RNP-RA/06-0104, Request for Partial Withdrawal of Technical Specifications Change to Core Operating Limits Report References

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Request for Partial Withdrawal of Technical Specifications Change to Core Operating Limits Report References
ML063180233
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 11/09/2006
From: Lucas J
Progress Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/06-0104
Download: ML063180233 (7)
v • d • e


Text

10 CFR 50.90

~ Progress Energy Serial: RNP-RA/06-0104 NOV 0 9 2006 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 REQUEST FOR PARTIAL WITHDRAWAL OF TECHNICAL SPECIFICATIONS CHANGE TO CORE OPERATING LIMITS REPORT (COLR) REFERENCES Ladies and Gentlemen:

In a letter dated April 11, 2006, Carolina Power and Light Company, also known as Progress Energy Carolinas (PEC), Inc., submitted a request for an amendment to the Technical Specifications (TS) contained in Appendix A of the Operating License for H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2. The proposed amendment would have modified TS 5.6.5 to add two NRC-approved topical reports to the Core Operating Limits Report (COLR) methodologies list.

Specifically, the proposed change would have added topical report EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," and topical report EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based." The purpose of this letter is to withdraw the request for the addition of topical report EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," to the COLR methodologies list.

The PEC request is unchanged for approval of the addition of topical report EMF-2310(P)(A),

"SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," to the COLR methodologies list. PEC requests approval by November 30, 2006, to allow for the use of topical report EMF-23 10(P)(A) in the evaluation of end-of-cycle Moderator Temperature Coefficient surveillance limits for the current operating cycle.

The withdrawal of EMF-2328(P)(A) does not impact the basis or conclusions of the technical justification, No Significant Hazards Consideration Determination, and Environmental Impact Consideration for the addition of EMF-2310(P)(A) provided in the amendment request letter dated April 11, 2006.

Progress Energy Carolinas, Inc.

Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550

United States Nuclear Regulatory Commission Serial: RNP-RA/06-0104 Page 2 of 2 Attachment I provides an Affirmation pursuant to 10 CFR 50.30(b).

Attachment II provides a revised markup of the current TS page and Attachment III provides a revised retyped page for the proposed TS.

In accordance with 10 CFR 50.91(b), PEC is providing the State of South Carolina with a copy of the proposed license amendment request partial withdrawal.'

If you have any questions concerning this matter, please contact Mr. C. T. Baucom at (843) 857-1253.

Sincerely, J. F. Lucas Manager - Support Services - Nuclear RAC/rac Attachments:

I. Affirmation II. Markup of Technical Specifications Page III. Retyped Technical Specifications Page c: Mr. T. P. O'Kelley, Director, Bureau of Radiological Health (SC)

Mr. H. J. Porter, Director, Division of Radioactive Waste Management (SC)

Dr. W. D. Travers, NRC, Region II Mr. C. P. Patel, NRC, NRR NRC Resident Inspectors, HBRSEP Attorney General (SC)

United States Nuclear Regulatory Commission Attachment I to Serial: RNP-RA/06-0104 Page 1 of 1 AFFIRMATION The information contained in letter RNP-RA/06-0104 is true and correct to the best of my information, knowledge, and belief; and the sources of my information are officers, employees, contractors, and agents of Carolina Power and Light Company, also known as Progress Energy Carolinas, Inc. I declare under penalty of perjury that the foregoing is true and correct.

Executed On: I't I0(O T. D. Walt Vice President H. B. Robinson Steam Electric Plant, Unit No. 2

United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/06-0104 2 pages including cover page H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 REQUEST FOR TECHNICAL SPECIFICATIONS CHANGE REGARDING REVISION TO CORE OPERATING LIMITS REPORT (COLR) REFERENCES MARKUP OF TECHNICAL SPECIFICATIONS PAGE

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

15. "Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 87 to Facility Operating License No. DPR-23, Carolina Power & Light Co.,

H. B. Robinson Steam Electric Plant, Unit No. 2, Docket No. 50-261," USNRC, Washington, DC 20555, 7 Nov. 84.

16. ANF-88-054(P), "PDC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H. B. Robinson Unit 2,"

approved version as specified in the COLR.

17. ANF-88-133 (P)(A), "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 Gwd/MTU," approved version as specified in the COLR.
18. ANF-89-151(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events," approved version as specified in the COLR.
19. EMF-92-081(A), "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors," approved version as specified in the COLR.
20. EMF-92-153(P)(A), "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel,"

approved version as specified in the COLR.

21. XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," approved version as specified in the COLR.
22. EMF-96-029(P)(A), "Reactor Analysis System for PWRs,"

approved version as specified in the COLR.

23. EMF-92-116, "Generic Mechanical Design Criteria for PWR Fuel Designs," approved version as specified in the COLR.
24. EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," approved version as specified in the COLR.
25. EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," approved version as specified in the COLR.

(continued)

HBRSEP Unit No. 2 5.0-30 Amendment No. 249

United States Nuclear Regulatory Commission Attachment III to Serial: RNP-RA/06-0104 2 pages including cover page H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 REQUEST FOR TECHNICAL SPECIFICATIONS CHANGE REGARDING REVISION TO CORE OPERATING LIMITS REPORT (COLR) REFERENCES RETYPED TECHNICAL SPECIFICATIONS PAGE

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

15. "Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 87 to Facility Operating License No. DPR-23, Carolina Power & Light Co.,

H. B. Robinson Steam Electric Plant, Unit No. 2, Docket No. 50-261," USNRC, Washington, DC 20555, 7 Nov. 84.

16. ANF-88-054(P), "PDC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H. B. Robinson Unit 2,"

approved version as specified in the COLR.

17. ANF-88-133 (P)(A), "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 Gwd/MTU," approved version as specified in the COLR.
18. ANF-89-151(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events," approved version as specified in the COLR.
19. EMF-92-081(A), "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors," approved version as specified in the COLR.
20. EMF-92-153(P)(A), "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel,"

approved version as specified in the COLR.

21. XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," approved version as specified in the COLR.
22. EMF-96-029(P)(A), "Reactor Analysis System for PWRs,"

approved version as specified in the COLR.

23. EMF-92-116, "Generic Mechanical Design Criteria for PWR Fuel Designs," approved version as specified in the COLR.
24. EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," approved version as specified in the COLR.
25. EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," approved version as specified in the COLR.

(continued)

HBRSEP Unit No. 2 5.0-30 Amendment No.

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