ML20046A215
| ML20046A215 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/13/1993 |
| From: | Edison G Office of Nuclear Reactor Regulation |
| To: | Sieber J DUQUESNE LIGHT CO. |
| References | |
| NUDOCS 9307270101 | |
| Download: ML20046A215 (4) | |
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UNITED STATES i'
NUCLEAR REGULATORY COMMISSION g
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WASHINGTON, D.C. 20555-0001 July 13, 1993 Docket Nos. 50-334 and 50-412 Mr. J. D. Sieber, Senior Vice President and Chief Nuclear Officer Nuclear Power Division Duquesne Light Company Shippingport, Pennsylvania 15077-0004
Dear Mr. Sieber:
SUBJECT:
REVIEW 0F CHANGES TO EMERGENCY CORE COOLING SYSTEM PERFORMANCE-EVALUATION (10 CFR 50.46 REPORT)
.The purpose of this letter is to inform you of the results of our review of your annual report of changes to your Beaver Valley emergency core cooling system (ECCS) performance evaluation.
That report, required by 10 CFR 50.46, was submitted by you on July 20, 1992. We have concluded that 10 CFR 50.46 requires you to provide, on an expedited basis, either a schedule for reanalysis of the limiting case small-break events for Units 1 and 2 and of large-break events for Unit 2, or a clarification justifying compliance with the requirements of 10 CFR 50.46(a).
On July 20, 1992, Duquesne Light Company submitted its annual 10 CFR 50.46 report of changes or errors in the ECCS analyses for its Beaver Valley Power Station (BVPS) Units 1 and 2.
That report contained a list of changes or errors in the licensing basis large-and small-break loss-of-coolant accident (LOCA) analyses for the Beaver Valley units, and identified an associated calculated peak cladding temperature. (PCT) change for each. The resulting estimated PCTs for the two units were:
BVPS-1 Large Break LOCA - 2149 'F BVPS 1 Small Break LOCA - 2010 *F BVPS-2 Small Break LOCA - 2191 *F BVPS-2 Small Break LOCA - 2176 *F The report reflected significant changes (per 10 CFR 50.46(a) definition) in all analyses except the BVPS-1 large-break LOCA analyses. The submittal concluded that since none of the calculated temperatures exceeded 2200 *F, no further action was required; however,10 CFR 50.46 requires further action if significant changes to, or errors in, an acceptable evaluation model are determined to have been made based on the results of ECCS performance calculations.
On February 19, 1993, you submitted a proposal to reduce the minimum reactor coolant system (RCS) total flow required in the BVPS 1 and 2 technical i
specifications. Our review of that issue involved a related consideration of-O h$ f Oohk OSO)oS34-
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J. D. Sieber July 13, 1993 BVPS ECCS analyses and changes to the analyses of record. During that review the following estimated LOCA analysis PCTs were provided by you, including consideration of changes since the July 20, 1992 report:
BVPS-1 Large Break LOCA - 2153 *F BVPS-1 Small Break LOCA - 2197 'F BVPS-2 Large' Break LOCA - 2166 'F.
BVPS-2 Small ' Break LOCA - 2176 *F We note that, in the process of making the model. changes, small-break LOCA events appear to have become limiting at PCT values very close to the 10 CFR 50.46 acceptance criterion (2200 *F).
From-our review, we conclude that significant changes, per 10 CFR 50.46 definition, have taken place affecting the BVPS 1 and 2 LOCA analyses of record, such that for all analyses, except the BVPS-1 large-break LOCA case, you should propose a schedule for reanalysis or other action to remain in conformance with 10 CFR 50.46.
1 The requirements of this letter affect fewer than 10 respondents, and, therefore, are not subject to the Office of Management and Budget review under PL 96-511.
Sincerely, Original signed by:
Gordon E. Edison, Senior Project Manager Project Directorate I-3 Division of Reactor Projects - I/II-Office of Nuclear Reactor Regulation cc:
See next page DISTRIBUTION:
Docket-File.
SLittle MCaruso NRC & Local PDRs GEdison F0rr PDI-3 Reading OGC SVarga ACRS (10)
JCalvo JLinville, RI WButler RJones, Jr.
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D:PDI-3 SM]e GEdison:mW RJones WButler,h mE d l993
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DATE OFFICl4L RECORD COPY
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FILENAME: A:\\BVRCCS.LTR
9 J. D. Sieber July 13, 1993 BVPS ECCS analyses and changes to the analyses of record.
During that review the following estimated LOCA analysis PCTs were provided by you, including consideration of changes since the July 20, 1992 report:
BVPS-1 Large Break LOCA - 2153 'F BVPS-1 Small Break LCCA - 2197 'F BVPS-2 Large Break LOCA - 2166 *F BVPS-2 Small Break LOCA - 2176 *F We note that, in the process of making the model changes, small-break LOCA events appear to have become limiting at PCT values very close to the 10 CFR 50.46 acceptance criterion (2200 *F).
From our review, we conclude that significant changes, per 10 CFR 50.46 definition, have taken place affecting the BVPS I and 2 LOCA analyses of record, such that for all analyses, except the BVPS-1 large-break LOCA case, you should propose a schedule for reanalysis or other action to remain in conformance with 10 CFR 50.46.
The requirements of this letter affect fewer than 10 respondents, and, therefore, are not subject to the Office of Management and Budget review under PL 96-511.
Sincerely, Gordon E. Edison, Senior Project Manager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc:
See next page
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Mr. J. D. Sieber Beaver Valley ' Power Station Duquesne Light Company Jnits 1 & 2 cc:
Bureau of Radiation Protection Jay E. Silberg, Esquire Pennsylvania Department of Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW.
Environmental Resources Washington, DC 20037 ATTN:
R. Barkanic Post Office Box 2063 Nelson Tonet, Manager Harrisburg, Pennsylvania 17120 Nuclear Safety Duquesne Light Company Mayor of the Borrough of Post Office Box 4 Shippingport Shippingport, Pennsylvania 15077 Post Office Box 3 Shippingport, Pennsylvania-15077 Commissioner Roy M. Smith West Virginia Department of Labor Regional Administrator, Region I Building 3, Room 319 U.S. Nuclear Regulatory Commission Capitol Complex 475 Allendale Road.
Charleston, West Virginia 25305 King of Prussia, Pennsylvania 19406 John D. Borrows Resident Inspector Director, Utilities Department U.S. Nuclear Regulatory Commission Public Utilities Commission Post Office Box 181 180 East Broad Street Shippingport, Pennsylvania 15077-Columbus, Ohio 43266-0573 George S. Thomas Director, Pennsylvania Emergency
'Vice President, Nuclear Services Management Agency Nuclear Power Division Post Office Box 3321 Duquesne Light Company Harrisburg, Pennsylvania 17105-3321 Post' Office Box 4 Shippingport, Pennsylvania 15077 Ohio EPA-DERR i
ATTN:
Zack A. Clayton Post Office Box 1049 I
Columbus, Ohio 43266-0149 l
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