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Category:Technical Specifications
MONTHYEARML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21154A0462021-07-13013 July 2021 Issuance of Amendments Nos. 222 and 222 Revision of Technical Specifications for the Ultimate Heat Sink ML21060B2812021-04-0202 April 2021 Issuance of Amendments Nos. 221, 221, 224, and 224 Regarding Technical Specifications 3.8.1, AC Sources-Operating ML20317A0012020-12-28028 December 2020 Non-Proprietary, Issuance of Amendment Nos. 219, 219, 223, and 223, Revise Loss-of-Coolant Accident Methodology in TS 5.6.5, Core Operating Limits Report (COLR) ML21008A4052020-12-17017 December 2020 Byron/Braidwood Stations - Revision 18 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications RS-20-154, Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections2020-12-16016 December 2020 Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections ML20167A0072020-09-11011 September 2020 R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20118C4292020-06-0909 June 2020 Issuance of Amendments Revision of Technical Specifications for the Ultimate Heat Sink ML20086M2882020-04-0202 April 2020 Correction of Amendments Nos. for Amendments Revising Instrument Testing and Calibration Definitions RS-19-115, Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-20020 December 2019 Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML19190A0812019-08-28028 August 2019 Issuance of Amendments Regarding Limiting Condition of Operation for Inoperability of Snubbers RS-19-018, Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times2019-02-14014 February 2019 Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times ML18067A1812018-06-0404 June 2018 Correction to Technical Specification Amendment Identification Format ML16180A2512016-08-0101 August 2016 Issuance of Amendments Regarding Use of Optimized Zirlo as Fuel Cladding Material ML16133A4382016-07-26026 July 2016 Issuance of Amendments Ultimate Heat Sink Temperature Increase RS-16-034, License Amendment Request and 10 CFR 50.12 Exemption Request for the Use of Optimized Zirlo Fuel Rod Cladding2016-02-23023 February 2016 License Amendment Request and 10 CFR 50.12 Exemption Request for the Use of Optimized Zirlo Fuel Rod Cladding ML15336A7312016-01-27027 January 2016 TS 50456-Bwd-AppsABC ML15307A7762015-12-21021 December 2015 Braidwood - Issuance of Amendments Regarding Installation of New Low Degraded Voltage Relays and Timers on the 4.16 Kv Engineered Safety Features (ESF) Buses (CAC Nos. MF4051 - MF4054) ML15341A3162015-12-14014 December 2015 Correction of Technical Specifications Related to Amendment 145 ML15286A2762015-11-19019 November 2015 Technical Specifications ML15232A4412015-10-28028 October 2015 Issuance of Amendments to Utilize WCAP-16143-P, Revision 1 Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Byron/Braidwood Units 1 and 2, Dated October 2014 ML15268A4862015-10-0606 October 2015 Correction of Amendments Adopting Technical Specification Task Force Traveler TSTF-523 (TAC Nos. MF4436-MF4446) ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML14323A5222015-04-0808 April 2015 Issuance of Amendments Regarding the Emergency Plan Definition of Annual Training RS-14-337, Units 1 & 2 - License Amendment Request for Diesel Generator Load Rejection Surveillance Requirement2014-12-18018 December 2014 Units 1 & 2 - License Amendment Request for Diesel Generator Load Rejection Surveillance Requirement ML14239A4272014-12-0707 December 2014 Issuance of Amendments to Clarify Technical Specification 3.3.1, Reactor Trip System Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System Instrumentation ML13311B4812014-07-21021 July 2014 Issuance of Amendments to Revise Technical Specifications Section 3.5.3 ML14085A5322014-07-21021 July 2014 Issuance of Amendments Adoption of TSTF-522 Ventilation System Surveillance Requirements ML14069A3372014-04-0202 April 2014 Final Response to Task Interface Agreement 2012-13, Braidwood Station Technical Specification 3.6.3 Compliance with One or More Main Steam Isolation Valves Inoperable ML13326A1072014-03-13013 March 2014 Issuance of Amendments to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program ML13281A0002014-02-0707 February 2014 Issuance of Amendments Regarding Measurement Uncertainty Recapture Power Uprate RS-13-240, License Amendment Request to Administratively Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program.2013-10-10010 October 2013 License Amendment Request to Administratively Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program. RS-13-137, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process2013-09-0303 September 2013 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process RS-13-175, Bryon, Units 1 and 2, License Amendment Request to Revise Technical Specifications Section 3.7.2, Main Steam Isolation Valves (Msivs).2013-08-21021 August 2013 Bryon, Units 1 and 2, License Amendment Request to Revise Technical Specifications Section 3.7.2, Main Steam Isolation Valves (Msivs). RS-12-009, License Amendment Request - Diesel Generator Steady State Maximum Frequency and Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel2012-05-0101 May 2012 License Amendment Request - Diesel Generator Steady State Maximum Frequency and Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel RS-12-028, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.2012-03-22022 March 2012 Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. RS-12-023, License Amendment Request to Revise Tech Specs Sections 5.5.9, Steam Generator (SG) Program, and TS 5.6.9, Steam Generator (SG) Tube Inspection Report, for Permanent Alternate Repair Criteria2012-03-20020 March 2012 License Amendment Request to Revise Tech Specs Sections 5.5.9, Steam Generator (SG) Program, and TS 5.6.9, Steam Generator (SG) Tube Inspection Report, for Permanent Alternate Repair Criteria RS-11-136, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications (TS) 3.3.12011-09-0202 September 2011 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications (TS) 3.3.1 ML1117900312011-06-23023 June 2011 Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate, Attachment 2A, Markup of Proposed Operating License and Technical Specifications Pages ML1032704352010-12-21021 December 2010 Tech Spec Pages for Braidwood and Byron Amendment Large Break Loss-of-Coolant Accident Analysis Using Astrum ML1032704452010-12-21021 December 2010 Tech Spec Pages for Braidwood and Byron Amendment Large Break Loss-of-Coolant Accident Analysis Using Astrum RS-10-197, License Amendment Request to Revise Technical Specifications (TS) Sections 5.5.9, Steam Generator Program, and TS 5.6.9, Steam Generator Tube Inspection Report, for Temporary Alternate Repair Criteria2010-12-14014 December 2010 License Amendment Request to Revise Technical Specifications (TS) Sections 5.5.9, Steam Generator Program, and TS 5.6.9, Steam Generator Tube Inspection Report, for Temporary Alternate Repair Criteria RS-10-114, License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal2010-06-29029 June 2010 License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal RS-10-052, License Amendment Request for an Extension of the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process2010-03-29029 March 2010 License Amendment Request for an Extension of the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process 2023-07-13
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Programs and Manuals 5.5
( 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented. and maintained.
5.5.1 Offsite Dose Calculation Manual (ODCM)
- a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents. in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints. and in the conduct of the radiological environmental monitoring program:
- b. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities. and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports required by Specification 5.6.2 and Specification 5.6.3: and
' c. Licensee initiated 'changes to the ODCM:
- 1. Shall be documented and records of reviews perforned shall be retained. This documentation shall contain:
- i. sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s). and ii. a determination that the change(s) maintain the levels of radioactive effluent control.required by 10 CFR 20.1302. 40 CFR 190. 10 CFR 50.36a.
and 10 CFR 50, Appendix I. and not adversely impact the accuracy or reliability of effluent.
dose. or setpoint calculations:
- 2. Shall become effective after the approval of the station manager: and BRAIDWOOD - UNITS 1 & 2 5.5 -1 ?,,hao Amendment 98
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM) (continued)
- 3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages. clearly indicating the area of the page that was changed, and shall indicate the date (i.e.. month and year) the change was implemented.
5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize len:age from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include the recirculation portions of the Containment Spray. Safety Injection.
Chemical and Volume Control. and Residual Heat Removal. The program shall include the following:
- a. Preventive maintenance and periodic visual inspection requirements: and
- b. Integrated leak test requirements for each system at refueling cycle intervals or less.
5.5.3 Deleted.
BRAIDWOOD - UNITS 1 & 2 5.5-2 Amendment 121
-.I-..-...-..- ---
Programs and Manuals 5.5
( 5.5 Programs and Manuals 5.5.41 Radioactive Effluent Controls Prooram This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures. and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
- a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;
- b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas.
conforming to 10 times the concentrations stated in 10 CFR 20. Appendix B. Table 2. Column 2 (to paragraphs 20.1001 - 20.2402):
- c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with
{. the methodology and parameters in the ODCM:
- d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I:
- e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days:
(
BRAIDW4OOD - UNITS 1 & 2 5.5 - 3 5 Amendment 98
Programs and Manuals 5.5
( 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)
- f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment. conforming to 10 CFR 50.
Appendix I;
- 9. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the following:
- 1. For noble gases: < a dose-rate of 500 mrem/yr to the whole body and s a dose rate of 3000 mrem/yr to the skin, and
- 2. For Iodine-131. Iodine-133. Tritium. and for all radionuclides in particulate form with half lives
> 8 days: s a dose rate of 1500 mrem/yr to any organ;
- h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50. Appendix I:
- i. Limitations on the annual and quarterly doses to a member of the public from Iodine-131. Iodine-133. Tritium. and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary. conforming to 10 CFR 50, Appendix I: and Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity' and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
5.5.E, ComDonent Cyclic or Transient Limit This program provides controls to track the UFSAR. Section 3.9.
cyclic and transient occurrences to ensure that components are maintained within the design limits.
BRAIDWOOD - UNITS 1 & 2 5.5 -4 Amendment 98
Reporting Requirements 5.6
( 5.6; Reporting Requirements 5.,6.2 Annual Radiological Environmental Operating Report
NOTE---------------
A single submittal may be made for the facility. The submittal should combine sections common to both units.
The Annual Radiological Environmental Operating Report covering the operation of the facility during the previous calendar year shall be submitted by May 15 of each year. The report shall include sunnaries, 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.
5.6.3 Radioactive Effluent Release Report
NOTE----
A single submittal may be made for the facility. The submittal
( -shall combine sections common to both units.
The Radioactive Effluent Release Report covering the operation of the facility during 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 facility.
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 ],
Section IV.B.1.
5.6.4 (Deleted)
BRAIDWOOD - UNITS 1 & 2 5.6 - 2 Amendment 136