IR 05000272/2019010

Biennial Problem Identification and Resolution Inspection Report 05000272/2019010 and 05000311/2019010

ML19094A667
Person / Time
Site:	Salem
Issue date:	04/04/2019
From:	Brice Bickett Reactor Projects Branch 3
To:	Sena P Public Service Enterprise Group
References
IR 2019010
Download: ML19094A667 (15)

Text

April 4, 2019

SUBJECT:

SALEM UNITS 1 AND 2 - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000272/2019010 AND 05000311/2019010

Dear Mr. Sena:

On February 15, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Salem Units 1 and 2. On March 7, 2019, the NRC inspectors discussed the results of this inspection with Patrick Martino, Salem Plant Manager, and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspection team reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.

The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.

Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.

Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment.

Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.

The NRC inspectors did not identify any finding or violation of more than minor significance. 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 (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Brice A. Bickett, Chief Projects Branch 3

Docket Nos.: 05000272 and 05000311 License Nos.: DPR-70 and DPR-75

Enclosure:

Inspection Report 05000272/2019010 and 05000311/2019010

Inspection Report

Docket Numbers:

05000272 and 05000311

License Numbers:

DPR-70 and DPR-75

Report Numbers:

05000272/2019010 and 05000311/2019010

Licensee:

PSEG Nuclear, LLC

Facility:

Salem, Units 1 and 2

Location:

Hancocks Bridge, NJ 08038

Inspection Dates:

January 28, 2019 to February 15, 2019

Inspectors:

N. Floyd, Senior Reactor Inspector

J. Rady, Reactor Inspector

J. Schoppy, Senior Reactor Inspector

J. Vazquez, Resident Inspector

Approved By:

Brice A. Bickett, Chief

Projects Branch 3

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting the biennial problem identification and resolution inspection report at Salem 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.

Findings and violations being considered in the NRCs assessment are summarized in the table below.

List of Findings and Violations

No findings were identified.

Additional Tracking Items

None.

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.

OTHER ACTIVITIES - BASELINE

71152B - Problem Identification and Resolution 02.04 Biennial Team Inspection

The inspectors performed a biennial assessment of PSEGs corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment.

• Corrective Action Program Effectiveness: The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems.

• Operating Experience, Self-Assessments and Audits - The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits, and self-assessments.

• Safety Conscious Work Environment - The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.

INSPECTION RESULTS

Observation 71152B The inspectors reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the inspectors determined PSEGs performance in each of these areas supported nuclear safety.

The inspectors also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments. Based on the samples reviewed, the inspectors determined that PSEGs performance in each of these areas supported nuclear safety.

Finally, the inspectors reviewed the stations programs to establish and maintain a safety conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs. Based on the inspectors observations and the results of these interviews, the inspectors found no evidence of challenges to the organizations safety conscious work environment. A cross section of PSEG employees were interviewed, and all stated a willingness to raise nuclear safety concerns through at least one of the several means available.

Observation 71152B Corrective Action Program - Identification: The inspectors determined that, in general, PSEG identified issues and entered them into the corrective action program at a low threshold. However, during plant tours, the inspectors identified several minor deficiencies not previously captured in PSEGs corrective action program.

PSEG promptly entered each item into their corrective action program and took actions to address the issues.

Observation 71152B Corrective Action Program - Evaluation: Based on the samples reviewed, the inspectors determined that, in general, PSEG appropriately prioritized and evaluated issues commensurate with the safety significance of the identified problem. PSEG appropriately screened notifications (NOTFs) for operability and reportability, categorized the NOTFs by significance, and assigned actions to the appropriate department for evaluation and resolution. However, the inspectors identified ten NOTFs that PSEG classified as significance level (SL) 4 (non-corrective action program) that should have been classified as SL 2 (condition adverse to quality) or SL 3 (condition adverse to regulatory compliance). The inspectors determined that this represented a performance issue of minor significance as the number of misclassified NOTFs was statistically insignificant (10 out of 9675 SL 4 NOTFs)and had no adverse impact on safety. PSEG initiated NOTFs 20792036, 20819293, and 20819656 for this issue.

Observation 71152B Corrective Action Program - Correcting Problems: The inspectors determined that the overall corrective action program performance related to resolving problems was effective. In most cases, PSEG implemented corrective actions to resolve problems in a timely manner.

However, the inspectors identified an inadequate corrective action related to a procedure revision to address the storage of transient combustibles near above-ground safety-related water storage tanks.

Prior to the change, procedure FP-AA-011, Control of Transient Combustible Material, Revision 6, required a transient combustible permit to be generated prior to staging any combustible materials within 50 feet of exposed, above-ground safety-related water tanks. In September 2018, however, the Salem Nuclear Oversight group identified several instances of transient combustibles, without permits, within the vicinity of the Unit 1 and Unit 2 primary water storage tanks and the Unit 2 auxiliary feedwater tank (NOTF 20804966).

As a corrective action, PSEG revised procedure FP-AA-011 to only require transient combustible permits in cases where an excessive amount of material was to be stored within 50 feet of associated tanks. The inspectors noted the revised procedure provided no guidance for what constituted an excessive amount of material. During inspector questioning, PSEG staff stated that this determination could be made by the Fire Marshall or a fire protection engineer using engineering judgment.

The inspectors determined that relying on this reasoning introduced a vulnerability into the process. Specifically, a work group supervisor (who is not necessarily a fire protection subject matter expert) could make the determination independently that materials being used do not constitute an excessive quantity, and would thereby not initiate a transient combustible permit. PSEG staff initiated NOTF 20819077 to capture the inspectors concerns and recommended an action to revise the procedure to clarify the requirements and/or remove the vulnerability.

Minor Violation 71152B Minor Violation: The inspectors identified a minor violation of Salem Unit 1 License Condition 2.C.(5) and Salem Unit 2 License Condition 2.C.(10) of the respective facility operating licenses for failure to implement and maintain in effect all provisions of the approved Fire Protection Program. Specifically, during the week of January 28, 2019, inspectors performed walkdowns of Salem Units 1 and 2 and identified several transient combustible permits that were expired within the plant. PSEG failed to utilize procedure FP-AA-011, Control of Transient Combustible Material, Revision 6, to administratively control the initial request, approval and close-out of transient combustible permits associated with online and outage work activities within several fire areas.

PSEG promptly performed an extent of condition review and identified 14 additional expired transient combustible permits at Salem Units 1 and 2. PSEG entered this issue into their corrective action program and documented corrective actions to be taken. This issue is related to the assessment of the Corrective Action Program Area of Problem Identification.

(Notifications 20815384, 20818077, 20818078, and 20818082)

Screening: The inspectors determined the performance deficiency was minor. The inspectors determined that this performance deficiency was administrative in nature and had minor significance because the aggregate transient combustible loading remained unchanged for these fire areas within the site's fire protection permitting software, and additional engineering evaluations were not required to extend the expiration dates for the expired transient combustible permits.

Enforcement:

This failure to comply with Salem Unit 1 License Condition 2.C.(5) and Salem Unit 2 License Condition 2.C.(10) of the respective facility operating licenses constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.

Minor Violation 71152B Minor Violation: The inspectors identified a minor violation of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, because PSEG did not adequately restrain equipment located in seismic control areas that contained safety-related systems, structures, and components (SSCs), as required by station procedures. Specifically, on January 30, 2019, while observing the conduct of operator rounds (twice-daily system/area status checks), the inspectors identified a wheeled cart and a wheeled tool box, both located in seismic control areas, with wheels that were not locked against rolling, as required by procedure CC-AA-320-011, Control of Transient Loads, Revision 1. This procedure prescribes requirements for controlling transient/non-permanent equipment in the plant to prevent seismic hazards, and also requires that an engineering evaluation be performed when these requirements cannot be met. Following identification of the issues by the inspectors, the PSEG operations crew took immediate actions to properly secure the equipment using chains and wheel chocks/clamps.

Based on discussions with operations staff, the inspectors understood that PSEG did not typically generate documentation for restraint issues if immediately actions were taken. The inspectors noted that not documenting equipment restraint issues did not allow for the condition to be evaluated by engineering and could prevent the organization from being able to capture potential trends. PSEG staff generated NOTF 20818191 to capture the instances of unrestrained equipment discussed above and NOTF 20819318 to capture the concern regarding expectations associated with documenting such issues. PSEG developed a corrective action to address the associated performance gaps. PSEG also performed an engineering evaluation to assess the potential impact of the unsecured toolbox on nearby safety-related SSCs. This evaluation concluded that there was reasonable assurance that there would not have been any adverse impact on the capability of the SSCs to perform safety-related functions during a design-basis seismic event. The inspectors reviewed this evaluation and determined that the PSEGs conclusions were reasonable.

The inspectors reviewed additional NOTFs generated throughout 2017 and 2018, which documented issues with equipment that were inadequately restrained in accordance with procedure CC-AA-320-011. Based on a review of these instances and the conversations with PSEG personnel regarding the performance gap in documenting issues using the stations established programs, the inspectors identified a potential trend in inadequately secured equipment in seismic control areas. PSEG documented this potential trend in NOTF 20820748.

Screening: The inspectors determined the performance deficiency was minor. The inspectors evaluated this issue using IMC 0612, Appendix B, Issue Screening, and IMC 0612, Appendix E, Examples of Minor Issues, and determined that it was of minor significance because there would be no adverse impact on the safety-related SSCs during a postulated design-basis seismic event.

Enforcement:

This failure to comply with 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

The inspectors confirmed that proprietary information was controlled to protect from public disclosure.

• On February 15, 2019, the inspectors debriefed the preliminary results to Charles McFeaters, Salem Vice President, and other members of the PSEG staff.

• On March 7, 2019, the inspectors conducted a telephone exit meeting presenting the final inspection results to Patrick Martino, Salem Plant Manager, and other members of the PSEG staff.

DOCUMENTS REVIEWED

71152B

Procedures

LS-AA-104, 50.59 Review Process, Revision 6

LS-AA-125, Corrective Action Program, Revision 25

LS-AA-125-1001, Cause Analysis, Revision 16

LS-AA-125-1002, Common Cause Evaluation Manual, Revision 10

LS-AA-128, Regulatory Review of Proposed Changes to the Approved Fire Protection Program,

Revision 1

MA-AA-716-021, Rigging and Lifting Program, Revision 25

MA-AA-716-026, Station Housekeeping / Material Condition Program, Revision 13

MA-AA-796-024, Scaffold Installation, Inspection and Removal, Revision 18

OP-AA-115-101, Operator Aid Postings, Revision 3

OP-SA-108-115-1001, Operability Assessment and Equipment Control Program, Revision 13

PIA-036, Equipment Reliability Evaluation, Revision 1

S1.OP-AR.DG-0001, 1A Diesel Generator Alarm Response, Revision 16

S1.OP-AR.ZZ-0002, Overhead Annunciators Window B, Revision 30

S2.OP-SO.RM-0001, Radiation Monitoring Systems Operation, Revision 42

SC.FP-ST.FS-0008, Fire Main Flow Test Methodology Review, Revision 5

SC.MD-CM.SW-0002, Service Water Valve and Pipe Flange Repair, Revision 8

SC.MD-CM.SW-0003, Service Water Lined Pipe Repair, Revision 4

SC.MD-PM.115-0001, 10/12 KVA Vital Instrument Bus Inverter Preventive Maintenance,

Revision 15

SC.MD-PM.SW-0003, Service Water Auto Strainer Adjustment, Inspection, Repair and

Replacement, Revision 44

SC.MD-PM.ZZ-0106, Disassembly, Inspection and Assembly of Henry Pratt Butterfly Valves

Model N-2FII, Revision 10

SC.MD-PM.ZZ-0135, Ventilation Damper Inspection and Guidelines, Revision 17

SC-DG025-01, Salem U1 & U2 DG Jacket Water Expansion Tank Level Alarms, Revision 0

WC-AA-106, Work Screening and Processing, Revision 21

Notifications (*initiated in response to inspection

20003201

20048734

20085452

20176314

232293

232295

262626

20337561

20401824

20421330

20439445

20458258

20475101

20481381

20495871

20506830

20508663

20522873

20523166

20548867

20551838

20562218

20571904

20577096

20585172

20586590

20606186

20607016

20607055

20611824

20626161

20626163

20636406

20638046

20642517

20643644

20647631

20648696

20651119

20653296

20655409

20656435

20665854

20670334

20674685

20675163

20675208

20675522

20675543

20675683

20685080

20699560

20702471

20711527

20718131

20724777

20725423

20727719

20734874

20736553

20740729

20745194

20748801

20751413

20752861

20753786

20757991

20764238

20764651

20765122

20766688

20769477

20771229

20771251

20771766

20772096

20772246

20772312

20772387

20772566

20772751

20772939

20772977

20773095

20773101

20773111

20773170

20773286

20773337

20774261

20774276

20774585

20774863

20775039

20775150

20775188

20775229

20775791

20775792

20775793

20775877

20776550

20776693

20776728

20777663

20777757

20777982

20778031

20779522

20779750

20779766

20780090

20780234

20780495

20780535

20780680

20780746

20780838

20781774

20781843

20781845

20781940

20782006

20782370

20783309

20783511

20783749

20783955

20783979

20785076

20785118

20785155

20785256

20785752

20786121

20786157

20786794

20786796

20787256

20787384

20787509

20787575

20787576

20787699

20787702

20787958

20788027

20788078

20788090

20788092

20788179

20788254

20788367

20788424

20788486

20788604

20789487

20789997

20790999

20792063

20792300

20793365

20793470

20793500

20793538

20793642

20794660

20795303

20795722

20795824

20796469

20796521

20796568

20796648

20796886

20797351

20797524

20797571

20797923

20798039

20798139

20798769

20798798

20799536

20799614

20799780

20799781

20800091

20800430

20800533

20800674

20800710

20801004

20801028

20801155

20801349

20802233

20802344

20802402

20802590

20802949

20803487

20803537

20803661

20803828

20803969

20804032

20804120

20804234

20804652

20804781

20804789

20805016

20805510

20805650

20805661

20805665

20806107

20806129

20806291

20806292

20806825

20806895

20807436

20807689

20807927

20808306

20808312

20808662

20808891

20809126

20809348

20809890

20810758

20810767

20811234

20811668

20813114

20813292

20813312

20813315

20813933

20813951

20815253

20815725

20816942

20818045

20818131

20818430

20818717

20818758

20818051*

20818052*

20818071*

20818075*

20818077*

20818078*

20818174*

20818177*

20818179*

20818187*

20818188*

20818191*

20818194*

20818195*

20818328*

20818362*

20818363*

20818371*

20818372*

20818389*

20818405*

20818412*

20818621*

20818626*

20818647*

20818773*

20818806*

20818807*

20818816*

20818888*

20818889*

20819076*

20819077*

20819088*

20819227*

20819257*

20819272*

20819273*

20819291*

20819293*

20819301*

20819314*

20819434*

20819439*

20819441*

20819447*

20819478*

20819526*

20819653*

20819656*

20819660*

20819661*

Maintenance Orders/Work Orders

30062930

30084709

30185727

206496

265378

288951

289986

291416

291417

292315

298209

30309212

30312654

30315826

30315883

30316464

30317596

30324473

50193332

60097269

60113280

60114217

60114664

60115349

60116868

60118068

60121390

60121391

60121840

60122014

60122325

60123985

60126676

60127438

60128003

60128308

60128788

60129009

60131247

60133115

60134375

60135852

60135971

60135986

60136007

60136065

60136323

60136324

60136339

60136739

60136964

60137052

60137117

60137241

60137401

60137844

60138139

60140144

60140281

60140659

60140853

60141121

70089527

70179496

70187865

70191433

70195617

70195979

70196181

70196611

70196738

70196828

70197610

70197669

70197758

70198344

70198345

70198747

70198897

70199078

70199317

200350

200382

200391

200408

200981

201207

201627

201741

202301

202371

202548

203111

203165

203938

204155

204597

204692

205686

80112300

Drawings

205241, Sh. 1, No. 1 & 2 Units Diesel Engine Auxiliaries, Revision 42

Evaluations

70189044, Salem Service Water Intake Structure MRule (a)(1) Evaluation, dated 11/3/16

70193055, Salem Unit 1 and Unit 2 Service Water System MRule (a)(1) Evaluation,

dated 5/24/17

70194685, CCE (Common Cause Evaluation), APTIM Trend in Significant Events,

dated 8/14/17

70195309, ERE (Equipment Reliability Evaluation), 2B Emergency Diesel Generator K1C

Relay Did Not Reset After Run, Revision 0

70195430, ERE, Broken Airline to 22SW122, 22 Component Cooling Heat Exchanger Service

Water Inlet Control Valve, dated 8/23/17

70196135, ACE (Apparent Cause Evaluation), Salem Station Identified Finding (SIF) -

Maintenance Training Continuing Training (CT) Gap, dated 1/31/18

70199253, WGE (Work Group Evaluation), Parts Storage Salem Mechanical Maintenance,

dated 3/8/18

70199518, ERE, 26 Service Water Pump Failed IST (Low Disch Press), dated 4/17/18

70199757, ERE, 2D Vital Instrument Bus Inverter Failure Alarm, Revision 0

200390, RCE (Root Cause Evaluation), 21 Reactor Coolant Pump Motor Winding

Temperature Failing, Revision 0

201764, ACE, Adverse Trend in ACAD 02-001 Objective 3, dated 8/10/18

201790, ACE, 11/12 SW Strainer Rigging Event, dated 8/21/18

202380, CCE, Salem SLTID Maintenance Declining Trend Report, dated 10/2/18

202475, ACE, Engineering CAP/QUALS Nuclear Oversight, Revision 0

202676, ERE, 22 SW Strainer Body Wear Ring Material Condition, dated 10/15/18

204260, ACE, Quality Maintenance Issue - Double Gasket, dated 12/12/18

202713, RCE, 23BF19 Positioner Feedback Failure and U2 Reactor Trip, Revision 0

70198299, ERE, 1R19B Steam Generator Blowdown Radiation Monitor Failed Checksource

Test, Revision 1

70196060, CCE, Adverse Trends in Station Human Performance, Revision 0

201878, CCE, Evaluation of 2018 Level 5 and Level 6 Reactivity Management Events,

Revision 0

Non-Cited Violations (NCV) and Findings (FIN)

FIN 05000272 and 05000311/2018001-01, Implementing Procedures for Beyond Design Basis

FLEX Mitigating Strategies Not Followed

FIN 05000272/2017004-05, Inadequate Evaluation of Operating Experience for Vital Instrument

Bus Inverter

NCV 05000272 and 05000311/2017007-01, Inadequate Design Verification that Inter-Cabinet

Bolts Were Installed Between SEC and Bailey Cabinets

NCV 05000272&311/2017007-02, Inadequate PM for the EDG Room Ventilation System

NCV 05000272/2017003-02, Violation of Containment Integrity Technical Specification

NCV 05000272/2017004-03, Worker Not Briefed on Dose Rates Before Entering a High

Radiation Area

NCV 05000272/2017004-04, Inadequate Maintenance Procedure for a Service Water Pump

Strainer Discharge Valve

NCV 05000272/2018001-03, Failure to Establish Containment Integrity during Plant Startup

NCV 05000311/2017007-03, Inadequate Corrective Action Regarding Missed Periodic

Inspections of 2C EDG AVR Card

NCV 05000311/2018002-01, Inadequate Design Change for Service Water Pumps

NCV 05000311/2018003-01, Inadequate Chiller Maintenance Procedures

NCV 05000311/2018003-02, Failure to Follow Generic Letter 89-13 Program Procedure

Self-Assessments and Audits

70191565-204, Maintenance Fundamentals Self-Assessment Report, dated 7/28/17

70191565-210, Salem Plant Leaks Gap Check-In Self-Assessment Report, dated 8/11/17

70198604, Salem Aging Management for Protective Relays, dated 8/2/18

80121006, Triennial Fire Protection Inspection Self-Assessment Report, dated 1/23/18

80121391-020, 2018 Salem Maintenance & Technical Training Comprehensive Self-Evaluation

Report, dated 3/23/18

NOSA-HPC-17-10, Nuclear Repair Program Audit Report Audit, dated 12/19/17

NOSA-HPC-18-02, Emergency Plan, Procedures, Facilities, and Interfaces Audit Report, dated

4/12/18

NOSA-HPC-18-07, Salem and Hope Creek Fire Protection Audit Report, dated 10/9/18

NOSA-HPC-18-10, Nuclear Repair Program Audit Report, dated 12/17/18

NOSA-SLM-17-08, Radiation Protection Audit Report dated 10/6/2017

NOSA-SLM-17-09, Operations, Operations Training, and PORC Audit Report dated 12/13/2017

NOSA-SLM-18-03, Maintenance Audit Report, dated 3/14/18

NOSA-SLM-18-04, Chemistry, Radwaste, Effluent and Environmental Monitoring Audit Report,

dated 5/9/18

NOSA-SLM-18-06, Salem Engineering Programs and Station Blackout Audit Report, dated

8/30/18

Miscellaneous

SB-032-UPS, Component Reliability on Cyberex Power Supplies, Revision C02

430868, Godwin Pumps Operating and Maintenance Manual, Revision 4

60129009-060, 21 SW Return Header VT-2 Visual Examination, dated 5/8/16

80124210-020, Seismic II/I FLEX Cart Evaluation, dated 03/01/19

Maintenance Plans PM034210, PM038088, PM043329, PM137336, and PM137343

Service Water Material Masters 1130607 and 1130683

Unit 1 Primary Plant Log (1A, 1B, and 1C EDG JW Level), 1/2/19 - 2/4/19