ML060520230

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Request for Additional Information, Estimate Loss of Coolant Accident Analysis Methodology in WCAP-16009-P
ML060520230
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 03/15/2006
From: Martin R
NRC/NRR/ADRO/DORL/LPLC
To: Stinson L
Southern Nuclear Operating Co
Martin R, NRR/DORL, 415-1493
References
TAC MC8588, TAC MC8589, WCAP-16009-P
Download: ML060520230 (4)


Text

March 15, 2006 Mr. L. M. Stinson Vice President - Farley Project Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION RE: USE OF BEST ESTIMATE LOCA ANALYSIS (TAC NOS. MC8588 AND MC8589)

Dear Mr. Stinson:

By letter dated October 6, 2005, Southern Nuclear Operating Company requested a revision to the Joseph M. Farley Nuclear Plant Unit 1 and 2 Technical Specifications to allow the use of the best Westinghouse estimate loss-of-coolant accident analysis methodology in WCAP-16009-P-A, Realistic Large Break LOCA Evaluation Methodology Using Automated Statistical Treatment of Uncertainty Method (ASTRUM). The U.S. Nuclear Regulatory Commission staff has reviewed the application and has determined that additional information is required, as identified in the enclosure.

We discussed these issues with your staff on March 14, 2006. Your staff indicated that you would attempt to provide your response within 30 days of the date you receive the questions.

Please contact me at (301) 415-1493, if you have any other questions on these issues.

Sincerely,

/RA/

Robert E. Martin, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364

Enclosure:

Request for Additional Information cc w/encl: See next page

ML060520230 NRR-088 OFFICE PDII-1/PM LPL2-1/LA LPL2-1/BC NAME RMartin RSola EMarinos DATE 3/14/06 02/28/06 3/15/06

Enclosure REQUEST FOR ADDITIONAL INFORMATION SOUTHERN NUCLEAR OPERATING COMPANY, INC.

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364 The U. S. Nuclear Regulatory Commission (NRC) staff has reviewed Southern Nuclear Operating Companys (SNCs) submittal dated October 6, 2005, regarding the use of the Westinghouse best estimate large break loss-of-coolant accident (LBLOCA) analysis methodology. The NRC staff has identified the following information that is needed to enable the continuation of its review.

1.

Please provide a statement to the effect that: SNC and its LBLOCA analyses vendor have ongoing processes that assure the input values and ranges of parameters for Farley Units 1 and 2 LBLOCA analyses conservatively bound the values and ranges of those parameters for the as-operated Farley plants. (This statement addresses certain programmatic requirements of Title 10 of the Code of Federal Regulations (10 CFR),

Section 50.46(c).)

2.

In Section 4.0, of its October 6, 2005 letter, SNC stated:

a)

Therefore the Unit 2 model was utilized for the subsequent steps of the original application of the best estimate large break LOCA evaluation model.

b)

Moreover, investigations revealed that the remaining differences in the vessels were small enough to justify the use of a single WCOBRA/TRAC geometric model for both Units 1 and 2.

While each plant may individually adopt the same calculation as its initial Analysis of Record (AOR), each plant must identify that analysis as its own specific AOR and track it separately from the other units AOR and AOR tracking, even if the changes and their calculated effects on peak cladding temperature (PCT) are identical for both plants.

This is necessary because it is possible for differences to arise between the units that affect the LOCA analyses for each plant differently.

Please identify all differences between the two Farley units individually and the AOR analytical model, and their effects on calculated PCT, including the remaining differences in the vessels. These differences and PCT effects must be reported in the initial AOR submittal, and subsequent emergency core cooling system reports, as required by 10 CFR 50.46 (a)(3) for each plant separately.

Joseph M. Farley Nuclear Plant cc:

Mr. Don E. Grissette General Manager -

Southern Nuclear Operating Company Post Office Box 470 Ashford, Alabama 36312 Mr. B. D. McKinney, Licensing Manager Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201-1295 Mr. M. Stanford Blanton Balch and Bingham Law Firm Post Office Box 306 1710 Sixth Avenue North Birmingham, Alabama 35201 Mr. J. B. Beasley, Jr.

Executive Vice President Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 State Health Officer Alabama Department of Public Health 434 Monroe Street Montgomery, Alabama 36130-1701 Chairman Houston County Commission Post Office Box 6406 Dothan, Alabama 36302 Resident Inspector U.S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, Alabama 36319 William D. Oldfield SAER Supervisor Southern Nuclear Operating Company P. O. Box 470 Ashford, Alabama 36312