IR 05000334/2019004
| ML20044D313 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/12/2020 |
| From: | Patrick Finney NRC/RGN-I/DRP/PB5 |
| To: | Penfield R FirstEnergy Nuclear Operating Co |
| Finney P | |
| References | |
| IR 2019004 | |
| Download: ML20044D313 (17) | |
Text
February 12, 2020
SUBJECT:
BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000334/2019004 AND 05000412/2019004
Dear Mr. Penfield:
On December 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Beaver Valley Power Station, Units 1 and 2. On January 16, 2020, 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,
/RA/
Patrick W. Finney, Acting Chief Reactor Projects Branch 5 Division of Reactor Projects
Docket Nos. 05000334 and 05000412 License Nos. DPR-66 and NPF-73
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000334 and 05000412
License Numbers:
Report Numbers:
05000334/2019004 and 05000412/2019004
Enterprise Identifier: I-2019-004-0040
Licensee:
FirstEnergy Nuclear Operating Company
Facility:
Beaver Valley Power Station, Units 1 and 2
Location:
Shippingport, PA
Inspection Dates:
October 1, 2019 to December 31, 2019
Inspectors:
J. Krafty, Senior Resident Inspector
S. Horvitz, Resident Inspector
E. Burket, Senior Reactor Inspector
B. Lin, Nuclear Systems Engineer
R. Rolph, Senior Health Physicist
Approved By:
Patrick W. Finney, Acting 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 Beaver Valley Power Station, Units 1 and 2, 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 in end-of-cycle coastdown operations. On October 13, 2019, Unit 1 was shutdown for a planned refueling outage (1R26). On November 3, 2019, operators commenced a reactor startup. On November 4, 2019, Unit 1 was manually tripped at 15 percent power due to steam pressure oscillations caused by erratic condenser steam dump operation. On November 5, 2019, operators commenced a reactor startup. Unit 1 reached rated thermal power on November 10, 2019 and remained at or near full power for the remainder of the inspection period.
Unit 2 operated at or near rated thermal power for the entire 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 plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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 03.02) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures.
71111.04Q - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walk downs of the following systems/trains:
- (1) Unit 1 reactor plant river water system realigned in a backflow configuration with the B header supplying the A return header on October 21, 2019
- (2) Unit 2 emergency diesel generator 2-2 following surveillance testing on November 20, 2019
- (3) Unit 2 turbine driven auxiliary feedwater pump following surveillance testing on November 25, 2019
71111.04S - Equipment Alignment
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) Unit 1 residual heat removal system on October 20, 2019
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (4 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Unit 1 and 2 hydrogen tanks, fire compartments 1-H-1 and 2-H-1, on October 2, 2019
- (2) Unit 1 and 2 general yard area, fire compartment 3-YARD-1, on October 4, 2019
- (3) Unit 1 reactor containment building, fire compartment 1-RC-1, on October 15, 2019
- (4) Unit 1 and 2 alternate access facility, fire compartment 3-AAF-1, on November 11, 2019
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from October 21, 2019 to October 30, 2019:
03.01.a - Nondestructive Examination and Welding Activities.
- Radiography testing (RT) of 4 field weld SDHV4F1 for replacement of residual heat release valve HCV-1MS-104.
- Ultrasonic testing (UT) of structural weld overlay, RC-72-7-OV-01.
- Visual examination (VE) of reactor vessel lower head bottom mounted-instrument nozzles for ASME Code case N-722.
- Repair activity associated with fretting indications on A and B pressurizer spray lines, RC-71, RC-72 (WO# 200803108, 200803109).
03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.
- Bare metal visual examination of Unit 1 reactor vessel head penetrations 7, 41, and 49 for ASME Code Case N-729-4.
03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
- Evaluation performed for 2018-02950, High Head Safety Injection Leakage Monitoring Connection, 1SI-347
- Evaluation performed for 2018-03516, Safety Injection Accumulator, 1SI-43 03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.
- None performed
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 Unit 1 operator performance in the control room during reactor shutdown for refueling outage 1R26 on October 12, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a crew of licensed operators in the Unit 1 simulator during licensed operator training conducted in preparation for upcoming plant evolutions on October 10, 2019.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Unit 2 compressed air system on November 25, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Unit 1 yellow shutdown risk for decay heat removal while reactor coolant system was depressurized and drained to the reactor vessel flange on October 17, 2019
- (2) Unit 1 yellow shutdown risk for decay heat removal and spent fuel pool cooling during core offload with only one train of residual heat removal and spent fuel pool cooling available on October 21, 2019
- (3) Unit 1 yellow shutdown risk for decay heat removal while reactor coolant system level is lowered to below the reactor vessel flange on October 28, 2019
- (4) Unit 1 elevated risk due to B river water pump planned maintenance and 1-2 emergency diesel generator testing on November 13, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (5 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Unit 1 source range channels (N31/N32) reading below expected values following the
1R26 shutdown on October 14, 2019 (2)
Unit 1 B low head safety injection pump suction valve, MOV-1SI-862B total thrust limit exceeded on October 17, 2019
- (3) Unit 1 Battery 1-3 cell 12, 29, and 55 discoloration on October 22, 2019
- (4) Unit 1 active boric acid leak on quench spray pump discharge check valve on October 31, 2019
- (5) Unit 2 service water valve, 2SWS-100, stuck open, diverting service water cooling from control room air conditioning unit, 2HVC-ACU201B, on November 26, 2019
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated post maintenance testing for the following maintenance/repair activities:
- (1) Unit 1 direct current panel 1-6 replacement on October 23, 2019
- (2) Unit 1 emergency diesel generator 1-1 scheduled maintenance on October 23, 2019
- (3) Unit 1 residual heat release valve replacement on October 29, 2019
- (4) Unit 1 battery 1-3 replacement of five cells on October 31, 2019
- (5) Unit 1 replacement of MOV-1SI-867A/B motor operator with a manual operator on October 31, 2019
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated Unit 1 refueling outage (1R26) activities from October 13, 2019 through November 8, 2019.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
(1)1OST-13.1, Quench Spray Pump [1QS-P-1A] Test on October 2, 2019 (2)1OST-11.14A, Low Head Safety Injection Full Flow Test on October 18, 2019 (3)1OST-36.4, Diesel Generator No. 2 Automatic Test and 1MSP-36.00B-E, Load Shedding and Auto Sequencing of B Train Emergency Bus Breaker Cubicles on October 25, 2019
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
(1)1OST-21.5, Main Steam Trip Valve (TV-1MS-101B and 101C) Full Closure Test on October 15,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Contamination and Radioactive Material Control (IP Section 02.03) (1 Sample)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
- (1) The inspectors verified the following sealed sources are accounted for and are intact:
- Shepard Calibrators in the Unit 1 and 2 instrument rooms
High Radiation Area and Very High Radiation Area Controls (IP Section 02.05) (1 Sample)
- (1) The inspectors evaluated risk-significant high radiation area and very high radiation area controls.
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 02.06) (1 Sample)
- (1) The inspectors evaluated radiation worker performance and radiation protection technician proficiency.
71124.02 - Occupational ALARA Planning and Controls
Radiological Work Planning (IP Section 02.01) (1 Sample)
The inspectors evaluated the licensees radiological work planning.
- (1) The inspectors reviewed the following activities:
- Radiography in the Steam Valve area
- Reactor Disassembly/Reassembly
- Scaffold work in the Reactor Building Containment
Implementation of ALARA and Radiological Work Controls (IP Section 02.03) (1 Sample)
The inspectors reviewed as low as reasonably achievable practices and radiological work controls.
- (1) The inspectors reviewed the following activities:
- 119-4018, Reactor Disassembly/Reassembly
- 119-4019, Remove/Replace CETNAs and Thermocouples
- 119-4023, ISI Support
- 119-4028, Scaffold/Emergent Work in the Reactor Building Containment
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 02.10)===
- (1) Unit 1 (October 1, 2018 through September 30, 2019)
- (2) Unit 2 (October 1, 2018 through September 30, 2019)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1 (October 1, 2018 through September 30, 2019)
- (2) Unit 2 (October 1, 2018 through September 30, 2019)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) Unit 1 and Unit 2 (September 1, 2018 through August 31, 2019)
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 16, 2020, the inspectors presented the integrated inspection results to Rod Penfield and other members of the licensee staff.
- On October 30, 2019, the inspectors presented the Inservice Inspection Activities Inspection results to Rod Penfield and other members of the licensee staff.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT, AND ABNORMAL
Impact of Financial Conditions on Continued Safe Performance
In that the licensee's parent company, FirstEnergy Solutions, was under bankruptcy protection/reorganization during the inspection period, NRC Region I conducted reviews of processes at Beaver Valley. Using the flexibilities in the baseline inspection program, the inspectors evaluated several aspects of FENOCs operations to assess whether any identified plant performance issues could be related to the station's financial condition. The factors reviewed included:
- (1) impact on regulatory required plant staffing,
- (2) corrective maintenance backlog,
- (3) changes to the planned maintenance schedule,
- (4) corrective action program implementation, and
- (5) reduction in outage scope, including risk-significant modifications.
In particular, the inspectors assessed whether FENOC personnel continued to identify problems at an appropriate threshold and enter these problems into the corrective action program for resolution. The inspectors also assessed whether FENOC continued to develop and implement corrective actions commensurate with the safety significance of the problems identified.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
2019-07771
2019-07787
2019-07788
2019-07789
2019-07850
2019-07907
Procedures
1OM-45.3.C.2
Power Supply and Control Switch List Heat Tracing System
Revision 24
1OST-45.11A
Cold Weather Protection Verification - Performed in
September and October
Revision 5
2OM-45D.3.C
Power Supply and Control Switch List,
Revision 13
2OST-45.11A
Cold Weather Protection Verification - Performed in
September and October
Revision 8
Drawings
RM-0424-003
Valve Oper No Diagram Auxiliary Feedwater
Revision 20
RM-0430-001
Piping & Instrumentation Diagram - River Water System
Revision 37
RM-0430-002
Piping & Instrumentation Diagram - River Water System
Revision 23
RM-0430-003
Piping & Instrumentation Diagram - River Water System
Revision 33
RM-0436-001
Valve Oper No Diagram - Diesel Fuel Oil
Revision 8
RM-0436-003
Valve Oper No Diagram - Diesel Starting Air
Revision 25
RM-0436-004B
Valve Oper No Diagram - Diesel Cooling Water
Revision 12
RM-421-2
Valve Oper No Diagram AFW Pump Steam & Resid Heat
Rel
Revision 17
Miscellaneous
Clearance 1R26-30-OPS-005
10/20/2019
Procedures
Operation of the Reactor Plant River Water System with
Normal Return Flow Path to Unit 1/2 Blowdown Isolated
Revision 14
2OST-24.4
Steam Driven Auxiliary Feed Pump [2FWE*P22] Quarterly
Test
Revision 91
Drawings
RM-0410-001
Piping & Instrumentation Diagram Residual Heat Removal
System
Revision 16
Procedures
1OM-10.3.B.1
Valve List - 1RH
Revision 8
71111.05Q Miscellaneous
BVPS Fire Safety Analysis Report
Revision 0
Fire Safety Analysis Report
Revision 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1/2PFP-AAFX
Alternate Access Facility, Fire Compartment 3-AAF-1
Revision 0
1/2PFP-YARD-
735
General Yard Area, Fire Compartment 3-YARD-1
Revision 0
Reactor Containment Building Fire Compartment 1-RC-1
Revision 3
Reactor Containment Building Fire Compartment 1-RC-1
Revision 3
Reactor Containment Building Fire Compartment 1-RC-1
Revision 3
Reactor Containment Building Fire Compartment 1-RC-1
Revision 3
HYD
Hydrogen Tanks North Yard, Fire Compartment 1-H-1
Revision 3
HYD
Hydrogen Tanks East Yard, Fire Compartment 2-H-1
Revision 1
Corrective Action
Documents
CR-2019-08565
CR-2019-08617
CR-2019-08793
Engineering
Evaluations
1901240.401
Flaw Evaluation of Safety Injection SI-72-8-S-01 Elbow-to-
Pipe Weld
10/29/2019
71111.11Q Corrective Action
Documents
2019-08356
Procedures
1OM-52.4.R.1.F
Station Shutdown from 100% Power to Mode 5
Revision 36
Corrective Action
Documents
2016-03770
2016-04318
2017-00692
2017-01418
2017-05487
2017-08280
2017-08759
2017-09705
2017-11168
2017-12247
2018-09051
2018-10205
2018-10427
2019-00376
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2019-02312
2019-03080
2019-04071
2019-07374
2019-08108
Miscellaneous
Maintenance Rule System Basis Document Compressed Air
System 34
Revision 9
Maintenance Rule Monthly Monitoring Spreadsheet, Unit 2
System 34, April 2019
Maintenance Rule System Basis Document Compressed Air
System 34
Revision 8
ECP-02-0540
Installation of BV-2 Station Instrument Air System Standby
Train
Revision 2
Procedures
BVPM-ER-3004
Maintenance Rule (MR) Program Supplemental Guidance
Revision 3
Corrective Action
Documents
2019-08726
2019-08730
2019-08731
2019-09028
Miscellaneous
Beaver Valley Key Shutdown Defense-in-Depth Turnover
Checklist
10/28/2019
Defense-in-Depth Protected Equipment
10/28/2019
Beaver Valley Unit 1 Week 11/11/2019, T-0 ICDP Profile
Revision 0
Beaver Valley Unit 1 Week 11/11/2019, T-0 ICDP Profil
Revision 1
Beaver Valley Key Shutdown Defense-in-Depth Turnover
Checklist
10/17/2019
Defense-in-Depth Protected Equipment
10/17/2019
Beaver Valley Key Shutdown Defense-in-Depth Turnover
Checklist
10/21/2019
Defense-in-Depth Protected Equipment
10/21/2019
Corrective Action
Documents
2017-11132
2018-04338
2019-08406
2019-08560
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2019-08646
2019-08682
2019-08686
2019-09157
2019-09972
Drawings
RM-0430-002
Valve Oper No Diagram Service Water Primary Cooling
Revision 43
Miscellaneous
DMC-2756
Torque Calculation for MOV-1SI-862A and MOV-1SI-862B
Revision 10
DMC-2936
MOV Weak Link Evaluation of Crane-Aloyco Valves MOV-
1SI-860A&B and MOV-1SI-862A&B Using ASME Allowable
Stresses
Revision 0
EER 600596672
EER 601243771
EER 601250941
Procedures
1-MSP-E-39-003
Vital Bus Batteries, Test and Inspection
Revision 10
1-MSP-E-39-403
Battery [BAT-1-3] Service Discharge Test
Revision 4
1OST-39.7
Weekly DC Bus Distribution Surveillance
Revision 8
Corrective Action
Documents
2019-08323
2019-08661
2019-08804
2019-08818
2019-08977
2019-09029
2019-09033
2019-09034
2019-09046
2019-09080
2019-09084
Miscellaneous
C&D Technologies Capacity Discharge Test Report
10/25/2019
101173-R-M-
00001
Functional Review of MOVs 1SI-867A through D
Revision 0
101173-R-M-
00001
Functional Review of MOVs 1SI-867A through D
Revision 0
ECP 15-0482-002
Replace PNL-DC1-6
Revision 1
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ECP 18-0166-001
ECP 18-0166-002
ECP-18-0001-000 Modify BVPS Unit 1 SI Valves MOV-1SI-867A/B
Revision 2
EER 601243635
EER 601244321
EER 601244327
EER 601244356
RM-0411-001
Piping & Instrumentation Diagram Safety Injection System
Revision 29
Procedures
1MSP-39.08-E
Battery No. 1-3 Inspection and Interconnection Resistance
Check
Revision 11
Vital Bus Batteries, Test and Inspection
Revision 10
1OST-1.10J
Cold Shutdown Valve Exercise Test (Part J) Main Steam
Valves
Revision 11
1OST-36.1
Diesel Generator No. 1 Monthly Test
Revision 70
1OST-39.7
Weekly DC Bus Distribution Surveillance
Revision 8
Work Orders
200437181
200648469
200698221
200698227
200698231
200742230
200742321
200742895
200742897
200742901
200742903
200742906
200744219
200744240
200744327
200744328
200744332
200744720
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
200747613
200787662
Corrective Action
Documents
2003-04053
2019-09029
2019-09392
Miscellaneous
EER 601244327
Procedures
1/2CMP-47-
CONTINGENCY
HATCH
CLOSURE-1M
Contingency Hatch Closure
Revision 1
1OM-50.4.D1
Reactor Startup from Mode 3 to Mode 2 - Initial Criticality
Revision 1
1OM-50.4.D2
Reactor Startup from Mode 3 to Mode 2,
Revision 2
1OM-52.4.B
Load Following
Revision 56
1OM-52.4.R.1.F
Station Shutdown from 100% Power to Mode 5
Revision 36
1OM-6.4.N
Draining the RCS for Refueling
Revision 29
1OST-47.2B
Containment Closeout Inspection
Revision 23
1RST-2.2
Core Design Check Test
Revision 19
NOP-WM-5008
Control of Scaffolding
Revision 1
Corrective Action
Documents
2019-08375
2019-08500
Procedures
1OST-11.14A
LHSI Full Flow Test
Revision 35
1OST-21.5
Main Steam Trip Valve [TV-1MS-101B] Full Closure Test
Revision 21
1OST-21.6
Main Steam Trip Valve [TV-1MS-101C] Full Closure Test
Revision 21
Corrective Action
Documents
2019-01513
Monthly surveys not performed due to no lighting
2019-7900
Sample Containment, Wrong Unit
Procedures
NOP-OP-4101
Access Controls for RCA
NOP-OP-4102
Radiological Posting and Labeling
NOP-OP-4106
Radiography
NOP-OP-4197
Radiation Work Permit (RWP)
NOP-OP-4502
Control on Radioactive Material (RAM)
Radiation
Surveys
103101
2' Containment
10/13/2019
103201
718' Containment
10/13/2019
103305
738' Containment
10/13/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
103401
767' Containment
10/13/2019
103410
767' Reactor Cavity
10/13/2019
BV-M-2019-0813-
BV2 Waste Handling Building 722'
8/13/2019
BV-M-2019-0828-
BV2 Condensate Polishing Building 735'
8/28/2019
BV-M-2019-0909-
PCA Shop Decon Room
9/9/2019
BV-M-2019-0916-
BV1 Decontamination Building 735'
9/16/2019
BV-M-2019-0923-
BV1 Solid Waste
9/23/2019
Corrective Action
Documents
2019-06842
PJR not performed
2019-08828
Accumulated dose alarm
Corrective Action
Documents
Resulting from
Inspection
2019-08804
Reactor Building Containment Phone Line
Procedures
NOP-OP-4005
ALARA Program
Revision 06
Self-Assessments SA-BN-2018-
1069
Fleet Radiation Protection ALARA, Dose Control, Dose
Monitoring Assessment
8/13/2019
71151
Miscellaneous
Unit 1 Reactor Coolant System Specific Activity, October
2018 through September 2019
Unit 2 Reactor Coolant System Leakage, October 2018
through September 2019
Unit 2 Reactor Coolant System Specific Activity, October
2018 through September 2019
Unit 1 Reactor Coolant System Leakage, October 2018
through September 2019
Procedures
1-CHM-SAM-3.26
RCS-Demineralizer Inlet and Outlet Header
Revision 13