|
|
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:August 17, 2007Mr. Christopher M. CranePresident and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 | | {{#Wiki_filter:August 17, 2007 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| BYRON STATION, UNIT NOS. 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION REQUIREMENTS FOR SELECT REACTOR TRIP SYSTEM, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM, AND CONTAINMENT VENTILATION ISOLATION, INSTRUMENTATION (TAC NOS. | | BYRON STATION, UNIT NOS. 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION REQUIREMENTS FOR SELECT REACTOR TRIP SYSTEM, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM, AND CONTAINMENT VENTILATION ISOLATION, INSTRUMENTATION (TAC NOS. |
| MD4009, MD4010, MD4011, AND MD4012) | | MD4009, MD4010, MD4011, AND MD4012) |
|
| |
|
| ==Dear Mr. Crane:== | | ==Dear Mr. Crane:== |
|
| |
|
| By letter to the Nuclear Regulatory Commission (NRC) dated January 8, 2007, ExelonGeneration Company, LLC submitted a request to extend the completion times, bypass test times, and surveillance test intervals for reactor protection system (RPS) and engineered safety features actuation system instrumentation, for the Byron Station, Unit Nos. 1 and 2, and Braidwood Station, Units 1 and 2.The NRC staff is reviewing your submittal and has determined that additional information isrequired to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on August 9, 2007, it was agreed that you would provide a response within 30 days from the date of this letter. The NRC staff considers that timely responses to requests for additional information helpensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3733.Sincerely,/RA/Robert F. Kuntz, Project ManagerPlant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. STN 50-454, STN 50-455, STN 50-456 and STN 50-457 | | By letter to the Nuclear Regulatory Commission (NRC) dated January 8, 2007, Exelon Generation Company, LLC submitted a request to extend the completion times, bypass test times, and surveillance test intervals for reactor protection system (RPS) and engineered safety features actuation system instrumentation, for the Byron Station, Unit Nos. 1 and 2, and Braidwood Station, Units 1 and 2. |
| | The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on August 9, 2007, it was agreed that you would provide a response within 30 days from the date of this letter. |
| | The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3733. |
| | Sincerely, |
| | /RA/ |
| | Robert F. Kuntz, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456 and STN 50-457 |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Informationcc w/encl: See next page August 17, 2007Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 | | |
| | Request for Additional Information cc w/encl: See next page |
| | |
| | August 17, 2007 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| BYRON STATION, UNIT NOS. 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION REQUIREMENTS FOR SELECT REACTOR TRIP SYSTEM, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM, AND CONTAINMENT VENTILATION ISOLATION, INSTRUMENTATION (TAC NOS. | | BYRON STATION, UNIT NOS. 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION REQUIREMENTS FOR SELECT REACTOR TRIP SYSTEM, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM, AND CONTAINMENT VENTILATION ISOLATION, INSTRUMENTATION (TAC NOS. |
| MD4009, MD4010, MD4011, AND MD4012) | | MD4009, MD4010, MD4011, AND MD4012) |
|
| |
|
| ==Dear Mr. Crane:== | | ==Dear Mr. Crane:== |
|
| |
|
| By letter to the Nuclear Regulatory Commission (NRC) dated January 8, 2007, ExelonGeneration Company, LLC submitted a request to extend the completion times, bypass test times, and surveillance test intervals for reactor protection system (RPS) and engineered safety features actuation system instrumentation, for the Byron Station, Unit Nos. 1 and 2, and Braidwood Station, Units 1 and 2.The NRC staff is reviewing your submittal and has determined that additional information isrequired to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on August 9, 2007, it was agreed that you would provide a response within 30 days from the date of this letter. The NRC staff considers that timely responses to requests for additional information helpensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3733.Sincerely, Robert F. Kuntz, Project ManagerPlant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. STN 50-454, STN 50-455, STN 50-456 and STN 50-457 | | By letter to the Nuclear Regulatory Commission (NRC) dated January 8, 2007, Exelon Generation Company, LLC submitted a request to extend the completion times, bypass test times, and surveillance test intervals for reactor protection system (RPS) and engineered safety features actuation system instrumentation, for the Byron Station, Unit Nos. 1 and 2, and Braidwood Station, Units 1 and 2. |
| | The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on August 9, 2007, it was agreed that you would provide a response within 30 days from the date of this letter. |
| | The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3733. |
| | Sincerely, Robert F. Kuntz, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456 and STN 50-457 |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Informationcc w/encl: See next pageDISTRIBUTION:PUBLICLPL3-2 R/FRidsNrrDorlLpl3-2RidsNrrPMRKuntzRidsNrrLAEWhittRidsAcrsAcnwMailCenter RidsOgcRpRidsRgn3MailCenterRidsNrrDorlDpr RidsNrrDraAplaCDoutt, NRRADAMS Accession Number: ML072270247OFFICELPL3-2/PMLPL3-2/LALPL3-2/BC NAMERKuntzEWhittRGibbs DATE8/16/078/16/078/17/07 OFFICIAL RECORD COPY Byron Station, Unit Nos. 1 and 2 cc: | | |
| Illinois Emergency Management AgencyDivision of Disaster Assistance & | | Request for Additional Information cc w/encl: See next page DISTRIBUTION: |
| Preparedness 1035 Outer Park Dr Springfield, IL 62704Document Control Desk - Licensingvia e-mailMr. Dwain W. Alexander, Project Managervia e-mailHoward A. LearnerEnvironmental Law and Policy Center of the Midwest 35 East Wacker Drive Suite 1300 Chicago, IL 60601-2110U.S. Nuclear Regulatory CommissionByron Resident Inspector's Office via e-mailMs. Lorraine CreekRR 1, Box 182 Manteno, IL 60950Chairman, Ogle County BoardP.O. Box 357 Oregon, IL 61061Mrs. Phillip B. Johnson1907 Stratford Lane Rockford, IL 61107Attorney General500 S. Second Street Springfield, IL 62701Plant Manager - Byron Station via e-mailSite Vice President - Byron Stationvia e-mailSenior Vice President - Operations Supportvia e-mailChairmanWill County Board of Supervisors Will County Board Courthouse Joliet, IL 60434Director - Licensing and Regulatory Affairsvia e-mailManager Regulatory Assurance - Byronvia e-mailAssociate General Counsel via e-mailVice President - Regulatory Affairsvia e-mailManager Licensing - Braidwood/Byronvia e-mailSenior Vice President - Midwest Operationsvia e-mailVice President - Regulatory Affairsvia e-mailManager Licensing - Braidwood, Byron and LaSalle via e-mailSenior Vice President - Midwest Operationsvia e-mailMr. Barry Quigley 3512 Louisiana Rockford, IL 61108 EnclosureREQUEST FOR ADDITIONAL INFORMATIONBYRON STATION, UNIT NOS. 1 AND 2,AND BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-454, STN 50-455,STN 50-456 AND STN 50-457In reviewing the Exelon Generation Company's (Exelon's) submittal dated January 8, 2007,related to extending the completion times (CT), bypass test times, and surveillance test intervals (STIs) for reactor protection system and engineered safety features actuation system (ESFAS) instrumentation, for the Byron Station, Unit Nos. 1 and 2 (Byron) and Braidwood Station, Units 1 and 2 (Braidwood), the NRC staff has determined that the following information is needed in order to complete its review:1.The analysis for WCAP-14333/WCAP-15376 assumed that maintenance on master andslave relays, logic cabinets, and analog channels while at power occurs only after a component failure, and that preventive maintenance does not occur. The topical report does not preclude the practice of at-power preventive maintenance but limits the total time a component is unavailable due to corrective or preventive maintenance to the values used in the analysis. If preventive maintenance is to be performed at Byron/Braidwood, confirm that the unavailability for components evaluated in WCAP-14333 are consistent with the plant specific estimates at Byron/Braidwood and do not exceed those assumed in the analysis. See the submittal, Attachment 6, Page 1, "Implementation Guidelines," Table 1, "AnalogChannel Calibration" as an example. 2. Provide an assessment of external events risk impact including, seismic, fire, andexternal floods/high wind with respect to the proposed CT and STI extensions, per Regulatory Guide (RG) 1.174 Section 2.2.4, "Acceptance Guidelines" and RG 1.177 Section 2.3.2, "Scope of the Probabilistic Risk Assessment (PRA) for technical specification (TS) Applications." Include any seismic vulnerabilities associated with instrumentation/logic systems or components and risk impacts on fire screening criteria and quantification of fire sequences in unscreened areas. In addition, confirm that the combined total Core Damage Frequency (CDF) from external and internal events remains less than the RG 1.174 base CDF of 1E-4 per year.3. Provide a discussion on the following aspects of PRA quality for Byron/Braidwood.*Provide the date of Byron/Braidwood's PRA industry peer review and the date ofcertification. Provide the results of the Peer review including disposition of "A" and "B" facts and observations. *The plant-specific PRA reflects the as-built, as-operated plant.*Applicable PRA updates conducted since completion of individual plantexamination (IPE) and individual plant examination of external events (IPEEE)and the status of any improvements identified by the IPE and IPEEE.*Reference PRA quality assurance programs/procedures, including expectedPRA revision schedules.*PRA adequacy and completeness with respect to evaluating the proposed CT,bypass test time under Tier 3 configuration risk management.*Plant design or operational modifications not reflected in theWCAP-14333/WCAP15376 PRA used in this application that are related to or could impact this application. Justify the acceptability of not including these modifications in the PRA, as part of this application.4. Consistent with RG 1.174, the cumulative risk of the present TS change in light of pastapplications (or additional applications planned or under review) should be understood. | | PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNrrPMRKuntz RidsNrrLAEWhitt RidsAcrsAcnwMailCenter RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr RidsNrrDraApla CDoutt, NRR ADAMS Accession Number: ML072270247 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME RKuntz EWhitt RGibbs DATE 8/16/07 8/16/07 8/17/07 OFFICIAL RECORD COPY |
| Cumulative risks were addressed for Byron/Braidwood with respect to the implementation of WCAP-10271, WCAP-14333, and WCAP-15376 only. Provide an evaluation of cumulative risk impact of previous and additional TS applications under development or review per RG 1.174, Section 3.3.2, as applicable to the implementation of WCAP-14333 and WCAP-15376.5. Does the configuration risk management program at Byron/Braidwood provide modelingof the reactor trip and ESFAS systems and components addressed by WCAP-15376 and WCAP-14333 when performing Tier 3 evaluations? Discuss how signals or components not specifically modeled will be addressed.6.Discuss the omission of reactor coolant system pressure relief systems from theregulatory commitments listed in Attachment 5, Page 1 of the submittal, see WCAP-15376 (Tier 2).}} | | |
| | Byron Station, Unit Nos. 1 and 2 Senior Vice President - Operations Support via e-mail cc: |
| | Chairman Illinois Emergency Management Agency Will County Board of Supervisors Division of Disaster Assistance & Will County Board Courthouse Preparedness Joliet, IL 60434 1035 Outer Park Dr Springfield, IL 62704 Director - Licensing and Regulatory Affairs via e-mail Document Control Desk - Licensing via e-mail Manager Regulatory Assurance - Byron via e-mail Mr. Dwain W. Alexander, Project Manager via e-mail Associate General Counsel via e-mail Howard A. Learner Environmental Law and Policy Vice President - Regulatory Affairs Center of the Midwest via e-mail 35 East Wacker Drive Suite 1300 Manager Licensing - Braidwood/Byron Chicago, IL 60601-2110 via e-mail U.S. Nuclear Regulatory Commission Senior Vice President - Midwest Operations Byron Resident Inspectors Office via e-mail via e-mail Vice President - Regulatory Affairs Ms. Lorraine Creek via e-mail RR 1, Box 182 Manteno, IL 60950 Manager Licensing - Braidwood, Byron and LaSalle Chairman, Ogle County Board via e-mail P.O. Box 357 Oregon, IL 61061 Senior Vice President - Midwest Operations via e-mail Mrs. Phillip B. Johnson 1907 Stratford Lane Mr. Barry Quigley Rockford, IL 61107 3512 Louisiana Rockford, IL 61108 Attorney General 500 S. Second Street Springfield, IL 62701 Plant Manager - Byron Station via e-mail Site Vice President - Byron Station via e-mail |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNIT NOS. 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-454, STN 50-455, STN 50-456 AND STN 50-457 In reviewing the Exelon Generation Companys (Exelons) submittal dated January 8, 2007, related to extending the completion times (CT), bypass test times, and surveillance test intervals (STIs) for reactor protection system and engineered safety features actuation system (ESFAS) instrumentation, for the Byron Station, Unit Nos. 1 and 2 (Byron) and Braidwood Station, Units 1 and 2 (Braidwood), the NRC staff has determined that the following information is needed in order to complete its review: |
| | : 1. The analysis for WCAP-14333/WCAP-15376 assumed that maintenance on master and slave relays, logic cabinets, and analog channels while at power occurs only after a component failure, and that preventive maintenance does not occur. The topical report does not preclude the practice of at-power preventive maintenance but limits the total time a component is unavailable due to corrective or preventive maintenance to the values used in the analysis. If preventive maintenance is to be performed at Byron/Braidwood, confirm that the unavailability for components evaluated in WCAP-14333 are consistent with the plant specific estimates at Byron/Braidwood and do not exceed those assumed in the analysis. |
| | See the submittal, Attachment 6, Page 1, Implementation Guidelines, Table 1, Analog Channel Calibration as an example. |
| | : 2. Provide an assessment of external events risk impact including, seismic, fire, and external floods/high wind with respect to the proposed CT and STI extensions, per Regulatory Guide (RG) 1.174 Section 2.2.4, Acceptance Guidelines and RG 1.177 Section 2.3.2, Scope of the Probabilistic Risk Assessment (PRA) for technical specification (TS) Applications. Include any seismic vulnerabilities associated with instrumentation/logic systems or components and risk impacts on fire screening criteria and quantification of fire sequences in unscreened areas. In addition, confirm that the combined total Core Damage Frequency (CDF) from external and internal events remains less than the RG 1.174 base CDF of 1E-4 per year. |
| | : 3. Provide a discussion on the following aspects of PRA quality for Byron/Braidwood. |
| | * Provide the date of Byron/Braidwoods PRA industry peer review and the date of certification. Provide the results of the Peer review including disposition of A and B facts and observations. |
| | Enclosure |
| | * The plant-specific PRA reflects the as-built, as-operated plant. |
| | * Applicable PRA updates conducted since completion of individual plant examination (IPE) and individual plant examination of external events (IPEEE) and the status of any improvements identified by the IPE and IPEEE. |
| | * Reference PRA quality assurance programs/procedures, including expected PRA revision schedules. |
| | * PRA adequacy and completeness with respect to evaluating the proposed CT, bypass test time under Tier 3 configuration risk management. |
| | * Plant design or operational modifications not reflected in the WCAP-14333/WCAP15376 PRA used in this application that are related to or could impact this application. Justify the acceptability of not including these modifications in the PRA, as part of this application. |
| | : 4. Consistent with RG 1.174, the cumulative risk of the present TS change in light of past applications (or additional applications planned or under review) should be understood. |
| | Cumulative risks were addressed for Byron/Braidwood with respect to the implementation of WCAP-10271, WCAP-14333, and WCAP-15376 only. Provide an evaluation of cumulative risk impact of previous and additional TS applications under development or review per RG 1.174, Section 3.3.2, as applicable to the implementation of WCAP-14333 and WCAP-15376. |
| | : 5. Does the configuration risk management program at Byron/Braidwood provide modeling of the reactor trip and ESFAS systems and components addressed by WCAP-15376 and WCAP-14333 when performing Tier 3 evaluations? Discuss how signals or components not specifically modeled will be addressed. |
| | : 6. Discuss the omission of reactor coolant system pressure relief systems from the regulatory commitments listed in Attachment 5, Page 1 of the submittal, see WCAP-15376 (Tier 2).}} |
RAI, to Extend the Completion Times, Bypass Test Times, & Surveillance Test Intervals for Reactor Protection Systems & Engineered Safety Features Actuation System Instrumentation| ML072270247 |
| Person / Time |
|---|
| Site: |
Byron, Braidwood  |
|---|
| Issue date: |
08/17/2007 |
|---|
| From: |
Robert Kuntz
NRC/NRR/ADRO/DORL/LPLIII-2 |
|---|
| To: |
Crane C
Exelon Generation Co |
|---|
| Kuntz, Robert , NRR/DLPM, 415-3733 |
| References |
|---|
| TAC MD4009, TAC MD4010, TAC MD4011, TAC MD4012 |
| Download: ML072270247 (5) |
|
|
|---|
Category:Letter
MONTHYEARML24263A1272024-09-23023 September 2024
– Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary
BYRON 2024-0046, Cycle 27 Core Operating Limits Report2024-09-19019 September 2024
Cycle 27 Core Operating Limits Report
RS-24-088, Relief Requests Associated with the Fifth Inservice Inspection Interval2024-09-13013 September 2024
Relief Requests Associated with the Fifth Inservice Inspection Interval
IR 05000456/20240112024-09-12012 September 2024
Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011
ML24164A0032024-09-10010 September 2024
Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink
ML24250A1182024-09-0606 September 2024
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
05000454/LER-2024-001, Both Trains of Control Room Ventilation Temperature Control System Inoperable2024-09-0505 September 2024
Both Trains of Control Room Ventilation Temperature Control System Inoperable
ML24227A0522024-08-29029 August 2024
Audit Plan for LAR to Remove ATWS Mtc Limit
IR 05000456/20240052024-08-29029 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005)
IR 05000454/20240052024-08-28028 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Byron Station, Units 1 and 2 (Report 05000455/2024005 and 05000454/2024005)
ML24225A1112024-08-13013 August 2024
Notification of NRC Fire Protection Team Inspection Request for Information
ML24222A6772024-08-0909 August 2024
Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
IR 05000454/20240112024-08-0808 August 2024
Phase 2 Post- Approval License Renewal Report 05000454/2024011
IR 05000456/20240022024-08-0808 August 2024
Integrated Inspection Report 05000456/2024002 and 05000457/2024002
ML24172A1252024-07-26026 July 2024
Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter
IR 05000454/20240022024-07-26026 July 2024
Integrated Inspection Report 05000454/2024002 and 05000455/2024002, and Exercise of Enforcement Discretion
ML24179A3262024-07-23023 July 2024
LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056)
05000456/LER-2024-001, Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open2024-07-0303 July 2024
Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open
RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024
Nuclear Radiological Emergency Plan Document Revisions
RS-24-066, Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller2024-06-25025 June 2024
Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller
ML24163A3922024-06-25025 June 2024
Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter
ML24170A7652024-06-19019 June 2024
Confirmation of Initial License Examination
RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
ML24164A2132024-06-13013 June 2024
Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant
RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024
License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink
IR 05000456/20240102024-05-31031 May 2024
License Renewal Phase 1 Report 05000456/2024010
RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024
License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed
RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024
Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
ML24142A3352024-05-21021 May 2024
Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes
RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024
2023 Corporate Regulatory Commitment Change Summary Report
BYRON 2024-0031, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-05-16016 May 2024
Completion of License Renewal Activities Prior to Entering the Period of Extended Operation
ML24136A0132024-05-15015 May 2024
2023 Annual Radiological Environmental Operating Report
ML24136A2452024-05-15015 May 2024
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004
IR 05000454/20240012024-05-10010 May 2024
Integrated Inspection Report 05000454/2024001; 05000455/2024001 and 07200068/2024001
BYRON 2024-0028, Annual Radiological Environmental Operating Report (AREOR)2024-05-0909 May 2024
Annual Radiological Environmental Operating Report (AREOR)
ML24128A1212024-05-0707 May 2024
Response to Braidwood and Dresden FOF Dates Change Request (2025)
BYRON 2024-0022, 2023 Regulatory Commitment Change Summary Report2024-05-0202 May 2024
2023 Regulatory Commitment Change Summary Report
ML24122A6522024-05-0101 May 2024
Submittal of 2023 Annual Radioactive Effluent Release Report
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
IR 05000456/20243012024-04-29029 April 2024
NRC Initial License Examination Report 05000456/2024301; 05000457/2024301
ML24116A0052024-04-25025 April 2024
Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25
ML24116A1192024-04-25025 April 2024
2023 Annual Radioactive Effluent Release Report (ARERR)
RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024
License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
IR 05000456/20240012024-04-24024 April 2024
Integrated Inspection Report 05000456/2024001 and 05000457/2024001
ML24113A1272024-04-22022 April 2024
Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary)
ML24113A2892024-04-22022 April 2024
Notification of NRC Baseline Inspection and Request for Information
IR 05000457/20240902024-04-19019 April 2024
Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090
BYRON 2024-0020, Annual Dose Report for 20232024-04-18018 April 2024
Annual Dose Report for 2023
ML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
2024-09-06
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24263A1272024-09-23023 September 2024
– Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary
ML24250A1182024-09-0606 September 2024
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML24197A0162024-07-12012 July 2024
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591
ML24142A3352024-05-21021 May 2024
Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes
ML24113A2892024-04-22022 April 2024
Notification of NRC Baseline Inspection and Request for Information
ML24053A3382024-02-22022 February 2024
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds (L-2023-LLR-0062)
ML24039A0412024-01-30030 January 2024
NRR E-mail Capture - Request for Additional Information Regarding Braidwood Request for Alternative (I4R-18)
ML23339A0452023-12-0505 December 2023
Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010
ML23297A2352023-10-26026 October 2023
Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection
ML23209A7242023-07-31031 July 2023
Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010
ML23198A0372023-07-17017 July 2023
Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant
ML23191A8442023-07-10010 July 2023
05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML23172A1172023-06-22022 June 2023
Notification of NRC Fire Protection Team Inspection Request for Information
ML23110A3202023-04-21021 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML23094A1352023-04-0404 April 2023
Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010
ML23069A0332023-03-0606 March 2023
Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1
ML23069A0342023-03-0606 March 2023
Unit 1 Lr Commitment 10 RAI Set 1 - (Non-Proprietary)
ML23115A2412023-01-20020 January 2023
NRR E-mail Capture - Preliminary RAIs Related to L-2022-LLA-0131 - Byron, Unit 2, Reinsertion of an Accident Tolerant Fuel Lead Test Assembly
ML23018A1632023-01-18018 January 2023
Notification of NRC Baseline Inspection and Request for Information
ML22241A0522022-08-29029 August 2022
Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000456/2022004 05000457/2022004
ML22237A0272022-08-25025 August 2022
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML22271A0772022-05-0606 May 2022
NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request
ML22129A0132022-05-0606 May 2022
NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10
ML22116A1272022-04-26026 April 2022
Unit 2 RFI for an NRC Triennial Heat Exchanger/Sink Performance Inspection and RFI IR 05000454/2022002 05000455/2022002
ML22091A0852022-04-0101 April 2022
NRR E-mail Capture - Braidwood and Byron - Final RAI Regarding Proposed Alternative for Various Pressurizer Welds (EPID L-2021-LLR-0035 and 0036)
ML22041B5362022-02-10010 February 2022
NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541
ML22034A9862022-02-0404 February 2022
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000456/2022402 05000457/2022402
ML21350A4372021-12-16016 December 2021
Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team) Inspection Report 05000456/2022010 and 05000457/2022010
ML21273A3312021-10-0404 October 2021
Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Byron Station
ML21256A1902021-09-10010 September 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21228A2352021-08-17017 August 2021
Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000457/2021004
ML21203A3112021-07-21021 July 2021
NRR E-mail Capture - Final Byron Permanently Defueled Technical Specifications (PDTS) - Second Round RAI
ML21193A0942021-07-12012 July 2021
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML21189A1612021-07-0808 July 2021
NRR E-mail Capture - Second Round Request for Additional Information - Byron Permanently Defueled Technical Specification Amendment
ML21189A1602021-07-0808 July 2021
NRR E-mail Capture - Request for Additional Information - Braidwood, Byron, and Ginna - Amendment to Address the Issues in Westinghouse NSALs
ML21144A2132021-05-24024 May 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21117A0342021-05-0505 May 2021
Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893
ML21062A0652021-03-0101 March 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting
ML21057A1022021-02-25025 February 2021
Notification of NRC Fire Protection Team Inspection Request for Information; Inspection Report 05000456/2021010; 05000457/2021010
ML21049A2572021-02-18018 February 2021
Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237)
ML21036A1102021-02-0404 February 2021
NRR E-mail Capture - Draft RAIs for Byron Station, Unit Nos. 1 and 2, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
ML21029A3302021-01-29029 January 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative Request to Use ASME Code Case N-885
ML21020A1292021-01-20020 January 2021
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2021002; 05000457/2021002
ML21004A1452020-12-30030 December 2020
NRR E-mail Capture - Request for Additional Information Regarding Relief Requests Braidwood I4R-11 and Byron I4R-18
ML20329A4852020-11-24024 November 2020
Notification of NRC Fire Protection Team Inspection Request for Information
ML20294A5492020-10-21021 October 2020
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML20289A1142020-10-0909 October 2020
NRR E-mail Capture - Preliminary RAIs for LAR Regarding Non-conservative TS EDG Frequency Tolerance
ML20153A7042020-06-0101 June 2020
NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26
ML20104C1452020-04-10010 April 2020
NRR E-mail Capture - Preliminary RAIs for Exelon'S April 6, 2020, Application to Defer Braidwood, Unit 2, Steam Generator Inspections
ML20077M2212020-03-20020 March 2020
Ti 2515/194 Inspection Documentation Request
2024-09-06
[Table view] |
Text
August 17, 2007 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BYRON STATION, UNIT NOS. 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION REQUIREMENTS FOR SELECT REACTOR TRIP SYSTEM, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM, AND CONTAINMENT VENTILATION ISOLATION, INSTRUMENTATION (TAC NOS.
MD4009, MD4010, MD4011, AND MD4012)
Dear Mr. Crane:
By letter to the Nuclear Regulatory Commission (NRC) dated January 8, 2007, Exelon Generation Company, LLC submitted a request to extend the completion times, bypass test times, and surveillance test intervals for reactor protection system (RPS) and engineered safety features actuation system instrumentation, for the Byron Station, Unit Nos. 1 and 2, and Braidwood Station, Units 1 and 2.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on August 9, 2007, it was agreed that you would provide a response within 30 days from the date of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3733.
Sincerely,
/RA/
Robert F. Kuntz, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456 and STN 50-457
Enclosure:
Request for Additional Information cc w/encl: See next page
August 17, 2007 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BYRON STATION, UNIT NOS. 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION REQUIREMENTS FOR SELECT REACTOR TRIP SYSTEM, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM, AND CONTAINMENT VENTILATION ISOLATION, INSTRUMENTATION (TAC NOS.
MD4009, MD4010, MD4011, AND MD4012)
Dear Mr. Crane:
By letter to the Nuclear Regulatory Commission (NRC) dated January 8, 2007, Exelon Generation Company, LLC submitted a request to extend the completion times, bypass test times, and surveillance test intervals for reactor protection system (RPS) and engineered safety features actuation system instrumentation, for the Byron Station, Unit Nos. 1 and 2, and Braidwood Station, Units 1 and 2.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on August 9, 2007, it was agreed that you would provide a response within 30 days from the date of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3733.
Sincerely, Robert F. Kuntz, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456 and STN 50-457
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNrrPMRKuntz RidsNrrLAEWhitt RidsAcrsAcnwMailCenter RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr RidsNrrDraApla CDoutt, NRR ADAMS Accession Number: ML072270247 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME RKuntz EWhitt RGibbs DATE 8/16/07 8/16/07 8/17/07 OFFICIAL RECORD COPY
Byron Station, Unit Nos. 1 and 2 Senior Vice President - Operations Support via e-mail cc:
Chairman Illinois Emergency Management Agency Will County Board of Supervisors Division of Disaster Assistance & Will County Board Courthouse Preparedness Joliet, IL 60434 1035 Outer Park Dr Springfield, IL 62704 Director - Licensing and Regulatory Affairs via e-mail Document Control Desk - Licensing via e-mail Manager Regulatory Assurance - Byron via e-mail Mr. Dwain W. Alexander, Project Manager via e-mail Associate General Counsel via e-mail Howard A. Learner Environmental Law and Policy Vice President - Regulatory Affairs Center of the Midwest via e-mail 35 East Wacker Drive Suite 1300 Manager Licensing - Braidwood/Byron Chicago, IL 60601-2110 via e-mail U.S. Nuclear Regulatory Commission Senior Vice President - Midwest Operations Byron Resident Inspectors Office via e-mail via e-mail Vice President - Regulatory Affairs Ms. Lorraine Creek via e-mail RR 1, Box 182 Manteno, IL 60950 Manager Licensing - Braidwood, Byron and LaSalle Chairman, Ogle County Board via e-mail P.O. Box 357 Oregon, IL 61061 Senior Vice President - Midwest Operations via e-mail Mrs. Phillip B. Johnson 1907 Stratford Lane Mr. Barry Quigley Rockford, IL 61107 3512 Louisiana Rockford, IL 61108 Attorney General 500 S. Second Street Springfield, IL 62701 Plant Manager - Byron Station via e-mail Site Vice President - Byron Station via e-mail
REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNIT NOS. 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-454, STN 50-455, STN 50-456 AND STN 50-457 In reviewing the Exelon Generation Companys (Exelons) submittal dated January 8, 2007, related to extending the completion times (CT), bypass test times, and surveillance test intervals (STIs) for reactor protection system and engineered safety features actuation system (ESFAS) instrumentation, for the Byron Station, Unit Nos. 1 and 2 (Byron) and Braidwood Station, Units 1 and 2 (Braidwood), the NRC staff has determined that the following information is needed in order to complete its review:
- 1. The analysis for WCAP-14333/WCAP-15376 assumed that maintenance on master and slave relays, logic cabinets, and analog channels while at power occurs only after a component failure, and that preventive maintenance does not occur. The topical report does not preclude the practice of at-power preventive maintenance but limits the total time a component is unavailable due to corrective or preventive maintenance to the values used in the analysis. If preventive maintenance is to be performed at Byron/Braidwood, confirm that the unavailability for components evaluated in WCAP-14333 are consistent with the plant specific estimates at Byron/Braidwood and do not exceed those assumed in the analysis.
See the submittal, Attachment 6, Page 1, Implementation Guidelines, Table 1, Analog Channel Calibration as an example.
- 2. Provide an assessment of external events risk impact including, seismic, fire, and external floods/high wind with respect to the proposed CT and STI extensions, per Regulatory Guide (RG) 1.174 Section 2.2.4, Acceptance Guidelines and RG 1.177 Section 2.3.2, Scope of the Probabilistic Risk Assessment (PRA) for technical specification (TS) Applications. Include any seismic vulnerabilities associated with instrumentation/logic systems or components and risk impacts on fire screening criteria and quantification of fire sequences in unscreened areas. In addition, confirm that the combined total Core Damage Frequency (CDF) from external and internal events remains less than the RG 1.174 base CDF of 1E-4 per year.
- 3. Provide a discussion on the following aspects of PRA quality for Byron/Braidwood.
- Provide the date of Byron/Braidwoods PRA industry peer review and the date of certification. Provide the results of the Peer review including disposition of A and B facts and observations.
Enclosure
- The plant-specific PRA reflects the as-built, as-operated plant.
- Applicable PRA updates conducted since completion of individual plant examination (IPE) and individual plant examination of external events (IPEEE) and the status of any improvements identified by the IPE and IPEEE.
- Reference PRA quality assurance programs/procedures, including expected PRA revision schedules.
- PRA adequacy and completeness with respect to evaluating the proposed CT, bypass test time under Tier 3 configuration risk management.
- Plant design or operational modifications not reflected in the WCAP-14333/WCAP15376 PRA used in this application that are related to or could impact this application. Justify the acceptability of not including these modifications in the PRA, as part of this application.
- 4. Consistent with RG 1.174, the cumulative risk of the present TS change in light of past applications (or additional applications planned or under review) should be understood.
Cumulative risks were addressed for Byron/Braidwood with respect to the implementation of WCAP-10271, WCAP-14333, and WCAP-15376 only. Provide an evaluation of cumulative risk impact of previous and additional TS applications under development or review per RG 1.174, Section 3.3.2, as applicable to the implementation of WCAP-14333 and WCAP-15376.
- 5. Does the configuration risk management program at Byron/Braidwood provide modeling of the reactor trip and ESFAS systems and components addressed by WCAP-15376 and WCAP-14333 when performing Tier 3 evaluations? Discuss how signals or components not specifically modeled will be addressed.
- 6. Discuss the omission of reactor coolant system pressure relief systems from the regulatory commitments listed in Attachment 5, Page 1 of the submittal, see WCAP-15376 (Tier 2).