ML20098G994
| ML20098G994 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/03/1984 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, John Miller Office of Nuclear Reactor Regulation |
| References | |
| 726F, NUDOCS 8410090214 | |
| Download: ML20098G994 (2) | |
Text
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' VIRGINIA ELucTurc Axn Powna COMPANY RICHMOND, VIRGINIA 202 61 W.L. STEWART NM'5fo"' Ufo,,,
October 3, 1984 Mr. Harold R. Denton, Director Serial No. 726F Office of Nuclear Reactor Regulation E&C/WBR:ses:2004N Attn: Mr. James R. Miller, Chief Docket No. 50-339 Operating Reactors Branch No. 3 License No. NPF-7
' Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 2 IMPLEMENTATION OF 587.8*F REACTOR COOLANT AVERAGE TEMPERATURE The NRC letter of March 13, 1984, from Mr. Leon B. Engle to Mr. W. L.
Stewart issued Amendment No. 54 to Facility Operating License No. NPF-4 for North Anna Power Station, Unit No. 1.
As requested by our letters of December 30,1982 (Serial No. 726) and September 29,1983 (Serial No. 480), the amendment revised the Unit No. 1 Technical Specifications to permit operation with a reactor coolant system (RCS) average temperature of 587.8 F and to allow optimization of the core loading pattern by changing the fractional thermal i
power multiplier from 0.2 to 0.3 for an RCS T-AVG of 587.8aF.
The Safety Evaluation for the 7.5 F uprating forwarded by the above NRC letter applied to Unit Nos. I and 2.
However, the issuance of an amendment for Unit No. 2 was held in abeyance until Vepco had modified the main feedwater regulating valve trim to provide operational flexibility for the uprating.
In lieu of a trim modification, the valve operators have been replaced to allow a larger valve stroke..This change enables the use of the full capacity of the existing valve trims. A review has been performed and it has been determined that the replacement of the valve operators has provided the required valve operational flexibility to permit operation at an RCS T-AVG of 587.8 F.
It is requested that the NRC issue an amendment to Facility Operating License No. NPF-7, for North Anna Power Station, Unit No. 2.
This amendment is needed to support implementation of the 7.5 F T-AVG increase at North Anna Unit No. 2 during the current refueling outage, which is scheduled to end on October 23, 1984.
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. Vaaornia Es. acinic Awn Powsm Courawy To
-Mr.' Harold R. Denton m
Please contact us at your earliest convenience if you should have any.
ovestions.-
ery truly-yours, W. L. Stewart ~
.cc: 'Mr. James P. O'Reilly-cRegional Administrator.
Region II~
.Mr.-M.
W.' Branch
.NRC Resident Inspector' North Anna Power Station i-i-
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