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Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Integrated Inspection Report 05000272/2017002 and 05000311/2017002
	ML17221A021
Person / Time
Site:	Salem
Issue date:	08/08/2017
From:	Bower F L; Reactor Projects Branch 3
To:	Sena P P; Public Service Enterprise Group
References
	IR 2017002
	Download: ML17221A021 (40)
	v • d • e

T. Joyce August 8, 2017 Mr. Peter P. Sena, III President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT: SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 - INTEGRATED INSPECTION REPORT 05000272/2017002 AND 05000311/2017002

Dear Mr. Sena:

On June 30, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Salem Nuclear Generating Station (Salem), Units 1 and 2. On July 13, 2017, 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.

NRC inspectors documented two licensee-identified violations which were determined to be of very low safety significance in this report. The NRC is treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2.a of the Enforcement Policy. No NRC-identified or self-revealing findings were identified during this inspection. If you contest the violations or significance of these NCVs, 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.

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 the NRC Public Document Room in accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding."

Sincerely,/RA/

Fred L. Bower, III, Chief Reactor Projects Branch 3 Division of Reactor Projects Docket Nos. 50-272 and 50-311 License Nos. DPR-70 and DPR-75

Enclosure:

Inspection Report 05000272/2017002 and 05000311/2017002

w/Attachment:

Supplementary Information cc w/encl: Distribution via ListServ

SUMMARY

Inspection Report (IR) 05000272/2017002, 05000311/2017002; 04/01/2017 - 06/30/2017; Salem Nuclear Generating Station Units 1 and 2 (Salem); Routine Integrated Inspection Report. This report covered a three-month period of inspection by resident inspectors and announced inspections performed by regional inspectors. No NRC-identified or self-revealing findings were identified during this inspection. The significance of most findings is indicated by their color (i.e.,

greater than Green, or Green, White, Yellow, Red) and determined using Inspection Manual Chapter (IMC) 0609, "Significance Determination Process (SDP)," dated October 28, 2016. Cross-cutting aspects are determined using IMC 0310, "Aspects Within Cross-Cutting Areas," dated December 4, 2014. All violations of NRC requirements are dispositioned in accordance with the NRC's Enforcement Policy, dated November 1, 2016. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 6.

Other Findings

Two violations of very low safety significance that were identified by PSEG were reviewed by the inspectors. Corrective actions (C/As) taken or planned by PSEG have been entered into PSEG's corrective action program (CAP). These violations and C/A tracking numbers are listed in Section 4OA7 of this report.

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REPORT DETAILS

Summary of Plant Status Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On May 15, operators identified a rise in primary to secondary leakage, indicating a possible steam generator (S/G) tube leak that was confirmed on May 16. The leak subsequently stabilized at a rate of approximately seven gallons per day. Around May 26, the leak rate slowly fell to less than the minimum detectable level of one gallon per day and remained below that threshold for the remainder of the inspection period. The unit remained at or near 100 percent RTP for the remainder of the inspection period. Unit 2 began the inspection period at 100 percent RTP. The unit completed a planned shutdown (S/D) on April 14 for the 2R22 refueling outage. On April 20, PSEG declared an Unusual Event due to elevated hydrazine levels in the containment atmosphere. A reactor startup was commenced on May 29 and full RTP was reached on June 2. The unit remained at or near 100 percent RTP for the remainder of the inspection period.

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R01 Adverse Weather Protection

Main article: IP 71111.01

.1 Summer Readiness of Offsite and Alternate Alternating Current Power Systems

a. Inspection Scope

The inspectors reviewed plant features and procedures for the operation and continued availability of the offsite and alternate alternating current (AC) power system to evaluate readiness of the systems prior to seasonal high grid loading on May 31. The inspectors reviewed PSEG's procedures affecting these areas and the communications protocols between the transmission system operator and PSEG. This review focused on changes to the established program and material condition of the offsite and alternate AC power equipment. The inspectors assessed whether PSEG established and implemented appropriate procedures and protocols to monitor and maintain availability and reliability of both the offsite AC power system and the onsite alternate AC power system. The inspectors evaluated the material condition of the associated equipment by interviewing the responsible system manager, reviewing condition reports and open work orders (WOs), and walking down portions of the offsite and AC power systems including the 500 kilovolt (kV) switchyard.

b. Findings

No findings were identified.

1R04 Equipment Alignment

.1 Partial System Walkdown

Main article: IP 71111.04Q

a. Inspection Scope

The inspectors performed partial walkdowns of the following systems: Unit 1, 12 Component cooling (CC) pump out of service (OOS) for degraded outboard bearing on June 9 Unit 2, Unborated water system isolation during S/D on April 17 Unit 2, Spent fuel (SF) pool cooling after full core offloaded on April 25 Unit 2, 21 Service water (SW) nuclear header following restoration and during subsequent planned maintenance on header components on May 8 Unit 2, 2B and 2C emergency diesel generator (EDG) mechanical and electrical support systems during planned maintenance on the 2A EDG on May 15 Common, Control area ventilation following a radiation monitor failure on May 8 The inspectors selected these systems based on their risk-significance relative to the reactor safety cornerstones at the time they were inspected. The inspectors reviewed applicable operating procedures, system diagrams, and notifications (NOTFs). The inspectors also performed field walkdowns of accessible portions of the systems to verify system components and support equipment were aligned correctly and were operable. The inspectors examined the material condition of the components and observed operating parameters of equipment to verify that there were no deficiencies. The inspectors also reviewed whether PSEG staff had properly identified equipment issues and entered them into the CAP for resolution with the appropriate significance characterization.

b. Findings

No findings were identified.

1R05 Fire Protection

.1 Resident Inspector Quarterly Walkdowns

Main article: IP 71111.05Q

a. Inspection Scope

The inspectors conducted tours of the areas listed below to assess the material condition and operational status of fire protection (FP) features. The inspectors verified that PSEG controlled combustible materials and ignition sources in accordance with administrative procedures. The inspectors verified that FP and suppression equipment was available for use as specified in the area pre-fire plan, and passive fire barriers were maintained in good material condition. The inspectors also verified that station personnel implemented compensatory measures for OOS, degraded, or inoperable FP equipment, as applicable, in accordance with procedures.

Unit 1, 4kV and 480V switchgear (SWGR) rooms on April 26 Unit 1, Diesel fuel oil storage tank and fuel oil transfer pump areas on May 15 Unit 1, EDGs and fuel oil day tank area on May 15 Unit 1, Turbine building on June 22 Unit 2, 230V/460V SWGR for continuous fire watch on April 3 Unit 2, Auxiliary building SF pool cooling pump area on April 26

b. Findings

No findings were identified.

1R06 Flood Protection Measures

Main article: IP 71111.06

Internal Flooding Review

a. Inspection Scope

The inspectors reviewed the site flooding analysis and plant procedures to identify internal flooding susceptibilities for the site. The inspectors' review focused on the Unit 1 and Unit 2 4 kV vital SWGR rooms of the Auxiliary Building. The inspectors verified the adequacy of equipment and wall seals located below the flood line, doorway flood curbs, and floor drains. They discussed the condition of the fire water header piping, the largest potential source of flood water in this area, with the Salem FP engineer as well as reviewed the CAP to determine if PSEG was identifying and correcting problems associated with flood mitigation features.

b. Findings

No findings were identified.

==1R07 Heat Sink Performance (711111.07A - 1 sample)

a. Inspection Scope

The inspectors reviewed the Unit 2 22 charging pump gear oil cooler heat exchanger (HX) readiness and availability to perform its safety functions. The inspectors observed portions of the as-found inspection of the HX. The inspectors discussed the results of the most recent inspection with engineering staff and reviewed the results of the eddy current testing performed to measure the HX tube wall thickness. The inspectors verified that PSEG initiated appropriate C/As for identified deficiencies. The inspectors also verified that the number of tubes plugged within the HX did not exceed the maximum amount allowed.

b. Findings

No findings were identified.

1R08 In-Service Inspection

==

Main article: IP 71111.08P

a. Inspection Scope

From April 24 to May 3, the inspectors conducted an inspection and review of in-service inspection (ISI) activities in order to assess the effectiveness of PSEG's program for monitoring degradation of the reactor coolant system boundary, risk-significant piping boundaries, and the containment system boundaries during the 2R22 refueling outage.

Non-destructive Examination and Welding Activities (IP Section 02.01) The inspectors observed a sample of in-process non-destructive examinations (NDE), reviewed completed documentation, and interviewed PSEG personnel to verify that the NDE activities performed as part of the fourth interval, second period, of the Unit 2 ISI program were conducted in accordance with the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 2004 Edition with no Addenda. For augmented examinations, the inspectors verified that activities were performed in accordance with PSEG's augmented inspection program and procedures, and with any applicable industry guidance documents. The inspectors verified that indications and effects, if present, were dispositioned in accordance with the ASME Code or an NRC-approved alternative, and verified that relevant indications were compared to previous examinations to determine if any changes had occurred. Activities included a review of ultrasonic testing (UT), liquid penetrant testing (LPT), and visual testing (VT). The inspectors reviewed certifications of the NDE technicians performing the examinations and verified that the inspections were performed in accordance with qualified NDE procedures and industry guidance. For UT activities, the inspectors also verified the calibration of equipment used to perform the examinations. The inspectors verified that the test results were reviewed and evaluated by certified Level III NDE personnel as directed by PSEG procedures and that the parameters used in the test were in accordance with the limitations, precautions, and prerequisites specified in the test procedure. ASME Code Required Examinations: Direct observation of the manual UT of the 22 S/G shell to upper head weld (22-STG-USUH).

Record review of the manual UT of the auxiliary feedwater (AFW) pipe to pipe weld (4-AF-2241-3). Other Augmented, License Renewal, or Industry Initiative Examinations: Record review of the LPT of the residual heat removal (RHR) pipe to elbow weld (12-RH-2252-39) and adjacent surface material as part of the owner augmented program to exam components susceptible to external chloride stress corrosion cracking.

Direct observation of the remote UT of the baffle-former bolts and VT of the baffle-former assembly, including baffle-edge bolts, inside the reactor vessel as part of the aging management program MRP-227-A, "Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines." The inspectors verified that UT results were dispositioned in accordance with PSEG's procedure and C/As were in accordance with NRC requirements. The inspectors verified that PSEG's actions were in-progress to replace all of the potentially degraded baffle-former bolts prior to Unit 2 restart from the 2R22 refueling outage, which included 9 bolts with UT indications, out of a total of 832. PSEG replaced a total of 129 baffle-former bolts. The inspectors did not identify any deviations from MRP-227-A.

Examination of Previous Indications The inspectors did not review any previous indications because there were no relevant indications from the previous outage that required re-examination or evaluation for continued service at this time. Welding on Pressure Boundary Systems The inspectors reviewed the pressure boundary risk-significant welding activity, including the associated NDE, of multiple pipe welds (2-RH-105-A/B/D, 2-RH-105-1, 2-RH-104-F) and one pipe to valve weld (2-RH-105-2) as part of a repair/replacement activity in the RHR system. Specifically, the scope of the activity was to cut out and replace a section of piping identified as having surface indications with a spool of new pipe. The inspectors directly observed a sample of in-shop welding and performed a documentation review of the remaining welding activities to verify that the welding, NDE, and final acceptance were performed in accordance with the ASME Code requirements. The inspectors reviewed the weld procedure specification to ensure it contained the required essential and supplemental essential weld variables and that those variables were within the ranges demonstrated by the supporting qualification record. The inspectors also reviewed the weld records to determine if they were performed with the base and weld filler materials listed in the welding specification. The repair was performed under WO 60130174.

Pressurized Water Reactor Vessel Upper Head Penetration Inspection Activities (IP Section 02.02) No reactor vessel head inspections were performed during this refueling outage. The inspectors verified that the reactor pressure vessel upper head penetration ultrasonic weld examinations and the bare metal visual examinations were scheduled in accordance with the periodicity requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.55a and ASME Code Case N-729-1, "Alternative Examination Requirements for pressurized water reactor (PWR) Reactor Vessel Upper Heads," to ensure the structural integrity of the reactor vessel head pressure boundary. Because the Unit 2 reactor vessel upper head was replaced with nozzles and welds made of PWSCC-resistant materials, the examinations do not have to be performed every refueling outage. Boric Acid Corrosion Control Inspection Activities (IP Section 02.03)

The inspectors reviewed Salem's boric acid corrosion control program as described in PSEG procedures and discussed the program requirements with the boric acid program owner. The inspectors performed independent walkdowns of various plant areas inside the containment building and reviewed photographic records of several identified boric acid leakage locations. The inspectors reviewed a sample of condition reports to verify that degraded or non-conforming conditions were identified properly within the CAP.

The inspectors reviewed two engineering evaluations (listed in the documents reviewed section) performed for boric acid found on piping and components to determine whether PSEG properly applied applicable corrosion rates to the affected components and properly assessed the effects of corrosion induced wastage on structural or pressure boundary integrity. The inspectors also reviewed the C/As planned and/or performed for those areas identified with evidence of boric acid leaks. Samples were selected based on actions for repair, component function, significance of leakage, and location where direct leakage or impingement on adjacent locations could cause degradation of safety system components. S/G Tube Inspection Activities (IP Section 02.04) The inspectors directly observed a sample of the S/G eddy current tube examinations, which consisted of full length bobbin inspection of 100 percent of all active tubes in each of the four S/Gs; +Point probe inspection of all Appui (AREVA-specific S/G tube supports) locations in all active tubes; array probe inspection of the top-of-tubesheet peripheral tubes and no-tube lane regions; and +Point probe inspection of any special interest tubes. The inspectors reviewed the results of the examinations to determine how well PSEG was able to predict future tube performance by comparing the results with the values predicted in the previous outage operational assessment. The inspectors then evaluated the scope of eddy current testing to determine if areas of potential degradation were inspected, noting if areas known to represent eddy current challenges were included. The inspectors also compared the S/G tube eddy current examination scope and expansion criteria with TS requirements to determine whether PSEG was in compliance with these requirements.

The inspectors verified that no in-situ pressure testing was required and no primary-to-secondary leakage occurred over the operating cycle. The inspectors verified that the S/G tube examination screening criteria was in accordance with the Electric Power Research Institute Steam Generator Guidelines and that the examination technique specification sheets used for the exams were appropriate for the expected types of tube degradation. The inspectors remotely observed a Qualified Data Analyst's review of five S/G tubes to determine that proper eddy current analysis techniques were applied.

Identification and Resolution of Problems (IP Section 02.05) The inspectors reviewed a sample of Salem Unit 2 C/A reports, which identified NDE indications, deficiencies, and other non-conforming conditions since the previous refueling outage and during the current outage. The inspectors verified that non-conforming conditions were properly identified, characterized, evaluated, and that C/As were identified and entered into the CAP for resolution.

b. Findings

No findings were identified.

1R11 Licensed Operator Requalification Program

Main article: IP 71111.11Q

.1 Quarterly Review of Licensed Operator Requalification Testing and Training

a. Inspection Scope

The inspectors observed licensed operator simulator training on June 13, which included a CC HX outlet valve failure, a reactor coolant pump (RCP) seal failure, and a small break loss of coolant accident. The inspectors evaluated operator performance during the simulated event and verified completion of risk significant operator actions, including the use of abnormal and emergency operating procedures. The inspectors assessed the clarity and effectiveness of communications, implementation of actions in response to alarms and degrading plant conditions, and the oversight and direction provided by the control room supervisor. The inspectors verified the accuracy and timeliness of the emergency classification made by the shift manager (SM) and the technical specification (TS) action statements entered by the shift technical advisor. Additionally, the inspectors assessed the ability of the crew and training staff to identify and document crew performance problems.

b. Findings

No findings were identified.

.2 Quarterly Review of Licensed Operator Performance in the Main Control Room

a. Inspection Scope

The inspectors observed and reviewed the reactor S/D for refuel outage, 2R22, on April 14. The inspectors observed operator performance to verify that procedure use, crew communications, and coordination of activities between work groups similarly met established expectations and standards.

b. Findings

No findings were identified.

1R12 Maintenance Effectiveness

Main article: IP 71111.12Q

a. Inspection Scope

The inspectors reviewed the samples listed below to assess the effectiveness of maintenance activities on structure, system, and component (SSC) performance and reliability. The inspectors reviewed system health reports, CAP documents, maintenance WOs, and maintenance rule (MR) basis documents to ensure that PSEG was identifying and properly evaluating performance problems within the scope of the MR. For each sample selected, the inspectors verified that the SSC was properly scoped into the MR in accordance with 10 CFR 50.65 and verified that the (a)(2) performance criteria established by PSEG staff was reasonable. As applicable, for SSCs classified as (a)(1), the inspectors assessed the adequacy of goals and C/As to return these SSCs to (a)(2). Additionally, the inspectors ensured that PSEG staff was identifying and addressing common cause failures that occurred within and across MR system boundaries.

Unit 1, S/G drains and blowdown on May 15 Unit 1, Radiation monitors on May 31 Common, 4kV breakers, and associated system functional impacts, following multiple failures to close on May 2

b. Findings

No findings were identified.

1R13 Maintenance Risk Assessments and Emergent Work Control

Main article: IP 71111.13

a. Inspection Scope

The inspectors reviewed station evaluation and management of plant risk for the maintenance and emergent work activities listed below to verify that PSEG performed the appropriate risk assessments prior to removing equipment for work. The inspectors selected these activities based on potential risk significance relative to the reactor safety cornerstones. As applicable for each activity, the inspectors verified that PSEG personnel performed risk assessments as required by 10 CFR 50.65(a)(4) and that the assessments were accurate and complete. When PSEG performed emergent work, the inspectors verified that operations personnel promptly assessed and managed plant risk. The inspectors reviewed the scope of maintenance work and discussed the results of the assessment with the station's probabilistic risk analyst to verify plant conditions were consistent with the risk assessment. The inspectors also reviewed the TS requirements and inspected portions of redundant safety systems, when applicable, to verify risk analysis assumptions were valid and applicable requirements were met.

Unit 1, Fire risk with 23 charging pump unavailable on May 8 Unit 1, Identification of primary-to-secondary leakage on 13 S/G on May 15 Unit 2, Yellow risk during 2A EDG outage on April 3 Unit 2, Yellow risk during 21 CC HX unavailability on May 8 Unit 2, Elevated risk and protected equipment verification during entry into, and exit from, reduced inventory control on May 23 and May 24 Common, Chilled water system cross-tie freeze seal in support of valve maintenance on April 11

b. Findings

No findings were identified.

1R15 Operability Determinations and Functionality Assessments

Main article: IP 71111.15

a. Inspection Scope

The inspectors reviewed operability determinations for the following degraded or non-conforming conditions based on the risk significance of the associated components and systems: Unit 1, 1C Safeguards equipment control cabinet door taped closed with monitoring instruments on April 25 Unit 1, 1 SW bay following emergent failure of the 1 SW bay sump pump on May 18 Unit 2, 22 Safety injection pump following as-found low flow condition on April 24 Unit 2, 21 SW nuclear leader degraded joint wall thickness on April 26 Unit 2, 22 Containment fan coil unit (CFCU) cooler tube blockage on April 28 Common, Log statements related to compliance with TS action statements on June 16 The inspectors evaluated the technical adequacy of the operability determinations to assess whether TS operability was properly justified and the subject component or system remained available such that no unrecognized increase in risk occurred. The inspectors compared the operability and design criteria in the appropriate sections of the TSs and Updated Final Safety Analysis Report (UFSAR) to PSEG's evaluations to determine whether the components or systems were operable. The inspectors confirmed, where appropriate, compliance with bounding limitations associated with the evaluations.

b. Findings

No findings were identified.

1R18 Plant Modifications

Main article: IP 71111.18

Permanent Modifications

a. Inspection Scope

The inspectors reviewed the permanent modifications listed below. The inspectors verified that the design bases, licensing basis, and performance capability of the affected systems were not degraded by the modification. In addition, the inspectors reviewed modification documents associated with the plant modifications, to verify the adequacy of the designs. The inspectors also interviewed engineering and operations personnel, to verify plant staff awareness and understanding of the modifications was consistent with design documents and installation.

Unit 2, Design Change Package (DCP) 80109340, 21 RCP S/D seal number 1 modification on April 17 Unit 2, DCP 80111452, replace source range and intermediate range instrumentation on June 13

b. Findings

No findings were identified.

1R19 Post-Maintenance Testing

Main article: IP 71111.19

a. Inspection Scope

The inspectors reviewed the post-maintenance tests for the maintenance activities listed below to verify that procedures and test activities adequately tested the safety functions that may have been affected by the maintenance activity, that the acceptance criteria in the procedure were consistent with the information in the applicable licensing basis and/or design basis documents, and that the test results were properly reviewed and accepted and problems were appropriately documented. The inspectors also walked down the affected job site, observed the pre-job brief and post-job critique where possible, confirmed work site cleanliness was maintained, and witnessed the test or reviewed test data to verify quality control hold point were performed and checked, and that results adequately demonstrated restoration of the affected safety functions.

Unit 1, 11SW223 CFCU flow control valve replacement on June 27 Unit 2, 21 Loop T cold resistance temperature detector swap after primary ground on April 5 Unit 2, Emergency core cooling system (ECCS) containment sump channel II replacement on May 8 Unit 2, 21 SW nuclear header following underground piping inspection and header outage on May 9 Unit 2, 2C EDG SW supply valve following valve and actuator replacement on May 15 Unit 2, RHR valves following corrective and preventive maintenance on May 17 Unit 2, RHR hot leg injection piping replacement on May 23

b. Findings

No findings were identified.

1R20 Refueling and Other Outage Activities

Main article: IP 71111.20

a. Inspection Scope

The inspectors reviewed the station's work schedule and outage risk plan for the Unit 2 maintenance and refueling outage (2R22), conducted April 14 through May 29. The inspectors reviewed PSEGs development and implementation of outage plans and schedules to verify that risk, industry experience, previous site-specific problems, and defense-in-depth were considered. During the outage, the inspectors observed portions of the S/D and cooldown processes and monitored controls associated with the following outage activities: Configuration management, including maintenance of defense-in-depth, commensurate with the outage plan for the key safety functions and compliance with the applicable TSs when taking equipment OOS Implementation of clearance activities and confirmation that tags were properly hung and that equipment was appropriately configured to safely support the associated work or testing Installation and configuration of reactor coolant pressure, level, and temperature instruments to provide accurate indication and instrument error accounting Status and configuration of electrical systems and switchyard activities to ensure that TSs were met Monitoring of decay heat removal operations Impact of outage work on the ability of the operators to operate the SF pool cooling system Reactor water inventory controls, including flow paths, configurations, alternative means for inventory additions, and controls to prevent inventory loss Activities that could affect reactivity Maintenance of secondary containment as required by TSs Refueling activities, including fuel handling and fuel receipt inspections Fatigue management Tracking of startup prerequisites, walkdown of the drywell (primary containment) to verify that debris had not been left which could block the emergency core cooling system suction strainers, and startup and ascension to full power operation Identification and resolution of problems related to refueling outage activities

b. Findings

No findings were identified.

1R22 Surveillance Testing

Main article: IP 71111.22

a. Inspection Scope

The inspectors observed performance of surveillance tests and/or reviewed test data of selected risk-significant SSCs to assess whether test results satisfied TSs, the UFSAR, and PSEG procedure requirements. The inspectors verified that test acceptance criteria were clear, tests demonstrated operational readiness and were consistent with design documentation, test instrumentation had current calibrations and the range and accuracy for the application, tests were performed as written, and applicable test prerequisites were satisfied. Upon test completion, the inspectors considered whether the test results supported that equipment was capable of performing the required safety functions. The inspectors reviewed the following surveillance tests: Unit 1, S/G blowdown radiation monitor testing on April 19 Unit 2, 21 RHR in-service test on April 5 Unit 2, Full flow AFW test on April 14 Unit 2, Containment ventilation valves, 2VC5(6) (primary containment isolation valve), on April 15 Unit 2, Containment isolation Phase B on April 17

b. Findings

No findings were identified. Cornerstone: Emergency Preparedness 1EP2 Alert and Notification System Evaluation (71114.02 - 1 Sample)

a. Inspection Scope

An onsite review was conducted to assess the maintenance and testing of the Alert and Notification System (ANS). During this inspection, the inspectors conducted a review PSEG's siren testing and maintenance programs. The inspectors reviewed the associated ANS procedures and the Federal Emergency Management Agency approved ANS Design Report to ensure PSEG's compliance with design report commitments for system maintenance and testing. Title 10 CFR 50.47(b)(5) and the related requirements of 10 CFR Part 50, Appendix E, were used as reference criteria.

b. Findings

No findings were identified. 1EP3 Emergency Response Organization Staffing and Augmentation System (71114.03 - 1 Sample)

a. Inspection Scope

The inspectors conducted a review of the Salem Emergency Response Organization (ERO) augmentation staffing requirements and the process for notifying and augmenting the ERO. The review was performed to verify the readiness of key PSEG staff to respond to an emergency event and to verify PSEG's ability to activate their emergency response facilities (ERFs) in a timely manner. The inspectors reviewed: the PSEG Nuclear LLC Emergency Plan for ERF activation and ERO staffing requirements; the ERO duty roster; applicable station procedures; augmentation test results; the most recent drive-in drill report; and C/A reports related to this inspection area. The inspectors also reviewed a sample of ERO responder training records to verify training and qualifications were up to date. Title 10 CFR 50.47(b) (2) and related requirements of 10 CFR Part 50, Appendix E, were used as reference criteria.

b. Findings

No findings were identified. 1EP5 Maintaining Emergency Preparedness

a. Inspection Scope

(71114.05 - 1 Sample) The inspectors reviewed a number of activities to evaluate the efficacy of PSEG's efforts to maintain the Salem emergency preparedness (EP) program. The inspectors reviewed: memoranda of agreement with offsite agencies; PSEG's maintenance of equipment important to EP; records of emergency planning zone population estimates; and provisions for, and implementation of, primary, backup, and alternative ERF maintenance.

The inspectors further evaluated PSEG's ability to maintain the Salem EP program through their identification and correction of EP weaknesses, by reviewing a sample of drill reports, actual event reports, self-assessments, and 10 CFR 50.54(t) reviews. Also, the inspectors reviewed a sample of EP-related NOTFs initiated at Salem from July 2015 through May 2017. Title 10 CFR 50.47(b) and the related requirements of 10 CFR Part 50, Appendix E, were used as reference criteria.

b. Findings

No findings were identified.

1EP6 Drill Evaluation

Main article: IP 71114.06

.1 Emergency Preparedness Drill Observation

a. Inspection Scope

The inspectors evaluated the conduct of a routine PSEG emergency drill on June 20 to identify any weaknesses and deficiencies in the classification, notification, and protective action recommendation development activities. The inspectors observed emergency response operations in the simulator and technical support center to determine whether the event classification, notifications, and protective action recommendations were performed in accordance with procedures. The inspectors also reviewed issues related to PSEG's critique to compare inspector observations with those identified by PSEG staff in order to evaluate PSEG's critique, and to verify whether the PSEG staff was properly identifying weaknesses and entering them into the CAP.

b. Findings

No findings were identified.

.2 Emergency Preparedness Training Observations

a. Inspection Scope

The inspectors observed a simulator training evolution for licensed operators on June 27, which required emergency plan implementation by an operations crew. PSEG planned for this evolution to be evaluated and included in performance indicator (PI) data regarding drill and exercise performance. The inspectors observed event classification and notification activities performed by the crew. The inspectors also attended the post-evolution critique for the scenario. The focus of the inspectors' activities was to note any weaknesses and deficiencies in the crew's performance and ensure that PSEG evaluators noted the same issues and entered them into the CAP.

b. Findings

No findings were identified.

RADIATION SAFETY

Cornerstones: Occupational and Public Radiation Safety

2RS1 Radiological Hazard Assessment and Exposure Controls

Main article: IP 71124.01

a. Inspection Scope

The inspectors reviewed PSEG's performance in assessing and controlling radiological hazards in the workplace. The inspectors used the requirements contained in 10 CFR Part 20, TSs, Regulatory Guide 8.38, and the procedures required by TSs as criteria for determining compliance. Radiological Hazards Control and Work Coverage (1 sample) The inspectors evaluated in-plant radiological conditions and performed independent radiation measurements during facility walkdowns and observation of radiological work activities. The inspectors assessed whether posted surveys; radiation work permits; worker radiological briefings and radiation protection (RP) job coverage; the use of continuous air monitoring, air sampling and engineering controls; and dosimetry monitoring were consistent with the present conditions. The inspectors examined the control of highly activated or contaminated materials stored within the SF pools and the posting and physical controls for selected high radiation areas (HRAs), locked HRAs and very HRAs to verify conformance with the occupational PI. Radiation Worker Performance and Radiation Protection Technician Proficiency (1 sample) The inspectors evaluated radiation worker performance with respect to RP work requirements. The inspectors evaluated RP technicians in performance of radiation surveys and in providing radiological job coverage.

b. Findings

No findings were identified.

2RS2 Occupational As Low As is Reasonably Achievable Planning and Controls

(71124.02 - 2 samples)

a. Inspection Scope

The inspectors assessed PSEG's performance with respect to maintaining occupational individual and collective radiation exposures as low as is reasonably achievable (ALARA). The inspectors used the requirements contained in 10 CFR Part 20, Regulatory Guides 8.8 and 8.10, TSs, and procedures required by TSs as criteria for determining compliance.

Inspection Planning

The inspectors conducted a review of Salem's collective dose history and trends; ongoing and planned radiological work activities; previous post-outage ALARA reviews; radiological source term history and trends; and ALARA dose estimating and tracking procedures. Verification of Dose Estimates and Exposure Tracking Systems (1 sample) The inspectors reviewed the current annual collective dose estimate; basis methodology; and measures to track, trend, and reduce occupational doses for ongoing work activities. The inspectors evaluated the adjustment of exposure estimates, or re-planning of work. The inspectors reviewed post-job ALARA evaluations of excessive exposure.

Radiation Worker Performance (1 sample)

The inspectors observed radiation worker and RP technician performance during radiological work to evaluate worker ALARA performance according to specified work controls and procedures. Workers were interviewed to assess their knowledge and awareness of planned and/or implemented radiological and ALARA work controls.

b. Findings

No findings were identified.

OTHER ACTIVITIES

4OA1 Performance Indicator Verification

Main article: IP 71151

.1 Unplanned Scrams, Unplanned Power Changes, and Unplanned Scrams with

Complications (6 samples)

a. Inspection Scope

The inspectors reviewed PSEG submittals for the following Initiating Events Cornerstone PIs for the period of July 1, 2016, through June 30, 2017.

Unit 1 Unplanned Scrams (IE01) Unit 2 Unplanned Scrams (IE01) Unit 1 Unplanned Power Changes (IE03) Unit 2 Unplanned Power Changes (IE03)

Unit 1 Unplanned Scrams with Complications (IE04) Unit 2 Unplanned Scrams with Complications (IE04) To determine the accuracy of the PI data reported during those periods, inspectors used definitions and guidance contained in Nuclear Energy Institute (NEI) Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7. The inspectors reviewed PSEG operator narrative logs, maintenance planning schedules, condition reports, event reports, and NRC integrated IRs to validate the accuracy of the submittals.

b. Findings

No findings were identified.

.2 Emergency Preparedness Performance Indicators (3 samples)

a. Inspection Scope

The inspectors reviewed data for the following three EP PIs: (1) drill and exercise performance; (2) ERO drill participation; and, (3) ANS reliability. The last NRC EP inspection at Salem Nuclear Generating Station was conducted in the second calendar quarter of 2016. Therefore, the inspectors reviewed supporting documentation from EP drills and equipment tests from the second calendar quarter of 2016 through the first calendar quarter of 2017 to verify the accuracy of the reported PI data. The review of the PIs was conducted in accordance with NRC Inspection Procedure 71151. The acceptance criteria documented in NEI 99-02, "Regulatory Assessment Performance Indicator Guidelines," Revision 7, was used as reference criteria.

b. Findings

No findings were identified.

4OA2 Problem Identification and Resolution

Main article: IP 71152

.1 Routine Review of Problem Identification and Resolution Activities

a. Inspection Scope

As required by Inspection Procedure 71152, "Problem Identification and Resolution," the inspectors routinely reviewed issues during baseline inspection activities and plant status reviews to verify PSEG entered issues into their CAP at an appropriate threshold, gave adequate attention to timely C/As, and identified and addressed adverse trends. In order to assist with the identification of repetitive equipment failures and specific human performance issues for follow-up, the inspectors performed a daily screening of items entered into their CAP and periodically attended condition report screening meetings. The inspectors also confirmed, on a sampling basis, that, as applicable, for identified defects and non-conformances, PSEG performed an evaluation in accordance with 10 CFR Part 21.

b. Findings

No findings were identified.

.2 Semi-Annual Trend Review

a. Inspection Scope

The inspectors performed a semi-annual review of site issues to identify trends that might indicate the existence of more significant safety concerns. As part of this review, the inspectors included repetitive or closely-related issues that may have been documented by PSEG outside of the CAP, such as trend reports, PIs, major equipment problem lists, system health reports, MR assessments, and maintenance or CAP backlogs. The inspectors also reviewed PSEG CAP database for the first and second quarters of 2017 to assess NOTFs written in various subject areas (equipment problems, human performance issues, etc.), as well as individual issues identified during the inspectors' daily condition report review (Section 4OA2.1). The inspectors reviewed the PSEG CAP trending data, conducted under LS-AA-125, to verify that PSEG personnel were appropriately evaluating and trending adverse conditions in accordance with applicable procedures.

b. Findings and Observations

No findings were identified. The inspectors noted that PSEG documented a number of trends in the first and second quarters of 2017, most notably: PSEG documented a trend of poor housekeeping issues identified by the inspectors (NOTF 20767496). The inspectors noted that housekeeping issues could impact the ability to properly control transient combustibles in accordance with the FP program, (NOTF 20764948); and could also impact fire-in-(a)(4) risk management actions, as documented in NCV 05000272/2017001-02.

PSEG documented a trend of safety injection check valve back-leakage (NOTF 20766650). PSEG identified issues during refuel outage surveillance testing, entered the issues in CAP, and promptly corrected the issues. ECCS check valve back-leakage has challenged the station for a number of years, as demonstrated by a 2014 freeze seal to replace a leaking check valve in a hi-head cold leg injection line, and as documented in a previous problem identification and resolution sample in NRC IR 2012-005.

PSEG completed industry benchmarking in February 2017, and determined the station was performing numerous containment entries, at full power, when compared to other stations (NOTF 20754274). PSEG performed the benchmarking efforts following a personnel airlock door seal failure on both the inner and outer doors (NOTF 20741576) in September 2016. PSEG determined the apparent cause of the airlock seal failures was attributed to not replacing the gaskets at the specified 18-month frequency, which was further attributed to satisfactory leak rate testing consistently being performed at an increased weekly frequency in accordance with the containment leak rate testing program due to the high number of containment entries.

PSEG identified a trend from March 2016 to March 2017, of 12 NOTFs written for FP system jockey pump performance problems (NOTF 20759159) that mostly consisted of breaker trips and short cycling. Inspectors noted these conditions frequently challenged the Salem FP system reliability, and often required opening the piping header cross-tie with Hope Creek as a compensatory action, to maintain the required system header pressure in accordance with station FP program procedures. The inspectors noted that PSEG has taken a number of actions to try and resolve the performance problems, including replacing the jockey pump. The inspectors noted that since corrective maintenance was performed on the jockey pump motor breaker on March 31 (NOTF 20758865), the jockey pump has performed its intended function thus improving Salem FP system reliability.

The inspectors identified a trend of non-CAP maintenance feedback, identified as N3 NOTFs, written for issues where N1 NOTFs (CAP) were also appropriate. Specifically, N1 NOTFs are required, in part, for plant equipment conditions adverse to quality as described in LS-AA-120, "Issue Identification and Screening Process," Revision 15. Additionally, N1 NOTFs are reviewed and screened for operability, reportability, and maintenance rule functional failures. N3 NOTFs are intended as feedback to the WO planning process as discussed in MA-AA-716-010-1000, "Maintenance Planning," Revision 9. The inspectors identified the following N3 NOTFs also warranted N1 NOTFs in accordance with station procedures: N3 20762289 was written for a safeguards equipment loading time delay relay as-found calibration out of specification during planned testing. The relay was adjusted and the as-left value was satisfactory. PSEG captured the issue under N1 20762302 following inspector questioning.

N3 20761539 was written for a reactor coolant system mid-loop level transmitter found as-found calibration out of specification. The transmitter was adjusted and the as-left value was satisfactory. PSEG captured the issue under N1 20762569 following inspector questioning.

N3 20762722 was written for a 2C EDG lube oil heater element mounting connection that was found damaged during planned maintenance. The mounting connection and heater element were replaced. PSEG captured the issue under N1 20762927 following inspector questioning.

N3 20760954 was written for a 2A EDG jacket water valve actuator air leak discovered during planned maintenance. The valve diagnostic testing was completed satisfactory, and the air leak was allocated to a future valve actuator overhaul. PSEG captured the issue under N1 20762898 following inspector questioning.

Three N3 NOTFs were written for Unit 2 safety injection accumulator level transmitter as-found values being out of specification: 20760957, 20760958, and 20762955. The transmitters were adjusted and the as-left values were satisfactory. After questioning whether an N1 was warranted to capture the trend in Unit 2 level transmitter values found out of specification, PSEG captured an adverse trend associated with Unit 2 safety injection accumulator level transmitters under N1 NOTF 20767271. The inspectors determined that none of the trends documented above were of more than minor safety significance in accordance with IMC 0612, Appendix B, Issue Screening.

4OA3 Follow-Up of Events and Notices of Enforcement Discretion

Main article: IP 71153

.1 Plant Events

a. Inspection Scope

For the plant events listed below, the inspectors reviewed and/or observed plant parameters, reviewed personnel performance, and evaluated performance of mitigating systems. The inspectors communicated the plant events to appropriate regional personnel, and compared the event details with criteria contained in IMC 0309, "Reactive Inspection Decision Basis for Reactors," for consideration of potential reactive inspection activities. As applicable, the inspectors verified that PSEG made appropriate emergency classification assessments and properly reported the event in accordance with 10 CFR 50.72 and 50.73. The inspectors reviewed PSEGs follow-up actions related to the events to assure that PSEG implemented appropriate C/As commensurate with their safety significance.

Unit 2, Unusual Event (EN 52699) due to hydrazine gas in containment on April 20

b. Findings

A PSEG-identified NCV is documented in Section

4OA7 of this report.

.2 (Closed) Licensee Event Report (LER) 05000272/2015-002-02:

Condition Prohibited by Technical Specification for One Channel of Steam Generator Level Indication Inoperable

a. Inspection Scope

On August 5, 2014, control room operators identified one S/G protection level channel indicator drifting high and approaching its channel deviation limit. On October 10, 2014, troubleshooting identified the level transmitter had exceeded its TS calibration acceptance criteria. The level transmitter was subsequently replaced. On February 12, 2015, PSEG completed a reportability evaluation and determined that the best estimate for when the transmitter would have exceeded its TS acceptance criteria was August 19, 2013. PSEG reported this condition under Revision 0 to this LER on April 10, 2015. After performing multiple revisions and updates to apparent cause evaluation (ACE) 70174936 conducted to assess to the equipment failure, PSEG submitted Revision 1 to this LER on July 6, 2015, and Revision 2 on November 16, 2016. Inspectors reviewed the ACE, associated C/As, interviewed station personnel, and walked down the associated plant indication.

b. Findings

A PSEG-identified NCV is documented in Section

4OA7 of this report.

This LER is closed.

4OA6 Meetings, Including Exit

On July 13, the inspectors presented the inspection results to Mr. Patrick Martino, Salem Plant Manager, and other members of the PSEG staff. The inspectors verified that no proprietary information was retained by the inspectors or documented in this report. PSEG management acknowledged and did not dispute the findings.

4OA7 Licensee-Identified Violations (994OA7 - 2 samples)

The following licensee-identified violations of NRC requirements were determined to be of very low safety significance (Green) and met the NRC Enforcement Policy criteria for being dispositioned as NCVs: 10 CFR 50.54(q)(2) states, in part, that the licensee shall follow and maintain the effectiveness of an emergency plan that meets the requirements in Appendix E to this part. Appendix E. IV.C.2, states, in part, that licensees shall establish and maintain the capability to assess, classify, and declare an emergency condition within 15 minutes after the availability of indications to plant operators that an emergency action level (EAL) has been exceeded and shall promptly declare the emergency condition as soon as possible following identification of the appropriate emergency classification level. Contrary to the above, on April 20, 2017, at 8:27 p.m., when the SM was informed of the presence of toxic gas (hydrazine) causing work stoppage and evacuation in the Salem Unit 2 containment, he did not promptly declare an emergency in accordance with the Salem EALs. The SM declared an Unusual Event, based on EAL HU.3.1, toxic gas that has adversely affected normal plant operations, at 9:10 p.m. (43 minutes after he had indications that the EAL was exceeded). PSEG identified that the emergency was not declared within the 15 minute requirement during a post-event review. This performance deficiency was more than minor because it was associated with the ERO performance attribute of the Mitigating System cornerstone, and adversely affected the cornerstone objective of ensuring that the licensee is capable of implementing adequate measures to protect the health and safety of the public in the event of a radiological emergency. The inspectors determined that the finding was of very low safety significance (Green) in accordance with IMC 0609, Appendix B, Figure 5.4-1, because the Unusual Event was declared in a degraded or untimely manner. PSEG entered this issue into the CAP as NOTF 20763130. Because the finding was of very low safety significance (Green) and was entered into PSEG's CAP, this issue is being treated as an NCV consistent with Section 2.3.2.a of the NRC's Enforcement Policy.

TS 3.3.1.1 requires that the reactor trip system instrumentation shown in Table 3.3-1 shall be operable. Table 3.3-1, Function 14, states there are a total of three channels, per S/G loop, of the water level low-low instrumentation. Action 6 states, in part, with the number of operable channels less than the total number of channels, the inoperable channel is to be placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Contrary to TS 3.3.1.1, one less than the total number of channels of S/G water level low-low was inoperable from August 19, 2013, until October 10, 2014, without being placed in the tripped condition. The condition was a licensee-identified violation because it was identified by operators in the main control room. Additional details are provided in the closure documentation for LER 05000272/2015-002-02 in report Section 4OA3.2. This performance deficiency was more than minor because it was associated with the equipment performance attribute of the Mitigating System cornerstone, and adversely affected the cornerstone objective of ensuring the reliability and capability of systems that respond to initiating events to prevent undesirable consequences. The inspectors determined that the finding was of very low safety significance (Green) in accordance with the screening criteria found in IMC 0609, Attachment 4, and Appendix A, Exhibit 2. PSEG entered this issue into the CAP as NOTF 20682366. Because the finding was of very low safety significance (Green) and was entered into PSEG's CAP, this issue is being treated as an NCV consistent with Section 2.3.2.a of the NRC's Enforcement Policy. ATTACHMENT:

SUPPLEMENTARY INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

C. McFeaters, Site Vice President

P. Martino, Plant Manager, Salem

M. Adair, Salem Fire Protection Program Engineer

S. Barr, Manager, Emergency Preparedness

T. Cachaza, Senior Regulatory Compliance Engineer

T. Cox, DFOST Cleaning and Inspection Project Manager

P. Fabian, Steam Generator Program Owner

T. Giles, ISI Program Owner

M. Hassler, Salem Radiation Protection Manager

A. Hess, Reactor Engineering Manager

J. Mallon, Compliance Director

D. Mannai, Senior Director Regulatory Operations

L. Martino, Radiation Protection Supervisor

P. Martitz, Radiation Protection Superintendent

D. Mora, PSEG NDE Level III

J. Owad, Design Engineering Manager

K. Powell, Salem Fire Marshall

J. Schmidt, Site Welding Engineer

W. Wikoff, Boric Acid Program Owner

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

Closed

05000272/LER-2015-002-02 LER Condition Prohibited by Technical Specification for One Channel of Steam Generator Level Indication Inoperable (Section 4OA7)

LIST OF DOCUMENTS REVIEWED

Indicates NRC-identified

Section 1R01: Adverse Weather Protection

Procedures

SC.OP-DL.ZZ-0007, Electrical Equipment Log, Revision 17

Notifications

20765795 20766467*

Section 1R04: Equipment Alignment

Procedures

Lesson Plan NOS05SFP000-08, Spent Fuel Pool Cooling System

OP-AA-108-101, Control of Equipment and System Status, Revision 8 S2.OP-SO.DG-0002, 2B Diesel Generator Operation, Revision 38 S2.OP-SO.DG-0003, 2C Diesel Generator Operation, Revision 42 S2.OP-SO.SF-0002, Spent Fuel Cooling System Operation, Revision 20 S2.OP-SO.SW-0001, Service Water Pump Operation, Revision 28 S2.OP-SO.SW-0002, 21 Nuclear Service Water Header Outage, Revision 26 S2.OP-SO.SW-0005, Service Water System Operation, Revision 42 S2.OP-SO.SW-0006, Service Water Accumulator Operation, Revision 10 S2.OP-SO.SWV-0001, Service Water Ventilation Operation, Revision 6 S2.OP-ST.ZZ-0007, Refueling Operations/Unborated Water Source Isolation Valves, Revision 0

Notifications

20732122

20762903*

20764104

20764723

20765346*

20765348*

20765349*

20767329*

20767330*

20764078

Drawings

205301, Sheet 1, Reactor Coolant, Revision 59

205328, Sheet 3, Chemical and Volume Control, Revision 41

205333, Spent Fuel Cooling, Revision 29

205342 Sh. 1, No. 2 Unit Service Water Nuclear Area, Revisions 81

205342 Sh. 2, No. 2 Unit Service Water Nuclear Area, Revisions 76

205342 Sh. 3, No. 2 Unit Service Water Nuclear Area, Revisions 80

211306, No.1 & 2 Units Diesel Generators Fuel Oil Instrument Schematic, Revision 11

Section 1R05: Fire Protection

Procedures

FP-AA-1081, Fire Protection Fundamentals, Revision 1

FP-SA-003, Actions for Inoperable Fire Protection - Salem Station, Revision 5

FP-SA-1161, Salem Pre-Fire Plan U/1 Turbine Generator Area, Revision 0

FP-SA-1151, Salem Pre-Fire Plan U/1 Turbine Generator Area, Revision 0

FP-SA-1141, Salem Pre-Fire Plan U/1 Turbine Generator Area, Revision 0

FP-SA-1543, Salem Pre-Fire Plan U/1 Auxiliary Feedwater Pumps Area, Revision 0

FP-SA-1545, Salem Pre-Fire Plan U/1 Diesel Fuel Oil Storage Area, Revision 0

FP-SA-1555, Salem Pre-Fire Plan U/1 Diesel Generator Area, Revision 0

FP-SA-2541, Salem Pre-Fire Plan U/2 460V Switchgear Rooms and Corridor, Revision 0

MA-SA-716-0236, Diesel Fuel Oil Storage Tank (DFOST) Pre-Outage Preparation Setup and Inspection, Revision 0

SH-PBD-AMP-XI.M30, Fuel Oil Chemistry Program Transient Combustible Permit for Eng. No.

20170411-05 #22 DFOST Rm. Unit 2 Aux Bldg., Fire

Area 2FA-D6-84E

Notifications

20707362

20758377

20761723*

20761754*

20761778*

20764270

20764271

20764472

20764741*

20765016*

Work Orders

30185808

60131050

Section 1R06: Flood Protection Measures

Procedures

SA-PRA-12, Salem Generating Station PRA Internal Flood Evaluation

Notifications

20645047

20659963

20660080

20661643

20701916

20708365 20736082

Section 1R07: Heat Sink Performance

Procedures

SC.MD-PM.ZZ-0026, Safety Related Lube and Gear Oil Cooler Internal Inspections,

Revision 12

Work Orders

30206746

30206815

30270185 30275385

Section 1R08: In-Service Inspection

Procedures

03-1246524, Instructions for Plug Inspection, Revision 12 54-ISI-400, Multi-Frequency Eddy Current Examination of Tubing, Revision 21 54-ISI-805, PDI Generic Procedure for Ultrasonic Examination of Reactor Pressure Vessel

Welds

PDI-UT-6, Revision 9 54-ISI-835, Ultrasonic Examination of Ferritic Pipe Welds, Revision 15

ER-AP-331, Boric Acid Corrosion Control (BACC) Program, Revision 5

ER-AP-331-1001, Boric Acid Corrosion Control (BACC) Inspection Locations, Implementation and Inspection Guidelines, Revision 6

ER-AP-331-1002, Boric Acid Corrosion Control Program Identification, Screening, and

Evaluation, Revision 6

ER-AP-331-1004, Boric Acid Corrosion Control (BACC) Training and Qualification, Revision 3

ER-AP-420, Steam Generator Management Program, Revision 13

ER-AP-420-0051, Conduct of Steam Generator Management Program Activities, Revision 18

WDI-STD-1073, Ultrasonic Test Procedure for the Inspection of Internal Hex Head

Baffle-Former Bolts with Welded Lock Bars, Revision 5 Welding Procedure Specification

WBM-NWP-7, Manual GTAW of P-8 to P-8 Material,

Revision 0

Notifications

20760868

20761976

20762331

20762486

20762545

20763513

20763664

20763703

20763976

Drawings

207498, Sheet 1, Penetration Sleeve Assembly Drawing, Revision 14

9046169, ASME Calibration Standard As-Built Drawing, Revision 0 A-62, Salem U2 - Weld/Hanger ISI Drawing of Residual Heat Removal System, Revision 2 B-68, Salem U2 - Weld/Hanger ISI Drawing of Residual Heat Removal System, Revision 2 B-123, Salem U2 - Weld/Hanger ISI Drawing of Auxiliary Feedwater System, Revision 1 BUEPSA/NGV9902, Sheet 1, General Drawing Replacement Steam Generators for Salem

Unit 2, Revision K

Work Orders

50182341

60130174

Miscellaneous

51-9118973, Qualified Eddy Current Examination Techniques for Salem Unit 2 AREVA 61/19T

Steam Generators, Revision 4 51-9225803, Salem Unit 2 Condition Monitoring for 2R20 and Final Operational Assessment for

Cycles 21 and 22, dated August 7, 2014 51-9266511, Salem Unit 2 2R22 Degradation Assessment - Spring 2017, dated April 21, 2017 51-9266999, Salem Unit 2 2R22 SG Eddy Current Inspection Plan, Revision 0 Boric Acid Evaluation for Component S2RC -22RC10 (NOTF 20760868), dated April 24, 2017 Boric Acid Evaluation for Component S2SJ -23SJ388 (NOTF 20699491), dated

September 11, 2015 Eddy Current Testing Screenshots for Steam Generator 22 Tubes R62C62, R73C77, and

R92C54, dated May 1, 2017 Eddy Current Testing Screenshots for Steam Generator 23 Tubes R86C64 and R92C62, dated

May 1, 2017 Integrated Strategic Plan for Long-Term Protection from External Chloride Stress Corrosion

Cracking, dated July 7, 2011

ISI-S2-LTP4, ISI Program Plan Fourth Ten-Year Inspection Interval Salem Generating Station

Unit 2, Revision 2

LR-N12-0157, Submittal of Relief Request Associated with the Fourth Ten-Year Inservice

Inspection (lSI) Interval Code Edition, dated June 7, 2012

LR-N13-0123, Request for Authorization to Continue Using a Risk-Informed lnservice Inspection

Alternative to the ASME Boiler and Pressure Vessel Code Section XI Requirements for Class 1 and 2 Piping, dated July 9, 2013

LR-N16-0025, Salem Unit 2 Owner's Activity Report for S2RFO21, dated February 26, 2016 PSEG Nuclear Repair Program Manual, Revision 22

PT Data Sheet for Weld 2-RH-105-D, dated May 15, 2017

PT Data Sheet for Weld 2-RH-105-E, dated May 8, 2017

PT-17-002, PT Data Sheet for Weld 12-RH-2252-39 (Summary 573390), dated April 17, 2017 Radiographic Data Sheet for Weld 2-RH-105-1, dated May 5, 2017 Radiographic Data Sheet for Weld 2-RH-105-A, dated May 6, 2017 Radiographic Data Sheets for Welds 2-RH-104-F, 2-RH-105-2 and 2-RH-105-B, dated

May 12, 2017 Salem Unit 2 Inservice Inspection Final Outage Report for Refueling Outage S2RFO21, dated

February 25, 2016 S-C-MPOO-MGS-001, Piping Specification

SPS-51 for Residual Heat Removal, Revision 5

UT-17-020, UT Data Sheet for Weld 4-AF-2241-3 (Summary 329320), dated April 21, 2017

UT-17-029, UT Data Sheet for Weld 22-STG-USUH (Summary 272850), dated April 26, 2017

VEN-17-001, VT Data Sheet for Reactor Vessel Baffle Edge and Angle Bolts (Summary

970060), dated May 1, 2017

WDI-PJF-1317681-FSR-001, Field Service Report for Salem Unit 2 Baffle-Former Bolt

Ultrasonic Inspections, Revision 0

WDI-TJ-1062, Technical Justification for the Ultrasonic Inspection of Internal Hex Head

Baffle-Former Bolts with Welded Lock Bars, Revision 2 Weld History Records 79591 through 79600 for

WO 60130174, dated May 15, 2017 Weld Pictogram for

WO 60130174 on Line 2-RH-104, dated April 27, 2017 Weld Pictogram for

WO 60130174 on Line 2-RH-105, dated April 27, 2017

Section 1R11: Licensed Operator Requalification Program

Procedures

S2.OP-AB.RCP-0001, Reactor Coolant Pump Abnormality, Revision 22 2-EOP-TRIP-1, Reactor Trip or Safety Injection, Revision 32 2-EOP-TRIP-3, Safety Injection Termination, Revision 31

Section 1R12: Maintenance Effectiveness

Procedures

ER-AA-310, Implementation of the Maintenance Rule, Revision 13

ER-AA-2002, System Health Indicator Program, Revision 16

ER-AA-2030, Conduct of Plant Engineering Manual, Revision 13

Notifications

20683597

20748458

20762362*

20763605*

20768819*

20768820*

20766326

20750692

20763055

20762277

20762591

20762295

20762585

20762277

20762278

20762279

20761979

20762219

20762220

Work Orders

60127910

70191071

70193583

Section 1R13: Maintenance Risk Assessments and Emergent Work Control

Procedures

OP-AA-101-112-1002, On-Line Risk Assessment, Revision 3

OP-AA-108-101, Control of Equipment and System Status, Revision 8

OP-AA-108-116, Protected Equipment Program, Revision 12

OP-SA-108-115-1001, Operability Assessment and Equipment Control Program, Revision 10

OU-AA-103, Shutdown Safety Management Program, Revision 23

OU-SA-105, Shutdown Safety Management Program - Salem Annex, Revision 9 S1.OP-AB.SG-0001, Steam Generator Tube Leak, Revisions 21 & 22 S2.OP-AR.ZZ-0003, C-19 SFP Temp Hi Alarm Response Procedure, Revision 19 S1.OP-AB.SG-0001, Steam Generator Tube Leak, Revision 21

SC.ER-PS.FP-0001-A4, Fire Events in Maintenance Rule (a)(4) Risk Evaluations, Revision 0

WC-AA-105, Work Activity Risk Management, Revision 6

Notifications

20544137

20702636

20764498

20764594*

20764596

20764891

20764926

20765132

20761457

20770712

20770194

20766040

20766038

20765846

20727153

20647694

20766551

20764904

20764901

20764816

20765496

20764498

20764891

20764496

20764497

20764926

20590109

Drawings

AF-1, Auxiliary Feed System, Revision 3

205336, Salem Nuclear Generating Station Number 2 Auxiliary Feedwater, Revision 52

Work Orders

60132175

60133347

60133759

70186162

Section 1R15: Operability Determinations and Functionality Assessments

Procedures

OP-SA-108-115, Operability Determinations and Functionality Assessments, Revision 4

OP-SA-108-115-1001, Operability Assessment and Equipment Control Program, Revision 10 S2.OP-SO.SW-0005, Service Water System Operation, Revision 42

Notifications

20762366

20762376

20763522

20760898

20762761

20765801

20760904

20717850

20768875

20762881

Work Orders

80120229

70193685

80110461

60122516

60115357

70194900

70193618

Section 1R18: Plant Modifications

Procedures

SC.RE-FR.ZZ-0019, Reactor Engineering - Refueling, Revision 27

Notifications

20761796

20743918

20763771

20759278

20760519

20762435

Work Orders

80119467

80109340

70165309

80111452

Section 1R19: Post-Maintenance Testing

Procedures

ER-AA-321, Administrative Requirements for Inservice Testing, Revision 13

MA-AA-716-012, Post Maintenance Testing, Revision 20 S2.IC-CC.WD-0013, 2LT-939 Containment Sump Level Channel II, Revision 12 S2.IC-FT.RCP-0001, 2TE-411A-B #21 Rx Coolant Loop Delta T-Tavg Protection Channel I,

Revision 57 S2.OP-ST.SJ-0020, Periodic Leakage Test RCS Pressure Isolation Valves, Revision 21 S2.RA-ST.DG-0003, Inservice Testing 2C Diesel Generator Surveillance Test Acceptance Criteria, Revision 7

S2.RA-ST.RHR-0004, Inservice Testing Residual Heat Removal Valves Acceptance Criteria, Revision 7

Notifications

20761505

20762577

20764428*

20764475

20764661

20764662*

20764824

20764848

20764287

20764237

20762557

20762558

20763948

20763190

Drawings

671332, Sheet 1, Unit 2 Residual Heat Removal, Revision 0

671332, Sheet 2, Unit 2 Residual Heat Removal, Revision 0

205232, Sheet 1, Unit 1 Residual Heat Removal, Revision 39

205232, Sheet 2, Unit 1 Residual Heat Removal, Revision 38

625017, Sheet 1, Unit 2 Building and Equipment Drains Containment Sump Pump Level

2LT939, Revision 1

240698, Sheet 1, Unit 2 Sumps and Flood Pumps - Contaminated, Revision 10

211514, Sheet 2, Unit 2 Residual Heat Removal System Containment Sump Level

LT-939,

Revision 15

Work Orders

30088150

30164489

30164521

30206683

30207070

30258534

30270436

30270645

30270704

30271195

30309923

60090744

60094634

60129677

60130174

60134270

60134353

60134573

30272176

50181407

50166967

50153683

50140018

Calculations

S-C-SW-NDC-2143, SVCE WTR DSL GEN JKT CLR INLET, Revision 1

Non Destructive Examinations

30206683-300,

VT-2 Visual Examination, performed 5/9/17 30270436-220,

VT-2 Visual Examination, performed 5/8/17 30270704-590,

VT-2 Visual Examination, performed 5/8/17 30271195-1570,

VT-2 Visual Examination, performed 5/8/17 60130174-190,

VT-2 Visual Examination, performed 5/15/17

Section 1R20: Refueling and Other Outage Activities

Procedures

NF-AA-310, Special Nuclear Material and Core Component Movement, Revision 15 S2.OP-AB.FUEL-0001, Fuel Handling Incident, Revision 5 S2.OP-IO.ZZ-0009, Defueled to Refueling, Revision 30 S2.OP-IO.ZZ-0010, Spent Fuel Pool Manipulations, Revision 34

S2.OP-IO.ZZ-0011, Control Room Operability with Unit 2 Defueled, Revision 7 S2.OP-IO.ZZ-0109, Defueled to Refueling Administrative Requirements, Revision 6 S2.OP-SO.SF-0009, Refueling Operations, Revision 19 S2.P-ST-SJ-0010, ECCS - Containment Inspection For Mode 4, Revision 6

SC.MD-FR.CAN-0001, Outage Equipment Hatch Installation, Removal, Seal Replacement and Door Manipulation for Containment Closure, Revision 20SC.RE-FR.ZZ-0001, Salem Generating Station/Reactor Engineering Fuel Handling, Revision 52

SC.RE-FR.ZZ-0002, New Fuel Receipt and Storage, Revision 22

Notifications

20760977

20762303*

20762311

20764528

20765143*

20765272*

20765690*

20765748*

20765759*

20765762*

20765816*

20765822*

20765824*

20765825*

20765827*

20765829*

20765830*

20765386*

20765400 20771475*

Section 1R22: Surveillance Testing

Procedures

S2.OP-ST.RHR-0001,

IST 21 Residual Heat Removal Pump, Revision 31 S2.OP-ST.SSP-0006, Engineered Safety Feature Containment Isolation - Phase B, Revision 16 S2.OP-ST.AF-0007, IST Auxiliary Feedwater Valves Mode 3, Revision 22 S2.RA-ST.AF-0007, IST Auxiliary Feedwater Valves Mode 3 Acceptance Criteria, Revision 12 S2.RA-ST.RHR-0001,

IST 21 Residual Heat Removal Pump Acceptance Criteria, Revision 13

Notifications

20761748

20761750

20761832

20762815*

20767219*

20768741*

20768804*

Work Orders

50167213

50180841

50181109 50192363

Section 1EP2: Alert and Notification System Evaluation

Procedures

EP-AA-121-1002, PSEG Alert Notification System (ANS) Program, Revision 1

EP-AA-121-1004, PSEG ANS Corrective Maintenance, Revision 1

EP-AA-121-1005, PSEG ANS Preventive Maintenance Program, Revision 2

EP-AA-121-1006, PSEG ANS Siren Monitoring, Troubleshooting, and Testing, Revision 1

Notifications

20731787

20762139

Section 1EP3: Emergency Response Organization Staffing and Augmentation System

Procedures

EP-AA-120-1007, Maintenance of Emergency Response Organization, Revision 7

EP-AA-120-1010, ERO Training Administration, Revision 1

EP-AA-121-1001, Automated Call-Out System Maintenance, Revision 2

EP-AA-121-1007, Primary Emergency Callout System Recovery Guide, Revision 2

Notifications

20736246

20737470

20738162

20763707

Section 1EP5: Correction of Emergency Preparedness Weaknesses

Procedures

EP-AA-120, Emergency Plan Administration, Revision 16

EP-AA-121, Emergency Response Facilities and Equipment Readiness, Revision 3

EP-AA-121-1003, Equipment Important to Emergency Response - Work Prioritization, Revision 3

EP-AA-124, Inventories and Surveillances, Revision 1

EP-AA-124-1001, Facilities Inventories and Equipment Tests, Revision 2

EP-AA-124-1001, Facilities Inventories and Surveillances, Revision 2

EP-AA-125, Emergency Preparedness Self Evaluation Process, Revision 1

WC-AA-106, Work Week Screening and Processing, Revision 19

Notifications

20698531

20702801

20705922

20708995

20711391

20711407

20712348

20737470

20738714

20739070

20743962

20746208

20746302

20751841

20752762

20755471

20759469

20763130

20763307

20765649

20765861

Section 1EP6: Drill Evaluation

Procedures

S2.OP-AB.RCP-0001, Reactor Coolant Pump Abnormality, Revision 22 S2.OP-AR.ZZ-0012, Control Console 2CC2, Revision 39 S2.OP-SO.AF-0001, Auxiliary Feedwater System Operation, Revision 43 S2.OP-SO.CVC-0006, Boron Concentration Control, Revision 25 S2.OP-SO.DG-0003, 2C Diesel Generator Operation, Revision 42 S2.OP-SO.GS-0001, Turbine Gland Sealing Steam Operation, Revision 10 2-EOP-TRIP-1, Reactor Trip or Safety Injection, Revision 32 2-EOP-TRIP-3, Safety Injection Termination, Revision 31

Notifications

20770243

20770155

20768901

Section 2RS1: Access Control to Radiologically Significant Areas

Notifications

20762305

20762727

20763044

20763063

20763503 20763630

Section 2RS2: Occupational

ALARA Planning and Controls

Notifications

20763276

Section 4OA1: Performance Indicator Verification

Procedures

EP-AA-125-1001, EP Performance Indicator Guidance, Revision 1

EP-AA-125-1002, ERO Performance - Performance Indicators Guidance, Revision 5

EP-AA-125-1003, ERO Readiness - Performance Indicators Guidance, Revision 1

EP-AA-125-1004, ANS Reliability - Performance Indicators Guidance, Revision 1

Notifications

20715510

20735719

20758110

Miscellaneous

ANS Reliability PI data, April 2016 - March 2017 Drill and Exercise Performance PI data, April 2016 - March 2017 ERO Drill Participation PI data, April 2016 - March 2017