|
---|
Category:Letter
MONTHYEARML24289A0152024-10-21021 October 2024 Review of the Fall 2023 Steam Generator Tube Inspection Report 05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024 Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary IR 05000336/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only) ML24281A1102024-10-0707 October 2024 Requalification Program Inspection 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24248A2272024-09-0404 September 2024 Operator Licensing Examination Approval ML24240A1532024-09-0303 September 2024 Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24221A2872024-08-0808 August 2024 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) 05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report ML24088A3302024-04-0404 April 2024 Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel IR 05000336/20240112024-04-0101 April 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011 ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification 2024-09-04
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024 Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications 05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications 05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications 05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML23334A1522023-11-30030 November 2023 Auxiliary Feedwater Control Valve Failure Resulting in a Condition Prohibited by Technical Specifications 05000423/LER-2019-0012020-02-13013 February 2020 LER 2019-001-00 for Millstone Power Station Unit 3 Regarding Plant Shutdown Required by Technical Specifications, Emergency Diesel Generator Exceeded Allowed Outage Time 05000423/LER-2017-0012017-03-20020 March 2017 Loss of Safety Function - Secondary Containment, LER 17-001-00 for Millstone, Unit 3 Regarding Loss of Safety Function - Secondary Containment 05000336/LER-2016-0022016-09-20020 September 2016 Manual Reactor Trip Due to Loss of Two Circulating Water Pumps, LER 16-002-00 for Millstone Power Station Unit 2 Regarding Manual Reactor Trip Due Loss Of Two Circulating Water Pumps 05000423/LER-2016-0052016-08-0909 August 2016 Technical Specification Required Shutdown and Manual Reactor Trip Due to Steam Generator Level Oscillation, LER 16-005-00 for Millstone Power Station Unit 3 RE: Technical Specification Required Shutdown and Manual Reactor Trip Due to Steam Generator Level Oscillation 05000423/LER-2016-0042016-07-13013 July 2016 Manual Reactor Trip Due to Low Hydrogen Gas Pressure In Main Generator, LER 16-004-00 for Millstone Power Station Unit 3 RE: Manual Reactor Trip Due to Low Hydrogen Gas Pressure In Main Generator 05000336/LER-2016-0012016-06-27027 June 2016 Turbine Driven Auxiliary Feedwater Putnp Room HELB Door Left Open, LER 16-001-00 for Millstone Power Station Unit 2 RE: Turbine Driven Auxiliary Feedwater Pump Room HELB Door Left Open 05000423/LER-2016-0032016-06-0808 June 2016 Loss of Safety Function- Supplementary Leak Collection and Release System, LER 16-003-00 for Millstone Power Station, Unit 3, Regarding Loss of Safety Function-Supplementary Leak Collection and Release System 05000423/LER-2016-0022016-03-23023 March 2016 Feedwater Isolation Signal Defeated Due to Wiring Error, LER 16-002-00 for Millstone Power Station Unit 3 Regarding Feedwater Isolation Signal Defeated Due to Wiring Error 05000423/LER-2016-0012016-03-16016 March 2016 Automatic Reactor Trip on Reactor Coolant System Low Flow Due to Loss of 'B' Reactor Coolant Pump, LER 16-001-00 for Millstone Power Station Unit 3, Regarding Automatic Reactor Trip on Reactor Coolant System Low Flow Due to Loss of 'B' Reactor Coolant Pump 05000336/LER-2015-0032016-01-0707 January 2016 Valid Actuation of the Reactor Protection System, LER 15-003-00 for Millstone, Unit 2, Regarding Valid Actuation of the Reactor Protection System ML0925900552009-09-0808 September 2009 Special Report for Seismic Instrumentation ML0719302812007-04-11011 April 2007 Final ASP Analysis- Millstone (LER 336/06-002) ML0622802402006-08-0808 August 2006 Special Report for Inoperable Radiation Monitor 2024-09-26
[Table view] |
LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications |
Event date: |
|
---|
Report date: |
|
---|
3362024001R00 - NRC Website |
|
text
Dominion En ergy Nu c lear Conn ecticut, In c. ~ Dominion M illston e Power Sta tion...@ ;+
31 4 Rop e Ferry Roa d, W a te rfo rd, CT 0638 5 Energy DominionEnergy.c om =#
U. S. Nuclear Regulatory Commission Serial No.: 24-191 Attention: Document Control Desk MPS Lic/JNP RO Washington, DC 20555 Docket No.: 50-336 JUN 1 0 2024 License No.: DPR-65
DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2 LICENSEE EVENT REPORT 2024-001-00
CONTROL ROOM AIR CONDITIONING UNIT INOPERABLE DUE TO REFRIGERENT OVERCHARGE RESULTING IN A CONDITION PROHIBITED BY TECHNICAL SPECIFICATIONS
This letter forwards Licensee Event Report (LER) 2024- 001-00, documenting a condition that was discovered at Millstone Power Station Unit 2 (MPS2) on Ap ril 14, 2024. This LER is being submitted pursuant to 10 CFR 50. 73 (a)(2)(i)(B) as a condition. prohibited by technical specifications.
There are no regulatory commitments contained in this letter or its enclosure.
Should you have any questions, please contact Mr. Dean E. Rowe, Manager of Emergency Preparedness and Licensing fo r Millstone Power Station, at (860) 444-5292.
Since rely,
\\
Michael J. O'Connor Site Vice President - Millstone
Enclosure: LER 336/2024-001 - 00 Serial No.24-191 Docket No. 50-336 Licensee Event Report 2024-001-00 Page 2 of 2
cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road, Suite 102, King of Prussia, PA 19406-1415.
R. V. Guzman NRC Project Manager Millstone Units 2 and 3 U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738
NRC Senior Resident Inspector Millstone Power Station Serial No.24-191 Docket No. 50-336 Licensee Event Report 2024-001-00
ATTACHMENT
LICENSEE EVENT REPORT 2024-001-00
CONTROL ROOM AIR CONDITIONING UNIT INOPERABLE DUE TO REFRIGERENT OVERCHARGE RES UL TING IN A CONDITION PROHIBITED BY TECHNICAL SPECIFICATIONS
MILLSTONE POWER STATION UNIT 2 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
Abstract
On April 14, 2024, at 1407 hours0.0163 days <br />0.391 hours <br />0.00233 weeks <br />5.353635e-4 months <br /> while Millstone Power Station Unit 2 was in Mode 1 at 100 percent reactor power, it was discovered that the 'A' Control Room Air Conditioning (CRAC) compressor assembly was not running following an increase in temperatures in the control room. Troubleshooting determined that the refrigerant in the 'A' CRAC was overcharged following the replacement of a leaking pressure switch. Following trimming of the refrigerant charge for the 'A' CRAC compressor, the 'A' Control Room Emergency Ventilation system was declared operable on April 20, 2024 at 2025 hours0.0234 days <br />0.563 hours <br />0.00335 weeks <br />7.705125e-4 months <br />. A historical review determined that this condition existed starting on April 10, 2024, and therefore existed for greater than the 7-day allowed outage time of the Technical Specification. This report is being submitted as a condition that was prohibited by plant Technical Specifications pursuant to 10 CFR 50.73(a)(2)(i)(B).
I
On April 14, 2024, at 1407 hours0.0163 days <br />0.391 hours <br />0.00233 weeks <br />5.353635e-4 months <br /> while Millstone Unit 2 was in Mode 1 operating at 100 percent reactor power, Operations entered Technical Specification Action Statement (TSAS) 3.7.6.1.a due to rising temperatures in the control room. A walk down of the 'A' Control Room Air Conditioning (CRAC) compressor assembly, M2F22A, found the compressor not running. Troubleshooting by station personnel with vendor support determined that the compressor was in an overcharged condition. Following trimming of the refrigerant charge, the 'A' CRAC compressor was returned to service. Operations declared the 'A' Control Room Emergency Ventilation (CREV) system OPERABLE on April 20, 2024, at 2025 hours0.0234 days <br />0.563 hours <br />0.00335 weeks <br />7.705125e-4 months <br />.
The 'A' CRAC compressor assembly (Trane 2F5C88) is part of the control room emergency ventilation system. The OPERABILITY of the control room emergency ventilation system as described in Technical Specifications (TS) 3.7.6.1 ensures that the ambient temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system, and the control room will remain habitable for Operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room.
For all postulated design basis accidents, the radiation exposure to personnel occupying the control room shall be 5 rem total effective dose equivalent (TEDE) or less consistent with the requirements of 10 CFR 50.67.
In Modes 1, 2, 3, and 4, Technical Specifications (TS) 3.7.6.1 "Control Room Emergency Ventilation System," requires two independent Control Room Emergency Ventilation Trains to be OPERABLE. If one Control Room Emergency Ventilation Train is inoperable, it must be restored to OPERABLE within 7 days or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
A historical review was performed on the 'A' CRAC compressor. On April 7, 2024, at 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br />, Operations entered the 7-day Technical Specification Action Statement (TSAS) 3.7.6.1.a due to the compressor not running. Maintenance determined that there was no refrigerant in the compressor assembly due to a leaking pressure switch. The pressure switch was replaced, and on April 10, 2024, at 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br />, the 'A' CRAC compressor assembly was charged with 200 lbs. of refrigerant, chlorodifluoromethane (R-22). Following successful completion of the surveillance test, the 'A' CREV system was placed into service, and Operations exited the TSAS on April 10, 2024, at 2340 hours0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.9037e-4 months <br />.
The historical review determined that the compressor overcharge condition was present from April 10, 2024, at 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br /> until April 20, 2024, at 2007 hours0.0232 days <br />0.558 hours <br />0.00332 weeks <br />7.636635e-4 months <br />. This condition would have prevented reliable operation of the 'A' CRAC, and it would not have met its required mission time. This condition existed for a period greater than the 7-day allowed outage time, which is reportable in accordance with 10 CFR 50.73(a)(2)(i)(B), "any operation or condition which was prohibited by the plant's Technical Specifications." From April 7 to April 20, 2024 the 'B' CRAC was functional, and the
'B' Control Room Emergency Ventilation (CREV) was OPERABLE.
CAUSE
The overcharge condition in the ' A' CRAC compressor assembly following the replacement of the leaking pressure switch caused the compressor to run inconsistently. The use of an uncontrolled job aid indicated that the compressor should be charged to 200 lbs., which led to the overcharged condition.
ASSESSMENT OF SAFETY CONSEQUENCES
Operation of the Control Room Emergency Ventilation (CREV) System is credited to limit dose to personnel in the control room to the 10 CFR 50.67 limit of 5 rem Total Effective Dose Equivalent (TEDE), and to maintain a suitable environment for personnel and safety related equipment in the control room. The CREV system is made up of two subsystems : control room air conditioning (CRAC) and control room filtration system (CRFS). During this period, with the unit in Mode 1, 'A' CREV was declared inoperable because the ' A' CRAC was unable to perform its cooling function.
This condition is considered to be of low safety significance based upon the availability of the 'B' CREV for the entire period. Per Millstone Power Station Unit 2 (MPS2) FSAR section 9.9.11.2.1, the CRAC subsystem consists of two full capacity, independent air handling and mechanical refrigeration subsystems with the exception of some common ductwork and dampers. Therefore, 'B' CRAC was capable of fulfilling the cooling requirement inside the control room.
MPS2 FSAR Chapter 14 dose analyses only credit one train of CRFS for mitigation of radiological consequences and calculated control room doses are below the 10 CFR 50.67 limit. Based on the discussion above, the safety functions of the CREV system were met with 'B' CREV operable.
CORRECTIVE ACTIONS
The refrigerant charge was trimmed from the 'A' CRAC compressor. This allowed the ' A' CREV system to be restored to OPERABLE on April 20, 2024, at 2025 hours0.0234 days <br />0.563 hours <br />0.00335 weeks <br />7.705125e-4 months <br />. Refrigerant charge values for the CREV system will be captured in station procedures. Additional corrective actions will be taken in accordance with the station ' s corrective action program.
PREVIOUS OCCURRENCES
There have been no similar events related to refrigerant levels causing a Control Room Emergency Ventilation system to be inoperable for a period longer than the Technical Specification Action Statement allowed outage time of 7 days at Millstone Power Station over the last three years.
In 2012, maintenance questioned the use of 200 lbs. of refrigerant following completion of maintenance on the 'A' CRAC:
Engineering performed an evaluation and determined the refrigerant charge, but that information was never incorporated into the maintenance procedure for charging the compressor. The maintenance work performed in 2012 did not cause the Control Room Emergency Ventilation system to be inoperable for a period longer than Technical Specification Action Statement allowed outage time of 7 days.
ENERGY IN DUSTRY IDENTIFICATION SYSTEM (EIIS) CODES
VI Control Building/Control Complex Environmental Control System
CMP Compressor
NRG FOR M 366A (0 4-02-2024) Page 3 of 3