IR 05000272/2019010
| 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
ril 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 Enterprise Identifier: I-2018-010-0063 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 20508663 20636406 20675543 20752861
20048734 20522873 20638046 20675683 20753786
20085452 20523166 20642517 20685080 20757991
20176314 20548867 20643644 20699560 20764238
232293 20551838 20647631 20702471 20764651
232295 20562218 20648696 20711527 20765122
262626 20571904 20651119 20718131 20766688
20337561 20577096 20653296 20724777 20769477
20401824 20585172 20655409 20725423 20771229
20421330 20586590 20656435 20727719 20771251
20439445 20606186 20665854 20734874 20771766
20458258 20607016 20670334 20736553 20772096
20475101 20607055 20674685 20740729 20772246
20481381 20611824 20675163 20745194 20772312
20495871 20626161 20675208 20748801 20772387
20506830 20626163 20675522 20751413 20772566
20772751 20783511 20796469 20805661 20818187*
20772939 20783749 20796521 20805665 20818188*
20772977 20783955 20796568 20806107 20818191*
20773095 20783979 20796648 20806129 20818194*
20773101 20785076 20796886 20806291 20818195*
20773111 20785118 20797351 20806292 20818328*
20773170 20785155 20797524 20806825 20818362*
20773286 20785256 20797571 20806895 20818363*
20773337 20785752 20797923 20807436 20818371*
20774261 20786121 20798039 20807689 20818372*
20774276 20786157 20798139 20807927 20818389*
20774585 20786794 20798769 20808306 20818405*
20774863 20786796 20798798 20808312 20818412*
20775039 20787256 20799536 20808662 20818621*
20775150 20787384 20799614 20808891 20818626*
20775188 20787509 20799780 20809126 20818647*
20775229 20787575 20799781 20809348 20818773*
20775791 20787576 20800091 20809890 20818806*
20775792 20787699 20800430 20810758 20818807*
20775793 20787702 20800533 20810767 20818816*
20775877 20787958 20800674 20811234 20818888*
20776550 20788027 20800710 20811668 20818889*
20776693 20788078 20801004 20813114 20819076*
20776728 20788090 20801028 20813292 20819077*
20777663 20788092 20801155 20813312 20819088*
20777757 20788179 20801349 20813315 20819227*
20777982 20788254 20802233 20813933 20819257*
20778031 20788367 20802344 20813951 20819272*
20779522 20788424 20802402 20815253 20819273*
20779750 20788486 20802590 20815725 20819291*
20779766 20788604 20802949 20816942 20819293*
20780090 20789487 20803487 20818045 20819301*
20780234 20789997 20803537 20818131 20819314*
20780495 20790999 20803661 20818430 20819434*
20780535 20792063 20803828 20818717 20819439*
20780680 20792300 20803969 20818758 20819441*
20780746 20793365 20804032 20818051* 20819447*
20780838 20793470 20804120 20818052* 20819478*
20781774 20793500 20804234 20818071* 20819526*
20781843 20793538 20804652 20818075* 20819653*
20781845 20793642 20804781 20818077* 20819656*
20781940 20794660 20804789 20818078* 20819660*
20782006 20795303 20805016 20818174* 20819661*
20782370 20795722 20805510 20818177*
20783309 20795824 20805650 20818179*
Maintenance Orders/Work Orders
30062930 60113280 60134375 60140853 70199317
30084709 60114217 60135852 60141121 70200350
30185727 60114664 60135971 70089527 70200382
206496 60115349 60135986 70179496 70200391
265378 60116868 60136007 70187865 70200408
288951 60118068 60136065 70191433 70200981
289986 60121390 60136323 70195617 70201207
291416 60121391 60136324 70195979 70201627
291417 60121840 60136339 70196181 70201741
292315 60122014 60136739 70196611 70202301
298209 60122325 60136964 70196738 70202371
30309212 60123985 60137052 70196828 70202548
30312654 60126676 60137117 70197610 70203111
30315826 60127438 60137241 70197669 70203165
30315883 60128003 60137401 70197758 70203938
30316464 60128308 60137844 70198344 70204155
30317596 60128788 60138139 70198345 70204597
30324473 60129009 60140144 70198747 70204692
50193332 60131247 60140281 70198897 70205686
60097269 60133115 60140659 70199078 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