ML20070L006

Forwards Proprietary Info Re Evaluation of Qualification Fuel Bundles Planned to Be Loaded During First Refueling Outage Scheduled for 910323.Encl Withheld

ML20070L006
Person / Time
Site:	Limerick
Issue date:	03/11/1991
From:	Beck G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19310D330	List: ML20070L006
References
NUDOCS 9103190243
Download: ML20070L006 (3)

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PHILADELPHIA ELECTRIC COMPANY NUCLEAR GROUP HEADQUARTERS 955 65 CHESTERBROOK BLVD.

WAYNE, PA 19007 5691 (ris) seo so00 March 11, 1991 '

Docket No. 50-353 License No. NPF-85 U.S. Nuclear Regulatory Commission ATTH: Document Control Desk Washington, DC 20555

SUBJECT:

Limer1.k Generating Station, Unit 2 Qualification fuel Bundles in Operating Cycle 2 ,

Dear Sirs:

Philadelphia Electric Company (PECo) plans to load twelve (12) commercially available qualification fuel bundles (QFbs) into Limerick Generating Station (LGS), Unit 2 during the first refueling outage scheduled to begin March 23, 1991. Accordingly, the purpose of this letter is to provide the NRC with informaticr regarding our evaluation of these QFBs. These QFBs are comprised of four (4) General Electric (GE) Company Gell QFBs, four (4) ABB Atom (ABBA), Inc.

SVEA-96 QFBs, and four (4) Advanced Nuclear Fuels (ANF) Corp. 9x9-9X+ QFBs. The Gell QFBs are a 9x9 design featuring part length fuel rods, the SVEA-96 QFBs a? c a 10x10 design featuring a water cross, and the ANF 9x9-9X+ QFBs are a 9x9 i design featuring a large central water channel. Fuel bundles similar to each of these designs are currently operating in a domestic Boiling Water Reactor (BWR).

The remainder of the reload bundles will be GE9B fuel.

Detailed descriptions of the Gell, SVEA-96, and ANF 9x9-9X+ QFBs are provided in Attachments 1, 4, and 5, respectively. Figures depicting the fuel I

rod lattice of the QFBs including U-235 enrichment and gadolinia distributions are also provided in these Attachments. Attachments 1 through 3 list the major faatures and design specifications of the Gell, SVEA-96 and ANF 9x9-9X+ QFBs, re.: t acti vely.

GE has designed and analyzed the Gell QFBs using NRC approved methods. The Gell QFBs are designed for, and meet, the same nuclear-thermal-mechanical criteria as standard reload bundles. Furthermore, analyses will be performed for the Gell QFBs specifically for operation during LGS Unit 2 Cycle 2 and subsequent cycles wherein the effect of the four GE QFBs will be considered for each of the applicable design basis events to establish appropriate core thermal limits. These analyses will be reviewed by the Plant Operations Review Committee ( 9RC) and approved prior to Unit 2 startup from the first refueling outage.

9103190243 910311 fDR ADOCK 05000353

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U.S. Nuclear R,egulatory Connission March 11, 1991 Page 2 The SVEA-96 and ANF 9x9-9X+ QFBs have been designed to bc mechanically, thermal-hydraulically, and neutronically compatible with the LGS Unit 2 Cycle 2 GE9B reload fuel bundle (i.e., GE98-P8CWB325-9GZ21032-80M-150-T). Analyses have been performed by ABBA and ANF to verify this compatibility and to conservatively evaluate the response of these QFBs to each of the appropriate design basis events relative to the GE9B reload bundle. The results of these analyses demonstrate that the SVEA-96 ar.d ANF 9x9 9X+ QFBs are conservatively bounded by the GE9B reload fuel bundle analyses and can be safely operated in the reactor core and monitored by the plant process computer. These analyses will be reviewed by PORC and approved prior to Unit 2 startup from the first refueling outage. With regard to minimum ciritical power ratio (MCPR), the results of the analyses establish the effective operating limit MCPRs for the QFBs relative to the GE98 reload fuel bundle. These results will be utilized to conservatively set the operating limit MCPR for each QFB in the LGS Unit 2 Cycle 2 Core Operating Limits Report these limits, along with the fuel bundle uranium mass, will then be supplied in the plant process computer for monitoring QFBs during operation. No other SVEA-96 or ANF 9x9-9X+ QFB specific data or constants need to be input to the plant process computer databank. The results of these analyses are summarized in Attachments 4 and 5.

Attachment 6 to thit letter identifies the anticiptted reactor core loadin!

positions for eech of the QFBs. These positions, which are typically lower in power than more central reactor core positions, will further assure that the QFBs will not be limiting fuel bundles with respect to thermal limits. As part of our routine reactor core management activities, exposure-dependent control rod patterns have been developed to meet all reactor core operating limits and to Verify that operating margins exist between tN QFBs and the limiting fuel bundles. These margins will be maintained by reactor core monitoring activities, Attachments 1 through 5 of this letter contain information which is proprietary to GE, ABBA, and ANF. Accordingly, we request that these attachments be withheld from public disclosure in accordance with the provisions l of 10 CFR 2.790(b)(1). Affidavits supporting this request are included in

Attachments 1 thrcugh 5.

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

l Very truly yours, I

G. J. Beck, Manager Licensing Nuclear Engineering and Support m-- - ---- g- p , .,a.,--,,,--ev. w q m pe, e-

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U.S. Nuclear Regulatory Commission March 11, 1991 Page 3

'l Attachment 1 - GEli Lead fuel Assembly Description and accompanying affidavit Attachment 2 - ABBA SVEA-96 Design Features and Specifications and accompanying affidavit Attachment 3 - ANF 9x9-9X+ Design Features and Specifications and accompanying affidavit Attachment 4 - ABBA Report BR-91-042 and accompanying affidavit Attachment 5 - ANF Report ANF-90-193(P) and accompanying affidavit Attachment 6 - QFD Core Loading Positions cc: T. T. Martin, Administrator, Region 1, USNRC w/ attachments T. J. Kenny, USMC Senior Resident inspector, l.GS w/ attachments I

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