Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
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MONTHYEARML1106200892011-03-0202 March 2011 Response to NRC Verification Inspection Report; 05000456/2011009; 05000457/2011009 Project stage: Request ML1117900402011-04-12012 April 2011 Westinghouse Electric Company Affidavit Supporting Withholding, Attachment 6 to Braidwood Station, Units 1 & 2, Byron Station, Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate Project stage: Request ML1117900432011-05-0909 May 2011 Affidavit from Cameron International Corporation Supporting Withholding of Attachments 8a Through 8d Project stage: Request ML1117900422011-06-21021 June 2011 Mur Technical Evaluation, (Non-Proprietary Version), Attachment 7 to Braidwood Station, Units 1 & 2, Byron Station, Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate Project stage: Request RS-11-099, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate2011-06-23023 June 2011 Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate Project stage: Request ML1117900382011-06-23023 June 2011 Steam Generator Tube Rupture Analysis Report, Attachment 5a to Braidwood Station, Units 1 & 2, Byron Station, Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate Project stage: Request ML11224A0832011-08-0303 August 2011 NRR E-mail Capture - Draft - Supplemental Information Request Braidwood and Byron Mur LAR (ME6587-ME6590) Project stage: Draft Other ML1121505632011-08-22022 August 2011 Supplemental Information Needed for Acceptance of Licensing Action Measurement Uncertainty Recapture Power Uprate Project stage: Acceptance Review ML1122315742011-09-19019 September 2011 Acceptance Review of License Amendment Request (LAR) Measurement Uncertainty Recapture (Mur) Power Uprate Project stage: Acceptance Review ML11266A0022011-09-19019 September 2011 NRR E-mail Capture - Draft RAI Braidwood/Byron - Measurement Uncertainty Recapture LAR Project stage: Draft RAI ML11262A1612011-10-12012 October 2011 Request for Addtional Information Measurement Uncertainty Power Uprate Request Project stage: Other RS-11-169, Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate2011-11-0101 November 2011 Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate Project stage: Request ML1129203422011-11-0303 November 2011 Request for Withholding Information from Public Disclosure Affidavit CAW-11-3137 Project stage: Withholding Request Acceptance ML1129305492011-11-0303 November 2011 Request for Withholding Information from Public Disclosure Affidavit CAW-11-03 Project stage: Withholding Request Acceptance ML1130104032011-11-28028 November 2011 Request for Additional Information #2 Measurement Uncertainty Power Uprate Request Project stage: RAI ML1202701462012-02-14014 February 2012 Request for Additional Information Measurement Uncertainty Recapture Power Uprate Request Project stage: RAI ML1202609362012-02-14014 February 2012 Request for Additional Information Measurement Uncertainty Recapture Power Uprate Request Project stage: RAI ML1205302582012-02-24024 February 2012 Request for Additional Information Measurement Uncertainty Recapture Power Uprate Request Project stage: RAI ML12068A3822012-03-0808 March 2012 E-MAIL - Mur LAR #1 Response Date Project stage: Other ML12068A2942012-03-0808 March 2012 Request for Additional Information Regarding Reactor Systems Mur Review (TACs ME6587, ME6588, ME6589, and ME6590) Project stage: RAI ML1205904602012-03-0909 March 2012 Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Project stage: RAI ML12089A4902012-03-29029 March 2012 E-MAIL - Draft Balance of Plant Request for Additional Information for Mur Review Project stage: Draft RAI ML12121A6942012-05-10010 May 2012 Braidwood Units 1 and 2 - Request for Additional Information Related to License Application for Measurement Uncertainty Recapture Uprate Project stage: RAI RS-12-081, Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate2012-05-16016 May 2012 Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate Project stage: Request ML12157A0632012-06-13013 June 2012 Request for Additional Information Related to Measurement Uncertainty Recapture Uprate Project stage: RAI ML12233A6012012-08-27027 August 2012 Request for Additional Information, Measurement Uncertainty Recapture Power Uprate Request Project stage: RAI RS-12-144, Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate2012-09-13013 September 2012 Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate Project stage: Request ML12216A0002012-09-27027 September 2012 Request for Additional Information Related to Measurement Uncertainty Uprate Project stage: RAI ML12271A3082012-12-0606 December 2012 Request for Additional Information and Suspension of Review of License Amendment Request for Power Uprate Project stage: RAI RS-13-227, Response to NRC HELB Audit Request for Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate2013-09-0505 September 2013 Response to NRC HELB Audit Request for Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate Project stage: Request RS-13-261, Supplemental Response to NRC HELB Audit Request for Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate2013-10-24024 October 2013 Supplemental Response to NRC HELB Audit Request for Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate Project stage: Supplement RS-13-267, Supplemental Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate2013-11-13013 November 2013 Supplemental Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate Project stage: Supplement 2012-02-14
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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] Category:Request for Additional Information (RAI)
MONTHYEARML23339A0452023-12-0505 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 ML23069A0342023-03-0606 March 2023 Unit 1 Lr Commitment 10 RAI Set 1 - (Non-Proprietary) ML23069A0332023-03-0606 March 2023 Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1 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 ML20023A0812020-01-23023 January 2020 NRR E-mail Capture - RAIs for L-2019-LLA-0201 - Braidwood, Units 1 and 2, LAR to Revise TS 3.7.9, Ultimate Heat Sink ML20008D3992020-01-0808 January 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000454/2020001 ML19350B2952019-12-16016 December 2019 NRR E-mail Capture - Draft Request for Additional Information Regarding Braidwood Station, Units 1 and 2, Impractical Inservice Inspection Requirements (L-2019-LLA-0081) ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19252C1542019-08-22022 August 2019 NRR E-mail Capture - Issuance of the Remainder of Preliminary RAIs for Braidwood/Byron TSTF-505 Application ML19232A2242019-08-0707 August 2019 NRR E-mail Capture - Partial Issuance of Final RAIs for Braidwood/Byron TSTF-505 Application ML19207A0672019-07-26026 July 2019 NRR E-mail Capture - Partial Issuance of Preliminary RAIs for Braidwood/Byron TSTF-505 Application 2023-07-31
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 12, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville,IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2 ~ REQUEST FOR ADDITIONAL INFORMATION RE: MEASUREMENT UNCERTAINTY POWER UPRATE REQUEST (TAC NOS. ME6587, ME6588, 6589, AND ME6590)
Dear Mr. Pacilio:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated June 23, 2011, as supplemented on August 25, 2011, Exelon Generation Company, LLC submitted a license amendment request associated with a measurement uncertainty recapture power uprate, for the Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 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 October 3, 2011, it was agreed that you would provide a response by November 3, 2011.
Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, we may reject your request for approval under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108.
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 NRC's goal of efficient and effective use of staff resources.
-2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1115.
Sincerely, Nicholas J. DiFrancesco, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-456, 50-457, 50-454 and 50-455
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION BRAIDWOOD STATION, UNITS 1 AND 2 AND BYRON STATION, UNIT NOS. 1 AND 2 REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST DOCKET NOS. 50-454, 50-455, 50-456 AND 50-457 TAC NOS. ME65S7, ME65SS, ME65S9, AND ME6590 In reviewing of the Exelon Generation Company, LLC (EGC) license amendment request, dated June 23, 2011, and as supplemented on August 25, 2011 (ADAMS Accession ML111790030 and ML11255A332, respectively), related to a measurement uncertainty recapture power uprate, for the Braidwood Station (Braidwood), Units 1 and 2, and Byron Station, (Byron), Unit Nos. 1 and 2, the U.S. Nuclear Regulatory Commission (NRC) staff has determined that the following information is needed in order to complete its review:
Request for Additional Information - Vessels and Internals Integrity Branch
- 1.Section IV.1.C.vi of Attachment 5 to the June 23, 2011, submittal stated, "the current capsule withdrawal schedule shown in each Unit's PTLR [Pressure Temperature Limits Report] will be updated to reflect the latest capsule f1uence, lead factor, and withdrawal EFPY [effective full power years] associated with each capsule." The updated capsule withdrawal schedules for Byron, Units 1 and 2, can be found in Tables IV.1.C.vi-1 and IV.1.C.vi-2 and for Braidwood, Units 1 and 2, in Tables IV.1.C.vi-3 and IV.1.C.vi-4 of Attachment 5 to the submittal. Although Note (b) of these Tables stated that the information was updated as part of the measurement uncertainty recapture power uprate (MUR PU), the source or reference for the latest capsule f1uence, lead factor, and withdrawal EFPY associated with each capsule is not given. Provide the references for the updated fluence, lead factor, and withdrawal EFPY for the Byron and Braidwood units surveillance capsules. If no such references exist, provide calculation details for the updated values in this application.
- 2. For Byron, Unit 2,Section IV.1.C.iii of Attachment 5 to the June 23, 2011, submittal stated, "For Unit 2, the limiting ART [adjusted reference temperature] values used in the development of the current P-T limit curves at 32 EFPY are Slightly lower than the MUR
[PU] limiting ART values {at 32 EFPY)." The NRC staff cannot verify this because this statement seems to contradict the information in Table IV.1.C.ii-1 of Attachment 5 where the maximum neutron fluence value of 2.06 E19 n/cm2 (E > 1.0 MeV) on record (Le., the 2006 PTLR for 32 EFPY) bounds the MUR PU maximum neutron f1uence value of 1.76 E 19 nlcm 2 (E > 1.0 MeV). Provide details regarding the calculation of the Byron, Unit Nos. 1 and 2, Reactor Pressure Vessel beltline material ARTs which demonstrate how the values in this submittal are different from the corresponding values in the 2006 Byron, Unit Nos. 1 and 2, PTLRs. These ARTs will be considered as the licensing basis in support of the MUR PU license amendment request.
Enclosure
- 2
- 3. For the upper-shelf energy (USE) evaluation,Section IV.1.C.v of Attachment 5 to the June 23,2011, submittal stated that the limiting projected Y4 T USE value is 65 ft-Ibs for the nozzle-to-intermediate shell forging circumferential weld for Byron, Unit 1, 68 ft-Ibs for the nozzle-to-intermediate shell forging circumferential weld for Byron, Unit 2, 75 ft-Ibs for the intermediate-to-Iower shell forging circumferential weld for Braidwood, Unit 1, and 66 ft Ibs for the intermediate-to-Iower shell forging circumferential weld for Braidwood, Unit 2.
However, the details regarding the calculation of these limiting USE values or appropriate references are not given in Attachment 5. The 2006 Byron and Braidwood PTLRs, Revision 4, contain no current USE estimates either. Please provide details regarding the calculation of the limiting USE values for the Byron and Braidwood units or references containing this information.
- 4.Section IV.1.AJi of Attachment 5 to the EGC's June 23, 2011, submittal provides generic information for only a few reactor vessel (RV) internals under the MUR PU conditions.
Table Matrix-1 of NRC RS-001, Revision 0, "Review Standard for Extended Power Uprates," provides the staff's basis for evaluating the potential for extended PU to induce aging effects on RV internals. Depending on the magnitude of the projected RV internals fluence, Table Matrix-1 may be applicable to the MUR application. In the Notes to Table Matrix-1, the NRC staff states that guidance on the neutron irradiation-related threshold for irradiation-assisted stress corrosion cracking (SCC) for pressurized water reactor RV internal components are given in BAW-2248A, "Demonstration of the Management of Aging Effects for the Reactor Vessel Internals," and WCAP-14577, Revision 1-A, "License Renewal Evaluation: Aging Management for Reactor Internals." The "Notes" to Table Matrix-1 state that for thermal and neutron embrittlement of cast austenitic stainless steel, SCC, and void swelling, licensees will need to provide plant-speCific degradation management programs or participate in industry programs to investigate degradation effects and determine appropriate management programs.
The BAW-2248A report and the WCAP-14577, Revision 1-A, have been superseded by the MRP-227 report, "Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines," which summarized the industry's most current recommended inspection and evaluation guidelines for RV internals. The safety evaluation dated June 22,2011, lists the limitations and conditions imposed by the NRC staff on use of the MRP-227 report. Please confirm whether you have established an inspection plan to manage the age-related degradation in the Byron and Braidwood units RV internals, or whether you have participated in the industry's initiatives on age-related degradation of PWR RV internals and plan to submit your plant-specific program consistent with the MRP-227 report guidelines. For the former case, discuss your management of the above-mentioned aging effects on RV internals and demonstrate that the management is appropriate to ensure integrity and operability of RV internals to the end of license.
Request for Additional Information - Fire Protection Branch
- 5. The NRC staff notes that the license amendment request (LAR), Attachment 5, MUR Technical Evaluation, Section VI1.6.A, "Fire Protection Program," on page VII-5 states
- 3 that, "...an analysis of the change in combustible loading determined that the overall increase in fire loading is small and does not change the fire load classification of each affected fire zone ..."
It is unclear to the NRC staff whether there are fire protection program plant modifications planned (e.g., adding new cable trays, or re-routing of existing cables) at MUR power uprate conditions. Clarify whether this request involves plant modifications, or changes to the fire protection program. If any, the staff requests the licensee to identify proposed modifications and discuss the impact of these modifications on the plant's compliance with the fire protection program licensing basis, Title 10 of the Code of Federal Regulations (10 CFR), Section 50.48, or applicable portions of Branch Technical Position, CMEB 9.5-1.
- 6. The NRC staff notes that the LAR, Attachment 5, MUR Technical Evaluation, Section VI1.6.A.i, "Fire Protection Systems," on page VII-6, states that the fire protection water is utilized to supply the spent fuel pool and cooling water to the centrifugal charging pumps.
Are there any other uses of fire water pumps and water for non-fire protection uses at Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2? If so, the MUR power uprate LAR should identify the specific situations and discuss to what extent, if any, the MUR power uprate affects these "non-fire-protection" aspects of the plant fire protection system.
In your response discuss how any non-fire suppression use of fire protection water will impact the need to meet the fire protection system design demands.
Request for Additional Information - Health Physics & Human Performance Branch
- 7. Section 3.4.5 of Attachment 1, (Plant Modifications) includes a list of modifications of interest. The last two bullets of that list include various Balance of Plant instrument rescaling, setpoint and alarm changes and A TWS Mitigation System time delay changes.
In addition,Section VII.2.B of attachment 5 states that the MUR power uprate modification will implement the changes that are required to certain non-safety related systems, including Control Room displays and alarms. There is no other information regarding what these changes might look like or how the licensee plans to validate them.
Please provide additional information regarding what potential modifications might be included, and how they will be verified and validated.
- 8. Section V11.2.A of Attachment 5, states that changes to emergency operating procedure (EOP) and abnormal operating procedure will be made in conformance with the Westinghouse EOP Setpoint Methodology. There is no additional information regarding this methodology. Please provide a description of the Westinghouse EOP Setpoint Methodology, or a reference if it is an approved methodology.
- 9. RIS 2002-03, "Guidance on the Content of Measurement Uncertainty Recapture Uprate Applications," asks for information on this topic:
-4 "A statement confirming licensee intent to revise existing plant operating procedures related to temporary operation above 'full steady-state licensed power levels' to reduce the magnitude of the allowed deviation from the licensed power level. The magnitude should be reduced from the pre-power uprate value of 2%
to a lower value corresponding to the uncertainty in power level credited by the proposed power uprate application."
This was not addressed in the submittal. Please provide information to assure that they have revised the administrative controls for preventing inadvertent excursions above the new 100 percent power level.
Request for Additional Information - Containment and Ventilation Branch
- 10. Attachment 5 Section 111.15.1 - Explain the Input Modification data base and how it is used.
- 11. Attachment 5 Section 111.15.1 - Why were corrections necessary to the reactor coolant pump homologous curves? What were these corrections? Did the corrections significantly affect the results of the mass and energy release analyses?
- 12. Attachment 5 Section 111.15.1 - Why is it assumed that containment spray is terminated at eight hours? What is the current assumption in the mass and energy release calculations and why was this assumption changed?
- 13. Attachment 5 Section 111.15.1 - Why is the barrel baffle metal mass only included for upfJow design plants? How significant is the omission of the barrel baffle metal mass in the current analyses?
- 14. Attachment 5 Section 111.15.1 - Please describe or reference a description of the "identified inconsistencies" in the EPITOME computer code. Did these inconsistencies Significantly affect the current mass and energy release calculation results?
- 15. Attachment 5 Section 111.15.3 - Describe or reference the modeling of the Unit 1 Babcock and Wilcox steam generators and the Unit 2 Westinghouse Model 05 steam generators with respect to mass and energy release calculations and explain why this modeling is conservative for mass and energy release calculations.
- 16. Attachment 5 Section 111.15.4 and Attachment 5 Section 111.16.4 - Describe or reference the computer codes and the assumptions used to derive the electrical equipment environmental qualification temperature and pressure profiles.
- 17. No Response Required
- 18. Attachment 5 Section 111.16.3 - Please describe the modeling of the two steam generator types for the MSLB analyses, especially those characteristics affecting the MSLB results, e.g., mass of water, location of nozzle, etc.
-5
- 19. Attachment 5 Table 111.16 What is meant by a composite curve? How is it determined?
Attachment 5 Section VI.1.F.ii - This section states that the heat loads in a limited number of areas did increase due to the MUR and that the increase was minimal.
Please state which areas would experience an increase in heat load and the magnitude of the increase. The maximum value of these increases is sufficient.
Request for Additional Information - Instrumentation and Control Branch Regulatory Basis Nuclear power plants are licensed to operate at a specified core thermal power.
Appendix K, "ECCS [emergency core cooling system] Evaluation Models," to 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," requires loss-of coolant accident and ECCS analyses to assume "that the reactor has been operating continuously at a power level at least 102 percent of the licensed thermal power level to allow for instrumentation uncertainties." Alternatively, Appendix K allows such analyses to assume a value lower than the specified 102 percent, but not less than the licensed thermal power level, "provided the proposed alternative value has been demonstrated to account for uncertainties due to power level instrumentation error." This allowance gives licensees the option of justifying a power uprate with reduced margin between the licensed power level and the power level assumed in the ECCS analysis by using more accurate instrumentation to calculate the reactor thermal power.
Because the maximum power level of a nuclear plant is a licensed limit, the NRC must review and approve a proposal to raise the licensed power level under the license amendment process. The LAR should include a justification for the reduced power measurement uncertainty to support the proposed power uprate.
The licensee developed the format of their submittal for the proposed power uprate based on the guidance of Regulatory Issue Summary (RIS) 2002-03, "Guidance on the Content of Measurement Uncertainty Recapture Power Uprate Applications," dated January 31,2002 and an approved topical report - ER-157(P-A) Revision 8 and Revision 8 Errata, "Supplement to Cal don Topical Report ER-80P: Basis for Power Uprates with an LEFM Check or an LEFM CheckPlus System," (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102950246). The NRC staff is evaluating the LAR using the provisions outlined in RIS 2002-03 as guidance.
Request for Additional Information
- 20. Engineering Report ER-800, Revision 1 (ADAMS Accession No. ML111790063),
contains several appendices labeled "A1, A2, A3, A4, & AS." These appendices contain detailed calculations, the results of which appear to be summarized in Appendix C, Table I. The NRC staff is having trouble identifying the equations in the approved topical report that correspond to the calculation in these appendices.
In order to confirm implementation please provide a detailed and explicit cross reference
-6 between the June 23, 2011, letter (ADAMS Accession No. ML111790030), Attachment Sa, (ADAMS Accession No, ML111790063) and the associated approved topical report equations (i.e., between ER-SOO Revision 1, Appendix A.1, and ADAMS Accession No. ML102950246).
- 21. Please confirm that the assumptions listed in Cameron Caldon Ultrasonics Engineering Report No. ER-157(P-A} Revision S and Revision S Errata (ADAMS Accession No. ML102950246), Appendix A, are valid for the Byron and Braidwood application.
- 23. Regulatory Guide 1.105, Revision 3, "Setpoints for Safety-Related Instrumentation,"
dated December 1999, describes a method for combining individual uncertainty terms in quadrature; this method assumes that the individual term each meet the 95/95 criteria.
Please describe how individual uncertainty term meets the 95/95 criteria.
- 24. Table I, "Reconciliation of Byron Unit 1 Nuclear Generating Station Uncertainties with Cameron Reports," of Appendix C (page 5) of Cameron Engineering Report ER-SOO Revision 1 (ADAMS Accession No. ML111790063) was compared with Table A-1, "Representative Thermal Power Uncertainties for a Total Feedwater Flow Measurement in a PWR or BWR Using Chordal LEFM Check and LEFM CheckPlus," of ER-157(P-A)
Revision S and Revision S Errata (ADAMS Accession No. ML102950246).
The Byron document seems to misquote the numbers in the approved topical report in some places, for example:
Table I identifies the ER-157P value for the Hydraulics Profile Factor as being "+/
0.25%" while the value in ER-157{P-A} Rev.S And Rev.SErrata is "+/- 0.22%."
Table I identifies the ER-157P value for the Time Measurements as being "+/
0.05%" while the value in ER-157(P-A) Rev.S And Rev.SErrata is "+/- 0.06%."
The Byron document also seems to indicate that in some cases the Byron Unit 1 system is credited as being better than the bounding topical report, for example:
Table I identifies the Byron Unit 1 value for the Subtotal mass Flow Uncertainty as being "+/- 0.26%" while the value in ER-157{P-A) Rev.S And Rev.SErrata is "+/
0.2S%."
Table I identifies the Byron Unit 1 value for the Feedwater Density and Feedwater Enthalpy as being "+/- 0.14%" while the value in ER-157{P-A) Rev.S And Rev.8Errata is "+/- 0.15%."
Please explain.
ML11262A161 I~CE LPL3-2/PM LPL3-2/LA LPL3-2/BC LPL3-2/PM NAME NDiFrancesco SRohrer JZimmerman i NDiFrancesco DATE 10106/11 1010611 10/11111 "11