Letter Sequence Other |
---|
TAC:MC4546, Changes to Section 5.0, Administrative Controls, Removal of Monthly Operating Report and Occupational Radiation Exposure Report (Open) TAC:MC4547, Changes to Section 5.0, Administrative Controls, Removal of Monthly Operating Report and Occupational Radiation Exposure Report (Open) |
|
MONTHYEARML0427204482004-09-20020 September 2004 Cycle 12 (U2C12) 12-Month Steam Generator Inspection Report Project stage: Request ML0427904822004-09-28028 September 2004 Duke Energy Corporation, Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Project stage: Request ML0509101512005-03-31031 March 2005 Tech Spec Pages for Amendment Nos. 222 and 217, TS Revisions to Eliminate Monthly Operating and Annual Occupational Radiation Exposure Reports Project stage: Other ML0507004922005-03-31031 March 2005 License Amendment Nos. 222 and 217, TS Revisions to Eliminate Monthly Operating and Annual Occupational Radiation Exposure Reports Project stage: Other ML0507002032005-04-0606 April 2005 RAI, SG Tube IST Reports for End-of-Cycle 12 Refueling Outage (Tac No. MC4545) Project stage: RAI ML0511204592005-04-22022 April 2005 Unit 2 - Response to Request for Information Regarding Steam Generator (SG) Inspection Reports from Unit 2 Cycle 12 Project stage: Response to RAI ML0518107112005-07-0808 July 2005 Ltr., SG ISI Reports Summary for Cycle 12 (Tac No. MC4545) Project stage: Other ML0522300542005-08-11011 August 2005 Notice of Meeting with Firstenergy Nuclear Operating Company Beaver Valley Unit 1 and 2 Extended Power Uprate Small-Break Loss-Of-Coolant Accident Analyses (TAC No. MC4545 and MC4546) Project stage: Meeting ML0520803432005-08-11011 August 2005 Federal Register, Notice of Consideration of Issuance of Amendments to Facility Operating Licenses for Extended Power Uprate (EPU) and Opportunity for Hearing (TACs MC4545 and MC4546 Project stage: Other ML0531101892005-11-0707 November 2005 11/30/2005, Forthcoming Meeting with Firstenergy Nuclear Operating Company (Fenoc), ET Al., Regarding Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and 2), Extended Power Uprate Project stage: Meeting ML0531201042005-11-0808 November 2005 11/30/05 Revised Forthcoming Meeting with Firstenergy Nuclear Operating Company, Regarding Beaver Valley Units 1 and 2 Extended Power Uprate Project stage: Meeting ML0606002062006-03-0202 March 2006 Westinghouse Electric Company, LLC, Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and 2) Project stage: Withholding Request Acceptance ML0605902302006-03-0202 March 2006 Westinghouse Electric Company, LLC, Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML0605901912006-03-0202 March 2006 Westinghouse Electric Company, LLC, Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and 2) Project stage: Withholding Request Acceptance 2005-03-31
[Table View] |
|
---|
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
I Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.
5.6.1 Not used.
5.6.2 Annual Radiological Environmental Operating Report A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.
The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in Chapter 16 of the UFSAR and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.
The Annual Radiological Environmental Operating Report shall include summarized and tabulated results of the analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.
5.6.3 Radioactive Effluent Release Report
-- A-------- -- ----- NOTE------a ----
A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.
The material provided shall be consistent with the objectives outlined in Chapter 16 of the UFSAR and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.
(continued)
Catawba Units 1 and 2 5.6-1 Amendment No. 222/217
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 Not used. I 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
- 1. Illustration of Reactor Core Safety Limits for Specification 2.1.1,
- 2. Moderator Temperature Coefficient BOL and EOL limits and 60 ppm and 300 ppm surveillance limits for Specification 3.1.3,
- 3. Shutdown Bank Insertion Limit for Specification 3.1.5,
- 4. Control Bank Insertion Limits for Specification 3.1.6,
- 5. Axial Flux Difference limits for Specification 3.2.3,
- 6. Heat Flux Hot Channel Factor for Specification 3.2.1,
- 7. Nuclear Enthalpy Rise Hot Channel Factor for Specification 3.2.2,
- 8. Overtemperature and Overpower Delta T setpoint parameter values for Specification 3.3.1,
- 9. Reactor Coolant System Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits for Specification 3.4.1,
- 10. Accumulator and Refueling Water Storage Tank boron concentration limits for Specification 3.5.1 and 3.5.4,
- 11. Reactor Coolant System and refueling canal boron concentration limits for Specification 3.9.1,
- 12. Spent fuel pool boron concentration limits for Specification 3.7.15,
- 13. SHUTDOWN MARGIN for Specification 3.1.1,
- 14. 31 EFPD Surveillance Penalty Factors for Specifications 3.2.1 and 3.2.2, and
- 15. Reactor Makeup Water Pumps Combined Flow Rates limit for Specifications 3.3.9 and 3.9.2.
(continued)
Catawba Unitc I and2 5.6-2 Amendment Nos. 222/217
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 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-1 0266-P-A, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE" (W Proprietary).
- 3. BAW-1 0168-P-A, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants" (B&W Proprietary).
- 4. DPC-NE-201 1-P-A, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors" (DPC Proprietary).
- 5. DPC-NE-3001-P-A, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology" (DPC Proprietary).
- 6. DPC-NF-201 0-A, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design."
- 7. DPC-NE-3002-A, "FSAR Chapter 15 System Transient Analysis Methodology."
- 8. DPC-NE-3000-P-A, "Thermal-Hydraulic Transient Analysis Methodology" (DPC Proprietary).
- 9. DPC-NE-1004-A, "Design Methodology Using CASMO-3/SIMULATE-3P."
- 10. DPC-NE-2004-P-A, "Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01" (DPC Proprietary).
- 11. DPC-NE-2005-P-A, "Thermal Hydraulic Statistical Core Design Methodology" (DPC Proprietary).
(continued)
Catawba Units 1 and 2 5.6-3 Amendment Nos. 222/217
e Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 12. DPC-NE-2008-P-A, "Fuel Mechanical Reload Analysis Methodology Using TACO3" (DPC Proprietary).
- 13. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code" (W Proprietary).
- 14. DPC-NE-2009-P-A, 'Westinghouse Fuel Transition Report" (DPC Proprietary).
- 15. WCAP-12945-P-A, Volume 1 and Volumes 2-5, "Code Qualification Document for Best-Estimate Loss of Coolant Analysis" (y Proprietary).
- 16. DPC-NE-1005P-A, 'Duke Power Nuclear Design Methodology Using CASMO-4/SIMULATE-3 MOX," (DPC Proprietary).
- 17. BAW-1 0231 P-A, "COPERNIC Fuel Rod Design Computer Code,"
(Framatome ANP Proprietary).
The COLR will contain the complete identification for each of the Technical Specifications referenced topical reports used to prepare the COLR (i.e., report number, title, revision number, report date or NRC SER date, and any supplements).
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
5.6.6 Ventilation Systems Heater Report When a report is required by LCO 3.6.10, "Annulus Ventilation System (AVS),"
LCO 3.7.10, 'Control Room Area Ventilation System (CRAVS)," LCO 3.7.12, Auxiliary Building Filtered Ventilation Exhaust System (ABFVES)," LCO 3.7.13,
'Fuel Handling Ventilation Exhaust System (FHVES)," or LCO 3.9.3, "Containment Penetrations," a report shall be submitted within the following 30 days. The report shall outline the reason for the inoperability and the planned actions to return the systems to OPERABLE status.
(continued)
Catawba Units 1 and 2 5.6-4 Amendment Nos. 222/217
4 e Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.7 PAM Report When a report is required by LCO 3.3.3, "Post Accident Monitoring (PAM)
Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
5.6.8 Steam Generator (SG) Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of the inspection. The report shall include:
- a. The scope of inspections performed on each SG,
- b. Active degradation mechanisms found,
- c. Non-destructive examination techniques utilized for each degradation mechanism,
- d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,
- e. Number of tubes plugged during the inspection outage for each active degradation mechanism,
- f. Total number and percentage of tubes plugged to date, and
- g. The results of condition monitoring, including the results of tube pulls and in-situ testing.
Catawba Units 1 and 2 5.6-5 Amendment Nos. 222/217