IR 05000334/2019004

Integrated Inspection Report 05000334/2019004 and 05000412/2019004

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

ary 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: DPR-66 and NPF-73 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 Enclosure

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.

71111.01 - Adverse Weather Protection Seasonal Extreme Weather Sample (IP Section 03.02)

(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)

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) Unit 1 residual heat removal system on October 20, 2019

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

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 6 safety injection weld, SI-73-8-S-01.

• 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) 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)

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)

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)

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)

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) 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,

71124.01 - Radiological Hazard Assessment and Exposure Controls Contamination and Radioactive Material Control (IP Section 02.03)

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)

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 Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action 2019-07771

Documents 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 Revision 5

September and October

2OM-45D.3.C Power Supply and Control Switch List, Revision 13

2OST-45.11A Cold Weather Protection Verification - Performed in Revision 8

September and October

71111.04Q 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 Revision 17

Rel

Miscellaneous Clearance 1R26-30-OPS-005 10/20/2019

Procedures 1OM-30.4.AB Operation of the Reactor Plant River Water System with Revision 14

Normal Return Flow Path to Unit 1/2 Blowdown Isolated

2OST-24.4 Steam Driven Auxiliary Feed Pump [2FWE*P22] Quarterly Revision 91

Test

71111.04S Drawings RM-0410-001 Piping & Instrumentation Diagram Residual Heat Removal Revision 16

System

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 Type Designation Description or Title Revision or

Procedure Date

1/2PFP-AAFX Alternate Access Facility, Fire Compartment 3-AAF-1 Revision 0

1/2PFP-YARD- General Yard Area, Fire Compartment 3-YARD-1 Revision 0

735

1PFP-RCBX-692 Reactor Containment Building Fire Compartment 1-RC-1 Revision 3

1PFP-RCBX-718 Reactor Containment Building Fire Compartment 1-RC-1 Revision 3

1PFP-RCBX-738 Reactor Containment Building Fire Compartment 1-RC-1 Revision 3

1PFP-RCBX-767 Reactor Containment Building Fire Compartment 1-RC-1 Revision 3

1PFP-Yard-701- Hydrogen Tanks North Yard, Fire Compartment 1-H-1 Revision 3

HYD

2PFP-Yard-735- Hydrogen Tanks East Yard, Fire Compartment 2-H-1 Revision 1

HYD

71111.08P Corrective Action CR-2019-08565

Documents CR-2019-08617

CR-2019-08793

Engineering 1901240.401 Flaw Evaluation of Safety Injection SI-72-8-S-01 Elbow-to- 10/29/2019

Evaluations Pipe Weld

71111.11Q Corrective Action 2019-08356

Documents

Procedures 1OM-52.4.R.1.F Station Shutdown from 100% Power to Mode 5 Revision 36

71111.12 Corrective Action 2016-03770

Documents 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 Type Designation Description or Title Revision or

Procedure Date

2019-02312

2019-03080

2019-04071

2019-07374

2019-08108

Miscellaneous Maintenance Rule System Basis Document Compressed Air Revision 9

System 34

Maintenance Rule Monthly Monitoring Spreadsheet, Unit 2

System 34, April 2019

Maintenance Rule System Basis Document Compressed Air Revision 8

System 34

ECP-02-0540 Installation of BV-2 Station Instrument Air System Standby Revision 2

Train

Procedures BVPM-ER-3004 Maintenance Rule (MR) Program Supplemental Guidance Revision 3

71111.13 Corrective Action 2019-08726

Documents 2019-08730

2019-08731

2019-09028

Miscellaneous Beaver Valley Key Shutdown Defense-in-Depth Turnover 10/28/2019

Checklist

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 10/17/2019

Checklist

Defense-in-Depth Protected Equipment 10/17/2019

Beaver Valley Key Shutdown Defense-in-Depth Turnover 10/21/2019

Checklist

Defense-in-Depth Protected Equipment 10/21/2019

71111.15 Corrective Action 2017-11132

Documents 2018-04338

2019-08406

2019-08560

Inspection Type Designation Description or Title Revision or

Procedure 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- Revision 0

1SI-860A&B and MOV-1SI-862A&B Using ASME Allowable

Stresses

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

71111.19 Corrective Action 2019-08323

Documents 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- Functional Review of MOVs 1SI-867A through D Revision 0

00001

101173-R-M- Functional Review of MOVs 1SI-867A through D Revision 0

00001

ECP 15-0482-002 Replace PNL-DC1-6 Revision 1

Inspection Type Designation Description or Title Revision or

Procedure 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 Revision 11

Check

1MSP-E-39-003 Vital Bus Batteries, Test and Inspection Revision 10

1OST-1.10J Cold Shutdown Valve Exercise Test (Part J) Main Steam Revision 11

Valves

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 Type Designation Description or Title Revision or

Procedure Date

200747613

200787662

71111.20 Corrective Action 2003-04053

Documents 2019-09029

2019-09392

Miscellaneous EER 601244327

Procedures 1/2CMP-47- Contingency Hatch Closure Revision 1

CONTINGENCY

HATCH

CLOSURE-1M

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

71111.22 Corrective Action 2019-08375

Documents 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

71124.01 Corrective Action 2019-01513 Monthly surveys not performed due to no lighting

Documents 2019-7900 Sample Containment, Wrong Unit

Procedures NOP-OP-4101 Access Controls for RCA 16

NOP-OP-4102 Radiological Posting and Labeling 14

NOP-OP-4106 Radiography 06

NOP-OP-4197 Radiation Work Permit (RWP) 18

NOP-OP-4502 Control on Radioactive Material (RAM) 06

Radiation 103101 692' Containment 10/13/2019

Surveys 103201 718' Containment 10/13/2019

103305 738' Containment 10/13/2019

Inspection Type Designation Description or Title Revision or

Procedure 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

71124.02 Corrective Action 2019-06842 PJR not performed

Documents 2019-08828 Accumulated dose alarm

Corrective Action 2019-08804 Reactor Building Containment Phone Line

Documents

Resulting from

Inspection

Procedures NOP-OP-4005 ALARA Program Revision 06

Self-Assessments SA-BN-2018- Fleet Radiation Protection ALARA, Dose Control, Dose 8/13/2019

1069 Monitoring Assessment

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

15