IR 05000272/2023011

Comprehensive Engineering Team Inspection Report 05000272/2023011 and 05000311/2023011

ML23066A013
Person / Time
Site:	Salem
Issue date:	03/07/2023
From:	Mel Gray Division of Operating Reactors
To:	Carr E Public Service Enterprise Group
References
IR 2023011
Download: ML23066A013 (1)

Text

March 7, 2023

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 -

COMPREHENSIVE ENGINEERING TEAM INSPECTION REPORT 05000272/2023011 AND 05000311/2023011

Dear Eric Carr:

On February 9, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Salem Nuclear Generating Station, Units 1 and 2 and discussed the results of this inspection with R.J. DeSanctis, Jr., 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 (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Mel Gray, Chief Engineering Branch 1 Division of Operating Reactor Safety

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

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000272 and 05000311

License Numbers:

DPR-70 and DPR-75

Report Numbers:

05000272/2023011 and 05000311/2023011

Licensee:

PSEG Nuclear, LLC

Facility:

Salem Nuclear Generating Station

Location:

Hancocks Bridge, NJ

Inspection Dates:

January 23, 2023 to February 9, 2023

Inspectors:

J. Brand, Reactor Inspector

J. Kulp, Senior Reactor Inspector

N. Mentzer, Resident Inspector

E. Miller, Reactor Inspector

J. Rady, Senior Reactor Inspector

J. Schoppy, Senior Reactor Inspector

A. Turilin, Reactor Inspector

Approved By:

Mel Gray, Chief

Engineering Branch 1

Division of Operating Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Comprehensive Engineering Team Inspection Report at Salem Nuclear Generating 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.

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.

REACTOR SAFETY

===71111.21M - Comprehensive Engineering Team Inspection

The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:

Structures, Systems, and Components (IP section 03.01)===

For each component or operator action sample listed below, the team reviewed licensing and design basis documents and a sampling of applicable operator actions, periodic testing results, corrective action program documents, internal and external operating experience, preventive and corrective maintenance work orders, modifications, and aging management programs. Additionally, the team performed walkdowns of the component or procedure and conducted interviews with licensee personnel.

The team used the attributes contained in IP 71111.21M, Appendix A, Component Review Attributes, such as those listed below as guidance. Specifically, the team evaluated these attributes in the course of applying 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M, Appendix C, Component Walkdown Considerations.

(1)12 Service Water Pump

• Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.

• Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Component controls will be functional and provide desired control during accident/event conditions.

• Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.

• Instrumentation and alarms are available to operators for making necessary decisions.

• Heat will be adequately removed from major components.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Performance capability of selected components have not been degraded through modifications.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

• Equipment qualification is suitable for the environment expected under all conditions.

• Equipment is adequately protected from environmental hazards.

The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.

(2) Risk Significant Operator Action: Bleed and Feed (Response to Loss of Secondary Heat Sink) and Associated Structures, Systems, and Components

• Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.

• Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Component controls will be functional and provide desired control during accident/event conditions.

• Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.

• Instrumentation and alarms are available to operators for making necessary decisions.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Performance capability of selected components have not been degraded through modifications.

• Potential degradation is monitored or prevented.

• Equipment is adequately protected from environmental hazards.

The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.

(3) Non-Safety-Related Auxiliary Feedwater (AFW) Pump and Diesel

• Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.

• Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Component controls will be functional and provide desired control during accident/event conditions.

• Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.

• Instrumentation and alarms are available to operators for making necessary decisions.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Performance capability of selected components have not been degraded through modifications.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

• Equipment qualification is suitable for the environment expected under all conditions.

• Component inputs and outputs are suitable for application and will be acceptable under accident/event conditions.

The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.

(4) Unit 1 1A Emergency Diesel Generator (1DAE4)

• Energy sources (fuel, air and electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Component controls will be functional and provide desired control during accident/event conditions.

• Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Performance capability of selected components have not been degraded through modifications.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Component inputs and outputs are suitable for application and will be acceptable under accident/event conditions.

The team used Appendix B guidance for Valves, Pumps, Instrumentation, Electrical Loads and As-Built System.

(5) Unit 1 1A 4kV Switchgear (S14KV-1SWGR1AD)

• Energy sources (electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Instrumentation and alarms are available to operators for making necessary decisions.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

• Component inputs and outputs are suitable for application and will be acceptable under accident/event conditions.

The team used Appendix B guidance for Valves, Pumps, Instrumentation, Electrical Loads and As-Built System.

(6) S128D-1BTRY1ADE - Unit 1 28VDC Battery, Charger, and Switchgear

• Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.

• Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Heat will be adequately removed from major components.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Performance capability of selected components have not been degraded through modifications.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

• Equipment qualification is suitable for the environment expected under all conditions.

• Equipment is adequately protected from environmental hazards.

• Component inputs and outputs are suitable for application and will be acceptable under accident/event conditions.

The team used Appendix B guidance for Valves, Pumps, Instrumentation, Electrical Loads and As-Built System.

(7) Time sensitive operator action - DC Load Shedding (EOP-LOPA-1) and Associated Structures, Systems, and Components

• Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Component controls will be functional and provide desired control during accident/event conditions.

• Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.

• Instrumentation and alarms are available to operators for making necessary decisions.

• Heat will be adequately removed from major components.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Performance capability of selected components have not been degraded through modifications.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

• Equipment qualification is suitable for the environment expected under all conditions.

• Equipment is adequately protected from environmental hazards.

The team used Appendix B guidance for Valves, Pumps, Instrumentation, Electrical Loads and As-Built System.

(8)23 Turbine Driven Auxiliary Feedwater Pump

• Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.

• Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Heat will be adequately removed from major components.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Performance capability of selected components have not been degraded through modifications.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

• Equipment is adequately protected from environmental hazards.

The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.

(9)22MS10 Main Steam Atmospheric Relief Valve

• Energy sources (air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.

• Component controls will be functional and provide desired control during accident/event conditions.

• Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.

• Instrumentation and alarms are available to operators for making necessary decisions.

• Heat will be adequately removed from major components.

• Installed configuration will support its design basis function under accident/event conditions.

• Component operation and alignments are consistent with design and licensing basis assumptions.

• Design bases and design assumptions have been appropriately translated into design calculations and procedures.

• Performance capability of selected components have not been degraded through modifications.

• Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.

• Tests and/or analyses validate component operation under accident/event conditions.

• Potential degradation is monitored or prevented.

• Equipment qualification is suitable for the environment expected under all conditions.

• Equipment is adequately protected from environmental hazards.

• Component inputs and outputs are suitable for application and will be acceptable under accident/event conditions.

The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.

Modifications (IP section 03.02) (5 Samples)

(1) ECP 80119413, Emergency Diesel Generator Field Flash Relay, Revision 1

(2) ECP 80111590, Replace SW EDG Supply Valves - SW21s, Revision 1

(3) ECP 80122162, Remove Automatic Rod Control, Revision 0

(4) ECP 80127591, TDAFP Pump Recirc Line Relief Valve Lifting [1(2)AF128],

Revision 0

(5) ECP 80123050, Salem 1&2 MS10 Valves Positioner Upgrade, Revision 1

10 CFR 50.59 Evaluations/Screening (IP section 03.03) (13 Samples)

(1) S2022-089, 50.59 review for procedure Revision S1(2).OP-AB.CN-0001(Q),

Revision 0

(2) S2021-101, DCP 80126494 Salem Unit 2 Up-flow Conversion and eLBB Implementation, Revision 0

(3) S2021-109, Containment Ventilation Operation 50.59 Screen, Revision 0

(4) S2019-222, Salem 1 & 2 MS10 Valves Positioner Upgrade, Revision 1

(5) S2022-118, Procedure Revisions S1(2).OP-AB.LOOP-0001 R35(R33), Revision 0

(6) S2022-111, Procedure Revisions - 125VDC Battery Operations, Revision 0

(7) S2018-063, Remove Auto Rod Withdrawal, Revision 0

(8) S2022-003, Generic Rosemount Transmitter Equivalent Change, Revision 0

(9) S2021-122, Procedure Revision - S2.OP-AB.SF-0001, Spent Fuel Pool Peak Temperature at Various In-Vessel Decay Times and Temperatures, Revision 0

(10) S2022-012, Reactor Coolant Pump Abnormality 50.59 Screen, Revision 0

(11) S2022-072, 1(2)RH21 Leakby (RWST Back-Leakage) 50.59 Evaluation, Revision 0

(12) S2022-065, Receipt of Bulk Chemical Trucks - SC.CH-GP.ZZ-2470 (Z), Revision 0

(13) S2021-117, Salem Unit 3 Gas Turbine (Jet) Interim Abandonment, Revision 0

Operating Experience Samples (IP section 03.04) (2 Samples)

(1) NRC Information Notice 2021-03, Operating Experience Related to the Duane Arnold Energy Center Derecho Event on August 10, 2020, dated August 11, 2021

(2) NRC Information Notice 2020-02, Flex EDG Operational Challenges, dated September 15,

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On February 9, 2023, the inspectors presented the Comprehensive Engineering Team Inspection results to R.J. DeSanctis, Jr., and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21M Calculations

ES-15.009

Study to Increase the 125V DC Battery Margin

Revision 15

ES-3.002(Q)

Volt DC Battery and Battery Charger Sizing Calculation

Revision 5

S-C-AF-MDC-

0432

Auxiliary Feedwater Pump NPSH

Revision 1

S-C-SW-MDC-

1350

Service Water System MODE OPS Analysis

Revision 9

S-C-SW-MDC-

1967

Service Water System Thermal Hydraulic Model

Revision 11

Corrective Action

Documents

20777337

20861944

20867126

20884341

Corrective Action

Documents

Resulting from

Inspection

20925886

20925899

20925918

20925919

20925920

20926157

20926165

20926173

20926182

20926183

20926184

20926185

20926186

20926191

20926203

20926277

20926279

20926280

20926291

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

20926294

20926296

20926428

20926429

20926430

20926443

20926457

20926458

20926459

20926460

20926461

20926486

20926523

20926552

20926572

20926599

20926605

20926606

20926610

20926611

20926625

20926626

20926627

20926635

20926772

20926775

20926792

20926874

20927031

20927042

20927044

20927051

20927053

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

20927070

20927071

20927072

20927139

20927146

20927147

20927154

20927171

20927175

20927222

20927236

20927324

Engineering

Evaluations

VTD 314204

Station Blackout Analysis for Salem Units 1 and 2, Volume 1

Revision 5

WCAP-18659-P

Reactor Internals Up-flow Conversion Program Engineering

Report for Salem Nuclear Generating Station Unit 2

Revision 0

Miscellaneous

S1.OP-ST.SW-

0002

Inservice Testing - 12 Service Water Pump

2/17/2022

S2.OP-ST.AF-

0003(Q)

Inservice Testing - 23 Auxiliary Feedwater Pump

11/23/2022

Procedures

1-EOP-FRHS-1

Response to Loss of Secondary Heat Sink

Revision 42

1-EOP-LOPA-1

Loss of All AC Power

Revision 41

S1.OP-AB.LOOP-

0001

Loss of Offsite Power

Revision 35

S1.OP-SO.SW-

0001

Service Water Pump Operation

Revision 31

S1.OP-SO.SW-

0005

Service Water System Operation

Revision 53

S2.OP-AB.LOOP-

0001

Loss of Offsite Power

Revision 34

S2.OP-SO.MS-

0002

Steam Dump System Operation

Revision 14

S2.RA-ST.MS-

0002

Inservice Testing Main Steam and Main Feedwater Valves

Acceptance Criteria

Revision 22

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

SC.OP-AR.AF-

0001(Z)

MSPI emergency diesel generator Pump Diesel Alarm

Response

Revision 0

SC.OP-PT.AF-

0001(Z)

Testing the MSPI Pump and Diesel

Revision 1

SC.OP-SO.AF-

0001(Q)

Feed Steam Generators with MSPI AFW Pump

Revision 1

Work Orders

30344911

50171438

60149379