ML17229A773

Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b

ML17229A773
Person / Time
Site:	Saint Lucie
Issue date:	06/15/1998
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17229A772	List: ML17229A771 ML17229A773
References
NUDOCS 9806220286
Download: ML17229A773 (3)

Text

NVU L ADOLOGICALE Vl 0 E L E A G 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 CO EOPERATI G LI 0 COL

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 3.1.1.4 Moderator Temperature Coefficient Specification 3.1.3.1 Movable Control Assemblies - CEA Position Specification 3.1.3.6 Regulating CEA Insertion Limits Specification 3.2.1 Linear Heat Rate Specification 3.2.2 Total Planar Radial Peaking Factors -

Specification 3.2.3 Integrated Radial Peaking Factor -F'otal Parameters - Axial Shape Index F,'NB Specification 3.2.5 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 or any approved Revisions and Supplements thereto:

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, Januaty 1995.

3. CENPD-199-P, Rev. 1-P-A, "C-E Setpoint Methodology: CE Local Power Density and DNB LSSS and LCO Setpoint Methodology for Analog Protection Systems," January 1986.

4. CENPD-266-P-A, 'The ROCS and DIT Computer Code for Nuclear Design,"

April 1983.

5. CENPD-275-P, Revision 1-P-A, "C-E Methodology for Core Designs Containing Gadolinia-Urania Burnable Absorbers," May 1988.

6. CENPD-188-A, "HERMITE: A Multi-Dimensional Space - Time Kinetics Code for PWR Transients," July 1976.

ST. LUCIE- UNIT2 6-20 Amendment No. ~5-,84 9806220286 9806i5 PDR ADQCK 05000389 P PDR

CORE OPERATING LIMITS EPORT COLR (Continued)

~ . b. (Continued)

CENPD-1 53-P, Rev. 1-P-A, "Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed Incore Detector System,"

May 1980.

CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 1:

CE Calculated Local Power Density and Thermal Margin/Low Pressure LSSS for St. Lucie Unit 1," December 1979.

CEN-123(F)-P, "Statistical Combination of.Uncertainties Methodology Part 2:

Combination of System Parameter Uncertainties in Thermal Margin Analyses for St. Lucie Unit 1," January 1980.

10. CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 3:

CE Calculated Departure from Nucleate Boiling and Linear Heat Rate I imiting Conditions for Operation for St. Lucie Unit 1," February 1980.

CEN-191 (B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 and 2," December 1981.

12. Letter, J.W. Miller (NRC) to J.R. Williams, Jr. (FPL), Docket No. 50-389, Regarding Unit 2 Cycle 2 License Approval (Amendment No. 8 to NPF-1 6 and SER), November 9, 1984 (Approval of CEN-123(F)-P (three parts) and CEN-1 91(B)-P) ~

13. CEN71(F)-P, "Extended Statistical Combination of Uncertainties,"

July 1989.

14. Letter, J.A. Norris (NRC) to J.H. Goldberg (FPL), Docket No. 50-389, "St. Lucie Unit 2- Change to Technical Specification Bases Sections '2.1.1 Reactor Core'nd '3/4.2.5 DNB Parameters'TAC No. M87722)," March 14, 1994 (Approval of CEN-371 (F)-P).

15. CENPD-161-P-A, "TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core," April 1986.

16. CENPD-162-P-A, "Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer Grids Part 1, Uniform Axial Power Distribution," April 1975.

17. CENPD-207-P-A, "Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer Grids Part 2, Non-uniform Axial Power Distribution,"

December 1984.

18. CENPD-206-P-A, "TORC Code, Verification and Simplified Modeling Methods," June 1981.

ST. LUCIE - UNIT 2 6-20a Amendment No.

CORE OPERA NG LI S EPO T COLR (Continued)

,, ...b.. (Continued)

34. Letter, J.A. Norris (NRC) to J.H. Goldberg (FPL), "St. Lucie Unit 2- Issuance of Amendment Re: Moderator Temperature Coefficient (TAC No.

M82517)," July 15, 1992.

35.

D k N. - P p L-84-1 48, June 4, 1984.

dLiiA d .~d'"

Letter, J.W. Williams, Jr. (FPL) to D.G. Eisenhut (NRC), "St. Lucie Unit No. 2,

36. Letter, J.R. Miller (NRC) to J.W. Williams, Jr. (FPL), Docket No. 50-389, Regarding Unit 2 Cycle 2 License Approval (Amendment No. 8 to NPF-1 6 and SER), November 9, 1984 (Approval of Methodology contained in L-84-1 48).

37. Letter, A.E. Scherer Enclosure 1-P to LD42-001, "CESEC-Digital Simulation of a Combustion Engineering Nuclear Steam Supply System,"

December 1981.

38. Safety Evaluation Report, "CESEC Digital Simulation of a Combustion Engineering Steam Supply System (TAC No.: 01142)," October 27, 1983.

39. CENPD-282-P-A, Volumes 1, 2 and 3, and Supplement 1, "Technical Manual for the CENTS Code," February 1991, February 1991, October 1991, and June 1993, respectively.

C. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SHUTDOWN MARGIN, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any mid cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

SEC L EO S 6.9.2 Special reports shall be submitted to the NRC within the time period specified for each report.

ST. LUCIE- UNIT2 Amendment No.