IR 05000272/2024002

Integrated Inspection Report 05000272/2024002 and 05000311/2024002

ML24212A053
Person / Time
Site:	Salem
Issue date:	07/30/2024
From:	Brice Bickett NRC/RGN-I/DORS
To:	Mcfeaters C Public Service Enterprise Group
References
IR 2024002
Download: ML24212A053 (1)

Text

July 30, 2024

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000272/2024002 AND 05000311/2024002

Dear Charles McFeaters:

On June 30, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Salem Nuclear Generating Station, Units 1 and 2. On July 18, 2024, the NRC inspectors discussed the results of this inspection with David Sharbaugh, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

One Severity Level IV violation without an associated finding is documented in this report. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy. The NRC will not conduct a follow-up inspection for this violation because it does not involve any of the initiating criteria in Inspection Procedure 92702, Follow-up on Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, and Order.

No NRC-identified or self-revealing findings were identified during this inspection.

If you contest the violation or the significance or severity of the violation documented in this inspection report, 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 Nuclear Generating Station, Units 1 and 2. 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, 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:

05000272/2024002 and 05000311/2024002

Licensee:

PSEG Nuclear, LLC

Facility:

Salem Nuclear Generating Station, Units 1 and 2

Location:

Hancocks Bridge, NJ

Inspection Dates:

April 01, 2024 to June 30, 2024

Inspectors:

L. Grimes, Resident Inspector

E. Garcia, Resident Inspector

A. Tran, Resident Inspector

Approved By:

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

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Salem Nuclear Generating Station, Units 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

Condition Prohibited by Technical Specifications Due to Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat Exchanger Cornerstone Severity Cross-Cutting Aspect Report Section Not Applicable Severity Level IV NCV 05000272,05000311/2024002-01 Open/Closed Not Applicable 71153 A self-revealed Severity Level IV non-cited violation (NCV) of Technical Specification 3.4.6.2,

Operational Leakage, was identified when the licensee operated Salem Generating Station,

Unit 1, with reactor coolant pressure boundary leakage through a reactor coolant pump (RCP)thermal barrier heat exchanger (TBHX) into the component cooling water (CCW) system from December 2022 to October 2023.

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000272/2024-001-00 LER 2024-001-00 for Salem Generating Station, Unit 1,

Pressure Boundary Leakage through a Reactor Coolant Pump Thermal Barrier Heat Exchanger 71153 Closed

PLANT STATUS

Unit 1 operated at or near rated thermal power for the entire inspection period.

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 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 activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. 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.

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk significant systems from high river water level on April 11, 2024 (Notification (NOTF)

===20962575).

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01)===

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

(1) Unit 1, CCW system, May 6, 2024

(2) Unit 2, 2A, 2B, and 2C emergency diesel generators, May 21, 2024

(3) Unit 2, CCW following unexpected rise in 21 component cooling loop temperature, June 25, 2024

(4) Unit 2, chemical and volume control system 23 charging pump, June 28, 2024

71111.05 - Fire Protection

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

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 2, service water pump bay 4, fire area FP-SA-2651, May 8, 2024

(2) Unit 1, 64' 4160V switchgear and battery rooms, fire area FP-SA-1531, June 13, 2024

(3) Unit 1, inner penetration area and chiller room, fire area FP-SA-1557, June 18, 2024

(4) Unit 1, diesel generator area, fire area FP-SA-1555, June 20, 2024

(5) Unit 1, electrical penetration area, fire area FP-SA-1546, June 26, 2024

(6) Unit 1, auxiliary feedwater pumps area, fire area FP-SA-153, June 27, 2024

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the on-site fire brigade training and performance during an unannounced fire drill on May 6, 2024.

71111.06 - Flood Protection Measures

Flooding Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated internal flooding mitigation protections in the Unit 1 cable condition monitoring program following identification of submerged 13.8 KV cables on April 11, 2024 (NOTF 20957252).

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

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

(1) The inspectors observed and evaluated a Unit 2 simulator scenario that included a grid stability power reduction, steam leak in containment, faulted steam generator, phase 'B' failed actuation, and a stuck open pressurizer power-operated relief valve on May 22, 2024.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (1 Sample)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Unit 1, main steam line discharge safety valves and atmospheric steam dumps, radiation monitors, June 18, 2024

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)

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, elevated risk during scheduled maintenance on 22 CCW pump, May 20, 2024

(2) Unit 2, elevated fire risk during 13 charging pump work window, week of May 27, 2024

(3) Unit 1, elevated risk during scheduled maintenance on 1A emergency diesel generator, May 29, 2024

(4) Unit 1, elevated risk during planned maintenance on 1C emergency diesel generator, June 17, 2024

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

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

(1) Unit 2, 22 containment spray due to inaccurate flow indication immediately following inservice testing, April 18,2024 (NOTF 20962796)

(2) Unit 1, 14 service water pump following failure to meet inservice test criteria, April 26, 2024 (NOTF 20963664)

(3) Unit 2, 2B emergency diesel generator due to the 22SW39, service water inlet valve, failing to meet the time required to open, June 4, 2024 (NOTF 20967302)

(4) Unit 2, reactivity control systems following loss of rod position indication, June 6, 2024 (NOTF 20967501)

(5) Unit 2, 21 steam generator feed pump following identification of both control oil power unit pumps running, June 27, 2024 (NOTF 20967753)

71111.24 - Testing and Maintenance of Equipment Important to Risk

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

Post-Maintenance Testing (PMT) (IP Section 03.01) (10 Samples)

(1) Unit 2, control area ventilation, April 25, 2024 (WO 50239174)

(2) Unit 2, 24 service water pump following maintenance due to increased vibrations, April 29, 2024

(3) Units 1 and 2, station blackout compressor following repairs to air dryer, May 2, 2024

(4) Unit 1, service water intake exhaust fan following 13 service water pump damper operator rebuild, May 7, 2024

(5) Unit 1, 12B CCW heat exchanger following temperature controller calibration, May 16, 2024 (WO 30341908)

(6) Unit 2, 21 chiller following service water inlet valve replacement, May 28, 2024

(7) Unit 1, 1A emergency diesel generator following planned maintenance, May 30, 2024

(8) Unit 2, 21 containment spray pump following breaker replacement, May 31, 2024

(9) Unit 1, 13 charging pump following maintenance, June 3, 2024

(10) Unit 2, 23 charging pump following pump motor inspection, June 27, 2024

Surveillance Testing (IP Section 03.01) (2 Samples)

(1) Unit 2, S2.IC-CC.RCP-0042, S2.IC-FT.RCP-0042, S2.IC-TR.RCP-0042; "22 Steam Generator Pressure Protection Channel III Channel Calibration, Functional Testing, and Response Time Testing," April 17, 2024

(2) Unit 2, S2.OP-ST.AF-0003, "Inservice Testing - 23 Auxiliary Feedwater Pump,"

June 11,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===

(1) Unit 1, April 1, 2023 through March 31, 2024

(2) Unit 2, April 1, 2023 through March 31, 2024

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)

(1) Unit 1, April 1, 2023 through March 31, 2024

(2) Unit 2, April 1, 2023 through March 31, 2024

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)

(1) Unit 1, April 1, 2023 through March 31, 2024

(2) Unit 2, April 1, 2023 through March 31, 2024

===71152A - Annual Follow-Up Problem Identification and Resolution

Annual Follow-Up of Selected Issues (Section 03.03)===

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Review of adherence to maintenance rule scoping and testing requirements for beyond-design-basis SSCs used in emergency operating procedures (NOTF

===20843869/Evaluation 70211323-0010)

71152S - Semiannual Trend Problem Identification and Resolution

Semiannual Trend Review (Section 03.02)===

(1) The inspectors reviewed 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 Event Report (IP Section 03.02)

The inspectors evaluated the following licensees event reporting determinations to ensure it complied with reporting requirements.

(1) LER 05000272/2024-001-00, "Pressure Boundary Leakage through a Reactor Coolant Pump Thermal Barrier Heat Exchanger" (ADAMS Accession No.

ML24130A090). The inspection conclusions associated with this LER are documented in the Inspection Results Section of this report. This LER is Closed.

INSPECTION RESULTS

Condition Prohibited by Technical Specifications Due to Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat Exchanger Cornerstone Severity Cross-Cutting Aspect Report Section Not Applicable Severity Level IV NCV 05000272,05000311/2024002-01 Open/Closed

Not Applicable 71153 A self-revealed Severity Level IV non-cited violation (NCV) of Technical Specification 3.4.6.2, Operational Leakage, was identified when the licensee operated Salem Generating Station, Unit 1, with reactor coolant pressure boundary leakage through a reactor coolant pump (RCP) thermal barrier heat exchanger (TBHX) into the component cooling water (CCW)system from December 2022 to October 2023.

Description:

In January 2023, PSEG identified higher than normal tritium in the CCW system and found that counts on the respective radiation monitor had slowly begun rising in December 2022. PSEG adapted chemistry methods used to monitor primary-to-secondary leakage to identify a RCP TBHX as a possible source of radioactivity in the CCW system; however, this could not be confirmed while the plant was operating.

Subsequent investigation by PSEG noted that reactor coolant system leakage to CCW was not measurable by routine methods and no changes to the reactor coolant system water inventory balance or the CCW surge tank level were observed. The leakage was not detectable via normal mass balance or online leak rate methods but was estimated as 0.2 gallons per day or less. PSEG replaced the associated RCP during the fall 2023 refueling outage and radioactivity levels in the CCW system returned to normal levels.

The removed reactor coolant pump was sent to the vendor where pressure drop testing confirmed that leakage from the reactor coolant system side to the CCW side of the TBHX occurred. Subsequently, PSEG determined that leakage through the 12 RCP TBHX as pressure boundary leakage which allowed radioactivity to enter the CCW system. PSEG was unable to determine the cause of the leak.

Corrective Actions: PSEG previously identified the 12 RCP TBHX as a possible leakage source and replaced the associated reactor coolant pump during the fall 2023 refueling outage.

Corrective Action References: NOTF 20927308

Performance Assessment:

The NRC determined this violation was not reasonably foreseeable and preventable by the licensee and therefore is not a performance deficiency.

Enforcement:

The Reactor Oversight Processes significance determination process does not specifically consider violations without a finding in its assessment of licensee performance.

Therefore, it is necessary to address this violation which has no performance deficiency using traditional enforcement to adequately deter non-compliance.

Severity: The NRC Enforcement Policy, Section 2.2.1, states, in part, that, whenever possible, the NRC uses risk information in assessing the safety significance of violations.

Accordingly, after considering that the condition represented very low safety significance, the inspectors concluded that the violation would be best characterized as Severity Level IV under the traditional enforcement process. For information, the inspectors screened the significance of the condition using IMC 0609, Appendix A, "The Significance Determination Process for Findings At-Power," and determined that the condition was of very low safety significance (Green) because the very small leak did not result in exceeding the reactor coolant system leak rate for a small loss of coolant accident and did not affect systems used to mitigate a loss of coolant accident.

Violation: Salem Generating Station, Unit 1, Limiting Condition for Operation 3.4.6.2, prohibits operation with pressure boundary leakage. When the limiting condition for operation was not met, Action 'A' was applicable which required that Unit 1 be placed in Mode 3 and Mode 5 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, respectively. Contrary to the above, from December 2022 to October 2023, PSEG operated Salem Generating Station, Unit 1, in Mode 1 with pressure boundary leakage.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

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

• On July 18, 2024, the inspectors presented the integrated inspection results to David Sharbaugh, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

Drawings

205231 Sh. 1 and

71111.05

Fire Plans

FP-SA-2651

FP-SA-2651-F1

FP-SA-2651-F2

71111.06

Procedures

ER-AA-3003

Cable Condition Monitoring and Aging Management Program 2

71111.12

Procedures

SC.CH.AB.ZZ-

1102

Response to Inoperable Technical Specification Effluent

Monitors and Equipment

71111.13

Procedures

OP-AA-108-116

Protected Equipment Program

71111.15

Engineering

Changes

235008-0020

Procedures

2.OP-ST.DG-

0002

2B Diesel Generator Surveillance Test

S1.OP-ST.SW-

0004

Inservice Testing - 14 Service Water Pump

Work Orders

30389862

249951

250552

250625

71111.24

Miscellaneous

NOTF 20967054

NOTF-20964873

Procedures

S1.OP-ST.CC-

0002

and 12 Component Cooling Heat Exchanger Operation

S2.OP-ST.CS-

0002

Inservice Testing - 21 Containment Spray Pump

Work Orders

30383872

60160185

71152A

Procedures

1-EOP-FRHS-1

Response to Loss of Secondary Heat Sink

1-EOP-TRIP-1

Reactor Trip or Safety Injection

SC.OP-AM.TSC-

0012

Feeding Steam Generators Utilizing Portable Diesel-Driven

Pump

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Work Orders

223882