IR 05000272/2020011

Design Basis Assurance Inspection (Teams) Inspection Report 05000272/2020011 and 05000311/2020011

ML20044C865
Person / Time
Site:	Salem
Issue date:	02/12/2020
From:	Mel Gray NRC Region 1
To:	Carr E Public Service Enterprise Group
References
IR 2020011
Download: ML20044C865 (12)

Text

ary 12, 2020

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000272/2020011 AND 05000311/2020011

Dear Mr. Carr:

On January 30, 2020, 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 Mr. Charles McFeaters and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Mel Gray, Chief Engineering Branch 1 Division of 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: 05000272/2020011 and 05000311/2020011 Enterprise Identifier: I-2020-011-0004 Licensee: PSEG Nuclear, LLC.

Facility: Salem Nuclear Generating Station, Units 1 and 2 Location: Hancocks Bridge, NJ Inspection Dates: January 13, 2020 to January 30, 2020 Inspectors: C. Baron, Contractor J. DeBoer, Reactor Inspector A. Della Greca, Contractor J. Kulp, Senior Reactor Inspector A. Patel, Senior Reactor Inspector J. Schoppy, Senior Reactor Inspector Approved By: Mel Gray, Chief Engineering Branch 1 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) 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 - Design Bases Assurance Inspection (Teams)

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

Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02)

=

(1) 1B Emergency Diesel Generator (Mechanical)

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents/procedures

• System health report, maintenance effectiveness and records, and corrective action history

• Design calculations

• Surveillance testing and recent test results

• Equipment protection from fire, flood, and water intrusion or spray

• Heat removal cooling water and ventilation

• Energy sources, fuel and air (e.g., engine start, operation, and control)

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

(2) Unit 2 Motor Driven Auxiliary Feedwater Pump

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents and procedures

• System health report, maintenance effectiveness and records, and corrective action history

• Equipment/environmental controls and qualification

• Operator actions

• Design calculations

• Surveillance testing and recent test results

• Range, accuracy, and setpoint of installed instrumentation

• Equipment protection from fire, flood, and water intrusion or spray

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

(3) 1B 4KV Switchgear

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents and procedures

• System health report, maintenance effectiveness and records, and corrective action history

• Switchgear bus, breaker, and cable sizing

• Control logic and control power adequacy

• Equipment vendor documentation

• Environmental controls and seismic qualification

• Operator actions

• Transformer tap settings and degraded grid/voltage drop calculation

• Load flow analysis

• Adequacy of electrical power supply for motor and controls

• Short circuit calculation

• Overload and short circuit protective relays setting

• Protection coordination, load in-rush and full load current

• Range, accuracy, and setpoint of installed instrumentation

• Technical Specification required surveillance testing and recent test results

• Component adequacy for minimum voltage The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.

(4) 11CC16 Residual Heat Removal Heat Exchanger Component Cooling Water Isolation Motor Operated Valve

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents and procedures

• System health report, maintenance effectiveness and records, and corrective action history

• Control logic

• Equipment/environmental controls and qualification

• Operator actions

• Design calculations

• Surveillance testing and recent test results

• Adequacy of electrical power supply for motor and controls

• Thermal overload protection settings

• Protection coordination; Load in-rush and full load current

• Equipment protection from fire, flood, and water intrusion or spray

• Heat removal cooling water and ventilation

• Contactor and fuse ratings; Component adequacy for minimum voltage

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

Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) (1 Sample)

(1) Unit 1 Containment Pressure and Vacuum Relief Isolation Valves (1VC5 and 1VC6)

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents and procedures

• Maintenance records and corrective action history

• Control logic

• Equipment/environmental controls and qualification

• Operator actions

• Design calculations

• Surveillance testing and recent test results

• Adequacy of electrical power supply for motor and controls

• Range, accuracy, and setpoint of installed instrumentation

• Heat removal cooling water and ventilation

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

Modification Review - Permanent Mods (IP Section 02.03) (5 Samples)

(1) 80111452, Salem 2 Nuclear Instrumentation Upgrade

(2) 80109929, Mitigating Systems Performance Indicator Non-Safety Related Auxiliary Feedwater Pump Modification

(3) 80116286, Auxiliary Feedwater Room Cooler Controls Replacement

(4) 80116637, Unit 2 Solid State Protection System Train A Wiring Rework Per TB-13-7

(5) 80110461, 11, 21, & 22 Service Water Return Header Review of Operating Experience Issues (IP Section 02.06) (3 Samples)

(1) NRC Information Notice 19-02, Emergency Diesel Generator Excitation System Diode Failures, dated June 3, 2019

(2) NRC Information Notice 15-01, Degraded Ability to Mitigate Flooding Events, dated January 9, 2015

(3) NRC Information Notice 19-08 Flow Accelerated Corrosion Events, dated October 8,

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On January 30, 2020, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. Charles McFeaters and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21M Calculations 317099(15)-01 Weak Link and Seismic Analysis Reports Revision 1

ES-13-006(Q) Breaker and Relay Coordination Calculation Safety-Related Revision 3

AC System

ES-15.017(Q) Salem Unit 1 & 2 Analytical Voltage Analysis Revision 3

S-C-CAN-MDC- Minimum Containment Air Pressure Prior to a LOCA Revision 1

2144

SC-CBV006-01 Containment Building Differential Pressure Indication LOOP Revision 3

Uncertainty

Corrective Action 20839697

Documents 20843273

Resulting from 20843274

Inspection 20843289

20843418

20843489

20843617

20843640

20843676

20843677

20843680

20843689

20843759

20843800

20843808

20843831

20843835

20843837

20843849

20843904

20843905

20843906

20843907

Inspection Type Designation Description or Title Revision or

Procedure Date

20843908

20843962

20843974

20843982

20844003

20844005

20844017

20844059

20844060

20844105

20844131

20844146

20844147

20844154

20844157

20844157

20844165

20844171

20844181

20844182

20844194

20844197

20844240

20844244

20844252

20844264

20844321

20844322

Engineering 80096586 Unit 1 & Unit 2 SSPS Circuit Card Upgrade Revision 2

Changes 80109929 Mitigating Systems Performance Indicator Non-Safety Revision 1

Related Auxiliary Feedwater Pump Modification

80110461 11, 12, 21, and 22 Service Water Nuclear Return Header Revision 2

Isolation Valve, Access Branch, and WEKO Seal

Inspection Type Designation Description or Title Revision or

Procedure Date

80110461 No. 11, 12, 21, and 22 Service Water Nuclear Return Revision 1

Header Isolation Valve and Access Branch Pipe and WEKO

Seal Installation 50.59 Review

80111452 Salem 2 Nuclear Instrumentation Upgrade Revision 2

80116286 Auxiliary Feedwater Room Cooler Controls Replacement Revision 0

80116637 Unit 2 SSPS Train A Wiring Rework per TB-13-7 Revision 0

Miscellaneous IST-SC-INT5 Inservice Testing Program Plan Valve Test Table Revision 0

Table 3-1

LR-N-17-006 PSEG Letter to USNRC, Focused Evaluation of External 6/30/2017

Flooding for Salem Generating Station, Units 1 and 2"

S1.0P-ST.DG- 1B Diesel Generator Endurance Run 4/11/2019

0013

TB-13-7 Westinghouse Technical Bulletin, SSPS New Design 12/10/2013

Universal Logic Board and Safeguards Driver Board 48 VDC

Input

Procedures ER-AA-430 Conduct of Flow Accelerated Corrosion Activities Revision 9

ER-AA-430-1001 Guidelines For Flow Accelerated Corrosion Activities Revision 11

OP-AA-102-106 Operator Response Time Program Revision 0

S1.MD-FT.4KV- ESFAS Instrumentation Functional Test 1B 4KV Vital Bus Revision 31

0002(Q) Undervoltage

S1.OP-AB.LOCA- Shutdown LOCA Revision 7

0001(Q)

S1.OP-AB.ZZ- Flooding Revision 4

0002

S1.OP-SO.CBV- Containment Pressure - Vacuum Relief System Operation Revision 21

0002

S1.OP-SO.DG- 1B Diesel Generator Operation Revision 41

0002

S1.OP-ST.4KV- Electrical Power Systems, 4KV Vital Bus Transfer Revision 16

0001(Q)

S1.OP-ST.CBV- Inservice Testing Containment Ventilation Valves Revision 8

0001

S1.RA-ST.CBV- Inservice Testing Containment Valves Acceptance Criteria Revision 18

0001

Inspection Type Designation Description or Title Revision or

Procedure Date

S2.OP-ST.AF- Inservice Testing- 22 Auxiliary Feedwater Pump Revision 18

0002(Q)

SC.OP-PT.AF- Testing the MSPI Pump and Diesel Revision 0

0001(Z)

Work Orders 60142009

209851

10