ML18016B052

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Proposed Tech Specs,Incorporating Analytical Methodology in TS 6.9.1.6.2 Which Are Used to Determine Core Operating Limits
ML18016B052
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Site: Harris Duke Energy icon.png
Issue date: 08/04/1999
From:
CAROLINA POWER & LIGHT CO.
To:
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ML18016B051 List:
References
NUDOCS 9908100166
Download: ML18016B052 (8)
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Enclosure 5 to SERIAL HNP-99-107 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT ADDITIONOF METHODOLOGY REFERENCES TO CORE OPERATING LIMITS REPORT TECHNICALSPECIFICATION PAGES 9908i00ibb 990804 05000400 PDR ADQCK P PDR

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ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued) d ',."XN-75-32(A), 'Supplements 1, 2, 3, and 4, "Computational Procedure for

. *'-Evaluating Fuel Rod Bowing," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

e. XN-NF-84-93(A), latest Revision and Supplements, "Steamline Break Methodology for PWRs," Exxon Nuclear Company, Richland WA 99352.

J-n$ eff.

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3.6-Control Bank Insertion Limits, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

Mlef.<

p, 4 EXEM PW Large Break LOCA Evaluation Model as defined by: Ll~

588/Ph)R XN-NF-82-20(A), latest Revision and Supplements, "Exxon Nuclear Company Evaluation Model EXEM/PWR ECCS Model Updates," Exxon Nuclear Company, Richland WA 99352.

XN-NF-82-07(A), latest Revision, "Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon Nuclear Company, Richland WA 99352.

XN-NF-81-58(A), latest Revision and Supplements, "RODEX2 Fuel Rod Thermal Response Evaluation Model," Exxon Nuclear Company, Richland WA 99352.

XN-NF-85-16(A), Volume 1 and Supplements, Volume 2, latest Revision and Supplements, "PWR 17x17 Fuel Cooling Test Program," Exxon Nuclear Company, Richland WA 99352.

XN-NF-85-105(A), and Supplements, "Scaling of FCTF Based Reflood Heat Transfer Correlation for Other Bundle Designs," Exxon Nuclear Co@own~~. Richland WA 99352.

(Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

g XN-NF-78-44(A), latest Revision, "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, and 3.2.2 - Heat Flux Hot Channel Factor).

SHEARON HARRIS - UNIT 1 6-24a Amendment No. 44

Insert 1 Steam Line Break Methodology as defined by:

EMF-84-093(A), latest Revision, "Steam Line Break Methodology for PWRs," Siemens Power Corporation, Richland WA 99352.

ANF-84-093(A), latest Revision and Supplements, "Steam Line Break Methodology for PWRs," Advanced Nuclear Fuels Corporation, Richland WA 99352.

Insert 2 EMF-2087(A), latest Revision, "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation, Richland WA 99352.

XN-NF-81-58(A), latest Revision and Supplements, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, Richland WA 99352.

ANF-81-58(A), latest Revision and Supplements, "RODEX2 Fuel Rod Thermal Mechanical Response Evaluation Model," Advanced Nuclear Fuels Corporation, Richland WA 99352.

XN-NF-82-06(A), latest Revision and Supplements, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company, Richland WA 99352.

ANF-88-133(A), latest Revision and Supplements, "Qualification of Advanced Nuclear Fuels'WR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, Richland WA 99352.

XN-NF-85-92(A), latest Revision, "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, Richland WA 99352.

EMF-92-116(A), latest Revision, "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, Richland WA 99352.

ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)

.'"';9.'2-.6;:3;. The core operating limits shall be determined so that all appl.icable limits (e.g., fuel thermal-mechanical limits, core thermal-

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hydraulic limits, 'nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.6.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements, sha'll be provided, upon issuance for each reload cycle, to the NRC Document Control Desk, with copies to the Regional Administrator and Resident Inspector.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the NRC in accordance with IOCFR50.4 within the time period specified for each report.

6.10 RECORD RETENTION

6. 10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at 1'east the minimum period indicated.
6. 10.2 The following records shall be retained for at least 5 years:

a~ Records and logs of unit operation covering time interval at each power level;

b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety; C. All REPORTABLE EVENTS;
d. Records of surveillance activities, inspections, and calibrations required by these Technical Specifications;
e. Records of changes made to the procedures required by Specification 6.8. 1;
f. Records of radioactive shipments;
g. Records of sealed source and fission detector leak tests and results; and SHEARON HARRIS - UNIT I 6-24c Amendment No. 44

'Insert 3

o. EMF-96-029 (A), Volume 1, Volume 2 and Attachment, "Reactor Analysis Systems for PWRs," Siemens Power Corporation, Richland WA 99352.

(Methodology for Specification 3.1.1.2 - SHUTDOWN MARGIN- MODES 3, 4 and 5, 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor, and 3.9.1 - Boron Concentration).

ADMINISTRATIVE CONTROL 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)

d. XN-75-32(A), Supplements 1, 2, 3, and 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

Steam Line Break Methodology as defined by:

EMF-84-093(A), latest Revision, "Steam Line Break Methodology for PWRs," Siemens Power Corporation, Richland WA 99352.

ANF-84-093(A), latest Revision and Supplements, "Steam Line Break Methodology for PWRs," Advanced Nuclear Fuels Corporation, Richland WA 99352.

(Methodology for Specification 3. 1.1.3 - Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3.6-Control Bank Insertion Limits, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

SEM/PWR Large Break LOCA Evaluation Model as defined by:

EHF-2087(A),latest Revision, "SEH/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation, Richland WA 99352.

XN-NF-81-58(A), latest Revision and Supplements, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, Richland WA 99352.

ANF-81-58(A), latest Revision and Supplements, "RODEX2 Fuel Rod Thermal Hehanical Response Evaluation Model," Advanced Nuclear Fuels Corporation, Richland WA 99352.

XN-NF-82-06(A), latest Revision and Supplements, "Qualification of Exxon Nuclear Fuel for Extended Burnup, 'xxon Nuclear Company, Richland WA 99352.

ANF-88-133(A), latest Revision and Supplements, "Qualification of Advanced Nuclear Fuels'WR Design Methodology f'r Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, Richland WA 99352.

XN-NF-85-92(A), latest Revision, "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, Richland WA 99352.

EMF-92-116(A), latest Revision, "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, Richland WA 99352.

(Methodology for Specification 3.2. 1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor ).

SHEARON HARRIS - UNIT 1 6-24a Amendment No.

ADMINISTRATIVE CONTRO 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)

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

Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3.6 - Control Bank Insertion Limits, and 3.2.2 - Heat Flux Hot Channel Factor).

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

Advanced Nuclear Fuels Corporation, Richland WA 99352.

(Methodology for Specification 3.2. 1 - Axial Flux Difference, and 3.2.2 - Heat Flux Hot Channel Factor).

WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY", July 1985 (W Proprietary).

(Methodology for Specification 3. 1. 1.2 - SHUTDOWN MARGIN - MODES 3, 4 AND 5, 3.2.2 - Heat Flux Hot Channel Factor and 3.2.3-Nuclear Enthalpy Rise Hot Channel Factor).

WCAP-10266-P-A, Rev. 2, "The 1981 Version of the WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE", March 1987 (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor).

WCAP-11837-P-A, "EXTENSION OF METHODOLOGY FOR CALCULATING TRANSITION CORE DNBR PENALTIES", January 1990 (W Proprietary).

(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

EHF-92-081(A), latest Revision and Supplements, "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors,"

Siemens Power Corporation, Richland WA 99352.

(Methodology for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3.6-Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

EHF-92-153(A), latest Revision and Supplements, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Nuclear Power Corporation, Richland WA 99352.

(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

XN-NF-82-49(A), latest Revision and Supplements, "Exxon Nuclear Company Evaluation Model EXEH PWR Small Break Model," Exxon Nuclear Company, Richland WA 99352.

SHEARON HARRIS - UNIT 1 6-24b Amendment No.

ADMINISTRATIVE CONTROL 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)

(Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

0. EMF-96-029(A). Volume 1, Volume 2 and Attachment, "Reactor Anal.vsis Systems for PWRs," Siemens Power Corporation, Richland WA 99352.

(Methodology for Specification 3. 1. 1.2 - SHUTDOWN MARGIN - MODES 3, 4 and 5, 3. 1. 1.3 - Moderator Temperature Coefficient. 3. 1.3.5-Shutdown Bank Insertion Limits, 3. 1.3.6 - Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channnel Factor, and 3.9. 1 - Boron Concentration.)

6.9.1.6.3 The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

6.9. 1.6.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements, shall be provided, upon issuance for each reload cycle, to the NRC Document Control l3esk, with copies to the Regional Administrator and Resident Inspector.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the NRC in accordance with 10CFR50.4 within the time period specified for each report.

6. 10 RECORD RETENTION 6.10. 1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regul'ations, the following records shall be retained for at least the minimum period indicated.

6.10.2 The following records shall be retained for at least 5 years:

a. Records and logs of unit operation covering time interval at each power level;
b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety;
c. All REPORTABLE EVENTS;
d. Records of surveillance activities, inspections, and calibrations required by these Technical Specifications;
e. Records of changes made to the procedures required by Specification 6.8.1; Records of radioactive shipments;
g. Records of sealed source and fission detector leak tests and results; and SHEARON HARRIS - UNIT 1 6-24c Amendment No.
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