IR 05000461/2023002
| ML23216A028 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 08/04/2023 |
| From: | Robert Ruiz NRC/RGN-III/DORS/RPB1 |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| References | |
| IR 2023002 | |
| Download: ML23216A028 (1) | |
Text
SUBJECT:
CLINTON POWER STATION - INTEGRATED INSPECTION REPORT 05000461/2023002
Dear David Rhoades:
On June 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Clinton Power Station. On July 24, 2023, the NRC inspectors discussed the results of this inspection with Norha Plumey, Plant Manager, 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.
If you contest the violation or the significance or severity of the violation 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.
August 4, 2023 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-2023-002-0047
Licensee:
Constellation Nuclear
Facility:
Clinton Power Station
Location:
Clinton, IL
Inspection Dates:
April 01, 2023 to June 30, 2023
Inspectors:
A. Athar, Senior Resident Inspector (acting)
J. Beavers, Senior Resident Inspector
S. Bell, Health Physicist
B. Bergeon, Senior Operations Engineer
T. Hooker, Health Physicist
A. Muneeruddin, Resident Inspector
J. Murphy, Illinois Emergency Management Agency
N. Shah, Senior Project 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.
List of Findings and Violations
Failure to Complete a Timely Operability Evaluation of a Deficient Condition Affecting the Division 2 Emergency Diesel Generator Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000461/2023002-01 Open/Closed
[P.3] -
Resolution 71111.15 The inspectors identified a Green non-cited violation of 10 CFR Part 50, Appendix B,
Criterion V, Instructions, Procedures, and Drawings, for Clinton Power Stations failure to complete a timely operability determination. Specifically, from April 2020 to May 11, 2023, the station failed to determine the operability impact of a lube oil leak on the division 2 emergency diesel generator (EDG).
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period in Mode 1, operating at or near full-rated thermal power (RTP). On April 15, 2023, the unit reduced reactor power to approximately 70 percent to perform a control rod sequence exchange. On April 16, 2023, the unit was returned to full RTP. On April 27, 2023, the unit reduced reactor power to approximately 90 percent due to an unexpected loss of extraction steam to the 2A, 3A and 4A feedwater heaters. Following restoration of the 3A and 4A feedwater heaters to service, the unit was returned to RTP on April 28, 2023. On May 13, 2023, the unit was shut down to cold shutdown (Mode 4) to perform a planned maintenance outage (C1M26) to replace both the 'A' and 'B' reactor recirculation pump seals and repair the 2A feedwater heater extraction steam bellows. On May 23, 2023, the unit was restarted, and the main generator synchronized to the grid. Following power ascension, the unit was returned to RTP on May 26, 2023. On May 27, 2023, the unit was shut down to cold shutdown to perform an unplanned forced outage (C1F64) to repair a leak that developed on the 'B' loop reactor recirculation suction line drain cap, which was determined to be the source of increased unidentified leakage observed during the previous startup. The unit was restarted on May 28, 2023, the main generator was synchronized to the grid on May 29, 2023, and following power ascension returned to RTP on June 1, 2023. On June 24, 2023, the unit reduced reactor power to approximately 71 percent to perform a rod pattern adjustment and returned the unit to at or near RTP on June 25, 2023. The unit operated 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
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)residual heat removal (RHR) 'A' on April 24, 2023 (2)division 1 emergency diesel generator on May 3, 2023 (3)low-pressure core spray on May 13, 2023
- (4) RHR 'B' shutdown cooling on May 17, 2023
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the reactor core isolation cooling system on May 5, 2023.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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)turbine building, elevation 800', division 2 switchgear and battery room on April 10, 2023
- (2) Fire Area/Fire Zone CB-1i, elevation 825', control building, air handling equipment room on May 1, 2023
- (3) Fire Area/Fire Zone CB-6a, elevation 800', control building, main control room on May 10, 2023
- (4) Fire Area/Fire Zone CB-4, elevation 781', control building, division 1 cable spreading room on May 10, 2023
- (5) Fire Area/Fire Zone C-1, elevation 723' and 737', drywell on May 18, 2023
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 the emergent power reduction due to the loss of feedwater heating on April 27, 2023.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated simulator training on May 2, 2023.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
(1)reactor recirculation pump 'B' outer seal degradation and replacement (Work Order 1281845)
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
- (1) Moore 535 temperature indicator unit material defect
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 Samples)
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)division 3 shutdown service water pump system outage window on May 3, 2023 (2)maintenance outage (C1M26) Yellow risk during reactor recirculating pump seal replacements with reduced inventory and high decay heat May 14-17, 2023
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Action Request (AR) 4665910, "Shutdown Service Water Piping Flaw"
- (2) AR 4677517, "Division 2 Emergency Diesel Generator Lube Oil Leak"
- (3) AR 4674068, "Diesel Generator Operability While Draining Accumulated Water from the Fuel Tanks" (4)emergency reserve auxiliary transformer load tap changer
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) RHR suction temporary shielding (2)permanent modification of reactor recirculation pump 'A' seal assembly
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (2 Samples)
- (1) The inspectors evaluated maintenance outage C1M26 activities from May 13-23, 2023.
- (2) The inspectors evaluated forced outage C1F64 activities from May 27-29, 2023.
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) (5 Samples)
(1)
'B' shutdown service water pump operability test (Work Order 5315295)
(2)
'B' RHR heat exchanger station outage window PMT (Work Order 5240627)
(3)post-maintenance test on the 'B' recirculation pump seals following replacement (Work Order 1281845)
(4)post-maintenance test on the 'A' recirculation pump seals following replacement (Work Order 4653307)
- (5) Clinton Power Station (CPS) 9337.81C006, "Drywell Flame Detector Test Following Cable Replacement and Modification" (Work Order 5224444-05)
Surveillance Testing (IP Section 03.01) (1 Sample)
(1)
93434.02B, ATWS [anticipated transient without scram] reactor pressure B21-N401B channel calibration, May 10, 2023 Inservice Testing (IST) (IP Section 03.01)
- (1) CPS 9015.01, "Standby Liquid Control Pump 'B' Operability" (Work Order 5344139)
- (2) CPS 9053.07, "Residual Heat Removal Pump 'B' Operability" (Work Order 5343475)
- (3) CPS 9052.01, "Low Pressure Core Spray Pump Operability" (Work Order 5351129)
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
(1)emergency planning drill observed on May 9, 2023, in the simulator and the technical support center
RADIATION SAFETY
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling,
Storage, & Transportation
Radioactive Material Storage (IP Section 03.01)
The inspectors walked down and evaluated the licensees performance in controlling, labeling, and securing the following radioactive materials:
(1)radioactive material storage locations outside the protected area (2)10 CFR Part 37 radioactive source location
Radioactive Waste System Walkdown (IP Section 03.02) (2 Samples)
The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
(1)radioactive waste truck bay and associated waste processing areas (2)radioactive waste solidification system and drum storage area
Waste Characterization and Classification (IP Section 03.03) (3 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste: (1)waste sludge resin (2)phase separator resin (3)concentrated waste
Shipping Records (IP Section 03.05) (4 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
(1)radioactive waste shipment W23-001 containing waste sludge packaged in a general design package for transport to radioactive waste vendor (2)radioactive waste shipment W21-011 containing class A phase separator resin packaged in a type A package for transport to a disposal facility (3)radioactive material shipment M23-007 containing a Cs-137 calibrator packaged in a type A package (4)radioactive waste shipment W23-002 containing concentrated waste packaged in a general design package for transport to a radioactive waste vendor
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05)===
- (1) Unit 1 (April 1, 2022, through March 31, 2023)
MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)
- (1) Unit 1 (April 1, 2022, through March 31, 2023)
MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)
- (1) Unit 1 (April 1, 2022, through March 31, 2023)
INSPECTION RESULTS
Failure to Complete a Timely Operability Evaluation of a Deficient Condition Affecting the Division 2 Emergency Diesel Generator Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000461/2023002-01 Open/Closed
[P.3] -
Resolution 71111.15 The inspectors identified a Green non-cited violation of 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for Clinton Power Stations failure to complete a timely operability determination. Specifically, from April 2020 to May 11, 2023, the station failed to determine the operability impact of a lube oil leak on the division 2 emergency diesel generator (EDG).
Description:
In April 2020, during the monthly operability run of the division 2 EDG, sparking was observed inside the commutator housing of the division 2 EDG 16-cylinder fuel priming pump motor.
The station determined that the fuel priming pump was still able to perform its function.
In December 2021, the 16-cylinder fuel priming pump was observed to not be running during a monthly surveillance test of the division 2 EDG. The EDG was at idle speed, and the priming pump for the 12-cylinder engine was observed to be running. Furthermore, the fuel pressure was observed to be 19 psig, which is well below the normal operating pressure of 35-45 psig. Additionally, the commutator inside the end of the motor was observed to not be moving. The fuel priming pump starts automatically upon engine start and is turned off by the speed switch as the engine approaches normal running speed. The fuel priming pump provides assurance that there will be adequate fuel to start the engine. Ultimately, the engine started normally and accelerated to running speed, so the EDG remained operable, but was in a degraded condition without the 16-cylinder fuel priming pump functioning.
The issue with the fuel priming pump was investigated, and the station found that lube oil had dripped onto the fuel priming pump motor, and intrusion into the commutator was preventing the fuel priming pump from functioning. The fuel priming pump was functional after it was cleaned. However, the station did need to install a drip shield above the fuel priming pump as a compensatory measure to divert the lube oil drips from causing further functionality issues.
While the station installed a drip shield to mitigate the consequences of a lube oil leak, the actual lube oil leak was not documented in the stations corrective action program (CAP) until the inspectors inquired about the issue on May 11, 2023. As such, the lube oil leak was not evaluated for operability until May 11, 2023, approximately 3 years after the lube oil leak began. The lube oil leak itself is a deficient SSC condition, as defined by the licensee in procedure OP-AA-108-115, revision 26, Operability Determinations. The licensees definition states, deficient SSC condition is one which may compromise the required capabilities of the affected SSC. In this case, lube oil leakage can cause excessive oil makeup requirements which could affect the ability of the EDG to operate for 7 days.
Furthermore, without the drip shield installed, this leak impacts and degrades the fuel oil priming pump, which is a safety-related piece of equipment.
Following the inspectors' questioning of the impact of the lube oil leak to the operability of the division 2 EDG, station personnel entered this issue into the stations CAP and the AR was routed to the shift manager for an operability evaluation. However, this occurred on May 11, 2023, which is approximately 3 years after the lube oil leak began. Station procedure OP-AA-108-115, revision 26, Operability Determinations, instructs operations shift management to immediately determine operability from an examination of the deficient condition affecting an SSC. Thus, the licensee failed to determine the operability impact of a lube oil leak on the division 2 EDG.
Corrective Actions: The station initiated an AR to identify the lube oil leak on the division 2 EDG, and the shift manager documented an operability determination on May 11, 2023.
Corrective Action References: ARs 4677517, 4468772, 4489698 and 4339936
Performance Assessment:
Performance Deficiency: The inspectors determined that the stations failure to promptly enter a condition adverse to quality into the CAP was a performance deficiency. Specifically, the station entered a lube oil leak on the division 2 EDG into their CAP program approximately 3 years after the lube oil leak was known to have begun.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Equipment Performance 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. Specifically, the division 2 EDG lube oil leak impacts and degrades the fuel oil priming pump. The fuel priming pump provides assurance that there will be adequate fuel to start the engine, so a malfunction of the fuel priming pump represents a reduction in the reliability of the division 2 EDG. Without the fuel priming pump running, the division 2 EDG must rely on fuel trapped under pressure in the fuel rail to accelerate the engine upon start; however, the AR generated by station personnel states that this feature should not be solely relied upon, as a loss of pressure (such as in the case of a leaking check valve) could limit the engines ability to accelerate to speed. Furthermore, lube oil leakage can cause excessive oil makeup requirements which could affect the ability of the EDG to operate for 7 days. The operability determination of May 11, 2023, found that this lube oil leak is small enough that it does not challenge the 7-day lube oil inventory by itself. However, when combined with other minor lube oil leaks, the total lube oil leakage from the EDG may add up to a more significant impact to the 7-day lube oil inventory. Failure to document this minor lube oil leak in the CAP meant that the leakage was not included in the stations spreadsheet that is used to keep track of the aggregate lube oil leakage from the EDG. As such, if additional lube oil leaks were to develop on the EDG, the station may not be aware of the true total lube oil leakage from the EDG and the associated impact to operability.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using Exhibit 2, Mitigating Systems Screening Questions, the inspectors determined the finding to be of very low safety significance (Green) because the finding was not a deficiency affecting the design or qualification of a mitigating SSC and the degraded condition does not represent a loss of the probabilistic risk assessment function of any equipment.
Cross-Cutting Aspect: P.3 - Resolution: The organization takes effective corrective actions to address issues in a timely manner commensurate with their safety significance. The licensee did not take effective corrective actions to address issues in a timely manner commensurate with their safety significance. Specifically, the lube oil leak was not entered into the CAP as its own issue until raised by the inspector; as a result, effective corrective actions were not taken in a timely manner.
Enforcement:
Violation: Title 10 Code of Federal Regulations Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, requires, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings. The licensee established OP-AA-108-115, revision 26, Operability Determinations, as the implementing procedure for operability determinations, an activity affecting quality.
Station Procedure OP-AA-108-115, revision 26, Operability Determinations, step 4.1.6, instructs station personnel to Immediately DETERMINE operability from a detailed examination of the deficient condition affecting an SSC, and step 4.1.8 instructs station personnel to document the operability determination results in the CAP.
Contrary to the above, from April 2020 to May 11, 2023, the licensee failed to complete a timely operability determination for a deficient condition affecting an SSC. Specifically, the licensee failed to assure that a lube oil leak on the division 2 EDG was promptly identified in the stations CAP.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 24, 2023, the inspectors presented the integrated inspection results to Norha Plumey, Plant Manager, and other members of the licensee staff.
On June 23, 2023, the inspectors presented the radiation protection baseline inspection results to Norha Plumey, Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NRC ID PCRA 3312.01V001
04/24/2023
NRC ID Housekeeping Issues
04/25/2023
Corrective Action
Documents
Resulting from
Inspection
NRC ID Items
05/14/2023
3310.01V001
Reactor Core Isolation Cooling Valve Lineup
3312.01V001
Residual Heat Removal Valve Lineup
17c
3312.01V001
Residual Heat Removal Valve Lineup
17c
3312.01V002
Residual Heat Removal Instrument Valve Lineup
9a
CPS 3312.03
RHR - Shutdown Cooling (SDC) & Fuel Pool Cooling and
Assist (FPC&A)
2e
3313.01V001
Low Pressure Core Spray Valve Lineup
13b
3313.01V002
Low Pressure Core Spray Instrument Valve Lineup
8a
3506.01P004
Placing Division 1 Diesel Generator 1A in Standby
Oe
Locked Equipment Program
Procedures
OP-CL-108-103-
1001
Locked Valve Lineup (Outside of Drywell)
Corrective Action
Documents
Damaged Piping Insulation in VC 'B' Room
05/03/2023
1893.04M003
Prefire Plan Legend
1893.04M130
781-790 Auxiliary: Div 2 Switchgear Prefire Plan
5b
1893.04M200
23-778 Drywell: Prefire Plan
Fire Plans
781 Control: Div 2 Cable Spreading Room Prefire Plan
5d
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1893.04M350
1893.04M352
781 Control: Div 1 Cable Spreading Room Prefire Plan
5d
1893.04M364
800 Control: Main Control Room Prefire Plan
3a
1893.04M370
25 Control: Control Room HVAC Prefire Plan
7b
1893.04M740
800 Turbine: Turbine Deck Prefire Plan
5c
1893.04M003
Prefire Plan Legend
1893.04M200
23-778 Drywell Prefire Plan
1893.04M350
Control: Div. 2 Cable Spreading Room Prefire Plan
5d
1893.04M352
781 Control: Div 1 Cable Spreading Room Prefire Plan
5d
1893.04M364
800 Control: Main Control Room Prefire Plan
3a
Procedures
ER-CL-600-1069
Clinton Unit 1, Site List of High-Risk Fire Areas
1TITVX002 Controller Found in Manual
07/24/2018
New Moore Controller from Stores Failed Bench Test
11/22/2022
Defective Moore 535 Received from Stores
2/22/2023
2nd Defective Moore 35 Received from Stores
2/22/2023
Moore 535 Controllers Failed Within the Last 4 Months
2/23/2023
Corrective Action
Documents
Trend in Moore Controller Issues
2/28/2023
Purchase Order
51636000
Controller, Digital, Model 535 Single Loop Process, Base Unit,
Universal Inputs, Universal Power Supply 90-250 Vac
09/08/2020
Miscellaneous
Receipt 249484
Quality Receipt Inspection Package, Catalog ID 1383969-1,
PO 51636000, Digital Controller
08/10/2020
CFR Part 21 Technical Evaluations
PES-S-002
Shelf Life
Processing of Level 3 OPEX Evaluations
Corrective Action Program (CAP) Procedure
Procedures
Warehouse Operations
Work Orders
Forced Outage Contingent 'B' RR PMP Seal Replacement
NRC ID Material
05/15/2023
Corrective Action
Documents
NRC ID House Keeping
05/15/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Resulting from
Inspection
Shutdown Risk Management
Shutdown Safety Management Program
Procedures
Shutdown Safety Approval/Notification Form
DIV 2 EDG 16 CYL Fuel Priming Pump Motor Sparking
04/30/2020
Div 2 DG 16 Cyl Priming Pump Not Running During Idle Start
2/29/2021
IR to Document TCP Requiring Extension Past Six Months
08/24/2022
5007-5M 4 kV Bus High Voltage
2/03/2022
1SXB2BB-3/4" UT Results Lower than Expected
03/03/2023
Clarify DG Remains Operable during Water Draining from
Tanks
04/30/2023
Corrective Action
Documents
Tech Spec Bases 3.8.1.B.4 Clarity Question
05/03/2023
NRC ID: Lube Oil Drip on Division 2 EDG 16 Cylinder Engine
05/11/2023
NRC ID: Tracking Mechanisms for Non-Contaminated Catch
Basins
05/18/2023
Corrective Action
Documents
Resulting from
Inspection
NRC ID: Untimely Resolution to the Leak/Prime Pump DIV 2
05/18/2023
Design Analysis
IP-M-0513
DIVISION I, II, AND III SX PIPE WALL THINNING ANALYSIS
INCLUDING RHR PIPING
03/20/2023
NB-3652
Allowable Stress at Various Code Service Levels (a) for Class
Piping, Equation (9), NB-3652
2/22/1982
TCP 1175
Transient Combustible Permit 1175
2/31/2021
Miscellaneous
TCP 1187
Transient Combustible Permit 1187
01/30/2022
3506.01C007
Checklist to Extend 72 Hour LCO Action to 14 Day LCO for
Diesel Generators (ITS 3.8.1.B.4) Bases)
3506.01C007
Checklist to Extend 72 Hour LCO Action to 14 Day LCO for
Diesel Generators (ITS 3.8.1.B.4 Bases)
Ultrasonic Thickness Calibration Sheet
Ultrasonic Thickness Calibration Sheet
Ultrasonic (UT) Measurement of Material Thickness and
Interfering Conditions
Procedures
Ultrasonic Thickness Calibration Sheet, WO 4980164-01
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Operability Determinations (CM-1)
OP-AA-108-115-
1002
Supplemental Consideration for on-Shift Immediate Operability
Determinations (CM-1)
Corrective Action Program (CAP) Procedure
Div 2 DG 16 Cyl Priming Pump Not Running During Idle Start
2/30/2021
Work Orders
Div 2 DG 16 Cyl Priming Pump Not Running During Idle Start
2/30/2021
Issuance of Piping and Support Calculations for Approved
TSPS
001
Engineering
Changes
Authorized Usage of Upgraded Seal Assembly for RR Pump
'A' Seal Previously Authorized for RR 'B' Pump Seal
Design Analysis
IP-M-0704
Evaluation Subsystem 1RH-09 Due to Installation of
Temporary Shielding Package TSP 2001-110, TSP 2001-120
and TSP 2001-121
11/20/2007
Survey Index No.:
01-06-03-07
Radiological Survey Sheet, Aux Building - 707' Elevation, RHR
Heat Exchanger and Pump Room (A)
06/03/2001
Miscellaneous
TSR 2001-120
and 2001-121
Installation of Temporary Shielding on Lines 1RH01BA-20",
1RH07A-16" and 1RH07C-16" Including Valves 1E12F006A
and 1E2F006B
Temporary Shielding Extension (Long-Term Shielding)
CC-CL-401
Temporary Shielding Permit
Procedures
7500.05F001
Temporary Shielding Request
C1R18 PEP MAP RHR C/DIV 2 EDG/SX/AC/DC/NSPS
C1R19 Standard RHR-B PEP
Drawings
STM Motor Modules PEP
Shutdown Safety Compensatory Measures Plan,
Compensatory Measure Plan #1 - FC and SDC Hardening
04/26/2023
Shutdown Safety Compensatory Measures Plan,
Compensatory Measure Plan #2-SRM Availability
04/26/2023
Shutdown Safety Compensatory Measures Plan,
Compensatory Measure Plan #3 - Management of Drain Time
Calculation Exemptions
04/26/2023
Procedures
Shutdown Safety Approval/Notification Form
04/19/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Shutdown Safety Approval/Notification Form
05/04/2023
Shutdown Safety Contingency Plan, Restore Shutdown
Cooling (SDC)/Alternate Shutdown Cooling (A-SDC) Upon
Loss of Running Train
07/02/2021
Shutdown Safety Contingency Plan, C1R20 Contingency
Plan #8 - FLEX Injection During High Decay Heat Conditions
08/19/2021
9534.02B
ATWS Reactor Pressure B21-N401B Channel Calibration
0h
9069.01P003
Division 2 Shutdown Service Water Operability Test
Procedures
CPS 9434.02B
ATWS Reactor Pressure B21-N401B Channel Calibration
0c
Forced Outage Contingent 'B RR PMP Seal Replacement
05/14/2023
1B33C001A - Contingent Seal Replacement
05/17/2023
9069.01, 1SX01PC Comprehensive Pump Test
03/10/2023
IM Install Temp Instrumentation for 9069.01 Div 3 SX Pump
03/06/2023
9069.01, 1SX01PC Comprehensive Pump Test
03/09/2023
EM PMT 9337.81C006 CF-Drywell Flame Detectors
05/17/2023
Perform MOV Thrust Verification and Clean/Inspection
1E12F014
04/26/2023
9534.02B(B20) IM CF ATWS Reactor Pressure High
B21-N401B
05/10/2023
9069.01B20 OP SX PUMP Operability Test (SX Pump B)
03/04/2023
OP 9053.07 RHR 'B' Pump Oper Test
05/31/2023
OP 9015.01 OP SLC Pump Operability (SLC Pump B)
06/02/2023
Work Orders
OP LPCS/RHR A Water Leg Pump Operability
06/12/2023
Miscellaneous
Clinton Station
EMPE, May 9,
23 Sim Manual
05/02/2023
Radwaste: Spent Resin Cask/Liner Inspection UNSAT
2/18/2020
Radwaste Processing Issues
06/17/2022
RPID Concentrated Waste Liner Survey Needed
2/16/2023
RWTB - Radwaste Truck Bay Scale Continued Discrepancy
Corrective Action
Documents
WW2314 & 2315 - No Support for WX Solid Radwaste
Processing
04/13/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
NRC Observation Regarding 10 CFR Part 37 Program
06/16/2023
Radioactive Material Transportation Specialist Training
Records
Various
L91767-2
CFR 61 Radiochemistry Analysis for Phase Separator
Resin
04/24/2021
L98770-1
CFR 61 Analysis of Waste Sludge Resin
11/01/2022
Miscellaneous
L98770-2
CFR 61 Radiochemistry Analysis for Concentrated Waste
11/15/2022
CPS 3909.03
Operating Waste Sludge System
Procedures
Process Control Program for Radioactive Wastes
Radiation Surveys
Radioactive Sealed Source Inventory and Leak Test Records
for December 2022
Various
Radioactive Solid Waste Processing and Radioactive Material
Handling, Storage, and Transportation
10/29/2021
NRC Inspection 71124.08 Radioactive Solid Waste Processing
and Radioactive Material Handling, Storage and Transportation
04/28/2022
NRC Inspection 71124.08 Radioactive Solid Waste Processing
and Radioactive Material Handling, Storage and Transportation
05/05/2023
Self-Assessments
AR 456037456037Chemistry, Radwaste, Effluent and Environmental Monitoring
Audit Report
04/14/2023
M23-007
Instrument Calibrator Transported in a Type A Package
2/06/2023
W21-011
Radioactive Waste Shipment of Phase Separator Resin
11/30/2021
W23-001
Radioactive Waste Shipment of Waste Sludge
01/31/2023
Shipping Records
W23-001
Radioactive Waste Shipment W23-001 Containing
Concentrated Waste
05/31/2023