ML18142A474

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Submits List of Valves for Which Repairs/Replacements Involving Welding on Pressure Boundary Planned for Nonisolable Portions of Blowdown Sys & Main Steam Branch Connections,Per Util 850503 Relief Request
ML18142A474
Person / Time
Site: Surry Dominion icon.png
Issue date: 06/21/1985
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Varga S
Office of Nuclear Reactor Regulation
References
85-305A, NUDOCS 8506270058
Download: ML18142A474 (2)


Text

WiLLMM L STEWART Vice President Nuclear Operations June 21, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:

Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

VIRGINIA POWER SURRY POWER STATION UNIT NO. 2 e

Nuclear Operations Department Post Office Box 26666 One James River Plaza Richmond, Virginia 23261 VIRGINIA POWER Serial No. 85-305A NO/JDH:cfm Docket No. 50-281 License No. DPR-37 ASME SECTION XI RELIEF REQUEST - SUPPLEMENT On May 3, 1985, we submitted a letter (Serial No.85-305) requesting relief from certain ASME Section XI requirements concerning hydrostatic testing.

During a subsequent telephone conversation with the NRC Surry Project Manager, we informed him that one of the two references cited in the letter was incorrect.

The incorrect reference is a Virginia Power letter, W. L. Stewart to H. R.

Denton, dated April 14, 1985, Serial No.

001B.

The correct reference is a Virginia Power letter, W. L. Stewart to H.

R.

Denton, dated April 12, 1984, Serial No. 201, which requested relief from certain post-repair/replacement test requirements delineated in ASME Section XI. This. relief request was approved by the NRC on May 17, 1984.

During the same discussion, the NRC Surry Project Manager requested that*

we specifically identify the several valves discussed in our May 3, 1985, request for which repairs or replacements involving welding on the pres-sure boundary are planned for non-isolable portions of the Blowdown System and Main Steam branch connections. These components do not exceed 2 inch nominal pipe size and are listed below:

Steam Generator Blowdown Root Valves 2-BD-1 2-BD-4 2-BD-11 2-BD-14 2-BD-21 2-BD-24 8506270058 850621 PDR ADDCK 05000281 P

PDR Main Steamline Drain Valves 2-MS-120 2-MS-266 2-MS-378 2-MS-379

lf you have any further questions or require additional information, please contact us immediately.

Very truly yours, W. L. Stewart cc:

Dr. J. Nelson Grace Regional Administrator Mr. D. J. Burke NRC Resident Inspector Surry Power Station