Letter Sequence Other |
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TAC:MF4436, Generic Letter 2008-01, Managing Gas Accumulation (Approved, Closed) TAC:MF4437, Generic Letter 2008-01, Managing Gas Accumulation (Approved, Closed) TAC:MF4438, Generic Letter 2008-01, Managing Gas Accumulation (Approved, Closed) TAC:MF4439, Generic Letter 2008-01, Managing Gas Accumulation (Approved, Closed) TAC:MF4440, Generic Letter 2008-01, Managing Gas Accumulation (Approved, Closed) TAC:MF4441, Generic Letter 2008-01, Managing Gas Accumulation (Approved, Closed) TAC:MF4442, Generic Letter 2008-01, Managing Gas Accumulation (Approved, Closed) TAC:MF4443, Generic Letter 2008-01, Managing Gas Accumulation (Approved, Closed) TAC:MF4444, Generic Letter 2008-01, Managing Gas Accumulation (Approved, Closed) TAC:MF4445, Generic Letter 2008-01, Managing Gas Accumulation (Approved, Closed) TAC:MF4446, Generic Letter 2008-01, Managing Gas Accumulation (Approved, Closed) |
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MONTHYEARML15114A1882015-06-19019 June 2015 Issuance of Amendments Adoption of Technical Specification Task Force (TSTF) Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation Project stage: Approval ML15268A4862015-10-0606 October 2015 Correction of Amendments Adopting Technical Specification Task Force Traveler TSTF-523 (TAC Nos. MF4436-MF4446) Project stage: Other 2015-10-06
[Table View] |
Correction of Amendments Adopting Technical Specification Task Force Traveler TSTF-523 (TAC Nos. MF4436-MF4446)ML15268A486 |
Person / Time |
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Site: |
Byron, Braidwood, Quad Cities ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
10/06/2015 |
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From: |
Blake Purnell Plant Licensing Branch III |
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To: |
Bryan Hanson Exelon Generation Co |
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Blake Purnell, NRR/DORL |
References |
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TAC MF4436, TAC MF4437, TAC MF4438, TAC MF4439, TAC MF4440, TAC MF4441, TAC MF4442, TAC MF4443, TAC MF4444, TAC MF4445, TAC MF4446 |
Download: ML15268A486 (11) |
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Category:Letter
MONTHYEARIR 05000254/20230042024-02-0505 February 2024 Integrated Inspection Report 05000254/2023004 and 05000265/2023004 IR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 IR 05000454/20230042024-02-0202 February 2024 Integrated Inspection Report 05000454/2023004 and 05000455/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation ML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 ML24004A0052024-01-17017 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0042 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval IR 05000254/20234032023-12-22022 December 2023 Public- Quad Cities Nuclear Power Station Security Baseline Inspection Report 05000254/2023403 and 05000265/2023403 IR 05000254/20230102023-12-20020 December 2023 Comprehensive Engineering Team Inspection Report 05000254/2023010 and 05000265/2023010 ML23349A1622023-12-17017 December 2023 Issuance of Amendment Nos. 298 and 294 Increase Completion Time in Technical Specification 3.8.1.B.4 (Emergency Circumstances) RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23320A1762023-12-13013 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0027 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23339A1762023-12-0505 December 2023 Notification of NRC Baseline Inspection and Request for Information (05000265/2024001) ML23318A5102023-12-0101 December 2023 Relief from the Requirements of the ASME Code ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report IR 05000454/20233012023-11-27027 November 2023 NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301 ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference ML23319A3342023-11-20020 November 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2 and 10 CFR 50.69 RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23321A0442023-11-17017 November 2023 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case BYRON 2023-0065, Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline2023-11-17017 November 2023 Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) IR 05000454/20230032023-11-13013 November 2023 Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information IR 05000254/20230032023-11-0909 November 2023 Integrated Inspection Report 05000254/2023003 and 05000265/2023003 ML23313A0852023-11-0909 November 2023 Submittal of 2023-301 Byron Initial License Examination Post-Examination Comments RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23278A0272023-10-0505 October 2023 Operator Licensing Examination Approval - Byron Station, October 2023 RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 2024-02-05
[Table view] Category:Technical Specifications
MONTHYEARML23349A1622023-12-17017 December 2023 Issuance of Amendment Nos. 298 and 294 Increase Completion Time in Technical Specification 3.8.1.B.4 (Emergency Circumstances) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs ML23122A3022023-07-20020 July 2023 Issuance of Amendments Technical Specifications 2.1.1 and 4.2.1 to Allow a Previously Irradiated Accident Tolerant Fuel Lead Test Assembly to Be Further Irradiated in Unit No. 2 ML23087A0762023-07-13013 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 ML22217A0442022-12-0707 December 2022 Issuance of Amendment Nos. 292 and 288 Control Rod Scram Times 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 RS-22-006, Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel2022-01-20020 January 2022 Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel 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 ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 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 ML20246G8652020-09-21021 September 2020 Issuance of Amendment Nos. 222 and 222 One-Time Extension of Unit No. 2 Steam Generator Inspections (COVID-19) 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 RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems ML20086M2882020-04-0202 April 2020 Correction of Amendments Nos. for Amendments Revising Instrument Testing and Calibration Definitions RS-20-046, Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.32020-04-0101 April 2020 Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.3 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 RS-18-102, License Amendment Request for a One-Time Extension to Technical Specification 3.8.1, AC Sources-Operating, Required Action A.22018-08-10010 August 2018 License Amendment Request for a One-Time Extension to Technical Specification 3.8.1, AC Sources-Operating, Required Action A.2 RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement ML18067A1812018-06-0404 June 2018 Correction to Technical Specification Amendment Identification Format ML17311A1622017-12-0101 December 2017 Issuance of Amendments Regarding Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML17298A4422017-10-19019 October 2017 Technical Requirements Manual RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Technical Requirements Manual2017-10-19019 October 2017 Quad Cities Nuclear Power Station, Units 1 & 2, Technical Requirements Manual 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 ML16111A1042016-05-11011 May 2016 Issuance of Amendments to Revise the Reactor Steam Dome Pressure in Technical Specification 2.1.1, Reactor Core SLs (CAC Nos. MF6640-MF6644) 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 RS-16-035, County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings2016-02-0303 February 2016 County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings 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) ML15324A4392015-12-17017 December 2015 Issuance of Amendments (CAC Nos. MF5471-MF5476) 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) ML15183A3512015-08-0505 August 2015 Issuance of Amendments Concerning Adding Topical References to Technical Specifications (TAC Nos. MF3359, MF3363, MF3361, and MF3362)(RS-13-288) ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML15106A9472015-04-24024 April 2015 Correction to Amendments Regarding Battery Surveillance Requirements (TAC Nos. MF4589 and MF4590) ML14323A5222015-04-0808 April 2015 Issuance of Amendments Regarding the Emergency Plan Definition of Annual Training 2023-08-30
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 6, 2015 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 -
CORRECTION OF AMENDMENTS ADOPTING TECHNICAL SPECIFICATION TASK FORCE TRAVELER TSTF-523 (TAC NOS. MF4436-MF4446)
Dear Mr. Hanson:
The U.S. Nuclear Regulatory Commission (NRC) issued the following amendments on June 19, 2015 (Agencywide Documents Access and Management System Accession No. ML15114A188):
- 1. Amendment No. 183 to Facility Operating License No. NPF-72 and Amendment No. 183 to Facility Operating License No. NPF 77 for the Braidwood Station, Units 1 and 2, respectively;
- 2. Amendment No. 189 to Facility Operating License No. NPF-37 and Amendment No. 189 to Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively; and
- 3. Amendment No. 257 to Renewed Facility Operating License No. DPR 29 and Amendment No. 252 to Renewed Facility Operating License No. DPR-30 for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively.
The amendments revised the technical specifications (TSs) to adopt Technical Specification Task Force (TSTF) Traveler TSTF-523, Revision 2, "Generic Letter 2008-01, Managing Gas Accumulation," dated February 21, 2013. The revised TS pages were provided when the amendments were issued, except as follows:
- 1. TS page 3.4. 7-3 for Braidwood Station, Units 1 and 2,
- 2. TS pages 3.4.7-3, 3.6.6-3, and 3.9.6-2 for Byron Station, Unit Nos. 1 and 2, and
- 3. TS page 3.4.8-2 for Quad Cities Nuclear Power Station, Units 1 and 2.
The NRC staff has determined that these pages were erroneously omitted and should have been issued with the amendments. The omitted TS pages are enclosed.
B. Hanson If you have any questions, please contact me at 301-415-1380.
Blake Purnell, Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454,STN 50-455, 50-254, and 50-265
Enclosure:
- 1. Braidwood Station, Units 1 and 2, Replacement TS Pages
- 2. Byron Station, Unit Nos. 1 and 2, Replacement TS Pages
- 3. Quad Cities Nuclear Power Station, Units 1 and 2, Replacement TS Pages cc w/encls: Listserv
BRAIDWOOD STATION, UNITS 1 AND 2 REPLACEMENT TECHNICAL SPEFICATION PAGES LICENSE AMENDMENT NOS. 183 AND 183 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the technical specifications with the attached revised pages.
The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove TS Page Insert TS Page 3.4.7-3 3.4.7-3 Enclosure 1
RCS Loops-MODE 5, Loops Filled 3.4. 7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Two required RHR loops D.1 Suspend all Immediately inoperable. operations involving a reduction of RCS OR boron concentration.
Required RHR loop AND inoperable and one or both required SG D.2.1 Initiate action to Immediately secondary side water restore one RHR loop level Cs) not within to OPERABLE status.
limits.
OR D.2.2 Initiate action to Immediately restore required SG secondary side water level Cs) to within limits.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify required RHR loop is in operation. In accordance with the Surveillance Frequency Control Program SR 3.4. 7.2 Verify SG secondary side narrow range water In accordance level is ~ 18% in required SGs. with the Surveillance Frequency Control Program SR 3.4.7.3 Verify correct breaker alignment and In accordance indicated power are available to each with the required RHR pump that is not in operation. Surveillance Frequency Control Program (continued)
BRAIDWOOD - UNITS 1 & 2 3.4.7 - 3 Amendment No. 183
BYRON STATION, UNIT NOS. 1 AND 2 REPLACEMENT TECHNICAL SPEFICATION PAGES LICENSE AMENDMENT NOS. 189 AND 189 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454 AND STN 50-455 Replace the following pages of the technical specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove TS Page Insert TS Page 3.4.7-3 3.4.7-3 3.6.6-3 3.6.6-3 3.9.6-2 3.9.6-2 Enclosure 2
RCS Loops-MODE 5, Loops Filled 3.4. 7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Two required RHR loops D.1 Suspend all Immediately inoperable. operations involving a reduction of RCS OR boron concentration.
Required RHR loop AND inoperable and one or both required SG D.2.1 Initiate action to Immediately secondary side water restore one RHR loop level Cs) not within to OPERABLE status.
limits.
OR D.2.2 Initiate action to Immediately restore required SG secondary side water level(s) to within limits.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify required RHR loop is in operation. In accordance with the Surveillance Frequency Control Program SR 3.4.7.2 Verify SG secondary side narrow range water In accordance level is~ 18% in required SGs. with the Surveillance Frequency Control Program SR 3.4. 7 .3 Verify correct breaker alignment and In accordance indicated power are available to each with the required RHR pump that is not in operation. Surveillance Frequency Control Program (continued)
BYRON - UNITS 1 &2 3.4.7-3 Amendment No. 189
Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.6.3 Verify each containment cooling train In accordance cooling water flow rate is~ 2660 gpm to with the each cooler. Surveillance Frequency Control Program SR 3.6.6.4 Verify each containment spray pump's In accordance developed head at the flow test point is with the greater than or equal to the required Inservice developed head. Testing Program SR 3.6.6.5 Verify each automatic containment spray In accordance valve in the flow path that is not locked, with the sealed, or otherwise secured in position, Surveillance actuates to the correct position on an Frequency actual or simulated actuation signal. Control Program SR 3.6.6.6 Verify each containment spray pump starts In accordance automatically on an actual or simulated with the actuation signal. Surveillance Frequency Control Program SR 3.6.6.7 Verify each containment cooling train In accordance starts automatically on an actual or with the simulated actuation signal. Surveillance Frequency Control Program SR 3.6.6.8 Verify each spray nozzle is unobstructed. Foll owing maintenance that could result in nozzle blockage OR Following fluid fl ow through the nozzles (cont rnued) I BYRON - UNITS 1 &2 3.6.6 - 3 Amendment No. 189
RHR and Coolant Circulation-Low Water Level 3.9.6 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR loop in B.1 Suspend operations Immediately operation. involving a reduction in reactor coolant boron concentration.
AND B.2 Initiate action to Immediately restore one RHR loop to operation.
AND B.3 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> penetrations providing direct access from containment atmosphere to outside atmosphere.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify one RHR loop is in operation and In accordance circulating reactor coolant at a flow rate with the of ~ 1000 gpm. Surveillance Frequency Control Program SR 3.9.6.2 Verify correct breaker alignment and In accordance indicated power available to the required with the RHR pump that is not in operation. Surveillance Frequency Control Program (continued)
BYRON - UNITS 1 &2 3.9.6 - 2 Amendment No. 189
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 REPLACEMENT TECHNICAL SPEFICATION PAGES LICENSE AMENDMENT NOS. 257 AND 252 RENEWED FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 DOCKET NOS. 50-254 AND 50-265 Replace the following pages of the technical specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove TS Page Insert TS Page 3.4.8-2 3.4.8-2 Enclosure 3
RHR Shutdown Cooling System-Cold Shutdown 3.4.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 ---------NOTE--------
Onl y appl i cable i f both RHR shutdown cooling subsystems are inoperable.
Verify reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> coolant circulating by an alternate method.
Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter A.3 ---------NOTE--------
Only applicable if both RHR shutdown cooling subsystems are inoperable.
Monitor reactor Once per hour coolant temperature and pressure.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify each RHR shutdown cooling subsystem In accordance manual and power operated valve in the flow with the path, that is not locked, sealed or Surveillance otherwise secured in position, is in the Frequency correct position or can be aligned to the Control Program correct position.
(continued) I Quad Cities 1 and 2 3.4.8-2 Amendment No. 257/252
B. Hanson If you have any questions, please contact me at 301-415-1380.
Sincerely, IRA!
Blake Purnell, Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454,STN 50-455, 50-254, and 50-265
Enclosure:
- 1. Braidwood Station, Units 1 and 2, Replacement TS Pages
- 2. Byron Station, Unit Nos. 1 and 2, Replacement TS Pages
- 3. Quad Cities Nuclear Power Station, Units 1 and 2, Replacement TS Pages cc w/encls: Listserv DISTRIBUTION:
PUBLIC LPL3-2 R/F RidsNrrDorllp13-2 Resource RidsNrrPMBraidwood Resource RidsNrrLASRohrer Resource RidsNrrPMByron Resource RidsNrrDorlDpr Resource RidsNrrPMQuadCities Resource RidsNrrPMExelon Resource RidsRgn3MailCenter Resource RidsAcrsAcnw_MailCTR Resource RecordsAmend Resource Accession No. ML15268A486 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC LPL3-2/PM NAME BPurnell SRohrer TTate BPurnell DATE 10/5/15 9/28/15 10/5/15 10/6/15 OFFICIAL RECORD COPY