ML18141A290
| ML18141A290 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/29/1983 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM 721, NUDOCS 8401040560 | |
| Download: ML18141A290 (2) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWABT VxcE PRESXDENT NUCLEAR 0PERATXONS December 29, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
Serial No. 721 PSE/HWB:ses/0016N Docket Nos.:
50-280 50-281 Li c e n s e No s. :
DP R-3 2 DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION STATUS OF NUREG-0737 ITEM II.D. 1.2 In our letter dated November 16, 1982 (Serial No. 3888), we provided a status of our evaluation of the Surry safety and relief valve discharge piping.
At that time, our plans called for the completion of the piping evaluation for North Anna Unit 2 first. This unit had been designated as the lead unit for these evaluations.
The plant-specific piping calculations for the remaining Vepco units were to be accomplished using information and guidance from the North Anna Unit 2 evaluation.
The analysis has now been completed for Surry Power Station, Units l and
- 2.
This analysis has demonstrated the feasibility of maintaining the safety valve loop seals provided the loop seals are maintained at an elevated temperature of approximately 400°F and modifications are made to the piping system supports.
The elevated temperature will be accomplished by modifying the pressurizer insulation adjacent to the loop seals and the addition of insulation to the loop seals.
We are now proceeding with the final engineering to accomplish the required modifications. It is our intention to complete the final engineering in 1984.
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e VIRGINIA ELECTRIC AND POWER CO!{PANY TO Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Page Two Implementation of the required modifications will begin following the completion of the final engineering.
cc:
Mr. James P. 0 1Reilly Regional Administrator Region II Mr. Steven A. Varga, Chief Operating Reactors Branch No.
Division of Licensing U. S. Nuclear Regulatory Commission Mr. D. J. Burke NRC Resident Inspector Surry Power Station Very truly yours, 0(~
W. L. Stewart