Letter Sequence Acceptance Review |
|---|
|
|
MONTHYEARRS-10-114, License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal2010-06-29029 June 2010
License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal
Project stage: Request
ML1021401282010-08-0505 August 2010
Unit Nos.1 and 2 - Supplemental Information Needed for Acceptance of Requested Licensing Action Low Temperature Overpessure Protection
Project stage: Acceptance Review
RS-10-137, Supplemental Information Supporting License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal2010-08-24024 August 2010
Supplemental Information Supporting License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal
Project stage: Supplement
ML1024204702010-09-0303 September 2010
Acceptance Review of License Amendment Request Low Temperature Overpressure Protection
Project stage: Acceptance Review
RS-11-006, Additional Information Supporting Request for License Amendment Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal2011-01-13013 January 2011
Additional Information Supporting Request for License Amendment Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal
Project stage: Request
ML11132A1292011-03-17017 March 2011
Transmittal of Ihpb Safety Evaluation, Byron, Units 1 and 2, Braidwood, Units 1 and 2, License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal
Project stage: Approval
ML1108406572011-06-29029 June 2011
Issuance of Amendments 167, 167, 174 & 174 Low Temperature Overpressure Protection and Loss of Decay Heat Removal
Project stage: Approval
2010-09-03
[Table View] |
|
|---|
Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024
Integrated Inspection Report 05000456/2023004 and 05000457/2023004
IR 05000454/20230042024-02-0202 February 2024
Integrated Inspection Report 05000454/2023004 and 05000455/2023004
ML24025C7242024-01-29029 January 2024
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002
IR 05000457/20230112024-01-25025 January 2024
2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation
ML24022A2722024-01-23023 January 2024
Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011
ML24018A0362024-01-17017 January 2024
Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618
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
ML23320A1762023-12-13013 December 2023
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0027 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
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
ML23318A5102023-12-0101 December 2023
Relief from the Requirements of the ASME Code
IR 05000454/20233012023-11-27027 November 2023
NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301
ML23331A8922023-11-22022 November 2023
Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference
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
BYRON 2023-0065, Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline2023-11-17017 November 2023
Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline
BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023
Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)
IR 05000454/20230032023-11-13013 November 2023
Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion
RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information
ML23317A1192023-11-10010 November 2023
Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information
ML23313A0852023-11-0909 November 2023
Submittal of 2023-301 Byron Initial License Examination Post-Examination Comments
RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023
Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds
ML23297A2352023-10-26026 October 2023
Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection
IR 05000456/20234012023-10-18018 October 2023
Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401
IR 05000456/20230102023-10-18018 October 2023
Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010
RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023
Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles
RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023
Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
ML23278A0272023-10-0505 October 2023
Operator Licensing Examination Approval - Byron Station, October 2023
RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023
Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75
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.
ML23251A1622023-09-29029 September 2023
Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements
RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023
Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals
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)
ML23242A3282023-09-0101 September 2023
Amendment No. 233 Correction
IR 05000454/20235012023-08-31031 August 2023
Emergency Preparedness Biennial Exercise Inspection Report 05000454/2023501 and 05000455/2023501
IR 05000454/20230052023-08-30030 August 2023
Updated Inspection Plan for Byron Station (Report 05000454/2023005 and 05000455/2023005)
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
IR 05000454/20230022023-08-0303 August 2023
Integrated Inspection Report 05000454/2023002 and 05000455/2023002
2024-02-02
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555"()001 August 5, 2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUB.JECT: BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS.
1 AND 2 - SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LOW TEMPERATURE OVERPRESSURE PROTECTION (TAC NOS. ME4194, ME4195, ME4196, AND ME4197)
Dear Mr. Pacilio:
By letter dated June 29,2010 (Agencywide Documents Access and Management System Accession No. ML101810069), Exelon Generation Company, LLC (EGC, the licensee) submitted a license amendment request for technical specification changes related to low temperature overpressure protection and loss of decay heat removal. The purpose of this letter is to provide the results of the Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to make the application complete, the NRC staff requests that EGC supplement the application to provide the information identified in the enclosure by August 24,2010. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of
M. Pacilio -2 any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and associated time frame in this letter was discussed with your staff on August 5, 2010.
If you have any questions, please contact me at (301) 415-1547.
Sincerely,
- t~enior Plant Licensing Branch 111-2 Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN-456, STN-457, STN 50-454, and STN 50-455
Enclosure:
Supplemental Information Needed cc w/encl: Distribution via Listserv
SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT REQUEST REGARDING LOW TEMPERATURE OVERPRESSURE PROTECTION BRAIDWOOD STATION. UNITS 1 AND 2 AND BYRON STATION. UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-456. STN 50-457 STN 50-454, AND STN 50-455 The Nuclear Regulatory Commission (NRC) staff is reviewing Exelon Generation Company, LLC's (the licensee's) license amendment request dated June 29,2010 (Agencywide Documents Access and Management System Accession No. ML101810069), which requested NRC review and approval of technical specification changes related to low temperature overpressure protection and loss of decay heat removal. The NRC staff has concluded that the information delineated below is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed license amendment in terms of regulatory requirements and the protection of public health and safety and the environment.
- 1. Please identify all operator manual actions that will be added, deleted, or changed to support the proposed license amendment.
- 2. What cues are provided to personnel that manual action(s) is/are required?
- 3. What cues are provided to personnel that the proposed action(s) is/are no longer required?
- 4. What administrative controls exist to assure that, when the action(s) is/are no longer required, the plant configuration is put in the correct configuration for the plant status?
- 5. Please describe any changes to procedures needed to support the proposed license amendment.
- 6. Please describe any changes to controls or displays (including the Safety Parameter Display System) needed to support the proposed license amendment.
- 7. Please describe any changes to training needs to support the proposed license amendment.
- 8. Please describe any changes to staffing or qualification needed to support the proposed license amendment.
ENCLOSURE
-2
- 9. What has been or will be done to assure that any new or changed human actions can be done in the environment that will be present, and within the time limits of the relevant scenario(s)?
- 10. If applicable precedents exist, has an operating experience review been done?
- 11. Please describe any increase in work load that will occur with the proposed licensed amendment.
- 12. Please describe any new scheduling constraints or new surveillance requirements due to the proposed license amendment.
- 13. Please provide all procedures related to the proposed license amendment.
M. Pacilio -2 any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and associated time frame in this letter was discussed with your staff on August 5, 2010.
If you have any questions, please contact me at (301) 415-1547.
Sincerely, IRA!
Marshall J. David, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN-456, STN-457, STN 50-454, and STN 50-455
Enclosure:
Supplemental Information Needed cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC RidsOgcRp Resource LPL3-2 RtF RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl3-2 Resource RidsNrrPMBraidwood Resource RidsNrrLATHarris Resource RidsNrrDirslhpb Resource RidsNrrPMByron Resource RidsNrrDssSrxb Resource RidsNrrDorlDpr Resource RidsRgn3MailCenter Resource CFranklin, NRR BParks, NRR GLapinsky, NRR ADAMS Accession No.: ML102140128 *Date of e-mail NRR-106 OFFICE LPL3-2/PM LPL3-2/LA IHPB/BC LPL3-2/BC NAME MDavid JBurkhardt for UShoop* CGratton for THarris RCarlson 8/5/10 8/2/10 7/28/10 8/5110 OFFICIAL RECORD COpy
