ML18138A049

Application to Amend Licenses DPR-32 & DPR-37 to Require at Least One Auxiliary Feedwater Pump to Be Operable When Temp & Pressure of Opposite Unit Are Greater than or Equal to 350F & 450 Psig,Respectively.Tech Spec Pages Encl

ML18138A049
Person / Time
Site:	Surry
Issue date:	02/26/1980
From:	Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18138A050	List: ML18138A049 ML18138A051
References
NUDOCS 8002280346
Download: ML18138A049 (3)

Text

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VXRGINXA. 23261

• February 26, 1980 Mr. Harold R. Denton, Director Serial No. 143 Office of Nuclear Reactor Regulation LQA/WRM:rab Attn: Mr. A. Schwencer, Chief Operating Reactors Branch No. 1 Do~ket Nos. 50-280 Division of Operating Reactors 50-281 U.S. Nuclear Regulatory Connnission License Nos. DPR-32 Washington, D.C. 20555 DPR-37

Dear Mr. Denton:

AMENDMENT TO.OPERATING LICENSE SURRY POWER STATION UNIT NOS~ 1 AND 2 PROPOSED TECHNICAL SPECIFICATION"CHANGE"NO~ 83 Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company hereby 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 changes are enclosed and have been designated as Change No. 83.

The enclosed proposed Technical Specification changes are in response to the NRC's Fire Protection ,Safety Evaluation Report dated September 19, 1979 concerning requirements for a sufficient number of auxiliary feedwater pumps from the opposite unit to be available at all times during power operation of either unit. In the event a fire disables the auxiliary feedwater.pumps of an operating unit, decay heat removal capability following a reactor shutdown is available through the auxiliary feedwater pumps of the opposite unit via the auxiliary feedwater system cross-connect. Presently there are procedures for cross-connecting the auxiliary feedwater systems; however, the existing Technical Specifications do not require the auxiliary feedwater pumps for a shutdown unit to be operable.

The proposed Technical Specification changes will require that at least one of three auxiliary feedwater pumps be operable when the temperature and pressure of the opposite unit are greater than or equal to 350°F and 450 psig respectively. The selection of one pump is sufficient since any one of the three pumps is capable of providing sufficient decay heat removal in the event of a unit shutdown and a system disabling fire.

The auxiliary feedwater pumps must have a water supply in order to be operable; therefore, the requirement for a minimum of 60,000 gallons of water in the protected condensate storage tank will provide a minimum of 120 minutes of operation for a motor driven auxiliary feedwater pump. This requirement allows sufficient time for operator action to align additional suction water via the fire S00~2ff0 ~:Y.~

._\

e VrnmNIA ELECTRIC AND PowER CoMPANY To Hr. Harold. R. Denton

• 2 booster pumps in the event the additional water is needed. The Technical Specification for testing is also modified to reflect the changes to the requirements for the auxiliary feedwater system operability.

The proposed changes for the fire protection auxiliary feed-water cross-connect will not decrease the margin of safety associated with the auxiliary feedwater system; indeed, safety will be enhanced by the assurance of decay heat removal capability through the use of a cross-connect between the auxiliary feedwater systems of the two units.

This proposed change has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the System Nuclear Safety and Operating Committee. It has been determined that this re-quest does not involve an unreviewed safety question.

In accordance with the NRC Fire Protection Safety Evaluation Report dated September 19, 1979, the accompanying request involves only NRC recommended Technical Specification changes; therefore, a license amendment fee is not required for submittal of this request.

Very truly yours,

~-m.J~

C. M. Stallings Vice President-Power Supply and Production Operations Attachments:

Proposed Technical Specification Change No. 83 cc: Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region II

COMMONWEALTH OF VIRGINIA )

) s. s.

CITY OF RICHMOND )

Before me, a Notary Public, in and for the City and Common-wealth aforesaid, today personally appeared C~ M. Stallings, who being duly sworn, made oath and said (1) that he is Vice President-Power Supply and Production Operations, of the Virginia Electric and Power Company, (2) that he is duly authorized to execute and file the fore-going Amendment in behalf of that Company, and (3) that the statements in the Amendment are true to the best of his knowledge and belief.

Given under my hand and notarial seal this :2.Jo day of FL~ 'IG\8'C.

My Commission expires ow~ .. -*

I qi 1q~.;2..

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