ML18139C299

Application for Amend to Licenses DPR-32 & DPR-37,adding Reactor Vessel Coolant Monitor to Tech Spec Tables 3.7-6 & 4.1-2 to Meet Requirements of NUREG-0737,Item II.F.2, Detection of Inadequate Core Cooling.

ML18139C299
Person / Time
Site:	Surry
Issue date:	03/31/1983
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Varga S Office of Nuclear Reactor Regulation
Shared Package
ML18139C300	List: ML18139C299 ML18139C301
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM 186, NUDOCS 8304110475
Download: ML18139C299 (3)

Text

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261

w. L. STEW~ll:T VxcE PRESIDENT NUCLEAR 0PERATI0~""S March 31, 1983 Mr. Harold R. Denton, Director Serial No. 186 Office of Nuclear Reactor Regulation NO/WDC:acm Attn: Mr. Steven A. Varga, Chief Docket No. 50-280 Operating Reactors Branch No. 1 50-281 Division of Licensing License Nos. DPR-32 U. S. Nuclear Regulatory Commission DPR-37 Washington, D. C. 20555 Gentlemen:

AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR-37 SURRY POWER STATION UNIT NOS. 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 Nos. 1 and 2. The proposed change is enclosed.

This proposed change adds a Reactor Vessel Level Coolant Monitor to Tables 3.7-6 and 4.1-2 to meet the requirements of NUREG-0737, Item II.F.2. The monitor provides direct readings of the reactor vessel coolant level. Final installation and calibration are being performed during the present refueling outage for Surry Unit 1. Final installation and calibration for Unit 2 will be performed during the next refueling outage presently scheduled for May, 1983. Final implementation of this system must be coordinated with the implementation of the revised emergency operating procedures prior to issuance of this amendment. The proposed Technical Specification change is provided in Attachment 1. A discussion of the proposed change is provided in Attachment 2.

This request has been reviewed and approved by the Surry 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.

Very truly yours, 8304110475 830331 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 for $4,400 cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. Don J. Burke NRC Resident Inspector Surry Power Station

e e 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. He 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.

Acknowledged before me this 3 / ,4-day of ~ , 19 .P.3 My Commission expires:

Notary Public (SEAL)

M2/004