ML20073K501

Responds to Rev 1 to IE Bulletin 79-26 & SER Section 4.2.3.14 Re Control Blades.Procedure Reflects Recommendations of Bulletin & GE Svc Info Ltr 157.Controlled Record of Blade Exposure to Be Developed W/Plant Operation

ML20073K501
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	04/14/1983
From:	James Smith LONG ISLAND LIGHTING CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
REF-SSINS-6820 IEB-79-26, SNRC-874, NUDOCS 8304200304
Download: ML20073K501 (3)

Text

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e_: = =~~ 3 j LONG ISLAND LIGHTING COMPANY fampf, SHOREHAM NUCLEAR POWER STATION 3 P.O. BOX 618 NORTH COUNTRY ROAD

• WADING RIVER, N.Y.11792 Direct Dial Number April 14, 1983 SNEC-874 t

Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Response to IE Bulletin 79-26, Revision 1 License Condition Number 1 (Section 4. 2. 3.14 of the SER)

Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322

References:

1) General Electric Service Information Letter (SIL)

Number 157 Rev. 2 " Control Blade Lifetime" Sept. 1981.

2) Shoreham Nuclear Power Station - Unit 1 Station Procedure SP 57.010.01 Rev 0.

Dear Mr. Denton:

In response to the requirements of IEB 79-26 Revision 1, General Electric formed an operating plant owners group to conduct examinations of control blades from several nuclear power stations with various operating histories. These examinations and the related analytical calculations have provided the basis for recommendations regarding the service life of the control blades, (reference 1).

LILCO has developed a station procedure (reference 2) which reflects the recommendations of the bulletin and the G.E. SIL.

The procedure uses existing process computer software to determine the B-10 depletion, averaged over each quarter segment of the control blade. Once Shoreham becomes operational, a controlled record of blade exposure will be developed and periodically up-dated to provide an operating history and projected exposures through the current and subsequent fuel cycle for each control blade.

3001 8304200304 830414 PDR ADOCK 05000322 G PDR FC-89 35.1

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April 15, 1983 SNRC-874 Page 2 Generally, if it is expected-that any control blade will exceed 34% average B-10 depletion in any quarter. segment, the procedure establishes a plant policy"to:  ;

Replace the affected control blade at the scheduled refueling outage prior to the blade exceeding the:34% depletion guideline or,

~

Move the high exposure control blade to a core location where reduced exposure will enable' operation for the following fuel cycle without, exceeding 34% depletion.

If it has been determined that a control blade has exceeded or will exceed the 34% B-10 depletion criterion before the next refueling outage, an analysis will be performed to quantify the reduction in relative reactivity worth. In all cases the calculated shutdown margin throughout the cycle. (accounting for the loss of boron carbide) must be within the Technical Specification require-ments.

The referenced station procedure was reviewed by the NRC resident inspector and a regional specialist. As discussed in item 5 of inspection report no. 50-322/81-20, the review determined that the procedure addresses the concerns identified in the bulletin and that the bulletin could be closed.

LILCO believes this information should be sufficient to resolve the license condition for OIE Bulletin 79-26, Revision 1 for the Shoreham Nuclear Power Station - Unit 1.

Very truly yours, .

t-

.55 /

. L.. Smith Manager, Special Projects Shoreham Nuclear Power Station RT:bc

- cc: J. Higgins All Parties Listed in Attachment 1

e-m o .-

• ATTACH'T!: 1 Laurence Drenner, Esq.  !!crbert H. Brown, Esq.

Administrative Judge Lawrence Coe Lanpher, Esq. .

Atomic Safety and Liccasing 1:arla J. Letsche, Esq.

Board Panel 1;irkpa trick , Lockhart, 11 i 1 1 U.S. Nuclear Regulatory Co=aission Christopher & Phillips Washington, D.C. 20555 8th Floor 1900 M Street, N.W.

Washington, D.C. 20036 Dr. Peter A. Morris Administrative Judge Atomic Safety and Licensing Mr. Marc M. Goldsmith

- Board Panel Energy P.esearch Group U.S. thiclear Regulatory Commission 4001 Totten Pond Road Washington, D.C. 20555 Waltham, Massachusetts 02154 Dr. James !!. Catpenter M!ID Technical Isscociates Administrative Judge 1723 Ilarailton Avenue Atomic Safety and Licensing Suite K Hoard Panel San Jose, California 95125 U.S. Nuclcar Regulatory Commission Wa shi nc; ton , D.C. 20555 -

Stephen B. Latham, Esq.

Tuomey, Latham & Shea Daniel P. Broun, Esq. 33 Uest Sccond Street Attorney P.O. Box 390 Atomic Safety and Licensin9 Riverhead, New York 11901 Board Panel U.S. Nuclear Regulatory Conmission Washington, D.C. 20555 Ralph Shapiro, Esq.

Cammer and Shapiro, P.C.

Bernard M. Bordenick, Esq.

9 East 40th Street New York, New York 10016 David A. Repka, Esq.

U.S. Nuclear ilegulatory Commissiori Washington, D.C. 20555

^

Matthou J. 1;elly, Esq.

State of New York James Dougherty .

Department of Public Service 3045 Porter Street Three Erapire State Pla:a Washington, D.C. 20003 Albany, New York 12223

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