ML20055H186

Application for Amends to Licenses NPF-4 & NPF-7,revising Effective Dates for Initiating Response Time Testing for Pressurizer Level Reactor Trip Function

ML20055H186
Person / Time
Site:	North Anna
Issue date:	07/23/1990
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20055H187	List: ML20055H186
References
90-460, NUDOCS 9007250290
Download: ML20055H186 (4)

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YtHOINIA F.txcrute Axn Pownu Comwxy RICitMOND,YINUINIA 200 61 July 23,1990 U.S. Nuclear Regulatory Commission Serial No.: 90-460-Attention: Document Control Desk NL&P/JDH R2 Washington, D.C. 20555 Docket Nos.: 50 338 50 339 ~

License Nos.: NPF-4 NPF-7.

Gentlemen:

l ylRGINIA- ELECTRIC AND POWER COMPANY NORTH ANNA POWER' STATION UNITS 1 AND 2 PROPOSED EMERGENCY TECHNICAL SPECIFICATION CHAMfaf REVISED EFFECTIVE DATES FOR INITIATING RESPONSE TIME TESTING FOR PRESSURIZER LEVEL REACTOR TRIP FUNCTION Pursuant L to 10 CFR 50.90, Virginia Electric and Power Company requests ,

amendments, in the form of changes to the Technical Specifications, to Operating ,

License Numbers NPF-4 and NPF-7 for North Anna Power Station Units 1 and 2, a respectively. These amendments will revise the effective dates for initiating response i time testing for the " pressurizer water level- high" reactor trip function from the effective - <

date.of previous license amendments to no later than startup from each unit's next

. refueling outage. The proposed Technical Specifications changes are presented in Attachments 1 and 2.

- The proposed change establishes and justifies revised start dates for implementing the " pressurizer water level--high" reactor trip function surveillance requirement. The '

surveillance requirement had previously been added to Technical Specification Table E, '3.3 2 by license amendment no.112 on January 3,1989 for Unit 1 and amendment no.100 on' June 00,1989 for Unit 2. However, s!nce that time the surveillances have not been conducted due to administrative oversight. The concern was identified by Virginia Electric and Power Company on July 19,1990 and a temporary waiver of compliance requested from NRC on July 20, 1990. The request was verbally L  : approved by NRC on July 20,1990. The temporary waiver approval was conditioned 1 i 'upon Virginia Electric and Power Company submitting an emergency Technical L  ; Specification change to justify and revise the dates for implementing the surveillance L requirement.

- Because response time surveillances are normally conducted during outages, the change proposes to reestablish ~the start date for conducting the surveillance at each o unit's next refusiing outage. For Unit 1 the change in implementation date would be from January 3,1989 to prior to startup for Cycle 9 operation (currently scheduled March 5,1991). Unit 1 is currently in Cycle 8 operation and is scheduled to shut down on January 4,1991 for a 60 day refueling outage. For Unit 2 the change in implementation date is from June 30,1989 to no later than startup for Cycle 8 ,

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operation (currently scheduled November 21,1990). Unit 2 is currently in Cycle 7 and is scheduled to shut down on September 7,1990 for a 75 day refueling outage. No i planned outage of either unit prior to their refueling outages is currently scheduled. I

? However,in the event of an unplanned shutdown to Mode 5 of either unit, the required  ;

survelliance would be conducted at that time.

O To establish a baseline for future surveillances, the initial surveillance requirement will be implemented on all three channels of the " pressurizer water level- high" trip function. Subsequent surveillances will be conducted in accordance with Technical i Specification 3.3.1.1.

This proposed change has been reviewed with respect to the_ proposed MERITS version of the North Anna Technical Specifications previously submitted. No changes .

to the previous MERITS T(chnical Specification submittal are required.

_This request has been reviewed by the Station Nuclear Safety and Operating.

Committee. It has been determined that this request does not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92. .The basis for our determination that this change does not involve a significant hazards consi%ation is provided in Attachment 4.

We request that the proposed change be processed as an emergency Technical Specification change and have determined that the proposed change meets the-criteria in 10 CFR 50.91(a)(5) for an emergency situation. The basis for that

' determination is provided in Attachment 5.

If'you have any questions or require additional information, please contact us immediately.

-Very truly yours, N

W L. Stewart Senior Vice President - Nuclear Attachments: ,

1. Proposed Technical Specification Change for North Anna Unit 1

2. Proposed Technical Specification Change for North Anna Unit 2

3. Discussion of Proposed Changes

4. 10 CFR 50.92 No Significant Hazards Consideration Determination

5. Basis for Emergency Request

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l m i >- oc: U.S. Nuclear Regulatory Commisslor l Region ll .

101 Marietta Street, N.W.

. Suite 2900

.l Atlanta, Georgia 30323 l Mr. M. S. Lesser NRC Senior Resident inspector  ;

North Anna Power Station Commissioner '

Departmont of Health  !

Room 400 109 Governor Street Richmond, Virginia 23219 i

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COUNTYOF HENRICO )

1 The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by W. L. Stewart who is Senior ,

Vice President Nuclear, of Virglnia 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 l his knowledge and belief. ,

Acknowledged before me this 23 day of h ab, ,1990.

My Commission Expires: ( 94u 3/ , 9W.

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Notary Public F

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