IR 05000259/2023002
| ML23221A274 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/10/2023 |
| From: | Louis Mckown NRC/RGN-II/DRP/RPB5 |
| To: | Jim Barstow Tennessee Valley Authority |
| References | |
| IR 2023001, IR 2023002 | |
| Download: ML23221A274 (15) | |
Text
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000259/2023002, 05000260/2023002, 05000296/2023002 AND 07200052/2023001
Dear Jim Barstow:
On June 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Browns Ferry Nuclear Plant. On July 20, 2023, the NRC inspectors discussed the results of this inspection with Mr. Manu Sivaraman 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, Louis J. McKown, II, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Nos. 05000259, 05000260, 05000296 and 07200052 License Nos. DPR-33, DPR-52 and DPR-68
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000259, 05000260, 05000296 and 07200052
License Numbers:
Report Numbers:
05000259/2023002, 05000260/2023002, 05000296/2023002 and
07200052/2023001
Enterprise Identifier:
I-2023-002-0013 and I-2023-001-0108
Licensee:
Tennessee Valley Authority
Facility:
Browns Ferry Nuclear Plant
Location:
Athens, Alabama
Inspection Dates:
April 01, 2023 to June 30, 2023
Inspectors:
P. Cooper, Senior Reactor Inspector
P. Gresh, Emergency Preparedness Inspector
N. Karlovich, Resident Inspector
D. Neal, Health Physicist
K. Pfeil, Resident Inspector
J. Steward, Senior Resident Inspector
J. Walker, Sr Emergency Preparedness Inspector
Approved By:
Louis J. McKown, II, Chief
Reactor Projects Branch #5
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Browns Ferry Nuclear 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
None.
PLANT STATUS
Unit 1 began the inspection period at full (100 percent) rated thermal power (RTP). On May 20, 2023, operators lowered power to 80 percent RTP to perform turbine control valve testing. On May 20, 2023, the unit scrammed during turbine control valve testing (Forced outage F110). Following corrective actions, the unit was restarted on May 22, 2023, and returned to full RTP on May 27, 2023. On June 10, 2023, operators lowered power to 33 percent RTP to perform planned maintenance on Offgas condenser drain valves and returned to RTP on June 10, 2023, where it operated at or near this level for the remainder of the inspection period.
Unit 2 began the inspection period at full RTP. On June 2, 2023, operators lowered power to 68 percent RTP to perform a planned control rod sequence exchange. On June 3, 2023, the unit was returned to full RTP where it operated at or near this level for the remainder of the inspection period.
Unit 3 began the inspection period at 98 percent RTP and returned to full RTP on April 2, 2023. On April 22, 2023, operators manually scrammed the unit to commence a planned forced outage (F312) to perform condenser circulating water repairs. Following these repairs, the unit was restarted on April 28, 2023, and returned to full RTP on May 4, 2023, where it operated at or near this level for the remainder 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
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal hot temperatures for the following systems:
Residual Heat Removal Service Water pumps on June 15, 2023.
Condenser Circulating Water pumps on June 15, 2023.
Control Bay Chillers on June 15, 2023.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Units 1 and 2 Shutdown battery chargers and batteries A, C, and D due to shutdown battery B out of service on April 28, 2023
- (2) Units 1 and 2 Emergency Diesel Generator (EDG) lube oil, starting air and emergency equipment cooling water systems during planned maintenance of Residual Heat Removal Service Water D1 pump on May 16, 2023
- (3) Unit 2 1B Control Rod Drive injection path when Control Rod Drive pump 2A was out of service on May 17, 2023
- (4) Unit 3 Control Bay chiller 3A while Unit 3 Control Bay chiller 3B was out of service on May 26, 2023
- (5) Unit 3 Emergency Diesel Generator (EDG) 3D starting air, fuel oil, electrical and panel lineup during Unit 3 EDG 3C planned maintenance on June 14, 2023.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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 Area 20, Units 1 and 2 EDG building elevations 565' and 583', on May 16, 2023
- (2) Fire Area 16-A, Units 1 and 2 Cable Spreading Room A, Control Building elevation 606', on June 15, 2023
- (3) Fire Area 16-O, Unit 3 Auxiliary Instrument Room 3, Control Building elevation 593',
on June 16, 2023.
- (4) Unit 1 High Pressure Coolant Injection (HPCI) pump room, Fire Area 1-1, Reactor Building elevation 519' on June 22, 2023
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
The inspectors observed and evaluated licensed operator performance in the Control Room during the following evolutions:
- (1) Unit 3 shutdown activities including the removal of condensate and feedwater pumps during power descension, insertion of a manual scram and scram recovery, and portions of unit cooldown to Mode 4 to commence a planned maintenance outage (F312) on April 22, 2023
Unit 3 startup activities including control rod withdrawal to criticality to point of adding heat, overlap of source range and intermediate range instrumentation, and withdrawal of source range detectors on April 28, 2023
Unit 3 main turbine roll to 1800 rpm and main generator synchronization to the grid to conclude F312 on April 29, 2023.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a licensed operator requalification training session in the Unit 2 simulator which included a simulated reactor building closed cooling water pump trip, fire in intake pumping structure, safety relief valve lift, anticipated transient without scram, reactor coolant system leak, and standby containment spray on May 30, 2023. This training session required the crew to enter various abnormal operating instructions, emergency operating instructions, and emergency plan implementing procedures to control the plant and appropriately classify the emergency.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 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) Unit 3 elevated risk (yellow) due to reactor power changes greater than 10 percent on April 29, 2023
- (2) Unit 1 elevated risk (yellow) due to scram during control valve testing on May 20, 2023.
- (3) Unit 1 emergent work activities in response to Control Rod 54-19 drift on June 22, 2023
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 2 Main Turbine Bypass Valve No. 1 operability assessment per CR 1848592 on April 19, 2023
- (2) Unit 2 HPCI suction pressure indicator operability assessment per CR 1828723 on April 26, 2023
- (3) Units 1 and 2 EDG B operability assessment per CRs 1826924 and 1826921 on May 19, 2023
- (4) Unit 3 Control Room Air Handling Unit 3B operability assessment per CR 1837659 on May 25, 2023
- (5) Unit 2 jet pump pairs 11/12, and 15/16 operability assessment per CR 1845877 on June 1, 2023
- (6) Unit 3 Main Steam Line D relief valve thermocouple operability assessment per CR
===1861199 on June 21, 2023
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) BFN 23-002, Unit 2 HPCI gland seal leak off piping reroute permanent modification on April 25, 2023
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01)===
- (1) The inspectors evaluated various Unit 3 forced outage F312 activities from April 22, 2023, through May 4, 2023
- (2) The inspectors evaluated various Unit 1 forced outage F110 activities from May 20, 2023, through May 22, 2023
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) (2 Samples)
(1)0-RM-90-259A, control room radiation monitor spiking during sounding of fire and medical emergency bell per work order (WO) 123612988 on April 24, 2023
- (2) Unit 2 HPCI gland seal leak off piping reroute inservice leak post maintenance test per WO 123243874 on April 25, 2023
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) Unit 1 Turbine Control Valve Fast Closure/Turbine Trip and Recirculation Pump Trip initiation Logic, 1-SR-3.3.1.1.8(9), per WO 122747830 on May 23, 2023
- (2) Unit 1 Reactor Heatup rate monitoring, 1-SR-3.4.9.1(1), per WO 123746198 on May 24, 2023
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) Unit 3 Core Spray flow rate, 3-SR-3.5.1.6(CS1) on May 8, 2023
71114.01 - Exercise Evaluation
Inspection Review (IP Section 02.01-02.11) (1 Sample)
- (1) The inspectors evaluated the biennial emergency plan exercise during the week of June 26, 2023. The exercise scenario began with a 4KV shutdown bus feeder breaker tripping open, causing a loss of all offsite power to two of the three units shutdown boards for more than 15 minutes. This met the conditions for declaring an Unusual Event. Afterwards, a reactor coolant system leak (RCS) develops in the drywell. An Alert is declared when radiation monitor readings rise above values for loss of RCS barrier. Radiation levels continue to rise above threshold for loss of fuel clad barrier and a Site Area Emergency is declared. When a steam leak in the Reactor Core Isolation Cooling (RCIC) is unable to be isolated, the conditions for a General Emergency are met allowing the Offsite Response Organizations to demonstrate their ability to implement emergency actions.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of June 26, 2023.
This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) The inspectors reviewed and evaluated the emergency response organization drill response during a training drill scenario on May 3, 2023. Elements of the drill included lowering spent fuel levels and elevated main turbine vibrations followed by an anticipated transient without scram. The inspectors observed the licensee assess emergency action levels and protective action recommendations as they progressed through the action levels and compared the licensee's response to the requirements contained in the licensee's emergency plan implementing procedures.
71114.08 - Exercise Evaluation - Scenario Review
Inspection Review (IP Section 02.01 - 02.04) (1 Sample)
- (1) The inspectors reviewed and evaluated in-office, the proposed scenario for the biennial emergency plan exercise at least 30 days prior to the day of the exercise.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) Unit 1 (April 1, 2022, through March 31, 2023)
- (2) Unit 2 (April 1, 2022, through March 31, 2023)
- (3) Unit 3 (April 1, 2022, through March 31, 2023)
MS07: High Pressure Injection Systems (IP Section 02.06) (3 Samples)
- (1) Unit 1 (April 1, 2022, through March 31, 2023)
- (2) Unit 2 (April 1, 2022, through March 31, 2023)
- (3) Unit 3 (April 1, 2022, through March 31, 2023)
MS08: Heat Removal Systems (IP Section 02.07) (3 Samples)
- (1) Unit 1 (April 1, 2022, through March 31, 2023)
- (2) Unit 2 (April 1, 2022, through March 31, 2023)
- (3) Unit 3 (April 1, 2022, through March 31, 2023)
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) April 1, 2022, through March 31, 2023.
EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) April 1, 2022, through March 31, 2023.
EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) April 1, 2022, through March 31, 2023.
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors performed a semiannual review of licensee problem identification program documents to identify potential trends that might indicate the existence of a more significant safety issue on June 2, 2023. Specifically, CR 1855226, identified a trend in parts that are identified as "like-for-like" but are not "like for like." The licensee's apparent cause evaluation identified gaps with the procurement process which resulted in specific corrective actions which have been incorporated into the apparent cause evaluation product for CR 1847346. No violations of regulatory requirements were identified as a result of this review.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow-up (IP section 03.01)
- (1) The inspectors evaluated the events and circumstances related to the Unit 2 Event Notification 56411 on March 15, 2023, which was subsequently retracted on March 28, 2023. The inspectors reviewed both the submittal and the retraction. No findings were identified as a result of this review.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
===60855 - Operation Of An ISFSI 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) 2690, Inspection Program for Storage of Spent Reactor Fuel and Reactor-Related Greater-than-Class C Waste at Independent Spent Fuel Storage Installations (ISFSI) and for 10 CFR Part 71 Transportation Packagings."
Operation Of An ISFSI===
- (1) From June 5 - 8, 2023 the inspectors performed a review of the licensees ISFSI activities to verify compliance with regulatory requirements. During the on-site inspection, the inspectors observed and reviewed licensee activities in each of the five safety focus areas including occupational exposure, public exposure, fuel damage, confinement, and impact to plant operations.
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. Additionally, the inspectors performed independent walkdowns of the heavy load lifting equipment and the ISFSI haul path. The inspector also performed an independent radiation survey of the ISFSI pad.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 20, 2023, the inspectors presented the integrated inspection results to Mr. Manu Sivaraman and other members of the licensee staff.
On June 29, 2023, the inspectors presented the Emergency Preparedness Exercise Inspection results to Mr. J. Quinn and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
0-GOI-200-3
Hot Weather Operations
Rev 15
Procedures
0-OI-23
Residual Heat Removal Service Water System
Rev 109
Procedures
0-OI-31
Control Bay and Off-Gas Treatment Building Air
Conditioning System
Rev 173
Drawings
0-47E840-3
Flow Diagram Fuel Oil System
Rev 27
Drawings
0-47E861-5
Flow Diagram - Cooling System and Lubricating Oil System
Standby Diesel Generator A
Rev 17
Drawings
0-47E861-6
Flow Diagram - Cooling System and Lubricating Oil System
Standby Diesel Generator B
Rev 15
Drawings
1-47E859-1
Flow Diagram Emergency Equipment Cooling Water
Rev 101
Drawings
3-47E861-4
Flow & Control Diagram Diesel Starting Air System Diesel
Gen 3D
Rev 22
Drawings
3-47E861-4A
Flow Diagram Diesel Starting Air System Diesel Gen 3D
Rev 11
Drawings
BFN-0-47E861-
Flow Diagram Diesel Starting Air System Diesel Gen B
Rev 9
Procedures
0-OI-18
Fuel Oil System
Rev 58
Procedures
0-OI-31
Control Bay and Off-Gas Treatment Building Air
Conditioning System
Rev 173
Procedures
0-OI-31/ATT-1
Valve Lineup Checklist
Rev 138
Procedures
0-OI-31/ATT-2
Panel Lineup Checklist
Rev 136
Procedures
0-OI-31/ATT-3
Electrical Lineup Checklist
Rev 137
Procedures
0-OI-31/ATT4
Instrument Inspection Checklist
Rev 137
Procedures
0-OI-67/ATT-1
Valve Lineup Checklist
Rev 93
Procedures
0-OI-82/ATT-1A
1A Standby Diesel Generator A Valve Lineup
Checklist
Rev 103
Procedures
0-OI-82/ATT-1B
1B Standby Diesel Generator B Valve Lineup
Checklist
Rev 102
Procedures
2-OI-85
Control Rod Drive System
Rev 160
Procedures
2-OI-85
Instrument Inspection Checklist
Rev 132
Procedures
2-OI-85/ATT-1
Valve Lineup Checklist
Rev 131
Procedures
2-OI-85/ATT-2
Panel Lineup Checklist
Rev 129
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
2-OI-85/ATT-3
Electrical Lineup Checklist
Rev 128
Procedures
3-OI-82
Standby Diesel Generator System
Rev 157
Procedures
3-OI-82
Standby Diesel Generator System
Rev 157
Procedures
3-OI-82/AT-1B
Standby Diesel Generator 3B valve Lineup Checklist
Rev 99
Procedures
3-OI-82/ATT-2B
Standby Diesel Generator 3B Panel Lineup Checklist
Rev 98
Procedures
3-OI-82/ATT-3B
Standby Diesel Generator 3B Electrical Lineup Checklist
Rev 98
Procedures
3-OI-82/ATT-4B
Standby Diesel Generator 3B Instrument Inspection
Checklist
Rev 9
Procedures
NPG-SPP-07.3.4
Protected Equipment
Rev 13
Fire Plans
FPR Appendix F -
FA16
Appendix F Fire Area 16
Rev 6
Fire Plans
FPR-Volume 2
Fire Protection Report Volume 2
Rev 76
Procedures
NPG-SPP-18.4.7
Control of Transient Combustibles
Rev 17
Procedures
NPG-SPP-18.4.8
Control of Ignition Sources (Hot Work)
Rev 14
Miscellaneous
SEG
- OPL175S901E,
Evaluation
Scenario
RBCCW pump trip/Fire at IPS/SRV lift/FWH leak/RCS leak
in DW/ATWS/STBY containment spray
Rev 0
Procedures
3-AOI-100-1
Reactor Scram
Rev 80
Procedures
3-GOI-100-12A
Unit Shutdown from Power Operation to Cold Shutdown and
Reductions in Power Operations
Rev 78
Procedures
3-GOI-100-1A
Unit Startup
Rev 144
Procedures
3-OI-47
Turbine Generator System
Rev 137
Corrective Action
Documents
1857715
05/20/2023
Engineering
Changes
BFN-20-1688-04
Reconfigure Unit 1 CV LVDTs
Rev 1
Engineering
Evaluations
Complex trouble
shooting for U1
Scram while
performing control
valve testing
associated with
CR 1857715
U1 Scram while performing control valve testing
05/21/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
1-AOI-85-5
Rod Drift In
Rev 5
Procedures
1-AOI-85-7
Mispositioned Rod
Rev 7
Corrective Action
Documents
1837659
Corrective Action
Documents
1848592,
1845280
Prompt Determination of Operability for Unit 2 Main Turbine
Bypass Valve No. 1
04/19/2023
Corrective Action
Documents
CR 1828723
Corrective Action
Documents
CR 1845877
Corrective Action
Documents
CRs 1826924,
26921
Drawings
0-47E861-2
Flow & Control Diagram Diesel Starting Air System Diesel
Generator B
Rev 13
Drawings
0-47E861-2A
Flow Diagram Diesel Starting Air System Diesel Gen B
Rev 9
Miscellaneous
BFN-50-702
Standby Diesel Generator
Rev 29
Miscellaneous
BFN-VTD-E147-
1910
Specification for GM Model 999 System Generating Plant
Rev 0
Procedures
OPDP-8
Operability Determination Process and Limiting Condition for
Operation Tracking
Rev 30
Engineering
Changes
BFN-23-002
Unit 2 HPCI Gland Seal Leak Off Piping Reroute permanent
modification
Rev 1
Corrective Action
Documents
1850759
04/24/2023
Corrective Action
Documents
CR 1858374,
1857707,
1858409
Procedures
1-SR-3.3.1.1.8(9)
Turbine Control Valve Fast Closure or Turbine Trip and RPT
Initiate Logic
Rev 23
Procedures
1-SR-3.4.9.1(1)
Reactor Heatup and Cooldown Rate Monitoring
Rev 14
Procedures
PMT-0-000-
MEC001
Leak Checks on Tube Fittings, Threaded, Flanged, Bolted or
Welded Connections
Rev 9
Work Orders
23243874
04/25/2023
Work Orders
23612988
04/24/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
Reactor Heatup rate monitoring
5/24/23
Procedures
Radiological Emergency Plan (Generic Part)
Rev. 115
Procedures
Browns Ferry Nuclear Plant Radiological Emergency Plan,
Appendix A
Rev. 112
Procedures
EPIP-1
Emergency Classification Procedure
Rev. 67
Procedures
EPIP-1,
BFN Hot & Cold Condition ICs/EALs
Rev. 67
Miscellaneous
23 BFN May Integrated Training Drill Scenario Guide
05/03/2023
71151
Miscellaneous
Regulatory Assessment Performance Indicator Guideline
Rev 7
Corrective Action
Documents
1855226,
1847346
06/02/2023
Corrective Action
Documents
CR 1846009,
1842365
Drawings
2-47E801-1-ISI
ASME Section XI Main Steam System Code Class
Boundaries
Rev 22