IR 05000461/2024004
| 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
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 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
Inspection Report
Docket Number:
05000461
License Number:
Report Number:
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
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: 71111.1
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
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
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
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.
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
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,
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) 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)
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) 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)
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.
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
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.
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
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.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Sec ID: Camera 110 Deficient/Winter Concerns
10/30/2024
Winter Readiness: Work Needs Scheduled on MPT A
Cooling Fans
10/30/2024
Winter Readiness: Heat Trace Tagged Out
11/10/2024
Corrective Action
Documents
Winter Readiness Concern for MWPH Trailer Lines
11/24/2024
Drawings
E-CLT6-T02-
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)
Station Housekeeping/Material Condition Program
OP-AA-108-111-
1001
Severe Weather and Natural Disaster Guidelines
Severe Weather Preparation and Response
Procedures
Seasonal Readiness
1DG01KC Exciter Diode D3 Found Loose Connection
09/30/2024
Corrective Action
Documents
Div 3 DG/SX SOW 4.0 Critique
10/06/2024
3506.01E001
Diesel Generator and Support Systems Electrical Lineup
18d
3506.01V001
Diesel Generator and Support Systems Valve Lineup
13a
Procedures
3506.01V002
Diesel Generator and Support Systems Instrument Valve
Lineup
11b
1893.04M210
737 Containment: Prefire Plan
6b
1893.04M220
755 Containment: Prefire Plan
1893.04M230
778 Containment: East Prefire Plan
1893.04M231
778 Containment: West Prefire Plan
Fire Plans
803 Containment: Prefire Plan
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1893.04M240
1893.04M250
28 Containment: Prefire Plan
6a
1893.04M360
800 Control: Tech Support Center Prefire Plan
5b
1893.04M361
800" Control: Operations Support Center Prefire Plan
5c
1893.04M363
2' Control: Breathing Air Bottle Corridor Prefire Plan
5c
1893.04M420
755 Fuel: Fuel Handling Floor Prefire Plan
4a
1893.04M430
781 Fuel: West Balcony Prefire Plan
4c
1893.04M431
781 Fuel: East Balcony Prefire Plan
2c
Miscellaneous
Email from
Richard Tyler,
Exam Author,
Constellation
Nuclear to James
Nance,
Operations
Engineer, U.S.
NR
- C.
TQ-AA-150-F25 Rev 007Property "Contact" (as page type) with input value "C.</br></br>TQ-AA-150-F25 Rev 007" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., LORT Annual Exam Status
Report - CPS 2024 Final Report
11/21/2024
Miscellaneous
ESG-LOR-425
CPS 3005.01
Unit Power Changes
CPS 3304.01
Control Rod Hydraulic and Control (RD)
CPS 3304.02
Rod Control and Information System (RC&IS)
23d
CPS 9031.06
Main Turbine Stop Valve and Combined Intermediate Valve
Tests
CPS 9031.07
Main Turbine Control Valve Tests
Procedures
CPS 9813.01
Control Rod Scram Time Testing
43a
New Hydramotor Failed During Prep Task
08/09/2019
Corrective Action
Documents
0VG01YA VG A Inlet Damper Indicated Closed
09/21/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Engage Health
(a)(1) Determination
11/21/2024
Procedures
Maintenance Rule - (a)(1) and (a)(2) Requirements
IMD TS&R 0VG004 Loop
09/22/2023
OPS 0FCVG004 Stroke Damper 0VG01YA To Support
Troubleshooting
09/22/2023
EM 0VG01YA Troubleshoot Damper / Hydramotor
09/23/2023
EM 0FZVG004 Install Replacement Hydramotor
09/25/2023
Work Orders
10/06/2023
NRC Identified 1SF005A Handwheel on Floor
10/01/2024
Corrective Action
Documents
Resulting from
Inspection
NRCID Issues
10/01/2024
Risk Management
On-line Risk Management
Protected Equipment Program
On-line Work Control Process
Procedures
On-line Risk Management and Assessment
Calculations
VG-16
Standby Gas Treatment System Cooling Load
5B
4708908
RCIC Procedure Enhancement
10/11/2023
1DG01KA: Minor Turbocharger Blade Impact Indications
09/30/2010
1DG01KA Impeller Blade Impact Indications
09/18/2020
1DG01KA 12 Cylinder Turbo Damage
09/09/2024
Corrective Action
Documents
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
E02-1RI99, Sheet
015
Reactor Core Isolation Cooling System (RI), Reactor Core
Iso Cooling Sys (NSPS) (1E51-1050)
Q
Drawings
E02-1RI99, Sheet
Reactor Core Isolation Cooling System (RI), Reactor Core
Iso Cooling Sys (NSPS) (1E51-1050)
F
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Division 1 Diesel Generator Turbocharger Impeller Blade
Indications
Engineering
Changes
Sbgt Room Maximum LOCA/LOOP Temperature with no
Room coolers
465407
138KV Voltage Transient during HPCS Pump Run on
2/2/24 and ERAT MSC Overvoltage Trip
2/06/2024
RAT MSC Trip 1A1 Bus Overvoltage Transient
Engineering
Evaluations
ECR 464247
EQ-CL044
Environmental Qualification Package ITT General Controls
NH-90 Series Hydromotor Actuators (Safety Related)
Operations Narrative Log Entries
10/14/2024
Operations Narrative Log Entries
11/20/2024
RICT Record for ERAT MSC Trip of 12/2/2024
2/09/2024
RCIC Sections
5.4.6 and 7.4.1.1
Clinton Power Station Updated Safety Analysis Report
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
Operability
Evaluations
Assignment 12
(OPDC)
Past Operability Determination
10/28/2024
3505.01
345 & 138 KV Switchyard (SY)
3505.04
ERAT Mechanically Switched Capacitor (MSC) Bank System
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
5063.05
Alarm Panel 5063 Annunciators - Row 5
CPS 3505.01
345 KV & 138KV Switchyard
Procedures
CPS 9082.01
Offsite Source Power Verification
2c
Engineering
Evaluations
465326
Engineering Change Request
11/21/2024
Work Orders
11/21/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1WX020 PCIV Closing Stroke Time Exceeded Limiting
Value
08/22/2024
1WX020 Performance Compromised due to Excessive
Cycling
11/12/2024
Replace 1WX020 During the Next Outage
11/14/2024
Add Lubrication of RO2 Slider to PMRQ for 1WX020
11/14/2024
Unexpected MCR Annunciator RCIC Pump Suction
Pressure High 5063-1D
11/19/2024
RCIC Turbine Trip During Startup
11/20/2024
Governor Drifts When Lowering RCIC Turbine Speed
9054.01
11/21/2024
Corrective Action
Documents
Div 1 NSPS Inverter Trouble
2/13/2024
3506.01C005
Diesel Generator Start Log
1c
3506.01D003
Diesel Generator 1C Operating Logs
9080.14
Diesel Generator 1C 24 Hour Run and Hot
Restart - Operability
CPS 3310.01
Reactor Core Isolation Cooling (RI)
9000.05D001
Suppression Pool Temperature Log Data Sheet
27c
9052.01P002
RHR Pump A Operability / WLP Double Check Valve Test
9053.04C001
RHR Loop A Valve Operability
3g
Procedures
9054.01C002
RCIC (1E51-C001) High-Pressure Operability Checks
Procedures
9054.01D002
RCIC (1E51-C001) High-Pressure Operability Checks
Checklist
26d
1WX020 PCIV Closing Stroke Time Exceeded Limiting
Value
11/14/2024
OPS PMT 1WX020 PCIV Timed Stroking of Valve
11/14/2024
Work Orders
OP 9080.03 DG 1C Operability - Monthly Test
10/05/2024
Addendum 1
Clinton Station On-Shift Staffing Technical Basis
Calculations
Clinton Evacuation Time Estimates
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Addendum 2
CPS Emergency Plan Revised for IPAWS Implementation,
Evaluation No. 23-35
23-35
Procedures
Constellation Radiological Emergency Plan Annex for
Clinton Station
24 4Q CPS
Integrated PI Drill
Exercise Scenario Manual
10/24/2024
Miscellaneous
Leakage From Pipe Cap Downstream of 2-0220-63B/64B
2/09/2019
Fleet Containment Leakage Elimination - Fleet Actions
04/12/2023
Drywell Floor Drain in Leakage High After Startup From
C1M26
05/24/2023
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,
27360,
4754245,
4773852
2/31/2024
Drawings
BA-M07-1072,
Sheet 005
Reactor Recirculation Piping 2" and Under
HJ
Cut and Cap RR Drain Lines 1RE100AA/AB for Both RR
Loop A and B
Engineering
Changes
Seal Pipe Caps for Drywell Drain Lines
Issue Identification and Screening Process
Procedures
Corrective Action Program (CAP) Procedure
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
2/27/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4806968,
4806364,
4805045,
4801535,
4794432
Through Wall Flaw Evaluation of 1SX88AA-3 In Accordance
With N-513-5
Engineering
Changes
Wall Thinning Evaluation of 1SX25A-4"
0