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MONTHYEARML13310B9292013-12-0606 December 2013 Summary of Meeting with Constellation Energy Group, Inc., to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During ... Project stage: Meeting RS-15-091, Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2015-03-31031 March 2015 Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink Project stage: Response to RAI ML15232A5892015-09-14014 September 2015 Regulatory Audit Report for the June 11, 2015 Audit in Support of the Ultimate Heat Sink License Amendment Request Project stage: Other RS-15-266, Response to Request for Additional Information Regarding Request for a License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink.2015-10-0909 October 2015 Response to Request for Additional Information Regarding Request for a License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink. Project stage: Response to RAI ML15299A0132015-10-21021 October 2015 NRR E-mail Capture - (External_Sender) 1 of 2: Final Report: Five Year Post-construction Monitoring of the Unionid Community Near Braidwood Station Kankakee River Discharge Project stage: Request ML15322A3172015-11-18018 November 2015 Record of Decision Project stage: Request ML15314A8142015-11-30030 November 2015 NUREG-1437, Suppl 55, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Braidwood Station, Units 1 and 2 Final Report. Project stage: Acceptance Review RS-16-049, Supplemental Information Regarding Request for a License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink.2016-02-12012 February 2016 Supplemental Information Regarding Request for a License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink. Project stage: Supplement ML16181A0072016-07-18018 July 2016 Environmental Assessment and Finding of No Significant Impact Related to Ultimate Heat Sink Modification Project stage: Other 2015-11-30
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Category:Audit Report
MONTHYEARML19253A9632019-09-30030 September 2019 TSTF505 LAR Audit Summary ML19219A1912019-08-0707 August 2019 NON-PROPRIETARY, Regulatory Audit Summary Regarding License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies ML15232A5892015-09-14014 September 2015 Regulatory Audit Report for the June 11, 2015 Audit in Support of the Ultimate Heat Sink License Amendment Request ML15134A4592015-05-27027 May 2015 Report for the Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML14141A3062014-06-0505 June 2014 Audit of the Licensee'S Managment of Regulatory Commitments ML14050A3042014-03-14014 March 2014 Scoping and Screening Methodology Audit Report Regarding the Byron Station, and Braidwood Station, Units 1 and 2, LRA ML14072A3692014-03-13013 March 2014 AMP Audit Enclosure (3) ML13225A5922013-12-17017 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13312A3172013-12-13013 December 2013 Audit Trip Report SAMA ML1029101822010-10-21021 October 2010 Audit of the Licensee'S Management of Regulatory Commitments ML0720003432007-07-27027 July 2007 Audit of the Licensee'S Management of Regulatory Commitments 2019-09-30
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MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case ML23321A0442023-11-17017 November 2023 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 ML23234A2462023-08-25025 August 2023 Confirmation of Initial License Examination IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23110A1152023-06-12012 June 2023 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter) RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23132A0472023-05-12012 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ML23130A0072023-05-10010 May 2023 Submittal of Core Operating Limits Report Cycle 24, Rev. 16 IR 05000456/20230012023-05-0808 May 2023 Integrated Inspection Report 05000456/2023001 and 05000457/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23118A0202023-04-28028 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML23095A1292023-04-0505 April 2023 Steam Generator Tube Inspection Report for Refueling Outage 23 ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations 2024-02-02
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Mr. Bryan C. Hanson Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 14, 2015 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: REGULATORY AUDIT REPORT FOR THE JUNE 11, 2015, AUDIT IN SUPPORT OF THE ULTIMATE HEAT SINK LICENSE AMENDMENT REQUEST (TAC NOS. MF4671 AND MF4672) Dear Mr. Hanson: By application dated August 19, 2014, Exelon Generation Company, LLC (EGC) submitted a license amendment request (LAR), (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14231A902), to modify the technical specifications for Braidwood Station, Units 1 and 2. Specifically, the change proposed would revise the surveillance requirement (SR) 3.7.9.2 temperature limit for the cooling water supplied to the plant from the ultimate heat sink. EGC requested to replace the existing SR limit of s; 100 °F with a new SR limit of s; 102 °F. To support the U.S. Nuclear Regulatory Commission (staff evaluation of this LAR, the NRC staff performed a regulatory audit at Braidwood Station in Braceville, Illinois, on June 11, 2015.
B. Hanson -2 -If you have any questions regarding the enclosed audit report, please contact me at (301) 415-6606. Docket No. STN 50-456 and STN 50-457 Enclosure: Audit Report cc w/encl: Distribution via Listserv Sincerely, oel S. Wiebe, Senior Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Background
REGULATORY AUDIT REPORT IN SUPPORT OF THE ULTIMATE HEAT SINK LICENSE AMENDMENT REQUEST BRAIDWOOD STATION. UNITS 1 AND 2 DOCKET NOS. STN 50-456 AND STN 50-457 By application dated August 19, 2014, Exelon Generation Company, LLC (EGC) submitted a license amendment request (LAR) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14231A902), to modify the technical specifications (TSs) for Braidwood Station, Units 1 and 2. Specifically, the change proposed would revise the surveillance requirement (SR) 3.7.9.2 temperature limit for the cooling water supplied to the plant from the ultimate heat sink (UHS). EGC requested to replace the existing SR limit of s 100 °F with a new SR limit of s 102 °F. In an email dated March 24, 2015 (ADAMS Accession No. ML 15084A018), the U.S. Nuclear Regulatory Commission (NRC) staff requested additional information (RAI), which the licensee provided in its submittal dated April 30, 2015 (ADAMS Accession No. ML 15120A396). In this letter the licensee identified the model information for the precision temperature instruments used to determine the UHS temperature. In addition, the submittal identified the methodology that was used to calculate the overall uncertainty of 0.07 °F. To support its safety evaluation, the NRC staff conducted an audit at Braidwood Station in Braceville, Illinois, on June 11, 2015. The purpose of this audit was to: (1) observe the implementation of the procedure for monitoring the UHS temperature using the precision instrument, and (2) verify the uncertainties and methodology used to calculate UHS temperature uncertainty. The NRC audit participants: Dan Warner, NRR/DE/EICB Joel Wiebe, Senior Project Manager, NRR/DORL EGC personnel contacted: Murtaza Abbas, Senior Regulatory Specialist Jessica Krejcie, Corporate Licensing Engineer Tony Casares, Equipment Operator Anne Mathews, Operations Field Supervisor Enclosure
-2 -Summary 1. Methodology to calculate overall instrument uncertainty. In the RAI response, the licensee stated they used Calculation BRW-02-0107-1, Revision 0, "M&TE (Measurement and Test Equipment) Uncertainty Using Hart Scientific Thermometer for Measurement of Essential Service Water Discharge Header Temperature," to calculate the overall instrument uncertainty. Calculation BRW-02-0107-1, Revision 0, was prepared in accordance with Exelon Standard BES-EIC-20.04. The NRC staff reviewed this calculation and observed the following:
- The uncertainties used were identified to correspond to the uncertainty values found in the data sheets and appear to be appropriately applied.
- The calculation used the square root sum of the squares (SRSS) methodology to combine the random errors and then algebraically added the non-random terms. This resulting number was combined using SRSS with the reading error to produce the final overall uncertainty. The methodology appears to be appropriately applied. 2. Procedure for monitoring the UHS temperature using the precision instrument. During the audit, the NRC staff reviewed the following procedures to determine how the licensee will use the precision thermometer and thermistor probe:
- Procedures 1 BwOSR 0.1-1,2,3, "Unit One -Modes 1, 2, and 3 Shiftly and Daily Operating Surveillance,"
- 1 BwOSR 0.1-4, "Unit One -Mode 4 Shiftly and Daily Operating Surveillance,"
- 2BwOSR 0.1-1,2,3, "Unit Two -Modes 1, 2, and 3 Shiftly and Daily Operating Surveillance," and
- 2BwOSR 0.1-4, "Unit Two -Mode 4 Shiftly and Daily Operating Surveillance." The NRC staff observed EGC personnel implement the procedures listed above for taking precision temperature readings at the discharge of two separate Service Water (SX) pumps. These procedures provide the following approach to monitoring the UHS temperature.
- Control room has indication for the temperatures at the discharge of the SX Pumps. If any of the indications for an operating SX pump exceeds 97 °F, then the temperature must be obtained using the precision temperature instrumentation. At this point, an operator is sent to the discharge of the SX pumps to measure the temperature using the precision thermometer and thermistor probe.
- At each SX Pump, the thermometer and thermistor are removed from their case along with a visual guide that shows how to set up the equipment. Once the
-3 -thermometer and probe are set up, a spare thermowell is used to record the temperature at the SX Pump Discharge.
- The equipment operator identified that in circumstances where the temperatures are approaching the TS values, operators will be stationed at the discharge of the SX pumps to take temperatures as often as every 15 minutes. The procedures were clear and easy to follow for monitoring the UHS temperature. The NRC staff determined that the use of the thermometer and thermister probe was consistent with precision instrument measurement techniques and licensee procedures. There were no open items identified as a result of this audit.
B. Hanson -2 -If you have any questions regarding the enclosed audit report, please contact me at (301) 415-6606. Docket No. STN 50-456 and STN 50-457 Enclosure: Audit Report cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC RidsNrrPMBraidwoodResource RidsAcrsAcnw_MailCTR Resource RidsRgn3MailCenter Resource ADAMS Accession No.: ML 15232A589 OFFICE LPL3-2/PM LPL3-2/LA NAME JWiebe SRohrer DATE 8/24/15 9/1/15 Sincerely, IRA! Joel S. Wiebe, Senior Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LPL3-2 R/F LPL3-2/BC TTate 9/14/15 RidsNrrDorllpl3-2 Resource RidsNrrLASRohrer Resource RidsNrrDorlDpr Resource LPL3-2/PM JWiebe 9 /14/15 OFFICIAL RECORD COPY