ML20023B726

Application to Amend License DPR-71 Revising Tech Specs to Complete Third Refueling Outage & Begin Cycle 4 Operation. Proposed Changes Revise Control Rod Scram Insertion Time Requirements

ML20023B726
Person / Time
Site:	Brunswick
Issue date:	05/02/1983
From:	Howe P CAROLINA POWER & LIGHT CO.
To:	Vassallo D Office of Nuclear Reactor Regulation
Shared Package
ML20023B727	List: ML20023B726 ML20023B728
References
LAP-83-99, NUDOCS 8305060176
Download: ML20023B726 (2)

Text

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SERIAL: LAP-83-99 Carolina Power & Light Company MAY 931983 Director of Nuclear Reactor Regulation Attention: Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 DOCKET NOS. 50-325 LICENSE NOS. DPR-71 REQUEST FOR REVISION TO TECHNICAL SPECIFICATIONS FUEL CYCLE NO. 4 - RELOAD LICENSING

Dear Mr. Vassallo:

SUfDfARY In accordance with the Code of Federal Regulations, Title 10, Part 50.90 and Part 2.101, Carolina Power & Light Company (CP&L) hereby requests revisions to the Technical Specifications (TS) for Brunswick Steam Electric Plant, Unit No. 1 (BSEP-1). These revisions are necessary to complete the third refueling of Unit No. I and begin Cycle 4 operation.

Changes to the TS are indicated by vertical lines in the right hand nargin of the affected pages which are attached.

DISCUSSION The BSEP-1 refueling outage is presently scheduled to end on June 24, 1983. Forty (40) copies of General Electric Report No. Y1003J01 A52,

" Supplemental Reload Licensing Submittal for BSEP-1, Reload 3 (without recirculation pump trip)" are attached to the letter.

Also enclosed are proposed changes to the TS that revise the control rod scram insertion time requirements listed in Specifications 3.1.3.3 and 3.1.3.4, which are used in proposed Specification 3.2.3.2. These time requirements were correct in the original Brunswick-2 Custom Technical Specifications, where they were listed in terms of percent of control rod insertion. When the change was made from Custom Technical Specifications to Standard Technical Specifications for Brunswick-2, the scran times were listed in terms of rod notch position. Since the rod notch position did not correspond precisely to percent of rod insertion, an offset of some of the 9 scram time limits were erroneously introduced. These Brunswick-2 TS were the L C)d)l model that the Brunswick-1 TS were based upon. The requested revision to the 'S Brunswick-1 TS will correct these errors. Of the four listed values of scram 40 8305060176 Gl:M1502 PDR ADOCM 05000325

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'D. B. Vassallo time, the proposed revision will increase one time limit slightly while decreasing the other three. The net result is a set of points which are on a line defined by the original data points that were described in terms of percent control rod insertion versus time.

ADMINISTRATIVE INFORMATION In accordance with 10 CFR 170.22, we have determined that this request constitutes a Class III amendment request. Our check for $4,000 is enclosed as payment for this amendment fee.

Should you have any questions concerning this submittal, please contact ,

our staff.

Yours very truly, G.w P. W. Howe Vice President Brunswick Nuclear Project JSD/pgp (6601JSD)

Enclosures cc: Mr. S. D. MacKay (NRC)

Mr. D. O. Myers (NRC-BSEP)

Mr. J. P. O'Reilly (NRC-RII)

P. W. Howe, having been first duly sworn, did depose and say that the information contained herein is true and correct to his own personal knowledge or based upon information and belief.

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