ML20246P562

Provides Addl Info to Support Util 890127 Reload 2 Tech Spec Change Request.Deletion of Tech Spec Page 3/4 2-6d Requested,Per Insps of Fuel Removed from Reactor. Safety Evaluation of Limerick 1,Cycle 3 Revised Core..., Encl

ML20246P562
Person / Time
Site:	Limerick
Issue date:	03/22/1989
From:	Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20246P565	List: ML20246P562 ML20246P567
References
NUDOCS 8903280252
Download: ML20246P562 (2)

Text

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i PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA A PA.19101 (215)841 4000 March 22, 1989 Docket No. 50-352' License No. NPF-39 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk l Washington, D.C. 20555

SUBJECT:

Limerick Generating Station, Unit 1 Additional Information in Support of the l Reloud 2 Technical Specifications Change Request

REFERENCE:

Letter from Philadelphia Electric Company to the NRC, dated January 17, 1989 l

Dear Sir:

Our letter dated January 27, 1989 (Reference), submitted the proposed changes to the Limerick Generating Station (LGS) Unit 1 Technical Specifications, to accommodate the second refueling of the reactor with new, previously irradiated, and reconstituted fuel bundles. As a result of inspections of fuel removed from the reactor during the current refueling outage, particularly the identification of failed fuel rods in Reload 1 fuel bundles, we have made changes to the planned Reload 2 core configuration. These changes (e.g., additional unirradiated fuel will replace most of the Reload 1 fuel) have been evaluated with

, respect to our determination that the proposed Technical Specifications (TS) l Change Request in our January 27. 1989 letter does not constitute an unreviewed safety question. This evaluation was performed by General Electric (GE), the fuel supplier, and concluded that the revised Reload 2 core configuration is bounded by the analysis supporting our TS Change Request and does not constitute an unreviewed safety question. In response to requests for additional information from the NRC representatives performing the review of our Reload 2 TS Change Request, made during a telephnne conversation held on March 9, 1989, the GE evaluation is provided in the enclosure to this letter.

Our January 27, 1989 TS Change Request included a proposed change to add TS page 3/4 2-6d. This proposed change was a curve of Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus average planar exposure for a reconstituted initial core fuel type (i.e., BP8CRB248A), to account for the l

replacement of up to four original irradiated gadolina fuel rods with fresh natural uranium fuel rods. As stated in the TS Change Request, this MAPLGHR curve was provided as a contingency option since, depending upon the results of the fuel inspection program, this particular reconstitution may not be performed. As we have decided not to employ this particular reconstitution option, we request that the proposed addition of TS page 3/4 2-6d, providing a new MAPLHGR curve, be fj 8903280252 890322 i g PDR ADOCK 05000352 P PDC

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Document Control Desk . . March 22, 1989 Page 2 deleted from our January 27, 1989 TS Change Request. This deletion does not affect the information supporting the TS Change Request provided by our January 27, 1989 letter.

If you have any further questions, or require additional information, please contact us.

Very truly yours,

h. f ah-G. A. Hunger, Jr.

Director Licensing Section Nuclear Support Division Enclosure cc: W. T. Russell, Administrator, Region I, USNRC T. J. Kenny, USNRC Senior Resident Inspector, LGS-1 T. Gerusky, Director, PA Bureau of Radiological Protection I

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