Letter Sequence Other |
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TAC:MB3343, Revise Topical Report References in ITS 5.6.5, Colr (Approved, Closed) TAC:MB3344, Revise Topical Report References in ITS 5.6.5, Colr (Approved, Closed) |
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MONTHYEARML0223301042002-08-0707 August 2002
Response to NRC Request for Additional Information and License Amendment Request Supplement
Project stage: Supplement
ML0223901102002-08-20020 August 2002
Catawba/Mcguire, Units 1 & 2, Notice of Consideration of Issuance of Amendments Technical Specifications 5.6.5.a Regarding the Core Operating Limits Report
Project stage: Other
ML0227405272002-10-0101 October 2002
License Amendments, Revising TS 5.6.5.a by Adding a Few Parameter Limits Currently Included in the Core Operating Limits Report
Project stage: Other
ML0227406772002-10-0101 October 2002
License Amendment 202 & 195 Revising TS 5.6.5 by Adding Parameter Limits Currently Included in Core Operating Limits Report
Project stage: Approval
ML0227502062002-10-0101 October 2002
Technical Specifications for Amendments 202 & 195 Revising TS 5.6.5.a by Adding a Few Parameter Limits Currently Included in the Core Operating Limits Report
Project stage: Other
ML0227501192002-10-0101 October 2002
TS Pages for Amendments 208 & 189 Revising TS 5.6.5.a
Project stage: Other
ML0233303722002-11-19019 November 2002
Proposed Revision to Page 3-1 of Topical Report DPC-NF-2010, Nuclear Physics Methodology for Reload Design
Project stage: Other
ML0305903242003-02-13013 February 2003
Submittal of Published Versions of Approved Topical Reports, Table of Contents - Safety Evaluation
Project stage: Other
ML0305902512003-02-13013 February 2003
Submittal of Published Versions of Approved Topical Reports, Table of Contents - Safety Evaluation
Project stage: Other
ML0305902452003-02-13013 February 2003
Submittal of Published Versions of Approved Topical Reports, Section 12 - Safety Evaluation Report
Project stage: Other
ML0305901742003-02-13013 February 2003
Submittal of Published Versions of Approved Topical Reports, Table of Contents - Section 11
Project stage: Other
ML0305901582003-02-13013 February 2003
Submittal of Published Versions of Approved Topical Reports
Project stage: Other
2002-08-20
[Table View] |
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Category:Technical Specifications
MONTHYEARML23195A0782023-08-29029 August 2023
Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1
ML22263A0432022-09-0707 September 2022
Editorial Change to SLC 16.10-5
ML20174A0452020-08-0404 August 2020
Issuance of Amendment No. 306 to Revise Technical Specification 3.4.3, RCS (Reactor Coolant System) Pressure and Temperature (P/T) Limits
RA-17-0051, Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating2017-11-21021 November 2017
Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating
RA-17-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2017-07-18018 July 2017
Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules
ML17066A3742017-04-26026 April 2017
Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049)
ML16124A6942016-06-0202 June 2016
Issuance of Amendments Regarding Changes to Technical Specification 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits
ML16081A3332016-04-29029 April 2016
Issuance of Amendments Regarding Measurement Uncertainty Recapture Power Uprate
ML16075A3012016-04-26026 April 2016
Issuance of Amendments Regarding the Revision of the Steam Generator Technical Specifications to Reflect the Adoption of TSTF-510(CAC Nos. MF6139,MF6140,MF6141,MF6142,MF6143,MF6144.
ML16082A0382016-04-18018 April 2016
Issuance of License Amendment Regarding Emergency Action Level Scheme Change
ML16067A2292016-04-0808 April 2016
Issuance of Amendments Regarding Removal of Obsolete Technical Specification Requirements
ML16007A1762016-01-12012 January 2016
Issuance of Amendments Regarding Non-Conservative Technical Specification Allowable Value
ML15320A3332015-12-18018 December 2015
Issuance of Amendments Regarding Non-Conservative Technical Specifications Allowable Value
ML15133A4532015-06-11011 June 2015
McGuire Nuclear Station, Oconee Nuclear Station - Issuance of Amendments Regarding Changes to Cyber Security Plan Implementation Schedule Milestone 8
ML15063A2712015-04-14014 April 2015
Issuance of Amendments Technical Specification 3.1.3, Moderator Temperature Coefficient and TS 5.6.5, Core Operating Limits Report.
ML15027A3662015-03-25025 March 2015
Issuance of Amendments DPC-NE-3001-P, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology
ML15002A3242015-02-12012 February 2015
McGuire Nuclear Station, and Oconee Nuclear Station - Issuance of Amendments Regarding Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Areas
CNS-14-076, License Amendment Request (LAR) for Measurement Uncertainty Recapture (Mur) Power Uprate2014-06-23023 June 2014
License Amendment Request (LAR) for Measurement Uncertainty Recapture (Mur) Power Uprate
ML14056A2172014-02-27027 February 2014
Issuance of Amendments Regarding Exigent License Amendment Request to Revise Technical Specification 3.3.4, Remote Shutdown System (TAC MF3473&74)
ML12194A2182012-07-0909 July 2012
Response to NRC Request for Additional Information on Proposed Technical Specifications (TS) and Bases Amendment TS and Bases 3.7.8, Nuclear Service Water System (Nsws)
ML12038A1732012-02-0101 February 2012
Proposed Tech Specs Amendment TS 3.4.13, TS 5.5.9, TS 5.6.8, License Amendment Request to Revise TS for Permanent Alternate Repair Criteria
ML1106705362011-03-29029 March 2011
Issuance of Amendments Regarding Revision of the Technical Specifications to Relocate Specific Surveillance Frequency Requirements to a Licensee Controlled Program Using a Risk-Informed Justification
ML1032700112010-12-20020 December 2010
Issuance of Amendments Regarding Revision of Technical Specification (TS) 3.8.4 DC Sources - Operating
ML1026405372010-09-27027 September 2010
Issuance of Amendment Regarding the Steam Generator Program.
ML1025601442010-09-0909 September 2010
Proposed Technical Specifications (TS) Amendment TS 5.5.9, Steam Generator (SG) Program TS 5.6.8, Steam Generator (SG) Tube Inspection Report License Amendment Request to Revise TS for Alternate Repair Criteria
ML1021605622010-08-0202 August 2010
Notice of Enforcement Discretion Request, Technical Specification 3.8.1, AC Sources - Operating, TS 3.78, Nuclear Service Water System, TS 3.7.5, Auxiliary Feedwater System, TS 3.6.6, Containment Spray System.
ML0925300882010-06-28028 June 2010
License Amendment, Issuance of Amendments Regarding Technical Specification Change to Allow Manual Operation of the Containment Spray System (TAC Nos. MD9752 and MD9753)
ML1017303882010-04-28028 April 2010
Proposed Technical Specifications Amendment TS 5.5.9, Steam Generator Program, TS 5.6.8, Steam Generator Tube Inspection Report, License Amendment Request to Revise TS for Alternate Repair Criteria
ML1009201602010-03-31031 March 2010
Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
ML0935600772009-12-15015 December 2009
Technical Specifications Revision Request to Adopt TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to RCS Specific Activity.
ML0923805882009-10-30030 October 2009
License Amendment, Implement Technical Specification Task Force (TSTF) Changes Travelers TSTF-479, Revision 0, Changes to Reflect Revision (Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a) 10 CFR 50.55a,..
ML0924003112009-09-21021 September 2009
Issuance of Amendments Regarding Proposed Implementation of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from Ts. 5.2.2 to Support Compliance with 10 CFR Part 26. Catawba Units 1& 2, McGuire, Units 1 & 2, Oconee, Units 1, 2, &
ML0919503552009-07-0101 July 2009
License Amendment Request to Support Plant Modifications to the Nuclear Instrumentation System
ML0914102832009-05-18018 May 2009
License Amendment Request to Revise the Definition of Shutdown Margin (SDM)
ML0905402522009-02-19019 February 2009
Proposed Technical Specifications Amendment TS 5.5.9, Steam Generator Program, TS 5.6-8, Steam Generator Tube Inspection Report.
ML0835704702008-12-18018 December 2008
Units 1 &2 - Proposed Technical Specification Amendment to Relax Completion Times and Surveillance Intervals for the Reactor Trip System Instrumentation TS 3.3.1, Engineered Safety Feature Actuation System Instrumentation.
ML0828800982008-10-0808 October 2008
Proposed Technical Specifications and Bases Amendment, TS and Bases Administrative Changes
ML0819803572008-07-15015 July 2008
Technical Specifications, Issuance of Emergency Amendment Regarding One-Time Extension of the Auxiliary Feedwater System and the Containment Spray System Allowed Outage Time
ML0817700602008-06-23023 June 2008
Proposed Technical Specifications (TS) and Bases Amendment, TS and Bases 3.7.8, Nuclear Service Water System, Response to Request for Additional Information
ML0806304962008-03-28028 March 2008
Technical Specifications, Issuance of Amendments Regarding a Change in Corporate Name of License & Oconee Independent Spent Fuel Storage Installation (TAC Nos. MD5156 - MD5162)
ML0731803132007-11-0808 November 2007
Tech Spec Pages for Amendments 238 and 234 Regarding Emergency Core Cooling System Strainer Modification
ML0730904132007-10-31031 October 2007
Technical Specifications, Issuance of Amendment Regarding Technical Specification 5.5.9 Steam Generator Tube Surveillance Program
ML0730604052007-10-31031 October 2007
Tech Spec Pages for Amendment 237 Regarding Extension of Time Limit to Complete Emergency Core Cooling Systems Sump Modification
ML0717703102007-06-25025 June 2007
Issuance of Amendments Regarding Emergency Diesel Generator Testing (TAC Nos. MD3217 and MD3218) - Technical Specifications
ML0707903972007-03-19019 March 2007
Tech Spec Pages for Amendments 235 and 231 Regarding Snubbers, TSTF-372, Rev. 4
ML0635303422006-12-0707 December 2006
Proposed Technical Specifications (TS) Amendments TS 3.7.10 (Catawba)/Ts 3.7.9 (McGuire) - Control Room Area Ventilation System (Cravs) TS 3.7.11 (Catawba)/Ts 3.7.10 (McGuire) - Control Room Area Chilled Water System (Cracws)
ML0629003532006-09-30030 September 2006
Tech Spec Pages for Amendments 234 and 230, Revising Reactor Coolant Systems Leakage Detection Instrumentation
ML0627105962006-09-27027 September 2006
Tech Spec Pages for Amendments 233 and 229 Revised Storage Criteria for Low-enriched Uranium Fuel
ML0626901142006-09-25025 September 2006
Technical Specifications Revision of Temperature Limits for the Standby Nuclear Service Water Pond
ML0626901122006-09-25025 September 2006
Tech Spec Pages for Amendments 231 and 227 Regarding Updated Final Safety Analysis Report and Emergency Operating Procedures
2023-08-29
[Table view] |
Text
"ReportingRequirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 1. Moderator Temperature Coefficient BOL and EOL limits and 60 ppm and 300 ppm surveillance limits for Specification 3.1.3,
- 2. Shutdown Bank Insertion Limit for Specification 3.1.5,
- 3. Control Bank Insertion Limits for Specification 3.1.6,
- 4. Axial Flux Difference limits for Specification 3.2.3,
- 5. Heat Flux Hot Channel Factor for Specification 3.2.1,
- 6. Nuclear Enthalpy Rise Hot Channel Factor for Specification 3.2.2,
- 7. Overtemperature and Overpower Delta T setpoint parameter values for Specification 3.3.1,
- 8. Accumulator and Refueling Water Storage Tank boron concentration limits for Specification 3.5.1 and 3.5.4,
- 9. Reactor Coolant System and refueling canal boron concentration limits for Specification 3.9.1,
- 10. Spent fuel pool boron concentration limits for Specification 3.7.15,
- 11. SHUTDOWN MARGIN for Specification 3.1.1,
- 12. 31 EFPD Surveillance Penalty Factors for Specifications 3.2.1 and 3.2.2, and
- 13. Reactor Makeup Water Pumps Combined Flow Rates limit for Specifications 3.3.9 and 3.9.2.
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY" (W Proprietary).
- 2. WCAP-10266-P-A, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE" (W Proprietary).
(continued)
Catawba Units 1 and 2 5.6-3 Amendment Nos.2 0 2 &-195
FQ(X,Y,Z)
B 3.2.1 BASES SURVEILLANCE REQUIREMENTS (continued) than the measured factor is of the current limit, additional actions must be taken. These actions are to meet the FQ(X,Y,Z) limit with the last FMa(XY,Z) increased by the appropriate factor specified in the COLR or to evaluate FQ(X,Y,Z) prior to the projected point in time when the extrapolated values are expected to exceed the extrapolated limits.
These alternative requirements attempt to prevent Fo(X,Y,Z) from exceeding its limit for any significant period of time without detection using the best available data. FMa(X,Y,Z) is not required to be extrapolated for the initial flux map taken after reaching equilibrium conditions since the initial flux map establishes the baseline measurement for future trending. Also, extrapolation of FMa(X,Y,Z) limits are not valid for core locations that were previously rodded, or for core locations that were previously within +/-2% of the core height about the demand position of the rod tip.
FQ(X,Y,Z) is verified at power levels > 10% RTP above the THERMAL POWER of its last verification, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving equilibrium conditions to ensure that FQ(X,Y,Z) is within its limit at higher power levels.
The Surveillance Frequency of 31 EFPD is adequate to monitor the change of power distribution with core burnup. The Surveillance may be done more frequently if required by the results of FQ(X,Y,Z) evaluations.
The Frequency of 31 EFPD is adequate to monitor the change of power distribution because such a change is sufficiently slow, when the plant is operated in accordance with the TS, to preclude adverse peaking factors between 31 day surveillances.
REFERENCES 1. 10 CFR 50.46.
- 2. UFSAR Section 15.4.8.
- 3. 10 CFR 50, Appendix A, GDC 26.
- 4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).
- 5. DPC-NE-201 1 PA "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors".
B 3.2.1 -11 Revision No. 3 Catawba Units I and 2
AFD B 3.2.3 BASES SURVEILLANCE REQUIREMENTS (continued)
This Surveillance verifies that the AFD, as indicated by the NIS excore channel, is within its specified limits and is consistent with the status of the AFD monitor alarm. With the AFD monitor alarm inoperable, the AFD is monitored every hour to detect operation outside its limit. The Frequency of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is based on operating experience regarding the amount of time required to vary the AFD, and the fact that the AFD is closely monitored. With the AFD monitor alarm OPERABLE, the Surveillance Frequency of 7 days is adequate considering that the AFD is monitored by a computer and any deviation from requirements is alarmed.
REFERENCES 1. DPC-NE-2011PA, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors".
- 2. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).
- 3. UFSAR, Chapter 7.
Catawba Units 1 and 2 B 3.2.3-4 Revision No. 1
