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{{#Wiki_filter:ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATIONS Marked-up Technical Specifications Pages, 6-20 95012/0>05000250 cynoii7 pDR ADOCK pD p ADHTN STRAT VE CONTROLS P AK NG FACTOR HIT REPORT (Continued)
{{#Wiki_filter:ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATIONS Marked-up Technical Specifications Pages, 6-20 95012/0>   cynoii7 ADOCK 05000250 pDR             pD p
Factor Limit Report, the Peaking Factor Limit Report shall be provided to the NRC Document Control desk with copies to the Regional Administrator and the Resident Inspector within 30 days of their implementation, unless otherwise approved by the Commission.
 
The analytical methods used to generate the Peaking Factor limits shall be those previously reviewed and approved by the NRC.If changes to these methods are deemed necessary they will be evaluated in accordance with 10 CFR 50.59 and submitted to the NRC for review and approval prior to their use if the change is determined to involve an unreviewed safety question or if such a change would require amendment of previously submitted documentation.
ADHTN STRAT VE CONTROLS P AK NG FACTOR       HIT REPORT   (Continued)
CORE OP RA G H TS REPORT 6.9.1.7 Core operating limits shall be established and documented in the CORE OPERATING LIHITS REPORT (COLR)before each reload cycle or any remaining part of a reload cycle for the following:
Factor Limit Report, the Peaking Factor Limit Report shall be provided to the NRC Document Control desk with copies to the Regional Administrator and the Resident Inspector within 30 days of their implementation, unless otherwise approved by the Commission.
1.Axial Flux Difference for Specification 3.2.1.2.Control Rod Insertion Limits for Specification 3.1.3.6.3.Heat Flux Hot Channel Factor-F~(Z)for Specification 3/4.2.2.The analytical methods used to determine the AFD limits shall be those previously reviewed and approved by the NRC in: 1.WCAP-10216-P-A,"RELAXATION OF CONSTANT AXIAL OFFSET CONTROL F SURVEILLANCE TECHNICAL SPECIFICATION," June 1983.2.WCAP-8385,"POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES
The analytical methods used to generate the Peaking Factor limits shall be those previously reviewed and approved by the NRC. If changes to these methods are deemed necessary they will be evaluated in accordance with 10 CFR 50.59 and if if submitted to the NRC for review and approval prior to their use                 the change is determined to involve an unreviewed safety question or               such a change would require amendment of previously submitted documentation.
-TOPICAL REPORT," September 1974.The analytical methods used to determine the K(Z)curve shall be those previously reviewed and approved by the NRC in: 1.WCAP-9220-P-A, Rev.1,"Westinghouse ECCS Evaluation Hodel-1981 Version," February 1982.2.WCAP-9561-P-A, ADD.3, Rev.1,"BART A-1: A Computer Code for the Best Estimate Analysis of Reflood Transients
CORE OP RA       G   H TS REPORT 6.9.1.7     Core operating     limits shall be   established and documented in the CORE OPERATING LIHITS REPORT (COLR) before each           reload cycle or any remaining part of a reload cycle     for the following:
-Special Report: Thimble Hodeling W ECCS Evaluation Hodel." The analytical methods used to determine the Rod Bank Insertion Limits shall be those previously reviewed and approved by the NRC in: 1.WCAP-9272-P-A,"Westinghouse Reload Safety Evaluation Methodology," July 1985.>WS<lZ.~(C)-k~The AFD, K(Z), and Rod Bank Insertion Lsmits shall be determined such that all applicable limits of the safety analyses are met.The CORE OPERATING LIHITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and the Resident Inspector, unless otherwise approved by the Commission.
: 1. Axial Flux Difference for Specification 3.2. 1.
'URKEY POINT-UNITS 3 5.4 6-20 AMENDHENT NOS 167 AND<<  
: 2. Control   Rod Insertion Limits for Specification 3.1.3.6.
~'9 a~eh-AN'p'if.J('b\f IH.t4~+PP+4SP-NJ L-95-006 INSERT A The ability to calculate the COLR nuclear design parameters are demonstrated in: 1.Florida Power&Light Company Topical Report NF-TR-95-01,"Nuclear Physics Methodology for Reload Design of Turkey Point&St.Lucie Nuclear Plants".Topical Report NF-.TR-95-01 was approved by the NRC for use by Florida Power&Light Company in: Safety Evaluation by the Office of Nuclear Reactor Regulations Related to Amendment No.xxx to Facility Operating License DPR-31 and Amendment No.xxx to Facility Operating License No.DPR-41, Florida Power&Light Company Turkey Point Units Nos.3 and 4, Docket Nos.50-250 and 50-251.
: 3. Heat Flux Hot Channel Factor       - F~(Z) for Specification 3/4.2.2.
The analytical methods used to determine the AFD limits shall be those previously reviewed and approved by the NRC in:
: 1. WCAP-10216-P-A, "RELAXATION OF CONSTANT AXIAL OFFSET         CONTROL F SURVEILLANCE TECHNICAL SPECIFICATION," June 1983.
: 2. WCAP-8385, "POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES
              - TOPICAL REPORT," September 1974.
The analytical methods used to determine the K(Z) curve shall             be those previously reviewed and approved by the NRC in:
: 1. WCAP-9220-P-A, Rev. 1, "Westinghouse         ECCS Evaluation Hodel-1981 Version," February 1982.
: 2. WCAP-9561-P-A, ADD. 3, Rev. 1, "BART A-1: A Computer Code           for the Best Estimate Analysis of Reflood Transients           Special Report:
Thimble Hodeling W ECCS Evaluation Hodel."
The analytical methods used to determine the Rod Bank Insertion Limits shall be those previously reviewed and approved by the NRC in:
: 1. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.
                            >WS<lZ.~ (C )     -k ~
The AFD, K(Z), and Rod Bank Insertion Lsmits shall be determined such that all applicable limits of the safety analyses are met. The CORE OPERATING LIHITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and the Resident Inspector, unless otherwise approved by the Commission.
'URKEY     POINT - UNITS 3 5. 4             6-20             AMENDHENT NOS   167 AND
                                                                                            <<
 
  '9 a~eh - AN 'p'if .J('b \
~ IH.t4~+PP+4SP-NJ           f
 
L-95-006 INSERT   A The ability to calculate   the COLR nuclear design parameters are demonstrated   in:
: 1. Florida Power & Light Company Topical Report NF-TR-95-01, "Nuclear Physics Methodology for Reload Design of Turkey Point & St. Lucie Nuclear Plants".
Topical Report NF-.TR-95-01 was approved by the NRC for use by Florida Power & Light Company in:
Safety Evaluation by the Office of Nuclear Reactor Regulations Related to Amendment No. xxx to Facility Operating License DPR-31 and Amendment No. xxx to Facility Operating License No. DPR-41, Florida Power & Light Company Turkey Point Units Nos. 3 and 4, Docket Nos. 50-250 and 50-251.
 
ATTACHMENT 4 FPL TOPICAL REPORT NF-TR-95-01:
ATTACHMENT 4 FPL TOPICAL REPORT NF-TR-95-01:
NUCLEAR PHYSICS METHODOLOGY FOR RELOAD DESIGN OF TURKEY POINT&ST.LUCIE NUCLEAR PLANTS}}
NUCLEAR PHYSICS METHODOLOGY FOR RELOAD DESIGN OF TURKEY POINT & ST. LUCIE NUCLEAR PLANTS}}

Revision as of 07:31, 22 October 2019

Proposed Tech Specs 6.9.1.7, COLR, Including Ref to Topical Rept NF-TR-95-01 Re Implementation of FPL Nuclear Physics Methodology for Calculations of COLR Parameters
ML17352B004
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 01/17/1995
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17352B002 List:
References
NUDOCS 9501270177
Download: ML17352B004 (5)
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Text

ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATIONS Marked-up Technical Specifications Pages, 6-20 95012/0> cynoii7 ADOCK 05000250 pDR pD p

ADHTN STRAT VE CONTROLS P AK NG FACTOR HIT REPORT (Continued)

Factor Limit Report, the Peaking Factor Limit Report shall be provided to the NRC Document Control desk with copies to the Regional Administrator and the Resident Inspector within 30 days of their implementation, unless otherwise approved by the Commission.

The analytical methods used to generate the Peaking Factor limits shall be those previously reviewed and approved by the NRC. If changes to these methods are deemed necessary they will be evaluated in accordance with 10 CFR 50.59 and if if submitted to the NRC for review and approval prior to their use the change is determined to involve an unreviewed safety question or such a change would require amendment of previously submitted documentation.

CORE OP RA G H TS REPORT 6.9.1.7 Core operating limits shall be established and documented in the CORE OPERATING LIHITS REPORT (COLR) before each reload cycle or any remaining part of a reload cycle for the following:

1. Axial Flux Difference for Specification 3.2. 1.
2. Control Rod Insertion Limits for Specification 3.1.3.6.
3. Heat Flux Hot Channel Factor - F~(Z) for Specification 3/4.2.2.

The analytical methods used to determine the AFD limits shall be those previously reviewed and approved by the NRC in:

1. WCAP-10216-P-A, "RELAXATION OF CONSTANT AXIAL OFFSET CONTROL F SURVEILLANCE TECHNICAL SPECIFICATION," June 1983.
2. WCAP-8385, "POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES

- TOPICAL REPORT," September 1974.

The analytical methods used to determine the K(Z) curve shall be those previously reviewed and approved by the NRC in:

1. WCAP-9220-P-A, Rev. 1, "Westinghouse ECCS Evaluation Hodel-1981 Version," February 1982.
2. WCAP-9561-P-A, ADD. 3, Rev. 1, "BART A-1: A Computer Code for the Best Estimate Analysis of Reflood Transients Special Report:

Thimble Hodeling W ECCS Evaluation Hodel."

The analytical methods used to determine the Rod Bank Insertion Limits shall be those previously reviewed and approved by the NRC in:

1. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

>WS<lZ.~ (C ) -k ~

The AFD, K(Z), and Rod Bank Insertion Lsmits shall be determined such that all applicable limits of the safety analyses are met. The CORE OPERATING LIHITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and the Resident Inspector, unless otherwise approved by the Commission.

'URKEY POINT - UNITS 3 5. 4 6-20 AMENDHENT NOS 167 AND

<<

'9 a~eh - AN 'p'if .J('b \

~ IH.t4~+PP+4SP-NJ f

L-95-006 INSERT A The ability to calculate the COLR nuclear design parameters are demonstrated in:

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

Topical Report NF-.TR-95-01 was approved by the NRC for use by Florida Power & Light Company in:

Safety Evaluation by the Office of Nuclear Reactor Regulations Related to Amendment No. xxx to Facility Operating License DPR-31 and Amendment No. xxx to Facility Operating License No. DPR-41, Florida Power & Light Company Turkey Point Units Nos. 3 and 4, Docket Nos. 50-250 and 50-251.

ATTACHMENT 4 FPL TOPICAL REPORT NF-TR-95-01:

NUCLEAR PHYSICS METHODOLOGY FOR RELOAD DESIGN OF TURKEY POINT & ST. LUCIE NUCLEAR PLANTS

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