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
November 9, 2021
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, Signed by Dickson, Billy on 11/09/21 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: NPF-3 Report Number: 05000346/2021003 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 Enclosure
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 71153 Closed Davis-Besse, Unit 1,
Anticipatory Reactor Trip System Actuated During Turbine Stop Valve Testing due to the Closure of a Main Turbine Stop Valve.
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 Type Designation Description or Title Revision or
Procedure Date
71111.04 Procedures DB-OP-06012 Attachment 2: DH LOOP 2 Normal Lineup Valve Checklist 80
DB-OP-06225 Transferring the MDFP from the Main Feedwater Mode to the 26
Auxiliary Feedwater Mode Valve Lineup
DB-SS-03090 MDFP Flow Path Valve Checklist 11
71111.05 Fire Plans PFP-AB-105 Auxiliary Building 9
PFP-AB-113 Auxiliary Building 9
PFP-AB-314 Auxiliary Building 9
PFP-AB-319 Auxiliary Building 8
PFP-AB-601E No. 1 Main Steam Line Area, Room 601E, Fire Area DH 4
PFP-AB-602 No. 2 Main Steam Line Area, Room 602, Fire Area DH 5
71111.06 Procedures DB-OP-06013 Containment Spray Train 2 Valve Checklist 28
DB-OP-06233 Auxiliary Feedwater System Train 1 Lineup Valve Checklist 45
DB-OP-06316 EDG 2 Switch and Breaker Checklist 66
71111.12 Corrective Action 2020-02223 IR21: Failed Mechanical Interlock on BE1183 03/14/2020
Documents 2020-08295 BF1182 Mechanical Interlock Found with Broken Piece and 10/26/2020
Mounting Screw Stripped
20-08328 BF1183 Forward/Reverse Contactor Mechanical Interlock 10/27/2020
Found Degraded
20-08416 CV5076 Sticking Mechanical Interlock 10/29/2020
21-01311 HIC DH14B Demand Signal Continued to Display 20 Percent 02/26/2021
Open While Set to 0 Percent Open
21-06239 DH14B Failed Closed 08/18/2021
21-06676 Mechanical Interlock Failure 09/02/2021
Drawings FSK-M-GCB-3-1 Decay Heat Pump Recirculation Piping 3
ISI-SK-050 Decay Heat Coolers 1-1 and 1-2 Outline and Supports 2
ISID2-033C Decay Heat Train 2 14
ISIM2-233F Low Pressure Injection System 8
ISIM2-234D Containment Spray System and Spent Fuel Pool Cooling 1
System
Engineering 60129065B Engineering Evaluation Request 10/26/2020
Changes
Inspection Type Designation Description or Title Revision or
Procedure Date
Procedures DB-SP-03446 Decay Heat Train 1 Pump and Valve Test 10
Work Orders 200694387 PM 11998 BF1183 Test 11/05/2020
200696633 MV2002B Inspect RPS/SFAS#3 08/31/2021
200790236 PM 12098 BF1181 Test 10/29/2020
71111.15 Corrective Action 2019-10673 SW Pump 3 Abnormal Noise 12/30/2019
Documents 2020-01303 DH2734 Declutched and Manually Seated 02/19/2020
20-02223 1R21: Failed Mechanical Interlock on BE1183 03/14/2020
20-02817 IST Trending: Adverse Step Change Closed Stroke Time on 03/31/2020
DH13A
20-04130 Service Water Pump 2 Packing Leak Off Excessive 05/09/2020
20-08295 BF1182 Mechanical Interlock Found with Broken Piece and 10/26/2020
Mounting Screw Stripped
20-08328 BF1183 Forward/Reverse Contactor Mechanical Interlock 10/27/2020
Found Degraded
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 02/26/2021
Open While Set to 0 Percent Open
21-03540 Makeup Pump Room A/C Unit Found Tripped Off 05/01/2021
21-03710 System Monitoring - Makeup Pump Motor 1 Pump 05/06/2021
End Bearing Oil Temperature, T747, Erratic Indication
21-04524 Cycle 22 1/8th Core Location H14 Max Segment Peaking 06/08/2021
Deviation Approaching BMAC Limit
21-05586 Wet Wash Building Wall Settled and Put Stress on Piping 07/22/2021
and Conduit for Makeup Pump Room Air Conditioner
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 07/24/2021
Packing Gland Leak Off
21-05658 Entry into Abnormal Procedure for Loss of Service Water 07/26/2021
Secondaries
21-06239 DH14B Failed Closed 08/18/2021
21-06676 Mechanical Interlock Failure 09/02/2021
Inspection Type Designation Description or Title Revision or
Procedure Date
Corrective Action 2021-06146 2021 NRC SIT: Switch DST for MUP Time Delay 08/13/2021
Documents Relay 2Y1 Isolation Potentially Exposed to Similar
Resulting from Degradation Mechanisms as EDG FFSS
Inspection
Drawings FSK-M-GCB-3-1 Decay Heat Pump Recirculation Piping 3
ISI-SK-050 Decay Heat Coolers 1-1 and 1-2 Outline and Supports 2
ISIM2-233F Low Pressure Injection System 8
ISIM2-234D Containment Spray System and Spent Fuel Pool Cooling 1
System
Engineering 60129065B Engineering Evaluation Request 10/26/2020
Changes
Miscellaneous 601264224 Davis-Besse Nuclear Power Tip Maintenance Notification 03/14/2020
Letter from
- M. Core Operating Limits Report, Cycle 21 3
Bezilla L-20-063
Procedures DB-SP-03446 Decay Heat Train 1 Pump and Valve Test 10
DB-SP-03446 Decay Heat Train 1 Pump and Valve Test 10
Work Orders 200694387 PM 11998 BF1183 Test 11/05/2020
200696633 MV2002B Inspect RPS/SFAS#3 08/31/2021
200790236 PM 12098 BF1181 Test 10/29/2020
71111.19 Corrective Action 2017-10465 Recent Hope Creek EDG OD: Failure of New Dynalco 11/15/2017
Documents Speed Switch
2017-10873 10 CFR Part 21 Notice from Engine Systems Inc. for 10/30/2017
EDG Speed Switch
2019-05707 C30205 SBODG Ground Meter Low mAMPs 07/03/2019
20-01303 DH2734 Declutched and Manually Seated 02/19/2020
20-02817 IST Trending: Adverse Step Change Closed Stroke Time on 03/31/2020
DH13A
21-01311 HIC DH14B Demand Signal Continued to Display 20 Percent 02/26/2021
Open While Set to 0 Percent Open
21-06239 DH14B Failed Closed 08/18/2021
Drawings FSK-M-GCB-3-1 Decay Heat Pump Recirculation Piping 3
ISI-SK-050 Decay Heat Coolers 1-1 and 1-2 Outline and Supports 2
ISID2-033C Decay Heat Train 2 14
Inspection Type Designation Description or Title Revision or
Procedure Date
ISIM2-233F Low Pressure Injection System 8
ISIM2-234D Containment Spray System and Spent Fuel Pool Cooling 1
System
Miscellaneous 10CFR21-0118 10CFR21 Reporting of Defects and Non-Compliance 0
24A-ISS6221 String/System Work Package 10
LER-2021-001 Emergency Diesel Generator Speed Switch Failure due to 0
Direct Current System Ground
Procedures DB-MI-04226 String Check of 24A-ISS6221/24A-ISS6221A 3
Diesel Generator 1-1 Speed Transmitters
DB-SP-03446 Decay Heat Train 1 Pump and Valve Test 10
DB-SP-03446 Decay Heat Train 1 Pump and Valve Test 10
Work Orders 200798736 AFP 1 Quarterly Test 08/11/2021
200801345 AFP 2 Quarterly Test 09/20/2021
200859701 EDG 1 Speed Switch Should be Replaced 08/12/2021
71111.22 Corrective Action 2020-01303 DH2734 Declutched and Manually Seated 02/19/2020
Documents 2020-02817 IST Trending: Adverse Step Change Closed Stroke Time on 03/31/2020
DH13A
21-01311 HIC DH14B Demand Signal Continued to Display 20 Percent 02/26/2021
Open While Set to 0 Percent Open
21-06239 DH14B Failed Closed 08/18/2021
Drawings FSK-M-GCB-3-1 Decay Heat Pump Recirculation Piping 3
ISI-SK-050 Decay Heat Coolers 1-1 and 1-2 Outline and Supports 2
ISID2-033C Decay Heat Train 2 14
ISIM2-233F Low Pressure Injection System 8
ISIM2-234D Containment Spray System and Spent Fuel Pool Cooling 1
System
Procedures DB-SC-03070 Emergency Diesel Generator 1 Monthly Test 43
DB-SP-03446 Decay Heat Train 1 Pump and Valve Test 10
DB-SP-03446 Decay Heat Train 1 Pump and Valve Test 10
DB-SS-04201 Emergency Feedwater Pump Quarterly Test 8
Work Orders 200798736 AFP 1 Quarterly Test 08/11/2021
200799536 EDG 1 Monthly Test 08/12/2021
200800408 EDG 2 Monthly Test 09/01/2021
Inspection Type Designation Description or Title Revision or
Procedure Date
71124.07 Corrective Action CR-2019-01163 REMP Air Monitor Failure Trend 12/10/2019
Documents
Corrective Action CR-2021-05395 NRC Identified: Vegetation Growth Around Radiological 07/15/2021
Documents Environmental Monitoring Program Air Sampling Stations
Resulting from CR-2021-05419 NRC Identified: DB-HP-01702: Procedure Confusion on 07/15/2021
Inspection Environmental Air Sampler Calibration
Miscellaneous 2020 Annual Radiological Environmental Operating Report 05/01/2021
Including the Radiological Effluent Release Report
Offsite Dose Calculation Manual 38
Procedures DB-CN-03005 Radiological Monitoring Weekly, Semi-Monthly, and Monthly 14
Sampling
DB-HP-01452 Air Sampler Calibration 08
DB-HP-01466 AVS-28A Constant Flow Air Sampler Calibration 02
DBPM-CHEM- Groundwater Monitoring Program 01
0004
NOP-OP-2012 Groundwater Monitoring 13
Self-Assessments NUPIC Audit Supplier Audit Report for ATI Environmental, Inc. 02/18/2020
Number:24879 Northbrook, IL
Work Orders 200788171 Meteorological Monitoring System Primary Channel 05/12/2021
Calibration
71152 Calculations C-CSS-099.20- Shield Building Evaluation of Interim Condition with Partial 0
076 and Limited Concrete Removal
Corrective Action 2021-06142 Shield Building Shoulder 3 Work Scope 08/13/2021
Documents
Corrective Action 2021-06134 2021 NRC SIT: Incorrect AP-913 Classification for C3621 08/13/2021
Documents
Resulting from
Inspection
Engineering 18-0037-006 Shield Building Shoulder 3 Removal 2
Changes
Engineering Notification Shield Building Evaluation Study for Knuckle Boom Crane 0
Evaluations 601275302 Loading Operation
Notification Shield Building Shoulder 3: Evaluate and Provide Details for 08/17/2021
601327705 Temporary Modification of Platform and Installation of
Inspection Type Designation Description or Title Revision or
Procedure Date
Scaffold Bearing on Second Platform
Miscellaneous 10 CFR 50.59 ECP 18-0037 3
Screen 18-00648
16