LIC-03-0110, Unit No.1 TS Updated for NRC Comments on Pending Amendment Request on Pressure-Temperature Limits Report

Unit No.1 TS Updated for NRC Comments on Pending Amendment Request on Pressure-Temperature Limits Report

ML032190363
Person / Time
Site:	Fort Calhoun
Issue date:	08/05/2003
From:	Clemens R Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-03-0110
Download: ML032190363 (6)

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Onaha Public Power stc 444 South 16th Street Mall Omaha NE 68102-2247 August 5, 2003 LIC-03-0110 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

References:

1. Docket No. 50-285

2. Letter from OPPD (D. J. Bannister) to NRC (Document Control Desk) dated October 8, 2002, Fort Calhoun Station Unit No. 1 License Amendment Request, "Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)" (LIC-02-0109)

3. Letter from OPPD (R. T. Ridenoure) to NRC (Document Control Desk) dated April 10, 2003, Response to Request For Additional Information, Pressure-Temperature Limit Report Amendment Request (LIC-03-0052)

4. Letter from OPPD (R. T. Ridenoure) to NRC (Document Control Desk) dated May 20, 2003, Response to Request for Additional Information, Pressure-Temperature Limits Report Amendment Request; Low Temperature Over Pressure (LIC-03-0081)

5. Letter from OPPD (R. T. Ridenoure) to NRC (Document Control Desk) dated July 31, 2003, Fort Calhoun Station Unit No. 1, Technical Specifications Updated for NRC Comments on Pending Amendment Request on the Pressure-Temperature Limits Report (LIC-03-0104)

SUBJECT:

Fort Calhoun Station Unit No. 1 "Technical Specifications Updated for NRC Comments on Pending Amendment Request on the Pressure-Temperature Limits Report" In support of the license amendment request, "Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)" (Reference 2), the Omaha Public Power District (OPPD) provided responses to the Nuclear Regulatory Commission (NRC) Requests for Additional Information in Reference 3 and 4. This transmittal re-submits Page 5-lOa of the proposed Technical Specifications which were originally submitted by Reference 5. The attached proposed Technical Specifications have been updated to include an additional reference to Technical Specification 5.9.6 requested by the NRC during their review of the amendment request.

I declare under penalty of perjury that the forgoing is true and correct (Executed on August 5, 2003). No commitments are made to the NRC in this letter.

Employment with Equal Opportunity km

U. S. Nuclear Regulatory Commission LIC-03-01 10 Page 2 If you have any questions or require additional information, please contact Dr. R. L. Jaworski of the Fort Calhoun Station Licensing staff at (402) 533-6833.

Division Manager Nuclear Assessments RPC/rrl Attachments: 1. Marked-Up - Technical Specifications Updated for Pending Amendment of the Pressure-Temperature Limits Report - Replacement Page

2. Clean Copy - Technical Specifications Updated for Pending Amendment of the Pressure-Temperature Limits Report - Replacement Page c: T. P. Gwynn, Acting Regional Administrator, NRC Region IV A. B. Wang, NRC Project Manager J. G. Kramer, NRC Senior Resident Inspector Division Administrator, Public Health Assurance, State of Nebraska

LIC-03 -01 10 Page 1 Attachment 1 Marked-Up Technical Specifications Updated for Pending Amendment of the Pressure-Temperature Limits Report Replacement Page

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LIC-03 -01 10 Page 1 Attachment 2 Clean Copy Technical Specifications Updated for Pending Amendment of the Pressure-Temperature Limits Report Replacement Page

- TECHNICAL SPECIFICATIONS 5.0 ADMINISTRATIVE CONTROLS 5.9.6 Reactor Coolant System (RCS) Pressure - Temperature Limits Report (PTLR)

a. RCS pressure and temperature limits for heatup, cooldown, low temperature overpressure protection, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for Technical Specifications 2.1.1 and 2.1.2.

b. The analytical methods used in the PTLR shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. CE NPSD-683-A, Revision 6, "Development of a RCS Pressure and Temperature Limits Report for the Removal of P-T Limits and LTOP Requirements from the Technical Specifications," April 2001.

2. WCAP-1 5443, Revision 0, "Fast Neutron Fluence Evaluations for the Fort Calhoun Unit I Reactor Pressure Vessel," July 2000.

3. Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment Number 199 to Facility Operating License DPR-40 Omaha Public Power District Fort Calhoun Station, Unit Number 1, dated June 7, 2001.

4. CEN-636, Revision 2, "Evaluation of Reactor Vessel Surveillance Data Pertinent to the Fort Calhoun Reactor Vessel Beltline Materials, dated July 2000.

5. FC06876, Revision 0, "Performance of Low Temperature Overpressure Protection System Analyses Using RELAP5: Methodology Paper.'

6. FC06877, "Low Temperature Overpressure Protection (LTOP) Analysis, Revision 1."

7. Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment Number 207 to Facility Operating License Number DPR-40 Omaha Public Power District Fort Calhoun Station, Unit Number 1, dated April 22, 2002.

8. Letter LTR-CI-01-25, Revision 0 from Westinghouse Electric Company (S.T. Byme) to OPPD (J. Jensen), "Assessment of Extended Beltline Limit for Fort Calhoun Station Reactor Pressure Vessel," dated December 18, 2001.

9. WCAP-1 5741, Revision 0, "Reactor Vessel Surveillance Program Withdrawal Schedule Modifications," dated September 2001.

10. Letter from NRC (A. B. Wang) to Omaha Public Power District (R.T.

Ridenoure), Fort Calhoun Station - Unit 1, Exemption from the Requirements of Appendix G to 10 CFR Part 50 (TAC No. MB8237), dated July 30, 2003.

11. Letter from Information Systems Laboratories (William Arcieri) to OPPD (J, Jensen), 'WCA-09-2002: Transmittal of RELAP5/MOD3.2d," dated August 2, 2002

c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period (i.e., the number of EFPY used in the P-T limitILTOP analysis) and for any revision or supplement thereto.

5-10Oa Amendment No.