IR 05000272/2018004

Integrated Inspection Reports 05000272/2018004 and 05000311/2018004

ML19030A321
Person / Time
Site:	Salem
Issue date:	01/30/2019
From:	Fred Bower Reactor Projects Branch 3
To:	Sena P Public Service Enterprise Group
References
IR 2018004
Download: ML19030A321 (21)

Text

January 30, 2019

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 -

INTEGRATED INSPECTION REPORTS 05000272/2018004 AND 05000311/2018004

Dear Mr. Sena:

On December 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Salem Nuclear Generating Stations (Salem) Units 1 and 2. On January 10, 2019, the NRC inspectors discussed the results of this inspection with Mr. Charles McFeaters, Salem Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

No NRC-identified or self-revealing findings were identified during this inspection. NRC inspectors documented one PSEG-identified violation which was determined to be Severity Level IV in this report. The NRC is treating this violation as a non-cited violation (NCV)

consistent with Section 2.3.2.a of the Enforcement Policy.

If you contest the violation or significance of the NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement; and the NRC Resident Inspector at Salem 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 the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Fred L. Bower, III, Chief Reactor Projects Branch 3 Division of Reactor Projects Docket Nos.: 50-272 and 50-311 License Nos.: DPR-70 and DPR-75

Enclosure:

Inspection Report 05000272/2018004 and 05000311/2018004

Inspection Report

Docket Nos. 50-272 and 50-311 License Nos. DPR-70 and DPR-75 Report Nos. 05000272/2018004 and 05000311/2018004 Enterprise Identifier: I-2018-004-0060 PSEG: PSEG Nuclear LLC PSEG Facility: Salem Nuclear Generating Station (Salem) Units 1 and 2 Location: Hancocks Bridge, NJ 08038 Dates: October 1, 2018 through December 31, 2018 Inspectors: P. Finney, Senior Resident Inspector A. Ziedonis, Resident Inspector J. Furia, Senior Health Physicist J. Schoppy, Senior Reactor Inspector P. Ott, Operations Engineer J. DeBoer, Emergency Preparedness Inspector M. Modes, Senior Reactor Inspector M. Hardgrove, Project Engineer B. DeBoer, Health Physicist Approved By: Fred L. Bower, III, Chief Reactor Projects Branch 3 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring PSEGs performance at

Salem Units 1 and 2 by conducting the baseline inspections described in this report 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. NRC identified and self-revealing findings, violations, and additional items are summarized in the table below. A PSEG-identified non-cited violation is documented in the following Inspection Results sections of the report: 71152.

List of Findings and Violations No findings or more-than-minor violations were identified.

Additional Tracking Items Type Issue number Title Inspection Status Results Section License 05000272/2016-006-01 Technical Specification 71153 Closed Event (TS) for Containment Report Integrity not met (LER)

PLANT STATUS

Unit 1 began the inspection period at rated thermal power. The unit remained at or near rated thermal power for the remainder of the inspection period.

Unit 2 began the inspection period at rated thermal power. On October 11, 2018, the Salem Unit 2 reactor was manually tripped from 13 percent power as part of a pre-planned evolution to commence the 2R23 refueling outage. A reactor startup was commenced on November 12, 2018, and the unit reached rated thermal power on November 16, 2018. There were no other operational power changes of regulatory significance for the remainder of the inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors 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 PSEGs performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

71111.01 - Adverse Weather Protection Seasonal Extreme Weather

The inspectors evaluated readiness for seasonal extreme weather conditions prior to seasonal cold temperatures.

71111.04 - Equipment Alignment Partial Walkdown

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 2, Service water (SW) following degraded vent and drain repairs on October 25, 2018

(2) Unit 2, Shutdown cooling during core reload on October 31, 2018

(3) Unit 2, Safety injection system (post outage) on November 13 , 2018

Complete Walkdown (1 Sample)

The inspectors evaluated system configurations during a complete walkdown of the Unit 2 auxiliary feedwater system during the week of November 11, 2018.

71111.05A/Q - Fire Protection Annual/Quarterly Quarterly Inspection

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Unit 1, Electrical penetration areas during and following chill water pump lube on October 5, 2018

(2) Unit 1, 480 V switchgear room while controlled as a fire risk management area on November 5, 2018

(3) Unit 1, 4160 V switchgear room while controlled as a fire risk management area on November 6, 2018

(4) Unit 2, Containment during core alterations on November 1, 2018

(5) Unit 2, Emergency diesel generator (EDG) and day tank areas on November 9, 2018

71111.07 - Heat Sink Performance Heat Sink

The inspectors evaluated PSEGs monitoring and maintenance of the 21 component cooling heat exchanger on October 17, 2018.

71111.08 - Inservice Inspection Activities

The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the following examinations from October 22 to 30, 2018:

(1) Ultrasonic Testing a. Containment liner S2-KNUCKLE-78 b. Vessel nozzle 29 RC 1220-1 c. Vessel nozzle 29 RC 1210-1

(2) Visual Examination a. Containment liner S2-KNUCKLE-78 b. Residual heat removal piping exterior surfaces

(3) Liquid Penetrant Examination a. Residual heat removal piping exterior surfaces The inspectors evaluated the PSEG boric acid control program performance.

71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification

The inspectors observed and evaluated a crew of licensed operators in the plants simulator during licensed operator requalification training that involved a condensate pump motor fire, loss of one condensate pump, and a steam generator tube leak that further degraded into a tube rupture, on December 3, 2018.

Operator Performance (2 Samples)

The inspectors observed a Unit 2 reactor shutdown and cooldown during a refueling outage on October 11, 2018.

The inspectors observed the Unit 2 post-refueling outage reactor start-up on November 12, 2018.

71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification Exam Results (Annual)

The inspectors reviewed and evaluated requalification examination results on October 19, 2018.

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Common, valve and damper linkages on October 9, 2018

(2) Unit 2, EDG fuel oil leakage on November 9, 2018

Quality Control (1 Sample)

The inspectors evaluated maintenance and quality control activities associated with the following equipment performance issues:

(1) Common, reactor coolant pump seal injection flexitallic gasket on November 9, 2018

71111.13 - Maintenance Risk Assessments and Emergent Work Control

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Common, secondary chemistry leak on 1H 4KV non-vital bus and actuation of 22 auxiliary feedwater (AFW) pump during calibration on October 16, 2018

(2) Unit 2, Reactor coolant system (RCS) drain down to mid loop for RCS vacuum fill resulting in a planned Orange risk condition on November 4, 2018

(3) Unit 2, TS 3.4.0.b for 24 and 25 containment fan coil units (CFCU) in operation during transition to mode 4 on November 6, 2018

71111.15 - Operability Determinations and Functionality Assessments

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Unit 1, 15 CFCU bearing packing break-in run on November 19, 2018

(2) Unit 1, Main turbine valve testing overdue on November 28, 2018

(3) Unit 2, EDG Appendix R transfer switch functionality on October 23, 2018

(4) Unit 2, A SEC following test failure on October 23, 2018

(5) Unit 2, 2 Bay SW motor bearing cooler orifice plate degraded on November 27, 2018

71111.18 - Plant Modifications

The inspectors evaluated the following temporary or permanent modifications:

(1) Unit 2, Advanced digital feedwater control system operation changes on October 11, 2018

(2) Unit 2, CFCU SW valve fill line on November 8, 2018

71111.19 - Post Maintenance Testing

The inspectors evaluated post maintenance testing for the following maintenance/repair activities:

(1) Unit 1, 13 component cooling water pump outboard pump and oil seal replacement on October 5, 2018

(2) Unit 1, 12 chiller following freeze penetration trip on October 28, 2018

(3) Unit 1, 11 chiller following repairs to fix refrigerant leak on November 2, 2018

(4) Unit 1, 2CC31, component cooler water heat exchange outlet valve to spent fuel pit cooling after motor operated valve stalled on November 2, 2018

(5) Unit 2, 2C EDG fuel oil leak repair on November 8, 2018

(6) Unit 2, PR2 pressurizer relief valve leakby on November 19, 2018

71111.20 - Refueling and Other Outage Activities

The inspectors evaluated Unit 2 refueling outage activities from October 11, 2018, to November 13, 2018.

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Routine

(1) Unit 2, 2A EDG endurance run and hot restart on October 2, 2018

(2) Unit 2, Reactor trip bypass breaker testing on October 21, 2018

(3) Unit 2, D Gamma metrics surveillance test on October 25, 2018

Inservice (2 Samples)

(1) Unit 2, 23 Turbine-driven AFW full flow testing on October 11, 2018

(2) Unit 2, 22 Safety injection pump full flow testing on October 21, 2018

Reactor Coolant System Leak Detection (1 Sample)

(1) Unit 2, Inadvertent draining of reactor coolant from letdown system on

December 17, 2018 Containment Isolation Valve (2 Samples)

(1) Reactor coolant pump seal water injection line valve, 21CV99, on October 17, 2018

(2) Reactor coolant pump seal water injection line valve, 24CV99, on October 17, 2018

71114.04 - Emergency Action Level and Emergency Plan Changes

The inspectors verified that the changes made to the emergency plan were done in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.54(q)(3), and any change made to the Emergency Action Levels, Emergency Plan, and its lower-tier implementing procedures, had not resulted in any reduction in effectiveness of the Plan.

This evaluation does not constitute NRC approval.

71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazards Control and Work Coverage

The inspectors evaluated in-plant radiological conditions and performed independent radiation measurements during facility walkdowns and observation of radiological work activities. The inspectors examined the physical controls for selected high radiation areas, locked high radiation areas, and very high radiation areas to verify conformance with the occupational performance indicator (PI).

Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)

The inspectors evaluated radiation worker performance with respect to radiation protection work requirements. The inspectors evaluated radiation protection technicians in performance of radiation surveys and in providing radiological job coverage.

71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls Implementation of ALARA and Radiological Work Control

The inspectors reviewed radiological work controls and ALARA practices during the observation of in-plant work activities. The inspectors reviewed the results achieved against the intended ALARA estimates to confirm adequate implementation and oversight of radiological work controls.

Radiation Worker Performance (1 Sample)

The inspectors observed radiation worker and radiation protection technician performance during radiological work to evaluate worker ALARA performance according to specified work controls and procedures.

OTHER ACTIVITIES - BASELINE

71003 - Post License Renewal Inspection (Unit 2, Phase II)

The inspectors verified PSEGs implementation of the portion of the Inservice Inspection Program credited with managing the aging of the:

(1) Containment liner (NUREG 1201, Appendix A, Commitment 28)

(2) External surfaces monitoring program applied to the residual heat removal system piping surfaces (NUREG 1201, Appendix A, Commitment 24)

(3) Inaccessible Medium Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements program (NUREG 1201, Appendix A, Commitment 38)

(4) Selective Leaching program (NUREG 1201, Appendix A, Commitment 21), and

(5) Firewater System aging management program (NUREG 1201, Appendix A, Commitment 16)

71151 - Performance Indicator Verification The inspectors verified PSEGs performance indicators submittals listed below for the period from September 2017 through September 2018.

(1) Unit 1, Emergency AC power system (MS06)

(2) Unit 2, Emergency AC power system (MS06)

(3) Unit 1, High pressure injection system (MS07)

(4) Unit 2, High pressure injection system (MS07)

(5) Unit 1, Cooling water system (MS10)

(6) Unit 2, Cooling water system (MS10)

71152 - Problem Identification and Resolution Semiannual Trend Review

The inspectors reviewed the PSEGs corrective action program for trends that might be indicative of a more significant safety issue.

71153 Follow-up of Events and Notices of Enforcement Discretion Licensee Event Reports

The inspectors evaluated the following licensee event reports which can be accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx:

(1) LER 05000272/2016-006-01 Technical Specification (TS) for Containment Integrity Not Met (ADAMS accession: ML17319A152)

The circumstances surrounding this LER are documented in Inspection Report 05000272/2017-003 Section 1R15.2.

INSPECTION RESULTS

Licensee Identified Non-Cited Violation 71152 This violation of very low safety significant was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a Non-Cited Violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: Salem Nuclear Generating Station, Unit No. 1 Renewed License No. DPR-70, Condition 2.C.11.b.3 and Salem Nuclear Generating Station, Unit No. 2 Renewed License No. DPR-75, Condition 2.C.27.b.3 requires, in part, that no disbursements or payments from the [decommissioning] trust shall be made by the trustee until the trustee has first given the NRC 30 days notice of the payment.

Contrary to the above, on occasions between 2001 and 2015, disbursements from the Hope Creek Generating Station decommissioning trust were made by the trustee and the trustee had not first given the NRC 30 days notice of the payment. Specifically, in 2001, 2012, and 2015, PSEG directed the Bank of New York Mellon (the trustee of the decommissioning trust for Hope Creek Generating Station) to disburse payments equaling $240,449.04 for decommissioning cost estimates. However, PSEG failed to notify the NRC of these disbursements until October 19, 2018 (ML18295A023).

Significance/Severity: This issue is considered within the traditional enforcement process because the failure to inform the NRC prior to disbursing decommissioning funds impacts the ability of the NRC to perform its regulatory oversight function. As noted in Section 2.2.4 of the NRC Enforcement Policy, such violations are dispositioned using traditional enforcement.

The inspectors evaluated the violation in accordance with the NRC Enforcement Policy and determined that it is appropriately characterized at Severity Level IV (SL IV) because it is similar to the SL IV example violation 6.9.d.7, describing a licensees failure to provide or make a 15-day or 30-day written report or notification that does not impact the regulatory response by the NRC. For this Salem issue, the inspectors determined that the disbursements were made for acceptable decommissioning expenses and would not have necessitated further inquiry or caused the NRC to object to the payments.

Corrective Action Reference: Notification 20808984 71152 Observation Semiannual Trend Review The inspectors evaluated a sample of notifications (NOTFs) over the past two quarters to identify trends that might indicate the existence of a more significant safety issue, and to identify potential adverse trends in systems, structures, and components (SSCs). The inspectors determined that PSEG personnel were appropriately identifying trends. During the inspection, the inspectors identified a potential adverse trend in procedure use and adherence across several different site departments based on the following minor issues:

August 24 - Supplemental workers signed off on a leak injection step for completion of an item that did not exist. (20802380)

August 27 - Mechanical technicians used the wrong procedure section and therefore a higher, incorrect torque value during Fuel Handling ventilation damper assembly that caused the center bar to shear and eject under spring force and required rework. (20803019)

September 13 - An engineer manipulated a Feedwater regulating valve (FRV) linkage arm that had misaligned without a procedure. (20801852)

September 19 - Instrument and control (I&C) technicians installed a shaft collar on a FRV that was not part of temporary configuration change package instructions. (20804188)

October 15 - I&C technicians incorrectly justified the N/A of a step given plant conditions that resulted in the automatic start of the 22 AFW pump. (20807482)

October 25 - Supplemental workers incorrectly N/Ad parts of a procedure that resulted in over-torque of a CCW motor-operated valve during a subsequent stroke and required rework.

(20808333)

October 31 - Supplemental workers installed a Spent Fuel Pool cooling jumper on the incorrect side of a breaker connection and required rework. (20809695)

November 7 - During the 2R23 1000 psig walk-down, an active leak was identified at the 24 reactor coolant pump seal water injection bypass line vent valve. PSEG attributed the apparent cause to inadequate procedure use and adherence. (20810767)

November 20 - Fire protection operators partially performed a two-part step that resulted in six fire dampers tripping closed and required fire watches for the impairments. (20812894)

December 12 - When placing a Unit 2 cation bed demin in service for lithium control in accordance with the system operating procedure, an equipment operator incorrectly manipulated a vent valve that transferred 1100 gallons of RCS to the waste holdup system at a rate of 84 gpm. The valve was reclosed approximately 13 minutes later. (20814748)

The inspectors noted that the issues applied to a number of site departments and therefore warranted additional attention. PSEG documented this in their CAP as NOTF 20816452 for station review.

EXIT MEETINGS AND DEBRIEFS

• On October 30, 2018, the inspector presented the inservice inspection and post license renewal results to PSEG staff and managers. The inspector verified that no proprietary information was retained.

• On November 2, 2018, the inspector presented the radiation safety inspection results to Mr. C. McFeaters, Salem Vice President, and other members of the licensee staff. The inspectors confirmed that proprietary information was controlled to protect from public disclosure.

• On January 10, 2019, the inspectors presented the quarterly resident inspector inspection results to Mr. Charles McFeaters, Salem Vice President, and other members of the PSEG staff.

DOCUMENTS REVIEWED

71111.01 - Adverse Weather Protection

Notifications (*initiated in response to inspection)

20799478*

20816657*

Procedures

SC.OP-AM.FLX-0050, Predicted Hurricane Storm Surge, Revision 2

71111.04 - Equipment Alignment

Completed Surveillances

S2.OP-ST.AF-0005, Inservice Testing Aux Feed Water Valves Modes 4-6, performed 11/7/18

S2.OP-ST.AF-0006, Inservice Testing Aux Feed Water Valves, performed 11/13/18

Drawings

205332, Residual Heat Removal, Revision 38

205333, Spent Fuel Cooling, Revision 29

205336, No. 2 Unit Auxiliary Feedwater, Revision 53

Miscellaneous

S2 Equipment Off Normal Report, dated 11/16/18

S2 Equipment Off Normal Tagged Report, dated 11/16/18

Notifications (*initiated in response to inspection)

20762074 20810547* 20810906 20812862*

20799420 20810656 20811042 20813027*

20809720 20810724* 20812859*

20809715* 20810905 20812860*

Procedures

S2.OP-SO.AF-0001, Auxiliary Feedwater System Operation, Revision 43

Work Orders

30177053 30285580 30310961 50154569

71111.05 - Fire Protection

Calculations

S-1-FP-FDC-2202, Combustible Loading Calculation for Fire Area 1FA-AB-84A, Revision 0

S-1-FP-FDC-2199, Combustible Loading Calculation for Fire Area 1FA-AB-64A, Revision 0

S-2-FP-FDC-2254, Combustible Loading Calculation for Fire Area 2FA-DG-100D, Revision 0

Miscellaneous

FP-SA-1531, Salem Pre-Fire Plan - U/1 4160V Switchgear & Battery Rooms El. 64, Revision 0

FP-SA-1541, Salem Pre-Fire Plan - U/1 460V Switchgear Rooms & Corridor El. 84, Revision 0

FP-SA-2555, Salem Pre-Fire Plan - U/2 Diesel Generator Area El. 100, Revision 0

Notifications (*initiated in response to inspection)

20799936* 20811947* 20811968* 20812729*

Procedures

FP-AA-011, Control of Transient Combustible Material, Revision 5

FP-SA-003, Actions for Inoperable Fire Protection - Salem Station, Revision 5

SC.FP-SV.ZZ-0058, Inspection of Class 1 Fire Doors and Safety Related Areas for Transient

Combustibles, Revision 22

Work Orders

270183

275135

71111.07 - Heat Sink Performance

Notifications

20807809

20808232

Work Orders

30310512

7111108P - Inservice Inspection and 71003 - Post-Approval Site Inspection For License

Renewal

Miscellaneous

AREVA Inc. Engineering Information Record Document No.: 51 - 9266511 - 001 Salem 2R22

Degradation Assessment - Spring 2017

AREVA Inc. Engineering Information Record Document No.: 51 - 9272400 - 000 Salem Unit 2

Steam Generator Condition Monitoring for 2R22 and Final Operational Assessment for

Cycles 23, 24, and 25

FASA / FBM Report, LS-AA-126-F4 Rev 0, 70162988, 09/30/2014, Inservice Inspection (ISI)

Program FASA, Station: PSEG Nuclear (Salem and Hope Creek) (Focused Area

Self-Assessment)

Order 000070195677 Operation 0020 Confirmation 0014792464 Confirmation counter

00000002, Review of NRC Information Notice 17-01 indicates low risk of CRDM

Housing Vent Plug leakage at Salem

Ultrasonic Test Report, 50182341, Component 4-PS-1211-23

Steam Generator Degradation & Operational Assessment Validation Technical Evaluation Order

80122740

Worksheet for Selection of Encoded vs. Non-Encoded UT Technology for Dissimilar Metal Weld

Examination, Weld 29-RC-1210-1 and 29-RC-1220-1

Order 000070190624 Operation 0060 Confirmation 0014888704, Add RCS leakage to CRDM

Cable Insp Scope

PSEG NUCLEAR L.L.C Salem Common Engineering Services ER-AP-330-1001 - Revision 5

Alloy 600 Management Plan

PSEG NUCLEAR L.L.C Salem Common Engineering Oversight ER-AP-331 - Revision 7 BORIC

Acid Corrosion Control (Bacc) Program

CISI-SC-LTP2-TOC Revision 2, Salem Generating Station Units 1 & 2 Containment Inservice

Inspection (CISI) Program Plan Second Ten-Year Inspection Interval

PSEG NUCLEAR L.L.C Salem and Hope Creek Common Corporate Engineering Services

ER-AA-330 - Revision 12 Conduct Of Inservice Inspection Activities

PSEG NUCLEAR L.L.C Salem Common Equipment Reliability Program Engineering

ER-AP-333, Revision 1 Pressurized Water Reactor Vessel Internals Aging Management

Program

ER-AA-330-007 Revision 9, PSEG NUCLEAR L.L.C. Visual Examination Of Section Xi Class

Mc Surfaces And Class CC Liners

ER-AA-330-005 Revision 10, PSEG NUCLEAR L.L.C. Visual Examination Of Section Xi Class

CC Concrete Containment Structures

NRC to PSEG Nuclear LLC, April 18, 2013, Salem Nuclear Generating Station, Unit No.2 -

Safety Evaluation Of Relief Request No. S2-14r-123 Regarding The Fourth 10-Year

Inservice Inspection Interval (TAC NO. ME8847)

ER-AA-330-005 Revision 10 Visual Examination Of Section Xi Class Cc Concrete Containment

Structures

Report No. 0901179.404, Revision 0, Project No. 0901179, April 2013, Risk-Informed Inservice

Inspection Interval Evaluation for Salem Generating Station Unit 2

Liquid Penetrant Examination, 573390/50182341

Multiple Weld History Record: 80418, Order #: 60135577, S2-KNUCKLE-78 WELD BUILDUP

Multiple Weld History Record: 80411, Order #: 60135577, WELD I.D.: S2-60135577-TEST

BOX-FW1 TO FW4

Ultrasonic Examination Report S2-004620, Weld 29-RC-1220-1

Ultrasonic Examination Report S2-004630, Weld 29-RC-1210-1

Commercial Change Package 80121603 Salem Switchyard Dewatering project - Mechanical

& Civil/Structural Scope

Commercial Change Package 80121604 Salem Switchyard Dewatering project - Electrical

Scope

Multiple Weld History Record: 80411, Weld I.D.: S2-60135577-Test Box-FW1 TO FW4*,

SALEM 2 CONTAINMENT 100' Liner Plate Repair

Multiple Weld History Record: 80418, Weld I.D.: S2-Knuckle-78 Weld Buildup, Salem 2

Containment 78' Knuckle Plate

Drawings

203000 S 8789-70 No. 1 and No. 2 Units Generators and Main Transformers One Line Control

205420 A 8765-34 Salem Nuclear Switching Station, 500KV Switchyard, Cable Trench,

Conduits, and Lighting

264901 A 2126-2 13KV South Substation Bus Plan

Notifications

20796846 20795460 20740531 20800332

20806851 20794692 20806851 20799892

20797354 20793553 20796846 20793715

20740531 20793263 20808113 20793189

20788433 20788164 20808656 20793191

20751387 20786449 20807736 20791975

20751323 20783302 20807735 20784509

20751220 20790836 20807503 20808931

20750086 20790707 20750603 20807503

20750084 20790716 20806424 20808186

20802005 20797354 20796243 20807460

Work Orders

201609 60138288 60110275 60121591

200947 60138233 30253047 60108481

60136309 60139561 60110254 60100159

60137335 60109316 60110581 60114932

60137909 60113259 60114132

71111.11 - Licensed Operator Requalification Program

Procedures

NF-AP-543, Beacon Estimated Critical Condition (ECC) Calculation, Revision 8

S2.OP-IO.ZZ-0003, Hot Standby to Minimum Load, Revision 46

S2.OP-IO.ZZ-0103, Hot Standby to Minimum Load Administrative Requirements, Revision 13

SC.RE-IO.ZZ-0002, Low Power Physics Testing and Power Ascension, Revision 20

SC.RE-RA.ZZ-0002, Inverse Count Rate Ratio During Reactor Startup, Revision 12

SC.RE-ST.ZZ-0013, Initial Criticality and Testing Advanced Digital Reactivity Computer,

Revision 22

71111.12 - Maintenance Effectiveness

Completed Surveillances

S2.OP-ST.DG-0005, 22 Fuel Oil Transfer System Operability Tes, performed 11/10/18

Notifications (*initiated in response to inspection)

20699313 20808653 20776183 20808971

20710872 20764722 20803845 20810709

20715499 20765029 20804790 20813025*

20762826 20769477 20804810

Work Orders

206495 30219066 30302710 70203109

206906 30219333 60127383

206922 30220323 60137362

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Calculations

S-C-RC-MDC-1911, Analysis of RCS Fill and Vent Piping Modification, Revision 0

Evaluations

80118806, Outage 2R23 Shutdown Safety Evaluation and Approval, dated 9/29/18

Notifications (*initiated in response to inspection)

20799942* 20807480 20810744*

20807482 20810724* 20811624

20807077 20810725* 20813929*

Procedures

OP-AA-108-116, Protected Equipment Program, Revision 12

S2.OP-SO.RC-0002, Vacuum Fill of the RCS, Revsion 37

S2.OP-SO.RC-0006, Draining the Reactor Coolant System Less Than 101 FT EL with Fuel in

the Vessel, Revsion 40

S2.OP-ST.CAN-0007, Refueling Operations - Containment Closure, Revsion 30

71111.15 - Operability Determinations and Functionality Assessments

Notifications (*initiated in response to inspection)

20799821* 20810351 20811243* 20811643

20811828* 20810352 20813764*

Work Orders

60140541

203667

Other

S1-SURV-010, Risk Assessment of Missed Surveillance - Turbine Overspeed Test, Revision 0

WCAP-16054-P, Probabilistic Analysis of Reduction in Turbine Valve Test Frequency for

Nuclera Plants with Siemens-Westinghouse BB-95/96 Turbines, April 2003

WCAP-11525, Probabilistic Evaluation of Reduction on Turbine Valve Test Frequency,

June 1987

71111.18 - Plant Modifications

Notifications (*initiated in response to inspection)

20807069*

71111.19 - Post-Maintenance Testing

Completed Surveillances

S2.OP-ST.DG-0003, 2C Diesel Generator Surveillance Test, performed 11/8/18

Notifications

20804901 20804750 20808333

20804102 20810709 20810678

20803972 20809696 20811332

Procedures

SC.MD-CM.RC-0004, PR1, PR2, and CV2 Valves Overhaul/Repacking, Revision 16

MA-AA-716-012, Post-Maintenance Testing, Revision 20

ER-AA-302, Motor-Operated Valve Program Engineering Procedure, Revision 7

Work Orders

204827 60140803 60111177

60139650 30166226

71111.20 - Refueling and Other Outage Activities

Miscellaneous

OP-AP-300-1003 Attachment 1, Salem 2 Cycle 24 BOC Startup and Power Ascension

Reactivity Maneuver Plan, dated 11/7/18

Notifications (*initiated in response to inspection)

20682685 20810550* 20810875* 20811841

20806864* 20810694* 20811645 20812727*

20807065* 20810868* 20811648 20812861*

20807437* 20810874* 20811827* 20813024*

Procedures

2-EOP-TRIP-1, Reactor Trip or Safety Injection, Revision 33

2-EOP-TRIP-2, Reactor Trip Response, Revision 33

S2.OP-IO.ZZ-0004, Power Operation, Revision 81

S2.OP-IO.ZZ-0005, Minimum Load to Hot Standby, Revision 25

S2.OP-IO.ZZ-0006, Hot Standby to Cold Shutdown, Revision 48

S2.OP-SO.RHR-0001, Initiating RHR, Revision 29

Other

CLP Salem 2 April 2018, Revision 8

Salem 2 Move Sheet package, Report 513, S2R23 Core Reload Using N31/32 Indications

71111.22 Surveillance Testing

Notifications (*initiated in response to inspection)

20654970 20806071 20647175 20762363

20807629* 20809202* 20708157 20807413

Procedures

S2.OP-ST.DG-0012, 2A Diesel Generator Endurance Run, Revision 26

S2.OP-ST.AF-0007, Inservice Testing Auxiliary Feedwater Valves Modes 1-3, Revision 23

S2.OP-LR.CVC-0004, Type C Leak Rate Test 21CV99, Revision 1

S2.OP-SO.CVC-0012, CVCS Demineralizer Normal Operations, Revision 34

Work Orders

203044 50205365 50194605

206250 50194482 50196304

205352 50194486 50195415

Other

TS 3.4.7.2

71151 - Performance Indicator Verification

Other

Unavailability and Unreliability Indeces for MSPIs

71152 - Problem Identification and Resolution

Notifications (*initiated in response to inspection)

20806821* 20811243* 20813601*

20809849* 20813764*

Procedures

AD-AA-101-1005, Procedure Revision Priority Coding and Expectations, Revision 1

Other

PSEG Nuclear: Salem Station October Metrics