IR 05000272/2019003

Integrated Inspection Report 05000272/2019003 and 05000311/2019003

ML19309E825
Person / Time
Site:	Salem
Issue date:	11/05/2019
From:	Brice Bickett Reactor Projects Branch 3
To:	Carr B Public Service Enterprise Group
References
IR 2019003
Download: ML19309E825 (12)

Text

ber 5, 2019

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000272/2019003 AND 05000311/2019003

Dear Mr. Carr:

On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Salem Nuclear Generating Station, Units 1 and 2 in Hancocks Bridge, New Jersey.

On October 10, 2019, the NRC inspectors discussed the results of this inspection with Mr. Patrick Martino, Salem Plant Manager 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.

A licensee-identified violation which was determined to be of very low safety significance 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.

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,

/RA/

Brice A. Bickett, Chief Reactor Projects Branch 3 Division of Reactor Projects Docket Nos. 05000272 and 05000311 License Nos. DPR-70 and DPR-75 Enclosure Inspection Report 05000272/2019003 and 05000311/2019003 cc w/ encl: Distribution via LISTSERV

ML19309E825 Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP NAME JHawkins PFinney BBickett DATE 11/5/19 11/5/19 11/5/19

U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Numbers: 05000272 and 05000311 License Numbers: DPR-70 and DPR-75 Report Numbers: 05000272/2019003 and 05000311/2019003 Enterprise Identifier: I-2019-003-0041 Licensee: PSEG Nuclear, LLC Facility: Salem Nuclear Generating Station, Units 1 and 2 Location: Hancocks Bridge, NJ 08038 Inspection Dates: July 01, 2019 to September 30, 2019 Inspectors: M. Hardgrove, Resident Inspector J. Hawkins, Senior Resident Inspector K. Mangan, Senior Reactor Inspector A. Ziedonis, Senior Resident Inspector Approved By: Brice A. Bickett, Chief Reactor Projects Branch 3 Division of Reactor Projects Enclosure

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. A licensee-identified non-cited violation is documented in report section: 71152.

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

Additional Tracking Items None.

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 August 11, 2019, the Unit was tripped from 83 percent power due to equipment challenges with steam generator water level control. A reactor startup was commenced on August 14, 2019 and the Unit reached rated thermal power the following day on August 15, 2019. The Unit remained at or near rated thermal power 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 licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

71111.01 - Adverse Weather Protection External Flooding Sample (IP Section 03.04)

(1) The inspectors evaluated readiness to cope with the following areas:

External Flooding

71111.04Q - 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, Source range nuclear instrumentation due to 1N34 mismatch on July 8

(2) Unit 1, 12 & 13 auxiliary feed water pumps during 11 auxiliary feed water pump IST on July 31

(3) Unit 2, Chill water system due to issues with isolation valve 2CH151 on July 8

71111.04S - Equipment Alignment Complete Walkdown Sample (IP Section 03.02)

(1) The inspectors evaluated system configuration during a complete walkdown of the 22 Steam Generator Feedwater Pump (SGFP) after not rotating on turning gear on August 14

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

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

(1) Unit 1, 11 Reactor Coolant Pump (Zone 130) hourly firewatch on August 5

(2) Unit 2, Emergency diesel generator area and auxiliary building on July 1

(3) Unit 2, Auxiliary building on July 10

(4) Unit 2, 23 Component cooling pump oil leak on July 28

(5) Unit 2, Emergency diesel generator control area door gasket degraded on August 7

71111.06 - Flood Protection Measures Inspection Activities - Underground Cables (IP Section 02.02c.)

The inspectors evaluated cable submergence protection in:

(1) 13.8 kV cable vaults on August 6

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) The inspectors observed and evaluated licensed operator performance in the Control Room during Unit 2 downpower to 89.5% power for turbine valve testing, then back to 100% power on August 2 Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)

(1) The inspectors observed and evaluated Control Area Air Conditioning System (CAACS) supply fan swap, loss of spent fuel pool level with elevated radiation levels in fuel handling building and auxiliary building, and inadvertent safety injection scenarios on July 23

(2) The inspectors observed and evaluated 21 Reactor Coolant (RC) loop cold leg resistance temperature detector (RTD) fails high, 23 charging pump trip, main turbine inadvertent trip and failure of automatic reactor trip, loss of 2A 4KV vital bus and 23 auxiliary feedwater pump (AFW) fails to auto-start, and 23 AFW pump trips with steam generator feedwater pump prompt recovery scenarios on September 10

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness Inspection (IP Section 02.01)

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

(1) Units 1 & 2, Station air compressors (SAC) following multiple issues with 1 SAC out of service on August 7

Quality Control (IP Section 02.02) (1 Sample)

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

(1) Units 1 & 2, reactor head vent valves after 1RC40 was found to be operable but degraded week of July 1 - July 5

71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)

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

(1) Units 1 & 2, Station air compressor high lube oil temperature alarm with #1 station air compressor out of service on July 26

(2) Unit 1, Source range nuclear instrumentation mismatch and on the spot change during startup from 1R26 on July 8

(3) Unit 1, 12 chiller out of service following loss of in-service light and high compressor suction pressure on August 19

(4) Unit 2, Failure of 23BF19 feedwater regulating valve leading to manual trip to Unit 2 on August 12

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Units 1 & 2, reactor head vent valves when 1RC40 was found operable but degraded week of July 1- July 5

(2) Unit 1, 12 auxiliary feed water pump suction pressure high during valve stroke on July 8

(3) Unit 1, 13 Auxiliary Feedwater Pump declared operable following relief valve removal and implementation of a blind flange on September 27

(4) Unit 2, 1A1 control rod misalignment during reactor startup on August 13

71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

The inspectors evaluated the following temporary or permanent modifications:

(1) Service water 54 bypass line on July 8

71111.19 - Post-Maintenance Testing Post-Maintenance Test Sample (IP Section 03.01)

The inspectors evaluated the following post maintenance tests:

(1) Unit 1, 1A Main power transformer cooling group 1 normal breaker tripped on July 8

(2) Unit 1 12SW223, 12 containment fan coil unit flow control valve, failed open during surveillance testing on September 4

(3) Unit 2, 21 Service water pump motor replacement on July 15

(4) Unit 2, 2R44B containment high range radiation monitor for capacitor replacement and environmental qualification maintenance on August 7

(5) Unit 2, 21 component cooling heat exchanger out of service following 21SW122 declared inoperable due to failure to open in auto and manual on September 5

(6) Unit 2, 21SW122 valve inoperable following 21 component cooling heat exchanger high flow flush on September 11

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Surveillance Tests (other) (IP Section 03.01)

(1) Unit 1, Reactor Head Vent solenoid verification position verification surveillance testing on July 5

Inservice Testing (IP Section 03.01) (2 Samples)

(1) Unit 1,11 Residual heat removal pump in-service testing on August 28

(2) Unit 2, 22 Containment spray pump in-service testing on July 24

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

(1) Unit 1, Elevated reactor coolant system reactor coolant drain tank in-leakage on August

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

MS07: High Pressure Injection Systems (IP Section 02.06) ===

(1) Unit 1, July 1, 2018-June 30, 2019

(2) Unit 2, July 1, 2018-June 30, 2019

MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)

(1) Unit 1, July 1, 2018-June 30, 2019

(2) Unit 2, July 1, 2018-June 30, 2019 MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)

(1) Unit 1, July 1, 2018-June 30, 2019

(2) Unit 2, July 1, 2018-June 30, 2019

71152 - Problem Identification and Resolution Annual Follow-up of Selected Issues (IP Section 02.03)

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

(1) Follow-up of chiller issues and 13 chiller low chilled water flow condition on July 1, 2019 - August 19, 2019

(2) 1PR1 and 1PR2 leakage events and history on July 8

71153 - Followup of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)

(1) The inspectors evaluated the 21HD9, 21 heater drain pump, failed open and licensees response on August 1

(2) The inspectors evaluated failure of 23BF19 feedwater regulating valve leading to manual trip for unit 2 and licensees response on August

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

===71003 - Post-Approval Site Inspection for License Renewal The inspection was conducted as outlined in NRC Inspection Procedure 71003, Phase 2 - Post-Approval Site Inspection for License Renewal, as a supplement to the Phase 2 team inspection completed at Salem Unit 1 (IR 05000272/2015011). This inspection effort included walkdowns of selected SSCs subject to aging management programs; interviews with engineers, and reviews of associated design and licensing documents to evaluate if PSEG was meeting their License Renewal commitments and to verify inspections or examinations required to be performed had been and would be completed prior to the period of extended operations. For the aging management programs selected, the inspector reviewed the parameters monitored or inspected, detection of aging effects, and acceptance criteria for program procedures. Documents reviewed for this inspection are listed in the Attachment.

The Aging Management Programs (AMPS) reviewed were:

Post-Approval Site Inspection for License Renewal ===

(1) Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS)

(2) One-Time Inspection

(3) One-Time Inspection of (ASME) Code Class 1 Small-Bore Piping

(4) Electrical Cables and Connections Not Subject to 10 CFR 50.49 Equipment Qualification Requirements

(5) Metal Enclosed Bus

(6) Periodic Inspections

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71152 This violation of very low safety significance 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: 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires that measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program.

PSEG procedures CC-AA-103, Revision 15, Configuration Change Control for Permanent Physical Plant changes, Section 4.5.10, and CC-AA-102, Revision 25, Design Input and Configuration Change Impact Screening, Section 4.1.5, implement these requirements for verifying or checking the adequacy of design.

Contrary to the above, since the approval of the Design Change Package (DCP) in October 2014 until present for the Salem Unit 1 and 2 Chilled Water System chillers replacement, PSEG did not adequately verify and check the adequacy of the design via design reviews, an alternate or simplified calculational method, or a suitable testing program. The inspectors determined that this is a violation of 10 CFR Part 50, Appendix B, Criterion III.

PSEG has implemented adequate intermediate corrective actions until the permanent corrective actions are completed to resolve the low chill water flow condition.

This violation of very low significance was identified by PSEG and has been entered into their corrective action program and is being treated as a NCV, consistent with Section 2.3.2 of the Enforcement Policy.

Significance/Severity: Green. The inspectors reviewed NRC IMC 0609, Initial Characterization of Findings, Attachment 4, issued on October 7, 2016 and IMC 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, issued on June 19, 2012. The inspectors determined that the finding is of very low safety significance (Green) because under Exhibit 2, Mitigating Systems Screening Questions, of IMC 0609, Appendix A, the finding screens to Green for being a deficiency affecting the design or qualification of a mitigating system, structure, or component (SSC) while the SSC maintains its operability or functionality.

Corrective Action References: 70206648, 70207634 Observation: Follow-up of chiller issues and 13 chiller low chilled water flow 71152 condition The inspectors performed an in-depth review of PSEGs evaluations and corrective actions associated with multiple equipment issues experienced on the chillers and chill water systems for Units 1 and 2 since July 1, 2018. The inspectors reviewed associated documents and interviewed personnel to assess the adequacy of PSEG completed actions and planned follow-up actions.

Following the permanent plant modification replacing the 13 chiller with a newly designed chiller in March 2019, a low chilled water flow condition was identified during the modification acceptance testing (MAT). The inspectors reviewed PSEGs actions to resolve the low flow condition and the overall system impact this condition could have on the chill water systems ability to fulfill its safety function. PSEG completed an extensive design review and operability evaluation to ensure the systems capabilities during normal and accident conditions. Prior to the replacement of the other Unit 1 and Unit 2 chillers, PSEGs planned corrective actions include performing a chiller system flow re-balance, using throttle valves to maintain the re-balanced system flow, and additional system MAT.

The inspectors evaluated all of the chiller system issues in accordance with the guidance in IMC 0612, Appendix B, Issue Screening, and Appendix E, Examples of Minor Issues, and determined all but one of the issues were of minor significance because the inspectors did not identify any condition adverse to quality that were not appropriately corrected or scheduled for correction in a reasonable period of time. Consequently, these issues are not subject to enforcement action in accordance with the NRCs enforcement policy. However, inspectors documented one deficiency associated with design control of the chillers, specifically with PSEGs control of the design change process. This deficiency is documented above.

EXIT MEETINGS AND DEBRIEFS

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

On October 10, 2019, the inspectors presented the integrated inspection results to Mr. Patrick Martino, Salem Plant Manager and other members of the licensee staff.

On July 19, 2019, the inspectors presented the License Renewal Phase II Inspection results to Mr. Patrick Martino, Salem Plant Manager and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71003 Corrective Action 20321027

Documents 20829308

Resulting from 20829309

Inspection 20829311

20829312

20829401

20829403

20829407

20829408

20829830

Miscellaneous 3 SA-PBD-AMP- Thermal Aging CASS Rev. 2

XI.M12

SA-PBD-AMP- OTI Small Bore Piping Rev. 3

XI.M35

SH-PBD-AMP- Periodic Rev. 3

PS2

SH-PBD-AMP- One Time Rev. 4

X1.M32

SH-PBD-AMP- Electrical Connections Rev. 1

XI-E6

SH-PBD-AMP- Metal Enclosed Bus Rev. 1

XI.E4

NUREG-2101 Safety Evaluation Report Related to the License Renewal of March 2011

Salem Nuclear Generating Station

10