IR 05000321/2021002
| ML21216A201 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/04/2021 |
| From: | Alan Blamey NRC/RGN-II |
| To: | Gayheart C Southern Nuclear Operating Co |
| T Francis | |
| References | |
| IR 2021002 | |
| Download: ML21216A201 (17) | |
Text
August 04, 2021
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000321/2021002 AND 05000366/2021002
Dear Ms. Gayheart:
On June 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Edwin I. Hatch Nuclear Plant. On July 23, 2021, the NRC inspectors discussed the results of this inspection with Sonny Dean 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,
/RA/
Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects
Docket Nos. 05000321 and 05000366 License Nos. DPR-57 and NPF-5
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000321 and 05000366
License Numbers:
Report Numbers:
05000321/2021002 and 05000366/2021002
Enterprise Identifier: I-2021-002-0015
Licensee:
Southern Nuclear Operating Company, Inc.
Facility:
Edwin I. Hatch Nuclear Plant
Location:
Baxley, GA
Inspection Dates:
April 01, 2021 to June 30, 2021
Inspectors:
C. Curran, Project Engineer
J. Hickman, Senior Resident Inspector
N. Peterka, Fuel Facility Inspector
R. Smith, Senior Resident Inspector
Approved By:
Alan J. Blamey, Chief
Reactor Projects Branch 2
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Edwin I. Hatch 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 100 percent rated thermal power (RTP). On June 11, 2021, the unit was shut down to investigate a step change increase in drywell unidentified leakage. The licensee determined the cause of the increase leakage to be a packing and pressure seal leak on the inboard high pressure coolant injection (HPCI) steam supply valve (1E41-F002). After repairs to the valve, the unit was restarted on June 16, 2021, and reached 100 percent RTP on June 20, 2021. On June 21, 2021, the unit was down powered to 85 percent RTP to perform the final rod pattern adjustment after startup and was returned to 100 percent RTP on the same day. On June 30, 2021, the unit commenced a shutdown to repair turbine temperature switches that were causing half group I signals on the A2 channel.
Unit 2 began the inspection period at 100 percent RTP. On April 8, 2021, the unit reduced power to 20 percent RTP to repair a main generator hydrogen cooler valve. After repairs were completed, the unit was returned to 100 RTP on April 13, 2021. On June 5, 2021, the unit was down powered to 70 percent RTP to perform turbine control valve testing and was returned to 100 percent RTP the same day. On June 26, 2021, the unit was down powered to 91 percent RTP due to fourth stage high pressure feedwater heater isolating. After repairs to the fourth stage high pressure feedwater heater level switch, the unit was returned to 100 percent RTP on June 27, 2021. On June 29, 2021, the unit was down powered to 96 percent RTP to perform the final rod pattern adjustment after the down power and was returned to 100 percent RTP on the same day. The unit operated there 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 reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week, increasing the amount of time on site as local COVID-19 conditions permitted.
As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
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 Summer Readiness for the following systems:
1. Offsite and alternate alternating current (AC) power systems on May 24, 2021.
2. Residual heat removal service water on May 26, 2021.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Alignment of the Unit 1 HPCI system while the reactor core isolation cooling (RCIC)system was inoperative for maintenance, using 34SO-E41-001-1, Version 30.4 on May 4, 2021.
- (2) Alignment of the Unit 2 residual heat removal (RHR) system 'A' and 'C' pumps, using 34SO-E11-010-2, Version 44.5 on May 5, 2021.
- (3) Alignment of the Unit 1 RHR system 'B' pump following emergent repair work on the pump piping, using 34SO-E41-010-1, Version 45.3, on May 12, 2021.
- (4) Alignment of the main control ventilation system following maintenance on the 'C' train, using 34SO-Z41-001-1, Version 24.0, on May 19, 2021.
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 plant service water (PSW) system on June 22, 2021.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 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) Unit 2 RCIC pump and turbine room, on April 21, 2021
- (2) Unit 2 NE RHR and core spray pump room, on April 21, 2021
- (3) Unit 1 working floor and adjustable speed drive (ASD) area, on April 27, 2021
- (4) Unit 1/2 control room, on April 28, 2021
- (5) Unit 1/2 control room roof, on May 5, 2021
- (6) Unit 1 600-volt switchgear rooms 1C/1D, and Unit 1 DC switchgear rooms 1A/1B, on May 19, 2021.
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite live fire brigade training and performance during an announced fire drill on April 15, 2021.
71111.06 - Flood Protection Measures
Cable Degradation (IP Section 03.02) (1 Sample)
The inspectors evaluated cable submergence protection in:
- (1) Safety related cables in pull boxes PB1-BJ and PB2-BJ on April 7, 2021.
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)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during shutdown of Unit 1 caused by a step change increase of drywell unidentified leakage, the inspectors observed reduction of power via decrease in recirculation flow, insertion of control rods followed by a reactor scram from 32 percent power and post scram activities to stabilize the plant in Mode 3 (Hot Shutdown). They also observed transfer of house loads, hourly updates of unidentified leakage calculations, de-inerting the drywell and preps for shutdown cooling on June 11-12, 2021.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated License Requalification Operator Training for the following training scenario: CPE-EOP: Main Turbine Bypass Valve Monthly, Steam Flow Instrument Failure, Fire in the Protected Area, Lowering Vacuum, Scram, Loss of High Pressure Feed, RCIC Steam Line break, RCIC failed to Isolate, Anticipated Emergency Depress, and Emergency Depress on May 5, 2021.
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) Safety related cables exposed to adverse environmental conditions.
(2)1A PSW pump surveillance test results placed the differential pressure ratio in the required action range, which was previously in the alert range. Additionally, the axial vibration level and calculated vibration ratio both increased to the alert range on June 3, 2021.
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) Emergent risk associated with Unit 2 following unplanned system outage of the 2D RHR pump for an extended period from April 16 to April 30, 2021.
- (2) Risk associated with the Unit 1 RCIC system outage from May 4 to May 7, 2021.
- (3) Emergent risk associated with Unit 1 following unplanned piping repair on the 1B RHR pump from May 10 to May 12, 2021.
- (4) Emergent risk associated with the following unplanned equipment failures, Unit 1C emergency diesel generator (EDG), automatic start light failed to illuminate after a monthly run, 1D RHR service water pump tripped from overcurrent, and Unit 2 vital AC inverter failure, from May 28, to June 11, 2021.
- (5) Unit 1 elevated risk for forced outage due to step change increase in drywell unidentified leakage, from June 12 and 18, 2021.
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) Condition Report (CR) 10788308, while performing semi-annual sampling of 2A EDG fuel oil storage tank, water and sediment failed at 2.5 percent on the bottom sample and CR 10788395, water found in 2A fuel oil day tank flush on April 8, 2021.
- (2) CR 10789017, During performance of 34SV-R43-010-0 EDG Fuel Oil Transfer Pump Surveillance, the 2Y52C001A 2A EDG Fuel Oil Transfer Pump was in the alert range for high vibrations and in the action range for high flow on April 09, 2021.
- (3) CR 10790963, While running the 2D Residual Heat Removal (RHR) Pump, alarm RHR Pump D OVLD/Lockout Relay Trip was received and the pump was manually secured. Following alarm relay replacement, the pump was restarted and tripped on Phase 2 overcurrent on April 16, 2021.
- (4) CR 10796694, leak was identified on the 1B Residual Heat Removal pump casing drain line on May 10, 2021.
- (5) CR 10782516, in leakage was seen on Unit 2 Core Spray 'B' loop as observed by increase pressure above jockey pump pressure on March 15, 2021.
- (6) CR 10799968, while performing the 1A Plant Service Water IST Quarterly surveillance, the ratio of the test dP value to reference dP value was calculated to be 0.9189, in the required action range. Axial vibration level was also measured at 0.206 in/sec with a calculated vibration ratio of 2.58, which places it in the alert range on May 23, 2021.
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) Engineering Change (EC) SNC 1118966 for the complete replacement of the Unit 2 turbine building chillers due to obsolete equipment.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
(1)34SV-E11-001-2, Residual Heat Removal Pump Operability, Version 22.2 following the overhaul of 2D RHR pump on April 30, 2021.
(2)34SV-E51-001-1 Reactor Core Isolation Cooling (RCIC) Pump Operability, Version 29.2, and 34SV-E51-001-1 RCIC Valve Operability, Version 18.7, after a Unit 1 RCIC system outage on May 7, 2021.
- (3) NMP-ES-024-301, Liquid Penetrant Examination Color Contrast and Fluorescent, Version 14.0 and 34SO-E11-010-1, Residual Heat Removal (RHR) System section 4.2.5, Version 45.3, after the replacement of 1B RHR pump casing drainpipe on May 12, 2021.
(4)34SV-E41-002-2 High Pressure Coolant Injection Pump (HPCI) Operability, Version 39.2, and 34SV-E41-001-2 HPCI Valve Operability, Version 13.7, after a Unit 2 HPCI system outage on May 13, 2021.
- (5) SNC1133912 Replacement of the Analog Trip and Testing System (ATTS) Power Supply 1E21K401B due to the original power supply failing previously, this work was completed on May 20, 2021.
(6)34SV-P41-001-1, Plant Service Water Pump Operability - 1B Preservice Test Section, Version 15.2 following the 1B pump replacement on May 30, 2021.
(7)34SV-E11-004-1, RHR Service Water Pump Operability - 1D RHRSW Pump Preservice Test Section, version 22.1, following the replacement of the pump and motor, on June 14, 2021.
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated Unit 1 forced outage activities due to increase in drywell unidentified leakage caused by a packing leak and pressure seal leak on the HPCI inboard steam isolation valve 1E41-F002, from June 11 to June 18.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
(1)34SV-P41-001-1, Plant Service Water Pump Operability, Version 15.2 on April 8, 2021.
(2)34SV-R43-002-2, Diesel Generator 1B Monthly Test, Version 26.4 on April 15, 2021.
(3)34SV-E11-004-1, RHR Service Water Pump Operability, Version 22.1 on April 19, 2021.
(4)57SV-C51-012-1, Average Power Range Monitor (APRM) Two-Out-Of-Four Time Response Testing Channel D, Version 0.6 on May 17, 2021.
Inservice Testing (IP Section 03.01) (1 Sample)
(1)34SV-E51-002-1, Reactor Core Isolation Cooling System Pump Operability IST, Version 29.2 on April 8, 2021.
RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)
- (1) CR 10789452 noted an increase in Unit 1 Drywell Floor Drain leakage, on April 10, 2021
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) Emergency Preparedness Drill 21EX02, Loss of Coolant Accident on April 13, 2021.
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Licensed reactor operators respond to a RCIC steam line break in the simulator and the inspectors observed the crew make an emergency declaration and notification. This represented a drill and exercise performance opportunity on May 19,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 03.10)===
- (1) Unit 1 (April 1, 2020 to March 31, 2021)
- (2) Unit 2 (April 1, 2020 to March 31, 2021)
BI02: RCS Leak Rate Sample (IP Section 03.11) (2 Samples)
- (1) Unit 1 (April 1, 2020 to March 31, 2021)
- (2) Unit 2 (April 1, 2020 to March 31, 2021)
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in the maintenance of FLEX equipment that might be indicative of a more significant safety issue.
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) CRs 10800377 and 10799775; pertaining to radiation protection (RP) technicians assigned to the Operations Support Center (OSC) that are not required to have specific training for the Emergency Response Organization (ERO) position. CRs addressing this issue by a licensee's senior RP technician who questioned whether the site is implementing the high standards to support OSC duties.
- (2) Operator Work Arounds, OS-BP-001, Operations Performance Indicators, Ver. 5.1 on June 14,
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 23, 2021, the inspectors presented the integrated inspection results to Sonny Dean and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
10763660, 1076427, 10765536, 10765906, 10766273,
10767122, 10767220, 10768440, 10768453, 10768454,
10768471, 10769701, 10769718, 10771873, 10772188,
10772360, 10772649, 10773111, 10774071, 10775427,
10775872, 10776196, 10776585, 10776712, 10776960,
10777662, 10777755, 10777876, 10778741, 10778745,
10782781, 10782932, 10783001, 10783711, 10784268,
10785362, 10785619, 10785935, 10789039, 10789486,
10792073 and 10796411
Various
10716238, 10717331, 10724811, 10725085, 10728553,
10729316, 10734089, 10739860, 10741950, 10744866,
10750143, 10754860, 10756890, 10759996, 10760944,
10765581, 10765925, 10770167, 10772281, 10773104,
10776508, 10784735, 10792705, 10794164, 10799968
Various
Corrective Action
Documents
Resulting from
Inspection
10795361
05/04/2021
Drawings
BASES PLANT
SYSTEMS B 3.7
B 3.7.2 Plant Service Water (PSW) System and Ultimate
Heat Sink (UHS)
D-11001
SERVICE WATER PIPING AT INTAKE STRUCTURE
91.0
H-11024
SERVICE WATER PIPING
67.0
H-11600
SERVICE WATER AT DIESEL GENERATOR
37.0
H-11609
SERVICE WATER PIPING
2.0
Miscellaneous
HNP-1-FASR-10
10.7 Plant Service Water System
TECH SPEC
PLANT
SYSTEMS 3.7
3.7.2 Plant Service Water
281
Procedures
Residual Heat Removal System
45.3
Residual Heat Removal System
44.5
High Pressure Coolant Injection (HPCI) System
30.4
Plant Service Water System
36.19
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Control Room Ventilation System
24.0
Drawings
A-43965 Sheets
28B, 29B, 30B
and 32B
600V Switchgear Rooms 1C/1D and DC Switchgear Rooms
1A/1B
6.0
Fire Plans
A43965, Sheet
100
Unit 2 RCIC Pump and Turbine Room
2.0
A43965, Sheet 48 Unit 1 and 2 Control Room
4.0
A43965, Sheet 50 Unit 1 and 2 Control Room Roof
1.0
A43965, Sheet 60 Unit 1 Working Floor South Reactor Building Elevation 158'
5.0
A43965, Sheet 99 Unit 2 NE RHR and Core Spray Pump Room
3.0
Procedures
NMP-ES-035-014
Fleet Transient Combustible Controls
5.0
71111.11Q Miscellaneous
H-LR-AF-CPE003 CPE-EOP: Main Turbine Bypass Valve Monthly, Steam
Flow Instrument Failure, Fire in the Protected Area,
Lowering Vacuum, Scram, Loss of High Pressure Feed,
Reactor Core Isolation Cooling (RCIC) Steam Line break,
RCIC failed to Isolate, Anticipated Emergency Depress, and
Emergency Depress
05/02/2021
Procedures
34GO-OPS-014-1 Fast Reactor Shutdown
14.2
Corrective Action
Documents
CR 10795220
05/04/2021
CR 10799968
06/03/2021
NDE Reports
HVA TD Report
Summary 2017-
2-14_2R23-
S004
Tan Delta Test Results for RHE202M02
2/14/2017
HVA TD Report
Summary R22-
S007-ES2-M06
Tan Delta Test Results for R22-S007-ES2-M06
2/25/2020
Procedures
Insulated Cables and Connections Program
1.1
NMP-ES-051
Cable Monitoring Program
9.2
NMP-ES-051-002
Tan Delta Testing
10.2
NMP-ES-051-003
Adverse Localized Equipment Environment Walkdown
2.5
NMP-ES-051-004
Pull Box Inspection
6.0
Corrective Action
Documents
10797456
05/12/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Resulting from
Inspection
Drawings
H-13414
Elementary Diagram Diesel Generation 1C
55.0
Procedures
Naturally Occurring Phenomena
20.0
34GO-OPS-007-0 Shutdown/Refueling Mode Preparation Strategy For Flex
1.2
NMP-OS-010-002 Hatch Protected Equipment Logs
11.1
NMP-OS-019-253 Hatch Unit C Sig-12, Mode 4/5 RPV Inventory Control
2.3
Corrective Action
Documents
10782516
03/15/2021
Drawings
H-26018
Unit 2 Core Spray System
40.0
Engineering
Evaluations
NMP-AD-012-F01 Prompt Determination of Operability for Unit Core Spray
Loop 'B'
05/18/2020
Miscellaneous
2R26 Hatch
Appendix J
Summarization
03/09/2021
Procedures
Cores Spray B Discharge Pressure High
4.4
Section 4.16
Core Spray System - System Pressure Control Due to In
leakage
26.5
Unit 2 LLRT for 2E21-F006B & 2E21-F037B
2/20/2021
Summarized LLRT Test Results for 2R26 Refueling Outage
03/09/2021
Engineering
Changes
SNC1118966
05/05/2021
Miscellaneous
H-15-0079
Unit 2 Turbine building Chiller Replacement - Project Status
Report
2/18/2020
Procedures
RR-1-2
Unit 2 Turbine Building Chillers 2P63-B019B & D Functional
Test
1.1
Corrective Action
Documents
10797252,
10797254
and10797255
05/12/2021
10797478
05/12/2021
10797539
05/12/2021
Miscellaneous
Unit 1 TRM
Mater Equipment Cross Reference - table T10.1-1 (Sheets
3, 4, 5, 11, 12, 13, and 14)
113.0
Procedures
RCIC Turbine Speed Control Test
05/07/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
RHR Service Water Pump Operability
2.1
HPCI Valve Operability
05/13/2021
HPCI Pump Operability
05/13/2021
RCIC Valve Operability
05/07/2021
RCIC Pump Operability
05/07/2021
Plant Service Water Pump Operability
15.2
Analog Master/Slave Trip Unit Calibration
16.8
Datametrics Voltage Converter Calibration
1.1
Work Orders
SNC1061116
05/07/2021
SNC11133912
05/20/2021
SNC115720
Repair of 1B RHR pump leak
05/12/2021
SNC1160130
6/14/2021
SNC1161391
06/11/2021
SNC614849
05/06/2021
SNC792312
05/04/2021
SNC833995
05/06/2021
SNC843513,
SNC842419,
SNC555959,
SNC636522,
SNC553993, and
SNC698526
05/12/2021
SNC845342
05/04/2021
SNC966362
05/04/2021
Miscellaneous
Unit 1: Initial Drywell entry Walkdown Briefing
06/07/2021
Hatch Unit 1: H12021A Drywell Leakage Outage Safety
Assessment
0.0
Procedures
31GO-OPS-024-0 Outage Safety Assessment
5.5
34GO OPS-001-1
Plant Startup
46.1
34GO-OPS-003-1 Startup System Status Checklist
14.8
REACTOR CORE ISOLATION COOLING SYSTEM 1E51-
F008
06/17/2021
COLD SHUTDOWN VALVE OPERABILITY 1E41-F002
06/16/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Cold Shutdown Valve Operability 1E21-F005B
6/17/2021
UNIT 1 LLRT 1E21-F005B
6-15-2021
06/16/2021
06/15/2021
Corrective Action
Documents
10789452
04/10/2021
Corrective Action
Documents
Resulting from
Inspection
10795064
05/03/2021
Miscellaneous
Unit 1 Chemistry
Drywell Floor
Drain Sump Data
04/14/2021
Unit 1 Increase
Drywell Floor
Drain Leakage
Fault Tree
04/12/2021
Procedures
Drywell & Reactor Building Sumps System
15.0
RHR Service Water Pump Operability
2.1
APRM Two-Out-Of-Four Time Response D
0.6
NMP-OS-028
ACMP - U1 DWFD Leakage Elevated
04/14/2021
Work Orders
SNC1102716
05/17/2021
Miscellaneous
Observation
Summary
Emergency Preparedness Observation Form
05/19/2021
71151
Procedures
Reactor Coolant Weekly
04/28/2020
Corrective Action
Documents
10714850, 10714599, 10784312, 10573812, 10781885,
10506986, 10527703, 10781885, 1084501 TE, 1087473 TE,
10796465
Various
Miscellaneous
Compensatory
Actions Requiring
Manipulations
Unit 2 Compensatory Actions List
Current List
Compensatory
Actions Requiring
Manipulations
Unit 1 Compensatory Actions
Current List
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
APC Sheet Number: 2-21-018P
03/16/2021
31GO-OPS-014-0 Annunciator and Plant Component Control
3.3
31GO-OPS-014-0 APC Sheet Number: 2-21-021
03/20/2021
31GO-OPS-014-0 APC Sheet Number: 2-21-020
03/20/2021
31GO-OPS-014-0 APC Sheet Number: 2-13-028P
09/12/2013
31GO-OPS-014-0 APC Sheet Number: 2-13-028P
06/12/2015
NMP-GM-002-
001
Corrective Action Program Instructions
40.0
NMP-OS-019-059 FLEX Storage Building Operating Instructions
2.1
NMP-OS-028
1B SJAE Monitoring Unit 1
2/04/2020
NMP-OS-028
U1 DWFD Leakage Elevated
04/16/2021
NMP-OS-028
Unit 1 Turbine Building Chilled Water System
04/30/2021
NMP-OS-028
2/14/2021
NMP-OS-028
1B Core Spray Inboard Injection Valve (1E21F005B) Bonnet
Leak
05/04/2021
NMP-OS-028
1A ASD Process Trouble and 1A ASD Trouble
2/03/2020
NMPS-OS-006-
2
Aggregate Operator Impact Review Instruction
3.0
OS-BP-001
Operations Performance Indicators
5.1