ML18004B824

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Application for Amend to License NPF-63,requesting Increased Fuel Enrichment to 4.2% U-235. Criticality Analysis of Shearon Harris Fuel Racks. Also Encl.Fee Paid
ML18004B824
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 05/26/1987
From: Cutter A
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML18004B825 List:
References
NLS-87-109, NUDOCS 8706050160
Download: ML18004B824 (6)


Text

B RE STORY INFORMATION DISTRIB ON SYSTEN (R IDS)

ACCESSION NBR: 8706050160 DOC. DATE: 87/05/26 NOTARIZED: NO DOCKET ¹ FACIL: 50-400 Shearon Harris Nuclear Pouer Pianti Unit 1> Carolina 05000400 AUTH. RANE AUTHOR AFFILIATION CUTTER> A. B. Carolina Pomer Zc Light Co.

RECIP. NAI'IE 'ECIPIENT AFFILIATION Document Control Branch <Document Control Desk )

SUBJECT:

Applicat'ion for amend to License NPF-63I requesting increased Fuel enrichment to 4. 2/ U-235. "Criticality Analgsi s oF Bhearon HaTris Fuel Racks. " also encl. Fee paid.

DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED: LTR Submittal: General Distribution I ENCL / SIZE: P~+

NOTES: Application For permit reneual Filed. 05000400 RECIPIENT COPIEB RECIPIENT COPIES ID CODE/NAI'IE LTTR ENCL ID CODEINANE LTTR ENCL PD2-1 LA 0 PD2-1 PD 5 5 BUCKLEY> B 1 INTERNAL: ACRB 6 6 ARI"I/DAF/LFNB 1 0 NRR/DEBT/ADE 1 MRR/DEBT/ADS 1 NRR/DOEA/TSB Y S/ILRB 1 1 OQC/HDB1 0 EC FIL 0'1 1 EXTERNAL: EQRcQ BRUBKEi B 1 1 LPDR NRC PDR MSIC gk<~

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Carolina Power 8 Ught Company P. O. Box 1551 ~ Raleigh, N. C. 27602 (919) 8364231 SERIAL: NLS-87-109 MAY 26 Iy A. B. CUTTER Vice President Nuclear Engineering & Ucensing United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-000/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT INCREASED FUEL ENRICHMENT TO 0.2 PERCENT Gentlemen:

SUMMARY

In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power R Light Company (CPrtcL) hereby requests a revision to the Technical Specifications (TS) for the Shearon Harris Nuclear Power Plant (SHNPP). The proposed change. concerns the storage and handling of fuel with an increased enrichment to 0.2 weight percent-.U-235. fhe enclosed marked-up TS pages'increase the allowed'fuel limit to accommodate the reload fuel being received for next cycle. The request is supported by the enclosed Westinghouse report, "Criticality Analysis of Shearon Harris Fuel Racks, 3anuary 1987." The scope of this request is limited to the handling and stot age of these more highly enriched fuel elements. Operation with the increased enrichment will be addressed in subsequent reload analyses.

SIGNIFICANT HAZARDS ANALYSIS The Commission has provided standards in 10CFR50.92(c) for determining whether a significant hazards consideration exists. A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not: (I) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety.

The following discussion is limited to the fuel storage and handling accident scenarios in the enclosed report. The impact of core enrichment upon operational safety margins is an integral part of each reload analysis. Carolina Power R Light Company has reviewed this request and determined that:

1. The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated. Fuel handling accidents remain bounded by the original FSAR analysis. The only accident scenarios for which the probability of occurrence are affected by fuel eel o) 870b0501b0 87052 PDR ADOCK 05000 QP gO p P R

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NLS-87-109 / Page 2 enrichment involve criticality events during fuel handling and storage. The enclosed criticality safety analysis demonstrates that the calculated Ke ff during fuel handling and storage is adequate to ensure subcriticality for all defined accident conditions. Since subcriticality is maintained, no releases result from the above fuel handling criticality accident scenarios. Therefore, the consequences of these accidents are not increased.
2. The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated. The only potential impact of increased enrichment upon fuel storage and handling involves the potential for criticality which has been addressed above.
3. The proposed amendment does not involve a significant reduction in the margin of safety.'he enclosed criticality analysis demonstrates that there is adequate margin to ensure subcriticality of the fuel during storage and .

handling operations.

The requested amendment is most similar to example (iii) of "Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" provided via 51FR 7751, March 6, 1986.

ADMINISTRATIVEINFORMATION The Company has evaluated this request in accordance with the provisions of 10CFR170.12 and determined that a license amendment application fee is required. A check for $ 150 is enclosed in payment of this fee.

Completion of your review is needed no later than December =31, 1987 so.that- fuel as scheduled for use in Cycle 2. Please refer any questions regarding this can'be'eceived submittal to Mr. Sherwood R. Zimmerman at (919) 836-6202.

Yo s very t ly, A. B. Cutter 3HE/lah (52033DK)

Enclosures A. B. Cutter, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power R Light Company.

Nota y Seal QJ My commission expires: 5/(8/9Q g yo4 cc: Mr. D. H. Brown (State of NC) ~, POsuc,.~,=

Mr. B. C. Buckley (NRC)

Dr. J. Nelson Grace (NRC-RII)

Mr. G. F. Maxwell (NRC-SHNPP) llllllllllll

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