ML030910469

Tech Spec Pages for Amendment No. 114 Addition of Methodology References to Core Operating Limits Report

ML030910469
Person / Time
Site:	Harris
Issue date:	03/28/2003
From:	NRC/NRR/DLPM
To:
References
TAC MB6226
Download: ML030910469 (3)

Text

ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)

d. XN-75-32(P)(A), "Computational Procedure for Evaluating Fuel Bowing," approved version as specified in the COLR. Rod (Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

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

approved version as specified in the COLR.

(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 Hot Channel Factor). Rise

f. EMF-2087(P)(A), "SEM/PWR-98: ECCS Evaluation Applications," approved version as specified Model for PWR LBLOCA in the COLR.

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

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

(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. 114

ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)

h. ANF-88-054(P)(A), "PDC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors Application of PDC-3 to H. B. Robinson Unit 2," approved and as specified in the COLR. version (Methodology for Specification 3.2.1 -

3.2.2 - Heat Flux Hot Channel Factor). Axial Flux Difference, and

i. EMF-92-081(P)(A), "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors," approved version as specified COLR. in the (Methodology for Specification 3.1.1.3 - Moderator Coefficient, 3.1.3.5 - Shutdown Bank Insertion Temperature Control Bank Insertion Limits, 3.2.1 - Axial FluxLimits, 3.1.3.6 -

3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Difference, Rise Hot Channel Factor). Nuclear Enthalpy

j. EMF-92-153(P)(A), "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," approved as specified in the COLR. version (Methodology for Specification 3.2.3 - Nuclear Enthalpy Channel Factor). Rise Hot

k. XN-NF-82-49(P)(A), "Exxon Nuclear Company Evaluation PWR Small Break Model," approved version as specified Model EXEM in the COLR.

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

1. EMF-96-029(P)(A), "Reactor Analysis Systems for PWRs,"

version as specified in the COLR. approved (Methodology for Specification 3.1.1.2 - SHUTDOWN MARGIN - MODES 3, 4 and 5, 3 .1 .1.3 - Moderator Temperature Coefficient, Shutdown Bank Insertion Limits, 3.1.3.6 - Control 3.1.3.5 -

Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Bank Insertion Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Flux Hot and 3.9.1 - Boron Concentration). Channel Factor,

m. EMF-2328(P)(A) PWR Small Break LOCA Evaluation Model, Based, approved version as specified in the COLR. S-RELAP5 (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 6-24b Amendment No. 114 I

ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)

n. Mechanical Design Methodologies XN-NF-81-58(P)(A), "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," approved version as specified in the COLR.

ANF-81-58(P)(A). "RODEX2 Fuel Rod Thermal Mechanical Response Evaluation Model," approved version as specified in the COLR.

XN-NF-82-06(P)(A), "Qualification of Exxon Nuclear Fuel for Extended Burnup," approved version as specified in the COLR.

ANF-88-133(P)(A), "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWd/MTU." approved version as specified in the COLR.

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

approved version as specified in the COLR.

EMF-92-116(P)(A). "Generic Mechanical Design Criteria for PWR Fuel Designs," approved version as specified in the COLR.

(Methodologies 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).

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 accident analysis limits) of the safety analysis are met. and 6.9.1.6.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements, shall be provided, upon issuance cycle, to the NRC Document Control Desk, with copies to the for each reload 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.

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SHEARON HARRIS - UNIT 1 6-24c Amendment No.114