ML041380358

Technical Specifications, Updated Core Limiting Operating Limits Report (COLR) Methodologies

ML041380358
Person / Time
Site:	Saint Lucie
Issue date:	05/06/2004
From:	NRC/NRR/DLPM/LPD2
To:
References
TAC MB5178
Download: ML041380358 (3)

Text

I ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (continued) 6.9.1.9 At least once every 5 years, an estimate of the actual population within 10 miles of the plant shall be prepared and submitted to the NRC.

6.9.1.10 At least once every 10 years, an estimate of the actual population within 50 miles of the plant shall be prepared and submitted to the NRC. -

6.9.1.11 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

Specification 3.1.1.1 Shutdown Margin - Tavg Greater Than 200 0F Specification 3.1.1.2 Shutdown Margin -Tavg Less Than or Equal to 2000F Specification 3.1.1.4 Moderator Temperature Coefficient Specification 3.1.3.1 Full Length CEA Position - Misalignment > 15 inches Specification 3.1.3.6 Regulating CEA Insertion Limits Specification 3.2.1 Linear Heat Rate T Specification 3.2.3 Total Integrated Radial Peaking Factor- Fr Specification 3.2.5 DNB Parameters Specification 3.9.1 Refueling Operations - Boron Concentration

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, as described in the following documents, approved Revisions and Supplements as specified in the COLR. I

1. WCAP-11596-P-A, "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988 (Westinghouse Proprietary)

2. NF-TR-95-01, "Nuclear Physics Methodology for Reload Design of Turkey Point & St. Lucie Nuclear Plants," Florida Power & Light Company, January 1995.

3. XN-75-27(A) [also Issued as XN-NF-75-27(A)], "Exxon Nuclear Neutronic(s) Design Methods for Pressurized Water Reactors" I

4. ANF-84-73(P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events" I

5. XN-NF-82-21(P)(A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations" I ST. LUCIE - UNIT 1 6-19 Amendment No. fI. i. 8X, 4-4-54,463,474,191

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (continued)

6. EMF-84-093(P)(A), "Steam Line Break Methodology for PWRs"

7. XN-75-32(P)(A), "Computational Procedure for Evaluating Fuel Rod Bowing"

8. XN-NF-82-49(P)'(A), "Exxon Nuclear Company Evaluation Model Revised EXEM PWR Small Break Model"

9. XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors"

10. XN-NF-621(P)(A), " Exxon Nuclear DNB Correlation for PWR Fuel Designs"

11. EMF-2087(P)(A), "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications"

12. XN-NF-82-06(P)(A), "Qualification of Exxon Nuclear Fuel for Extended Burnup"

13. ANF-88-1 33(P)(A), "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWd/MTU"

14. XN-NF-85-92 (P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results"

15. ANF-89-151 (P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events"

16. DELETED

17. EMF-92-116(P)(A), "Generic Mechanial Design Criteria for PWR Fuel Design"

18. EMF-92-153(P)(A), "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel"

19. EMF-96-029(P)(A), Volumes 1 and 2, "Reactor Analysis System for PWRs Volume 1 - Methodology Description, Volume 2 - Benchmarking Results" ST. LUCIE - UNIT 1 6-19a Amendment No. 4I0, 4S.191

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (continued)

20. EMF-1 961 (P)(A), "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors" I

21. EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for l Pressurizer Water Reactors" I

22. EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based" I ST. LUCIE - UNIT 1 6-1 9b Amendment No. 463.44, 191