ML20090G189
| ML20090G189 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/17/1984 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, John Miller Office of Nuclear Reactor Regulation |
| References | |
| 224A, NUDOCS 8407240262 | |
| Download: ML20090G189 (5) | |
Text
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VIRGINIA ELECTRIC AND Power COMPANY HrcunoNn, VIRGINIA 23261 W.L.SrawAur d*,,"j","",'*, ",[,
July 17, 1984 Mr. Harold R. Denton, Director Serial No. 224A Office of Nuclear Reactor Regulation PSE/GLD:klh:2006N Attn: Mr. James R. Miller, Chief Docket No. 50-338 Operating Reactors Branch No. 3 License No. NPF-4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 1 I
RELOAD INFORMATION FOR CYCLE 5 REDESIGNED CORE North Anna Unit No. 1 is currently in its Cycle 4/5 refueling outage. Vepco
-has completed the fuel examination and core redesign program described to you in our letter dated May 3,1984 (Serial No. 224).
To date, the fuel rod examination program has consisted of vacuum sipping, visual inspection via binoculars and high magnification TV, and use of fuel assembly cleaning equipment developed by Westinghouse Electric Corporation. The results of the examination program will be provided to the NRC in a special report at a later date.
As a result of these inspections, Vepco has developed a revised Cycle 5 reload core design. All irradiated fuel assemblies to be used in the Cycle 5 redesigned core have beea confirmed to be sound through the inspection program.
The Cycle 5 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 these analyses indicated that no key analysis parameters would become more limiting during Cycle 5 operations than the values assumed in the currently applicable safety analyses.
Further, the analyses demonstrated that the current Technical Specifications, as approved through Operating License Amendment No. 58, are appropriate and require no additional changes.
The reload analysis results predict a slightly positive (less than 1 pcm/*F) moderator temperature coefficient for the beginning of cycle, unrodded core condition at hot zero power.
If a positive moderator temperature coefficient is measured during startup physics testing, limits on control rod withrirawal will be implemented, in accordance with Unit No. 1 Technical Specification 3.1.1.4.
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7 vi.ointi ttzernic ino ro vei cour xv ro Mr. Harold R. Denton, Director The analyses necessary to support Cycle 5 operation have been performed and reviewed by our technical staff, using the Westinghouse methodology and 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 10CFR50.59 will exist as a result of the Cycle 5 reload core.
The redesign of the Cycle 5 reload core has made it necessary to revise the previously proposed Cycle 5 Core Surveillance Report limits. Attachment 1 provides the revised 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. 1 Technical Specification 6.9.1.10 and is based on the current total peaking factor (FQ) limit of 2.20.
As discussed with Mr. Leon Engle on July 5,1984, we request an exemption to the normal 60 day advance submittal requirement of Technical Specification 6.9.1.10, to allow use of the revised limits for Cycle 5 startup and subsequent power operation.
Cycle 5 is currently scheduled to begin operation on August 11, 1984.
Should you have questions, please contact us at your earliest convenience.
Very truly you s A
W. L. Stewar Attachment (1) Core Surveillance Report for North Anna 1, Cycle 5 cc: Mr. James P. O'Reilly-Regional Administrator Region II Mr. Leon B. Engle NRC Project Manager - North /,nna Operating Reactors Branch No. 3
' Division of Licensing Mr. M. W. Branch NRC Resident Inspector North Anna Power Station
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ATTACHMENT 1 NORTH ANNA UNIT 1, CYCLE 5 CORE SURVEILLANCE REPORT FOR'FQ = 2.20
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1 of 2 TABLE 1 MORTH ANNA UNIT 1,
CYCLE 5 CORE SURVEILLANCE LIMITS, F2 = 2.20 I.
The F-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 S 1.60 for all unrodded core planes from 15 to 27%
of core height, or 3.
Txy-RTP S 1.58 for all unrodded core planes from 27 to 85%
of core height.
l II. The axial power distribution surveillance threshold power level shall bei 1.
Pm = 100% of RATED THERMAL POWER.
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