Division of Licensing V. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 2 RELOAD INFORMATION FOR CYCLE 4 North Anna Unit No. 2 is scheduled to complete its third cycle of operation on August 17, 1984, and will go into an outage for refueling.
The purpose of this letter is to advise you of our plans for the Cycle 4 reload core and to transmit to you the Core Surveillance Report containing specific power distribution limits applicable for Cycle 4 operation.
The Cycle 4 reload core was analyzed in accordance with the methodology documented in Westinghouse Topical Report WCAP-9272 entitled " Westinghouse Reload Safety Evaluation Methodology." The results of this analysis indicated that no key analysis parameters would become more limiting during Cycle 4 operation 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. 40 are appropriate and require no additional changes.
The analyses necessary to support Cycle 4 operation have been performed and reviewed by our technical staff, using the Westinghouse inethodology and analysis techniques.
In addition, a review has been performed by both the Station Nuclear Safety and Operating Connittee 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 4 reload core. provides the Core Surveillance Report containing the specific Cycle 4 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 current total peaking factor (F )
O limit of 2.20.
I B407250248 840718 fg PDR ADOCK 05000339 P
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- vi iwii rtscr ic ixo rown couei=r To Mr. Harold R. Denton Director This letter is provided for your information and planning. However, should you have questions, please contact us at your earliest convenience.
Very trul yo,urs, hl tub"7,.
W. L. Stewart V Attachment
'(1) Core Surveillance Report for North Anna 2, Cycle 4 cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. Leon B.. Engle NRC Project Manager - North Anna Operating Reactors Branch No. 3 Division of Licensing Mr.. M. W. Branch NRC Resident Inspector North Anna Power Station 4
4 ATTACHMENT 1 CORE SURVEILLANCE REPORT NORTH ANNA 2, CYCLE 4 e
1 of 2 TABLE 1 NORTH ANNA UNIT 2, CYCLE 4 CORE SURVEILLANCE LIMITS, FQ = 2.20 I.
The F-xy limits for RATED THERMAL POWER within specific core planes shall be:
1.
Fxy-RTP s 1.71 for all core planes containing bank "D" control rods, and 2.
Fxy-RTP s 1.61 for all unrodded core planes.
II. The axial power distribution surveillance threshold power level shall be:
1.
Pm = 100% of RATED THERMAL POWER.
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