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| {{#Wiki_filter:February 05, 2009 BW090008 U.S.Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos.NPF-72 and NPF-n NRC Docket Nos.STN 50-456 and STN 50-457 | | {{#Wiki_filter:February 05, 2009 BW090008 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF- n NRC Docket Nos. STN 50-456 and STN 50-457 |
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| ==Subject:== | | ==Subject:== |
| Regulatory Commitment Change Summary Report Enclosed is the Exelon Generation Company, LLC (EGG)"Regulatory Commitment Change Summary Report" for Braidwood Station.This report includes a summary of the changes processed during the period from January 1, 2008 through December 31, 2008.In addition, this report includes a description of changes processed during the period from January1, 2001 through January 31, 2001 since it was discovered that these changes were previously not reported.Revisions to regulatory commitments made in docketed correspondence were processed using the Nuclear Energy Institute's (NEI)99-04, Revision 0,"Guidelines for Managing NRC Commitment Changes," dated July 1999 and applicable procedures. | | Regulatory Commitment Change Summary Report Enclosed is the Exelon Generation Company, LLC (EGG) "Regulatory Commitment Change Summary Report" for Braidwood Station. This report includes a summary of the changes processed during the period from January 1, 2008 through December 31, 2008. In addition, this report includes a description of changes processed during the period from January 1, 2001 through January 31, 2001 since it was discovered that these changes were previously not reported. |
| Should you have any questions concerning this report, please contact Mr.David Gullott, Regulatory Assurance Manager, at (815)417-2800.Respectfully, Bryan Hanson Site Vice President Braidwood Station | | Revisions to regulatory commitments made in docketed correspondence were processed using the Nuclear Energy Institute's (NEI) 99-04, Revision 0, "Guidelines for Managing NRC Commitment Changes," dated July 1999 and applicable procedures. |
| | Should you have any questions concerning this report, please contact Mr. David Gullott, Regulatory Assurance Manager, at (815) 417-2800. |
| | Respectfully, Bryan Hanson Site Vice President Braidwood Station |
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| ==Attachment:== | | ==Attachment:== |
| | Regulatory Commitment Change Summary Report |
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| Regulatory Commitment Change Summary Report Attachment Braidwood Station Regulatory Commitment Change Summary Report Commitment Change Tracking Number: 2001*01 Originating Document: Letter from H.E.Bliss to U.S.NRC,"Response to Inspection Reports Nos.50-456/88011 and 50-457/88013," dated May 12, 1988.SUbject of Change: Delete the requirement for a guidance document on the Control Power System that identifies equipment powered from each point in the 120-Volt Distribution System based on the adequacy of controls in the current Out of Service (OOS)process and availability of electrical drawing information in the Electronic Work Control System (EWCS).Original Commitment:
| | Attachment Braidwood Station Regulatory Commitment Change Summary Report Commitment Change Tracking Number: 2001*01 Originating Document: |
| The original regulatory commitment was made in response to a Notice of Violation for failure to take proper action when two Non-accessible Exhaust Filter Plenums were inoperable.
| | Letter from H.E. Bliss to U.S. NRC, "Response to Inspection Reports Nos. 50-456/88011 and 50-457/88013," dated May 12, 1988. |
| The cause of the event was determined to be an administrative and management deficiency in that the personnel assigned the task of determining and verifying the isolation points for the control power to the Auxiliary Building Ventilation System lacked the expertise and adequate reference material required to perform the function.In response to the Notice of Violation, Commonwealth Edison (currently Exelon Generation Company, LLC (EGC>>committed to develop a guidance document on the Control Power System that would identify equipment powered from each point in the 120-Volt Distribution System (Le., identification of what equipment will be de-energized if a specific breaker/relay/fuse is removed from service).Revised Commitment:
| | SUbject of Change: |
| Adequate controls have been built into the OOS process to ensure OOS scopes are accurate and well defined.Current electrical print information is updated, maintained and available through EWCS controlled documents.
| | Delete the requirement for a guidance document on the Control Power System that identifies equipment powered from each point in the 120-Volt Distribution System based on the adequacy of controls in the current Out of Service (OOS) process and availability of electrical drawing information in the Electronic Work Control System (EWCS). |
| As a result, no additional procedural guidance is required to be maintained.
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| Basis: The OOS Program provides specific directions for OOS preparation and approval for Technical Specification (TS)and safety related activities.
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| The required preparation and independent review by licensed operators for TS and safety related equipment OOS ensure the OOS does not impact the operability of other required equipment.
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| The specific duties of the OOS preparer, approver and authorizers ensure an adequate condition prior to hanging a new OOS.The OOS process requires the OOS to include current/approved drawings and information relative to the isolation points.The OOS procedure contains impact review checklists for preparation, approval and authorization priortohanging an OOS.These actions require verification of Limiting Condition for Operation (LCO)and administrative requirements to ensure applicable LCO requirements are entered as a result of circuit manipulation.
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| Page 1 of 4 Attachment Braidwood Station Regulatory Commitment Change Summary Report Commitment Change Tracking Number: 2001-02 Originating Document: Letter from T.R.Tramm to U.S.NRC,"Post Accident Sampling System," dated January 5, 1984.SUbject of Change: Revise the frequency for training all radiation-chemistry technicians on the Post Accident Sampling System (PASS)from at least every six months to annually with the content determined by the Chemistry Curriculum Review Committee.
| |
| Original Commitment: | | Original Commitment: |
| The regulatory commitment documented in the above referenced correspondence requires special retraining on PASS to be completed by all radiation-chemistry technicians at least every six months.Revised Commitment: | | The original regulatory commitment was made in response to a Notice of Violation for failure to take proper action when two Non-accessible Exhaust Filter Plenums were inoperable. The cause of the event was determined to be an administrative and management deficiency in that the personnel assigned the task of determining and verifying the isolation points for the control power to the Auxiliary Building Ventilation System lacked the expertise and adequate reference material required to perform the function. In response to the Notice of Violation, Commonwealth Edison (currently Exelon Generation Company, LLC (EGC>> committed to develop a guidance document on the Control Power System that would identify equipment powered from each point in the 120-Volt Distribution System (Le., identification of what equipment will be de-energized if a specific breaker/relay/fuse is removed from service). |
| The commitment change completed in 2001 revised the original regulatory commitment to conducting annual PASS training with the content determined bytheChemistry Curriculum Review Committee. | | Revised Commitment: |
| At that time, conducting annual training would have been consistent with Updated Final Safety Analysis Report (UFSAR)Section E.21.1.2.1.2. | | Adequate controls have been built into the OOS process to ensure OOS scopes are accurate and well defined. Current electrical print information is updated, maintained and available through EWCS controlled documents. As a result, no additional procedural guidance is required to be maintained. |
| Subsequent to the commitment change completed in 2001, the licensing basis for the PASS was revised.The PASS requirements were removed from Technical Specifications in accordance with Braidwood Technical Specification Amendment No.137 issued on May 26,2005.The PASS licensing basis described in the UFSAR was revised accordingly and the requirement to perform PASS training deleted.Basis: The change in frequency of conducting PASS training from at least every six months to annually was based on the following: | | Basis: |
| 1)the technicians are familiar with the sample system because it is used for routine sampling, 2)the frequency of panel use is twice as often because the number of technicians was reduced, and 3)the sample system is not safety related nor is it required for mitigating plant conditions. | | The OOS Program provides specific directions for OOS preparation and approval for Technical Specification (TS) and safety related activities. The required preparation and independent review by licensed operators for TS and safety related equipment OOS ensure the OOS does not impact the operability of other required equipment. The specific duties of the OOS preparer, approver and authorizers ensure an adequate condition prior to hanging a new OOS. The OOS process requires the OOS to include current/approved drawings and information relative to the isolation points. The OOS procedure contains impact review checklists for preparation, approval and authorization prior to hanging an OOS. These actions require verification of Limiting Condition for Operation (LCO) and administrative requirements to ensure applicable LCO requirements are entered as a result of circuit manipulation. |
| Subsequently, the requirements for PASS were deleted and training is no longer required.Page 2 of 4 Attachment Braidwood Station Regulatory Commitment Change Summary Report Commitment Change Tracking Number: 2001-03 Originating Document: Letter from G.L.Alexander to U.S.NRC,"Supplemental Response to Generic Letter No.83-28,"Required Actions Based on Generic Implications ofSalemA TWS Events,"" dated August 21, 1985.SUbject of Change: Delete the original commitment to perform a trend analysis following each refueling outage after reactor trip breaker maintenance to determine whether the frequency may be increased, reduced, or remain the same for the reactor trip breakers.Original Commitment: | | Page 1 of 4 |
| For each refueling outage after reactor trip breaker maintenance, prior to unit start-up, the Braidwood Technical Staff will perform a trend analysis on the 4 parameters from item 4.2.2 (Le., undervoltage trip attachment dropout voltage, trip force, breaker response time for undervoltage trip, and breaker insulation resistance). | | |
| Based on the results of the parameter review and trend analysis, the maintenance frequency may be increased, reduced, or remain the same for the reactor trip breakers.Revised Commitment: | | Attachment Braidwood Station Regulatory Commitment Change Summary Report Commitment Change Tracking Number: 2001-02 Originating Document: |
| The original commitment is deleted based on implementation of the Maintenance Rule.Basis: This commitment was made before the Maintenance Rule was enacted, Le., 10 CFR 50.65,"Requirements for monitoring the effectiveness of maintenance at nuclear power plants." With the rule in effect, the commitment above becomes a redundant action and does not allow for flexibility in trending.The intent of the original commitment is met through the Maintenance Rule.Page 3 of 4 Attachment Braidwood Station Regulatory Commitment Change Summary Report Commitment Change Tracking Number: 2008-01 Originating Document: Letter from T.J.Tulon to U.S.NRC,"Regulatory Commitment Change Summary Report," dated February 4, 2000.Subject of Change: Delete the revised commitment to include overtime controls and guidelines to meet the requirements of Generic Letter 82-12,"Nuclear Power Plant Staff Working Hours," in procedureAA-119.Original Commitment: | | Letter from T.R. Tramm to U.S. NRC, "Post Accident Sampling System," dated January 5, 1984. |
| The original commitment was contained in a letter from K.L.Kaup to U.S.NRC, dated October 4, 1994 and was associated with an allegation regarding excessive overtime.The original commitment stated that SwAP 100-7,"Overtime Guidelines for Station Personnel," would be revised to properly reflect the requirement of the current revision of NOD OA.13.The original commitment was subsequently revised in the referenced Regulatory Commitment Change Summary Report to state that the requirements previously stated in NOD OA.13, originally documented in SwAP 100-7, are now incorporated in RS-AA-119,"Overtime Controls." Revised Commitment: | | SUbject of Change: |
| The revised commitment is deleted.Basis: The revised commitment is deleted based on the current procedure, LS-AA-119,"Overtime Controls," providing the appropriate current regulatory guidance (Le., Generic Letters 82-12 and14).The guidance for overtime controls will be revised as necessary upon implementation of the new rule regarding work hour limitations (Le., 10 CFR 26,"Fitness for Duty," Subpart I,"Managing Fatigue"). | | Revise the frequency for training all radiation-chemistry technicians on the Post Accident Sampling System (PASS) from at least every six months to annually with the content determined by the Chemistry Curriculum Review Committee. |
| | Original Commitment: |
| | The regulatory commitment documented in the above referenced correspondence requires special retraining on PASS to be completed by all radiation-chemistry technicians at least every six months. |
| | Revised Commitment: |
| | The commitment change completed in 2001 revised the original regulatory commitment to conducting annual PASS training with the content determined by the Chemistry Curriculum Review Committee. At that time, conducting annual training would have been consistent with Updated Final Safety Analysis Report (UFSAR) Section E.21.1.2.1.2. Subsequent to the commitment change completed in 2001, the licensing basis for the PASS was revised. The PASS requirements were removed from Technical Specifications in accordance with Braidwood Technical Specification Amendment No. 137 issued on May 26,2005. The PASS licensing basis described in the UFSAR was revised accordingly and the requirement to perform PASS training deleted. |
| | Basis: |
| | The change in frequency of conducting PASS training from at least every six months to annually was based on the following: 1) the technicians are familiar with the sample system because it is used for routine sampling, 2) the frequency of panel use is twice as often because the number of technicians was reduced, and 3) the sample system is not safety related nor is it required for mitigating plant conditions. |
| | Subsequently, the requirements for PASS were deleted and training is no longer required. |
| | Page 2 of 4 |
| | |
| | Attachment Braidwood Station Regulatory Commitment Change Summary Report Commitment Change Tracking Number: 2001-03 Originating Document: |
| | Letter from G.L. Alexander to U.S. NRC, "Supplemental Response to Generic Letter No. 83-28, "Required Actions Based on Generic Implications of Salem ATWS Events,"" dated August 21, 1985. |
| | SUbject of Change: |
| | Delete the original commitment to perform a trend analysis following each refueling outage after reactor trip breaker maintenance to determine whether the frequency may be increased, reduced, or remain the same for the reactor trip breakers. |
| | Original Commitment: |
| | For each refueling outage after reactor trip breaker maintenance, prior to unit start-up, the Braidwood Technical Staff will perform a trend analysis on the 4 parameters from item 4.2.2 (Le., |
| | undervoltage trip attachment dropout voltage, trip force, breaker response time for undervoltage trip, and breaker insulation resistance). Based on the results of the parameter review and trend analysis, the maintenance frequency may be increased, reduced, or remain the same for the reactor trip breakers. |
| | Revised Commitment: |
| | The original commitment is deleted based on implementation of the Maintenance Rule. |
| | Basis: |
| | This commitment was made before the Maintenance Rule was enacted, Le., 10 CFR 50.65, "Requirements for monitoring the effectiveness of maintenance at nuclear power plants." With the rule in effect, the commitment above becomes a redundant action and does not allow for flexibility in trending. The intent of the original commitment is met through the Maintenance Rule. |
| | Page 3 of 4 |
| | |
| | Attachment Braidwood Station Regulatory Commitment Change Summary Report Commitment Change Tracking Number: 2008-01 Originating Document: |
| | Letter from T.J. Tulon to U.S. NRC, "Regulatory Commitment Change Summary Report," dated February 4, 2000. |
| | Subject of Change: |
| | Delete the revised commitment to include overtime controls and guidelines to meet the requirements of Generic Letter 82-12, "Nuclear Power Plant Staff Working Hours," in procedure RS-AA-119. |
| | Original Commitment: |
| | The original commitment was contained in a letter from K.L. Kaup to U.S. NRC, dated October 4, 1994 and was associated with an allegation regarding excessive overtime. The original commitment stated that SwAP 100-7, "Overtime Guidelines for Station Personnel," would be revised to properly reflect the requirement of the current revision of NOD OA.13. The original commitment was subsequently revised in the referenced Regulatory Commitment Change Summary Report to state that the requirements previously stated in NOD OA.13, originally documented in SwAP 100-7, are now incorporated in RS-AA-119, "Overtime Controls." |
| | Revised Commitment: |
| | The revised commitment is deleted. |
| | Basis: |
| | The revised commitment is deleted based on the current procedure, LS-AA-119, "Overtime Controls," providing the appropriate current regulatory guidance (Le., Generic Letters 82-12 and 83-14). The guidance for overtime controls will be revised as necessary upon implementation of the new rule regarding work hour limitations (Le., 10 CFR 26, "Fitness for Duty," Subpart I, "Managing Fatigue"). |
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Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 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 ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 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 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)) IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 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 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference 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 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 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 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums 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 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-23-097, 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 RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 ML23234A2462023-08-25025 August 2023 Confirmation of Initial License Examination IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23110A1152023-06-12012 June 2023 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter) RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23132A0472023-05-12012 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ML23130A0072023-05-10010 May 2023 Submittal of Core Operating Limits Report Cycle 24, Rev. 16 IR 05000456/20230012023-05-0808 May 2023 Integrated Inspection Report 05000456/2023001 and 05000457/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23118A0202023-04-28028 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML23095A1292023-04-0505 April 2023 Steam Generator Tube Inspection Report for Refueling Outage 23 ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 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 RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations 2024-02-02
[Table view] Category:Report
MONTHYEARBW230054, Attachment 2: MDMP Deviation Form2023-11-17017 November 2023 Attachment 2: MDMP Deviation Form ML23321A0452023-11-17017 November 2023 EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 BW220062, Pressure and Temperature Limits Report (Ptlr), Revision 92022-10-20020 October 2022 Pressure and Temperature Limits Report (Ptlr), Revision 9 NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-22-071, License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds2022-06-0707 June 2022 License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML21349A1062021-12-15015 December 2021 Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273 BW210065, Pressure and Temperature Limits Report, Revision 82021-10-27027 October 2021 Pressure and Temperature Limits Report, Revision 8 RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-22022 October 2021 Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021 R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections BW210047, ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval2021-06-30030 June 2021 ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval RS-21-056, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld2021-05-12012 May 2021 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping 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 ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20195B1622020-06-30030 June 2020 Attachment 11 - SG-SGMP-17-25-NP, Revision 1, Foreign Object Limits Analysis for the Byron and Braidwood Unit 2 Steam Generators June 2020 ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 ML18348A9792018-12-14014 December 2018 Transmittal of 10 CFR 50.59 Summary Report ML18348A9722018-12-12012 December 2018 Submittal of Analytical Evaluation in Accordance with ASME Code Section XI RS-17-048, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2017-04-0707 April 2017 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 RS-16-223, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-12-0707 December 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-16-174, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review...2016-11-0303 November 2016 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review... ML17170A1472016-10-0707 October 2016 Areva, 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML16356A0202016-10-0707 October 2016 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17360A1742016-10-0707 October 2016 Attachment 6: Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations (Non-Proprietary) RS-17-039, Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.2016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17095A2692016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML16236A2082016-08-23023 August 2016 Report of Backfit Appeal Review Panel ML16214A1992016-08-11011 August 2016 an Assessment of Core Damage Frequency for Byron/Braidwood Backit Appeal Review RS-16-099, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal ML16250A5182016-04-30030 April 2016 Technical Evaluation Report Related to the Exelon Generation Company, LLC, License Amendment Request to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink. Docket Nos. Stn 50-456 & 457 RS-16-073, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2016-04-0707 April 2016 Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-16-057, Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds2016-03-15015 March 2016 Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds ML16014A1882016-01-22022 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review of Insights ML15344A1592015-12-10010 December 2015 Submittal of Pressure and Temperature Limits Reports (Ptlrs), Revision 8 and Braidwood, Unit 2 - Pressure and Temperature Limits Reports (Ptlrs), Revision 7 ML15322A3172015-11-18018 November 2015 Record of Decision ML15237A3822015-10-15015 October 2015 Pressure and Temperature Limits Report for Measurement Uncertainty Recapture Power Uprate RS-15-259, Final Report: Five Year Post-Construction Monitoring of the Unionid Community Near the Braidwood Station Kankakee River Discharge.2015-09-30030 September 2015 Final Report: Five Year Post-Construction Monitoring of the Unionid Community Near the Braidwood Station Kankakee River Discharge. RS-15-129, Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 20152015-04-30030 April 2015 Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 2015 ML14349A6572014-12-15015 December 2014 CFR 50.59 Changes, Tests, and Experiments, Paragraph (d)(2), Summary Report RS-14-348, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application2014-12-15015 December 2014 Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14141A1332014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML14178B2222014-06-24024 June 2014 Technical Review of TIA 2013-02, Single Spurious Assumptions for Braidwood and Byron Stations Safe-Shutdown Methodology ML14101A4452014-06-0404 June 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tac No. MF0095) ML14101A3522014-06-0404 June 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14127A1742014-05-0707 May 2014 Startup Report for the Measurement Uncertainty Recapture Power Uprate ML14120A0392014-04-24024 April 2014 Units 1 & 2 - License Amendment Request to Install New Low Degraded Voltage Relays & Timers on the 4.16 Kv Engineered Safety Features (ESF) Buses 2023-04-20
[Table view] Category:Miscellaneous
MONTHYEARBW230054, Attachment 2: MDMP Deviation Form2023-11-17017 November 2023 Attachment 2: MDMP Deviation Form ML23321A0452023-11-17017 November 2023 EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood RS-22-071, License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds2022-06-0707 June 2022 License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML21349A1062021-12-15015 December 2021 Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273 RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-22022 October 2021 Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting RS-17-048, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2017-04-0707 April 2017 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 RS-16-174, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review...2016-11-0303 November 2016 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review... RS-17-039, Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.2016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17170A1472016-10-0707 October 2016 Areva, 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17095A2692016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML16236A2082016-08-23023 August 2016 Report of Backfit Appeal Review Panel ML16214A1992016-08-11011 August 2016 an Assessment of Core Damage Frequency for Byron/Braidwood Backit Appeal Review RS-16-099, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal RS-16-073, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2016-04-0707 April 2016 Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML16014A1882016-01-22022 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review of Insights ML15344A1592015-12-10010 December 2015 Submittal of Pressure and Temperature Limits Reports (Ptlrs), Revision 8 and Braidwood, Unit 2 - Pressure and Temperature Limits Reports (Ptlrs), Revision 7 ML15322A3172015-11-18018 November 2015 Record of Decision ML15237A3822015-10-15015 October 2015 Pressure and Temperature Limits Report for Measurement Uncertainty Recapture Power Uprate RS-15-129, Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 20152015-04-30030 April 2015 Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 2015 ML14349A6572014-12-15015 December 2014 CFR 50.59 Changes, Tests, and Experiments, Paragraph (d)(2), Summary Report RS-14-348, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application2014-12-15015 December 2014 Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application ML14141A1332014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML14101A4452014-06-0404 June 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tac No. MF0095) ML14101A3522014-06-0404 June 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14127A1742014-05-0707 May 2014 Startup Report for the Measurement Uncertainty Recapture Power Uprate ML14120A0392014-04-24024 April 2014 Units 1 & 2 - License Amendment Request to Install New Low Degraded Voltage Relays & Timers on the 4.16 Kv Engineered Safety Features (ESF) Buses ML14066A4792014-03-0404 March 2014 Clarification of Licensing Basis Assumptions for a Natural Circulation Cooldown Event ML14059A1242014-02-28028 February 2014 Pressure and Temperature Limits Reports (Ptlrs) IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML12349A3632012-12-14014 December 2012 10 CFR 50.59 Summary Report for June 19, 2010 Through June 18, 2012 ML12339A2172012-11-16016 November 2012 12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 1 of 5 ML12339A2182012-11-16016 November 2012 12Q0108.10-R-002, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 2. Part 5 of 5 ML12339A2192012-11-16016 November 2012 12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 2 of 5 ML12339A2202012-11-16016 November 2012 12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 3 of 5 ML12339A2212012-11-16016 November 2012 12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 4 of 5 ML12339A2222012-11-16016 November 2012 12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 5 of 5 2023-11-17
[Table view] |
Text
February 05, 2009 BW090008 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF- n NRC Docket Nos. STN 50-456 and STN 50-457
Subject:
Regulatory Commitment Change Summary Report Enclosed is the Exelon Generation Company, LLC (EGG) "Regulatory Commitment Change Summary Report" for Braidwood Station. This report includes a summary of the changes processed during the period from January 1, 2008 through December 31, 2008. In addition, this report includes a description of changes processed during the period from January 1, 2001 through January 31, 2001 since it was discovered that these changes were previously not reported.
Revisions to regulatory commitments made in docketed correspondence were processed using the Nuclear Energy Institute's (NEI) 99-04, Revision 0, "Guidelines for Managing NRC Commitment Changes," dated July 1999 and applicable procedures.
Should you have any questions concerning this report, please contact Mr. David Gullott, Regulatory Assurance Manager, at (815) 417-2800.
Respectfully, Bryan Hanson Site Vice President Braidwood Station
Attachment:
Regulatory Commitment Change Summary Report
Attachment Braidwood Station Regulatory Commitment Change Summary Report Commitment Change Tracking Number: 2001*01 Originating Document:
Letter from H.E. Bliss to U.S. NRC, "Response to Inspection Reports Nos. 50-456/88011 and 50-457/88013," dated May 12, 1988.
SUbject of Change:
Delete the requirement for a guidance document on the Control Power System that identifies equipment powered from each point in the 120-Volt Distribution System based on the adequacy of controls in the current Out of Service (OOS) process and availability of electrical drawing information in the Electronic Work Control System (EWCS).
Original Commitment:
The original regulatory commitment was made in response to a Notice of Violation for failure to take proper action when two Non-accessible Exhaust Filter Plenums were inoperable. The cause of the event was determined to be an administrative and management deficiency in that the personnel assigned the task of determining and verifying the isolation points for the control power to the Auxiliary Building Ventilation System lacked the expertise and adequate reference material required to perform the function. In response to the Notice of Violation, Commonwealth Edison (currently Exelon Generation Company, LLC (EGC>> committed to develop a guidance document on the Control Power System that would identify equipment powered from each point in the 120-Volt Distribution System (Le., identification of what equipment will be de-energized if a specific breaker/relay/fuse is removed from service).
Revised Commitment:
Adequate controls have been built into the OOS process to ensure OOS scopes are accurate and well defined. Current electrical print information is updated, maintained and available through EWCS controlled documents. As a result, no additional procedural guidance is required to be maintained.
Basis:
The OOS Program provides specific directions for OOS preparation and approval for Technical Specification (TS) and safety related activities. The required preparation and independent review by licensed operators for TS and safety related equipment OOS ensure the OOS does not impact the operability of other required equipment. The specific duties of the OOS preparer, approver and authorizers ensure an adequate condition prior to hanging a new OOS. The OOS process requires the OOS to include current/approved drawings and information relative to the isolation points. The OOS procedure contains impact review checklists for preparation, approval and authorization prior to hanging an OOS. These actions require verification of Limiting Condition for Operation (LCO) and administrative requirements to ensure applicable LCO requirements are entered as a result of circuit manipulation.
Page 1 of 4
Attachment Braidwood Station Regulatory Commitment Change Summary Report Commitment Change Tracking Number: 2001-02 Originating Document:
Letter from T.R. Tramm to U.S. NRC, "Post Accident Sampling System," dated January 5, 1984.
SUbject of Change:
Revise the frequency for training all radiation-chemistry technicians on the Post Accident Sampling System (PASS) from at least every six months to annually with the content determined by the Chemistry Curriculum Review Committee.
Original Commitment:
The regulatory commitment documented in the above referenced correspondence requires special retraining on PASS to be completed by all radiation-chemistry technicians at least every six months.
Revised Commitment:
The commitment change completed in 2001 revised the original regulatory commitment to conducting annual PASS training with the content determined by the Chemistry Curriculum Review Committee. At that time, conducting annual training would have been consistent with Updated Final Safety Analysis Report (UFSAR) Section E.21.1.2.1.2. Subsequent to the commitment change completed in 2001, the licensing basis for the PASS was revised. The PASS requirements were removed from Technical Specifications in accordance with Braidwood Technical Specification Amendment No. 137 issued on May 26,2005. The PASS licensing basis described in the UFSAR was revised accordingly and the requirement to perform PASS training deleted.
Basis:
The change in frequency of conducting PASS training from at least every six months to annually was based on the following: 1) the technicians are familiar with the sample system because it is used for routine sampling, 2) the frequency of panel use is twice as often because the number of technicians was reduced, and 3) the sample system is not safety related nor is it required for mitigating plant conditions.
Subsequently, the requirements for PASS were deleted and training is no longer required.
Page 2 of 4
Attachment Braidwood Station Regulatory Commitment Change Summary Report Commitment Change Tracking Number: 2001-03 Originating Document:
Letter from G.L. Alexander to U.S. NRC, "Supplemental Response to Generic Letter No. 83-28, "Required Actions Based on Generic Implications of Salem ATWS Events,"" dated August 21, 1985.
SUbject of Change:
Delete the original commitment to perform a trend analysis following each refueling outage after reactor trip breaker maintenance to determine whether the frequency may be increased, reduced, or remain the same for the reactor trip breakers.
Original Commitment:
For each refueling outage after reactor trip breaker maintenance, prior to unit start-up, the Braidwood Technical Staff will perform a trend analysis on the 4 parameters from item 4.2.2 (Le.,
undervoltage trip attachment dropout voltage, trip force, breaker response time for undervoltage trip, and breaker insulation resistance). Based on the results of the parameter review and trend analysis, the maintenance frequency may be increased, reduced, or remain the same for the reactor trip breakers.
Revised Commitment:
The original commitment is deleted based on implementation of the Maintenance Rule.
Basis:
This commitment was made before the Maintenance Rule was enacted, Le., 10 CFR 50.65, "Requirements for monitoring the effectiveness of maintenance at nuclear power plants." With the rule in effect, the commitment above becomes a redundant action and does not allow for flexibility in trending. The intent of the original commitment is met through the Maintenance Rule.
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Attachment Braidwood Station Regulatory Commitment Change Summary Report Commitment Change Tracking Number: 2008-01 Originating Document:
Letter from T.J. Tulon to U.S. NRC, "Regulatory Commitment Change Summary Report," dated February 4, 2000.
Subject of Change:
Delete the revised commitment to include overtime controls and guidelines to meet the requirements of Generic Letter 82-12, "Nuclear Power Plant Staff Working Hours," in procedure RS-AA-119.
Original Commitment:
The original commitment was contained in a letter from K.L. Kaup to U.S. NRC, dated October 4, 1994 and was associated with an allegation regarding excessive overtime. The original commitment stated that SwAP 100-7, "Overtime Guidelines for Station Personnel," would be revised to properly reflect the requirement of the current revision of NOD OA.13. The original commitment was subsequently revised in the referenced Regulatory Commitment Change Summary Report to state that the requirements previously stated in NOD OA.13, originally documented in SwAP 100-7, are now incorporated in RS-AA-119, "Overtime Controls."
Revised Commitment:
The revised commitment is deleted.
Basis:
The revised commitment is deleted based on the current procedure, LS-AA-119, "Overtime Controls," providing the appropriate current regulatory guidance (Le., Generic Letters 82-12 and 83-14). The guidance for overtime controls will be revised as necessary upon implementation of the new rule regarding work hour limitations (Le., 10 CFR 26, "Fitness for Duty," Subpart I, "Managing Fatigue").
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