HNP-02-112, Request for License Amendment Re Addition of Methodology References to Core Operating Limits Report
| ML022700572 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/28/2002 |
| From: | Scarola J Carolina Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| HNP-02-112 | |
| Download: ML022700572 (17) | |
Text
SCP&L X CP&L AProgress Energy Company James Scarola Vice President Harris Nuclear Plant AUG 2 8 2002 United States Nuclear Regulatory Commission SERIAL: HNP-02-112 ATTENTION: Document Control Desk 10CFR50.90 Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT ADDITION OF METHODOLOGY REFERENCES TO CORE OPEATING LIMITS REPORT
Dear Sir or Madam:
In accordance with the Code of Federal Regulations, Title 10, Part 50.90, Carolina Power &
Light Company (CP&L) requests a revision to the Technical Specifications (TS) for the Harris Nuclear Plant (HNP). The proposed amendment revises the TS to incorporate analytical methodology references in TS 6.9.1.6.2, which are used to determine core operating limits.
These analytical methodologies are documented in topical reports, which have been accepted by the Nuclear Regulatory Commission for referencing in licensing applications. provides a description of the proposed changes and the basis for the changes. details, in accordance with 10 CFR 50.91(a), the basis for CP&L's determination that the proposed changes do not involve a significant hazards consideration. Enclosure 3 provides an environmental evaluation which demonstrates that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental assessment is required for approval of this amendment request. Enclosure 4 provides page change instructions for incorporating the proposed revisions. Enclosure 5 provides the proposed Technical Specification pages.
CP&L requests approval of the proposed amendment by February 15, 2003 to support the Cycle 12 refueling outage schedule. CP&L also requests that the proposed amendment be issued such that implementation will occur within 60 days of issuance to allow time for procedure revision and orderly incorporation into copies of the Technical Specifications.
In accordance with 10 CFR 50.91(b), CP&L is providing the State of North Carolina with a copy of the proposed license amendment.
PO Box 165 New Hill, NC 27562 T> 9193622502 F> 919 362 2095
Please refer any questions regarding this submittal to Mr. J. R. Caves at (919) 362-3137.
Sincerely, RTG
Enclosures:
- 1. Basis for Change Request
- 2. 10 CFR 50.92 Evaluation
- 3. Environmental Considerations
- 4. Page Change Instructions
- 5. Technical Specification Pages James Scarola, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief, and the sources of his information are employees, contractors, and agents of Carolina Power & Light Company.
Notary (Seal)
My commission expires:
,), --, / - 0Lo 5 c:
Mr. J. B. Brady, NRC Sr. Resident Inspector Mr. M. Fry, Director, N.C. DEHNR Mr. R. Subbaratnam, NRC Project Manager Mr. L. A. Reyes, NRC Regional Administrator
bc: Ms. D. B. Alexander Mr. M. T. Janus Mr. C. Baucom Mr. A. Khanpour Mr. L. R. Belier Mr. R. D. Martin Mr. W. F. Conway Mr. B. Morrison Mr. G. W. Davis Mr. T. C. Morton Mr. R. J. Duncan II Mr. J. M. Taylor Ms. T. A. Hardy Mr. B. C. Waldrep Mr. K. N. Harris Licensing File(s) (2 copies)
Mr. C. S. Hinnant Nuclear Records Mr. J. W. Holt
ENCLOSURE 1 TO SERIAL: HNP-02-112 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT ADDITION OF METHODOLOGY REFERENCES TO CORE OPEATING LIMITS REPORT BASIS FOR CHANGE REQUEST
Background
The Harris Nuclear Plant (HNP) Technical Specifications (TS) Section 6.9.1.6 provides information regarding the Core Operating Limits Report (COLR). HNP Plant Procedure PLP 106, "Technical Specification Equipment List Program and Core Operating Limits Report,"
implements the cycle-specific core parameter limits. TS 6.9.1.6.2 requires that the analytical methods used to determine the PLP-106 core operating limits shall be those previously reviewed and approved by the Nuclear Regulatory Commission (NRC) at the time the reload analyses are performed, and the approved revision number shall be identified in the COLR.
Proposed Change The amendment proposed by Carolina Power & Light Company to the Harris Nuclear Plant (HNP) Technical Specifications (TS) revises TS 6.9.1.6.2 to add analytical methodology references, which are used to determine core operating limits. TS 6.9.1.6.2.f is being revised to relocate six of the referenced methodologies to TS 6.9.1.6.2.n, which groups the mechanical design methodologies together. The six relocated methodologies are: XN-NF-81-58 (P)(A),
ANF-81-58 (P)(A), XN-NF-82-06 (P)(A), ANF-88-133 (P)(A), XN-NF-85-92 (P)(A), and EMF 92-116 (P)(A). Two new methodologies have been added to TS 6.9.1.6.2. EMF-2310 (P)(A),
"SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," has been added to TS 6.9.1.6.2.m, and EMF-2328 (P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," has been added to TS 6.9.1.6.2.o.
Basis for the Proposed Change HNP TS 6.9.1.6.2 requires that methods that are used to determine core operating limits be previously approved by the NRC. The analytical methodologies being added to the HNP TS have been reviewed and approved by the NRC, and this approval is documented within the (P)(A) designated methodology documents in accordance with the guidance in NUREG-0390. EMF 2310 (P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," was approved by NRC Safety Evaluation Report (SER) by letter dated May 11, 2001. Methodology EMF-2328 (P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," was approved by NRC SER in a letter dated March 15, 2001.
Page El-1 of 1
ENCLOSURE 2 TO SERIAL: HNP-02-112 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT ADDITION OF METHODOLOGY REFERENCES TO CORE OPEATING LIMITS REPORT 10 CFR 50.92 EVALUATION The Commission has provided standards in 10 CFR 50.92(c) for determining whether a significant hazards consideration exists. A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety. Carolina Power & Light Company has reviewed this proposed license amendment request and determined that its adoption would not involve a significant hazards determination. The bases for this determination are as follows:
Proposed Change The amendment proposed by Carolina Power & Light Company to the Harris Nuclear Plant (HNP) Technical Specifications (TS) revises TS 6.9.1.6.2 to add analytical methodology references, which are used to determine core operating limits. TS 6.9.1.6.2.f is being revised to relocate six of the referenced methodologies to TS 6.9.1.6.2.n, which groups the mechanical design methodologies together. The six relocated methodologies are: XN-NF-81-58 (P)(A),
ANF-81-58 (P)(A), XN-NF-82-06 (P)(A), ANF-88-133 (P)(A), XN-NF-85-92 (P)(A), and EMF 92-116 (P)(A). Two new methodologies have been added to TS 6.9.1.6.2. EMF-2310 (P)(A),
"SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," has been added to TS 6.9.1.6.2.m, and EMF-2328 (P)(A), "PWR Small Break LOCA Evaluation Model, S RELAP5 Based," has been added to TS 6.9.1.6.2.o.
Basis This change does not involve a significant hazards consideration for the following reasons:
- 1. The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes incorporate additional references to methodologies used to evaluate core operating limits. These methodologies have been approved by the NRC for use in licensing applications. Plant structures, systems, and components will not be operated in a different Page E2-1 of 2
manner as a result of these proposed changes and no physical modifications to equipment are involved. Adding these references to the Core Operating Limits Report section of Technical Specifications does not increase the probability or consequences of an accident previously evaluated.
- 2. The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed changes incorporate additional references to methodologies used to evaluate core operating limits. These methodologies have been approved by the NRC for use in licensing applications. Plant structures, systems, and components will not be operated in a different manner as a result of these changes and no physical modifications to equipment are involved.
Adding these references to the Core Operating Limits Report section of Technical Specifications does not create the possibility of a new or different type of accident from any previously evaluated.
- 3. The proposed amendment does not involve a significant reduction in the margin of safety.
The proposed changes incorporate additional references to methodologies used to evaluate core operating limits. These methodologies have been approved by the NRC for use in licensing applications. Plant structures, systems, and components will not be operated in a different manner as a result of these changes and no physical modifications to equipment are involved.
Adding these references to the Core Operating Limits Report section of Technical Specifications does not involve a significant reduction in the margin of safety.
Page E2-2 of 2
ENCLOSURE 3 TO SERIAL: HNP-02-112 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT ADDITION OF METHODOLOGY REFERENCES TO CORE OPEATING LIMITS REPORT ENVIRONMENTAL CONSIDERATIONS 10 CFR 51.22(c)(9) provides criterion for and identification of licensing and regulatory actions eligible for categorical exclusion from performing an environmental assessment. A proposed amendment to an operating license for a facility requires no environmental assessment if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; (3) result in a significant increase in individual or cumulative occupational radiation exposure. Carolina Power & Light Company has reviewed this request and determined that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment. The basis for this determination follows:
Proposed Change The amendment proposed by Carolina Power & Light Company to the Harris Nuclear Plant (HNP)
Technical Specifications (TS) revises TS 6.9.1.6.2 to add analytical methodology references, which are used to determine core operating limits. TS 6.9.1.6.2.f is being revised to relocate six of the referenced methodologies to TS 6.9.1.6.2.n, which groups the mechanical design methodologies together. The six relocated methodologies are: XN-NF-81-58 (P)(A), ANF-81-58 (P)(A), XN-NF-82-06 (P)(A), ANF-88-133 (P)(A), XN-NF-85-92 (P)(A), and EMF-92-116 (P)(A).
Two new methodologies have been added to TS 6.9.1.6.2. EMF-2310 (P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," has been added to TS 6.9.1.6.2.m, and EMF-2328 (P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," has been added to TS 6.9.1.6.2.o.
Basis The change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) for the following reasons:
- 1. As demonstrated in Enclosure 2, the proposed amendment does not involve a significant hazards consideration.
Page E3-1 of 2
- 2. The proposed amendment does not result in a significant change in the types or increase in the amounts of any effluents that may be released offsite.
The change does not introduce any new effluents or significantly increase the quantities of existing effluents. As such, the change cannot significantly affect the types or amounts of any effluents that may be released offsite.
- 3. The proposed amendment does not result in a significant increase in individual or cumulative occupational radiation exposure.
The proposed change does not result in any physical plant changes or new surveillances that would require additional personnel entry into radiation controlled areas. Therefore, the amendment has no significant affect on either individual or cumulative occupational radiation exposure.
Page E3-2 of 2
ENCLOSURE 4 TO SERIAL: HNP-02-112 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT ADDITION OF METHODOLOGY REFERENCES TO CORE OPEATING LIMITS REPORT PAGE CHANGE INSTRUCTIONS Removed Page Inserted Page 6-24a 6-24a 6-24b 6-24b 6-24c 6-24c Page E4-1 of 1
ENCLOSURE 5 TO SERIAL: HNP-02-112 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT ADDITION OF METHODOLOGY REFERENCES TO CORE OPEATING LIMITS REPORT TECHNICAL SPECIFICATION PAGES Page E5-1 of 8 (including TS pages)
ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)
- d. XN-75-32(P)(A), "Computational Procedure for Evaluating Fuel Rod Bowing," approved version as specified in the COLR.
(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 Rise Hot Channel Factor).
- f. EMF-2087(P)(A), "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," approved version as specified in the COLR.
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-O6(P)(A). "Qualification of Exxon Nuclear Fuel for Extended Burnup," approved version as specified in the COLR.
for Rod BurnupsofofAdvanced Fuelso Nuclearapproved PWR Design Methodology "Qualification ANF-88-133(P)(A), 62 GWd/MTU,"
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 J Designs,." approved_ version as specified in the-- COLR. _
Flu or pecification 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(NP)(A), "A Generic Analysis of the Control Rod Ejection Iransient Tor Pressurized water Keactors, approveu 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.
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 and Application of PDC-3 to H. B. Robinson Unit 2," approved version as specified in the COLR.
(Methodology for Specification 3.2.1 - Axial Flux Difference, and 3.2.2 - Heat Flux Hot Channel Factor).
- i. EMF-92-081(P)(A), "Statistical Setpoint/Transient Methodology for Westinghouse COLR. Type Reactors," approved version as specified in the )I (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).
- j. EMF-92-153(P)(A). "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," approved version as specified in the COLR.
Enthalpy Rise Hot DC1Iav (Methodology for Specification 3.2.3 - Nuclear Channel Factor).
- k. XN-NF-82-49(P)(A), "Exxon Nuclear Company Evaluation Model EXEM PWR Small Break Model," approved version as specified in the COLR.
(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.
ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued) . C ,4
- 1. EMF-96-029(P)(A), "Reactor Analysis Systems for PWRs," approved version as specified in the COLR. Q 7N (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, J
S*,,and 3.9.1 - Boron Concentration).
6.9.1.6.3 The core operating li mits shall be determined so that all applicable limits (e.g.. fuel the rrmal-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, upon including any mid-cycle revisions or supplements, shall b e provided, issuance for each reload cycle, to the NRC Document Contro I Desk, with copies to the Regional Administrator and Resident Inspec :tor.
SPECIAL REPORTS 6.9.2 Special reports shall be s ubmitted to the NRC report. in accordance with 10CFR50.4 within the time period specified for each 6.10 DELETED hInse"Ar n and~'~
(PAGE 6-25 DELETED)
Amendment No.(
SHEARON HARRIS - UNIT 1 6-24c
"/I1 CbjA41vkLke&
Methodologyfor Presszuinzed Water rn-MF-21 O()(A)Ra~bM-8,SRP Chapter 15 Non-LOCA ia APM4 201 t-rmaom IfSr--k reeC A Reactors, 3.1..1.3 - Moderator Temperature (Methodology for Specification Bank Insertion Limits. 3.'1.3.6 Coefficient..3.1.3.5 - Shutdown .3.2.1 Axial Flux Difference.
Control Bank Insertion Limits. Factor. and 3.2.3 - Nuclear Enthalpy Hot Channel 3.2.2 - Heat Flux Facto.r).
Rise Hot Channel Vnei'tt4 L (10 6 L es -
ri.
Response
XN-NF-81-58(P)(A). "RODEX2 Fuel Rod Thermal-Mechanical as specified in the C.OLR.
Evaluation Model." approved version ANF-B1-58(P)(A). "RODEX2 Euelversion Rod Thdrmal Mechanical Response Evaluation Model." approved as specified in the COLR.
Nuclear Fuel for XN-NF-82-06(P)(A). "Qualification ofas Exxon specified in the COLR.
Extended Burnup." approved version
- j ANF-88-133(P)(A). "Qualification of Advanced Nuclear Fuels* PWR GWd/MTU." approved Design Methodology .for Rod Burnups of 62
-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.
q EMF-92-116(P)(A). "Generic M.chanical Design Criteria for PWR Fuel in the COLR.
Designs. a ved version as specified 3.2.1. - Axial Flue Difference.
1.
(Methodoloks~o& Specification Factor. and 3.2.3 Nuclear Enthalpy Hot Channel 3 2.2 - HeatFl ux Factor).
.Rise Hot Channel S-RELA5 Based, EMF-2328(P)(A) *= PWR Small BreakLOCA Evaluation Model, v4r~ ), ikhe Fr;L~a 11ffwP.§A;_e h,2O0l. efou~
(leL.hodology for Specification 3.2.1'- Axial FluxDifference.
3.2.2.- 11eaR .Flux.Hot Channel Factor. and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)
- d. XN-75-32(P)(A). "Computational Procedure for Evaluating Fuel Rod Bowing," approved version as specified in the COLR.
(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 Rise Hot Channel Factor).
- f. EMF-2087(P)(A), "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications." approved version as specified in the COLR.
(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(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.
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 and Application of PDC-3 to H. B. Robinson Unit 2," approved version as specified in the COLR.
(Methodology for Specification 3.2.1 - Axial Flux Difference, and 3.2.2 - Heat Flux Hot Channel Factor).
- i. EMF-92-081(P)(A). "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors," 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, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
- j. -EMF-92-153(P)(A). "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," approved version as specified in the COLR.
(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
- k. XN-NF-82-49(P)(A), "Exxon Nuclear Company Evaluation Model EXEM PWR Small Break Model," approved version as specified in the COLR.
(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).
- 1. EMF-96-029(P)(A), "Reactor Analysis Systems for PWRs," approved version as specified in the COLR.
(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,._3,23_ NuclearEnthalpy._Ri-se Hot_Channel Factor, and 3.9.1 - Boron Concentration).
- m. EMF-2310(P)(A). SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors. 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, 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. 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).
- o. EMF-2328(P)(A) PWR Small Break LOCA Evaluation Model, S-RELAP5 Based, approved version as specified in the COLR.
(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).
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 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 10CFR50.4 within the time period specified for each report.
6.10 DELETED (PAGE 6-25 DELETED)
SHEARON HARRIS - UNIT 1 6-24c Amendment No.