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MONTHYEARML0508701832005-03-22022 March 2005
Technical Specifications, Elimination of Monthly Operating and Occupational Radiation Exposure Report Requirements,
Project stage: Other
ML0508106582005-03-22022 March 2005
License Amendment Nos. 239 & 220, Elimination of Monthly Operating and Occupational Radiation Exposure Report Requirements
Project stage: Other
2005-03-22
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Category:Technical Specifications
MONTHYEARML23072A0892023-05-0101 May 2023
(Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements
ML21232A2172021-10-19019 October 2021
Issuance of Amendment Nos. 288 and 271 to Revise Technical Specifications Battery Surveillance Testing
ML21280A3282021-10-0707 October 2021
Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions
ML20325A0952021-03-19019 March 2021
Issuance of Amendment to Revise Technical Specifications to Allow Usage of a Small Break Loss of Coolant Accident Methodology (Non-Proprietary)
ML20302A1792020-10-29029 October 2020
Non-Proprietary, Issuance of Amendment Nos. 286 and 269 to Revise Technical Specifications to Allow Usage of a Full Spectrum Loss of Coolant Accident Methodology
ML19238A1272019-09-12012 September 2019
Issuance of Amendment Nos. 282 and 265 to Revise Technical Specifications Regarding Open Phase Protection
ML19196A1102019-07-0909 July 2019
Attachments 2, 3 & 4 - Response to NRC Request for Additional Information and Correction of SBLOCA Analysis Error and Revised Marked-Up/Typed NAPS and SPS Technical Specifications Pages
ML19156A2072019-05-24024 May 2019
Response to Request for Additional Information on Proposed License Amendment Request Open Phase Protection Per NRC Bulletin 2012-01
ML17187A1322017-06-28028 June 2017
Submittal of Topical Report VEP-NE-1, Revision 0.2-A, Relaxed Power Distribution Control Methodology and Associated Fq Surveillance Technical Specifications for Information Only
ML16252A4782016-10-17017 October 2016
Issuance of Amendments Revising Technical Specifications to Address the Issue Identified in Westinghouse NSAL-09-5, Revision 1, and NSAL-15-1, Revision 0
ML16013A4442016-02-22022 February 2016
(NAPS) - Issuance of Amendment for Changes to Technical Specification (TS) 3.8.1 - AC Sources, Operating Revised Surveillance Requirement
ML15307A3002016-02-0202 February 2016
(NAPS) - Issuance of Amendments for Changes to the Emergency Action Level Revisions - Correction of Equipment Mark Number
ML15245A4822015-10-0707 October 2015
Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses
ML15133A3812015-06-16016 June 2015
Issuance of Amendments to Extended Type a Test Frequency to 15 Years
ML15147A0292015-05-22022 May 2015
Proposed License Amendment Request (Lar), TS 3.8.1 - AC Sources - Operating, Revised Surveillance Requirement
ML15083A4362015-05-14014 May 2015
Issuance of Amendments Regarding Alternate Control Rod Position Monitoring
ML15041A6672015-02-0404 February 2015
Proposed License Amendment Request Re Alternate Control Rod Position Monitoring
ML14188C4532014-08-27027 August 2014
Issuance of Amendments Regarding Modification of Control Bank Sequence and Overlap Technical Specifications
ML14169A3592014-08-12012 August 2014
Stations, Units 1 and 2, Issuance of Amendments Regarding Addition of an Analytical Methodology to the Core Operating Limits Reports and an Increase to the Surry Minimum Temperature for Criticality
ML14183B3182014-06-30030 June 2014
Proposed License Amendment Request Permanent Fifteen-Year Type a Test Interval
ML13302B8922013-10-0202 October 2013
Technical Specification Bases
ML12356A2982012-12-13013 December 2012
Supplemental Information for Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process.
ML12219A0722012-07-30030 July 2012
Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process
ML12136A4512012-05-11011 May 2012
Proposed License Amendment Request - Temporary Change to Allow Two Inoperable Demand Position Indicators Per Control Bank
PLA-6842, Response to E-mail (Dated March 30, 2012), Request for Additional Information on Proposed Amendment Number 2812012-04-0202 April 2012
Response to E-mail (Dated March 30, 2012), Request for Additional Information on Proposed Amendment Number 281
ML1111900932011-04-27027 April 2011
License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation.
ML1029804472010-10-21021 October 2010
Proposed License Amendment Request (LAR) Addition of Analytical Methodology to COLR Best-Estimate Large Break Loss of Coolant Accident (BE-LBLOCA)
ML0935004002010-03-0303 March 2010
Issuance of Amendments to Adopt TSTF-490, Revision 0, Regarding Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Using the Consolidated Line Item Improvement Process
ML0920503812009-07-23023 July 2009
License Amendment Request, One Time Extension of the Completion Time for 1 J - 480 Volt AC Distribution Subsystem
ML0909000552009-03-26026 March 2009
License Amendment Request, Measurement Uncertainty Recapture Power Uprate
ML0904004652009-02-0606 February 2009
License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Work Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26
ML0815106502008-06-30030 June 2008
Technical Specifications, Issuance of Amendment Regarding One-Time 5-Year Extension to Type a Test Interval
ML0735202472007-12-17017 December 2007
Proposed License Amendment Request, One-time Risk-Informed Extension to the Completion Time for EDG Fuel Oil Storage Tank Recoating
ML0730604062007-10-31031 October 2007
Tech Spec Pages for Amendments 252 and 232 Control Room Habitability, Using the Technical Specification Task Force Traveler, TSTF-448, Revision 3
ML0730304002007-10-17017 October 2007
Tech Pages for Amendments 251 and 231 Technical Specification Change to Add Limiting Condition for Operation 3.0.8 on the Inoperability of Snubbers, Using the Consolidated Line Item Improvement Process, TSTF-372, Rev 4
ML0715001452007-05-29029 May 2007
Proposed License Amendment Request, Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process
ML0714104632007-05-21021 May 2007
Proposed License Amendment Request Addition of LCO 3.0.8 - Inoperability of Snubbers Using the Consolidated Line Item Improvement Process Technical Specification Improvement
ML0702202192007-01-19019 January 2007
Technical Specifications Corrected Page for Amendment Nos. 249 and 229
ML0701003492007-01-0909 January 2007
Technical Specifications, Relocated the ASTM Standard Used to Test the Total Particulate Concentration of the Stored Fuel Oil from TS 5.5.12, Emergency Diesel Generator Fuel Oil Testing Program to a Licensee-controlled Program
ML0634502592006-12-11011 December 2006
Tech Spec Pages for Amendments 249 and 229 Regarding Diesel Fuel Oil Testing Program
ML0630000282006-10-16016 October 2006
Tech Spec Pages for Amendments 248 and 228 Regarding Consolidated Line Item Improvement Process for the Steam Generator Tube Integrity
ML0627700182006-09-25025 September 2006
Technical Specification Bases Pages
ML0620604672006-07-18018 July 2006
Technical Specifications, Issuance of Amendments on Changes to Analytical Methodology and Core Operating Limits Report, MC7526 and MC7527
ML0615101992006-05-30030 May 2006
Proposed Technical Specifications Change Diesel Fuel Oil Testing Program
ML0533502792005-11-21021 November 2005
10 CFR 50.9 Correction of Information Provided to Support Technical Specification Change for Quench Spray and Recirculation Spray Nozzles Surveillance Frequency
ML0529900852005-10-25025 October 2005
Enclosure, Technical Specifications, Amd MC7612, Equation for Over-Temperature Delta T Function Allowable Value
ML0529900152005-10-24024 October 2005
Technical Specifications, Revised Test Frequency of P-4 Interlock Function
ML0526301042005-09-15015 September 2005
Tech Spec Pages for Amendment Nos. 243 and 224, Revise the Administrative Controls Section
ML0519604352005-07-14014 July 2005
Proposed Technical Specification Changes Correction to Equation for Overtemperature T Function Allowable Value
ML0518900342005-07-0505 July 2005
Proposed Technical Specification Changes Addition of Analytical Methodology to COLR
2023-05-01
[Table view] |
Text
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
NOTE--------------------------------
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 1 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 the Offsite Dose Calculation Manual (ODCM),
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 the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements commensurate with the format in the ODCM.
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 Annual Radioactive Effluent Release Report
-__ __ _____-_ --------- NOTE--------------------------------
A single submittal may be made for a multiple unit station. The submittal shall 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 Annual 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 (continued)
North Anna Units 1 and 2 5.6-1 Amendment Mos. 239/220
- - t- -I Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 Annual Radioactive Effluent Release Report (continued) 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 the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.
5.6.4 Not used 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. Safety Limits,
- 2. SHUTDOWN MARGIN,
- 3. Moderator Temperature Coefficient,
- 4. Shutdown Bank Insertion Limits,
- 5. Control Bank Insertion Limits,
- 6. AXIAL FLUX DIFFERENCE limits,
- 7. Heat Flux Hot Channel Factor,
- 8. Nuclear Enthalpy Rise Hot Channel Factor,
- 9. Power Factor Multiplier,
- 10. Reactor Trip System Instrumentation - OTAT and OPAT Trip Parameters,
- 11. RCS Pressure, Temperature, and Flow DNB Limits, and
- 12. Boron Concentration.
North Anna Units 1 and 2 5.6-2 Amendment Nos. 239/220
R rr R 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. VEP-FRD-42-A, "Reload Nuclear Design Methodology."
- 2. WCAP-9220-P-A, "WESTINGHOUSE ECCS EVALUATION MODEL-1981 VERSION."
- 3. WCAP-9561-P-A, "BART A-1: A COMPUTER CODE FOR THE BEST ESTIMATE ANALYSIS OF REFLOOD TRANSIENTS-SPECIAL REPORT:
THIMBLE MODELING IN W ECCS EVALUATION MODEL."
- 4. WCAP-10266-P-A, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code."
- 5. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code."
- 6. WCAP-10079-P-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code."
- 7. WCAP-12610, "VANTAGE+ FUEL ASSEMBLY-REFERENCE CORE REPORT."
- 8. VEP-NE-2-A, "Statistical DNBR Evaluation Methodology."
- 9. VEP-NE-3-A, "Qualification of the WRB-1 CHF Correlation in the Virginia Power COBRA Code."
- 10. VEP-NE-1-A, "VEPCO Relaxed Power Distribution Control Methodology and Associated FQ Surveillance Technical Specifications."
- 11. WCAP-8745-P-A, "Design Bases for Thermal Overpower Delta-T and Thermal Overtemperature Delta-T Trip Function."
- 12. WCAP-14483-A, "Generic Methodology for Expanded Core Operating Limits Report."
- 13. BAW-10227P-A, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel."
(continued)
North Anna Units 1 and 2 5.6-3 Amendment Nos. 239/220
I Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- b. (continued)
- 14. BAW-10199P-A, "The BWU Critical Heat Flux Correlations."
- 15. BAW-10170P-A, "Statistical Core Design for Mixing Vane Cores."
- 16. EMF-2103 (P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors."
- 17. EMF-96-029 (P)(A), "Reactor Analysis System for PWRs."
- 18. BAW-10168P-A, "RSG LOCA - BWNT Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants,"
Volume II only (SBLOCA models).
- 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 PAM Report When a report is required by Condition B of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
5.6.7 Steam Generator Tube Inspection Report
- a. Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Nuclear Regulatory Commission within 15 days.
North Anna Units 1 and 2 5.6-4 Amendment Nos. 239/220
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 Steam Generator Tube Inspection Report (continued)
- b. The complete results of the steam generator tube inservice inspection shall be reported to the NRC by March 1 of each year for the previous calender year. This report shall include:
- 1. Number and extent of tubes inspected.
- 2. Location and percent of wall-thickness penetration for each indication of an imperfection.
- 3. Identification of tubes plugged.
- c. Results of steam generator tube inspections that fall into Category C-3 require prompt notification of the Commission pursuant to Section 50.72 to 10 CFR Part 50. A Licensee Event Report shall be submitted pursuant to Section 50.73 to 10 CFR Part 50 and shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
North Anna Units 1 and 2 5.6-5 Amendment Nos. 239/220
