|
|
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:February 9, 2021 | | {{#Wiki_filter: |
| | |
| ==SUBJECT:==
| |
| SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000272/2020004 AND 05000311/2020004
| |
| | |
| ==Dear Mr. Carr:==
| |
| On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Salem Nuclear Generating Station, Units 1 and 2. On January 14, 2021, the NRC inspectors discussed the results of this inspection with Mr. Richard DeSanctis, Plant Manager 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, X /RA/
| |
| Signed by: Brice A. Bickett 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 05000272/2020004 and 05000311/2020004
| |
| | |
| ==Inspection Report==
| |
| Docket Numbers: 05000272 and 05000311 License Numbers: DPR-70 and DPR-75 Report Numbers: 05000272/2020004 and 05000311/2020004 Enterprise Identifier: I-2020-004-0017 Licensee: PSEG, Nuclear LLC Facility: Salem Nuclear Generating Station Units 1 and 2 Location: Hancock's Bridge Inspection Dates: October 1, 2020 to December 31, 2020 Inspectors: J. Hawkins, Senior Resident Inspector M. Hardgrove, Resident Inspector P. Finney, Senior Project Engineer J. Kulp, Senior Reactor Inspector J. Rady, Emergency Preparedness Inspector G. Walbert, Reactor Engineer S. Wilson, Senior Health Physicist 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 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.
| |
| | |
| =PLANT STATUS=
| |
| | |
| Unit 1 began the inspection period at rated thermal power. On October 2, 2020, Unit 1 was manually tripped from 12 percent power as part of a planned evolution to commence 1R27 refueling outage. A reactor startup was commenced on December 13, 2020 but was subsequently taken offline from 18 percent power to address turbine stop valve issues. A reactor startup was commenced on December 17, 2020 and reached rated thermal power on December 21, 2020. There were no other operational power changes of regulatory significance for the remainder of the inspection period.
| |
| | |
| Unit 2 began the inspection period at rated thermal power. 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.
| |
| | |
| Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week, increasing the amount of time on site as local COVID-19 conditions permitted. As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
| |
| | |
| ==REACTOR SAFETY==
| |
| | |
| ==71111.01 - Adverse Weather Protection==
| |
| | |
| ===Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)===
| |
| : (1) The inspectors evaluated readiness for seasonal extreme weather conditions, during the week of November 15, prior to the onset of extreme low temperatures experienced during the winter months for the following systems: emergency diesel generators, auxiliary feedwater, and circulating water systems
| |
| | |
| ===External Flooding Sample (IP Section 03.03) (1 Sample)===
| |
| : (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment were consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding from November 8 - 15
| |
| | |
| ==71111.04 - Equipment Alignment==
| |
| | |
| ===Partial Walkdown Sample (IP Section 03.01) (3 Samples)===
| |
| The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
| |
| : (1) Unit 1 and 2, walkdown of spent fuel pool water transfer valve and system lineup after the inadvertent transfer of water during the week of October 19
| |
| : (2) Unit 2, 22 safety injection pump prior to the 21 safety injection pump surveillance testing on October 27
| |
| : (3) Unit 1 and Unit 2, control room emergency air conditioning system (CREACS)following 13 chiller trip with Unit 2 CREACS out of service for scheduled maintenance on December 15
| |
| | |
| ===Complete Walkdown Sample (IP Section 03.02) (2 Samples)===
| |
| : (1) Unit 1, chemical volume control system on November 2
| |
| : (2) Unit 1, service air system after containment piping was found damaged during the week of November 15
| |
| | |
| ==71111.05 - Fire Protection==
| |
| | |
| ===Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 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 1, containment elevations during the week of October 5
| |
| : (2) Unit 2, 4160V switchgear and battery rooms on October 6
| |
| : (3) Unit 1 and Unit 2, ISI storage room and waste evaporator room during the week of October 26
| |
| | |
| ==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, Auxiliary Building Flood Area AB-084-A on October 14
| |
| | |
| ===Cable Degradation (IP Section 03.02) (1 Sample)===
| |
| The inspectors evaluated cable submergence protection in:
| |
| : (1) Unit 1 and 2, review of the switchyard cable vaults after multiple vaults were found submerged and re-flooded during the week of December 3
| |
| | |
| ===71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01) ===
| |
| {{IP sample|IP=IP 71111.08|count=1}}
| |
| : (1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities during the Salem Unit 1 outage from October 13, 2020 to November 6, 2020:
| |
| 03.01.a - Nondestructive Examination and Welding Activities.
| |
| | |
| Manual ultrasonic examination of the 11 steam generator lower head to tube sheet weld (UT-20-054)
| |
| Ultrasonic thickness examination of containment liner panel, 78-017 (UT-20-016)
| |
| Encoded phased array ultrasonic examination of reactor pressure vessel #11 cold leg nozzle to safe end weld, 27.5-RC-1110.5 (Summary 060000)
| |
| Dye penetrant test of the 12 safety injection accumulator nozzles (60146777)
| |
| Bare metal visual examination of flux thimble welds, 1-58 (VEN-20-037)
| |
| Automated phased array ultrasonic examination of reactor vessel to flange circumferential weld, W01, 1-RPV-7042 (VEN-20-009)
| |
| Remote visual examination of zero degree thermal shield flexure on Salem Unit 1 (WDI-STD-088), dated 10/13/2020 03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities Evaluation of boric acid on S1RHR-1RH47 tail piece pipe cap (20861187)
| |
| Evaluation of boric acid on S1SJ-12SJ174 tail piece pipe cap (20861307)
| |
| | |
| ==71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance==
| |
| | |
| ===Requalification Examination Results (IP Section 03.03) (1 Sample)===
| |
| : (1) The inspectors reviewed and evaluated the licensed operator requalification exam results for the annual operating exam and biennial written exam on November 6, 2020
| |
| | |
| ==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 and evaluated licensed operator performance in the control room during Unit 1 reactor shutdown for the 1R27 refueling outage on October 2 and 3
| |
| | |
| ===Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)===
| |
| : (1) The inspectors observed and evaluated licensed operator requalification training on November 4
| |
| : (2) The inspectors observed and evaluated licensed operator requalification training on November 17
| |
| | |
| ==71111.12 - Maintenance Effectiveness==
| |
| | |
| ===Maintenance Effectiveness (IP Section 03.01) (3 Samples)===
| |
| 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, review of the 1A emergency diesel generator governor quality control, refurbishment process, and extent of condition during the week of October 26
| |
| : (2) Unit 2, review of the 22-component cooling water heat exchanger service water inlet valve (22SW122) failure to stroke correctly during surveillance testing during the week of December 3
| |
| : (3) Unit 1 and Unit 2, service water inlet containment isolation valves (SW58) for containment fan cooling units failing to close during surveillance testing on
| |
| | |
| ===December 2 Aging Management (IP Section 03.03) (1 Sample)===
| |
| The inspectors evaluated the effectiveness of the aging management program for the following SSCs that did not meet their inspection or test acceptance criteria:
| |
| : (1) Unit 1 and 2, review of the circulating water intake structures after grating and structural steel degraded and failed during the week of December 3
| |
| | |
| ==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 1, Yellow risk during reactor coolant drain down to the reactor flange on October 5.
| |
| : (2) Unit 1 and 2, turbine building, main generator and main power transformer areas during heavy load lift of the Unit 1 stator from the foundation to the turntable during the week of October 19
| |
| : (3) Unit 1, 1B emergency diesel generator outage maintenance window with 1A emergency diesel generator governor hunting troubleshooting ongoing on October 26
| |
| : (4) Unit 1, spent fuel pool with full core offload during refueling outage on November 5
| |
| | |
| ==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 1, safety injection flow balance lower than minimum required flow during the week of October 13
| |
| : (2) Unit 1, 11 and 12 containment fan cooling unit installed non-safety related bearings in a safety related application on October 15
| |
| : (3) Unit 1, 12 reactor coolant pump trip breaker solid state protection system fuse and relay failure on October 20
| |
| : (4) Unit 1, reactor head vent solenoid valve (1RC40) failed to open on demand on October 21
| |
| : (5) Unit 2, 2A emergency diesel generator after testing and engine analysis showed abnormal noise during the week of October 5
| |
| | |
| ==71111.19 - Post-Maintenance Testing==
| |
| | |
| ===Post-Maintenance Test Sample (IP Section 03.01) (3 Samples)===
| |
| The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
| |
| : (1) Unit 1, repair of the number 1 station power transformer during the week of October 13
| |
| : (2) Unit 1, 11 reactor coolant pump replacement on November 5
| |
| : (3) Unit 1, 1A emergency diesel generator governor replacement following governor hunting on November 10
| |
| | |
| ==71111.20 - Refueling and Other Outage Activities==
| |
| | |
| ===Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)===
| |
| : (1) Unit 1, scheduled refueling outage 1R27 from October 3 to December 14
| |
| ==71111.22 - Surveillance Testing==
| |
| | |
| The inspectors evaluated the following surveillance tests:
| |
| | |
| ===Surveillance Tests (other) (IP Section 03.01)===
| |
| {{IP sample|IP=IP 71111.22|count=2}}
| |
| : (1) Unit 1, high head cold leg throttling valve flow balance surveillance test during the week of October 13
| |
| : (2) Unit 2, pressurizer pressure protection channel I (2PT-455) functional surveillance testing on October 27
| |
| | |
| ===RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)===
| |
| : (1) Unit 2, reactor coolant system leak detection since January 1, 2020 on November 20
| |
| | |
| ===Containment Isolation Valve Testing (IP Section 03.01) (2 Samples)===
| |
| : (1) Unit 1, containment airlock local leak rate testing prior to startup on December 4
| |
| : (2) Unit 2, containment isolation valve testing failure of the 22-component cooling water heat exchanger service water inlet valve (22SW122) during the week of December 14
| |
| | |
| ===FLEX Testing (IP Section 03.02) (1 Sample)===
| |
| : (1) Unit 1, 11 auxiliary feed water pump surveillance retest during the week of October 26
| |
| | |
| ==71114.02 - Alert and Notification System Testing==
| |
| | |
| ===Inspection Review (IP Section 02.01-02.04) (1 Sample)===
| |
| : (1) The inspectors evaluated PSEG's maintenance and testing of the alert and notification system common to Salem and Hope Creek on September 28 - October 2, 2020, for the period of January 2019 through September 2020.
| |
| | |
| ==71114.03 - Emergency Response Organization Staffing and Augmentation System==
| |
| | |
| ===Inspection Review (IP Section 02.01-02.02) (1 Sample)===
| |
| : (1) The inspectors evaluated the readiness of PSEG's Emergency Preparedness Organization common to Salem and Hope Creek on September 28 - October 2, 2020.
| |
| | |
| ==71114.04 - Emergency Action Level and Emergency Plan Changes==
| |
| | |
| ===Inspection Review (IP Section 02.01-02.03) (1 Sample)===
| |
| : (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes onsite on September 28 - October 2, 2020.
| |
| * Evaluation No.: 2019-36, NC.EP-EP.ZZ-0202, Operations Support Center Activation and Operations, Revision 27
| |
| * Evaluation No.: 2019-44, NC.EP-EP.ZZ-0903, Opening of Emergency Operations Facility, Revision 5
| |
| * Evaluation No.: 2019-48, EP-AA-120-1007, Maintenance of Emergency Response Organization, Revision 8
| |
| * Evaluation No.: 2020-26, Emergency Plan Section 7, Emergency Communications, Revision 17 This evaluation does not constitute NRC approval.
| |
| | |
| ==71114.05 - Maintenance of Emergency Preparedness==
| |
| | |
| ===Inspection Review (IP Section 02.01 - 02.11) (1 Sample)===
| |
| : (1) The inspectors evaluated the maintenance of PSEG's emergency preparedness program common to Salem and Hope Creek on September 28 - October 2, 2020, for the period of January 2019 through September 2020.
| |
| | |
| ==71114.06 - Drill Evaluation==
| |
| | |
| ===Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)===
| |
| The inspectors evaluated:
| |
| : (1) The emergency planning aspects of a licensed operator simulator evaluation was conducted in the plant-reference simulator on December 1. This evaluation included the initiating conditions that resulted in associated emergency classification and notifications in accordance with PSEG's emergency plan.
| |
| | |
| ==OTHER ACTIVITIES - BASELINE==
| |
| | |
| ===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
| |
| EP01: Drill/Exercise Performance (IP Section 02.12) ===
| |
| {{IP sample|IP=IP 71151|count=1}}
| |
| : (1) January 1, 2019 to June 30, 2020 (common to Salem and Hope Creek)
| |
| | |
| ===EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)===
| |
| : (1) January 1, 2019 to June 30, 2020 (common to Salem and Hope Creek)
| |
| | |
| ===EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)===
| |
| : (1) January 1, 2019 to June 30, 2020 (common to Salem and Hope Creek)
| |
| | |
| ===MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)===
| |
| : (1) Unit 1, October 1, 2019 - September 30, 2020
| |
| : (2) Unit 2, October 1, 2019 - September 30, 2020
| |
| | |
| ===MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)===
| |
| : (1) Unit 1, October 1, 2019 - September 30, 2020
| |
| : (2) Unit 2, October 1, 2019 - September 30, 2020
| |
| | |
| ===OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)===
| |
| The inspectors verified the licensees Occupational Exposure Control Effectiveness occurrences for the time period from October 1, 2019, to September 30, 2020.
| |
| : (1) The inspectors verified that greater than or equal to one Roentgen per hour High Radiation Area Technical Specifications or regulatory non-conformances were properly captured in the performance indicator occurrences reported by the licensee.
| |
| | |
| The inspectors reviewed licensee notifications and radiologically controlled area entries where individual whole body doses were greater than 100 millirem per entry.
| |
| | |
| The inspectors also discussed the performance indicator requirements with the radiation protection manager.
| |
| | |
| PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
| |
| The inspectors verified the licensees Radiological Effluent Performance Indicator occurrences for the time period from October 1, 2019, to September 30, 2020.
| |
| : (1) The inspectors reviewed notifications related to the radiation protection program effluents, reviewed the 2019 Annual Radioactive Effluent Release Report and interviewed the radiation protection manager.
| |
| | |
| ==71152 - Problem Identification and Resolution==
| |
| | |
| ===Semiannual Trend Review (IP Section 02.02) (1 Sample)===
| |
| : (1) Unit 1 and 2, review of potential trends in the corrective action program related to aging management, equipment failures, system operation and preventive maintenance during the week of December 3
| |
| | |
| ===Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)===
| |
| The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
| |
| : (1) Root Cause Evaluation (70207205) of the unexpected number of baffle former bolt failures identified during Salem Unit 1 spring 2019 refueling outage.
| |
| | |
| ==INSPECTION RESULTS==
| |
| Observation: Root Cause Evaluation (70207205) of the Unexpected Number of 71152 Baffle Former Bolt Failures Identified during Salem Unit 1 Spring 2019 Refueling Outage.
| |
| | |
| The inspectors performed a focused problem identification and resolution sample to assess PSEGs evaluation and corrective actions associated with the discovery of an unexpected amount of failed baffle former bolts (BFB) during the 2019 Unit 1 Spring refueling outage (1R26). Specifically, the number of baffle former bolts that were characterized as failed in
| |
| | |
| {{a|1R26}}
| |
| ==1R26 exceeded the amount that was expected based on results of a site-specific predictive==
| |
| | |
| model. The inspectors reviewed PSEGs root cause evaluation to assess whether PSEG identified the causes of the underprediction problem in the site-predictive model and provided for corrective actions in a timely manner commensurate with the safety significance of the issue. The inspectors also evaluated whether PSEG considered the extent of condition for Salem Unit 2.
| |
| | |
| The inspectors concluded that PSEG appropriately evaluated the potential causes of the inaccurate results of the predictive model with regards to the underprediction of the number of baffle former bolt failures expected. Additional information from the Spring 2019 refueling outage indicated to PSEG the causes of BFB underprediction may be related to the condition of other supporting in vessel components involving thermal shield support block bolts and thermal shield flexure welds. Specifically, during the Spring 2019 Unit 1 refueling outage, PSEG staff found several broken bolts, which they replaced, and indications on two thermal shield flexure supports.
| |
| | |
| During the subsequent refueling outage (1R27), PSEG planned and completed actions to replace all original 347 stainless steel BFB with new bolts of an improved design and material (316 stainless steel). The other 460 previously replaced bolts, replaced during the 1R24 (2016) and 1R26 (2019) outages, were examined ultrasonically with no unacceptable indications identified. PSEG communicated these results to industry via normal reporting processes to factor into predictive models. The inspectors concluded the actions were timely and commensurate with the safety significance of the issue.
| |
| | |
| Observation: Semi Annual Trend Review 71152 The inspectors evaluated several issues and associated notifications (NOTFs) generated over the course of the past two quarters that provide input to the quarterly trend reports. The inspectors determined that, in most cases, issues and potential trends were appropriate identified, evaluated, and resolved by PSEG as noted below.
| |
| | |
| PSEG documented issues identified by the inspectors related to PSEG operator actions during the controlled shut down of Unit 1. The inspectors noted that PSEGs NOTF 20861832 associated follow-up actions appropriately evaluated the issues. PSEG completed corrective actions (CAs) in Order 70214938 for all licensed operators as part of the extent of condition. The inspectors observed additional main control room activities, including the Unit 1 reactor startup in December 2020, and did not note similar concerns with operator performance.
| |
| | |
| PSEG documented a potential adverse trend associated with the differential pressure for the Unit 2, 23 auxiliary feedwater pump in-service testing. The inspectors noted that PSEGs NOTF 20867126 associated follow-up actions appropriately evaluated the potential cause of the trend. The station determined the trend was related to running the pump at or near minimum speed and PSEG revised the pumps testing procedure to address the trend.
| |
| | |
| In addition to the issues noted above, the inspectors found that PSEG appropriately documented 65 other NOTFs identifying potential adverse trends in various safety-related and non-safety-related areas since June 1, 2020.
| |
| | |
| The inspectors did note a few instances where PSEG was not timely or did not appropriately identify, evaluate, and resolve adverse trends. Examples of these are documented below:
| |
| The inspectors identified that PSEG had not initiated corrective action program (CAP) actions to perform past operability and reportability reviews associated with the failures of the 22SW122 and the 22SW39 valves. The inspectors also noted that these reviews were not documented in CAP. PSEG documented this issue in CAP under NOTF 20867733 and 20864169.
| |
| | |
| The inspectors identified that PSEG had not appropriately evaluated and documented the causes of two equipment failures (70214350 and 70214617) in accordance with their causal evaluation procedure. PSEG CAP procedures require that at least one causal analysis attribute be checked YES for all equipment reliability evaluations. PSEG documented this issue in CAP under NOTF 20867540.
| |
| | |
| In NRC Inspection Report 2020002, the inspectors had previously identified PSEGs oil analysis and trending program as a potential adverse trend based on recent events, including an NRC identified auxiliary feedwater pump (AFW) oil issue (NRC Inspection Report 2020001) and the recent failure of 23 turbine driven AFW pump governor due to potential oil contamination. PSEG documented this in NOTF 20854127 on May 28, 2020. At the time, PSEG CAs were in-progress to address the oil sampling and analysis program gaps due to process rigor. Part of these actions included completing an extent of condition and self-assessment of Salems Lubrication Program and the revision to ER-AA-230-1001. The inspectors identified that these actions were still outstanding as of January 4, 2021.
| |
| | |
| The inspectors evaluated these issues IAW IMC 0612, Appendix B, Issue Screening, and Appendix E, Examples of Minor Issues, and determined the issues did not constitute performance deficiencies or were of minor significance. Consequently, these issues were not subject to enforcement action in accordance with the NRCs enforcement policy.
| |
| | |
| ==EXIT MEETINGS AND DEBRIEFS==
| |
| The inspectors verified no proprietary information was retained or documented in this report.
| |
| * On October 2, 2020, the inspectors presented the Emergency Preparedness Program inspection results to David Sharbaugh, Plant Manager and other members of the licensee staff.
| |
| * On October 29, 2020, the inspectors presented the Radiation Protection Performance Indicators (OR01, PR01); NEI 99-02, Revision 7 inspection results to William Noval, Site Compliance Manager and other members of the licensee staff.
| |
| * On December 2, 2020, the inspectors presented the Root Cause Evaluation (70207205)of the unexpected number of baffle former bolt failures identified during Salem Unit 1 spring 2019 refueling outage inspection results to William Kopchick, Senior Director of Engineering Services and other members of the licensee staff.
| |
| * On January 14, 2021, the inspectors presented the integrated inspection results to Mr. Richard DeSanctis, Plant Manager and other members of the licensee staff.
| |
| | |
| =DOCUMENTS REVIEWED=
| |
| | |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| 71111.05 Corrective Action 20861836*
| |
| Documents 20861735*
| |
| Resulting from 20861832*
| |
| Inspection
| |
| 71114.02 Miscellaneous Design Report Final 2005 REP-10 Design Review Report for PSEG Salem Revision 1
| |
| and Hope Creek Generating Stations
| |
| 71114.03 Corrective Action 20861144
| |
| Documents 20861168
| |
| Resulting from
| |
| Inspection
| |
| Miscellaneous On-Shift Staffing Hope Creek and Salem Generating Station On-Shift Staffing Revision 0
| |
| Report Analysis Report
| |
| PSEG Nuclear PSEG Nuclear Emergency Plan dated April 8,
| |
| LLC - EP 2020
| |
| 71114.04 Procedures EP-AA-120-1001 10 CFR 50.54(q) Change Evaluation Revision 5
| |
| 71114.05 Corrective Action 20861175
| |
| Documents 20861333
| |
| Resulting from 20861334
| |
| Inspection
| |
| Procedures EP-AA-121-1003 Equipment Important to Emergency Response - Work Revision 5
| |
| Prioritization
| |
| 71151 Corrective Action 20844992 Unplanned Dose to Worker February 18,
| |
| Documents 2020
| |
| 20846943 Unanticipated dose rate alarm March 21,
| |
| 20
| |
| Radiation Surveys LR-N20-0025 2019 Annual Radioactive Effluent Release Report April 27,
| |
| 20
| |
| 13
| |
| }} | | }} |
