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{{#Wiki_filter:End losu'"e page 2 of 3 L-96-118 G (Continued)
{{#Wiki_filter:End losu'"e page 2     of 3 L-96-118 G                       (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.
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.
EOP RA G 0 6.9.1.7 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR)before each reload cycle or any remaining part of a reload cycle for the following:
The  analytical methods used to generate the Peaking Factor limits shall be th(ye previously reviewed and approved by the NRC. If changes to these methods ard 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.
1.Axial Flux Diffe}ence for Specifications 3.2.1.2.Control Rod Insertion Limits for Specification 3.1.3.6.3.Heat Flux Hot Channel Factor-Fo(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.MCAP-10216-P-A,'RELAXATION OF CONSTANT AXIAL OFFSET CONTROL F~SURVEILLANCE TECHNICAL SPECIFICATION,'une 1983.2.MCAP-8385,'POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES
EOP   RA   G             0 6.9.1.7 Core operating limits shall       be established and documented in the CORE OPERATING LIMITS REPORT (COLR) before each         reload cycle or any remaining part of a reload cycle     for the following:
-TOPICAL REPORT,'eptember 1974.The analytical methods used to determine the K(Z)curve shall be those previously reviewed and approved by the NRC in: 1.MCAP-9220-P-A, Rev.1,'Westinghouse ECCS Evaluation Model-1981 Version,'ebruary 1982.2.WCAP-9561-P-A, ADD.3, Rev.1,"BART A-1: A Computer Code for the Best Estimate Analysis of Reflood Transients
: 1. Axial Flux Diffe}ence for Specifications 3.2.1.
-Special Report: Thimble Modeling g ECCS Evaluation Model." 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,'uly 1985.The ability to calculate the COLR nuclear design parameters are demonstrated in: 1.Florida Power L Light Company Topical Report NF-TR-95-01,"Nuclear Physics Methodology for Reload Design of Turkey Point L St.Lucie Nuclear Plants'.TlHXEY POINT-UNITS 3 It 4 6-20 9605i40367 960509 PDR ADOCK 05000250 P, PDR AMENDMENT NOS.]74 AND]68 The analytical methods used to generate the Peaking Factor limits shall be th(ye previously reviewed and approved by the NRC.If changes to these methods ard 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.
: 2. Control Rod Insertion Limits for Specification 3.1.3.6.
Enclosure Page, g of 3 L-96-118 Insert A 3.4.WCAP-10054-P-A, (proprietary),"Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code", August 1985.WCAP-10054-P, Addendum 2, Revision 1 (proprietary),"Addendum to the Westinghouse Small Break LOCA ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection in the Broken Loop and Improved Condensation Model", October 1995.+Insert B"This reference is only to be used subsequent to NRC approval.
: 3. Heat Flux Hot Channel Factor     - Fo(Z) for Specification 3/4.2.2.
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The   analytical methods used to determine the AFD       limits shall be those previously reviewed and approved by the NRC in:
: 1. MCAP-10216-P-A, 'RELAXATION OF CONSTANT AXIAL OFFSET       CONTROL F~
SURVEILLANCE TECHNICAL SPECIFICATION,'une 1983.
: 2. MCAP-8385, 'POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING
                        - TOPICAL REPORT,'eptember 1974.
PROCEDURES The   analytical methods used to determine the K(Z) curve shall         be those previously reviewed and approved by the NRC in:
: 1. MCAP-9220-P-A, Rev. 1, 'Westinghouse       ECCS Evaluation Model                 - 1981 Version,'ebruary 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 Modeling g ECCS Evaluation Model."
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,'uly 1985.
The   ability to calculate     the COLR nuclear design parameters     are demonstrated                   in:
: 1. Florida Power L Light Company Topical Report NF-TR-95-01, "Nuclear Physics Methodology for Reload Design of Turkey Point L St. Lucie Nuclear Plants'.
P, TlHXEY POINT 9605i40367 960509 PDR      ADOCK
                        - UNITS 3 It 4 05000250 PDR 6-20               AMENDMENT NOS.                 ]74 AND   ]68
 
Enclosure                                                   L-96-118 Page, g of 3 Insert A
: 3. WCAP-10054-P-A, (proprietary), "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code", August 1985.
: 4. WCAP-10054-P, Addendum 2, Revision 1 (proprietary),
      "Addendum to the Westinghouse Small Break LOCA ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection in the Broken Loop and Improved Condensation Model", October 1995.+
Insert B "This reference is only to be used subsequent to NRC approval.
 
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Revision as of 08:20, 22 October 2019

Proposed Tech Specs Re SBLOCA re-analysis
ML17353A678
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 05/09/1996
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17353A677 List:
References
NUDOCS 9605140367
Download: ML17353A678 (3)
v • d • e


Text

End losu'"e page 2 of 3 L-96-118 G (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 th(ye previously reviewed and approved by the NRC. If changes to these methods ard 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.

EOP RA G 0 6.9.1.7 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR) before each reload cycle or any remaining part of a reload cycle for the following:

1. Axial Flux Diffe}ence for Specifications 3.2.1.
2. Control Rod Insertion Limits for Specification 3.1.3.6.
3. Heat Flux Hot Channel Factor - Fo(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. MCAP-10216-P-A, 'RELAXATION OF CONSTANT AXIAL OFFSET CONTROL F~

SURVEILLANCE TECHNICAL SPECIFICATION,'une 1983.

2. MCAP-8385, 'POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING

- TOPICAL REPORT,'eptember 1974.

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

1. MCAP-9220-P-A, Rev. 1, 'Westinghouse ECCS Evaluation Model - 1981 Version,'ebruary 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 Modeling g ECCS Evaluation Model."

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,'uly 1985.

The ability to calculate the COLR nuclear design parameters are demonstrated in:

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

P, TlHXEY POINT 9605i40367 960509 PDR ADOCK

- UNITS 3 It 4 05000250 PDR 6-20 AMENDMENT NOS. ]74 AND ]68

Enclosure L-96-118 Page, g of 3 Insert A

3. WCAP-10054-P-A, (proprietary), "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code", August 1985.
4. WCAP-10054-P, Addendum 2, Revision 1 (proprietary),

"Addendum to the Westinghouse Small Break LOCA ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection in the Broken Loop and Improved Condensation Model", October 1995.+

Insert B "This reference is only to be used subsequent to NRC approval.

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