ML19210D613

Proposes Mod of Appendix a of License DPR-35.Change Consists of Adding Sections Re Multiple Fuel Rod Removal During Refueling Operations

ML19210D613
Person / Time
Site:	Pilgrim
Issue date:	11/21/1979
From:	Howard J BOSTON EDISON CO.
To:	Ippolito T Office of Nuclear Reactor Regulation
Shared Package
ML19210D614	List: ML19210D613 ML19210D623
References
79-235, NUDOCS 7911270394
Download: ML19210D613 (3)

Text

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BOSTON EOl5ON COMPANY acNamat omCas eco eOvosTON sine T BOSTON. MassACNustTTs a2199 G. Cast ANDOoNINI sWPERINTENDENT NUCLCAR OPEmaTeONs DEPARTMENT November 21, 1979 BECo. Ltr. #79-235 Proposed Change No. 79- 7 Mr. Thomas A. Ippolito, Chief Operating Reactors Branch #3 Division of Opera ting Reactors Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555 License No. DPR-35 Docket No. 50-293 Technical Specification Change Concerning Multiple Control Rod Removal Reference (a) M3eting on October 12, 1979 with members of BECo Staff and NRC Staf f at Washington, concerning proposed Technical Specification Change on Multiple Control Rod Removal

Dear Sir:

Introduction Pursuant to Section 50.90 of the Commission's Rules and Regulations, Boston Edison Company hereby proposes the following modification to Appendix A of Operating License No. DPR-35.

Proposed Change Reference is made to Pilgrim Station Operating License No. DPR-35 Appendix A, Section 3.10 " Refueling". The desired change would consist of adding sections (as attached) to the Technical Specifications to make provisions for Multiple Control Rod Removal during Refueling Operations.

Reason for Change During Pilgrim Nuclear Power Station's next refueling outage, part of the scheduled maintenance to be performed will consist of rebuilding or re-placing certain Control Rods or Control Rod Drive mechanisms. Our current l restrictive wording of Technical Specifications prohibits removal of more 37 than one control rod at a time when the mode switch is in the " refuel" position,and also prohibits operation of the refueling platform when one 1x99 04a rod is out of position. The change would allow for more than one rod to be 7 9112 '2 0 3 7 h

Boe[DN Eo: SON COMPANY Mr. Thomas A. Ippolito, Chief Nove-ber 21, 1979 Page 2 removed at a time by bypassing the "one rod As out circuitry",

such, it wouldwhen be the reactor possible to mode switch is in the " refuel" position.

repair more than one rod at a time which would sutstantially reduce mainten-ance outage time, and in turn lower personnel radiation exposures associated with such maintenance.

Safety Considerations These specifications ensure that maintenance or repair of control rods or control rod drives will be performed under conditions that limit the prob-ability of inadvertent criticality. The operation is performed with the mode switch in the " Refuel" position to provide the refueling interlocks normally available during refueling as explained in the Bases for Specifica-tion 3.10.A. In order to withdraw more than one control rod, it is necessary to bypass the refueling interlock on each withdrawn control rod which prevents more than one control rod from being withdrawn at a time. The requirement that the fuel assemblies in the cell controlled by the control rod be removed f rom the reactor core before the interlock can be bypassed insures that with- Each drawal of another control rod does not result in inadvertent criticality.

control rod essentially provides reactivity control for the fuel assemblies in Thus, removal of an entire cell the cell associated with the control rod.

(fuel assemblies plus control rod) results in a lower reactivity potential of the core.

The methodology utilized in the determination that renoval of one or mulitple controlled cells during cold shutdown conditions leads to a less reactive state was discussed with NRC ataff personnel on October 12, 1979 (Reference (a)). A report on this subject is in process and it is anticipated it will be submitted separately on or about December 1,1979.

Thest changes have been reviewed by the Nuclear Safety Review and Audit Committee and revitaed and approved by the Operations Review Committee.

Schedule of Change Boston Edison Company intends to make modifications during the January 1980 refueling outage whose duration could be minimized by use of this Technical Specification Ctange. Thus Boston Edison would like this proposed Technical Specification Change to be effective upon NRC approval. As previously mentioned, this letter is being sent with a report to follow, in order to initiate this change into the Commission's Technical Specification Amendment process without delay.

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Fee Consideration

- In accordance with Section 170.12 of the Commission's Regulations, Boston Edison proposes this license change as Class III. Accordingly a check for Four Thousand Dollars ($4,000) is enclosed.

1399 044

BOSTON EDISDN COMPANY Mr. Thomas A. Ippolito, Chief November 21, 1979 Page 3 Should you have any further questions on this subject, please do not hesitate to contact us.

Very truly yours, f7 2 ()

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Attachments 3 signed originale and 37 copies Commonwealth of Massachusetts)

County of Suffolk )

Then personally appeared before L a J. Edward Howard, who, being duly sworn, did state that he is Vice President - Nuclear of Bostot Edison Company, the applicant herein, and that he is duly authorized to execute and file the sub-mittal contaiaed herein in the name and on behalf of Boston Edison Company and that the statements in said submittal are true to the best of his knowledge and belief.

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