ML031410680

(TMI-1), Cycle 15 Core Reload Design Request for Additional Information (RAI)

ML031410680
Person / Time
Site:	Three Mile Island
Issue date:	05/21/2003
From:	Colburn T NRC/NRR/DLPM/LPD1
To:	Skolds J AmerGen Energy Co
Colburn T, NRR/DLPM, 415-1402
References
TAC MB7270
Download: ML031410680 (6)

Text

May 21, 2003 Mr. John L. Skolds, Chairman and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, UNIT 1 (TMI-1), CYCLE 15 CORE RELOAD DESIGN REQUEST FOR ADDITIONAL INFORMATION (RAI) (TAC NO. MB7270)

Dear Mr. Skolds:

By letter dated January 16, 2003, you requested approval for changes to the TMI-1 Technical Specifications (TSs) associated with the Cycle 15 core reload design analysis. The Nuclear Regulatory Commission staff has reviewed your request and determined that it will need the additional information contained in the enclosure to complete its review. This information was faxed to your staff on May 5, 2003, in preparation for a May 13, 2003, conference call. As discussed with and agreed to by your staff during that call, you are requested to provide your response within 30 days of receipt of this request.

If you have any questions, please contact me at 301-415-1402.

Sincerely,

/RA/

Timothy G. Colburn, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-289

Enclosure:

RAI cc w/encl: See next page

May 21, 2003 Mr. John L. Skolds, Chairman and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, UNIT 1 (TMI-1), CYCLE 15 CORE RELOAD DESIGN REQUEST FOR ADDITIONAL INFORMATION (RAI) (TAC NO. MB7270)

Dear Mr. Skolds:

By letter dated January 16, 2003, you requested approval for changes to the TMI-1 Technical Specifications (TSs) associated with the Cycle 15 core reload design analysis. The Nuclear Regulatory Commission staff has reviewed your request and determined that it will need the additional information contained in the enclosure to complete its review. This information was faxed to your staff on May 5, 2003, in preparation for a May 13, 2003, conference call. As discussed with and agreed to by your staff during that call, you are requested to provide your response within 30 days of receipt of this request.

If you have any questions, please contact me at 301-415-1402.

Sincerely,

/RA/

Timothy G. Colburn, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-289

Enclosure:

RAI cc w/encl: See next page DISTRIBUTION:

PUBLIC JUhle OGC TColburn PDI-1 Reading SColpo ACRS MOBrien RLaufer BPlatchek, Rgn-I DOCUMENT NAME: G:\PDI-1\TMI-1\MB7270RAI.WPD Accession Number: ML031410680 *See previous concurrence OFFICE PDI-1/PM PDI-1/LA SRXB/SC PDI-1/SC NAME TColburn MOBrien JUhle* RLaufer DATE 5/14/03 5/14/03 05/14/03 5/21/03 OFFICIAL RECORD COPY

REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED AMENDMENT TO TECHNICAL SPECIFICATIONS IMPLEMENTATION OF STATISTICAL CORE DESIGN THREE MILE ISLAND NUCLEAR STATION, UNIT 1 DOCKET NO. 50-289 By letter dated January 16, 2003, AmerGen Energy Company, LLC (the licensee) submitted a proposed amendment to the Technical Specifications (TSs) for Three Mile Island Nuclear Station, Unit 1 (TMI-1). The proposed amendment would implement the Statistical Core Design (SCD) Methodology described and approved in Framatome ANP Topical Report, BAW-10187P-A.

The Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed TS changes. In order for the staff to complete its evaluation, the following additional information is requested:

1. As discussed in the NRC staff's letter dated March 24, 1993, that transmitted the safety evaluation for Topical Report BAW-10187P-A to Framatome ANP, the topical report is acceptable for referencing in license amendment applications to the extent specified, and under the limitations delineated in the report, and in the associated safety evaluation.

Page 4 of Enclosure 1 of your submittal states that the restrictions specified in the approved topical report have been addressed in the core reload design analysis for TMI-1.

Please provide the information needed to justify your plant-specific application of this methodology by identifying any TMI-1 features or conditions outside the range of the generic assessment. Refer to Table 3-4 of BAW-10187P-A that specifies the range of applicability.

Additionally, the hot pin statistical design limit of 1.313 is acceptable with the following limitations. Please provide justification for your plant-specific application of this methodology.

a. The component uncertainties and their distributions are to be reviewed on a plant-specific basis to determine their applicability.

b. The bounding assembly-wise power distribution assumed in the core-wide SCD calculation should be shown to bound the expected operating power distributions on a cycle-specific basis.

c All core state variables that were not included in the statistical design must continue to be input to thermal-hydraulic computer codes at their most adverse allowable level rather than at their nominal value.

Enclosure

d. The response surface model should be validated and revised (as necessary) when applied to new fuel assembly designs and extended operating conditions, and with new computer codes and departure from nucleate boiling (DNB) correlations. The approved

codes are LYNXT, LYNX1, and LYNX2, and the approved correlation is the BWC DNB correlation.

Three Mile Island Nuclear Station, Unit 1 cc:

Site Vice President - Three Mile Island Nuclear AmerGen Energy Company, LLC Station, Unit 1 P. O. Box 480

Middletown, PA 17057 Rich Janati, Chief Division of Nuclear Safety Senior Vice President Nuclear Services Bureau of Radiation Protection AmerGen Energy Company, LLC Department of Environmental Protection 4300 Winfield Road Rachel Carson State Office Building Warrenville, IL 60555 P.O. Box 8469 Harrisburg, PA 17105-8469 Vice President - Mid-Atlantic Operations Support AmerGen Energy Company, LLC Three Mile Island Nuclear Station, Unit 1 200 Exelon Way, KSA 3-N Plant Manager Kennett Square, PA 19348 AmerGen Energy Company, LLC P. O. Box 480 Senior Vice President - Middletown, PA 17057 Mid Atlantic Regional Operating Group AmerGen Energy Company, LLC Regulatory Assurance Manager - Three Mile 200 Exelon Way, KSA 3-N Island Nuclear Station, Unit 1 Kennett Square, PA 19348 AmerGen Energy Company, LLC P.O. Box 480 Vice President - Middletown, PA 17057 Licensing and Regulatory Affairs AmerGen Energy Company, LLC John F. Rogge, Region I 4300 Winfield Road U.S. Nuclear Regulatory Commission Warrenville, IL 60555 475 Allendale Road King of Prussia, PA 19406 Regional Administrator Region I Michael A. Schoppman U.S. Nuclear Regulatory Commission Framatome ANP 475 Allendale Road Suite 705 King of Prussia, PA 19406 1911 North Ft. Myer Drive Rosslyn, VA 22209 Chairman Board of County Commissioners of Dauphin County Dauphin County Courthouse Three Mile Island Nuclear Station, Unit 1 Harrisburg, PA 17120 cc: continued Chairman Board of Supervisors Vice President, General Counsel and Secretary of Londonderry Township AmerGen Energy Company, LLC R.D. #1, Geyers Church Road 2301 Market Street, S23-1 Middletown, PA 17057 Philadelphia, PA 19101 Senior Resident Inspector (TMI-1) Dr. Judith Johnsrud U.S. Nuclear Regulatory Commission National Energy Committee P.O. Box 219 Sierra Club Middletown, PA 17057 433 Orlando Avenue State College, PA 16803 Director - Licensing - MId-Atlantic Regional Operating Group Eric Epstein AmerGen Energy Company, LLC TMI Alert Nuclear Group Headquarters 4100 Hillsdale Road Correspondence Control Harrisburg, PA 17112 P.O. Box 160 Kennett Square, PA 19348 Correspondence Control Desk

AmerGen Energy Company, LLC 200 Exelon Way, KSA 1-N Kennett Square, PA 19348 Manager Licensing - Oyster Creek and Three Mile Island AmerGen Energy Company, LLC Nuclear Group Headquarters Correspondence Control P.O. Box 160 Kennett Square, PA 19348