IR 05000315/2022002
| ML22216A258 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/08/2022 |
| From: | Laura Kozak Reactor Projects Region 3 Branch 4 |
| To: | Lies Q Indiana Michigan Power Co |
| References | |
| IR 2022002 | |
| Download: ML22216A258 (29) | |
Text
SUBJECT:
DONALD C. COOK NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000315/2022002 AND 05000316/2022002
Dear Mr. Lies:
On June 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Donald C. Cook Nuclear Plant and discussed the results of this inspection with you 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 did not involve a violation of NRC requirements.
Licensee-identified violations which were determined to be of very low safety significance are documented in this report. We are treating these violations as non-cited violations (NCVs)
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 Donald C. Cook Nuclear Plant.
If you disagree with a finding not associated with a regulatory requirement 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 Donald C. Cook Nuclear Plant.
August 8, 2022
Q. 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, Laura L. Kozak, Acting Chief Branch 4 Division of Reactor Projects Docket Nos. 05000315 and 05000316 License Nos. DPR-58 and DPR-74
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000315 and 05000316
License Numbers:
Report Numbers:
05000315/2022002 and 05000316/2022002
Enterprise Identifier:
I-2022-002-0047
Licensee:
Indiana Michigan Power Company
Facility:
Donald C. Cook Nuclear Plant
Location:
Bridgman, MI
Inspection Dates:
April 1, 2022 to June 30, 2022
Inspectors:
S. Bell, Health Physicist
M. Domke, Reactor Inspector
M. Garza, Emergency Preparedness Inspector
J. Gewargis, Reactor Engineer
I. Hafeez, Senior Reactor Inspector
J. Mancuso, Resident Inspector
R. Ng, Project Engineer
J. Reed, Health Physicist
R. Wehrmann, Reactor Engineer
P. Zurawski, Senior Resident Inspector
Approved By:
Laura L. Kozak, Chief
Branch 4
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Donald C. Cook Nuclear Plant, 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. Licensee-identified non-cited violations are documented in report sections: 71111.20 and 71124.0
List of Findings and Violations
Spent Fuel Crane Bridge Modification Not Processed Correctly Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green FIN 05000315,05000316/2022002-01 Open Unable to Identify 71111.18 A Green finding was NRC-identified and associated with the licensees failure to process a permanent spent fuel handling crane bridge modification in accordance with licensee procedure IP ENG-001, Standard Design Process, Revision 0. Specifically, a permanent modification to a seismic category I structure, system, or component (SSC) was processed as a commercial change on May 26, 2020, which was prohibited by IP ENG-001.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period at 100 percent power and shut down for a refueling outage on April 3, 2022. The unit was returned to rated thermal power on June 2, 2022. Unit 2 began the inspection period at rated thermal power and power was reduced to approximately 92 percent on June 10, 2022, for main feedwater pump and turbine valve functional checks. The unit was returned to full rated power on June 11,
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
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated summer readiness of offsite and alternate alternating current (AC) power systems prior to the onset of excessive heat and hot weather conditions on June 13, 2022.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1 turbine driven auxiliary feedwater (AFW) Pump on May 21, 2022
- (2) Unit 1 north and south safety injection (SI) pumps on May 24, 2022
- (3) Unit 1 east and west residual heat removal (RHR) pumps on May 24, 2022
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 Zone 53; Unit 1 Control Room, elevation 633' -0" on April 15, 2022
- (2) Fire Zone 56; Unit 1 Auxiliary Cable Vault, elevation 620'-6" on April 29, 2022
- (3) Fire Zone 52; Unit 1 and Unit 2 Auxiliary Building, elevation 633' on May 10, 2022
- (4) Fire Zone 69; Unit 1 and Unit 2 Auxiliary Building, elevation 650' on May 17, 2022
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from April 4, 2022 to April 25, 2022:
03.01.a - Nondestructive Examination and Welding Activities.
Volumetric Examination of Component 1-SI-31-26F, ASME Section XI Category R-A/R1.20
Volumetric Examination of Bolts 1-24 in accordance with ASME Section XI Category B-G/B6.180
Volumetric Examination of Component 1-WD-644-03S, ASME Section XI Category R-A/R11.S
Surface Examination of ASME Class II Reactor Coolant Pump Seal Injection Lines 1, 2, 3, 4
Pressure Boundary Taper Fillet Welds 1, 4, 5, 8 on Charging Pump Bypass Line per Work Order 5550042-01 03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.
Visual Examination of Reactor Closure Head and All 58 and 2 Vent Penetrations in accordance with ASME Section XI Category N-729/B4.30 03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
Boric Acid Evaluation AR 2020-7358-1, 9/19/2020, 1-SI-153E has a Boric Acid Leak
Boric Acid Evaluation AR 2020-7371, 9/19/2020, BA Leak at 1-CS-440-4
Boric Acid Evaluation AR 2020-7379, 9/19/2020, BA Leak at 1-CS-441-4
Boric Acid Correction Action AR 2022-2559, 1-CS-451-3 Flange Leak
Boric Acid Correction Action AR 2022-2651, 1-RH-143 Boric Acid Leak
Boric Acid Correction Action AR 2022-2587, 1-SI-153W Pipe Cap Leak 03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.
Steam Generators 11, 12, 13, 14 examined 100 percent tubes by eddy current.
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 Unit 1 startup following refueling outage U1C31 on May 23, 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated Licensed Operator Requalification RQ-S-4704-U2 on June 8, 2022.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples 1 Partial)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Evaluation of 1-HE-15W west component cooling water (CCW) heat exchanger (HX)partial re-tubing on April 25, 2022
(Partial)
Loss of Auxiliary Building integrity on May 4, 2022
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 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) Unit 1 outage risk due to dual loop essential service water (ESW) outage on April 13, 2022
- (2) Hot connection on 2-TR21B transformer on May 2, 2022
- (3) Maintenance risk during east CCW/RHR work windows on June 7, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) AR 2022-2874; Stem Nut Replacement Reduces Anchor-Darling ECCS Valve Stroke Length, on April 8, 2022
- (2) AR 2022-2319; Unit 2 Train B CEQ [Containment Equalization] Fan Failed Surveillance Acceptance Criteria, on April 11, 2022
- (3) AR 2022-2701; Boric Acid Deposit on U1 Seal Water Injection Piping Suspect Through Wall, on April 11, 2022
- (4) AR 2022-3865; Hot Connection on 2-TR21B Transformer, on May 2, 2022
- (5) AR 2022-4450; Gas Void at 2-RH-125W, on May 18, 2022
- (6) AR 2022-4891; 2-HV-AFP-T2AC Room Cooler Suspected Compressor Issues, on June 7, 2022
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) Engineering Change (EC): 57459; Permanent storage of camera boxes on the Spent Fuel Handling Machine Bridge, on May 17, 2022
- (2) EC 54743; Unit 1 Moisture Separator Reheater (MSR) system controls upgrade, on Jun 30, 2022
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
- (1) U1C31 Containment Penetration 1-CPN-26 VT after Integrated Leak Rate Test (ILRT)on May 13, 2022
- (2) Upper Containment Airlock Local Leak Rate Test, 1-AIRLOCK-C650, after ILRT on May 16, 2022 (3)1-IMO-325 Leak Inspection after stem nut replacement on May 15, 2022
- (4) West RHR Pump Leak Test after seal cooler cleaning on May 16, 2022
- (5) Main turbine startup after high pressure turbine thrust bearing repairs on May 30, 2022
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage U1C31 activities from April 2 to May 31, 2022.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (6 Samples)
(1)12-MHP-4030-010-001; Ice Basket Weighing, on April 4, 2022
- (2) Unit 2 CD Diesel Generator Slow Start Monthly Surveillance, on April 11, 2022 (3)12-EHP-4030-051-256; Main Steam Safety Valve Setpoint Verification with Lift Assist Device, on April 11, 2022 (4)12-MHP-4050-FHP-005; Unit 1 Core Unload/Reload, on April 11, 2022 (5)12-MHP-4030-031-01; Inspection of the Recirculation Sump, on May 5, 2022 (6)2-IHP-4030-211-001A; Train A Solid-State Protection System Logic/Reactor Trip Breakers Surveillance, on May12, 2022
Inservice Testing (IP Section 03.01) (1 Sample)
(1)1-EHP-4030-134-202; Unit 1 Containment Integrated Leak Rate Test, as documented in Work Order (WO) 5544779 on May 12, 2022
Ice Condenser Testing (IP Section 03.01) (1 Sample)
(1)12-MHP-4030-010-001; U1C131 Ice Condenser Basket Weighing Surveillance, on April 4, 2022
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated the licensees compliance with the requirements specified in the Federal Emergency Management Agency-approved Alert and Notification System Design Report.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the Emergency Preparedness Organization.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program.
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) Emergency response facility drill, on June 28,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Workers exiting the radiologically controlled area (RCA) at the Radiation Protection Access Facility during the Unit 1 refueling outage
- (2) Workers and equipment exiting the Unit 1 Containment Lower Access Facility during the Unit 1 refueling outage
- (3) Workers exiting the RCA at the Turbine Building Access Facility during the Unit 1 refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) RWP 221186 U1C31; Radiological Diving to Repair the Upender
- (3) RWP 221148 U1C31; Steam Generator Primary Activities
- (4) RWP 221128 U1C31; Valve Activities in the Auxiliary Building, Containment, and Plant RCA High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) Unit 1 587' Auxiliary Building Reactor Coolant Filter Room
- (2) Unit 1 Containment Reactor Pit
- (3) Unit 1 Containment Steam Generator 1-3 Secondary Side
- (4) Unit 1 Accumulator 1-1 Annulus Ladder Entrance
- (5) Unit 1 Fuel Transfer Tube Room Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) Steam Generator high efficiency particulate air (HEPA) unit #1607, (1600 cubic feet per minute unit)
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation Radioactive Material Storage (IP Section 03.01) (1 Partial)
The inspectors evaluated the licensees performance in controlling, labeling, and securing the following radioactive materials:
(1)
(Partial)
Material Containers in the Radioactive Materials Building (RMB)
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS07: High Pressure Injection Systems (IP Section 02.06)===
- (1) Unit 1 (April 1, 2021 - March 31, 2022)
- (2) Unit 2 (April 1, 2021 - March 31, 2022)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (April 1, 2021 - March 31, 2022)
- (2) Unit 2 (April 1, 2021 - March 31, 2022)
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) July 1, 2021 through December 31, 2021 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) July 1, 2021 through December 31, 2021 EP03: Alert and Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) July 1, 2021 through December 31, 2021
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends that might be indicative of a more significant safety issue associated with U1C31 refueling outage main turbine vibrations during the weeks ending June 24 and June 30,
INSPECTION RESULTS
Spent Fuel Crane Bridge Modification Not Processed Correctly Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green FIN 05000315,05000316/2022002-01 Open/Closed Unable to Identify 71111.18 A Green finding was NRC-identified and associated with the licensees failure to process a permanent spent fuel handling crane bridge modification in accordance with licensee procedure IP ENG-001, Standard Design Process, Revision 0. Specifically, a permanent modification to a seismic category I structure, system, or component (SSC) was processed as a commercial change on May 26, 2020, which was prohibited by IP ENG-001.
Description:
On May 17, 2022, during tour of the 650-0 elevation of the Auxiliary Building, the inspectors observed items stored on the spent fuel handling crane bridge. The licensee implemented Permanent Engineering Change, (EC)-0000057459 that authorized storage of up to 8 boxes of camera equipment on the bridge. In addition, storage permit 30105224 was implemented for temporary storage of boxes beyond the EC requirements. Moreover, the inspector observed loose items that did not comply with either the storage permit or the EC.
The inspectors reviewed IP ENG-001, Standard Design Process, Revision 0. Section 1.2.6 states in part, any Yes answer to the following questions prohibits the use of Commercial Change for the proposed activity. Question 7 states in part, Are any affected Structure, System, or Component (SSC) seismic category I or required to be seismically mounted. The spent fuel handling crane bridge is a seismic category I SSC and required a yes answer to Question 7, which precluded the use of a Commercial Change for EC-0000057549.
However, the EC was processed as a commercial change on May 26, 2020 and none of the boxes on the crane bridge were seismically mounted.
Corrective Actions: Immediate corrective actions included removal of the loose items as well as reconfiguration of the boxes stored on the bridge.
Corrective Action References: AR 2022-4404
Performance Assessment:
Performance Deficiency: The licensees failure to adequately process EC-0000057549 was contrary to Section 1.2.6 of licensee procedure IP ENG-001, Standard Design Process, Revision 0, and was a performance deficiency. Specifically, the licensee processed the EC as a commercial change, which was prohibited by the IP ENG-001 procedure.
Screening: The inspectors determined the performance deficiency was more than minor because if left uncorrected, it would have the potential to lead to a more significant safety concern. Specifically, the failure to properly implement the engineering change process resulted in lack of updates to design bases documents associated with the spent fuel handling crane bridge and could result in modifications not adequately incorporating prior changes resulting in unanalyzed conditions, or exceeding design limits.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors determined that the finding had very low safety significance (Green) because each of the questions in Section E of Exhibit 3 was answered NO.
Cross-Cutting Aspect: Unable to Identify. No cross-cutting aspect was assigned to this finding because the inspectors were unable to identify a cross-cutting aspect that represents the cause or most-significant contributor as to why the performance deficiency exists using Inspection Manual Chapter 0310.
Enforcement:
Inspectors did not identify a violation of regulatory requirements associated with this finding.
Licensee-Identified Non-Cited Violation 71111.20 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: Technical Specification (TS) 5.4.1.a, Procedures requires, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Appendix A, February 1978. Regulatory Guide 1.33, Appendix A, Section 3.f.(1) recommended Maintaining Containment Integrity as a general plant operating procedure.
Contrary to the above, on May 14, 2022, the licensee failed to implement a written procedure covering a procedure recommended in Regulatory Guide 1.33, Appendix A, February 1978. Specifically, the licensee established procedure 12-MHP-5021-001-189 CPN-71 Service Penetration, Revision 015, to cover the procedure recommended by Section 3.f.(1) of Regulatory Guide 1.33, Appendix A. In part, Steps 3.2 and 3.6 of this procedure required service penetration CPN-71 to be placed in service to provide containment integrity and containment closure capability during Mode 5 and when containment closure was required during service penetration removal, then at least one cover be installed. However, during Mode 5 with containment integrity required, the licensee removed an integrated leak rate test device from the outboard CPN-71 service penetration flange prior to closure of its inboard cover.
Significance/Severity: Green. The inspectors evaluated the significance of this issue using Inspection Manual Chapter 0609, Appendix H, "Containment Integrity Significance Determination Process and screened the issue Green in Step 2.1.
Corrective Action References: AR 2022-4243 Licensee-Identified Non-Cited Violation 71124.08 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: Title 10 CFR 37.45
- (d) states, the licensee shall coordinate with the local law enforcement agency (LLEA) at least every 12 months, or when changes to the facility design or operation adversely affect the potential vulnerability of the licensee's material to theft, sabotage, or diversion.
Title 10 CFR 37.55
- (a) states, each licensee shall be responsible for the continuing effectiveness of the security program. Each licensee shall ensure that the security program is reviewed to confirm compliance with the requirements of this subpart and that comprehensive actions are taken to correct any noncompliance that is identified. The review must include the radioactive material security program content and implementation. Each licensee shall periodically (at least annually) review the security program content and implementation.
Contrary to the above, from July 30, 2015 to December 22, 2021, the licensee failed to (1)coordinate with the local law enforcement agency (LLEA) at least every 12 months, or when changes to the facility design or operation adversely affect the potential vulnerability of the licensee's material to theft, sabotage, or diversion, and
- (2) periodically (at least annually)review the security program content and implementation.
Significance/Severity: Green. The inspectors assessed the significance of the finding using IMC 609 Appendix D, Public Radiation Safety SDP. The inspectors evaluated the finding by applying the Part 37 Subpart A, B or C finding branch of the SDP. The finding was determined to be of very low safety significance (i.e., Green) because:
- (1) there was no actual loss of material,
- (2) access was not granted to an individual who is not trustworthy and reliable,
- (3) there was not an ineffective security zone, and
- (4) there was not a deficient security zone.
Corrective Action References: AR 2021-9421 and AR 2021-9047
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On June 30, 2022, the inspectors presented the integrated inspection results to Mr. Q. S. Lies, Senior VP and Chief Nuclear Officer, and other members of the licensee staff.
On April 25, 2022, the inspectors presented the inservice inspection results to Mr. J. Gebbie, Senior VP and Chief Nuclear Officer, and other members of the licensee staff.
On April 28, 2022, the inspectors presented the radiation protection baseline inspection results to Mr. S. Lies, Site Vice President, and other members of the licensee staff.
On May 6, 2022, the inspectors presented the emergency planning program inspection results to Mr. J. Gebbie, Senior VP and Chief Nuclear Officer, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
PMI-5055
Winterization/Summerization
008
Procedures
PMP-5055-001-
001
Winterization/Summerization
039
Corrective Action
Documents
AR 2022-3787
Repeat Maintenance Preventable Functional Failure
04/29/2022
Corrective Action
Documents
AR 2022-4269
1-QT-506 not Stroking Properly.
05/16/2022
Drawings
OP-1-5106A
Flow Diagram Aux-Feedwater Unit 1
068
Drawings
OP-1-5142
Flow Diagram Emergency Core Cooling (SIS)
Drawings
OP-1-5143
Flow Diagram Emer. Core Cooling (RHR) Unit No. 1
Miscellaneous
GT 2022-3778
Track completion of 156-107T, LU1 TDAFP
05/02/2022
Procedures
1-OHP-4021-017-
2
Placing In Service the Residual Heat Removal System
Procedures
1-OHP-4030-108-
051N
North Safety Injection Pump System Test
Procedures
1-OHP-4030-108-
051S
South Safety Injection Pump System Test
23
Procedures
1-OHP-4030-156-
017T
Turbine Driven Auxiliary Feedwater System Test
031
Corrective Action
Documents
AR 2022-3408
Unpermitted combustibles Found in Level B Area
04/20/2022
Corrective Action
Documents
AR 2022-4139
Unattended Combustibles
05/10/2022
Corrective Action
Documents
AR 2022-4386
NRC Identified Degraded Fire Hose at FHC 84
05/17/2022
Fire Plans
2-5975
Fire Hazard Analysis Plan EL 601' 609 & 620' 6" to 625' 10"
004
Fire Plans
2-5976
Fire Hazard Analysis Turbine Building Main Floor Elevation
633'-0" Units 1 & 2
014
Procedures
2-FPP-2270-
066-055
Fire Detection Instrument Channel Functional Test
(U-1 Zones 7, 16, 22, 24, and Unit 2 Zones 2, 15, 16, 20)
Procedures
2-FPP-2270-
066-057
Fire Detection Instrumentation Channel Functional Test
(U-2 Zones 6, 9, 22, 24, 26, and Shared Zone 4)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
2-FPP-2270-
066-058
Fire Detector Instrumentation Channel Functional Test
(U-1 Zones 10, 11, 13[RCT], 14[4kV], 18, 20, 22 and Shared
Zone 5)
Procedures
2-FPP-4030-
066-201
Fire Detection Instrumentation Operational Test (U-1 Zone
16, U-2 Zone 11 and Shared Zone 2)
Procedures
2-FPP-4030-
066-205
Fire Detection Instrumentation Channel Operational Test
(U-1 Zones 6, 8, 9, 12, 13[4kV], 14[RCT], 15[4kV], 17, 19,
21, 23, 24.
Procedures
PMP-2270-CCM-
001
Control of Combustible Materials
050
Work Orders
55537568-01
OPFP, 1-EFR-FIREZONE 22, Channel Functional Test
07/08/2020
Work Orders
1-EFR-FIRE-ZONE-4 OPFP, 1-EFR-FIREZONE-4, Channel
Functional Test
07/29/2021
Corrective Action
Documents
2011-11547
Step Change in Steam Generator Eddy Current Indication
Count
10/05/2011
Corrective Action
Documents
20-7358-1
1-SI-153E has a Boric Acid Leak
09/19/2020
Corrective Action
Documents
20-7371
BA Leak at 1-CS-440-4
09/19/2020
Corrective Action
Documents
20-7379
BA Leak at 1-CS-441-4
09/19/2020
Corrective Action
Documents
20-7699
Improper Evaluation of BMI Inspection Relevant Conditions
09/25/2020
Corrective Action
Documents
20-8218-12
Revise EHI-5054-RHI Revision 2, Reactor Head Inspection
Program
01/28/2021
Corrective Action
Documents
22-2559
1-CS-451-3 Flange Leak
04/02/2022
Corrective Action
Documents
22-2587
1-SI-153W Pipe Cap Leak
04/03/2022
Corrective Action
Documents
22-2651
1-RH-143 Boric Acid Leak
04/04/2022
Corrective Action
Documents
Resulting from
22-2744
Limited Coverage Obtained During ISI Examination
04/06/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
Engineering
Changes
57714
Use 2 to 1 Taper Fillet Welds on Charging Pump Bypass
Lines
NDE Reports
51-9280743-000
DC Cook Unit 1 Steam Generator Condition Monitoring for
Cycles 26 and 27 and Final Operational Assessment for
Cycles 28, 29, and 30.
NDE Reports
C10013391002
Liquid Penetrant Examination Report
04/08/2022
NDE Reports
U1-UT-22-005
UT Calibration/Examination
04/05/2022
NDE Reports
U1-UT-22-008
UT Calibration/Examination
04/06/2022
NDE Reports
U1-UT-22-035
UT Calibration/Examination
04/20/2022
NDE Reports
U1-VT-22-016
Visual Examination of Boric Acid (VT-BM)
04/05/2022
NDE Reports
U1-VT-22-023
Visual Examination of Boric Acid (VT-BM)
04/10/2022
Procedures
2-QHP-5050-
NDE-001
Liquid Penetrant Examination
Procedures
EHI-5054-RHI
Reactor Head Inspection Program
Procedures
MRS-GEN-1240
Positive Verification Procedure
Procedures
SGP-PLG-RIB-
Mechanical Ribbed Plugging of Steam Generator Tubes
5.0
Procedures
WDI-STD-1186
Generic Ultrasonic Examination Procedure for Austenitic
Welds in accordance with PDI-UT-2
Work Orders
55550042-01
to 1 Fillets
09/30/2020
Miscellaneous
DIT-10000-00
Unit 1 Cycle 30 End-of-Cycle (EOC) Time-to-Boil Information
03/02/2022
Miscellaneous
DIT-10001-00
Unit 1 Cycle 31 Beginning-of-Cycle (BOC) Time-to-Boil
Information
03/07/2022
Miscellaneous
PMP-4015-RMP-
001
Reactivity Management Program, Data Sheet 1; Unit 1 Cycle
TREVI Testing Downpower and Shutdown
03/15/2022
Miscellaneous
RQ-S-4702-U2-
T1
Period 4702 U2 Training Scenario T1
Procedures
1-OHP-4021-001-
2
Reactor Startup
069
Procedures
1-OHP-4021-001-
003
Power Reduction
Procedures
1-OHP-4021-001-
006
Power Escalation
086
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation
Surveys
1-OHP-4023 E-0
Reactor Trip or Safety Injection
Corrective Action
Documents
AR 2022-3902
Aux Building Bent on 650' Elevation Opened During
Refueling
05/03/2022
Work Orders
C10007737002
1-HE-15W, Perform Tube Plug, Without Tube
05/15/2022
Work Orders
MTM, 1-HE-15E, Perform Inprocess Test/Check For Tube
Leaks
04/15/2022
Work Orders
1-HE-15E, Perform Partial Retube of CCE Heat Exchanger
05/18/2022
Work Orders
MTM, 1-HE-15E, Disassemble/Reassemble ESW Side of
05/15/2022
Work Orders
MTM, 1-HE-15W, Inspect for Tube Leaks (As-Left Test)
05/15/2022
Work Orders
Vendor, 1-HE-15W, Perform Partial Tube Replacement
05/15/2022
Work Orders
Vendor 1-HE-15W, Re-install Channel Head
05/15/2022
Work Orders
West ESW Train Flow Verification
05/06/2022
Work Orders
East ESW Train Flow Verification
04/20/2022
Corrective Action
Documents
AR 2022-3865
Hot Connection on 2-TR21B Transformer
05/02/2022
Miscellaneous
Unit 1 and 2 Cycle 122, Work Week 10 Risk
Procedures
2-OHP-4021-082-
21
Removal and Restoration of Power to 600V Bus 21B and
Associated Motor Control Center
Procedures
2-OHP-4022-082-
005
Loss of Power to a 600V Emergency Bus
001
Work Orders
C10023002
2-TTR21B Hot Connection
05/02/2022
Calculations
NEID-2DCP650-
2
2-DCP-650, CEQ Fan Timing Relay Setpoint Calculation
Corrective Action
Documents
AR 2022-2319
Unit 2 CEQ Fan Quarterly Surveillance Failed
03/24/2022
Corrective Action
Documents
AR 2022-2701
Boric Acid Deposit on U1 SWI Piping Suspect Through Wall
04/05/2022
Corrective Action
Documents
AR 2022-2874
Anchor-Darling Valve Stem Nuts Replacement
04/08/2022
Corrective Action
Documents
AR 2022-3865
Hot Connection on 2-TR21B Transformer
05/02/2022
Corrective Action
AR 2022-4450
Gas Void at 2-RH-125W
05/12/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Corrective Action
Documents
AR 2022-4891
2-HV-AFP-T2AC Room Cooler Suspected Compressor
Issues
06/03/2022
NDE Reports
2-QHP-5050-
NDE-001
Liquid Penetrant Examination
Operability
Evaluations
AR 2022-2874
Stem Nut Replacement Reduces Anchor-Darling ECCS
Valve Stroke Length
Procedures
2-IHP-4030-228-
005B
Train B CEQ Fan Surveillance and ESF Response Time
Test
Work Orders
55448317
2-IMO-350-ACT, Perform As-Found/As-Left Diagnostic Test
04/26/2021
Work Orders
55448318
2-IMO-340-ACT, Perform As-Found/As-Left Diagnostic Test
04/26/2021
Work Orders
55527055
2-ICM-306-ACT, Perform As-Found/As-Left Diagnostic
04/09/2021
Work Orders
55530574
As-Left Diagnostic Test
09/26/2020
Work Orders
2-ICM-305-ACT, Perform As-found/As-Left Diagnostic
04/19/2021
Corrective Action
Documents
AR 2022-4044
EC-0000057459 Not Properly Implemented
05/17/2022
Engineering
Changes
Unit 1 Moisture Separator Reheater (MSR) System Controls
Upgrade
Engineering
Changes
Storage of Camera Boxes on Spent Fuel Handling Machine
Bridge
001
Procedures
IP ENG-001
Standard Design Process
001
Work Orders
TPG, R01, PMT of Components Relocated in Panel 1-C
05/17/2022
Work Orders
TPG, R01, Control Room, Demo Panel 1-C and Rack 1-CR
04/10/2022
Work Orders
WO-
C10001471063
TPG, MSR, Repair Fire Seal F6163
04/01/2022
Work Orders
WO-
C10001471065
TPG, MSR, Repair Fire Seal F6123
04/01/2022
Work Orders
WO-
C10001471066
TPG, R1P, MSR, EC-54743, Install Cables, Control Room
03/21/2022
Work Orders
WO-
C10001471078
TPO, U1, MSR, EC-54743, Install & Terminate Panel T
1-SG-21
04/27/2022
Work Orders
WO-
C10001471080
TPG, MSR, Repair Fire Seal F6163 (FCR-54743-010)
04/12/2022
Work Orders
WO-
TPG, MSR, Repair Fire Seal F6167 (FCR-54743-010)
04/23/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
C10001471082
Work Orders
WO-
C10001471084
TPG, P1P, MSR, EC-54743, Install Cables, Control Room
04/13/2022
Work Orders
WO-
C10001471096
TPG, U1, MSR, Incorporation of RFI-54743-054
05/09/2022
Work Orders
WO-
C10001858020
U1, MSR Re-Install Temp Removed Components Panel 1-C
04/19/2022
Work Orders
WO-
C1000858019
U1, MSR, Temp Remove Components 1-C
04/14/2022
Drawings
DC-03871
Personnel Airlock (Upper) General Arrangement and
Drawing Index
Drawings
OP-1-5143
Flow Diagram Emergency Core Cooling (RHR)
Engineering
Changes
Removal of Bellows, Protective Cover, and Weld Build Up
for Containment Penetration 1-CPN-26
Procedures
1-OHP-4021-050-
001
Turbine Generator Normal Startup and Operation
05/30/2022
Procedures
2-QHP-5070-
NDE-005
Visual Examinations: Metallic Containment Pressure
Retaining Components and Their Integral Attachments.
007
Work Orders
OPS: 1-IMO-325; Perform PMT Leak Inspection
06/02/2022
Work Orders
WO C10007271-
013
U1C31 Containment Penetration CPN-26 VT after ILRT
05/13/2022
Work Orders
West RHR Leak Rate Test
05/16/2022
Work Orders
WO-
C10012372001
MTI, 1-AIRLOCK-C650, Perform 12-IHP-4030-046-002 Seal
LRT
05/17/2022
Calibration
Records
AR 2022-2559
1-CS-451-3 Flange Leak
04/02/2022
Calibration
Records
AR 2022-2574
Evidence of Prior Leak on Reactor Pit Wall
04/02/2022
Corrective Action
Documents
AR 2022-2501
1-SI-167-2 Downstream Cap Is Leaking onto Carbon Steel
03/31/2022
Corrective Action
Documents
AR 2022-2503
Boric Acid Leaking from Pipe Cap 1-SI-159E
03/31/2022
Corrective Action
Documents
AR 2022-2504
1-NS-622 Boric Acid Leak
03/31/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
AR 2022-2506
1-NLP-151-1E Boric Acid Leak
03/31/2022
Corrective Action
Documents
AR 2022-2551
Boric Acid Leaking from Packing on 1-IRV-147
04/02/2022
Corrective Action
Documents
AR 2022-2560
1-SI-169-L1 Boric Acid Leak
04/02/2022
Corrective Action
Documents
AR 2022-2561
1-QRV-114 Boric Acid Leak
04/02/2022
Corrective Action
Documents
AR 2022-2571
- 14 RCP Excessive Leakage
04/02/2022
Corrective Action
Documents
AR 2022-2587
1-SI-153W Pipe Cap Leak
04/03/2022
Corrective Action
Documents
AR 2022-2604
1-CS-119N 80 DPM Leak
04/03/2022
Corrective Action
Documents
AR 2022-2646
RCP Shaft Seal is Overflowing Down the Side of the
Pump
04/04/2022
Corrective Action
Documents
AR 2022-3333
Two Positive WBCs from Changing Steam Generator HEPA
Filters
04/18/2022
Corrective Action
Documents
AR 2022-3363
Two Divers with Positive Whole-Body Counts
04/19/2022
Corrective Action
Documents
AR 2022-4240
Potential Uptakes during Vertical Missile Block Installation
05/13/2022
Miscellaneous
Operational Narrative Logs (April 01-04, 2022)
Miscellaneous
GT 2020-7120-50
SU1C31 Refueling Outage Shutdown Safety Plan Report
(Outage Milestone 21B, GT 2020-7120-50)
Miscellaneous
U1C31 Refueling
Outage Shutdown
Safety Plan
The Shutdown Safety Plan Report
2/25/2022
Procedures
1-OHP-4030-001-
2
Containment Inspection Tours
Procedures
2-MHP-4050-
FHP-023
Reactor Vessel Head Removal with Fuel in The Vessel
Procedures
PMP-2060-WHL-
001
Work Hour Limitation and Fatigue Management
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
AR 2021-9935
One Cup of Oil Discharged from DG2CD 2R Bank during
Blowdown.
2/08/2021
Miscellaneous
2CD EDG
DG2CD System Engineer's Leak Tracking Log.
04/11/2022
Procedures
1-EHP-4030-134-
2
014
Procedures
2-EHP-4030-
051-256
Main Steam Safety Valve Setpoint Verification with Lift
Assist Device
03/31/2022
Procedures
2-MHP-4030-
010-001
Ice Condenser Basket Weighing Surveillance
Procedures
2-MHP-4030-
031-001
Inspection of the Recirculation Sump
Procedures
2-MHP-4050-
FHP-005
Core Unload/Reload and Incore Shuffle
Procedures
2-OHP-4030-232-
27CD
CD Diesel Generator Operability Test (Train A) Attachment 1
DG2CD Slow Speed Start
068
Procedures
260934-01
Perform Recirculation Sump Inspection
Work Orders
55557124-02
MTM, 1-STN-320 Recirculation Sump Inspection
05/18/2021
Work Orders
C10004756001
MTI, 2-IHP-4030-211-001A, TR A SSPS LOGIC/RX TRIP
BKRS SURV
05/12/2022
Work Orders
1-OME-ICE-COND Ice Basket Weighing Surveillance
04/21/2022
Corrective Action
Documents
AR 2020-4409
Prompt NRC Notification 4-hour Report for EP Sirens
05/27/2020
Miscellaneous
Alert and Notification System Evaluation Report
Corrective Action
Documents
AR 2020-4343
ERO Shift Staffing Requirements Were Not Met
05/23/2020
Corrective Action
Documents
AR 2020-9382
Revise EPP-100 with New ERONS Instruction
2/03/2021
Corrective Action
Documents
AR 20202-5493
First Half 2020 Unannounced Drill Was 8 Days Late
07/09/2020
Corrective Action
Documents
AR 2021-10362
Everbridge System Down
2/22/2021
Corrective Action
Documents
AR 2021-1871
ERO Use of Procedure Was Not Up to Standards
2/23/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
AR 2021-7359
EOF Activation Time During Drill Exceeded CEP
Requirements
08/26/2021
Corrective Action
Documents
AR 2021-7950
ERO Notification System ERONS/Everbridge
09/22/2021
Corrective Action
Documents
AR 2021-7980
ERO Exercise Result
09/21/2021
Corrective Action
Documents
AR 2022-0327
EOF Full Staffing Level Not Met Within 1 Hour Expectation
01/12/2022
Corrective Action
Documents
AR 2020-3833
U1 Red NRC Phone Did Not Ring When NRC Called
05/06/2020
Corrective Action
Documents
AR 2020-5910
NRC Red Phone Not Functioning
07/24/2020
Corrective Action
Documents
AR 2020-6553
Emergency Plan SCBA's in the Control Room
08/20/2020
Corrective Action
Documents
AR 2020-7626
NRC Red Phone Not Functioning
09/24/2020
Corrective Action
Documents
AR 2020-9382
Converting 2020 Unannounced Drive-In Drill to Call-Only
11/10/2020
Corrective Action
Documents
AR 2021-10289
Berrien County EOC Ringdown Phone Inoperable
2/18/2021
Corrective Action
Documents
AR 2021-1870
Review/Correct MIDAS Issues During ERO Drill
2/25/2021
Corrective Action
Documents
AR 2021-2965
Poor Procedure Change Review and 50.54q Screening by
04/12/2021
Corrective Action
Documents
AR 2021-4717
NRC Red Phone Issues
05/21/2021
Corrective Action
Documents
AR 2021-4818
NRC HPN Phone Issues
05/25/2021
Corrective Action
Documents
AR 2021-4910
10CFR50.54q Screenings
05/27/2021
Corrective Action
Documents
AR 2021-5056
NRC Phone System Wide Failure
06/02/2021
Corrective Action
Documents
AR 2021-5149
TSC NRC RSCL Inoperable
06/07/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
AR 2021-5654
Control Room NRC Red Phones Not Working
06/24/2021
Corrective Action
Documents
AR 2021-6449
EOC Phones Failed Daily Testing in SAS and CAS
07/26/2021
Corrective Action
Documents
AR 2021-7980
ERO Exercise Result
09/21/2021
Corrective Action
Documents
AR 2021-7982
ERO Exercise Result
09/23/2021
Corrective Action
Documents
AR 2021-8901
BCSD Ringdown Phone Not Working as Designed
10/29/2021
Corrective Action
Documents
AR 2021-9059
09/21/2021
Corrective Action
Documents
AR 2021-9069
OSC Facility was Declared to be Minimum Staff
11/04/2021
Corrective Action
Documents
AR 2022-0343
Backup Method Required to Notify MSP During ERO Drill
01/12/2022
Corrective Action
Documents
AR 2022-1277
RMT-2080-PPA-001 Data Sheet Document Incorrect
2/15/2022
Corrective Action
Documents
AR 2022-1317
TPD-600-EPT Silent on Implementation of Planning
Standard
2/16/2022
Corrective Action
Documents
AR 2022-1455
Conduct of HP Drills
2/22/2022
Corrective Action
Documents
GT 2021-1685
Document Items from the ERO Drill
2/22/2021
Miscellaneous
D.C. Cook Nuclear Plant Emergency Plan
Miscellaneous
D.C. Cook Nuclear Power Plant Unusual Event (HU4.1)
Declaration Evaluation Report
2/15/2022
Miscellaneous
Emergency Response Resource Readiness
Sample
From 2020-
21
Miscellaneous
DC Cook Nuclear Power Plant August 25, 2020, Training
Drill
09/24/2020
Miscellaneous
DC Cook Nuclear Power Plant Health Physics Drill
01/26/2021
Miscellaneous
DC Cook Nuclear Power Plant June 2, 2021, Training Drill
09/02/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
DC Cook Nuclear Power Plant NRC Evaluated Exercise
10/25/2021
Miscellaneous
AR 2021-1936
2/23 Training Drill EAL Classification Different than Manual
2/23/2021
Miscellaneous
PMP-2080-EPP-
101
Emergency Classification
Miscellaneous
Emergency Response Facility Drill Scenario (June 28, 2022)
Corrective Action
Documents
AR 2022-2860
Posting of 609' Demin During Resin Sluice
04/07/2022
Corrective Action
Documents
Resulting from
Inspection
AR 2022-3456
Alpha Surveys and Smears not Consistent
04/21/2022
Engineering
Evaluations
RP-07-02
Technical Basis for D. C. Cook's Alpha Program
Miscellaneous
Reactor Cavity Upender Dive Repair Sentinel Dosimetry
Records
04/09/2022
Miscellaneous
LHRA and VHRA Door Verification
03/23/2022
Miscellaneous
Radiography Shot Plan - Unit 1 RHR
04/20/2022
Miscellaneous
Historical Alpha
Data
Characterization
Data
Historical Alpha Data Characterization Data
Various
Procedures
2-THP-6010-
RPP-019
Locked High Radiation Area and Very High Radiation Area
Verification
Procedures
2-THP-6010-
RPP-301
Radiation Protection Actions for Radiological Controlled
Area Material Control
Procedures
2-THP-6010-
RPP-401
Performance of Radiation and Contamination Surveys
Procedures
2-THP-6010-
RPP-407
Special Radiological Evolutions
Procedures
2-THP-6010-
RPP-413
Radiological Controls for Nuclear Diving Operations
Procedures
2-THP-6010-
RPP-418
Radiological Postings
Procedures
PMP-6010-RPP-
Radiation Work Permit Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
006
Radiation
Surveys
U1C31 Refueling Outage Air Sample Data
Various
Radiation
Surveys
CNP 2204-00323
U1 U/C Lower Cavity Upender Repair Dive
04/09/2022
Radiation
Surveys
CNP-2204-00508
Unit 1 591' RHR Vestibule Internals of ICM Valves
04/15/2022
Radiation
Surveys
CNP-2204-00535
Unit 1 Lower Containment Steam Generator Platforms 1 and
04/18/2022
Radiation
Surveys
CNP-2204-00562
U1 C31 591' RHR Vestibule Reassembly of 1-ICM-305
04/17/2022
Radiation
Surveys
CNP-2204-00587
Unit 1 Lower Containment 615' Initial Breach of SI-158-L2
04/18/2022
Radiation
Surveys
CNP-2204-00592
Unit 1 Lower Containment Steam Generator Platforms 2 and
04/18/2022
Radiation
Surveys
CNP-2204-00598
Unit 1 591' RHR Vestibule Breach of 1 DCR-205
04/18/2022
Radiation
Surveys
CNP-2204-00660
Unit 1 Lower Containment 598' Initial Breach of 1-SI-170-L3
04/21/2022
Radiation Work
Permits (RWPs)
21128
U1C31 - Valve Activities in the Auxiliary, Containment, &
Turbine Buildings & Plant Radiologically Controlled Areas
(RCAs)
Radiation Work
Permits (RWPs)
21130
U1C31-Perform Radiography in Auxiliary, Containment, &
Turbine Buildings & Plant Radiologically Controlled Areas
(RCAs)
Radiation Work
Permits (RWPs)
21148
U1C31 - Steam Generator Primary Activities
Radiation Work
Permits (RWPs)
21186
U1C31 - Support Work for Diving Activities
Miscellaneous
Total Effective Dose Evaluation (TEDE) for SI-170-L3
04/20/2022
Procedures
2-THP-6010-
RPP-315
HEPA Equipment Issue, Control, and Maintenance
Procedures
2-THP-6010-
RPP-403
Portable Air Sampling
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
2-THP-6010-
RPP-405
Analysis of Airborne Radioactivity
Corrective Action
Documents
AR 2021-7962
RMB Roll Up Door Left Open
09/22/2021
Corrective Action
Documents
AR 2021-9047
No Objective Evidence Identified for 10 CFR 37.55
11/04/2021
Corrective Action
Documents
AR 2021-9421
Reporting Category 1 and Category 2 Quantities to LLEA
11/17/2021
71151
Miscellaneous
NRC Performance Indicator Data; Emergency
Preparedness - ERO Participation Drill
3rd Quarter
21
through 4th
Quarter
21
71151
Miscellaneous
NRC Performance Indicator Data; Emergency
Preparedness - Drill/Exercise Performance
3rd Quarter
21
through 4th
Quarter
21
71151
Miscellaneous
MSPI Deviation Report MSPI High Pressure Systems
(10/01/2021 - 03/31/2022) Unit 1
71151
Miscellaneous
MSPI Deviation Report MSPI High Pressure Systems
(10/01/2021 - 03/31/2022) Unit 2
71151
Miscellaneous
MSPI Deviation Report MSPI Cooling Water Systems
(10/01/2021 - 03/31/2022) Unit 1
71151
Miscellaneous
Operational Narrative Logs (October 2021 - March 2022)
71151
Miscellaneous
MSPI Deviation Report MSPI Cooling Water Systems
(10/01/2021 - 03/31/2022) Unit 2
0