IR 05000346/2021003
| ML21313A272 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/10/2021 |
| From: | Billy Dickson NRC/RGN-III/DRP/B2 |
| To: | Tony Brown Energy Harbor Nuclear Corp |
| References | |
| IR 2021003 | |
| Download: ML21313A272 (18) | |
Text
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION - INTEGRATED INSPECTION REPORT 05000346/2021003
Dear Mr. Brown:
On September 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Davis-Besse Nuclear Power Station. On October 26, 2021, 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, Billy C. Dickson, Jr., Chief Branch 2 Division of Reactor Projects Docket No. 05000346 License No. NPF-3
Enclosure:
As stated
Inspection Report
Docket Number:
05000346
License Number:
Report Number:
Enterprise Identifier:
I-2021-003-0072
Licensee:
Energy Harbor Nuclear Corp.
Facility:
Davis-Besse Nuclear Power Station
Location:
Oak Harbor, OH
Inspection Dates:
July 01, 2021 to September 30, 2021
Inspectors:
R. Cassara, Resident Inspector
J. Cassidy, Senior Health Physicist
D. Mills, Senior Resident Inspector
J. Nance, Operations Engineer
J. Neurauter, Senior Reactor Inspector
R. Rolph, Senior Resident Inspector
Approved By:
Billy C. Dickson, Jr., Chief
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 Davis-Besse Nuclear Power Station, 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 05000346/2019-003-00 LER 2019-003-00 for Davis-Besse, Unit 1,
Anticipatory Reactor Trip System Actuated During Turbine Stop Valve Testing due to the Closure of a Main Turbine Stop Valve.
71153 Closed
PLANT STATUS
Unit 1 began the inspection period at full power. On July 8, 2021, the unit tripped from 100 percent power due to a failure of the generator exciter power supply that caused a turbine trip.
The unit was returned to full power on July 12, 2021 and remained at or near full power 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 seasonal warm temperatures and heavy rains for plant systems including the emergency diesel generators, component cooling water system, and service water system.
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) Emergency diesel generator train 2 during the week ending September 11, 2021
- (2) Containment spray train 2 during the week ending September 11, 2021
- (3) Motor driven feedwater while auxiliary feedwater train 2 inoperable for scheduled maintenance and broken governor linkage replacement during the week ending September 25, 2021
- (4) Auxiliary feedwater train 1 while auxiliary feedwater train 2 inoperable for scheduled maintenance and broken governor linkage replacement during the week ending September 25, 2021
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) Decay heat/low pressure injection full system walkdown during the week ending September 4, 2021
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) Main steam line rooms 1 and 2, fire area DH, during the week ending July 17, 2021
- (2) Auxiliary feed pump 1 room, fire area F, during the week ending July 26, 2021
- (3) Emergency core cooling system 2 room and decay heat coolers room, fire area AB-01, during the week ending August 28, 2021
- (4) Diesel Generator 1-2 room, fire area J, during the week ending September 11, 2021
- (5) Mechanical penetration room 4, fire area A, during the week ending September 11, 2021
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Emergency core cooling system room 2 and mechanical penetration room 4
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 service water pump 3 testing and shutdown following pump replacement
- (2) The inspectors observed and evaluated licensed operator performance in the control room during shutdown operations and restart following the reactor trip on July 8, 2021
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) Observation of operator performance during simulator training for drill and exercise performance during the week ending September 11, 2021
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 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) Repair of atmospheric vent valve 2 during the week ending July 10, 2021
- (2) Decay heat/low pressure injection cooler 1 outlet valve failed closed during the week ending August 21, 2021
- (3) Motor-operated valve interlock switch replacements CV2002 during the week ending September 30, 2021
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
- (1) Emergency diesel generator 1 voltage regulator reference adjuster replacement during the week ending August 7, 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) Train 2 emergency core cooling systems CR-2021-05793 during the week ending July 31, 2021
- (2) Decay heat train 1 due to failed DH14B CR 2021-06239 during the week ending August 21, 2021
- (3) DH14B failed closed CR 202-06239 during the week ending August 21, 2021
- (4) Motor-operated valve interlock switch replacements CV2002 during the week ending September 4, 2021
- (5) CV-2002B motor-operated valve failed to cycle during maintenance during the week ending September 4, 2021
- (6) Auxiliary feedwater pump turbine governor linkage broken during maintenance, CR 2021-07124, during the week ending September 25, 2021
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Auxiliary feedwater pump 1 following planned maintenance during the week ending August 14, 2021
- (2) Emergency diesel generator 1 following planned replacement of speed switch ST6221 during the week ending August 21, 2021
- (3) Decay heat/low pressure injection pump quarterly test following DH14B repair during the week ending August 21, 2021
- (4) Emergency diesel generator train 1 following speed switch replacement during the week ending August 7, 2021
- (5) Auxiliary feedwater train 2 following scheduled maintenance and broken governor linkage replacement during the week ending September 25, 2021
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated activities related to plant trip on July 8, 2021
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Reactor protection system manual reactor trip during the week ending July 10, 2021
- (2) Auxiliary feedwater pump 1 quarterly surveillance run during the week ending August 14, 2021
- (3) Emergency diesel generator 2 monthly test during the week ending September 4, 2021
Inservice Testing (IP Section 03.01) (2 Samples)
- (1) Decay heat/low pressure injection pump 1 quarterly test reperformed on August 19, 2021
- (2) Emergency diesel generator 1 monthly test during the week ending August 21, 2021
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) Emergency feedwater pump quarterly run during the week ending September 4, 2021
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Integrated drill on August 24,
RADIATION SAFETY
71124.07 - Radiological Environmental Monitoring Program
Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.
Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.
GPI Implementation (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative program to identify incomplete or discontinued program elements.
OTHER ACTIVITIES - BASELINE
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Shield building core bore inspections including the expansion of shoulder 3 work scope due to increased crack size
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 2019-003 "Anticipatory Reactor Trip System Actuated Unexpectedly During Turbine Stop Valve Testing due to the Closure of a Main Turbine Stop Valve" (ADAMS Accession No. ML19312A071), (also see EN 54263). During scheduled quarterly turbine valve testing on September 7, 2019, the plant tripped from 95 percent power due to spurious closure of main stop valve Number 4 during main stop valve Number 2 testing. Following the trip maintenance and component replacements were performed to address licensee identified electrohydraulic control system failure modes. On February 28, 2021, during scheduled main stop valve testing, the same issue was noted but did not result in a reactor trip. Following this the licensee began testing the stop valves at 40 percent power (below the ARTS trip setpoint). Subsequently the licensee identified a 1997 General Electric Technical Information Letter that suggested installation of restricting orifices in the EHC system.
Following the reactor trip on July 8, 2021, the licensee installed the restricting orifices and successfully tested the main stop valves at 95 percent power. The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements. This LER is closed.
INSPECTION RESULTS
Observation: Expansion of Shoulder 3 Work Scope Due to Increased Crack Size 71152 As indicated in Condition Report (CR) 2021-06142: During ECP 18-0037-006 preparation, the exact extent of the Shield Building shoulder repair in the upper region was not able to be obtained. The inability to obtain the exact extent of repair for this region was due to the station vent platforms/ladders interfering with performing Impulse Response. During the demolition of the upper region, the licensee observed that the laminar crack extended beyond the initial demo limits. The licensee performed subsequent Impulse Response and identified that the demo limits would need to be expanded to completely encapsulate the laminar crack.
The inspectors reviewed the licensee's documentation affected by expanding Shoulder 3 demolition limits. Specifically, the inspector reviewed CR 2021-06142 for issues the licensee needed to resolve related to expanded Shoulder 3 repair, the associated EC 18-0037-006 including 50.59 Screen 18-00648, and related engineering calculations and evaluations:
Calculation C-CSS-099.20-076 that demonstrated shield building structural integrity during the interim concrete demolition condition,
Evaluation EER 601327705 that evaluated and provided details for the temporary modification of the platform brace and installation of scaffold bearing on the second platform, and Evaluation EER 601275302 that evaluated the structural adequacy of the shield building dome and shell with additional loads from the knuckle boom crane during the concrete repair.
The inspectors verified that the licensee had calculations/evaluations that supported expanding Shoulder 3 repair limits, including modifying existing supporting structures.
No findings of significance were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On October 26, 2021, the inspectors presented the integrated inspection results to Mr. T. Brown, Site Vice President, and other members of the licensee staff.
On July 16, 2021, the inspectors presented the radiation protection inspection results to Mr. T. Brown, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DB-OP-06012
2: DH LOOP 2 Normal Lineup Valve Checklist
DB-OP-06225
Transferring the MDFP from the Main Feedwater Mode to the
Auxiliary Feedwater Mode Valve Lineup
Procedures
DB-SS-03090
MDFP Flow Path Valve Checklist
Auxiliary Building
Auxiliary Building
Auxiliary Building
Auxiliary Building
No. 1 Main Steam Line Area, Room 601E, Fire Area DH
Fire Plans
No. 2 Main Steam Line Area, Room 602, Fire Area DH
DB-OP-06013
Containment Spray Train 2 Valve Checklist
DB-OP-06233
Auxiliary Feedwater System Train 1 Lineup Valve Checklist
Procedures
DB-OP-06316
EDG 2 Switch and Breaker Checklist
20-02223
IR21: Failed Mechanical Interlock on BE1183
03/14/2020
20-08295
BF1182 Mechanical Interlock Found with Broken Piece and
Mounting Screw Stripped
10/26/2020
20-08328
BF1183 Forward/Reverse Contactor Mechanical Interlock
Found Degraded
10/27/2020
20-08416
CV5076 Sticking Mechanical Interlock
10/29/2020
21-01311
HIC DH14B Demand Signal Continued to Display 20 Percent
Open While Set to 0 Percent Open
2/26/2021
21-06239
DH14B Failed Closed
08/18/2021
Corrective Action
Documents
21-06676
Mechanical Interlock Failure
09/02/2021
FSK-M-GCB-3-1
Decay Heat Pump Recirculation Piping
ISI-SK-050
Decay Heat Coolers 1-1 and 1-2 Outline and Supports
ISID2-033C
Decay Heat Train 2
ISIM2-233F
Low Pressure Injection System
Drawings
ISIM2-234D
Containment Spray System and Spent Fuel Pool Cooling
System
Engineering
Changes
60129065B
Engineering Evaluation Request
10/26/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
DB-SP-03446
Decay Heat Train 1 Pump and Valve Test
200694387
PM 11998 BF1183 Test
11/05/2020
200696633
MV2002B Inspect RPS/SFAS#3
08/31/2021
Work Orders
200790236
PM 12098 BF1181 Test
10/29/2020
2019-10673
SW Pump 3 Abnormal Noise
2/30/2019
20-01303
DH2734 Declutched and Manually Seated
2/19/2020
20-02223
1R21: Failed Mechanical Interlock on BE1183
03/14/2020
20-02817
IST Trending: Adverse Step Change Closed Stroke Time on
DH13A
03/31/2020
20-04130
Service Water Pump 2 Packing Leak Off Excessive
05/09/2020
20-08295
BF1182 Mechanical Interlock Found with Broken Piece and
Mounting Screw Stripped
10/26/2020
20-08328
BF1183 Forward/Reverse Contactor Mechanical Interlock
Found Degraded
10/27/2020
20-08416
CV5076 Sticking Mechanical Interlock
10/29/2020
21-00465
MUP 1 O/B Temperature Element Failed
01/26/2021
21-01311
HIC DH14B Demand Signal Continued to Display 20 Percent
Open While Set to 0 Percent Open
2/26/2021
21-03540
Makeup Pump Room A/C Unit Found Tripped Off
05/01/2021
21-03710
System Monitoring - Makeup Pump Motor 1 Pump
End Bearing Oil Temperature, T747, Erratic Indication
05/06/2021
21-04524
Cycle 22 1/8th Core Location H14 Max Segment Peaking
Deviation Approaching BMAC Limit
06/08/2021
21-05586
Wet Wash Building Wall Settled and Put Stress on Piping
and Conduit for Makeup Pump Room Air Conditioner
07/22/2021
21-05609
MUP Room Temperature Exceeds 115 Degrees Fahrenheit
07/23/2021
21-05626
Makeup Pump 1 Speed Increaser Oil Level Low
07/23/2021
21-05633
SW Pump 3 Full Flow Testing Stopped due to Loss of Pump
Packing Gland Leak Off
07/24/2021
21-05658
Entry into Abnormal Procedure for Loss of Service Water
Secondaries
07/26/2021
21-06239
DH14B Failed Closed
08/18/2021
Corrective Action
Documents
21-06676
Mechanical Interlock Failure
09/02/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
21-06146
21 NRC SIT: Switch DST for MUP Time Delay
Relay 2Y1 Isolation Potentially Exposed to Similar
Degradation Mechanisms as EDG FFSS
08/13/2021
FSK-M-GCB-3-1
Decay Heat Pump Recirculation Piping
ISI-SK-050
Decay Heat Coolers 1-1 and 1-2 Outline and Supports
ISIM2-233F
Low Pressure Injection System
Drawings
ISIM2-234D
Containment Spray System and Spent Fuel Pool Cooling
System
Engineering
Changes
60129065B
Engineering Evaluation Request
10/26/2020
601264224
Davis-Besse Nuclear Power Tip Maintenance Notification
03/14/2020
Miscellaneous
Letter from M.
Bezilla L-20-063
Core Operating Limits Report, Cycle 21
DB-SP-03446
Decay Heat Train 1 Pump and Valve Test
Procedures
DB-SP-03446
Decay Heat Train 1 Pump and Valve Test
200694387
PM 11998 BF1183 Test
11/05/2020
200696633
MV2002B Inspect RPS/SFAS#3
08/31/2021
Work Orders
200790236
PM 12098 BF1181 Test
10/29/2020
2017-10465
Recent Hope Creek EDG OD: Failure of New Dynalco
Speed Switch
11/15/2017
2017-10873
CFR Part 21 Notice from Engine Systems Inc. for
EDG Speed Switch
10/30/2017
2019-05707
C30205 SBODG Ground Meter Low mAMPs
07/03/2019
20-01303
DH2734 Declutched and Manually Seated
2/19/2020
20-02817
IST Trending: Adverse Step Change Closed Stroke Time on
DH13A
03/31/2020
21-01311
HIC DH14B Demand Signal Continued to Display 20 Percent
Open While Set to 0 Percent Open
2/26/2021
Corrective Action
Documents
21-06239
DH14B Failed Closed
08/18/2021
FSK-M-GCB-3-1
Decay Heat Pump Recirculation Piping
ISI-SK-050
Decay Heat Coolers 1-1 and 1-2 Outline and Supports
Drawings
ISID2-033C
Decay Heat Train 2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ISIM2-233F
Low Pressure Injection System
ISIM2-234D
Containment Spray System and Spent Fuel Pool Cooling
System
10CFR21 Reporting of Defects and Non-Compliance
String/System Work Package
Miscellaneous
LER-2021-001
Emergency Diesel Generator Speed Switch Failure due to
Direct Current System Ground
DB-MI-04226
String Check of 24A-ISS6221/24A-ISS6221A
Diesel Generator 1-1 Speed Transmitters
DB-SP-03446
Decay Heat Train 1 Pump and Valve Test
Procedures
DB-SP-03446
Decay Heat Train 1 Pump and Valve Test
200798736
AFP 1 Quarterly Test
08/11/2021
200801345
AFP 2 Quarterly Test
09/20/2021
Work Orders
200859701
EDG 1 Speed Switch Should be Replaced
08/12/2021
20-01303
DH2734 Declutched and Manually Seated
2/19/2020
20-02817
IST Trending: Adverse Step Change Closed Stroke Time on
DH13A
03/31/2020
21-01311
HIC DH14B Demand Signal Continued to Display 20 Percent
Open While Set to 0 Percent Open
2/26/2021
Corrective Action
Documents
21-06239
DH14B Failed Closed
08/18/2021
FSK-M-GCB-3-1
Decay Heat Pump Recirculation Piping
ISI-SK-050
Decay Heat Coolers 1-1 and 1-2 Outline and Supports
ISID2-033C
Decay Heat Train 2
ISIM2-233F
Low Pressure Injection System
Drawings
ISIM2-234D
Containment Spray System and Spent Fuel Pool Cooling
System
DB-SC-03070
Emergency Diesel Generator 1 Monthly Test
DB-SP-03446
Decay Heat Train 1 Pump and Valve Test
DB-SP-03446
Decay Heat Train 1 Pump and Valve Test
Procedures
DB-SS-04201
Emergency Feedwater Pump Quarterly Test
200798736
AFP 1 Quarterly Test
08/11/2021
200799536
EDG 1 Monthly Test
08/12/2021
Work Orders
200800408
EDG 2 Monthly Test
09/01/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-2019-01163
REMP Air Monitor Failure Trend
2/10/2019
CR-2021-05395
NRC Identified: Vegetation Growth Around Radiological
Environmental Monitoring Program Air Sampling Stations
07/15/2021
Corrective Action
Documents
Resulting from
Inspection
CR-2021-05419
NRC Identified: DB-HP-01702: Procedure Confusion on
Environmental Air Sampler Calibration
07/15/2021
20 Annual Radiological Environmental Operating Report
Including the Radiological Effluent Release Report
05/01/2021
Miscellaneous
Offsite Dose Calculation Manual
DB-CN-03005
Radiological Monitoring Weekly, Semi-Monthly, and Monthly
Sampling
DB-HP-01452
Air Sampler Calibration
DB-HP-01466
AVS-28A Constant Flow Air Sampler Calibration
DBPM-CHEM-
0004
Groundwater Monitoring Program
Procedures
NOP-OP-2012
Groundwater Monitoring
Self-Assessments
NUPIC Audit
Number:24879
Supplier Audit Report for ATI Environmental, Inc.
Northbrook, IL
2/18/2020
Work Orders
200788171
Meteorological Monitoring System Primary Channel
Calibration
05/12/2021
Calculations
C-CSS-099.20-
076
Shield Building Evaluation of Interim Condition with Partial
and Limited Concrete Removal
Corrective Action
Documents
21-06142
Shield Building Shoulder 3 Work Scope
08/13/2021
Corrective Action
Documents
Resulting from
Inspection
21-06134
21 NRC SIT: Incorrect AP-913 Classification for C3621
08/13/2021
Engineering
Changes
18-0037-006
Shield Building Shoulder 3 Removal
Notification
601275302
Shield Building Evaluation Study for Knuckle Boom Crane
Loading Operation
Engineering
Evaluations
Notification
601327705
Shield Building Shoulder 3: Evaluate and Provide Details for
Temporary Modification of Platform and Installation of
08/17/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Scaffold Bearing on Second Platform
Miscellaneous
CFR 50.59
Screen 18-00648
ECP 18-0037
3