ML20091P452

Application for Amend to License NPF-4,modifying License Condition 2.D(1) Re Max Power Level to Add Footnote Which States That Max Reactor Power Level Shall Be Limited to 95% of Rated Thermal Power

ML20091P452
Person / Time
Site:	North Anna
Issue date:	01/28/1992
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20091P454	List: ML20091P452 ML20091P456
References
92-042, 92-42, NUDOCS 9202030109
Download: ML20091P452 (3)

Text

_ _... - _ - - _ _ _ _ _ _ _ _ _ - _ - _ _ - _ _ _ _ _ - - - _ _ - - - _ _ _ - - - _ -. _ _ _ _ _ - _ _ _ _ - _ _. - - _ - _ - - -

k t

4 VildOINI A l$1.lTTlfl(' AN D POWi!!( f o bil'A N Y l{ lo tt M ON D, VI!HilNI A Ull.t 01 January 20, 1992 t

U.S. Nuclear Regulatory Commission Sorial No.

92 042 Attuation: Document Control Des'.

NL&P/JBL:

R2 Wash!ngton, D.C. 20555 Docket Nos.

50 338 Licenso Nos. NPF 4 Gentiomon:

VIRGINIAJLECTRIC AND POWER QDMPANY NORTH ANNA POWER STATION UNIT 1 PROPOSED TECHNICAL SPEQlFICATION CHANGE REDUCTION IN MAXIMUM REACTOR POWER LEVEL i

-DUE TO INCREASED STEAM _ GENERATOR TUBE PL_QQQlhG LL 'EL Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests amendments, in the form of changes to the operating licenso and the Technical Specifications, to Facility Operating License Number NPF 4 for North Anna Power Station Unit 1. The proposed change to the operating license will limit maximum reactor power to 95% of rated thermal power for the interim period of operation until steam generator replacement. The proposed change to the Technical Specifications willimpose more restrictive equipment operability requirements for the Emergency Cort, Cooling System (ECCS).

Those proposed changos are necessary to accommodate the interim effects of increased steam generator tube plugging on the large break Loss of Coolant Accident (LOCA) analysis.

1 SpeclNcally, we request a change which modifies license condition 2.D.(1), Maximum Power Level, by adding a footnote which states that the maximum reactor power lovel shall be limited to 95% of rated thermal power, We also request a change to Action Statement "a" of Specification 3.5.2, ECCS Subsystems Tavg 23506F, by adding a footnote which requires the charging pump in each ECCS subsystem be operable if either low head safety injection pump is inoperable to comply with the requiroments of the Action Statement.. These proposed changes are applicable for the remaining pened of operation until the North Anna Unit 1 steam generators are replaced in 1993.

3 l-North Anna Power Station Unit 1 is currently involved in a mid cyclo steam generator inspection outago. An extensive eddy current inspection of the North Anna Unit i steam generator tubes is being performed using very conservativo analysis guidelines -

and-plugging criteria.

As such, a substantially ' Increased number of tubos are expected to be plugged.

The predictions of steam generator tubo plugging required during this mid cycle outage are such that the effects of increased RCS loop resistance on the largo break Loss of Coolant Accident (LOCA) analysis would not permit full rated power operation t

j 920203o109 920129 l

PDR ADOCK 05o00330 P-PDR

f f

I for the romalnder of Cycle 9 operation for North Anna Unit 1.

Thorofore, safety analysos and evaluallons have been performed to extend the steam gonorator tube e

plugging limit valuo from 30% to 35% foi tho most restrictive steam generator and i

continue to suppoli operation with an imposed 95% reactor power rostriction. The attached safety ovaluation has boon prepared to discuss the changes to the large break LOCA analysis and support a licenso amendment associated with the restriction in reactor power.

The proposed changes are prosented in Attachment 1. A discussion of the proposed changos is provided in Attachment 2 and a safety evaluation is provided in Attachment

3. This request has boon reviewed and approved by the Station Nuclear Safety and Operating Committoo and the Managomont Safoty Review Committoo, it has boon 4

dolormined that this request does not involvo an unroviewed safety question as 3

defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92. The basis for our dolormination that those changos do not involve a significant hazards consideration is provided in Attachment 4.

North Anna Unit 1 was shut down to perform steam generator tubo inspections on December 23, 1992.

The unit is scheduled to conclude the steam generator inspections and commenco startup not later than March 20,1992. We request your approval of the enclosed changes prior to this scheduled startup date.

Should you have any questions or require additional information, please contact us immodlately.

Very truly,yours, I\\.(1-d, g

i W. L. Stowart Senior Vice President Nuclear Attachments cc:

U.S. Nuclear Regulatory Commission Region ll 1

101 Marietta Street, N.W.

Suito 2000 -

Atlanta, Georgia 30323 Mr. M. S. Lessor NRC Senior R9sident inspector

- North Anna Pc.wer Station Commissioner i

L Department of Health Room 400 109 Gavornor Street

. Richmond Virginia 23219 l

~.~.,... ~..--,..._,.._.._ -..-..,....._~.- --

, _ _. _ _,,. -... _ _ _. ~,.. _,.. _,., _,.. _. _, _

t I

COMMONWEALTH OF VIRGINIA )

)

COUNTYOFHENRICO

)

The foregoing document was acknowled0od before me, in and for the County and Commonwealth aforesaid, today by W. L. Stewart who is Senior Vico President Nuclear, of Virginia Electric and Power Company.

He is duly authorized to execute and file the foregoin0 document in behalf of that Company, and the statomonts in the document are true to the best of his knowled0o and belief.

Y d

1992 Acknowledged before me this / 8Y ay of./)z/Jytou,

/

M 2/1n 7/

_ '. 19 W.

My Commission Expires:

t

(/

i i

I __

t.

fd._.

_s Notary Public I

i (SEAL)