IR 05000272/2022001

Integrated Inspection Report 05000272/2022001 and 05000311/2022001

ML22124A025
Person / Time
Site:	Salem
Issue date:	05/04/2022
From:	Brice Bickett NRC/RGN-I/DORS
To:	Carr E Public Service Enterprise Group
Bickett B
References
IR 2022001
Download: ML22124A025 (10)

Text

May 4, 2022

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000272/2022001 AND 05000311/2022001

Dear Mr. Carr:

On March 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Salem Nuclear Generating Station, Units 1 and 2. On April 7, 2022, the NRC inspectors discussed the results of this inspection with Mr. Dave Sharbaugh, Site Vice President, 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 inspecti on.

This letter, its enclosure, and your response (if any) will be m ade available for public inspection and copying at http://www.nrc.gov/reading-rm /a dam s.h tm l 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, Brice A. Bickett, Chief Projects Branch 3 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: 05000272/2022001 and 05000311/2022001

Enterprise Identifier: I-2022- 001-0051

Licensee: PSEG Nuclear, LLC

Facility: Salem Nuclear Generating Station, Units 1 and 2

Location: Hancocks Bridge, NJ

Inspection Dates: January 1, 2022 to March 31, 2022

Inspectors: J. Dolecki, Senior Resident Inspector P. Finney, Senior Project Engineer M. Hardgrove, Resident Inspector G. Walbert, Reactor Engineer

Approved By: Brice A. Bickett, Chief Projects Branch 3 Division of Operating Reactor Safety

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licens ees performance by conducting an integrated inspection 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 h ttps://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.

PLANT STATUS

Salem Unit 1 and Unit 2 operated at or near rated thermal power for the entire 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 websi te a t http://www.nrc.gov/reading -

rm /doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requireme nts 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 activities described in IMC 2515, Appendix D, Plant Status, conducted routine reviews using IP 71152, Problem Identification and Resolution, observed risk significant activities, and completed on-site portions of IPs.

The inspectors reviewed selected procedures and records, observed activities, and interview ed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards

71111.04 - Equipm ent Alignment

Partial Walkdown Sample (IP Section 03.01) (4 Samples)

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

(1) Unit 2, service water bays 2 and 4 with 25 service water pump out of service for planned maintenance, on January 19, 2022

(2) Unit 1, 11 chilled water system during 12 chiller replacement, on February 8, 2022

(3) Unit 1, 1A emergency diesel generator, on February 28, 2022

(4) Unit 2, 23 turbine driven auxiliary feedwater (AFW) pump room and 22 AFW pump during 21 AFW pump in-service testing, on March 2, 2022

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Sam ples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Unit 1, diesel generator area in pre -fire plan FP-SA-1555, on January 4, 2022

(2) Unit 1, turbine building elevation 120', pre-fire plan FP-SA-1161, on January 6, 2022

(3) Unit 2, turbine building elevation 120', pre-fire plan FP-SA-2161, on January 6, 2022

(4) Unit 1, auxiliary building 84', fire areas 1FA-AB-84B and 1FA-AB-84C, on February 2, 2022

(5) Unit 1, 64' and 84' switchgear rooms, on February 2, 2022

(6) Unit 2, auxiliary building 84' and 10 ton CO2 tank room, fire areas 2FA-AB-84B and 2FA-DG-84F, on February 2, 2022

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Units 1 and 2, 13.8 kV cable vaults in switchyard, on March 23, 2022

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed Units 1 and 2 operations personnel during pre -refueling outage and surveillance activities, on March 14 and 16, 2022

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed a Unit 2 simulator evaluati on that included charging system leak, degraded turbine lube oil pressure, failure of 500 kV breaker, reactor trip, and small break loss of coolant without recirculation capability, on January 18, 2022

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (4 Sam ples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) Unit 2, emergent work on pressurizer power -operated relief valve block valve, 2PR7, following failure to reopen during surveillance testing, on January 25, 2022

(2) Unit 2, elevated risk during scheduled acti vities on 21 safety injection and 23 charging system s, on February 1, 2022

(3) Units 1 and 2, elevated risk during scheduled activity on 500 kV Bus Section 2, on February 9, 2022

(4) Unit 2, emergent work on pressurizer power -operated relief valve lines following elevated tailpipe temperature during planned 500 kV Bus Section 1 outage, during week of February 14, 2022

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (8 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Unit 1, 22 com ponent cooling water heat exchanger inlet valve (22SW122) flow oscillations following valve modification during refueling outage 2R25, on January 3, 2022 (Notification (NOTF ) 20888338)

(2) Unit 1, 1B emergency diesel generator due to degraded stroke time testing of service water isolation valve, 12SW39, on January 11, 2022 (NOTF 20894475)

(3) Unit 2, reactor coolant head vents due to part 21 regarding nonconformance of main disc lift misalignment, on January 19, 2022 (NOTF 20844061)

(4) Unit 2, performance of surveillance for core reactivity balance following 60 effective full power days due to missed surveillance and declaring Technical Specification 4.0.3, on January 19, 2022 (NOTF 20895239)

(5) Unit 2, pressurizer power-operated relief valve 2PR2 elevated tailpipe temperatures following seat leakage, on February 15, 2022 (NOTF 20897290)

(6) Unit 2, 22 service water strainer due to high internal clearances, on February 24, 2022 (Operability Engineering Justification (OEJ) 70221624)

(7) Unit 1, 12 chiller anchorage discrepancy due to stainless steel bolting, on February 28, 2022 (OEJ 70221911)

(8) Unit 1, 1C emergency diesel generator due to jacket water leakage during testing, on March 28, 2022 (Work Order (WO) 702105821)

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (3 Sam ples)

The inspectors evaluated the following post -maintenance testing activities to verify system operability and/or functionality:

(1) Unit 2, 23 containment fan coil unit pillow block bearing repacking, on January 19-20, 2022 (WO 40047349)

(2) Unit 2, adjustment to motor control center cabinet connections to repair degraded stroke time of pressurizer motor-operated block valve, 2PR7, on January 26, 2022 (WO 60152902)

(3) Unit 1, 1B emergency diesel generator service water inlet valve to cooler, 12SW39, repair to degraded stroke time, on March 7, 2022 (WO 60152748)

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:

Surveillance Tests (other) (IP Section 03.01) (2 Samples)

(1) Unit 1, S1.OP-S T. DG-0002, "1B Diesel Generator Surveillance Test," on January 10, 2022 (WO 50232812, 50231404, 50231410, and 50229673)

(2) Unit 1, S1.OP-S T. DG-0001(Q), "1A Diesel Generator Surveillance Test," on February 28, 2022 (WO 50232617 and 50230390)

RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) Unit 2, S2.OP-ST.RC-0008, Reactor Coolant System Water Inventory Balance, on March 14, 2022 (NOTF 20898459)

71114.06 - Drill Evaluation

Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated the emergency action level notification corresponding to the simulator-scenario conducted at Unit 2, on January 18, 2022

O T HE R ACT IVIT IES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (2 Sam ples)

(1) Unit 1, January 1, 2021 - December 31, 2021

(2) Unit 2, January 1, 2021 - December 31, 2021

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===

(1) Unit 1, January 1, 2021 - December 31, 2021

(2) Unit 2, January 1, 2021 - December 31, 2021

BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Sam ples)

(1) Unit 1, January 1, 2021 - December 31, 2021

(2) Unit 2, January 1, 2021 - December 31,

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On April 7, 2022, the inspector s presented the integrated inspection results to Mr. Dave Sharbaugh, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.05 Corrective Action *20894017 NRC - pre-fire plan discrepancy 01/06/2022

Docum ents

Resulting from

Inspection

71111.06 Work Orders 30355027-0060 1-year preventive maintenance 03/23/2022

71111.11Q Corrective Action *20895544 Revision request for TQ-AA-201, Exam Security and 01/25/2022

Docum ents Administration

Resulting from

Inspection

71111.13 Corrective Action 20897290 PZR Relief Valve Temp Rise 02/14/2022

Docum ents

Corrective Action *20897662

Docum ents

Resulting from

Inspection

Engineering 70222064 Elevated Tailpipe Temperature 2PR2 02/14/2022

Evaluations

71111.15 Corrective Action *20898239 Procedure OP-SA-108-115-1001, Operability Assessment and 02/26/2022

Docum ents Equipment Control Program, contains deficiency pertaining to

Resulting from 'operable but degraded'

Inspection

Engineering 70211325 Assessing safety hazard for 10CFR Part 21 Report, NID# 10/25/2021

Evaluations 20007, "Notification of a Defect, Unauthorized Modification of

a Valve Component and Main Disc Lift Misadjustment" for

Target Rock 1 and 2 solenoid operated valve assemblies."

Work Orders 60150500 Corrective action to replace reactor head vents 2RC40,

2RC41, 2RC42, and 2RC43

71111.22 Corrective Action 20898459 Nine consecutive RCS unidentified leakage rates above 03/05/2022

Docum ents quarterly average

Corrective Action 20898079 Jacket leak at L4 cylinder 02/28/2022

Docum ents

Resulting from

Inspection Type Designation Description or Title Revision or

Procedure Date

Inspection

Procedures S2.OP-S T. RC-Reactor Coolant System Water Inventory Balance Revision 46

0008 (Q)

S2.OP-SO.RC-Identifying and Measuring Leakage Revision 16

0004(Q)

8