ML20116N841

Application for Amends to Licenses NPF-4 & NPF-7,authorizing Operation w/core-rated Thermal Power of 2,893 Mwt/Nsss Power of 2,905 Mwt.Safety Evaluations,Proposed Tech Specs & Response to NRC Comments at 841011 Meeting Encl.Fee Paid

ML20116N841
Person / Time
Site:	North Anna
Issue date:	05/02/1985
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, John Miller Office of Nuclear Reactor Regulation
Shared Package
ML20116N845	List: ML20116N841 ML20116N858 ML20116N864 ML20116N875
References
85-077, 85-77, NUDOCS 8505070373
Download: ML20116N841 (5)

Text

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F; ,. ygg gg<g;ynnem 3 mu:w waaim onejarm,mmnaa Rdxnorkf Virginka.T.L%1 May 2, 1985 vmormarowen Mr. Harold R. Denton, Director Serial No.: 85-077 Office of Nuclear Reactor Regulation E&C/WBR:ses:2010N Attn: Mr. James R. Miller, Chief Docket Nos.: 50-338 Operating Reactors Branch No. 3 50-339 Division of Licensing License Nos.: NPF-4 U. S. Nuclear Regulatory Commission NPF-7 Washington, D. C. 20555 Gentlemen:

AMENDMENT TO OPERATING LICENSES NPF-4 AND NPF-7 2

NORTH ANNA POWER STATION UNIT N05. 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGES ,

Pursuant to 10CFR50.90, Virginia Power requests an amendment, in the form of changes to the Technical Specifications, to Operating License Nos. NPF-4 and NPF-7 for the North Anna Power Station Unit Nos. 1 and 2.

As discussed with members of the Staff in a meeting on October 11, 1984, Virginia Power is requesting an increase'in the maximum core power as the final phase in a program to maximize the electrical output of North Anna Unit Nos. 1 and 2. The proposed changes of this amendment will allow operation of the North Anna units with a core rated thermal power of 2893 MWt (Nuclear Steam Supply System (NSSS) power.of2905MWt).

Enclosures 1 and 2, respectively, provide Safety Evaluations for the NSSS -

and Balance of Plant (80P) systems in support of operation up to a NSSS rating of 2910 MWt. However, because of turbine generator limitations, this request would allow operation for a NSSS rating of only 2905 MWt. The specific Technical Specification' revisions required for this change are given in

-Enclosure 3. Several associated setpoint changes are required for operation at the.uprated conditions, and these setpoint changes will be incorporated into the Precautions,LimitationsandSetpoints'(PLS)documentandtheplantprocedures prior ta implementation of the uprating. The UFSAR revisions associated with the-reanalyses will be incorporated into the UFSAR during the annual update following implementation of the;uprating. Enclosure 4 addresses a number of specific comments raised by.the NRC staff at the October 11. 1984 meeting.

As discussed in Enclosure 2, the B0P review determined that the only plant modification required to support operation at the uprated conditions is a minor change for the Unit 2 main feedwater regulating valve internals to provide operational flexibility at the uprated conditions. p ge,o l o$ch l ,

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Mr. Harold R. Denton Page 2 -

VIRGINIA POWER The large break LOCA analysis for the most limiting case reported in Enclosure 1 incorporates the revised Westinghouse procedure for accurate treatment of core flooding rate during reflood. Westinghouse informed the NRC of the details associated with this input methodology change via the March 22,

- 1985 letter from E. P. Rahe to D. G. Eisenhut (No. NS-NRC-85-3025).

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 involve any unreviewed safety-questions as defined in 10CFR50.59 or a significant hazards considaration as defined in 10CFR50.92.

~ We have evaluated this request in accordance with the criteria in 10CFR170.12. A voucher check in the amount of $150 is enclosed as an application fee.

We would like to implement the core uprating during the next refueling

' outages. We request that your review and approval be completed by December 1, 1985. Please contact us if you need additional information to review this submittal.

ery truly yours, W. L. Stewarts Enclosures (1) NSSS Safety Evaluation for 2910 MWt NSSS Rating

2) B0P Safety Evaluation-for 2910 MWt NSSS Rating Proposed Technical Specification Changes Response to NRC Comments and Questions

. Voucher' Check for $150-cc: Dr. J. Nelson Grace Mr. Leon B. Engle Regional Administrator NRC Project Manager - North Anna

. Region II .

Operating Reactors Branch No. 3

Atlanta, GA- 30323 Division of Licensing Mr. Charles Price Mr.-M. W. Branch Department of Health NRC Resident Inspector 109 Governor. Street- North Anna Power Station Richmond, Virginia 23219 y V "

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[ . . . .

4 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 Virginia Power. 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 74 day of TY\ ct, , 19 Ys ,

My Commission expires: hhes m. \n , 19 SS .

\L ~\\(N\(Q\t.

Notary Public (SEAL)

S/001 m

~ . . _ . . _ _ . . - _ _ . _ _ __ .__ ___ _ _ ___

ADM-6.11 Attecha:nt 1 Pcg2 2 of'2 10-25-84 REQUEST TO CHANGE TECHNICAL SPECIFICATION

, NORTH ANNA POWER STATION VIRGINIA ELECTRIC AND POWER COMPANY TO: Director Safety Evaluation and Control 1 Request No. 2

, Ms. N. E. Clark i f g[ f f p i Number of Technical Specification to be changed: 3

Reference Attachment 1 R; quested Change: (Please attach a marked up copy of the Tech. Spec. basis to be revised) 4 j Reference Attachment iV 4 4 mcw& fr,//wuw t, w%a hwse swsed inov+ oer l K'w%f% meme -4 TvfY/orf do dec/ W,, /M Raccon for Change: Attached Techrical Soecification chances are required to support 5 I i a NSSS unratino to 2905 MWt. Reference attached copy of the Lore Uprating Licensing ,

l Submitt al .

l 1

P:rson responsible for written safety evaluation:

Stone & Webster (BOP), Westinghouse (NSSS) & Virginia Power (G. L. Darden & W. B. Rodill) 6

~

4 Submitted By:.4/ 6 #ced.I# gg g Date:

D to: Q 7 Authorized By: AM >M _ 8

/-3/- 75 fj /yfpf-R viewed By: Die 1- @

• M I 1 ion and Control 9 Date: 10 M ,m. x&L K Wl5C R: viewed by Vice Presidi.a ilue1==e Onerations: 11 ed Disapproved Approved od),fied RecommendedAction:]sk.

Signature:

Remarks:

Q((n._-b Date: 1 4(

' ' ~

R: viewed by Station Nuclear Safety and Operating Committese 12 Recommended Action: Approved Disapproved Approved as modified Chairman's Signature: Date:

Reviewed By: Safety Evaluation trol Staff: 13 Recommended Action: roved Disapproved Approved as modified Director's Signature: /) Date:

Rsqu2st Forwarded to NRC:

N S o b 4 Tl 5-( oak 3- /8-B[

Dato of Letter:

(/ 14 Serial No.

Racptnse from NRC:

15 Approved Disapproved Approved as modified Date of Letter:

Ch:nge distributed to holders of the Technical Specification: 16 l Tech. Spec. Change No.: Date of Distribution:

l Amendment No.:

Acknowledged Complete By: Director-Safety Evaluation and Control 17 Date: 18 r

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