IR 05000397/2021010
| ML21236A264 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 08/29/2021 |
| From: | Ami Agrawal Division of Reactor Safety IV |
| To: | Schuetz R Energy Northwest |
| References | |
| IR 2021010 | |
| Download: ML21236A264 (17) | |
Text
August 29, 2021
SUBJECT:
COLUMBIA GENERATING STATION - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000397/2021010
Dear Mr. Schuetz:
On July 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Columbia Generating Station. On August 2, 2021 the NRC inspectors 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.
The NRC inspection team reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Finally, the team reviewed the stations programs to establish and maintain a safety conscious work environment and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews, the team found that your organization appeared to have a safety conscious work environment where individuals felt free to raise concerns without fear of retaliation. Most expressed positive experiences after raising issues to their supervisors and documenting issues in condition reports, and all individuals indicated that they would not hesitate to raise safety concerns.
However, the team noted that several individuals brought up continuing morale concerns, consistent with the results of the previous problem identification and resolution inspection (NRC Problem Identification and Resolution Inspection Report 05000397/2019010). The team noted that if not addressed properly, these morale concerns could erode the individuals willingness to bring up safety concerns in the future.
No findings or violations of more than minor significance were identified during this inspection. 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, Signed by Agrawal, Ami on 08/29/21 Ami N. Agrawal, Team Leader Inspection Programs & Assessment Team Division of Reactor Safety Docket No. 05000397 License No. NPF-21
Enclosure:
As stated
Inspection Report
Docket Number: 05000397 License Number: NPF-21 Report Number: 05000397/2021010 Enterprise Identifier: I-2021-010-0003 Licensee: Energy Northwest Facility: Columbia Generating Station Location: Richland, WA Inspection Dates: July 12, 2021 to July 30, 2021 Inspectors: F. Ramirez Munoz, Senior Reactor Inspector (Team Lead)
H. Freeman, Senior Project Engineer N. Greene, Senior Health Physicist P. Niebaum, Senior Resident Inspector R. Smith, Senior Resident Inspector Approved By: Ami N. Agrawal, Team Leader Inspection Programs & Assessment Team Division of or Reactor Safety Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution inspection at Columbia Generating 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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
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 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin tele-work. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 02.04)
- (1) The inspectors performed a biennial assessment of the licensees corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment.
Corrective Action Program Effectiveness: The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems. The inspectors sampled over 220 condition reports and their associated cause evaluations, if applicable. The inspectors also conducted a five-year review of the high pressure core spray system and the emergency chilled water system, which included review of failures, maintenance issues, surveillances, corrective and preventive maintenance, reliability, and maintenance rule performance. In addition, the inspectors reviewed 16 findings and violations issued during the biennial period.
Operating Experience, Self-Assessments and Audits: The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits, and self-assessments. The sample included industry operating experience communications like 10 CFR Part 21 notifications and other vendor correspondence, NRC generic communications, publications from various industry groups, and site evaluations. The sample also included reviews of licensee self-assessments and internal audits.
Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety conscious work environment. The team interviewed 55 individuals, attended routine meetings, interviewed the Employee Concerns Program Manager, and reviewed employee concerns files.
INSPECTION RESULTS
Assessment 71152B Corrective Action Program Assessment Based on the samples reviewed, the team determined that the licensees corrective action program complied with regulatory requirements and self-imposed standards. The licensees performance in each of the areas of Problem Identification, Problem Prioritization and Evaluation, and Corrective Actions adequately supported nuclear safety.
Effectiveness of Problem Identification: Based on the samples reviewed, the team determined that the licensee's performance in this area adequately supported nuclear safety. Overall, the team found that the licensee was identifying and documenting problems at an appropriately low threshold that supported nuclear safety.
Effectiveness of Prioritization and Evaluation of Issues: Overall, the team found that the licensee was appropriately prioritizing and evaluating issues to support nuclear safety. Of the samples reviewed, the team found that the licensee correctly characterized each condition report as to whether it represented a condition adverse to quality, and then prioritized the evaluation and corrective actions in accordance with program guidance.
In January 2021, the licensee began using the IBM Watson artificial intelligence system to pre-screen all condition reports instead of the departmental performance improvement specialists that had previously performed this task. The artificial intelligence system pre-screens the condition report to determine the priority (whether it represents a condition adverse to quality or not), category (A, B, C, D, etc.), and responsible department based upon program inputs. The inspectors noted that following the artificial intelligence pre-screen, 12 percent of condition reports needed to be corrected for priority and 14 percent of condition reports needed to be corrected for severity. However, the final determination review is still performed by the management review team and changes are incorporated back into the artificial intelligence algorithm. As such, the team did not identify any concerns with the licensees implementation of this pre-screening process.
Effectiveness of Corrective Actions: Overall, the team concluded that the licensee's corrective actions supported nuclear safety. Specifically, the Columbia Generating Station developed effective corrective actions for the problems evaluated in the corrective action program and generally implemented these corrective actions in a timely manner commensurate with their safety significance. As part of this inspection, the team selected the plants high pressure core spray and emergency chilled water systems for a focused review within the corrective action program. For these systems, the team performed sample selections of condition reports, looking at the adequacy of the licensee's evaluation process for determining which items are placed in the corrective action process, and the corrective actions taken. The team did not identify any concerns with these systems that were not already being addressed by the station's monitoring and corrective action programs.
Assessment 71152B Use of Self-Assessment & Audits The team reviewed a sample of Columbia Generating Station's departmental self-assessments and audits to assess whether performance trends were regularly identified and effectively addressed. The team also reviewed audit reports to assess the effectiveness of assessments in specific areas. Overall, the team concluded that the licensee had an adequate departmental self-assessment and audit process.
Assessment 71152B Operating Experience The team reviewed a variety of sources of operating experience including NRC generic communications, and publications from various industry groups, such as the Nuclear Energy Institute (NEI) and Electric Power Research Institute (EPRI). The team determined that the Columbia Generating Station is adequately screening and addressing issues identified through operational experience that apply to the station and that this information is evaluated in a timely manner once it is received.
Assessment 71152B Safety Conscious Work Environment (SCWE)
The team conducted safety conscious work environment interviews with 55 employees from five different disciplines that included electrical maintenance, instrumentation and controls, mechanical maintenance, operations, and security. The purpose of these interviews was (1)to evaluate the willingness of the licensee staff to raise nuclear safety issues, either by initiating a condition report or by another method,
- (2) to evaluate the perceived effectiveness of the corrective action program at resolving identified problems, and
- (3) to evaluate the licensee's safety conscious work environment (SCWE). The team also observed interactions between employees during routine daily production meetings, operational focus meetings and management condition report review meetings. The team interviewed the Employee Concerns Program Manager and reviewed the results of the latest safety culture surveys and a sample of case files that may relate to safety conscious work environment.
The team found that the licensee had a safety conscious work environment where individuals felt free to raise concerns without fear of retaliation. Most expressed positive experiences after raising issues to their supervisors and after documenting issues in condition reports, and all individuals indicated that they would not hesitate to raise safety concerns, through at least one of the several means available at the station. Based on feedback from these interviews regarding anonymous condition reports, the station should consider enhancing communications with plant personnel so that it is better understood how anonymous condition reports are treated. Additionally, the team noted that several individuals brought up continuing morale concerns, particularly mechanical maintenance, electrical maintenance and instrument and controls. These morale concerns appear to be caused by union contract negotiations and arbitration and its impact on the relationship between the staff and senior management. The team noted that the morale concerns are consistent with the results of the previous problem identification and resolution inspection (NRC Problem Identification and Resolution Inspection Report 05000397/2019010) and if not addressed properly could erode the individuals willingness to bring up safety concerns in the future.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On August 2, 2021, the inspectors presented the biennial problem identification and resolution inspection results to Robert Schuetz and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Corrective Action AR-xxxxxx 224656, 231738, 276051, 300881, 303254, 322254, 333679,
Documents 334459, 353023, 355482, 358871, 359059, 359206, 360595,
2801, 366178, 366179, 366189, 367730, 368369, 368573,
369273, 369740, 369803, 371289, 372512, 372892, 373494,
376273, 376387, 378159, 378162, 378527, 378892, 382784,
386750, 387435, 388173, 388855, 389079, 389652, 389753,
389808, 389856, 389987, 390029, 390041, 390048, 390379,
390486, 390800, 390812, 391337, 391579, 391893, 392031,
393112, 393215, 393268, 393270, 393438, 393618, 393990,
393998, 394506, 394579, 394892, 395031, 395167, 395246,
395843, 396051, 396543, 396587, 397224, 397451, 397558,
398065, 398820, 398943, 399263, 399463, 399548, 399557,
400046, 400052, 400330, 400349, 400405, 401003, 401129,
401200, 401246, 401325, 401663, 401906, 401907, 402059,
2121, 402186, 402296, 402303, 402483, 402556, 402648,
403029, 403084, 403835, 404225, 404472, 404507, 405209,
405309, 405974, 406348, 406957, 407057, 407314, 407648,
407939, 407977,407984, 408057, 408149, 408181, 408505,
408562, 408563, 408604, 408708, 409123, 409203, 409238,
409249, 409261, 409650, 409842, 410087, 410266, 410403,
410451, 410638, 410709, 411103, 411140, 411263, 411560,
411598, 411840, 412247, 412778, 412795, 412801, 412816,
413001, 413040, 413545, 414236, 414277, 415034, 415122,
415187, 415317, 415351, 415479, 415798, 415885, 416095,
416249, 416254, 416546, 417140, 417217, 417274, 417343,
417361, 417374, 417546, 417952, 418191, 418344, 418442,
418510, 418593, 418722, 418872, 418921, 418950, 419140,
419420, 419458, 419485, 419609, 419652, 419654, 419702,
419840, 419866, 420293, 420343, 420564, 420679, 420829,
20881, 421315, 422275, 422381
71152B Corrective Action AR-xxxxxx 423579, 423658, 423667, 423713, 423714, 423727, 423728
Documents
Inspection Type Designation Description or Title Revision or
Procedure Date
Resulting from
Inspection
71152B Drawings M520 Flow Diagram HPCS and LPCS Systems, Reactor Building 105
71152B Engineering EC11288 Replace the Stack Monitors 01/15/2019
Changes
71152B Engineering EC14954 CCH Bypass Line AR 224656 09/11/2017
Changes
71152B Engineering EC16619 Credit CCH For MCR Equipment Operability 3
Changes
71152B Engineering EC17951 500 KV Loss Of Bus Protection
Changes
71152B Engineering AR276051 (a)(1) Performance Improvement Plan and Goals - 42 015
Evaluations devices
71152B Engineering Design Base Radwaste Building Mixed Air System 7
Evaluations Document
Division 300
Section 351
71152B Miscellaneous Reportability Evaluation for AR: 417140 (417217)
71152B Miscellaneous Simulator Inspection Report 06/02/2021
71152B Miscellaneous Training for Performance Improvement w/ Post-training 06/21/2021
Evaluations
71152B Miscellaneous Daily Production Meeting (0615) 07/13/2021
71152B Miscellaneous Columbia Generating Station Daily Report 07/13/2021
71152B Miscellaneous Daily Management CR Review CRs to Review 7/12/2021 To 07/13/2021
7/13/2021
71152B Miscellaneous Operations Aggregate Index (Online/Outage) 07/08/2021
71152B Miscellaneous Daily 15 for Thursday August 1, 2019 08/01/2019
71152B Miscellaneous Condition Monitoring for CCH-SYS-A and CCH-SYS-B
71152B Miscellaneous Violation Report - Operations (FFD) 07/12/2021
71152B Miscellaneous Daily Management CR Review - CRs to Review 7/25/2021 to
7/26/2021
71152B Miscellaneous Columbia Generating Station Daily Report 07/26/2021
71152B Miscellaneous List of the Main Control Room Deficiencies Including Back 07/28/2021
Panels
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Miscellaneous IBM Watson Statistics - January thru June 2021 06/17/2021
71152B Miscellaneous Reportability Evaluation for AR 00409238: CMS-RIS-27E 0
and F Do Not Meet Required Seismic Configuration
71152B Miscellaneous Supervisor Shipping Paperwork Review 11
71152B Miscellaneous 1Q2021 High Pressure Core Spray System Health Report 03/31/2021
71152B Miscellaneous 25999 R8 Effectiveness Review for AR-CR 386750 03/28/2019
71152B Miscellaneous 392366 Operating Experience Request
71152B Miscellaneous 401659 Operating Experience Request
71152B Miscellaneous 404198 Operating Experience Request
71152B Miscellaneous 406289 PM Change Request for Inspect Cooling Water Fans 04/27/2020
71152B Miscellaneous 408591 Operating Experience Request
71152B Miscellaneous 411134 Operating Experience Request
71152B Miscellaneous 413989 Operating Experience Request
71152B Miscellaneous 415824 Operating Experience Request
71152B Miscellaneous 417418 PM Change Request for Inspect Cooling Water Fans 03/18/2021
71152B Miscellaneous CAP KPI/LTCA- PERFORMANCE ASSESSMENT REVIEW BOARD (PARB) 07/13/2021
JUNE Meeting Minutes
71152B Miscellaneous Division 300, High Pressure Core Spray Design Basis Document 016
Section 308
71152B Miscellaneous MT000723 Gap, Drive, Action, Results (GDAR) Presentation 03/31/2020
71152B Miscellaneous Root Cause 11 Parameters for PRM-SR-1 Were Incorrect 12/28/2018
Evaluation
386750
71152B Miscellaneous Root Cause HPCS Diesel Starting Air Depressurization Event 01/22/2020
Evaluation
399463
71152B Miscellaneous TREQ 19-0099 Recovery Actions ABN-FWH-HILEVEL/TRIP 07/19/2019
71152B Miscellaneous TREQ 19-0173 Suppression Pool cooling Prioritization 11/20/2019
71152B Operability Technical Assessment Supporting Reportability for AR-
Evaluations 417140
71152B Operability 334459 Control Room Chilled (CCH), Radwaste Mixed Air (WMA) 1
Evaluations
71152B Procedures 1.3.66 Operability Determination 037
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Procedures 1.3.76 Integrated Risk Management 056
71152B Procedures 1.4.7 Control of Supplemental Personnel 019/009
71152B Procedures 10.25.13 A 4.16KV Vacuum Breaker Maintenance with Stored Energy 021
Mechanism
71152B Procedures 10.25.13 A 4.16kV Vacuum Breaker Maintenance with Stored Energy 021
Mechanisms
71152B Procedures CDM-01 Cause Determination Manual 017
71152B Procedures DIC 234.1 Standard Procurement And Use Policy 29
71152B Procedures ISP-APRM/RRC- APRM-CHS-1 Recirculation Flow Transmitters Calibration 003
B301
71152B Procedures OI-14 Columbia Generating Station Operational Challenges and 017
Risk Program
71152B Procedures OI-9 Operations Standards and Expectations 079
71152B Procedures OSP-CCH/IST- Control Room Emergency Chiller System A Operability 055
M701
71152B Procedures OSP-CCH/IST- Control Room Emergency Chiller System A Operability 054
M701
71152B Procedures OSP-CCH/IST- Control Room Emergency Chiller System B Operability 049
M702
71152B Procedures OSP-HPCS-A701 High Press Core Spray Keep Fill Integrity Test 010
71152B Procedures OSP-SW/IST- HPCS Service Water Operability 030
Q703
71152B Procedures PPM 1.5.13 Preventive Maintenance Optimization Living Program 42, 44
71152B Procedures PPM 10.19.1 Cooling Tower Fan Maintenance 16
71152B Procedures PPM 10.25.13B DHP-VR-350 3000 Amp Circuit Breaker Maintenance 005
71152B Procedures PPM 11.2.23.1 Shipping Radioactive Materials and Waste 22
71152B Procedures PPM 11.2.23.44 Operation of the Self Engaging Rapid Dewatering System 8
(SERDS)
71152B Procedures PPM 11.2.23.46 Shipment of Category 1 and 2 Material 0
71152B Procedures PPM 11.2.23.47 DOT Non-Radioactive Material Shipments 0
71152B Procedures PPM 11.2.23.48 Packaging and Shipment of Type A Packages 0
71152B Procedures PPM 11.2.23.49 Radioactive Material LSA and SCO Requirements and 0
Checklist
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Procedures PPM 11.2.23.50 Type B Package and Requirements Checklist 0
71152B Procedures PPM 11.2.23.51 Shipment of Excepted Packages 0
71152B Procedures PPM 3.1.10 OPS-4 Logs 014
71152B Procedures PPM 6.2.1 New Fuel Handling, Delivery Truck to Railroad Bay 028/001
71152B Procedures SOP-CCH- Emergency Chill Water Chiller Start Quick Card (CCH-CR- 000/002
START-QC 1A(B))
71152B Procedures SOP-DG-DSA Diesel Starting Air Operations 13, 15, 18
71152B Procedures SOP-HVAC/CR- Control, Cable, and Critical Switchgear Rooms HVAC Lineup 002
LU
71152B Procedures SOP-HVAC/CR- Control, Cable, and Critical Switchgear Rooms HVAC 028
OPS Operation
71152B Procedures SWP-CAP-01 Corrective Action Program 044
71152B Procedures SWP-CAP-06 Condition Reports 028
71152B Procedures SWP-CHE-02 Chemical Process Management and Control 030
71152B Procedures SWP-CSW-31 Cyber Security Audit and Accountability 001
71152B Procedures SWP-FFD-04 Work Hour Control 009/003
71152B Procedures TDI-04 Processing of Training Request 22
71152B Procedures TDI-06 Simulator Management 21
71152B Procedures TDI-24 Exam Security 017
71152B Procedures TSP-CCH/ISI- ASME CCH System Leakage Test (Loop A) 002
G801
71152B Procedures TSP-HPCS-B801 HPCS Leakage Surveillance 006
71152B Self-Assessments Columbia Nuclear Station Plant Nuclear Safety Culture 04/20/2020
Assessment
71152B Self-Assessments 01-2020 Quality Functional Area Scorecard (FAS 3.0) 01/2021
71152B Self-Assessments 01-2020 Reactor Functional Area Scorecard (FAS 3.0) 01/2020
Fuels (NF.1)
71152B Self-Assessments 01-2021 Functional Area Scorecard (FAS 3.0) 01/2021
Maintenance
71152B Self-Assessments 01-2021 Functional Area Scorecard (FAS 3.0) 01/2021
Operations
71152B Self-Assessments 01-2021 Functional Area Scorecard (FAS 3.0) 01/2021
Radiation
Inspection Type Designation Description or Title Revision or
Procedure Date
Protection
71152B Self-Assessments 01-2021 Training Functional Area Scorecard (FAS 3.0) 01/2021
71152B Self-Assessments 02-2020 Functional Area Scorecard (FAS 3.0) 02/2020
Operations
71152B Self-Assessments 02-2020 Functional Area Scorecard (FAS 3.0) 02/2020
Radiation
Protection
71152B Self-Assessments 02-2021 Functional Area Scorecard (FAS 3.0) 02/2021
Emergency
Preparedness
71152B Self-Assessments 02-2021 Functional Area Scorecard (FAS 3.0) 02/2021
Radiation
Protection
71152B Self-Assessments 02-2021 Reactor Functional Area Scorecard (FAS 3.0) 02/2021
Fuels
71152B Self-Assessments 03-2020 Functional Area Scorecard (FAS 3.0) 03/2020
Maintenance
71152B Self-Assessments 03-2021 Functional Area Scorecard (FAS 3.0) 03/2021
Radiation
Protection
71152B Self-Assessments 05-2020 Functional Area Scorecard (FAS 3.0) 05/2020
Radiation
Protection
71152B Self-Assessments 12-2020 Functional Area Scorecard (3.0) 12/2020
Radiation
Protection
71152B Self-Assessments 2-2021 Functional Area Scorecard (FAS 3.0) 02/2021
Engineering
71152B Self-Assessments AR-SA 356852 Fluid Leak Management 00
71152B Self-Assessments AR-SA 374692 Risk Management 04/08/2021
71152B Self-Assessments AR-SA 376387 71124.06 Radioactive Gaseous and Liquid Effluent 09/05/2019
Treatment
71152B Self-Assessments AR-SA 378159 71124.08 Radioactive Solid Waste Processing and 01/21/2019
Radioactive Material Handling, Storage and Transportation
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Self-Assessments AR-SA 378162 RESPIRATORY PROTECTION PROGRAM 03/12/2020
71152B Self-Assessments AR-SA 390029 2021 Pre-PI&R 02/29/2021
71152B Self-Assessments AR-SA 397558 Plant Status Control 09/05/2019
71152B Self-Assessments AR-SA 400251 Health of the 10 CFR 50.59 Program 01/16/2020
71152B Self-Assessments AR-SA 404481 Nuclear Projects 10/15/2020
71152B Self-Assessments AR-SA 411359 Fire Protection 01/13/2021
71152B Self-Assessments AU-CA-20 Quality Services Audit Report - Corrective Action Program 08/05/2020
71152B Self-Assessments AU-CH-20 Chemistry and Environmental Monitoring Program 10/01/2020
71152B Self-Assessments AU-CL-19 Calibration Laboratory Program 03/14/2019
71152B Self-Assessments AU-DC-20 Quality Services Audit Report (QSAR) - Independent Spent 04/16/2020
Fuel Storage Installation
71152B Self-Assessments AU-EN-20 QSAR - Engineering Program 03/26/2020
71152B Self-Assessments AU-EP-21 QSAR - Emergency Preparedness 03/02/2021
71152B Self-Assessments AU-MM-20 Materials Management Program 11/12/2020
71152B Self-Assessments AU-MM-20 Quality Services Audit Report Material Management Program 12/03/2020
71152B Self-Assessments AU-MN-21 QSAR - Maintenance Program 01/28/2021
71152B Self-Assessments AU-OP/TS-19 Quality services Audit Report for Operations, Technical 07/31/2019
Specifications and Applicable License
Conditions Programs
71152B Self-Assessments AU-RP/RW-19 Radiation Protection and Process Control Programs 12/05/2019
71152B Self-Assessments AU-RP/RW-20 Radiation Protection and Process Control Programs 12/16/2020
71152B Self-Assessments AU-SE-PADS- Quality Services Audit Report for Security, Personnel Access 09/20/2020
MRO/SAE-20 Data System (PADS), Medical Review
Officer (MRO), and Substance Abuse Expert (SAE)
Programs
71152B Self-Assessments AU-TQ-20 Quality Services Audit Report for Training Qualification and 06/25/2020
Performance of Unit Staff Program and
Processes
71152B Shipping Records 21-27 Paperwork Package for Shipment 21-27 04/21/2021
71152B Work Orders 00GL92 - 05 RECRANK PMT (DG-ENG-1C)
71152B Work Orders 01045033-01 CW-CT-2 A Structural Inspection 06/10/2003
71152B Work Orders 02046448-01 01/22/2014
71152B Work Orders 02050016 - 07 RECRANK PMT (DG-ENG-1C)
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Work Orders 02072674-01 Inspect Cooling Tower Fan CW-FN-1 03/04/2017
71152B Work Orders 02080487-01 06/29/2016
71152B Work Orders 02087667-01 05/21/2021
71152B Work Orders 02087671-01 05/20/2021
71152B Work Orders 02089994-06 RECRANK PMT (DG-ENG-1C)
71152B Work Orders 02109310
71152B Work Orders 02110808-01 Clean Cooling Tower for CW-CT-2C 05/07/2019
71152B Work Orders 02126103-01 12/24/2019
71152B Work Orders 02140306-01/02 Inspect/Clean/Repair Seal for CW-CT-2B 06/09/2021
71152B Work Orders 02165498-01 10/03/2020
71152B Work Orders 02165835-01 01/02/2021
71152B Work Orders 02167179-01 CMS-RIS-27F Does Not Meet Required Seismic 07/30/2020
Configuration (In-Containment Hi Range Area Radiation
Readout)
71152B Work Orders 02167180-01 CMS-RIS-27E Does Not Meet Required Seismic 07/30/2020
Configuration (In-Containment Hi Range Area Radiation
Readout)
71152B Work Orders WO214516 and
71152B Work Orders WO2176936
71152B Work Orders WR29158405
14