ML18139C204

Application for Amend to Licenses DPR-32 & DPR-37,revising Tech Spec Tables 3.8-1 & 3.8-2 Re Containment Isolation Valves

ML18139C204
Person / Time
Site:	Surry
Issue date:	01/10/1983
From:	STEWART W L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	DENTON H R, VARGA S A Office of Nuclear Reactor Regulation
Shared Package
ML18139C205	List: ML18139C204 ML18139C206
References
654, NUDOCS 8301130078
Download: ML18139C204 (4)

Text

)* -----.r' r e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VxcE PRESIDENT NUCLEAR OPERATIONS January 10, 1983 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:

Serial No. 654 NO/WDC:acm Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR-37 SURRY POWER STATION UNIT NO. 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGE Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests an amendment, in the form of changes to the Technical Specifications, to Operating Licenses DPR-32 and DPR-37 for the Surry Power Station, Unit No. 1 and 2. The proposed changes are enclosed.*

This proposed change is to revise Technical Specification Tables 3. 8-1 and 3. 8-2. Two air operated trip valves were installed to provide containment integrity for the Post-Accident Sampling System Containment Return Lines. The manual isolation valves in the Hydrogen Analyzer System were replaced with ten remote-manual valves to upgrade the system. An air operated trip valve was removed and replaced with two direct acting solenoid valves in the Residual Heat Removal Sample Lines to increase assurance of reliable operation during accident conditions.

New instrumentation replaced two air operated trip valves from the Leakage Monitoring System. Administrative and typographical errors were corrected.

The proposed Technical Specification changes are enclosed in Attachment

1. The corresponding overleaf pages are also provided in Attachment 1 to provide document completeness.

A discussion of the proposed changes are in Attachment

2. This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been determined that this request does not pose an unreviewed safety question as defined in 10 CFR 50.59. We have reviewed this request in accordance with the criteria in 10 CFR 170.22. Since this request involves a safety issue which the staff should be able to determine does not involve a significant hazards consideration for Unit 1 and a duplicate safety issue for Unit 2, a Class III license amendment fee and a Class I license amendment fee are required for Unit 1 and Unit 2, respectively.

A check in the amount of $4,400 is enclosed in payment of the required fees. -a:ioi 130078

• a30{10 PDR ADOCK 05000280 p PDR e VIRGINIA ELECTRIC AND POWER COMPANY TO Harold R. Denton Attachments:

1. Proposed Technical Specification Change 2. Discussion of Proposed Technical Specification Change 3. Voucher Check No. 88196 for $4,400 cc: Mr. James P. O'Reilly Regional Administrator Region II COMMONWEALTH OF VIRGINIA) ) CITY OF RICHMOND ) .. The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by W. L, Stewart, who is Vice President-Nuclear Operations, of the Virginia Electric and Power Company. lie is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief. -cl., Acknowledged before me this /l> day of , 19 ~3 My Commission expires: ~-;l...b , 19 S1-S--. Notary Public (SEAL) M2/004 l .* ---**-*-* --*-* -****--**---~~

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