IR 05000341/2022002
| ML22214B341 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/04/2022 |
| From: | Laura Kozak Reactor Projects Region 3 Branch 4 |
| To: | Peter Dietrich DTE Electric Company |
| References | |
| IR 2022002 | |
| Download: ML22214B341 (28) | |
Text
SUBJECT:
FERMI POWER PLANT, UNIT 2 - INTEGRATED INSPECTION REPORT 05000341/2022002
Dear Mr. Dietrich:
On June 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Fermi Power Plant, Unit 2. On July 6, 2022, 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.
Two findings of very low safety significance (Green) are documented in this report. Two of these findings involved violations of NRC requirements. 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 Fermi Power Plant, Unit 2.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; and the NRC Resident Inspector at Fermi Power Plant, Unit 2.
August 4, 2022 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, Chief Branch 4 Division of Reactor Projects Docket No. 05000341 License No. NPF-43
Enclosure:
As stated
Inspection Report
Docket Number:
05000341
License Number:
Report Number:
Enterprise Identifier:
I-2022-002-0042
Licensee:
DTE Electric Company
Facility:
Fermi Power Plant, Unit 2
Location:
Newport, MI
Inspection Dates:
April 01, 2022 to June 30, 2022
Inspectors:
T. Briley, Senior Resident Inspector
J. Gewargis, Reactor Engineer
R. Ng, Project Engineer
T. Ospino, Resident Inspector
T. Taylor, Senior Resident Inspector
D. Turpin, Reactor Engineer
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 Fermi Power Plant, Unit 2, 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
Unsecured and Unapproved Ladder Near Safety-Related Equipment Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000341/2022002-01 Open/Closed
[P.3] -
Resolution 71152S During a routine tour of the plant, the inspectors identified an extension ladder set up in the emergency diesel generator (EDG) 12 fuel oil storage tank (FOST) Room. The ladder reached from the floor up to the lube oil storage tank (approximately 12 feet) and was unlabeled and unsecured, contrary to plant procedures. This resulted in an NRC-identified finding of very low safety significance (Green) with an associated Non-Cited Violation (NCV).
Fire Protection Equipment Blocked Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000341/2022002-02 Open/Closed
[P.3] -
Resolution 71152S An NRC-identified finding of very low safety significance (Green) with an associated NCV occurred when the inspectors identified a manual fire alarm station blocked by a cart, contrary to plant procedures.
Additional Tracking Items
None.
PLANT STATUS
The plant was in a planned refueling outage at the beginning of the inspection period. On May 8, 2022, a reactor startup was completed, and the plant synchronized to the grid on May 13, 2022. The plant was restored to 100 percent power on May 18, 2022, and remained at or near that power until June 24, 2022, when the plant scrammed due to an electrical perturbation on the 345kV main generator disconnect mat. The scram was not complicated, repairs were made, and the reactor startup was completed on June 26, 2022. The plant was restored to 100 percent power on June 29, 2022, and remained at or near that level for the rest of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Division 1 core spray during the week ending April 9, 2022
- (2) Division 2 core spray during the week ending June 11, 2022
- (3) Division 2 emergency equipment cooling water (EECW) during the week ending July 1, 2022
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the division 1 emergency diesel generator (EDG) 11 system during the week ending June 11, 2022.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Drywell fire (welding cable) and extent of condition during the week ending May 21, 2022
- (2) Division 1 switchgear room during the week ending June 17, 2022
- (4) DC motor control center room during the week ending June 17, 2022
- (5) Reactor core isolation cooling / reactor building northeast corner basement during the week ending June 17, 2022 Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Partial)
(1)
(Partial)
The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill on June 9, 2022. The drill was done in conjunction with the local fire department. The inspectors will assess other facets of the inspection procedure in later quarters.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Division 1 residual heat removal (RHR) heat exchanger 'A' baffle plate during RF21
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during downpower to ~77 percent on May 25, 2022
- (2) The inspectors observed and evaluated licensed operator performance in the control room during approach to criticality during startup from forced outage on June 26, 2022
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (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)
(Partial)
Motor operator valve actuator removal and installation practices
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 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) Shutdown cooling system outage during the week ending May 21, 2022
- (2) Restoration from main generator disconnect arc-fault issue during the week ending June 30, 2022
- (3) Planned degraded vacuum during auto voltage regulator testing during the week ending June 30, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples 1 Partial)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Operability review of the SST-64 due to issues with cable 200001H-OP, CARD 22-22914 during the week ending April 9, 2022
- (2) Operability review of the division 2 RHR heat exchanger after emergent work CARD 22-24469 April 7 to 26, 2022
- (3) Reactor Protection System 'A' spurious trips during the week ending May 21, 2022
- (4) Engineering Functional Assessment regarding surge suppressors associated with DC transient (and continued follow-up) during the week ending June 25, 2022
- (5) Main steam line drain inboard and outboard primary containment isolation valves B2103F016 and B2103F019 following actuator to yoke connection issues on B2103F019
- (6) Impact of a failed square root circuit component on jet pump 11 during the week of June 25, 2022.
(7)
(Partial)
Division 1 turbine building area temperature high channel failure
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (7 Samples 1 Partial)
- (1) Tasks related to the repair of the cable 200001H-0P (SST-64) on April 5, 2022
- (2) Review of post maintenance test (PMT) actions after smoke detected in traversing in-core probes (TIP) relay during the firing of the TIP 'C' squib on May 17, 2022
- (3) EDG 11 following outage maintenance (questions on bearing flashing),post-maintenance runs, and relays during the week ending May 21, 2022
- (4) Environmental qualification seal project - select issues/components, environmental seal replacements on circuits during the week ending May 21, 2022
- (5) New visual annunciator system installation - issues with spurious alarms during the week ending May 21, 2022
- (6) High pressure coolant injection (HPCI) speed sensor and min flow valve during the week ending June 4, 2022
(Partial)
Division 1 B21N117B turbine building area temperature high instrumentation following channel failure during the week ending May 21, 2022
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
Core verification after fuel movements during the RF21 outage between the days of April 11 to 19, 2022. Additionally, reactor startup and containment closure activities were observed.
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) (4 Samples)
- (1) Deluge system functionality test verification on new transformer-65 on April 13, 2022
- (2) Scram time test surveillance and changes during the week ending June 4, 2022
- (3) Integrated leak rate test during the week ending June 11, 2022
- (4) Reactor pressure vessel hydrostatic test during the week ending June 30, 2022
Inservice Testing (IP Section 03.01) (2 Samples)
- (1) HPCI 1000-pound test following outage and complications during the week ending June 11, 2022
- (2) Standby feedwater pump 'A' flow test verification on June 30, 2022 RCS Leakage Detection Testing (IP Section 03.01) (1 Partial)
(1)
(Partial)
CARD 22-27022 documenting an increasing trend in RCS unidentified leakage
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) EP drill on May 24,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05)===
- (1) April 1, 2021 - March 31, 2022
MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)
- (1) April 1, 2021 - March 31, 2022
BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)
- (1) April 1, 2021 - March 31, 2022
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 in that might be indicative of a more significant safety issue.
71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Follow-Up (IP Section 03.01)
- (1) The inspectors evaluated the licensees response to a turbine trip and automatic reactor scram on June 24, 2022, due to electrical transient on 345 kV main generator disconnect switchyard.
INSPECTION RESULTS
Unsecured and Unapproved Ladder Near Safety-Related Equipment Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000341/2022002-01 Open/Closed
[P.3] -
Resolution 71152S During a routine tour of the plant, the inspectors identified an extension ladder set up in the emergency diesel generator (EDG) 12 fuel oil storage tank (FOST) Room. The ladder reached from the floor up to the lube oil storage tank (approximately 12 feet) and was unlabeled and unsecured, contrary to plant procedures. This resulted in an NRC-identified finding of very low safety significance (Green) with an associated Non-Cited Violation (NCV).
Description:
On May 26, 2022, the inspectors toured the EDG 12 FOST room. The room is adjacent to the EDG 12, and houses equipment mainly used for the storage and transfer of lube oil and fuel oil for the EDG. The inspectors noted an extension ladder had been set up from the floor to the top of the lube oil tank (approximately 12 feet in height). The inspectors checked to see if the ladder was secured and labelled in accordance with plant procedures. The ladder was not secured in any way, nor was there a ladder tag affixed to the ladder. Site procedures govern ladder installation because during seismic events they can become a hazard to nearby equipment. The ladder tagging process is used to ensure ladders are installed according to standards and tracked. In this instance, during a seismic event there was a potential for the ladder to topple into safety-related equipment. Additionally, contrary to procedure the ladder was set up within three inches of safety-related equipment (instrument tubing and piping for the fuel oil transfer pumps). The inspectors reported the issue by phone to the control room supervisor. On June 3, 2022, the inspectors reviewed the last several days' worth of CARDs (corrective action documents) and noticed that there were no CARDs written for the ladder. The inspectors contacted the shift manager. The shift manager confirmed that the ladder had in fact been moved but that a CARD had not been generated at the time. The shift manager ensured a CARD was created.
Corrective Actions: The ladder was removed, and a CARD generated.
Corrective Action References: CARD 22-26823
Performance Assessment:
Performance Deficiency: Licensee procedure MOP23 Enclosure E, "Ladder Installation and Tracking," Revision 8 requires that all general use ladders, when unattended or not in immediate use, be secured and identified with a General Use tag. Further, the procedure states a minimum of three inches horizontal and one-inch vertical separation be maintained between equipment and ladders in safety-related areas. Contrary to these requirements, a ladder was installed in a safety-related area without being secured or labelled.
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, contrary to plant procedures, a ladder was installed such that it could become a hazard to nearby safety-related equipment designed to mitigate accidents during a seismic event. Additionally, there is evidence of a lack of sensitivity towards correcting plant storage issues. For instance, when identified by the inspectors, a CARD was not generated until the NRC asked about the condition several days later. Further, the licensee has had several violations of this nature within recent quarters (NCV 2021004-01; NCV 2021001-01).
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power.
Specifically, based on the best information available regarding when the ladder could have been placed in the plant, the inspectors were able to answer no to all of the questions in IMC 0609, Appendix A, Exhibit 2.
Cross-Cutting Aspect: P.3 - Resolution: The organization takes effective corrective actions to address issues in a timely manner commensurate with their safety significance. Specifically, despite violations of this nature within recent quarters (NCV 2021004-01; NCV 2021001-01),a negative trend exists in the proper storing and staging of materials.
Enforcement:
Violation: Technical Specification 5.4.1, "Procedures," requires, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978. Section 9 of Regulatory Guide 1.33 states, in part, that maintenance that can affect the performance of safety-related equipment should be properly preplanned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances. The licensee established procedure MOP23, "Plant Storage," Revision 8, to implement storage and staging requirements of equipment during, in part, maintenance activities that could affect the performance of safety-related equipment. Enclosure E required that all general use ladders, when unattended or not in immediate use, be secured and identified with a General Use tag. Further, the procedure stated a minimum of three inches horizontal and one-inch vertical separation be maintained between equipment and ladders in safety-related areas.
Contrary to the above, on May 26, 2022, the licensee failed to implement a procedure recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978.
Specifically, the inspectors discovered a ladder extended and staged in the EDG 12 FOST room that was neither secured nor labelled. Further, it was within the minimum required distance away from safety related equipment. Based on the best available information, the violation is assumed to have existed for 1-2 days.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Fire Protection Equipment Blocked Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000341/2022002-02 Open/Closed
[P.3] -
Resolution 71152S An NRC-identified finding of very low safety significance (Green) with an associated NCV occurred when the inspectors identified a manual fire alarm station blocked by a cart, contrary to plant procedures.
Description:
On June 7, 2022, the inspectors found a tool cart blocking access to a manual fire pull station on the first floor of the reactor building. There were no personnel around nor evidence of ongoing work. The inspectors reviewed CARDs (corrective action documents) related to fire protection issues, as it was believed during the outage the same pull station had been blocked. Besides finding the CARD documenting the issue during the outage, the inspectors found a CARD from four days prior (June 3, 2022) that identified the same pull station being blocked by the same cart. Additionally, the inspectors found another CARD from the day before (June 6, 2022) documenting other fire protection equipment being blocked by staged material elsewhere in the plant. The inspectors performed a further review of CARDs and discovered that going back to February 13, 2022, in addition to the three aforementioned issues, ten CARDs had been written documenting fire protection equipment being blocked.
Some of those CARDs documented several issues at once (i.e. four of six fire extinguishers, and three out of four manual pull stations blocked on one walk down). On March 22, 2022, the site initiated a trend CARD documenting issues with blocked fire protection equipment.
Following this trend CARD, issues continued with five of the ten CARDs mentioned above being written, followed by the three in June (one of which, a two-time repeat issue, was identified by the inspectors). Additional trend CARDs were written: 22-26671, "NQA Area of Concern - Lack of station sensitivity to potential fire hazards," 5/30/2022, and 22-24731, "NQA RF21 Observation-Trend - Station not incorporating and using lessons-learned,"
4/5/2022. Despite the station-recognized trend, continued instances of blocking fire protection equipment continued. The most recent trend CARD following NRC identification, 22-27006, "Gap identified in the fire protection program criteria for fire prevention," was classified as NCAP (not meeting the threshold for entry into the formal corrective action process).
Corrective Actions: Multiple trend CARDs were written. Individual issues were corrected soon after discovery.
Corrective Action References: CARD 22-27006.
Performance Assessment:
Performance Deficiency: Procedure MOP11, "Fire Protection," defines "storage" in section 3.15 and refers to the requirements of MOP23, "Plant Storage." MOP23 states in Enclosure D that storage or staging that could impact the ability of operators to reach equipment is not allowed. Further, it states fire brigade response time is crucial to keep fires from propagating and that blocking of required equipment will slow response time. Contrary to these requirements, a manual fire pull station was repeatedly blocked.
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, continued blocking of fire protection equipment could result in delays responding to an actual fire should it occur. The inspectors were informed by IMC 0612, "Issue Screening," Section 05.01, paragraph b.2. While improper staging of equipment is generally a human error issue, the inspectors viewed the various examples as a condition of "evidence showing an increased likelihood that the error may be repeated," and not an isolated incident.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix F, Fire Protection and Post - Fire Safe Shutdown SDP. Specifically, the inspectors determined in accordance with step 1.3 that the finding had a 'low' degradation rating. The inspectors based this on an assessment of the Attachment 2 examples for fire detection systems and findings against hot work permitting/fire watch provisions since there was not an exact matching example. In those examples, there was a partial degradation in capability (i.e. other extinguishers were nearby or other portions of a suppression system were available). The inspectors determined this was analogous to individual pull stations or extinguishers being obstructed.
Cross-Cutting Aspect: P.3 - Resolution: The organization takes effective corrective actions to address issues in a timely manner commensurate with their safety significance. Specifically, the inspectors noted a number of repeat issues regarding the blockage of fire protection equipment despite numerous CARDs (including trend CARDs) being written.
Enforcement:
Violation: Technical Specification 5.4, "Procedures," states, in part, that written procedures will be established, implemented, and maintained covering various subjects, one of which is the fire protection program. Procedure MOP11, "Fire Protection," implements the fire protection program. MOP11 refers to the requirements in MOP23, "Plant Storage." Enclosure D of MOP23 states, in part, that storage or staging that could impact the ability of operators to reach equipment is not allowed. Further, it states fire brigade response time is crucial to keep fires from propagating and that blocking of required equipment will slow response time. Contrary to these requirements, a manual fire pull station was repeatedly blocked with a tool cart, which could impede fire brigade response time. The pull station was identified as blocked by inspectors on June 7, 2022. On June 3, 2022, the pull station was blocked and identified by licensee personnel. The pull station was also identified as blocked on February 13, 2022, by licensee personnel. In each instance, access was restored within a day. The licensee generated a CARD in each instance.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Observation: Continuing trend in parts control 71152S The inspectors noted an NQA-identified (Nuclear Quality Assurance) CARD regarding improper management and storage of quality material outside the warehouse (CARD 22-27175). Several examples were provided of unapproved storage areas, missing monthly inspections, and inventory logs that weren't up-to-date. Most of the examples centered around the Fermi 1 storage areas, however, the inspectors noted an ongoing trend of material control issues going back to at least 2015 site-wide. NQA findings were identified in 2015 and 2017, an elevation was written in 2019, and an escalation in 2020 by NQA, all centered around material control. The NRC identified issues within this timeframe as well:
CARD 22-23291 regarding stop-gap measures not put in place following identification of environmental control issues in a storage area, and 19-27193 regarding differences between PT Events (tasks) to check areas for parts and what the material control procedures require. During the current inspection period, the NRC toured shop areas and determined there may be inconsistent and/or unclear requirements for how long material is allowed to be staged outside the warehouse before work begins. The licensee stated recurring tasks to remove material from the shops that was not going to be used in the near future had been eliminated. The licensee was going to revisit the need for the periodic walkdowns.
Additionally, a part removed from the plant was being used as a training aid in one of the shops but was not labelled correctly per procedure. While the inspectors did not discover any operability or functionality concerns resulting from the various observations (therefore screened as minor issues), the inspectors were concerned about the recurring issues in material control.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 6, 2022, the inspectors presented the integrated inspection results to Peter Dietrich, Chief Nuclear Officer, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
2-26750
EDG 11 Switchgear Room Division 1 Temp Controller
Display is Blank
Corrective Action
Documents
2-26819
EDG Governor Amphenol Connections
Corrective Action
Documents
Resulting from
Inspection
2-26936
NRC Identified Issues in the Reactor Building
06/08/2022
Corrective Action
Documents
Resulting from
Inspection
2-27542
NRC Identified Missing Labels for EDG 11
06/29/2022
Drawings
Diagram Core Spray System Reactor Building
Drawings
Core Spray System CSS Reactor Building
Drawings
Emergency Equipment Cooling Water System Division 2
BW
Drawings
RHR Service Water Makeup Decant and Overflow Systems
Functional Operating Sketch
03/15/2022
Drawings
Reactor Building Closed Cooling Water Functional Operating
Sketch
Drawings
Emergency Equipment Cooling Water (Division 2) Functional
Operating Sketch
BE
Drawings
Emergency Diesel Generator System Functional Operating
Sketch
05/18/2022
Drawings
P & ID Diesel Generator System Division 1 RHR Complex
10/22/2015
Drawings
P & ID Diesel Fuel Oil System & Lube Oil System Division I
RHR Complex
2/03/2018
Drawings
P & ID RHR Service Water System Division 1 RHR Complex
03/15/2022
Drawings
P & ID Diesel Generator Ventilation RHR Complex Division 1 10/15/2014
Drawings
RHR Complex Ventilation Diesel Generators and Switchgear
10/31/1985
Miscellaneous
23.127
1B
Division 2 EECW Valve Lineup
Miscellaneous
23.127
Division 2 EECW Electrical Lineup
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2B
Miscellaneous
23.127
3B
Division 2 EECW Instrumentation Lineup
Miscellaneous
23.127
Division 2 RBCCW/ECCW Standby Verification Checklist
Miscellaneous
23.203
1B
Core Spray System Division 2 Initial Valve Lineup
Miscellaneous
23.203,
4B
Division 2 Core Spray Standby Independent Verification
Checklist
Miscellaneous
T2300-
000014(32)
Bay 14 and Part of Bay 15: Refuel Outage Torus Diving
Activities -> Division 1 Core Spray and TWMS North Suction
04/07/2022
Procedures
23.207
Diesel Generator System Procedure
Procedures
23.208
Diesel Generator Service Water System
Corrective Action
Documents
2-10224
Extent of Condition Concern Related to 22-23350
04/07/2022
Corrective Action
Documents
2-22857
Recommendation: Station Electrical Cord/Lead Management
Program
04/07/2022
Corrective Action
Documents
2-23350
Electrical Near Miss with a 480V/100 Amp Appleton
Connector
03/09/2022
Corrective Action
Documents
2-24539
Safety Concern Identified as There is no Access to a Phone
Inside the Drywell
04/01/2022
Corrective Action
Documents
2-24719
NQA - RF21 - Allied Performed Work Activities without
Appropriate Direction for Work Order 58384874 EDP 80124
Travel Path Interferences Drywell Cooler 13
04/05/2022
Corrective Action
Documents
2-24752
A Small Fire in the Drywell Basement Near Drywell Cooler
was Extinguished Within Three Minutes by the Fire
Watch
04/05/2022
Corrective Action
Documents
2-24800
Extent of Condition for DWC Fire
04/06/2022
Corrective Action
Documents
Resulting from
Inspection
2-21392
Broken Phone - NRC Identified
2/09/2022
Drawings
Fire Protection Functional Operating Sketch
2/15/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Fire Plans
FP-AB-2-9b
Auxiliary Building, Division 1 Switchgear Room, Zone 9,
EL. 613' 6"
Fire Plans
FP-AB-3-14F
Auxiliary Building DC Motor Control Center (MCC) Room
Zone 14, EL. 643'-6"
Fire Plans
FP-CWPH-1-32
Circulating Water Pumphouse Zone 32, Elevation 583'6"
Fire Plans
FP-RB-B-5b
Reactor Building Basement Northeast Corner Room Zone 5,
EL. 562.0"
Fire Plans
FP-RHR-1-14-
RHR Complex, EDG 14 Room, EL. 590' 0"
Miscellaneous
Radiological Emergency Response Preparedness Letter of
Agreement
11/03/2021
Miscellaneous
Generic Hot Work Fire Watch Lesson Plan
Miscellaneous
Fire Brigade
Record Form
LP-FP-940-2512/CWPH Switchgear Room, Circ. Water
Pumphouse Zone 32
06/09/2022
Procedures
20.000.22
Plant Fires
Procedures
28.501.08
Fire Hose Station Monthly Inspection
Procedures
28.502.02
CO2 System Valve Lineup Verification
Procedures
MOP 11-100
Fire Protection Implementation
Corrective Action
Documents
2-25099
Area of Concern Identified on South RHR Hx Channel Cover
Work Orders
90990172
EDP-70288 Removal - Reinstallation of Channel cover
04/04/2022
Corrective Action
Documents
2-00052
Discrepancies Encountered During Data Taken During
Performance of 57.000.15
05/25/2022
Miscellaneous
Rod Pull Sheet - Sequence A002
2/14/2022
Miscellaneous
20625 Reactor Startup Reactor Engineering RMP
Supplement
Miscellaneous
Reactivity Maneuvering Plan - 220625 Reactor Startup
Procedures
2.000.02
Plant Startup to 25 Percent Power
106
Procedures
2.000.03
Power Operation 25% to 100% to 25%
107
Procedures
23.138.01
Reactor Recirculation System
119
Procedures
57.000.15
Recirculation System Performance Data Collection and
Speed Limiter Setpoint Determination
Corrective Action
Documents
2-21563
Overthrust of E1150F024A While Testing
2/11/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
2-27461
FO 22-01 Start Up WalkDown MOV Actuator Disconnected
from Bonnet
06/27/2022
Corrective Action
Documents
2-27475
Actuator Broke Free of Yolk Mounting Bolts - B2103F019
06/27/2022
Corrective Action
Documents
2-27545
IST Evaluation 22-019 PMT Requirements (B2103F019)
06/29/2022
Corrective Action
Documents
2-27547
IST Evaluation 22-108 Appendix J AF and AL Testing
Requirements (B2103F019)
06/29/2022
Drawings
061531
NPS 3" - Class 900 OSY Gate Valve
D
Drawings
M-6089
3" 900 Lb - Powell OSY Gate Valve with Limitorque Operator
A
Procedures
35.306.003
Limitorque Motor Operator - Periodic Inspection
56A
Procedures
35.LIM.004
Limitorque SMB-000 Operator - Maintenance
Procedures
35.LIM.007
SMB-Style Limitorque Operator Removal and Installation
Procedures
35.LIM.011
Motor, Motor Pinion, Torque Switch and Limit Switch Rotor
Installation/Replacement
Procedures
47.306.06
MOV Diagnostic Testing with the Quicklook 3 System
Work Orders
58375116
IST Req'd - Perform MOV Diagnostic Testing B2103F019
Corrective Action
Documents
2-23206
Bus 72EB Pos 2D Failed to Open
03/07/2022
Corrective Action
Documents
2-24674
E1150F008 Thrust Trace Indicates Increased Stem Nut
Wear
04/04/2022
Corrective Action
Documents
2-24770
Gland Follower Shifted Slightly After Operations Stroke
04/06/2022
Corrective Action
Documents
2-26548
9D14 Trip of 72EB 2D Breaker
05/25/2022
Drawings
Residual Heat Removal Division 2
Miscellaneous
FRAGNET Schedule for Forced Outage Dated 6/25/2022
06/25/2022
Miscellaneous
Agenda-Startup 1 OSRO Meeting Number 1536 OSRO
06/25/2022
Procedures
MMR Appendix H
Online Core Damage Risk Management Guidelines
Procedures
ODE-20
Protected Equipment
Procedures
SOE 20-03
AVR Testing with Degraded Vacuum Test Procedure
Work Orders
65369048
Breaker 72EB Pos. 2D Tripped
05/25/2022
Work Orders
65371264
Troubleshooting for Cause of 72EB, Pos. 2D Trip
05/25/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
2-22578
Faulted Secondary Side Cable (64 Transformer)
2/24/2022
Corrective Action
Documents
2-22578-02
Past Operability Review
03/14/2022
Corrective Action
Documents
2-22724
Results of Secondary Side Cable Testing on 64 Transformer
(Event Z896)
2/24/2022
Corrective Action
Documents
2-22972
Division 2 RHR Heat Exchanger Channel Cover May Have
Same Indications as North
03/02/2022
Corrective Action
Documents
2-24011
B2103F019 Degraded DC Motor Performance
03/21/2022
Corrective Action
Documents
2-24613
As-Found Inspection of E1101B001B Indicates Bypass Flow
Present in Heat Exchanger
04/03/2022
Corrective Action
Documents
2-25734
Spurious RPS A1 Actuator Trip and Half Scram
04/27/2022
Corrective Action
Documents
2-26351
3D56 Testability Logic CH/A/B RPS/PWR Failure -
B21N617B Gross Failure Downscale
05/16/2022
Corrective Action
Documents
2-26412
3D56 Testability Logic CH A/B RPS/PWR Failure in Alarm
05/17/2022
Corrective Action
Documents
2-27163
Square Rooter Found OOT During Jet Pump Flow Loop
Calibration
06/15/2022
Corrective Action
Documents
2-27271
Received 3D18 IPCS Monitored Inputs Abnormal Due to
Loss of Input of Total Core Average Flow
06/20/2022
Corrective Action
Documents
2-27280
Create Procedure for Alternate Method to Measure
Recirculation Loop Flow
06/20/2022
Corrective Action
Documents
2-27349
Received 3D18 IPCS Monitored Inputs Abnormal due to
Loss of Input of Total Core Flow Average
06/22/2022
Corrective Action
Documents
2-27461
FO 22-01 Start Up WalkDown MOV Actuator Disconnected
from Bonnet
06/27/2022
Corrective Action
Documents
2-27475
Actuator Broke Free of Yolk Mounting Bolts - B2103F019
06/27/2022
Corrective Action
Documents
Resulting from
Inspection
2-27708
NRC Question - CARD 22-26351 Past Operability
07/05/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
061531
NPS 3" - Class 900 OSY Gate Valve
D
Drawings
61721-2225-02
Schematic Diagram - HPCI System Power Distribution
S
Drawings
61721-2714-01
Schematic Diagram - EDG Automatic Digital Load
Sequencing System
G
Drawings
Reactor Protection System Trip system 'A' Scram Trip Logic
M
Drawings
RPS Trip System A2 Scram Trip Logic
C
Drawings
M-2089
Nuclear Boiler System
BP
Drawings
M-5707-01
Nuclear Boiler System Functional Operating Sketch
Drawings
M6089
3" 900 LB - Powell OSY Gate Valve with Limitorque
Operator
A
Miscellaneous
21-27388
Equipment Cause Evaluation
Procedures
23.601
Instrument Trip Sheets
Procedures
23.601
Instrument Trip Sheets
Procedures
24.000.02
Shiftly, Daily, and Weekly Required Surveillances
161
Procedures
44.020.435
NSSSS - Turbine Building Area Temperature Trip System 'B'
Channel 'B' B21-N617B Calibration/Functional
& 31
Work Orders
64138108
Replace Surge Suppressor on MSIV DC Pilot Selonoids
03/05/2022
Work Orders
64138289
Replace Surge Suppressor on SG Relay P44M803B
04/13/2022
Work Orders
64138347
Replace Surge Suppressor on EDG Sequencer Circuit
04/09/2022
Engineering
Changes
2-0012
Design Change Package 22-0012 Temporary Monitoring of
RPS A1 Trip String in H11P609
05/04/2022
Corrective Action
Documents
16-25611
2016 EQ Program Self-Assessment Deficiency: EQ Central
Files EQ1-EF2-020 and - 058 Lack Formal Documentation
for the Use of "Sound Reasons to the Contrary" IAW with
10CFR50.49 Par. (1)
07/14/2016
Corrective Action
Documents
2-21822
Upper Main Bearing Degraded
2/15/2022
Corrective Action
Documents
2-22914
Testing Results of Cable 200001H-0P After Repairs
2/26/2022
Corrective Action
Documents
2-23316
CARD 22-23316 Smoke Generated in Relay Room TIP VCM
C Drawer During Firing of TIP C Squib 3/932022
03/09/2022
Corrective Action
Documents
2-23629
Damaged Cable
03/18/2022
Corrective Action
2-23638
NQA RF21 - EQ Engineer Request to Add QC Hold Points
03/14/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
for EDP 80144, EQ Seals
Corrective Action
Documents
2-23847
EDP-80144, Cannot be Implemented for Restoring
Non-Conforming P44N401B EQ Seal in RF21
03/18/2022
Corrective Action
Documents
2-23950
EQ Seals Procedure Change for RTD's
03/20/2022
Corrective Action
Documents
2-23986
NQA - RF21 - Rework Required for Several TRDs Being
Replaced for EDP 80144 EQ Seals
03/21/2022
Corrective Action
Documents
2-24744
RTD Resistance Less than 1 Megaohm
04/05/2022
Corrective Action
Documents
2-24748
NQA RF21 - MSIV Junction Box Supports Do Not Meet
Design Criteria
04/05/2022
Corrective Action
Documents
2-24983
Existing Cables for T48N468B are to Short to Make Splice
04/10/2022
Corrective Action
Documents
2-25028
EDP-80024 - VAS Input Paddle Board Design Error
04/11/2022
Corrective Action
Documents
2-25464
As Lefts for 45.606.06 Section 6.6 Table 4 As Lefts
Tolerance Could Not Meet Criteria
04/21/2022
Corrective Action
Documents
2-25931
Potential MMA18 Violation - Work Performed Without
Clearance
05/02/2022
Corrective Action
Documents
2-25936
Rework WO 57242646 Due to 'B' Indexer N2 Purge Line
from C5102J011 is Not Connected
05/03/2022
Corrective Action
Documents
2-26226
Unexpected HPCI Turbine Trip
05/11/2022
Corrective Action
Documents
2-26318
E4150F012 Cycling Open/Closed after HPCI System S/D
from Surveillance Run
05/14/2022
Corrective Action
Documents
2-26351
3D56 Testability Logic CH A/B RPS/PWR Failure -
B21N617B Gross Failure Downscale
05/16/2022
Corrective Action
Documents
2-26412
3D56 Testability Logic CH A/B RPS/PWR Failure in Alarm
05/17/2022
Corrective Action
Documents
Resulting from
Inspection
2-25094
Potential Damage to Main Steam Tunnel Leak Detection
RTD Found by NRC
04/12/2022
Corrective Action
2-25553
NRC Identified Broken Conduits
04/23/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Resulting from
Inspection
Drawings
Instrument Tubing Plans and Details Traversing in Core
Probe System
C
Drawings
Primary Containment Pneumatic Supply system
Z
Engineering
Changes
DCP 80144
EQ Conduit Seal Replacements
B
Miscellaneous
FCR 80024-7
Paddle Board Jumpers
Miscellaneous
VMC1-61
Rosemont 710DU Trip/Calibration System
G
Procedures
23.307
Emergency Diesel Generator System
131
Procedures
23.316
Procedures
23.601
Instrument Trip Sheets
Procedures
44.020.435
NSSSS - Turbine Building Area Temperature, Trip System
'B' Channel 'B' B21-N617B Calibration/Functional
& 31
Procedures
44.020.438
NSSSS - Turbine Building Area Temperature, Trip System
B, Channel D B21-N616D Calibration/Functional
Procedures
MMA 11
Post Maintenance Testing Guidelines
Work Orders
2485692
Main Steam Tunnel Leak Detection RTD
03/08/2022
Work Orders
58547562
EDP-80144 Replace EQ Seals for RTDs in TB Steam
Tunnel B21N117A - B21N117D
04/29/2022
Work Orders
60746030
Perform Splice Repair(s) of Cable 200001H-0P at
Secondary Side of SS XFMR#64
03/03/2022
Work Orders
64717612
Smoke Generated in Relay Room TIP VCM C Drawer During
05/05/2022
Work Orders
267358
Unexpected HPCI Turbine Trip, Troubleshoot and Repair
05/11/2022
Work Orders
269101
Replace Failed HPCI Speed Sensor
05/12/2022
Work Orders
297203
3D56 Testability Logic CH A/B RPS/PWR Failure -
B21N617B Gross Failure Downscale
05/17/2022
Work Orders
65315835
3D56 Testability Logic CH A/B RPS/PWR Failure in Alarm
Swap B21N117B Leads
05/18/2022
Corrective Action
Documents
2-00213
Failure of TIP Movement in Channel 10 for Multiple TIP
Drawers
05/05/2022
Corrective Action
2-23343
Fuel Bundles Require Re-Seating Prior to Core Verification
03/09/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Corrective Action
Documents
2-25511
E5100F113 Leaks at 60 DPM during Hydro Pressure Test
04/22/2022
Corrective Action
Documents
2-25548
PIP Positions Missing from CR 54-23 (Repeat Problem)
04/23/2022
Corrective Action
Documents
2-25674
APS-Supervisor Hold Point Bypassed
04/26/2022
Corrective Action
Documents
2-25884
Reactor Engineering Needs to Know if Scram Time Testing
is Required on Various Control Rods
05/01/2022
Corrective Action
Documents
2-25914
IPCS Showing 179 Rod Drifts with Only 6 Rods Indicating
Full In
05/02/2022
Corrective Action
Documents
2-25965
Need to Perform PM M590 for the SRFPT Prior to Startup
05/03/2022
Miscellaneous
Master core
loading pattern
Cycle 22 Master Core Loading
04/19/2022
Procedures
20.205.01
Loss of Shutdown Cooling
Procedures
2.000.02
Plant Startup to 25 Percent Power
106
Procedures
23.610
Procedures
23.623
Reactor Manual Control System
Procedures
2.000.04
Refueling and Core Post - Alteration Verification
04/09/2022
Procedures
ODE-20
Protected Equipment
Procedures
Shutdown Safety
Risk
Management
Plan
RF21 Reactor Cavity Drain Down Evolution
2/21/2022
Corrective Action
Documents
2-26267
Engineering Evaluation HPCI
05/12/2022
Corrective Action
Documents
2-26277
DW Floor Drain Sump Inlet Flow Change
05/13/2022
Corrective Action
Documents
2-26337
E4150F012 Exceeded Industry Guidance for MOV Motor
Starts
05/15/2022
Corrective Action
Documents
2-27022
Drywell Unidentified Leakage is Increasing
06/10/2022
Corrective Action
2-27342
ODMI-22-002 and Associated AIM Actions for Drywell
06/22/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Unidentified Leakage Team
Corrective Action
Documents
2-27399
Drywell Floor Drain Sump Level Recorded Indicated a 1 Inch
Step Change in Level After Pump Down
06/24/2022
Corrective Action
Documents
Resulting from
Inspection
2-27604
NRC Identified - IPCS Drywell Floor Drain Leakage
Indications Investigation
06/30/2022
Drawings
High Pressure Coolant Injection System (HPCI) Reactor
Building
BQ
Drawings
High Pressure Coolant Injection System Barometric Cylinder
Reactor Building
AJ
Drawings
Residual Heat Removal Division 1
BS
Procedures
2.000.05
Pressure/Temperature Monitoring During Heatup and
Cooldown
Procedures
24.000.02
Shiftly, Daily, and Weekly Required Surveillances
161
Procedures
24.107.03
SBFW Pump and Valve Operability and Lineup Verification
Test
Procedures
24.137.21
Reactor Pressure Vessel System Leakage Test
Procedures
43.401.100
Integrated Leak Rate Test - Type 'A' - General
34A
Procedures
47.425.01
Unidentified Drywell Leakage Response Guidelines
Procedures
54.000.03
Control Rod SCRAM Insert Time Test
& 61
Procedures
MES 49
Evaluation and Control of Leakage from Class 1, 2, and 3
Piping Systems
Procedures
MGA 02
Procedure, Manuals, and Orders
Procedures
MMA 11
Instrument Testing
Procedures
MMA 11
Miscellaneous Equipment Testing
Work Orders
241895
Perform 24.202.01 HPCI Pump/Flow Test and Valve Stroke
at 1025 PSIG
05/06/2022
Work Orders
64980231
Perform 28.501.19 (SECT 5.2) Deluge System Functional
Test for System Service Transformer 65-License Renewal
04/13/2022
Work Orders
65327770
Perform 24.202.01 HPCI Pump/Flow Test and Valve Stroke
at 1025 PSIG
05/18/2022
Corrective Action
Documents
2-26595
May 2022 RERP Drill Critique - TSC Staffing
05/26/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
2-26727
RERP Drill 052422 - Marginal Objective Rating K5
06/01/2022
Corrective Action
Documents
2-26728
RERP Drill 052422 - Inconsistency with Facility Updates and
Facility Briefs
06/01/2022
Corrective Action
Documents
2-26904
RERP Drill 052422 - Failed Objective F3.2 (WebEOC Use)
06/07/2022
Miscellaneous
May 24, 2022 Drill Package
05/24/2022
Procedures
Classification of Emergencies
Procedures
Procedures
Drills and Exercises
71151
Miscellaneous
MSPI Derivation Report - High Pressure Injection System
Unreliability Index
March 2022
71151
Miscellaneous
MSPI Derivation Report - High Pressure Injection System
Unavailability Index
March 2022
71151
Miscellaneous
Selected Operators' Log Entries
April 2021 -
March 2022
71151
Miscellaneous
Fermi 2 HPCI Performance Indicators
April 2021 -
March 2022
71151
Miscellaneous
MSPI Derivation Report - Emergency AC Power System
Unavailability Index (UAI)
April 2021 -
March 2022
71151
Miscellaneous
MSPI Derivation Report - Emergency AC Power System
Unreliability Index (URI)
April 2021 -
March 2022
71151
Miscellaneous
EDG MSPI and WANO Performance Indicators
April 2021 -
March 2022
71151
Miscellaneous
RCS Leakage Data
April 2021 -
March 2022
71151
Procedures
24.000.02
Reactor Coolant System (RCS) Operational Leakage
April 2021 -
March 2022
Corrective Action
Documents
2-24926
NQA RF21 - Safety Related Parts Not Properly Controlled
04/08/2022
Corrective Action
Documents
2-26531
Humidity Exceeded 60 Percent in Level 'A' Storage C&M
Buildings
05/24/2022
Corrective Action
Documents
2-26820
Blocked Manual Alarm Station on Reactor Building 1
06/03/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
2-26871
Blocked Manual Alarm Pull Station
06/06/2022
Corrective Action
Documents
2-27175
NQA Audit 22-0105 Finding - MMM 08 Requirements Not
Implemented by Projects for Storing QA 1 Material Outside
of the Warehouse
06/15/2022
Corrective Action
Documents
Resulting from
Inspection
19-27193
NRC Identified Concern - PT Events ME76 and ME77
09/24/2019
Corrective Action
Documents
Resulting from
Inspection
2-23291
NRC Identified: Stop Gap was Not Put in Place for ARD
2-22406
03/08/2022
Corrective Action
Documents
Resulting from
Inspection
2-26823
NRC Identified Concern: During Walkdown of EDG 12 Fuel
Oil Room There was a Ladder Staged to the EDG 12 Day
Tank
06/03/2022
Corrective Action
Documents
Resulting from
Inspection
2-27709
NRC Identified - CARD not Generated in a Timely Manner
for NRC Identified Condition
07/05/2022
Corrective Action
Documents
Resulting from
Inspection
2-27710
NRC Identified - Fire Protection CARDs Being Classified as
NCAP
07/05/2022
Corrective Action
Documents
Resulting from
Inspection
2-27711
NRC Observation - Parts Staging
07/05/2022
Corrective Action
Documents
Resulting from
Inspection
2-29936
NRC Identified Issues in the Reactor Building
06/08/2022
Procedures
35.306.020
Motor Operated Valve Mini Periodic Inspection
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
MMM 07-100
Material Request and Return
Procedures
MOP 22
Ladder Installation and Tracking
Procedures
MQA 11-300
Screening and Assignment
Work Orders
57168882
Replace Electrolytic Capacitors in RCIC Pump Discharge
Flow Indicator
06/28/2022
Work Orders
59415366
Calibrate RPV Jet Pump 11 Flow/Pressure Indicating Loop
06/15/2022
Work Orders
65157979
RF21 - Division II CCHVAC Chiller Surging
05/01/2022
Work Orders
269101
Replace Failed HPCI Speed Sensor
05/12/2022
Corrective Action
Documents
20-27545
Loss of 345kV Due to Mayfly Infestation
07/02/2020
Corrective Action
Documents
2-27403
Turbine Trip Resulting in Reactor Scram
06/25/2022
Corrective Action
Documents
2-27602
FO 22-01 Perform TORMIS Evaluation of Portable Lights
and Fans for 27.322 Mayfly Infestation Preparation Plan
06/30/2022
Drawings
SD-2500-01
One Line Diagram Plant 4160V and 480V System Service
Procedures
27.322
Mayfly Infestation Preparation Plan
& 22