ML19325E373

Grants Waiver from Tech Spec 6.9.1.7 Reporting Requirements for Core Surveillance Rept,Per 890914 & 1016 Requests,Due to Licensees Program to Extend Life of Steam Generators

ML19325E373
Person / Time
Site:	North Anna
Issue date:	10/27/1989
From:	Engle L Office of Nuclear Reactor Regulation
To:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
References
NUDOCS 8911060379
Download: ML19325E373 (3)

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UNITED STATES gAo:

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October 27, 1989 f

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M Docket Nos. 50-338

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and 50-339 Mr..W.'R. Cartwright i

Senior '!!ce President - Power Virginia Electric and Power Company

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5000 Dominion Blvd.-

Glen Allen, Virginia 23060

SUBJECT:

NORTH' ANNA POWER STATION UNITS 1 AND 2 (NA-182) - T TEMPERATURE

.REDUCTIONPR9GRAMANDTECHNICALSPECIFICATIONREPORYT[IGREQUIREMEN FOR THE CORE SURVEILLANCE REPORT The NA-1&2 Technical-Specification (TS) 6.0.1.7 requires a Core Surveillance Report be provided to'the NRC 60 days prior to cycle. criticality cr prior to any. changes during core life unless a written waiver is granted by the NRC staff.

l By letters dated September 14,.1989 and October 16, 1989, the licensee indicated'that the 60-day. advance submittal requirement be waived by the NRC 4

for'the following reasons.

Virginia Electric and Power Company '(tt.e' licensee) is pursuing implementation of a Reactor Coolant System T temperatuie recuction for both NA-1&2.

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temperature-reduction is a key hart of the licensee's program to extend th$ t

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life of.the NA-1&2 steam generators. The reduced hot leg temperature reduces the potential for ii.itiation and propagation of primary water stress corrosion l'

cracking (PWSCC) of the steam generator tubes.

linplementation of the T t

L temperaturereductionprogramrequiresthatnuclearcoredesigncalculaki$ns L

be modifieo. Specifically, the Relaxed Power Distribution Control l

calculations.must be revised to support reduced 'enerature operation for the L

remainoer, of the current North Anna operating cycle. These analyses will result in revised N NA-1 lc began its eight cyckEy functions for normal operation of. both Units.

normal operation as describeration on Julyed in the Core Surveillance Report k6hm of o 16, 1989 with the N function f or letter April 28, 1989. Likewi:e, NA-2 began its seventh cycle of operation on l

itay9,1989withtheN($hrve1116nceReportsubmittedMay function for normal operation es described in Revision 1 of the Core 22, 1989. As stated

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above,.tne N tunction for normal eperation will change as a result of this temperatureh$huction3rogram.

Therefore, ir, accordance with the TS 6.9.1.7 reporting provision, t,e licensee requested the 50-day advance suomitt61 requirunent be waived by the NRC, ano alternately, the licensee proposed to

.cbmit the required Core Surveillance Report by October 20, 1989.

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Mr. W. R. Cartwright October 27, 1989 i

i by letter dated October 20, 1989, the licensee submitted the required Cycle 8 and 7 Core Surveillance Re) ort for NA-?&2. The Cycle 8 and 7 reload core was analyzed in accordance wit 1 the methodology documented in the NRC-approved i

Topical Report VEP-fRD-42 Revision I-A, " Reload Nuclear Design Methodology,"

usino NRC-approved codes as referenced in trie Topical Report.

The information in tfie NA-1&2 Core Surveillance Report was developed in accordance with the l

licensee Topical Report VEP-NE-1-A, " Relaxed Power Distribution Control Methodology and Associated FQ Surveillance Technical Specifications." The 3

results of the analyses indicated that no key analysis parameters would become more limiting during Cycle 7 operation than the values assumed in the currently applicable NA 1&2 safety analyses and as specified in the NA-1&2 TS.

The Core Surveillance Report consists of the NA-1&2 Cycle 8 and 7 Nrlitly-3 function and the axial flux difference limits, which are based upon the curre approved total peaking factor (F ) limit of 2.19.

q Therefore, based on the above, the staff finds the NA-1&2 Cycle 8 and 7 Core Surveillance Report to be acceptable and a waiver is hereby grarted to the i

NA-1&2 TS 6.9.1.7 reporting requirements.

Sincerely, Original signed by Leon B. Engle, Project Manager Project Directorate II-2' Division,ofsReactor Projects - I/II

.0ffice of Nuclear Reactor Regulation i

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NRC & Local PDRs LEngle PDII-2 Rdg. File OGC (info. only) s SVarga,14/E/4 EJordan, NNBB 3302 o

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.Mr. W. R. Cartwright North Anna Power Station

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Virginia Electric & Fower Company Units 1 and 2 cc:

Mr. William C. Porter, Jr.

C. M. G. Buttery, ii.D., M.P.H.

County Administrator Departnent of Health Louisa County 109 Governor Street P.O. Box 160 Richmor.d, Virginia 23219 Louisa, Virginia 23093 Regional Administrator, Region II flichael W. Maupin, Esq.

U.S. Nucleer Regulatory Commission Hunton and Williams 101 Marietta Street N.W.. Suite 2900 P, 0. Box 1535 Atlanta, Georgia 30323 Richmond, Virginia 23212 fir. W. T. Lough Virginia Corporation Commission Mr. G. E. Kane, Manager Division of Energy Regulation fiorth Anna Power Station P. O. Box 1197 P.O. Box 402 f!1chmond, Virginia 23209 Mineral, Virginia 23117 010 Dominion Electric Cooperative Mr. J. P. O'Hanlon c/o Executive Vice President Vice President - Nuclear Services Innsbrook Corporate Center Virginie Electric and Power Company 4222 Cox Road, Suite 102 5000 Old Dominion Blvd.

Glen Allen, Virginia 23060 Glen Allen, Virginia 23060 Mr. W. R. Cartwr ight Mr. R. F. Saunders Vica President - Nuclear Operations Manager - Nuclear Licensing Virginie Electric and Power Co.

Virginia Electric and Power Company 5000 Old Dominion Blvd.

5000 Old Dominion bivo.

Glen Allen, Virginia 23C60 Glen Allen, Virginia 23060 Mr. Patrick A. O' Hare Office of the Attorney General Suprene Court Building 101 North 8th Street Richmond, Virginia 23219 Senior R sident Inspector North Anna Power Station U.S. Nuclear Regulatory Commissior.

Route 2, Box 78 Minet't, Virginia 23117

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