ML25037A225
| ML25037A225 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 02/06/2025 |
| From: | Robert Ruiz NRC/RGN-III/DORS/RPB1 |
| To: | Rhoades D Constellation Energy Generation |
| References | |
| IR 2024004 | |
| Download: ML25037A225 (1) | |
Text
David Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer (CNO)
Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CLINTON POWER STATION - INTEGRATED INSPECTION REPORT 05000461/2024004
Dear David Rhoades:
On December 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Clinton Power Station. On January 24, 2025, the NRC inspectors discussed the results of this inspection with Norha Plumey, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violations or the significance or severity of the violations documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at Clinton Power Station.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; and the NRC Resident Inspector at Clinton Power Station.
February 6, 2025
D. Rhoades 2
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Robert Ruiz, Chief Reactor Projects Branch 1 Division of Operating Reactor Safety Docket No. 05000461 License No. NPF-62
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Ruiz, Robert on 02/06/25
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available OFFICE RIII RIII NAME NShah:gmp RRuiz DATE 02/06/2025 02/06/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
05000461 License Number:
NPF-62 Report Number:
05000461/2024004 Enterprise Identifier:
I-2024-004-0055 Licensee:
Constellation Nuclear Facility:
Clinton Power Station Location:
Clinton, IL Inspection Dates:
October 01, 2024, to December 31, 2024 Inspectors:
J. Kutlesa, Senior Emergency Preparedness Inspector A. Muneeruddin, Resident Inspector J. Murphy, Illinois Emergency Management Agency - Resident Inspector J. Nance, Operations Engineer J. Steward, Senior Resident Inspector Approved By:
Robert Ruiz, Chief Reactor Projects Branch 1 Division of Operating Reactor Safety
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Clinton Power Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. A licensee-identified non-cited violation is documented in report section: 71111.15.
List of Findings and Violations Surveillance Test Procedure Inappropriate to the Circumstances Resulting in RCIC Turbine Trip Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000461/2024004-01 Open/Closed
[H.1] -
Resources 71111.15 A self-revealed Green finding and associated non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures and Drawings, was identified for the licensees failure to provide a procedure of the appropriate type to the circumstances.
Specifically, the procedure lacked the required specificity and granularity to prevent the RCIC turbine from tripping on low suction pressure during routine high-pressure operability surveillance testing.
Additional Tracking Items Type Issue Number Title Report Section Status LER 05000461/2023-002-01 LER 2023-002-01 for Clinton Power Station, Unit 1, Reactor Core Isolation Cooling Inoperable Prior to Mode Change 71153 Closed LER 05000461/2023-002-00 LER 2023-002-00 for Clinton Power Station, Unit 1, Reactor Core Isolation Cooling System Inoperable Prior to Mode Change 71153 Closed
3 PLANT STATUS Unit 1 began the inspection period at rated thermal power (RTP). On October 15, 2024, Unit 1 lowered power slightly to 98.5 percent RTP to support three condensate pump operation during the planned work to replace the motor for condensate pump B. Following return of condensate pump B to service on October 19, 2024, the unit was returned to RTP. On November 23, 2024, Unit 1 lowered reactor power to 77 percent RTP to perform a planned control rod sequence exchange, main turbine control valve testing, and scram time testing. On November 24, 2024, the unit was returned to RTP and continued to operate at or near RTP for the remainder of the inspection period.
INSPECTION SCOPES Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY 71111.01 - Adverse Weather Protection Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems, including the 345 kV and 138 kV switchyard from impending severe weather with expected temperatures below freezing on December 2 and 9, 2024.
71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1) division 3 diesel generator on October 9, 2024
4 71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
(1)
Fire Areas CB-6(b) and CB-6(c), control building, elevation 800', operations support center (OSC) and technical support center (TSC) on November 6, 2024 (2)
Fire Area CB-7, control building, elevation 802', breathing air bottle corridor on November 6, 2024 (3)
Fire Area F-1(p), fuel building, elevations 755'-781', fuel handling floor and balconies on November 19, 2024 (4)
Fire Area C-2, containment building, elevations 737'-828' on December 23, 2024 71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance Requalification Examination Results (IP Section 03.03) (1 Sample)
(1)
The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered between September 4, 2024, and November 21, 2024.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
(1 Sample)
(1)
The inspectors observed and evaluated licensed operator performance in the control room during a planned downpower to 77 percent RTP for turbine valve testing, control rod scram time testing, and control rod sequence exchange on November 23, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed and evaluated licensed operator requalification training on October 22, 2024.
71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
(1) failure of standby gas treatment 'A' main inlet damper, 0VG01YA, per Action Request (AR) 4704162 on December 17, 2024 (2) failure of division 2 rod control and information system power supply per Work Order (WO) 5586202 on December 12, 2024
5 71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
(1) elevated online risk due to planned maintenance windows for division 3 diesel generator, shutdown service water, and high-pressure core spray on October 3, 2024 71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1) reserve auxiliary transformer 'B' mechanically switched capacitor trip per AR 4809148 on October 17, 2024 (2) unexpected valve positions during division 2 shutdown service water flow balance per AR 4798179 on October 29, 2024 (3) division 1 diesel generator turbocharger impeller blade indications per ARs 4800455 and 4800456 on November 5, 2024 (4)
RCIC turbine trip on low suction pressure per AR 4818766 on December 19, 2024 (5) unexpected main control room alarm 5011-8E, emergency reserve auxiliary transformer, mechanically switched capacitor trip per AR 4821069 on December 30, 2024 71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
(1 Partial)
The inspectors evaluated the following temporary or permanent modifications:
(1)
(Partial)
RCIC temporary modification per Engineering Change Request (ECR) 465326 and AR 4818766 to disable the low suction pressure trip on November 26, 2024. Inspectors intend to complete this partial sample in NRC Integrated Inspection Report 05000461/2025001.
6 71111.24 - Testing and Maintenance of Equipment Important to Risk The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (4 Samples)
(1) division 3 diesel generator operability run following a planned maintenance window per WO 557881 on November 8, 2024 (2) residual heat removal pump 'A' and associated valve operability following a planned maintenance window per WO 5570437 on November 19, 2024 (3) 1WX020, reactor water cleanup backwash outboard isolation valve operability following a planned maintenance window per WO 5571419 on November 27, 2024 (4) division 1 nuclear system protection system (NSPS) inverter trouble post-maintenance test following repairs per WO 5606829-02 on December 17, 2024 Surveillance Testing (IP Section 03.01) (2 Samples)
(1) diesel generator 1C 24-hour run and hot restart - operability per Clinton Power Station (CPS) 9080.14 on November 5, 2024 (2)
RCIC high-pressure operability checks per CPS 9054.01C002 on December 6, 2024 71114.04 - Emergency Action Level and Emergency Plan Changes Inspection Review (IP Section 02.01-02.03) (1 Sample)
(1)
The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes.
EP-AA-1003, Constellation Radiological Emergency Plan Annex for Clinton Station, Revision 30 EP-AA-1003, Addendum 1, Clinton Station On-Shift Staffing Technical Basis, Revision 3 EP-AA-1003, Addendum 2, Clinton Evacuation Time Estimates, Revision 2 EP-AA-120-1001, CPS Emergency Plan Revised for IPAWS Implementation, Evaluation No. 23-35 This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation Additional Drill and/or Training Evolution (2 Samples)
The inspectors evaluated:
(1) an emergency response organization drill involving the operations requalification crew in the simulator control room, operations support center (OSC), and technical support center (TSC) on October 24, 2024 (2) an emergency response organization drill involving the operations requalification crew in the simulator control room, OSC, and TSC on November 7, 2024
7 OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)
(1)
Unit 1 (October 1, 2023, through September 30, 2024) 71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1) review and assessment of the stations corrective actions to address a negative trend and degradation of the site maintenance and test equipment program documented in AR 4816900 on December 31, 2024 (2) review and assessment of the station's corrective actions following a plant shutdown due to an increased drywell leakage trend as documented in AR 4681106 on December 31, 2024 71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02) (1 Sample)
(1)
The inspectors reviewed the licensees corrective action program to identify potential trends observed in the pipe wall degradation of the shutdown service water system that might be indicative of a more significant safety issue on December 27, 2024.
71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensees event reporting determinations to ensure it complied with reporting requirements.
(1)
Licensee Event Reports (LERs) 2023-002-00 and 2023-002-01 for Clinton Power Station, Unit 1, Reactor Core Isolation Cooling System Inoperable Prior to Mode Change (ADAMS [Agencywide Document Access Management System] Accession Nos. ML24051A083 [LER 2023-002-00] and ML24270A035 [LER 2023-002-01]). The inspectors determined that the cause of the condition described in the LER was determined to be a performance deficiency; the conclusions of which are included in the Inspection Results Section. These LERs are closed.
8 INSPECTION RESULTS Surveillance Test Procedure Inappropriate to the Circumstances Resulting in RCIC Turbine Trip Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000461/2024004-01 Open/Closed
[H.1] -
Resources 71111.15 A self-revealed Green finding and associated non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures and Drawings, was identified for the licensees failure to provide a procedure of the appropriate type to the circumstances.
Specifically, the procedure lacked the required specificity and granularity to prevent the RCIC turbine from tripping on low suction pressure during routine high-pressure operability surveillance testing.
==
Description:==
On November 20, 2024, at 1203 with Unit 1 at full power, the RCIC turbine was started per CPS 9054.01C002, RCIC(1E51-C001) High Pressure Operability Checks, Revision 10, for routine surveillance testing. The test is performed on a quarterly frequency to verify operational readiness of the RCIC pump, turbine, and system valves and satisfies Technical Specification (TS) Surveillance Requirement (SR) 3.5.3.3, which demonstrates RCIC operability per TS 3.5.3, "RCIC System."
The procedure at step 8.4.9, directs the operator to open 1E51-F045, RCIC turbine steam supply shutoff valve. This step is preceded by a CAUTION statement which requires the operator to be aware of specific precautions and limitations during the performance of the next several steps, in particular, the following precaution states, Do not delay proceeding to step 8.4.10. Step 8.4.10 directs the operator to throttle open 1E51-F022, RCIC pump first test valve to storage tank, to an indicated flow of greater than 600 gpm. However, when operators began to throttle 1E51-F022 open, the RCIC turbine tripped on low suction pressure. At this point, the surveillance test was discontinued and RCIC was declared inoperable. Site engineering concluded that a low suction pressure develops if valve 1E51-F022 is not opened within 20 seconds after step 8.4.9. As stated above, the caution statement did not specify this time limit.
After troubleshooting and confirming the correct valve lineup, the licensee implemented an engineering change request (ECR) to disable the RCIC turbine trip on low suction pressure.
On November 21, 2024, 9054.01C002 was completed satisfactorily and RCIC was declared operable. Inspectors reviewed the approved ECR and identified no concerns.
Corrective Actions: Extent of Condition for the low-pressure coolant injection, low-pressure core spray, and high-pressure core spray pumps were reviewed for low suction pressure trips. Drafting and implementation of EC 643138, scheduled for approval and execution the first quarter of 2025. Procedure change request initiated to update 9054.01C002, specifically the Caution statement prior to step 8.4.9, to provide the specificity and granularity to ensure this section is performed consistently every performance.
Corrective Action References: AR 4818766
9 Performance Assessment:
Performance Deficiency: The inspectors determined that the failure to provide a procedure appropriate to the circumstance to perform RCIC high-pressure operability surveillance testing that ensured proper suction pressure to the RCIC pump was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Procedure Quality attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power.
Cross-Cutting Aspect: H.1 - Resources: Leaders ensure that personnel, equipment, procedures, and other resources are available and adequate to support nuclear safety.
Enforcement:
Violation: 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, requires, in part, that activities affecting quality be prescribed by documented procedures of a type appropriate to the circumstances and be accomplished in accordance with these procedures. The licensee established procedure CPS 9054.01C002, RCIC (1E51-C001)
High Pressure Operability Checks, Revision 10, as the implementing procedure for performing the surveillance test which demonstrates RCIC operability per TS 3.5.3., an activity affecting quality.
Contrary to the above, on November 20, 2024, the licensee failed to provide a procedure that was of a type appropriate to the circumstances. Specifically, procedure 9054.01C002 did not specify a timing requirement to sequence the opening of 1E51-F022 once the step to open 1E51-F045 was executed. Site-specific analysis concluded that a delay of greater than 20 seconds results in the trip of the RCIC turbine on low suction pressure. However, the CAUTION before step 8.4.9 simply stated, in part, Do not delay proceeding to step 8.4.10.
As a result of following the instructions as written, the RCIC turbine tripped on low suction pressure.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Licensee-Identified Non-Cited Violation 71111.15 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
10 Violation: Clinton Nuclear Power Station (CPS), Technical Specification (TS) Section 3.0, LCO [limiting condition for operation] Applicability, Subsection LCO 3.0.4, requires, in part that when an LCO is not met, entry into a mode or other specified condition in the applicability shall only be made when the associated actions to be entered permit continued operation in the mode or other specified condition in the applicability for an unlimited period of time.
TS 3.5.3 LCO requires the RCIC system to be operable in Mode 1, and Modes 2 and 3 with reactor steam dome pressure greater than 150 psig.
Contrary to the above, on October 9, 2023, during a unit startup following an outage, when CPS entered Mode 2 with steam dome pressure greater that 150 psig, the unit entered a TS 3.5.3 applicable mode when LCO 3.5.3 required actions were not met, and the associated actions of TS 3.5.3 did not permit continued operation in the mode for an unlimited period of time. In addition, the unit was placed in Mode 1 on October 10, 2023, with the RCIC system inoperable. RCIC was returned to operability on October 16, 2023.
Significance/Severity: Green. The inspectors determined the significance in accordance with the Significance Determination Process for Findings at Power, Inspection Manual Chapter (IMC) 0609, Appendix A, effective January 1, 2021. All questions in IMC 0609, Mitigating System Screening Questions, exhibit 2 were answered "No," so the issue screened to Green.
Corrective Action References: ARs 4708661 and 4725087 EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On January 24, 2025, the inspectors presented the integrated inspection results to Norha Plumey, Site Vice President, and other members of the licensee staff.
On December 16, 2024, the inspectors presented the emergency action level and emergency plan changes inspection results to Rachael Lorch, Emergency Preparedness Manager, and other members of the licensee staff.
11 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date AR 4813356 Sec ID: Camera 110 Deficient/Winter Concerns 10/30/2024 AR 4813384 Winter Readiness: Work Needs Scheduled on MPT A Cooling Fans 10/30/2024 AR 4816455 Winter Readiness: Heat Trace Tagged Out 11/10/2024 Corrective Action Documents AR 4819527 Winter Readiness Concern for MWPH Trailer Lines 11/24/2024 Drawings E-CLT6-T02-0SY01-1 Single Line Diagram 345KV Switchyard Clinton Power Station - Units 1 & 2 W
Miscellaneous Constellation Memo Site Certification for Winter Readiness 10/31/2024 3505.01 345 & 138KV Switchyard (SY) 25 MA-AA-716-026 Station Housekeeping/Material Condition Program 23 OP-AA-108-111-1001 Severe Weather and Natural Disaster Guidelines 30 SY-AA-101-146 Severe Weather Preparation and Response 4
71111.01 Procedures WC-AA-107 Seasonal Readiness 30 AR 4805616 1DG01KC Exciter Diode D3 Found Loose Connection 09/30/2024 Corrective Action Documents AR 4807223 Div 3 DG/SX SOW 4.0 Critique 10/06/2024 CPS 3506.01E001 Diesel Generator and Support Systems Electrical Lineup 18d CPS 3506.01V001 Diesel Generator and Support Systems Valve Lineup 13a 71111.04 Procedures CPS 3506.01V002 Diesel Generator and Support Systems Instrument Valve Lineup 11b CPS 1893.04M210 737 Containment: Prefire Plan 6b CPS 1893.04M220 755 Containment: Prefire Plan 5
CPS 1893.04M230 778 Containment: East Prefire Plan 5
CPS 1893.04M231 778 Containment: West Prefire Plan 5
71111.05 Fire Plans CPS 803 Containment: Prefire Plan 5
12 Inspection Procedure Type Designation Description or Title Revision or Date 1893.04M240 CPS 1893.04M250 828 Containment: Prefire Plan 6a CPS 1893.04M360 800 Control: Tech Support Center Prefire Plan 5b CPS 1893.04M361 800" Control: Operations Support Center Prefire Plan 5c CPS 1893.04M363 802' Control: Breathing Air Bottle Corridor Prefire Plan 5c CPS 1893.04M420 755 Fuel: Fuel Handling Floor Prefire Plan 4a CPS 1893.04M430 781 Fuel: West Balcony Prefire Plan 4c CPS 1893.04M431 781 Fuel: East Balcony Prefire Plan 2c 71111.11A Miscellaneous Email from Richard Tyler, Exam Author, Constellation Nuclear to James
- Nance, Operations Engineer, U.S.
NRC.
TQ-AA-150-F25 Rev 007, LORT Annual Exam Status Report - CPS 2024 Final Report 11/21/2024 Miscellaneous ESG-LOR-425 CPE Style OBE 2024 0
CPS 3005.01 Unit Power Changes 55 CPS 3304.01 Control Rod Hydraulic and Control (RD) 41 CPS 3304.02 Rod Control and Information System (RC&IS) 23d CPS 9031.06 Main Turbine Stop Valve and Combined Intermediate Valve Tests 37 CPS 9031.07 Main Turbine Control Valve Tests 36 71111.11Q Procedures CPS 9813.01 Control Rod Scram Time Testing 43a AR 4270633 New Hydramotor Failed During Prep Task 08/09/2019 71111.12 Corrective Action Documents AR 4704162 0VG01YA VG A Inlet Damper Indicated Closed 09/21/2023
13 Inspection Procedure Type Designation Description or Title Revision or Date Miscellaneous Engage Health AR 4704162 (a)(1) Determination 11/21/2024 Procedures ER-AA-320-1004 Maintenance Rule - (a)(1) and (a)(2) Requirements 3
WO 5402454 IMD TS&R 0VG004 Loop 09/22/2023 WO 5402454-02 OPS 0FCVG004 Stroke Damper 0VG01YA To Support Troubleshooting 09/22/2023 WO 5402454-03 EM 0VG01YA Troubleshoot Damper / Hydramotor 09/23/2023 WO 5402454-07 EM 0FZVG004 Install Replacement Hydramotor 09/25/2023 Work Orders WO 5402454-08 OP PMT 0VG01YA Damper 10/06/2023 AR 4806012 NRC Identified 1SF005A Handwheel on Floor 10/01/2024 Corrective Action Documents Resulting from Inspection AR 4806031 NRCID Issues 10/01/2024 ER-AA-600 Risk Management 7
ER-AA-600-1042 On-line Risk Management 13 OP-AA-108-117 Protected Equipment Program 7
WC-AA-101 On-line Work Control Process 33 71111.13 Procedures WC-AA-101-1006 On-line Risk Management and Assessment 4
Calculations VG-16 Standby Gas Treatment System Cooling Load 5B 4708908 RCIC Procedure Enhancement 10/11/2023 AR 1120272 1DG01KA: Minor Turbocharger Blade Impact Indications 09/30/2010 AR 4370466 1DG01KA Impeller Blade Impact Indications 09/18/2020 AR 4800455 1DG01KA 12 Cylinder Turbo Damage 09/09/2024 71111.15 Corrective Action Documents AR 4800456 1DG01KA 16 Cylinder Turbo Damage 09/09/2024 Corrective Action Documents Resulting from Inspection 4811237 Procedure Guidance needed for IRIS Event Reporting Updates 10/22/2024 E02-1AP03, Sheet 1 Electrical Loading Diagram, Clinton Power Station Unit 1 AD E02-1RI99, Sheet 015 Reactor Core Isolation Cooling System (RI), Reactor Core Iso Cooling Sys (NSPS) (1E51-1050)
Q 71111.15 Drawings E02-1RI99, Sheet 2
Reactor Core Isolation Cooling System (RI), Reactor Core Iso Cooling Sys (NSPS) (1E51-1050)
F
14 Inspection Procedure Type Designation Description or Title Revision or Date EC 632585 Division 1 Diesel Generator Turbocharger Impeller Blade Indications 1
Engineering Changes EC 642810 Sbgt Room Maximum LOCA/LOOP Temperature with no Room coolers 0
465407 138KV Voltage Transient during HPCS Pump Run on 12/2/24 and ERAT MSC Overvoltage Trip 12/06/2024 EC 642718 RAT MSC Trip 1A1 Bus Overvoltage Transient 0
Engineering Evaluations ECR 464247 0
EQ-CL044 Environmental Qualification Package ITT General Controls NH-90 Series Hydromotor Actuators (Safety Related) 26 ESOMS Operations Narrative Log Entries 10/14/2024 ESOMS Operations Narrative Log Entries 11/20/2024 OP-AA-108-118 RICT Record for ERAT MSC Trip of 12/2/2024 12/09/2024 RCIC Sections 5.4.6 and 7.4.1.1 Clinton Power Station Updated Safety Analysis Report 11 TS 3.8.1 Clinton Unit 1 Technical Specifications and Bases - AC Sources - Operating 10/17/2024 Miscellaneous USAR Chapters 8.2 and 8.3 Offsite and Onsite Power Systems 23 Operability Evaluations AR 4798179 Assignment 12 (OPDC)
Past Operability Determination 10/28/2024 3505.01 345 & 138 KV Switchyard (SY) 25 3505.04 ERAT Mechanically Switched Capacitor (MSC) Bank System 2
5007.05 Alarm Panel 5007 Annunciators - Row 5 31a 5010.05 Alarm Panel 5010 Annunciators - Row 5 27e 5011.08 Alarm Panel 5011 Annunciators - Row 8 31 5063.05 Alarm Panel 5063 Annunciators - Row 5 34 CPS 3505.01 345 KV & 138KV Switchyard 25 Procedures CPS 9082.01 Offsite Source Power Verification 42c Engineering Evaluations 465326 Engineering Change Request 11/21/2024 71111.18 Work Orders WO 5421341 11/21/2024
15 Inspection Procedure Type Designation Description or Title Revision or Date AR 4796050 1WX020 PCIV Closing Stroke Time Exceeded Limiting Value 08/22/2024 AR 4816841 1WX020 Performance Compromised due to Excessive Cycling 11/12/2024 AR 4817490 Replace 1WX020 During the Next Outage 11/14/2024 AR 4817498 Add Lubrication of RO2 Slider to PMRQ for 1WX020 11/14/2024 AR 4818576 Unexpected MCR Annunciator RCIC Pump Suction Pressure High 5063-1D 11/19/2024 AR 4818766 RCIC Turbine Trip During Startup 11/20/2024 AR 4818876 Governor Drifts When Lowering RCIC Turbine Speed 9054.01 11/21/2024 Corrective Action Documents AR 4823527 Div 1 NSPS Inverter Trouble 12/13/2024 3506.01C005 Diesel Generator Start Log 1c 3506.01D003 Diesel Generator 1C Operating Logs 8
9080.14 Diesel Generator 1C 24 Hour Run and Hot Restart - Operability 41 CPS 3310.01 Reactor Core Isolation Cooling (RI) 33 CPS 9000.05D001 Suppression Pool Temperature Log Data Sheet 27c CPS 9052.01P002 RHR Pump A Operability / WLP Double Check Valve Test 0
CPS 9053.04C001 RHR Loop A Valve Operability 3g 71111.24 Procedures CPS 9054.01C002 RCIC (1E51-C001) High-Pressure Operability Checks 10 Procedures CPS 9054.01D002 RCIC (1E51-C001) High-Pressure Operability Checks Checklist 26d WO 5571419 1WX020 PCIV Closing Stroke Time Exceeded Limiting Value 11/14/2024 WO 5571419-02 OPS PMT 1WX020 PCIV Timed Stroking of Valve 11/14/2024 71111.24 Work Orders WO 5578814 OP 9080.03 DG 1C Operability - Monthly Test 10/05/2024 EP-AA-1003, Addendum 1 Clinton Station On-Shift Staffing Technical Basis 3
71114.04 Calculations EP-AA-1003, Clinton Evacuation Time Estimates 2
16 Inspection Procedure Type Designation Description or Title Revision or Date Addendum 2 EP-AA-120-1001 CPS Emergency Plan Revised for IPAWS Implementation, Evaluation No. 23-35 23-35 Procedures EP-AA-1003 Constellation Radiological Emergency Plan Annex for Clinton Station 30 2024 4Q CPS Integrated PI Drill Exercise Scenario Manual 10/24/2024 71114.06 Miscellaneous SE-LOR-800 LORT EP Practice Scenario 0
AR 4302516 Leakage From Pipe Cap Downstream of 2-0220-63B/64B 12/09/2019 AR 4669527 Fleet Containment Leakage Elimination - Fleet Actions 04/12/2023 AR 4680584 Drywell Floor Drain in Leakage High After Startup From C1M26 05/24/2023 AR 4681106 Plant Shutdown Due to Increased Drywell Leakage Trend 05/27/2023 AR 9736029736021B33F051B: Deficiency Identified During DW Close Out 10/01/2009 Corrective Action Documents ARs 4770172,
- 4750492, 4736518,
- 4727360, 4754245, 4773852 12/31/2024 Drawings BA-M07-1072, Sheet 005 Reactor Recirculation Piping 2" and Under HJ EC 378419 Cut and Cap RR Drain Lines 1RE100AA/AB for Both RR Loop A and B 1
71152A Engineering Changes EC 639676 Seal Pipe Caps for Drywell Drain Lines 0
PI-AA-120 Issue Identification and Screening Process 13 71152A Procedures PI-AA-125 Corrective Action Program (CAP) Procedure 9
71152S Corrective Action Documents ARs 4812887,
- 4812222, 4811898,
- 4809307, 4808007,
- 4809055, 4807802, Various Issue Reports Describing Low UT Readings, Leaks, Degradation, and Additional Inspections per Code Case on SX Piping and Components 12/27/2024
17 Inspection Procedure Type Designation Description or Title Revision or Date
- 4806968, 4806364,
- 4805045, 4801535, 4794432 EC 642704 Through Wall Flaw Evaluation of 1SX88AA-3 In Accordance With N-513-5 0
Engineering Changes EC 642849 Wall Thinning Evaluation of 1SX25A-4" 0