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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
[Table view] Category:Letter
MONTHYEARRS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024 Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality ML24291A0012024-10-17017 October 2024 Submittal of Core Operating Limits Report, Cycle 25 RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - 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 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary 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 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) ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit 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 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 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) 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 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 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 ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) 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 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) ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 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) 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 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 RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24094A2692024-04-0303 April 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report, WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear Westinghouse Domestic Fleet Operational Projections RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24057A0372024-03-26026 March 2024 Proposed Alternative from Certain Requirements Contained in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML24067A3252024-03-0707 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites ML24066A0122024-03-0606 March 2024 Operator Licensing Examination Approval Braidwood Station, Units 1 and 2, March 2024 IR 05000456/20244012024-03-0505 March 2024 Cyber Security Inspection Report 05000456/2024401 and 05000457/2024401 (Public) IR 05000456/20230062024-02-28028 February 2024 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2023006 and 05000457/2023006) ML24057A3022024-02-26026 February 2024 Regulatory Conference Supplemental Information ML24047A2382024-02-20020 February 2024 Regulatory Conference to Discuss Risk Associated with 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Leak RS-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators IR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 2024-09-23
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 14, 2015 Mr. Bryan C. Hanson Senior Vice President 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. ML14231A902), 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 If you have any questions regarding the enclosed audit report, please contact me at (301) 415-6606.
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 Docket No. STN 50-456 and STN 50-457
Enclosure:
Audit Report cc w/encl: Distribution via Listserv
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
Background
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. ML14231A902), 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. ML15084A018), 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. ML15120A396). 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
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 1BwOSR 0.1-1,2,3, "Unit One - Modes 1, 2, and 3 Shiftly and Daily Operating Surveillance,"
- 1BwOSR 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
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.
ML15232A589 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC LPL3-2/PM NAME JWiebe SRohrer TTate JWiebe DATE 8/24/15 9/1/15 9/14/15 9 /14/15