ML21013A422
ML21013A422 | |
Person / Time | |
---|---|
Site: | Monticello ![]() |
Issue date: | 01/13/2021 |
From: | Hironori Peterson Region 3 Branch 3 |
To: | Conboy T Northern States Power Company, Minnesota |
References | |
IR 2020010 | |
Download: ML21013A422 (16) | |
See also: IR 05000263/2020010
Text
January 13, 2021
Mr. Thomas Conboy
Site Vice President
Monticello Nuclear Generating Plant
Northern States Power Company, Minnesota
2807 West County Road 75
Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT - BIENNIAL PROBLEM
IDENTIFICATION AND RESOLUTION INSPECTION REPORT
Dear Mr. Conboy:
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 of more than minor significance were identified during this inspection.
T. Conboy
2
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
cc w/ encl: Distribution via LISTSERV
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available
OFFICE RIII
RIII
NAME
NShah:wc via email
HPeterson via email
DATE
1/12/2021
1/13/2021
Enclosure
U.S. NUCLEAR REGULATORY COMMISSION
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
2
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 of more than minor significance were identified.
Additional Tracking Items
None.
3
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 Sample)
(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.
4
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
5
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 the risk and 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
has no backstop for completing corrective actions, and they can be 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 of these 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. For example,
CAP 5010000015382, which was identified on 8/8/2018, had a current due date of 12/9/2020;
and CAP 501000035317 which was identified on 12/4/2019, had a current due date of
12/9/2020. During this review, the inspectors concluded that both issues were likely to be
extended again, leaving the CAQs uncorrected. 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 uncorrected,
contrary to Criterion XVI of 10 CFR Part 50, Appendix B. The licensee documented this issue
as CAP item 501000046796. Because there were no open operability or safety concerns, the
inspectors concluded that the failure to timely correct the CAQs was minor in nature.
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-
6
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.
7
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.
8
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
12/21/2017
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
11 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
12/11/2018
501000021275
Potential Part 21--OTBD MSIV
12/20/2018
501000022240
Equipment Cause Evaluation: P-25A Will Not Establish Flow
01/22/2019
501000022876 11-297 Incorrect Stroke Time Criteria
02/07/2019
501000022942
11 EDG Vent-Cocks Leaking
02/10/2019
9
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
501000023118
13 DG/52-710 Locked Out
02/13/2019
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
10
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
02/04/2019
501000035427
NRC Part 21 with Monticello as Affected Plant
12/06/2019
501000037768
CR Received Unanticipated 13K028 Alarm
02/20/2020
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
13 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
2020 NRC Part 21 Reports with Monticello Not Listed
02/05/2020
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
12/06/2019
610000000851
GE SIL No. 683 Rev. 0 OP-Amp Board Polyur
12/20/2019
610000000868
Industry OE for Bolt Failure in ESW Pump
01/14/2020
610000000882
Industry Operating Experience Evaluation: Fermi Non-Cited
05/09/2020
11
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
12/01/2020
501000046791
PI&R: GAP IN Severity & Timeliness: NSAL-19-2
11/30/2020
501000046796
Observations of Potential GAP in FP-PA-ARP-01
12/01/2020
501000046823
PI&R: CAP Not Submitted to SRO Screening
12/02/2020
501000046844
Opportunity in CAP Formatting
12/03/2020
501000046845
Missed Tracking Assignment for Corrective Action
12/03/2020
501000046850
PI&R: Inconsistent Use of CAP Fields
12/03/2020
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
4
9111-05
Decay Heat Removal Hardening
1
9111-05
Decay Heat Removal Hardening
5
FP-E-P21-01
10 CFR Part 21 Evaluations
6
FP-E-SE-03
10CFR50.59 and 72.48 Processes
13
FP-G-DOC-04
Procedure Processing
40
FP-OP-OL-01
Operability/Functionality Determination
21
FP-OP-OL-01
Operability
22
FP-PA-ARP-01
CAP Process
58
FP-PA-EVAL-01
Evaluation Methods
6
12
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
FP-PA-OL-01
Operability
22
FP-PA-PAR-01
Performance Assessment Review Board and Performance
Assessment Oversight
17
FP-PA-SA-03
Snapshot Evaluation
8
FP-STND-NSC-
01
Nuclear Safety Culture Monitoring Process
9
FP-T-SAT-71
NRC Exam Security Requirements
12
OWI-01.03
Operations Communications Standard
53
Self-Assessments
Nuclear Safety Culture Assessment June/July 2020
07/23/2020
600000542411
Integrated Performance Monitoring: Operations 1st and 2nd
Quarter 2019
1
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
02/21/2019
606000001073
FSA: Problem Identification and Resolution at MNGP
11/13/2020
606000001092
INPO Plant Evaluation of Watts Bar
12/19/2020
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-
2020-1
2020 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-
2020-1
2020 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
13
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
2020
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