ML20153E612

Advises of Plans for Cycle 5 Reload Core & Transmits Core Surveillance Rept Containing Specific Power Distribution Limits Applicable for Cycle 5 Operation

ML20153E612
Person / Time
Site:	North Anna
Issue date:	02/20/1986
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Rubenstein L Office of Nuclear Reactor Regulation
References
86-099, 86-99, NUDOCS 8602250077
Download: ML20153E612 (5)

Text

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VtNoixtA ELECTRIC AND POWHH COMi*ANY N ICll M O N D. VI NG I N I A M 832 61 W. L. SrMWART wY.5.S'[.'.",1.

February 20, 1986 Mr. Harold R. Denton, Director Serial No.86-099 Office of Nuclear Reactor Regulation E&C/ JOE: ace Attn: Mr. Lester S. Rubenstein, Director Docket No. 50-339 PWR Project Directorate #2 License No. NPF-7 i

Division of PWR Licensing-A J

U.S. Nuclear Regulatory Commission Washington, D.C. 20555 i

Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 2 i

I 5 LOAD INFORMATION FOR CYCLE 5 1

North Anna Unit No. 2 is scheduled to complete its fourth cycle of operation on March 14, 1986, and will go into an outage for refueling.

l The purpose of this letter is to advise you of our plans for the Cycle 5 reload core and to transmit to you the Core Surveillance Report containing l

specific power distribution limits applicable for Cycle 5 operation.

l The Cycle 5 reload core was analyzed in accordance with the methodology documented in Vepco topical VEP-FRD-42, Rev. 1, " Reload Nuclear Design Methodology", using NRC approved codes as referenced in the topical. This i

methodology is consistent with that documented in Westinghouse Topical Report WCAP-9272, entitled " Westinghouse Reload Safety Evaluation Methodology." These analyses were performed and reviewed by our technical staff. The results of these analyses indicated that no key analysis l

parameters would become more limiting during Cycle 5 operations than the values assumed in the currently applicable safety analyses. Further, the j

analyses demonstrated that the Current Technical Specifications, as approved through Operating License Amendment No. 61 are appropriate and require no additional changes.

l For the control rod reactivity worth determination using the rod swap

{

technique for previous North Anna cycles, the NRC has required a comparison of the Vepco prediction "with the prediction by the i

organization performing the safety analysis", as stated in the NRC letter of November 7,1980, R. L. Tedseco (NRC) to W. N. Thomas (Vepco), subject

" Acceptance for Referencing of Topical Report VEP-FRD-36 ' Control Rod Reactivity Worth Determination by Rod Swap Technique'."

Since NRC i

approved Vepco codes were used for both the reload analyses and the l

onalyses supporting control rod reactivity worth determination with the j

rod swap techrique, this comparison is not required for Cycle 5 and future cycles using the Vepco methodology.

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Viuonwu Euctuic axn POWEB COMPANY TO 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 question as defined in 10 CFR 50.59 will exist as a result of the Cycle 5 reload core. provides the Core Surveillance Report containing the specific Cycle 5 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 6.9.1.7 and is based on the current total peaking factor (F q) limit of 2.20.

This letter provided for your information and planning. However, should you have questions, please contact us at your earliest convenience.

Very truly yours, J

(

(QO.Sq

5..

V. L. Stewart Attachment 1.

Core Surveillance Report for North Anna 2, Cycle 5 cc:

Dr. J. Nelson Grace Regional Administrator 57C Region II Mr. Morris W. Branch h7C Resident Inspector North Anna Power Station Mr. Leon B. Engle NRC North Anna Project Mcnager PWR Project Directorate (12 Division of PWR Licensing-A

T ATTACllMENT 1 i

NORTil ANNA UNIT 2, CYCLE 5 l

C_AOC CORE SURVEILLANCE REPORT FOR FQ = 2.20 r

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Page 1 of 2 TABLE 1 NORTH ANNA UNIT 2, CYCLE 5 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 1.65 for all unrodded core planes between 15% and 36%

of core height, or 3.

Fxy-RTP $ 1.62 for all unrodded core planes between 36% and 85% of core height.

II. The axial power distribution surveillance threshold power level shall Le:

1.

Pm = 100% of RATED THERMAL POWER.

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