IR 05000263/2024001
ML24117A352 | |
Person / Time | |
---|---|
Site: | Monticello ![]() |
Issue date: | 04/29/2024 |
From: | Richard Skokowski NRC/RGN-III/DORS/RPB3 |
To: | Hafen S Northern States Power Company, Minnesota |
References | |
IR 2024001 | |
Download: ML24117A352 (1) | |
Text
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT - INTEGRATED INSPECTION REPORT 05000263/2024001
Dear Shawn Hafen:
On March 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Monticello Nuclear Generating Plant. On April 11, 2024, 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.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Richard A. Skokowski, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety Docket No. 05000263 License No. DPR-22
Enclosure:
As stated
Inspection Report
Docket Number:
05000263
License Number:
Report Number:
Enterprise Identifier:
I-2024-001-0075
Licensee:
Northern States Power Company, Minnesota
Facility:
Monticello Nuclear Generating Plant
Location:
Monticello, MN
Inspection Dates:
January 01, 2024 to March 31, 2024
Inspectors:
N. Bolling, Acting Resident Inspector
T. McGowan, Resident Inspector
C. Norton, Senior Resident Inspector
J. Reed, Health Physicist
Approved By:
Richard A. Skokowski, Chief
Reactor Projects Branch 3
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated 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 to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000263/2023-002-00 LER 2023-002-00 for Monticello Nuclear Generating Plant, Reactor Scram and Containment Isolation due to Valve Responses during Main Turbine Control Valve Testing 71153 Closed LER 05000263/2023-003-00 LER 2023-003-00 for Monticello Nuclear Generating Plant, Condition Prohibited by Technical Specifications due to Inoperable Main Steam Line Low Pressure Isolation Switch 71153 Closed
PLANT STATUS
Monticello began the inspection period at rated thermal power. On February 28, 2024, the unit tripped and entered Mode 4. On March 2, 2024, the licensee commenced a reactor startup, and synced to the grid on March 3, 2024. The unit returned at or near rated thermal power on March 5, 2024. On March 27, 2024, the licensee performed a shutdown to Mode 4 to replace a safety relief valve. On March 30, 2024, the licensee commenced a unit startup, and synced to the grid on March 31, 2024, and ended the inspection period at 31% of rated thermal power.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather on January 10, 2024.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Emergency diesel generator (EDG) 11 starting air and fuel oil systems prior to making EDG 12 inoperable for testing on January 30, 2024
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Fire Zone 1-E, high pressure coolant injection (HPCI) room on January 4, 2024
- (2) Fire Zone 1-G, control rod drive pump room on January 4, 2024
- (3) Fire Zone 14-A, upper 4KV bus area (14 and 16) on January 5, 2024
- (4) Fire Zone 12-A, lower 4KV bus area (13 and 15) on January 5, 2024
- (5) Fire Zone 1-C, reactor core isolation cooling room on January 10, 2024
- (6) Fire Zone 2-H, west shutdown cooling area on January 12, 2024
- (7) Fire Zone 33, emergency filtration building third floor on January 12, 2024
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 reactor startup to critical and the point of adding heat on March 2, 2024.
- (2) The inspectors observed and evaluated licensed operator performance in the control room during reactor startup on March 31, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated crew as found simulator exam on January 16, 2024.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) P111D, emergency service water (ESW) pump 14
- (2) F safety relief valve degrading tailpipe temperature on March 26, 2024
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 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) Risk associated with the B feedwater regulating valve lockup on January 16, 2024
- (2) Risk associated with clamping C outboard main team isolation valve (MSIV)instrument air line on February 7, 2024
- (3) Risk associated with anticipated transient without scram reactor coolant pump trip reactor pressure restoration of setpoint after reactor SCRAM on February 29, 2024
- (4) Risk associated with cycling breaker 3A-CB1, reactor manual control system 120 VAC logic power supply on March 7, 2024
- (5) Risk associated with HPCI inboard steam isolation valve and failure of leak rate testing isolation valves on March 28, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
(1)
===501000081180, ESW 14 quarterly flow degradation (2)501000080744, VD-9175B, B control room pressure control damper failed to open (3)501000082034, inadvertent BKR 4300 operation (4)501000082532, check valve failed during RHRSW quarterly (5)501000082683, reactor pressure vessel bottom head cooldown rate >100 degrees per hour (6)501000082407, LS-2-3-680F and LS-2-3-680H reactor feed pump and main turbine trip failure to reset
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
=
The inspectors evaluated the following temporary or permanent modifications:
- (1) VD-9175A emergency filtration train control room ventilation damper
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (2 Samples)
- (1) The inspectors evaluated forced outage MIF 3202 activities from February 28 to March 2, 2024.
- (2) The inspectors evaluated forced outage MIF 3203 activities from March 26 to 31, 2024.
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (10 Samples)
- (1) B.05.07-05, local manual control of feedwater regulating valves after repair of programable logic controller on January 20, 2024
- (2) Electric fire pump after replacement of the seal water PCV on February 27, 2024
- (3) K61D relay replacement, March 1, 2023
- (4) Reactor manual control system after power supply breaker exercising on March 7, 2024
- (5) HPCI governor actuator remote servo after maintenance on March 22, 2024
- (6) HPCI governor after maintenance on March 22, 2024
- (7) HPCI gland seal drain pump after maintenance on March 22, 2024
- (8) HPCI inlet steam trap drain after maintenance on March 22, 2024
- (9) HPCI exhaust pressure root valve after replacement on March 22, 2024
- (10) A Inboard MSIV after packing adjustment due to steam leak on March 31, 2024
Surveillance Testing (IP Section 03.01) (4 Samples)
- (1) Security system emergency generator operability check and alarm on January 8, 2024
- (2) EDG 12 quarterly test on January 29, 2024
- (3) Residual heat removal (RHR) pump 11 time delay over current relay calibration on March 5, 2024 (4)2-of-4 voter average power range monitor channel functional test on March 14, 2024
Inservice Testing (IST) (IP Section 03.01) (2 Samples)
- (1) RHR service water B pump testing on January 26, 2024
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) Licensed operator requalification including emergency classification and notification on January 16,
RADIATION SAFETY
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling,
Storage, & Transportation
Radioactive Material Storage (IP Section 03.01)
The inspectors evaluated the licensees performance in controlling, labeling, and securing the following radioactive materials:
(1)10 CFR 37 material storage locations
- (2) Radioactive materials stored outside the protected area
Radioactive Waste System Walkdown (IP Section 03.02) (2 Samples)
The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
- (1) Condensates resin processing system
- (2) Reactor water clean-up (RWCU) system
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste:
- (1) RWCU
- (2) Dry active waste (DAW)
Shipping Records (IP Section 03.05) (4 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
- (1) Radioactive material shipment 23-57 containing control rod drive mechanisms in a general design package
- (2) Radioactive waste shipment 23-99 containing powder resin of class A waste in a general design package
- (3) Radioactive material shipment 24-04 containing control rod drive equipment in a general design package
- (4) Radioactive waste shipment 23-92 containing powder resin of class A waste in a general design package
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) January 1, 2023, through December 31, 2023 IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
- (1) January 1, 2023, through December 31, 2023
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
- (1) January 1, 2023, through December 31, 2023
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow up (IP Section 03.01)
- (1) The inspectors evaluated a reactor SCRAM with recirculation pump trip and licensees response on February 28, 2024.
Event Report (IP Section 03.02) (2 Samples)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000263/2023-002-00, Reactor Scram and Containment Isolation due to Valve Responses during Main Turbine Control Valve Testing (ADAMS Accession No. ML23317A359). The inspectors determined that the cause of the condition described in the LER was not reasonably within the licensee's ability to foresee and correct, and therefore was not reasonably preventable. No performance deficiency nor violation of NRC requirements was identified. This LER is Closed.
- (2) LER 05000263/2023-003-00, Condition Prohibited by Technical Specifications due to Inoperable Main Steam Line Low Pressure Isolation Switch (ADAMS Accession No. ML23338A184). The inspectors determined that the cause of the condition described in the LER was not reasonably within the licensees ability to foresee and correct, and therefore was not reasonably preventable. The inspection conclusions associated with this LER are documented in this report under Inspection Results Section. This LER is Closed.
INSPECTION RESULTS
Minor Violation 71153 LER 05000263/2023-003-00, Condition Prohibited by Technical Specifications due to Inoperable Main Steam Line Low Pressure Isolation Switch Minor Violation: The inspectors reviewed LER 05000263/2023-003-00, Condition Prohibited by Technical Specification (TS) due to Inoperable Main Steam Line Low Pressure Isolation Switch, for the licensees failure to comply with the actions required in TS limiting condition for operation (LCO) 3.3.6.1. Specifically, on October 7, 2023, at 0228 when the reactor entered Mode 1, the licensee failed to enter TS LCO 3.3.6.1 Condition A for One or more required channels inoperable, when the B1 main steam line low pressure isolation switch reset prior to its allowed TS value. This condition existed until it was discovered and corrected on October 10, 2023, at 0901 when the B1 main steam line low pressure isolation switch was recalibrated using TS Surveillance Requirement (SR) 3.3.6.1.4. As a result, the licensee operated in a condition prohibited by TS by failing to place the affected channel in trip within the required time in TS LCO 3.3.6.1 Condition A and subsequently failing to transition to Mode 2 by the required time in TS LCO 3.3.6.1 Condition E.
Screening: The inspectors determined the performance deficiency was minor.
Enforcement:
This failure to comply with Technical Specification 3.3.6.1 constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 11, 2024, the inspectors presented the integrated inspection results to Shawn Hafen, and other members of the licensee staff.
- On March 7, 2024, the inspectors presented the radiation protection baseline inspection results to K. Lorensen, Director Site Performance and Operations Support, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
1444
Pre and Post Severe Weather Inspection Checklist
2154-14
Fuel Oil System Prestart Valve Checklist
Procedures
2154-28
Diesel Generator Air Start System Prestart Valve Checklist
Strategy A.13-12-
A
Lower 4 KV Bus Area (13&15)
Strategy A.3-01-C
RCIC Room and Appendix R Cable Enclosure
Strategy A.3-01-E
HPCI Room - Reactor Building Elevation 896'
Strategy A.3-01-G
Fire Zone 1-G, CRD Pump Room
Strategy A.3-02-H
West Shutdown Cooling Area
Strategy A.3-14-A
Upper 4KV Bus Area (14&16)
Fire Plans
Strategy A.3-33
EFT Building Third Floor
Corrective Action
Documents
Resulting from
Inspection
501000082463
IRM 12 HI HI Light on C-36 During SU
03/03/2024
Miscellaneous
RQ-SS-203
Loss of Control Rod Drive, Loss of Load Center 103, Bus 15
Lockout, Reactor Water Cleanup Leak Requiring Blowdown
1371
Drywell Prestart Inspection
2159
Predicted Critical for Plant Startup
2167
Plant Startup
110
2167-04
Startup Checklist for Surveillance Requirements
2167-05
Startup Checklist for Transition from Mode 2 to Mode 1
2300
Reactivity Adjustment
Procedures
253 B
Defeat/Reinstall Drywell Personal Airlock Interlocks
Procedures
255-11-III-4
ESW 14 Quarterly Pump and Valve Tests
501000080923
B FRV Lockup
01/17/2024
501000080960
CV-6-12B-IL Amber Light Not Lit
01/17/2024
501000080971
PRA Model for Main FRV Configuration
01/17/2024
Corrective Action
Documents
501000080986
Challenge Board Materials Timeliness
01/18/2024
Engineering
Evaluations
601000004946
Replace HPCI-1 and HPCI-2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
700136403
Weld Control Record HPCI-1/HPCI-2
03/28/2024
FP-PA-HU-05
Type 2-Operational Decision Making Issue
Evaluation - AO-2-86C (13 OTBD MSIV) Pilot Air Line
2/06/2024
Miscellaneous
FP-WM-IRM-01
Planning and Approval of High Risk or Scheduled Risk
Work - Restore Set-Point PIS-2-3-678C
2/29/2024
B.05.07-03
Local Manual Control of Main FW Reg Valves
Procedures
C.6-005-B-40
FW Control Valve Locked
7000091883
3A-CB1-Cycle Breaker
700130106-0020
ATWS RCP Trip Reactor Pressure
Work Orders
700136403-0030
M-2035 Upstream Test/Drain
Calculations16-062
Development of Test Acceptance Criteria Basis for Monticello
FSW Pumps
0A
501000058253
V-D-9175A Failed to Open
05/19/2022
501000068971
V-EAC-14A Tripped During CRV Swap
01/09/2023
501000075980
VD-9175B Didnt Open When B CRV Placed in Service
08/13/2023
501000077303
VD-9175B Does Not Open
10/02/2023
501000078405
255-11-III-4 Flow Less Than 71.0 gpm
10/30/2024
501000080176
VD-9175B Failed to Open
2/20/2023
501000080744
VD-9175B Failed to Open
01/10/2024
501000081180
ESW Quarterly Flow Degradation
01/23/2024
501000082034
Inadvertent BKR 4300 Operation
2/18/2024
501000082407
High Level Trips Not Clearing
03/01/2024
501000082532
Check Valve Failed During RHRSW Quarterly
03/05/2024
501000082683
RPV Bottom Head Cooldown Rate>100/hr
03/08/2024
Corrective Action
Documents
501000082684
Further Evaluation Needed for 501000082683
03/09/2024
Drawings
NH-170037
Main Control Room CRV/EFT System
Engineering
Evaluations
2400420.401
Initial Operability Summary for the MNGP Reactor Pressure
Vessel Bottom Head
03/08/2024
255-05-IA-1-1
A RHRSW Quarterly Pump and Valve Tests
255-11-III-4
ESW Quarterly Pump and Valve Tests
B.09.07-05
Operations Manual Section: 480 Volt Station Auxiliary
Procedures
Evaluate Failure of SW-21-1, 21-2, 22-1, and 22-2 through
3/4 Inch Keep Fill Lines
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ECR4849-NX-
20010-29
Control Panel C243A Wiring Diagram
0-76
ECR4849-NX-
20010-32
Control Panel C243A Wiring Diagram
0-E
NE-93503-18
Damper VD-9175A Control Scheme V211 Channel 1
Drawings
NE-93527
Loop Diagram Outlet Flow From V-ERF-14-A/B Flow Control
Engineering
Changes
601000004849
Modify EFT Hydramotor Damper Logic
2140
Deinerting Primary Containment
2167
Plant Startup
110
2167-03
Startup Transition from Mode 4 to Mode 2
204
Plant Shutdown
2300
Reactivity Maneuvering Steps
2404-03
Shutdown Checklist Transition from Mode 3 to Mode 4
B.03.04-05 D.1.
Shutdown Cooling Mode-Loop A Startup
OSP-CRD-0539-
A
Control Rod Testing
IRM Functional Test
Procedures
SRM Functional Test
Corrective Action
Documents
501000080637
Over Crank Alarm Received
01/08/2024
0187-02
Emergency Diesel Generator 12/Emergency Service Water
Quarterly Pump and Valve Tests
111
255-04-IA-2
RHR System Cold Shutdown Valve Operability Tests
255-05-IA-1-2
B RHRSW Quarterly Pump and Valve Tests
255-06-IA-1
HPCI Quarterly Pump and Valve Tests
113
255-06-IA-1
HPCI Quarterly Pump and Valve Tests
113
298-02
Security System Emergency Generator Operability
Check & Alarm
1069
HPCI Flow Control System Dynamic Test Procedure
4850-504-PM
2-504, 11 RHR Pump Relay Maintenance, Calibration and
Trip Testing
Procedures
B.08.05-05
Start P-110 Electric Fire Pump
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-of-4 Voter Channel Functional Check
OPS MAN
B.02.04-05
OPs Man
B.05.02-05 Rod Worth Minimizer
OPS Man
B.08.01.03-05
Startup of RHRSW Pump
OSP-MSC-0542-
Breaker Alignment and Indicating Power Availability
Verification of Required Offsite Circuits
PCV-3163
PMT/RTS
Seal Water PCV to Electric Fire Pump (P-110)
700080595-0020
Replace Relay K61D
700091883
PMT/RTS Instructions After RMCS 120 Control Power Breaker
Cycling
03/07/2024
700112498-0010
Security System EDG - Annual Check
01/08/2024
700133351-0070
MT:1CFW:CV-6-12B, B Main Feed Water Regulation Valve
Work Orders
700136470-0010
INBD MSIV AO-2-80-A Adjust Packing
Procedures
FP-EP-EPIP-01
ERO Position Checklist
501000073443
Class B RW Shipment to Non-QSL Location
05/09/2023
501000078865
NOS: Issues in Rad Waste Shipment Record
11/09/2023
501000079937
Rad Waste Drumming Aisle
2/11/2023
Corrective Action
Documents
501000081633
Lost Part 61 Paperwork
2/04/2024
501000082538
03/05/2024
501000082591
Records Legibility Issues
03/05/2024
501000082605
Shipment 23-92 Documentation
03/06/2024
Corrective Action
Documents
Resulting from
Inspection
501000082628
Accurate Records Submission
06/06/2024
Engineering
Changes
601000003555
RDS-1000 Replacement
03/23/2023
Engineering
Evaluations20-002
Evaluation of Used Oil for Radiological Contamination
5863
Dewatering Resins in Waste Liners
Procedures
FP-RP-RW-001
Additional Security Measures for Transportation of Radioactive
Material Part 37 Category 1 Quantities
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
FP-RP-RW-02
Radioactive Shipping Procedure
FP-RP-RW-03
10CFR37 Material Accountability
FP-RP-RW-09
Rad Waste Streams and Scaling Factors
PCP-01
Process Control Program for Wet Radioactive Wastes
R.06.09
Storage and Inventory of Radioactive Material Outside the
Power Block
600001146487
NRC Inspection Activities for IP71124.08.
2/15/2023
Self-Assessments
606000002023
71124.08 Radioactive Solid Waste Processing and
Radioactive Material Handling, Storage, and Transportation
2/05/2023
22 RWCU
50/50 Mix
10CFR61 Analysis for Reactor Water Clean-Up
08/08/2022
23-57
Shipping Papers for Twelve Control Rod Drive Mechanisms
05/09/2023
23-92
Shipping Papers for Dewatered Powder Resin
08/18/2023
23-99
Shipping Papers for Dewatered Powder Resin
09/22/2023
24-04
Shipping Papers for CRD Handling System Tooling
01/16/2024
L101029
10CFR61 Analysis for Secondary Resin Waste Stream
2/05/2024
Shipping Records
L101029-3
10CFR61 Analysis for Dry Active Waste (DAW)
2/05/2024
Work Orders
700120331-0010
Semiannual Source Inventory and Smear Test
2/13/2023
71151
Miscellaneous
QF0445
Monthly Operating Report - Generation Occurrences,
January 2023 - December 2023
Drawings
NF-36790
Reactor Vessel Thermocouple Locations & Expansion Lead
FP-E-TS-01
Troubleshooting Plan PCIS - Group 1 Isolation
FP-PA-CSE-01
Cause Evaluation Template Reactor Scram Number 141
FP-PA-CSE-01
Equipment Cause Evaluation PS-2-134B Out of As-Found
Miscellaneous
FP-PA-HU-05
Type 2 - Operational Decision Making Issue Evaluation Group
Isolation on Main Steam Line High Flow
Operability
Evaluations
FP-OP-OL-01
Past Operability Review PS-2-134B
0058-B
Main Steam Line Low Pressure Group 1 Isolation Instrument
Test and Calibration (RX in Run)
0118
Reactor Vessel Temperature Monitoring
B.01.04-05
Reactor Recirculation System H.6 Stratification Recovery
Procedures
FP-OP-REP-01
Event Reporting and Notification Process
13