IR 05000263/2020010
ML21062A129 | |
Person / Time | |
---|---|
Site: | Monticello ![]() |
Issue date: | 03/02/2021 |
From: | Hironori Peterson Region 3 Branch 3 |
To: | Conboy T Northern States Power Company, Minnesota |
References | |
IR 2020010 | |
Download: ML21062A129 (16) | |
Text
March 2, 2021
SUBJECT:
REISSUE - MONTICELLO NUCLEAR GENERATING PLANT - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000263/2020010
Dear Mr. Conboy:
In the inspection report sent to you dated January 13, 2021 (ML21013A422), the NRC had documented a minor violation associated with the failure to promptly correct Conditions Adverse to Quality, in accordance with 10 CFR 50, Appendix B, Criterion XVI. After a subsequent review of additional information provided by your staff, the NRC concluded that this violation was not warranted. As a result, the NRC has reissued the report in its entirety addressing the updated subject. None of these changes affected the overall technical aspect of the report.
On December 4, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Monticello Nuclear Generating Plant and discussed the results of this inspection with Mr. D. Barker, Plant Manager, 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 no evidence of challenges to your organizations safety-conscious work environment. Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available. No findings or violations 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,
/RA/
Hironori Peterson, Chief Branch 3 Division of Reactor Projects
Docket No. 05000263 License No. DPR-22
Enclosure:
As stated
Inspection Report
Docket Number:
05000263
License Number:
Report Number:
Enterprise Identifier: I-2020-010-0032
Licensee:
Northern States Power Company, Minnesota
Facility:
Monticello Nuclear Generating Plant
Location:
Monticello, MN
Inspection Dates:
November 16, 2020 to December 04, 2020
Inspectors:
J. Draper, Health Physicist
J. Neurauter, Senior Reactor Inspector
N. Shah, Project Engineer
J. Weigandt, Reactor Engineer
Approved By:
Hironori Peterson, Chief
Branch 3
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution inspection at Monticello Nuclear Generating 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 https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations were identified.
Additional Tracking Items
None.
PLANT STATUS
Monticello operated at or near rated thermal power for the entire 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 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 Disease (COVID-19), regional inspectors were directed to begin telework. During this time regional baseline inspections were evaluated to determine if all or portions of the objectives and requirements stated in the IP could be performed remotely. In some cases, portions of an IP were completed remotely and on-site.
The inspection documented below was determined that the objectives and requirements stated in the IP could be completed remotely.
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 also conducted a five-year review of the Part 21 process.
- Operating Experience, Self-Assessments and Audits: The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits and self-assessments.
- Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
INSPECTION RESULTS
Assessment 71152B Assessment of the Corrective Action Program
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Generally, issues were screened and evaluated consistent with the guidance in licensee procedure FP-PA-ARP-01, CAP Process, revision 58. However, the team did identify some examples where issues were either improperly handled or weaknesses in the CAP process; these are discussed in the appropriate subsection below.
Effectiveness of Problem Identification
Overall, the station was effective at identifying issues at a low threshold and was properly entering them into the corrective action program (CAP) as required by station procedures.
During interviews, workers were familiar with how to enter issues into the CAP and stated that they were encouraged to use it to document issues. The team determined that the station was generally effective at identifying negative trends that could potentially impact nuclear safety. For the areas reviewed, the team did not identify any issues in the area of problem identification.
The team identified a missed opportunity to identify a potential generic station issue with configuration/status control during the performance and subsequent screening of apparent cause evaluation for CAP 501000045769, CV-1502 Demand Signal Went to 100%. This evaluation discussed a prior event documented in the Root Cause for CAP 5010000028365, AS-78, AS-79 Found Open. In both events, the cause was inappropriate configuration/status controls used during work activities by workers in maintenance (instrumentation and controls) and operations, respectively. The apparent cause did not address whether the occurrence of similar issues for similar causes potentially indicated a generic issue with configuration/status controls. In fact, the apparent cause simply documented the prior event with no evaluation of its applicability or influence. Since the corrective actions were limited to the specific work groups, based on its recurrence, there is a potential that more generic actions are needed. The licensee documented this issue as CAP item 501000046645.
Effectiveness of Prioritization and Evaluation of Issues
In-depth reviews of a risk-informed sampling of condition reports (CRs), work orders (WOs),and root and apparent cause and condition evaluations were completed. The team determined that the licensee had established a low threshold for entering deficiencies into the CAP, that the issues were generally being appropriately prioritized and evaluated for resolution, and that corrective actions (CAs) were implemented to mitigate the future risk of issues occurring that could affect overall system operability and/or reliability.
Effectiveness of Corrective Actions
The team concluded that the licensee was generally effective in developing CAs that were appropriately focused to correct the identified problem and to address the root and contributing causes for significant conditions adverse to quality to preclude repetition. The licensee generally completed CAs in a timely manner and in accordance with procedural requirements commensurate with the safety significance of the issue. For NRC-identified issues, the team determined that the licensee generally assigned CAs that were effective and timely.
For issues identified as Conditions Adverse to Quality (CAQ), station procedure FP-PA-ARP-01, required that they be documented in the CAP and screened as either level "A, B or C" commensurate with level of evaluation needed to assess the issue. Those classified as level "C" were typically well understood and of low risk, and therefore required only a condition evaluation instead of a root or apparent cause evaluation. Regardless of the classification, each CAQ was required to have an associated corrective action assigned.
NRC regulation 10 CFR Part 50, Appendix B, Criterion XVI, states that measures shall be established to ensure that Conditions Adverse to Quality (CAQ), such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and non-conformances are promptly identified and corrected. Attachment 8 to FP-PA-ARP-01, further clarified that corrective actions associated with CAQs, should be completed as soon as possible, not to exceed the next refueling outage. However, this requirement was only applied to "A" and "B" level CAPs; for CAQs associated with "C" level CAPs, the Attachment had no backstop for completing corrective actions, and they can be potentially postponed indefinitely. Some examples identified by the inspectors included CAP items 501000015382, Internal Flooding Concerns, and 501000035317, Essential Service Water Division II Insulated, not Per Calculation. Both CAPs documented issues with design documents for safety-related components. These issues were correctly classified as CAQs and screened as level "C" CAPs, as the issues were well understood and determined not to affect operability.
However, the team identified that the associated corrective actions had been extended several times due primarily to resource availability and remained open.
The team questioned whether the verbiage in FP-PA-ARP-01 resulted in inappropriate, disparate treatment for CAQs based on the CAP screening, which in this case, resulted in the above two CAQs remaining open for an extended period. Additionally, the associated extension justification focused primarily on the resource availability and not on the fact that these were still CAQs and if it still required timely closure. The inspectors noted a potential concern that this practice could result in licensee staff becoming desensitized to the need to promptly address CAQs. The licensee documented this issue as CAP item 501000046796.
No violations or findings were identified.
Assessment 71152B Assessment of Operating Experience and Self-Assessment and Audits
Based on the samples reviewed, the team determined that licensee performance in the use of Operating Experience (OE) and Self-Assessments and Audits adequately supported nuclear safety.
Use of Operating Experience
The licensee routinely screened industry and NRC OE information for station applicability.
Based on these initial screenings, the licensee-initiated actions in the CAP to fully evaluate the impact, if any, to the station. When applicable, actions were developed and implemented in a timely manner to prevent similar issues from occurring. Operating Experience lessons-learned were communicated and incorporated into plant operations.
During the 5-year review of the Part 21 process, the team identified one example of a Part 21 report applicable to the station that was improperly reviewed. Specifically, CAP 501000031467, documented a Part 21 associated with Westinghouse Nuclear Safety Advisory Letter (NSAL) 19-2, issued in September 2019. This NSAL, documented an issue with Size 1 Freedom Series contactors failing to release/open when de-energized under certain conditions. Westinghouse had determined that Monticello had these contactors and recommended that an evaluation be performed to determine the site impact. During CAP screening, this issue was classified as a non-CAP item, meaning that it was not considered a CAQ. As a consequence, it was considered of low priority and assigned a due date of December 2020 to complete the evaluation. In the interim, no action was taken to determine if the contactors were used at Monticello, specifically in any safety-related application.
Subsequently, after prompting by the NRC, the licensee determined that the contactors were installed in safety-related equipment, but that the specific conditions described in the NSAL for inoperability, were not present; therefore, the contactors (and by extension, the affected equipment) were operable. Although the inspectors had no issues with the operability assessment, given that the NSAL potentially affected safety-related components at Monticello, it should have been classified as a Condition Adverse to Quality (CAQ), consistent with Attachment 5 to FP-PA-ARP-01, instead of a non-CAP item. The licensee documented the failure to properly screen and correct this issue as CAP item 5010000046791. Because there were no safety or operability concerns, the inspectors concluded that the failure to properly characterize and evaluate this issue was minor in nature.
Self-Assessments and Audits
The inspectors reviewed several audits and self-assessments and deemed those sampled as thorough and intrusive with regards to following up with the issues that were identified through previous NRC inspections and in the self-assessments and fleet oversight audits.
Reviewed corrective actions for the identified issues were deemed reasonable and completed commensurate with their safety significance. The inspectors regarded licensee performance as adequately self-critical of their own performance and that performance-related issues were being identified through their self-assessment process.
Assessment 71152B Assessment of Safety-Conscious Work Environment
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, workers at the station expressed freedom to raise and enter safety concerns through any one of the various avenues available to them, and the team encountered no indications of chilling or retaliation. Finally, all plant personnel interviewed were aware of the Employee Concerns Program and expressed a willingness to use it as an avenue to raise concerns, if desired.
In addition, the team included questions on the topic of the ongoing extended COVID pandemic and the associated changes to plant staffing, including extended use of telework, to assess for any negative impacts on safety performance or overall safety culture both for the individuals and the organization. Employees consistently communicated the belief that sufficient competency, engagement, resources, and commitment exist at the station to maintain high performance standards at the site.
In July 2020, the licensee completed a safety culture assessment of the site. Overall, the licensee concluded that an appropriate environment existed for the raising and addressing of concerns and that workers felt comfortable using the various processes available. However, an issue was identified in the Program Engineering group, specifically that engineering management was ineffectively prioritizing work and that insufficient resources existed to handle the workload. As a result, there was a potential for certain activities, that may affect conditions adverse to quality, not being completed. The licensee had captured this issue in the CAP and developed an action plan to address it. Although it was too early to assess its effectiveness, the inspectors concluded that this plan appeared reasonable to address the concern.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On December 4, 2020, the inspectors presented the biennial problem identification and resolution inspection results to Mr. D. Barker, Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71152B
Corrective Action
Documents
500001552560
Service Water Microbiologically Influenced Corrosion (MIC)
Pitting Detected in Line ESW1-3-H
03/08/2017
500001552684
Service Water-Microbiologically Influenced Corrosion (MIC)
Pitting Detected in Line ESW1-3-H
03/09/2017
501000000027
Elevation of High-Pressure Coolant Injection Trend
06/26/2017
501000006644
Target Sets Inspec URI Operator Action
2/21/2017
501000009060
Inadequate Security Search (NRC ID)
03/01/2018
501000010484
Steam Chase CAM Met ACMI Action Level
04/06/2018
501000012880
Steam Leak from Vlv Packing on AO-2-86C (ACE)
06/05/2018
501000014866
Security Manual AVBS Out of Alignment
07/26/2018
501000015382
Internal Flooding Calculation Details
08/08/2018
501000015405
DSC SVP Exam Additional Documents
08/14/2018
501000015691
Exam Control Adverse Trend (ACE)
08/15/2018
501000015701
U/I Watch Performed Under Exam Security
08/16/2018
501000015782
Environmental Qualification Cable Submergence
Documentation Issue
08/17/2018
501000016026
Inboard Main Steam Isolation Valve Calculation Not Updated
for Extended Power Uprate
08/23/2018
501000016054
Incorrect Assumption in Operating Experience Evaluation
08/23/2018
501000016705
CST-103-1 / 104-1 Failed to Seat (ECE)
09/10/2018
501000018035
2018 PI&R--CE Did Not Document Extent of Condition
10/30/2018
501000018660
EDG Failed to Load (ECE)
10/15/2018
501000020085
Equipment Cause Evaluation: "C" Outboard Main Steam
Isolation Valve Failed to Stroke
11/16/2018
501000020222
Apparent Cause Evaluation: As Found Hydrogen Cooler
Gasket Condition
11/20/2018
501000020960
CE for the UPS-PAL-1 and 2 Recent Failures
2/11/2018
501000021275
Potential Part 21--OTBD MSIV
2/20/2018
501000022240
Equipment Cause Evaluation: P-25A Will Not Establish Flow
01/22/2019
501000022876
11-297 Incorrect Stroke Time Criteria
2/07/2019
501000022942
EDG Vent-Cocks Leaking
2/10/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
501000023118
DG/52-710 Locked Out
2/13/2019
501000023534
V-EAC-14B Compressor Tripped During Swap
10/01/2019
501000023854
SW-21-1 & SW-22-1 Failed In-Service Test Testing
03/05/2019
501000024419
MR A(1) Determination Needed for Deferral
03/19/2019
501000025469
Drywell Dose Rates Significantly Higher
04/13/2019
501000025624
RHR DHR Hardening Issue Identified (ACE)
04/16/2019
501000026282
Past Operability Review: HPCI-14 Failed In-Service Test
04/24/2019
501000026577
Past Operability Review: Check Valve BF-14 Failed Testing
04/30/2019
501000026645
NOS: PT Indication on SR-27-2 Poppet
05/01/2019
501000026727
C.4-I (Plant Flooding) Entry (ACE)
05/22/2019
501000026921
Improperly Searched Employee Entered PA
05/06/2019
501000027212
Configuration Control Issues RFO29
05/10/2019
501000027329
Drywell Eq. Sump Alarms Coming In
05/13/2019
501000027374
1R29: 900# DW Inspection Results
05/13/2019
501000027548
Shutdown Safety Lessons Learned From ACE
05/17/2019
501000027548
Shutdown Safety (RCE)
0a
501000028099
50.59 Missed Title 10 Code of Federal Regulations 50.46
Report
06/04/2019
501000028365
Drywell Isolation Downstream as 40
06/11/2019
501000028365
AS-78, AS-79 Found Open
06/11/2019
501000028661
- 11 Recirc Pump Seal Pressure Trend
06/18/2019
501000029829
Scram Discharge Volume High Level Scram Channel B2
07/21/2019
501000029837
V-EAC-14B Compressor Trip on Startup (ECE)
07/21/2019
501000030237
CRDs Refurbished Without ASME XI RR Plan
07/31/2019
501000031306
NRC P21 Fisher Butterfly Valve Taper Pins
09/10/2019
501000031370
Otbd MSIV Spec Conflicts
08/30/2019
501000031467
Westinghouse NSP-19-48/NSAL-19-2 Contact
09/04/2019
501000031593
MO-2034 Actuator Grease Discrepancy
09/09/2019
501000032300
2019 MT Outage Readiness FSA Not Perform
09/24/2019
501000034409
Bearing Defects Developing, 11 CRD Pump (CA)
11/07/2019
501000034573
Apparent Cause Evaluation: Reactor Core Isolation Cooling
(RCIC) Isolation MO-2076 Times Out of Specification
11/12/2019
501000034676
Apparent Cause Evaluation: Reactor Core Isolation Cooling
11/14/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
(RCIC) Failed to Start During Component Testing
501000035317
Emergency Service Water Division II Insulated, Not Per
Calculation
2/04/2019
501000035427
NRC Part 21 with Monticello as Affected Plant
2/06/2019
501000037768
CR Received Unanticipated 13K028 Alarm
2/20/2020
501000040100
GEH SC 20-04 R0 Nameplate Discrepancy
06/25/2020
501000040114
Operating Permit Use Issue Identified (ACE)
04/29/2020
501000040138
Part 21 4KV-150/151-604-A Relay
05/04/2020
501000041066
Radioactive Shipment Not in Accordance with Manifest
05/27/2020
501000043571
Unexpected Response During ATWS Mod
08/06/2020
501000044981
Water Leak 962 RWPR RWCU Phase Sep Room
10/01/2020
501000045576
Downscale of NLO Must Perform Tasks
10/16/2020
501000045769
CV-1502 Demand Signal Went to 100 Percent
10/22/2020
501000046175
Batt. Pos. Post Bulging/Seal Leaks
11/05/2020
501000046204
LS-23-90/1 Leaking Steam
11/05/2020
501000046365
MO-3502 Diagnostic Test Follow-Up Items
11/13/2020
501000046402
Foreign Material Exclusion in 3 Cells of 13 Diesel Generator
Battery
11/13/2020
501000046495
Scope Addition to MT X-Ray Project
11/18/2020
501000046639
Part 21 SC 20-06 Rev 0 Issued
11/24/2020
601000000530
10/17/2018
601000000856
20 NRC Part 21 Reports with Monticello Not Listed
2/05/2020
601000000911
GE SIL No. 684, Rev 0--Noble Chem TM Plating
04/14/2020
610000000546
Industry Operating Experience Evaluation: Flow Accelerated
Corrosion Leak on Reactor Water Clean Up Missed by
Ultrasonic Examination (UT) Technique
07/02/2019
610000000639
SIL 682 R0 Flow Induced Vibration Load
07/23/2019
610000000824
Limerick LER Multiple Trains of RHRSW Inoperable for
Greater than Time Allowed by Technical Specifications due
to Pipe Corrosion
2/06/2019
610000000851
GE SIL No. 683 Rev. 0 OP-Amp Board Polyur
2/20/2019
610000000868
Industry OE for Bolt Failure in ESW Pump
01/14/2020
610000000882
Industry Operating Experience Evaluation: Fermi Non-Cited
05/09/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Violation 2020 Torus Coating Issues
610000000897
Industry Operating Experience Evaluation: Dresden
Feedwater Nozzle
07/03/2020
Corrective Action
Documents
Resulting from
Inspection
501000046645
Missed Opportunity IN ACE Internal OE
11/23/2020
501000046784
PI&R Activity Closed Without Note
2/01/2020
501000046791
PI&R: GAP IN Severity & Timeliness: NSAL-19-2
11/30/2020
501000046796
Observations of Potential GAP in FP-PA-ARP-01
2/01/2020
501000046823
PI&R: CAP Not Submitted to SRO Screening
2/02/2020
501000046844
Opportunity in CAP Formatting
2/03/2020
501000046845
Missed Tracking Assignment for Corrective Action
2/03/2020
501000046850
PI&R: Inconsistent Use of CAP Fields
2/03/2020
Miscellaneous
Licensee Event
Report 05000-
263/2019-002-00
Tso Manual Primary Containment Isolation Valves Found
Open Resulting in a Condition Prohibited by Technical
Specifications
06/11/2019
N/A
Corrective Action Program Pre-Screening Meeting
11/18/2020
N/A
Operating Experience Pre-Screening Meeting
11/18/2020
N/A
Corrective Action Program Screening Meeting
11/19/2020
N/A
Plant Heath Committee Meeting
11/20/2020
N/A
Performance Assessment Review Board (PARB) Meeting
11/24/2020
NA
Corrective Action Program Pre-Screening Meeting
11/30/2020
NA
Corrective Action Program Screening Meeting
11/30/2020
Procedures
4AWI-05.04.03
9111-05
Decay Heat Removal Hardening
9111-05
Decay Heat Removal Hardening
FP-E-P21-01
CFR Part 21 Evaluations
FP-E-SE-03
10CFR50.59 and 72.48 Processes
FP-G-DOC-04
Procedure Processing
FP-OP-OL-01
Operability/Functionality Determination
FP-OP-OL-01
Operability
FP-PA-ARP-01
CAP Process
FP-PA-EVAL-01
Evaluation Methods
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
FP-PA-OL-01
Operability
FP-PA-PAR-01
Performance Assessment Review Board and Performance
Assessment Oversight
FP-PA-SA-03
Snapshot Evaluation
FP-STND-NSC-
Nuclear Safety Culture Monitoring Process
FP-T-SAT-71
NRC Exam Security Requirements
OWI-01.03
Operations Communications Standard
Self-Assessments
Nuclear Safety Culture Assessment June/July 2020
07/23/2020
600000542411
Integrated Performance Monitoring: Operations 1st and 2nd
Quarter 2019
600000613359
Operations Dept. Excellence Summary - Oct. 2019
10/30/2019
606000000691
Snapshot Self-Assessment: 50.59 71111/17T
11/14/2019
606000000694
Snapshot Self-Assessment: External Flooding
FP-PE-IMEP-01
11/14/2019
606000000704
FSA: Outage Readiness
11/14/2019
606000000705
FSA: Electrical Safety Governance
07/17/2020
606000000859
2019 Corrective Action Quality Closure Self-Assessment
2/21/2019
606000001073
FSA: Problem Identification and Resolution at MNGP
11/13/2020
606000001092
INPO Plant Evaluation of Watts Bar
2/19/2020
606000001103
Self-Assessment on CAQ Work Orders
11/07/2019
A-CAP-MNGP-
2018-1
MNGP NOS Corrective Action Program Audit 2018
03/07/2018
A-DES-MNGP-
20-1
20 Nuclear Oversight Audit of Monticello Nuclear
Generating Plant Design Control
07/16/2020
A-MAINT-MNGP-
2019-1
Maintenance (Nuclear Oversight Audit Report)
07/11/2019
A-PROG-MNGP-
20-1
20 Nuclear Oversight Audit of Monticello Nuclear
Generating Plant Programs (PROG)
03/27/2020
MO-20-08
Employee Concern Issue Plan
11/23/2020
N/A
Xcel Energy Survey: Safety Conscious Work Environment
07/23/2020
N/A
Integrated Performance Monitoring: Engineering
3rd Quarter
2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
N/A
Xcel Fleet: Engineering Department Excellence Summary
March 2019
N/A
Xcel Fleet: Engineering Department Excellence Summary
March 2020
N/A
Xcel Fleet: Engineering Department Excellence Summary
January
20
N/A
Xcel Fleet: Engineering Department Excellence Summary
July 2020
N/A
Integrated Performance Monitoring: Engineering
2nd Quarter
2019
NA
Operations Dept. Excellence Summary - Aug 2020
08/04/2020
NA
Operations Dept. Excellence Summary - Jan 2020
01/23/2020
NA
Operations Dept. Excellence Summary - Apr 2020
04/27/2020
NA
Operations Dept. Excellence Summary - Oct 2020
10/07/2020