IR 05000443/2015004

IR 05000443/2015004 and 07200063/2015001 - Seabrook Station, Unit 1 - Integrated Inspection Report and Independent Spent Fuel Storage Installation Report

ML16043A391
Person / Time
Site:	Seabrook
Issue date:	02/12/2016
From:	Bower F L Reactor Projects Branch 3
To:	Dean Curtland NextEra Energy Seabrook
bower, fl
References
IR 2015001, IR 2015004
Download: ML16043A391 (50)

Text

February 12, 2016

Mr. Dean Curtland Site Vice President Seabrook Nuclear Power Plant NextEra Energy Seabrook, LLC c/o Mr. Michael Ossing P.O. Box 300 Seabrook, NH 03874

SUBJECT: SEABROOK STATION, UNIT NO. 1 INTEGRATED INSPECTION REPORT 05000443/2015004 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION REPORT NO. 07200063/2015001

Dear Mr. Curtland:

On December 31, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Seabrook Station, Unit No. 1. The enclosed report documents the inspection results, which were discussed on January 21, 2016, with you and other members of your staff. NRC Inspectors examined activities conducted under your license as they relate to safety and The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings of significance were identified. However, a licensee-identified violation, which was determined to be of very low safety significance, is listed in Section 4OA7 of this report. If you contest the non-cited violations (NCVs) in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at Seabrook Station. In accordance with Title 10 of the Code of Federal Regulations (CFR) 2.390 of the NRCs the Publicly Available Records component of the and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA/ Fred L. Bower, III, Chief Reactor Projects Branch 3 Division of Reactor Projects Docket No. 50-443 License No. NPF-86

Enclosure:

Inspection Report 05000443/2015004 and ISFSI Report 07200063/2015001

w/Attachment:

Supplementary Information cc w/encl: Distribution via ListServ

ML16043A391 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP NAME PCataldo/ RSB for RBarkley/ RSB FBower/ FLB DATE 02/11 /16 02/ 11 /16 02/ 11 /16 1 Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION I Docket No: 50-443 License No: NPF-86 Report No: 05000443/2015004 Licensee: NextEra Energy Seabrook, LLC Facility: Seabrook Station, Unit No.1 Location: Seabrook, New Hampshire 03874 Dates: October 1, 2015 through December 31, 2015 Inspectors: P. Cataldo, Senior Resident Inspector C. Newport, Resident Inspector J. Vasquez, Project Engineer D. Silk, Senior Operations Engineer B. Dionne, Health Physicist J. Nicholson, Senior Health Physicist Reactor Inspector B. Cook, Senior Reactor Analyst Approved by: Fred L. Bower, Chief Reactor Projects Branch 3 Division of Reactor Projects 2

SUMMARY

Inspection Report 05000443/2015004 and Independent Spent Fuel Storage Installation (ISFSI) Report 07200063/2015001; 10/01/2015 12/31/2015; Seabrook Station, Unit No. 1; Routine Integrated Inspection Report. This report covered a three-month period of inspection by resident inspectors and announced inspections performed by regional inspectors. operation of commercial nuclear power reactors is described in NUREG-

Other Findings

A violation of very low safety significance was identified by NextEra and reviewed by the inspectors. Corrective actions taken or planned by NextEra have been entered into the corrective action program (CAP). This violation and corrective action tracking number are listed in Section 4OA7 of this report.

4

REPORT DETAILS

Summary of Plant Status Seabrook began the assessment period at less than 20 percent reactor power, continuing the coastdown for shutdown and entry into Refueling Outage No. 17 (OR17). Seabrook remained shutdown during performance of OR17, until reactor criticality was achieved on November 12, 2015. Subsequently, Seabrook synchronized to the grid on November 13, 2015, and achieved full power (100 percent) on November 17, 2015. Seabrook operated at full power for the remainder of the assessment period.

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R01 Adverse Weather Protection

Readiness for Seasonal Extreme Weather Conditions

a. Inspection Scope

temperatures. The review focused on the service water (SW) cooling tower (CT) and the supplemental emergency power system generators, as well as other areas of cold weather protection for various areas of interest onsite, such as weather enclosures for the condensate storage tank. The inspectors reviewed the updated final safety analysis report (UFSAR), technical specifications (TSs), control room logs, and the CAP to determine what temperatures or other seasonal weather could challenge these systems, and to ensure NextEra personnel had adequately prepared for these challenges. The preparation procedure and applicable operating procedures. The inspectors performed walkdowns of the selected systems to ensure station personnel identified issues that could challenge the operability of the systems during cold weather conditions. Documents reviewed for each section of this report are listed in the Attachment.

b. Findings

No findings were identified.

1R04 Equipment Alignment

.1 Partial System Walkdowns

a. Inspection Scope

The inspectors performed partial walkdowns of the following systems: 'A' SW return to service on October 29 'B' residual heat removal (RHR) return to service on November 17 'B' charging system during 'A' train maintenance on December 17 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, the UFSAR, TSs, work orders (WOs), condition reports (CRs), and the impact of ongoing work activities on redundant trains of equipment performance of its intended safety functions. 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 NextEra 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.

.2 Full System Walkdown

a. Inspection Scope

During October and November 2015, the inspectors performed a complete system walkdown of accessible portions of the primary component cooling water system to verify the existing equipment lineup was correct. The inspectors reviewed operating procedures, surveillance tests, system diagrams, equipment line-up check-off lists, WOs, work requests, CRs, TSs, and the UFSAR to verify the system was aligned to perform its required safety functions. The inspectors also reviewed electrical power availability, component lubrication and equipment cooling, hanger and support functionality, and operability of support systems. The inspectors performed field walkdowns of accessible portions of the systems to verify system components and support equipment were aligned correctly and 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 NextEra staff had appropriately evaluated and resolved any equipment issues and other performance deficiencies and entered them into their CAP for resolution with the appropriate significance characterization.

b. Findings

No findings were identified.

1R05 Fire Protection Resident Inspector Quarterly Walkdowns

a. Inspection Scope

The inspectors conducted tours of the areas listed below to assess the material condition and operational status of fire protection features. The inspectors verified that NextEra controlled combustible materials and ignition sources in accordance with administrative procedures. The inspectors verified that fire protection 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 out of service, degraded, or inoperable fire protection equipment, as applicable, in accordance with procedures.

Containment 0' (C-F-2-Z) on October 14 Containment -26' (C-F-1-Z) on October 20 Containment 25' (C-F-3-Z) on October 24 Supplement emergency power system (SEPS-F-1-0) on December 3 Essential switchgear 'A' (CB-F-1A-A) on December 17

b. Findings

No findings were identified.

1R07 Heat Sink Performance (711111.07A

1 sample)

a. Inspection Scope

emergency diesel generator (EDG) heat exchanger to determine its readiness and availability to perform its safety functions. The inspectors reviewed the design basis NRC Generic Letter 89-13. The inspectors reviewed results of previous inspections of ger, observed the most recent inspection results of heat exchanger, and discussed the results with NextEra staff. The inspectors also verified that NextEra initiated appropriate corrective actions for identified deficiencies.

b. Findings

No findings were identified.

1R08 Inservice Inspection (711111.08

1 sample)

a. Inspection Scope

The inspectors conducted a review of NextEras implementation of inservice inspection (ISI) program activities for monitoring degradation of the reactor coolant system (RCS) boundary, risk significant piping and components, and containment systems during the Seabrook Unit 1, OR17. Inspection sample selection was based on the inspection procedure objectives and risk priority of those pressure retaining components in systems where degradation would result in a significant increase in risk. The inspectors observed in-process non-destructive examinations (NDE), reviewed documentation, and interviewed NextEra personnel to verify that the NDE examination activities performed as part of the Seabrook Unit 1 ISI program were being conducted during the Seabrook Interval 3, Period 2, 2nd Outage, ISI in accordance with the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI, 2004 Edition, no Addenda. Non-destructive Examination and Welding Activities (Inspection Manual Chapter (IMC) Section 02.01) The inspectors performed direct observations of select NDE activities, and reviewed records of the NDEs listed below. The inspectors reviewed certifications of the NDE technicians performing the examinations. The inspectors verified that the examinations were performed in accordance with approved procedures and that the results were reviewed and evaluated by certified Level III NDE personnel. ASME Code Required Examinations The inspectors observed the remote, bare-metal visual (VT-2) examination of the reactor vessel upper closure head and control rod drive mechanism (CRDM) nozzle penetrations.

The inspectors reviewed the VT-3 direct visual examination data from NextEra examination of the CRDM structural supports to determine whether all results were satisfactory.

The inspectors reviewed the examination data sheets for the post mechanical stress improvement process phased array, outside diameter ultrasonic test inspections and the eddy current (EC), inside weld surface inspections of seven reactor vessel hot leg and cold leg nozzle dissimilar metal safe-end welds. The inspectors verified the examinations were completed in accordance with the applicable Seabrook TSs, ASME Boiler and Pressure Vessel Code,Section XI, 2004 Edition, Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(b)(2)(xiv, xv and xiv), Code Case N-770-1 and the Examination Program Plan (Scan Plan) WDI-PJF-1312142-EPP-001, Revision 0, as submitted to, and reviewed by, the NextEra staff. The inspectors determined whether the examination results were dispositioned in accordance with the applicable requirements for the weld records identified in the list of documents reviewed section of this report.

The inspectors reviewed the data records from the visual examinations of the containment liner concrete pad and floor plugs. The inspectors determined whether NextEra personnel documented the conditions for investigation, repair, and monitoring in accordance with their program requirements.

The inspectors observed the ultrasonic test examination of two ASME Class 2 feedwater nozzle-to-pipe welds (FW 4607-04-19 and FW 4607-04-20) to determine whether the examinations were performed to check for indications of thermal fatigue in the welds and whether the results were properly dispositioned. No new indications were detected, and previously detected indications were confirmed to show that no changes had occurred.

The inspectors reviewed the documentation for a containment liner anomaly on the inside surface of the containment dome. NextEra staff completed a VT-1 remote, visual examination on October 2, 2015. This indication, identified as IWE-15-159-176, was first documented in October 2009, and re-examined in October 2012 and April 2014. NextEra engineering staff evaluated the results and did not identify measureable changes in the length, width, contour or color of the anomaly from 2009 thru 2015. The inspectors noted that NextEra engineers were not able to accurately measure the height of the anomaly due to limitations of their imaging equipment. NextEra staff initiated plans to perform an examination during the next refueling outage. The inspectors determined NextEra staff tracked and dispositioned this indication in accordance with their program requirements. Review of Originally Rejectable Indications Accepted by Evaluation The inspectors determined there were no samples available for review during this inspection that involved examinations with recordable indications that had been accepted for continued service after evaluation. Repair/Replacement Consisting of Welding Activities The inspectors reviewed WO 4036801501, which provided direction to fabricate a diesel fuel system connection to implement design change EC282581. The inspectors reviewed the WO to determine whether welding was completed in accordance with ASME Code welding requirements. Specifically, the inspectors determined whether approved plant welding procedures and parameters were specified and that post-weld quality control examinations were identified. The inspectors verified that the WO contained completed weld traveler information, documentation of completed examinations, and appropriate documentation of the work steps completed by NextEra personnel.

Pressurized Water Reactor Vessel Lower Head Penetration Inspection Activities (IMC Section 02.02) The inspectors reviewed visual inspection records of the bare-metal visual examination (VT-2) of the exterior surface of the Unit 1 lower reactor vessel head surface and instrument penetrations for indications of boric acid leakage in order to confirm appropriate inspection coverage was achieved and to verify that no boric acid leakage or wastage had been observed. The inspectors further verified that NextEra staff took actions, tracked in their CAP, to ensure the lower head surface was sufficiently clean to accurately observe the annulus between the penetrations and the openings in the lower head. The inspectors reviewed the examination records to verify that there was no evidence of boric acid.

Steam Generator (SG) Tube Inspection Activities (IMC Section 02.04) The inspectors reviewed the NextEra degradation assessment report for OR17, and reviewed records associated with a sample of SG tube examinations completed from all four SGs. The inspectors determined the following activities were planned: 1. Base scope of 100 percent full length bobbin coil examinations in all SGs to inspect general tube conditions; 2. Hot and cold leg tube support plate to tube intersections examinations in high stress diameter stress corrosion cracking due to tube bulges and tube expansion transitions near the top of the tube sheet; 3. Examinations of all SGs ubobbin probes, such as small radius U-bends and local profile anomalies; 4. Inspection of cracking near the top of the tube sheet; and 5. Examination of large residual noise tube support plate locations on high-stress tubes for outside diameter stress corrosion cracking and primary water stress corrosion cracking, as well as regions not inspectable with bobbin probes, such as small radius U-bends and local profile anomalies. The inspectors reviewed the scope of the EC examinations to verify that known and potential areas of tube degradation were inspected. The inspectors also verified that examination scope expansion criteria were implemented based upon inspection results, Steam Generator Examination Guidelines. The inspectors verified compliance of these examinations with the Seabrook TSs, the ASME Code,Section XI, and Nuclear Energy Institute (NEI) 97-06, Steam tubes with identified wall wear of 40 percent or greater were plugged. The inspectors reviewed EC examination records and determined NextEra staff identified a single axial indication in SG A, row 20, column 80 that was subsequently plugged in accordance with program requirements. NextEra staff review of EC examination results also identified a defect, due to anti-vibration bar wear in SG A, row 50, column 79, which was plugged during the refueling outage to remove it from service. EC examination results further showed a single axial indication in SG C, row 39, column 46, below the top of the tube sheet in the hot leg, which was plugged in accordance with program requirements. The inspectors determined NextEra staff developed and completed an expansion plan for all four SGs without discovery of further indications. The inspectors verified that NextEra staff completed condition monitoring evaluations for these indications to properly determine, in accordance with program requirements, that in-situ pressure testing was not required in these tubes.

Boric Acid Corrosion Control Inspection Activities (IMC Section 02.03) The components. The inspectors verified the adequacy of VT-2 visual examination results of the bare-metal examination of the Unit 1 reactor pressure vessel lower head penetration nozzle welds that was performed by NextEra personnel during OR17. The inspectors reviewed a sample of photographs and visual inspection documentation records to verify whether indications of boric acid leakage were identified. The inspectors verified that potential deficiencies identified were entered into the CAP and reviewed evaluations of selected deficiencies documented in CRs to verify that the corrective actions were consistent with the requirements of the ASME Code and 10 CFR 50, Appendix B, Criterion XVI. The inspectors also reviewed a sample of engineering evaluations for the above CRs to verify that equipment or components that were wetted or impinged upon by boric acid solutions were properly analyzed for degradation that might impact their function. Identification and Resolution of Problems (IMC Section 02.05) The inspectors reviewed a sample of CRs since the previous refueling outage, and verified that non-conforming conditions associated with ISI and SG inspections were properly identified, evaluated, dispositioned, and appropriately entered into the CAP.

b. Findings

No findings were identified.

1R11 Licensed Operator Requalification Program and Licensed Operator Performance (71111.11Q

2 samples; 71111.11B 1 sample)

.1 Quarterly Review of Licensed Operator Requalification Testing and Training

a. Inspection Scope

The inspectors reviewed the implementation of just-in-timetraining for licensed operators on September 30 through October 1, 2015. This training included the verification of plant shutdown activities consistent with the training plan and associated objectives for the shutdown and entry into OR17.

b. Findings

No findings were identified.

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

a. Inspection Scope

The inspectors observed infrequently performed test or evolution briefings, pre-shift briefings, and reactivity control briefings to verify that the briefings met the criteria tive Procedure OP-AA-100-he inspectors observed turbine overspeed testing, power reduction, reactivity management, and reactor shutdown and entry into OR17 on October 1, 2015. In addition, inspectors observed transition to shutdown cooling and implementation of alarm response procedures on October 1, 2015, and RCS drain-down to mid-loop activities on November 1, 2015. The inspectors observed test 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.

.3 Licensed Operator Requalification Biennial Review

a. Inspection Scope

The following inspection activities were performed using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 10, and Inspection Examination Results On December 29, 2015, the results of the annual operating tests were reviewed in-office to determine if pass/fail rates were consistent with the guidance of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 10, and NRC (individual or crew) did not exceed 20 percent.

Five out of 52 operators failed at least one section of the annual exam. The overall individual failure rate was 9.6 percent. One out of 11 crews failed the simulator test. The crew failure rate was 9.1 percent. Written Examination Quality The inspectors reviewed two written examinations administered during the 2015 examination cycle for qualitative and quantitative attributes as specified in Appendix B of Attachment 71111.11B, Licensed Operator Requalification Program. Operating Test Quality Ten job performance measures (JPMs) and four dynamic scenarios were reviewed for qualitative and quantitative attributes as specified in Appendix C of 71111.11B, Licensee Administration of Operating Tests The dynamic simulator exams and JPMs administered during the week of November 30, 2015, were observed. These observations included facility evaluations of Shift Crew B and Staff Crew Four during two dynamic simulator exams and individual performance of five JPMs. Examination Security also checked JPMs, scenarios, and written examinations for excessive overlap of test items from week to week. Remedial Training and Re-Examinations The remediation plans for two individual JPM failures from the 2014 segment 14F annual requalification exam, and one biennial comprehensive written exam failure from November 2013, were reviewed to assess the effectiveness of the remedial training.

Conformance with Operator License Conditions Medical records for ten license holders were reviewed to assess conformance with license conditions. Proficiency watch standing records were reviewed for the second and third quarters of 2015. The reactivation plans for license holders in 2015 were reviewed to assess the effectiveness of the reactivation process.

Simulator Performance Simulator performance and fidelity was reviewed for conformance to the reference plant control room. A sample of simulator deficiency reports was also reviewed to ensure facility staff addressed identified modeling problems. Simulator test documentation was also reviewed. Problem Identification and Resolution A review was conducted of recent operating history documentation found in inspection reports, CAP, and the most recent NRC plant issues matrix. The inspectors also reviewed specific events from CAP which, indicated possible training deficiencies, to verify that they had been appropriately addressed. The NRC resident

b. Findings

No findings were identified.

1R12 Maintenance Effectiveness

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 NextEra 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 NextEra staff were reasonable. As applicable, for SSCs classified as (a)(1), the inspectors assessed the adequacy of goals and corrective actions to return these SSCs to (a)(2). Additionally, the inspectors ensured that NextEra staff was identifying and addressing common cause failures that occurred within and across MR system boundaries.

Radiation monitors Various safety-related snubber maintenance and leak resolutions SW CT fan electrical and mechanical maintenance activities

b. Findings

No findings were identified.

1R13 Maintenance Risk Assessments and Emergent Work Control

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 NextEra 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 NextEra personnel performed risk assessments as required by 10 CFR 50.65(a)(4) and that the assessments were accurate and complete. When NextEra 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 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.

RCS drain-down to the reactor vessel flange on October 5 SW system outage during core offload period (i.e., out-of-service) on October 8 RCS decreased inventory and mid-loop operations on October 30

b. Findings

No findings were identified.

1R15 Operability Determinations and Functionality Assessments

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: Feed regulating valve localized flow erosion on October 14 Foreign material (i.e., ball bearings) identified in the reactor vessel and system piping from an ultrasonic inspection tool on October 23 Containment liner leakage rate floor plugs and channel inspections on October 28 Through wall leak on pipe threads of MS-V-413 drain line on December 21 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 UFSAR to 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

.1 Permanent Modifications

a. Inspection Scope

The inspectors reviewed the permanent modifications listed below. This included two modifications a Japan Lessons Learned Order. The inspection did not address whether the modification satisfactorily addressed the objectives of Order EA-12-049. The inspection scope for the modification was restricted to those elements necessary to satisfy the stated objectives of Inspection Procedure 71111.18, specifically: 1) to verify that the modifications have not affected the safety functions of important safety systems; 2) to verify that the design bases, licensing bases, and performance capability of risk significant SSCs have not been degraded through modifications; and, 3) to verify that modifications performed during increased risk-significant configurations did not place the plant in an unsafe condition. The inspectors reviewed modification documents that included applicable 10 CFR 50.59 documentation, post-modification testing, and design interface activities, such as procedure changes and applicable training activities.

EC282453, replacement of MS-V-393 EC282474, installation of reactor coolant pump low leakage shutdown seals EC282580, Fukushima FLEX strategy RCS makeup

b. Findings

No findings were identified.

1R19 Post-Maintenance Testing

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 points were performed and checked, and that results adequately demonstrated restoration of the affected safety functions.

Reactor trip breaker inspection and testing on October 1 and November 4 RHR pump retest following outage maintenance activities on October 26 Emergency feedwater pump P-37A retest following outage maintenance activities on November 12 10 CFR Part 21, primary/secondary trip latch replacement on ABB Model 7 K-Line breaker for CT fan, 2-SW-FN-51B, on December 1 'D' vital battery cell #18 replacement on December 30

b. Findings

No findings were identified.

1R20 Refueling and Other Outage Activities

a. Inspection Scope

maintenance and refueling outage (OR17), conducted October 1 through November 13. and schedules to verify that risk, industry experience, previous site-specific problems, and defense-in-depth were considered. During the outage, the inspectors observed operator performance and other attributes associated with portions of the shutdown and cooldown processes, and compliance with cooldown rates associated with TS. Further, the inspectors reviewed multiple surveillance and other critical evolutions in the control room, and monitored controls associated with the following outage activities: Configuration, risk, and outage management, including monitoring of key shutdown safety functions, and compliance with the applicable TSs when taking equipment out of service; 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; Configuration and appropriate monitoring of reactor coolant level and temperature instruments, particularly during activities associated with the highest level of shutdown risk, which occurred during the RCS drain-down and reactor vessel head de-tensioning activities, as well as the drain-down to support RCS evacuation and fill; Status and configuration of electrical systems and switchyard activities to ensure that TSs were met; activities associated with the installation and testing of the new generator step-up transformers, including monitoring systems for combustible gas generation and induced currents from solar magnetic disturbances; Monitoring of decay heat removal operations, during initial onset into shutdown cooling, as well as activities associated with spent fuel pool cooling following full core offload; post-Fukushima beyond design basis mitigating strategies and to verify no impacts on systems important to safety for both operating and shutdown conditions; Reactor water makeup and inventory controls, including appropriate flow paths, configurations, alternative means for inventory additions, and controls to prevent inventory loss; Activities that could affect reactivity; Industrial safety activities, including equipment heavy lifts consistent with the Memorandum of Understanding with the Occupational Safety and Health Administration; Refueling activities, including fuel handling during core offload and reload inside containment, fuel handling in the spent fuel pool, as well as pre-outage fuel receipt inspections; Fatigue management that involved covered workers, and review of work hour controls and waivers; Prioritization and completion of mode hold condition reports and work orders, and review of operating mode transition checklists; Performed a final containment closeout/walk-down to verify that debris or equipment had not been left inside, particularly in areas that could impact operability of the containment recirculation sumps; additionally, performed condition assessment of debris interceptor screens, scuppers and doorways that contribute to overall operability of the containment sumps and emergency core cooling systems and component; Reactor start-up, plant heat-up, and power ascension activities; and Problem identification and resolution actions related to OR17 refueling outage activities.

b. Findings

No findings were identified.

1R22 Surveillance Testing

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 NextEra 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: Refueling water storage tank to charging pump suction isolation valve, 1-CS-LCV-112E, inservice test surveillance on October 8 (inservice test) CBS-V-8 containment isolation valve equipment qualification and operability testing on October 11 (containment isolation valve test)

b. Findings

No findings were identified. Cornerstone: Emergency Preparedness

1EP2 Alert and Notification System Evaluation

a. Inspection Scope

An onsite review was conducted to assess the maintenance and testing of the Seabrook Station Alert and Notification System (ANS). During this inspection, the inspectors conducted a review of the ANS testing and maintenance programs. The inspectors reviewed the associated ANS procedures and the Federal Emergency Management Agency approved ANS Design Report to ensure compliance with design report commitments for system maintenance and testing. The inspectors toured the facility used by, and interviewed, the dedicated Seabrook staff responsible for the maintenance and testing of the Seabrook ANS. 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

a. Inspection Scope

The inspectors conducted a review of the Seabrook Station 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 licensee staff activate their emergency response facilities (ERFs) in a timely manner. The inspectors reviewed the Seabrook Station Emergency Plan for ERF activation and ERO staffing requirements, the ERO duty roster, applicable station procedures, augmentation test reports, the most recent drive-in drill report, and corrective action 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.

1EP4 Emergency Action Level and Emergency Plan Changes

a. Inspection Scope

NextEra implemented various changes to the Seabrook Emergency Action Levels (EALs), Emergency Plan, and Implementing Procedures. NextEra had determined that, in accordance with 10 CFR 50.54(q)(3), any change made to the EALs, emergency plan, and its lower-tier implementing procedures had not resulted in any reduction in effectiveness of the Plan, and that the revised Plan continued to meet the standards in 50.47(b) and the requirements of 10 CFR Part 50 Appendix E.

The inspectors performed an in-office review of all EAL and emergency plan changes submitted by NextEra as required by 10 CFR 50.54(q)(5), including the changes to lower-tier emergency plan implementing procedures, to evaluate for any potential reductions in effectiveness of the emergency plan. This review by the inspectors was not documented in an NRC Safety Evaluation Report and does not constitute formal NRC approval of the changes. Therefore, these changes remain subject to future NRC inspection in their entirety. The requirements in 10 CFR 50.54(q) were used as reference criteria.

b. Findings

No findings were identified.

1EP5 Maintaining Emergency Preparedness

a. Inspection Scope

efforts to maintain the Seabrook emergency preparedness (EP) program. The inspectors reviewed: Memorandums of Understanding with offsite agencies; the 10 CFR 50.54(q) emergency plan change process and practices; NextEra maintenance of equipment important to EP; records of evacuation time estimate population evaluation; and provisions for, and implementation of, primary, backup, and alternate emergency Seabrook with new NRC EP regulations regarding: EALs for hostile action events; protective actions for on-site personnel during events; emergency declaration timeliness; ERO augmentation and alternate facility capability; evacuation time estimate updates; on-shift ERO staffing analysis; and, ANS back-up means. their identification and correction of EP weaknesses, by reviewing a sample of drill reports, actual event reports, self-assessments, 10 CFR 50.54(t) review reports, and EP-related CRs. The inspectors reviewed a sample of EP-related CRs initiated at Seabrook from July 2013 through December 2015. The inspection was conducted in accordance with NRC Inspection Procedure 71114.05. 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.

RADIATION SAFETY

Cornerstone:

Public Radiation Safety

2RS1 Radiological Hazard Assessment and Exposure Controls

a. Inspection Scope

hazards in the workplace. The inspectors used the requirements contained in 10 CFR 20, TSs, applicable Regulatory Guides (RGs), and the procedures required by TSs as criteria for determining compliance.

Inspection Planning

The inspectors reviewed the performance indicators (PIs) for the occupational exposure cornerstone, radiation protection (RP) program audits, and reports of operational occurrences in occupational radiation safety since the last inspection.

Radiological Hazard Assessment The inspectors reviewed recent plant radiation surveys and any changes to plant operations since the last inspection to identify any new radiological hazards for onsite workers or members of the public.

Instructions to Workers The inspectors observed several containers of radioactive materials and assessed whether the containers were labeled and controlled in accordance with requirements.

dosimetdocumentation in the CAP, and whether compensatory dose evaluations were conducted when appropriate.

Contamination and Radioactive Material Control The inspectors observed themonitoring of potentially contaminated material leaving the radiological control area and inspected the methods and radiation monitoring instrumentation used for control, survey, and release of that material. The inspectors selected several sealed sources from inventory records and assessed whether the sources were accounted for and were tested for loose surface contamination. The inspectors evaluated whether any recent transactions involving nationally tracked sources were reported in accordance with requirements. Radiological Hazards Control and Work Coverage The inspectors assessed whether posted surveys, radiation work permits, worker radiological briefings, the use of continuous air monitoring, and dosimetry monitoring were consistent with the present plant conditions. The inspectors examined the control of highly activated or contaminated materials stored within the spent fuel pool and the posting and physical controls for selected high radiation areas, locked high radiation areas, and very high radiation areas to verify conformance with the occupational PI.

b. Findings

No findings were identified.

2RS2 Occupational ALARA Planning and Controls

a. Inspection Scope

The inspectors assessed performance with respect to maintaining occupational individual and collective radiation exposures as low as is reasonably achievable (ALARA). The inspectors used the requirements in 10 CFR Part 20, RG 8.8, RG 8.10, Radiological Work Planning

b. Findings

No findings were identified.

4OA1 Performance Indicator Verification

.1 Mitigating Systems Performance Index (3 samples)

a. Inspection Scope

The inspectors reviewed submittal of the Mitigating Systems Performance Index for the following systems for the period of October 1, 2014, through September 30, 2015: Safety System Functional Failures (MS05) RHR System (MS09) Cooling Water System (MS10) To determine the accuracy of the PI data reported during those periods, the inspectors used definitions and guidance contained in NEI Document 99-Revision 7. The inspectors also reviewed Noperator narrative logs, mitigating systems performance index derivation reports and basis documents, event reports, and NRC integrated inspection reports to validate the accuracy of the submittals.

b. Findings

No findings were identified.

.2 Occupational Exposure Control Effectiveness (1 sample)

a. Inspection Scope

The inspectors reviewed NextEra submittals for the occupational radiological occurrences PI for the fourth quarter 2014 through the third quarter 2015. The inspectors used PI definitions and guidance contained in NEI Document 99-02, Revision electronic personal dosimetry accumulated dose alarms, dose reports, and dose assignments for any intakes that occurred during the time period reviewed, to determine if there were potentially unrecognized PI occurrences. The inspectors conducted walkdowns of various locked high radiation area entrances to determine the adequacy of the controls in place for these areas.

b. Findings

No findings were identified.

===.3 Radiological Effluent TS/Offsite Dose Calculation Manual Radiological Effluent Occurrences (1 sample)

a. Inspection Scope

The inspectors reviewed licensee submittals for the radiological effluent TS/Offsite Dose Calculation Manual radiological effluent occurrences PI for the fourth quarter 2014 through the third quarter 2015. The inspectors used PI definitions and guidance contained in NEI Document 99-02, Revision 7, to determine if the PI data was reported properly. public radiation safety to determine if related data was accurately calculated and reported. The inspectors reviewed the CAP database to identify any potential occurrences such as unmonitored, uncontrolled, or improperly calculated effluent releases that may have impacted offsite dose. The inspectors reviewed gaseous and liquid effluent summary data and the results of associated offsite dose calculations to determine if indicator results were accurately reported.

b. Findings

No findings were identified.

.4 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 Seabrook was conducted in the second calendar quarter of 2012. Therefore, the inspectors reviewed supporting documentation from EP drills and equipment tests from the fourth calendar quarter of 2014 through the third calendar quarter of 2015 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 99-7, was used as reference criteria.

b. Findings

No findings were identified.

=

.1 Routine Review of Problem Identification and Resolution Activities

a. Inspection Scope

inspectors routinely reviewed issues during baseline inspection activities and plant status reviews to verify NextEra entered issues into the CAP at an appropriate threshold, gave adequate attention to timely corrective actions, 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 the CAP and periodically attended CR screening meetings. The inspectors also confirmed, on a sampling basis, that, as applicable, for identified defects and non-conformances, NextEra 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, as required by Inspection indicate the existence of more significant safety issues. In this review, the inspectors included repetitive or closely-related issues that may have been documented by NextEra 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 assess CRs written in various subject areas (equipment problems, human performance eview (Section 4OA2.1). Evaluation and Trending Analysis report for the second quarter of 2015, conducted under PI-AA-207-1000, Station Self-Evaluation and Trending Analysis, Revision 5, to verify that NextEra personnel were appropriately evaluating and trending adverse conditions in accordance with applicable procedures. The inspectors evaluated a sample of departments that are required to provide input into the quarterly trend reports, which included the operations and maintenance departments. This review included a sample of issues and events that occurred over the course of the past two quarters to objectively determine whether issues were appropriately considered or determined to be emerging or adverse trends, and in some cases, verified the appropriate disposition of resolved trends. The inspectors verified that these issues were addressed within the scope of the CAP, or through department review and documentation in the quarterly trend report for overall assessment.

b. Findings and Observations

No findings were identified. The inspectors noted that on occasion, potential adverse trends were identified through:

(1) the use of statistical tools available to staff and utilized throughout the quarter to identify statistically significant issues that reach a predetermined threshold, or

(2) cognitive trends by staff or collectively during review by the Management Review Committee (MRC) while screening action requests (ARs). In general, the inspectors noted that new and existing adverse trends, as well as management awareness areas, were consistent with those identified by the NRC through daily CR reviews, including those trends identified as cognitive trends during MRC reviews. For example, the inspectors had identified several issues associated with Maintenance Department -assessments were independently initiated by maintenance personnel to evaluate potential causes of the rework.

.3 Annual Sample: Transmitter Failures

a. Inspection Scope

The inspectors performed an in-actions associated with multiple transmitter spurious indications and failures occurring on site. The entification threshold, problem analysis, extent of condition reviews, compensatory actions, and the prioritization and timeliness of corrective actions to determine whether NextEra was appropriately identifying, characterizing, and correcting problems associated with these transmitter issues and whether the planned or completed corrective actions were appropriate. The basis, and other requirements. The inspectors interviewed engineering and operations personnel to assess the effectiveness of the implemented corrective actions, reasonableness of the planned corrective actions, and to evaluate the extent of any on-going problems.

The inspectors evaluated seven ARs (see below) documenting various transmitter malfunctions and failures. The transmitter issues spanned multiple systems and occurred over a timeframe of approximately 18 months. The review focused on various aspects of the corrective actions and operability process to assess the effectiveness and scope of corrective actions, including trending, and the bases and supporting information for immediate operability evaluations, as applicable. Associated documentation and bases, as well as the MRCs review of operability statements and actions to address weaknesses were assessed as well. The ARs that were reviewed included: Volume control tank level transmitter spurious indication (AR 01972065) Containment building sump level transmitter spiking (AR 01999679) SW jacket water cooling flow transmitter out of tolerance low (AR 01995588) Thermal barrier heat exchanger head pipe level transmitter erratic (AR 02002668) SW jacket water cooling flow transmitter discolored water during calibration (AR 02013241) Volume control tank level deviations (AR 01991967) reactor coolant pump hi-range leakage flow transmitter noisy condition (AR 02011136)

b. Findings and Observations

No findings were identified.

Based on the documents reviewed and discussions with NextEra personnel, the commensurate with their safety significance, and that the actions completed and planned were reasonable to address the issues identified.

.4 Annual Sample:

Motor Control Center Breaker Failure to Trip

a. Inspection Scope

The inspectors performed an in-with CR 1998220, Breaker at 1-EDE-MCC-512 for 1-AS-V-175 Would Not Close. Specifically, a breaker failed to reset several times following manual trip actions during the performance of breaker preventive maintenance.

cause analyses, extent of condition reviews, and compensatory actions, as well as the prioritization and timeliness of corrective actions to determine whether NextEra was appropriately identifying, characterizing, and correcting problems associated with this issue and whether the planned or completed corrective actions were appropriate. The CAP and 10 CFR 50, Appendix B. In addition, the inspectors performed field walkdowns and interviewed appropriate personnel to assess the effectiveness of the implemented corrective actions.

b. Findings and Observations

No findings were identified. NextEra originally suspected a well-known industry phenomenon of hardened grease as the cause of the breaker to not operate as expected during implementation of breaker preventive maintenance in October 2014, under WO 40274287. The inspectors noted that the preventive maintenance included an activity to assess the quality of the grease consistent with the grade characteristics of the National Lubricating Grease Institute, and ision 10. The as-found grease condition of Grade 2 was consistent with grease that is new, and therefore, was not the probable cause of the breaker failure to operate. Subsequent inspections resulted in the replacement of a unitized starter associated with the breaker circuitry. Following successful replacement of the starter, the post-maintenance testing was performed and the breaker operated as designed.

.5 Annual Sample:

Review of Corrective Actions for Alkali-Silica Reaction (ASR) Affected Structures

a. Inspection Scope

During this inspection period, a region-based inspector accompanied Office of Nuclear Reactor Regulation, Division of Engineering and Division of License Renewal staff Austin, Ferguson Structural Engineering Laboratory (FSEL). The audit was conducted to suppotesting program.

The inspectors also conducted an in-(RCE) and corrective actions related to the identification of differential movement, or deformation, of the containment enclosure building (CEB). This condition is described in an NRC inspection report, dated August 25, 2015 (Agencywide Documents Access and Management System (ADAMS) Ascension No. ML15217A256). In addition, inspectors reviewed evaluations related to discrete cracks identified in below grade, internal walls in the RHR and containment spray (CS) equipment vault structure. This condition was previously described in an NRC inspection report dated August 5, 2014 (ADAMS Accession No. ML14212A458).

The inspectors assessed the problem identification threshold, operability and functionality assessments, extent of condition reviews, and the prioritization and timeliness of corrective actions to determine whether NextEra personnel were appropriately identifying, characterizing, and correcting problems associated with the ASR-compliance with the CAP procedure and 10 CFR 50, Appendix B requirements. The resident inspectors continued to conduct routine walk downs of Seabrook Station ASR-affected structures, focusing on the identification of any changes that have the potential for further degrading the functional performance of these structures or associated systems and components.

b. Findings and Observations

During the week of October 26, 2015, the NRC audit team observed the last planned large-scale specimen testing at FSEL, reviewed test program results and analyses completed, to date, and interviewed NextEra staff and their consultants. Audit team activities and conclusions are documented in an NRC audit report (ADAMS Accession No. ML15307A019) dated December 17, 2015. No significant observations or concerns were identified related to the conduct of testing to appropriate quality assurance criteria. NextEra staff planned to have the test data analyses completed by the end of 2015, in support of submitting to the NRC a license amendment request in 2016, to address an ASR-related non-conforming condition with the current licensing basis. NRC inspectors conducted in-office reviews of the root cause evaluation for the 3, dated March 17, 2015. CEB deformation, NextEra staff concluded that internal expansion (strain) produced by ASR in the CEB concrete (in-plane direction of the CEB shell) and ASR expansion in the backfill concrete, coincident with a unique building configuration, resulted in CEB deformation. Second, regarding NRC identification of this issue, NextEra concluded this was not identified by plant staff due to an organizational mindset that viewed conditions such as concrete cracks, water infiltration, and misalignment issues as acceptable and inconsequential. Additionally, the RCE identified that NextEra staff did not perform and document comprehensive evaluations of building conditions that could have potentially revealed more significant underlying conditions, such as localized deformation of the CEB. These NRC-identified performance deficiencies were previously dispositioned as non-cited violation (NCV) 2015002-01 and NCV 2015002-02 in NRC inspection report 05000443/2015002 (ADAMS Accession No. ML15217A256).

The inspectors determined NextEra corrective actions to address these problems included: 1) a revision to their design control procedures to require pozzolanic materials like fly ash or slag cement to be added to concrete mixes to prevent ASR in any new concrete structures; and, 2) the implementation of multiple training and program changes to correct the organizational mindset issues and strengthen individual responsibilities and accountability for implementation of the Seabrook Structures Monitoring Program. The inspectors concluded the RCE was reasonably thorough and utilized a cause and effect methodology that was appropriate to the problem statement.

HowNRC inspectors, and not plant staff, identified the presence of localized ASR-induced viewed conditions such as concrete cracks, water infiltration, and misalignment issues as acceptable and inconsequential. The inspectors concluded the RCE was reasonably thorough and utilized a cause and effect methodology that was appropriate to the problem statement. The planned and in-process organizational and program related corrective actions appeared appropriately focused on the identified causes of the problem. However, the inspectors concluded that the corrective actions, taken to date, to implement multiple training, program and oversight changes to correct the organizational mindset issues and strengthen individual responsibilities and accountability for implementation of the Seabrook Structures Monitoring Program have either not been implemented or are not yet effective and thus require additional management attention near-term. The inspectors noted that the CEB RCE referenced the results of a Finite Element Analysis (FEA) model of the CEB. The FEA and results were documented in FP 100985. The inASR expansion to assess the impact of expansion induced deformation on the structural performance of the CEB. The FEA evaluated CEB design capacity against assumed loading, based on ACI 318-71 criteria, including simulated loads associated with the as-deformed condition. As documented in FP 100985, the FEA model also simulated the impact of the external structural loading due to ASR expansion of the backfill concrete.

Based upon the review of the CEB structural assessment described in FP 100985 and the limited structural analysis of the RHR/CS vault documented in FP100903, the inspectors had multiple follow-up questions regarding the CEB and RHR/CS vault structural assessments and the open Immediate Operability Determinations and Prompt Operability Determinations (PODs) for these ASR-affected structures (reference AR 01664399, AR 01929460, AR 01977456, AR 02004749, and AR 02044627). The follow-up questions were developed via a collegial review by the Region 1 Senior Reactor Analyst and structural engineers from NRC Offices of Nuclear Reactor Regulation and Region 2, under the auspices of the Seabrook ASR Technical Team (ADAMS Accession No. ML14014A378). The questions were documented and shared with the NextEra staff on December 23, 2015 (ADAMS Accession No. review are planned for the first quarter of 2016 and will be documented in an NRC inspection report.

Following the guidance of IMC Structures Monitoring Program. Specifically, the structural evaluations, performed by contractors and accepted by NextEra staff via the FP process, included discussions that identified the potential to exceed limits in the applicable design code (ACI 318-71) for specific locations in the CEB and RHR/CS vault walls. The evaluations further recommended actions to determine whether this was the case. The inspectors noted that the Seabrook staff screened or reviewed these evaluations without documenting a justification in a revision or update to the open PODs for these structures. The additional information requested on December 23, 2015 is required for the inspectors to determine whether this issue involves a performance deficiency. As a result, the NRC opened an unresolved item (URI). Introductionimplementation of the Seabrook structures monitoring program and acceptance of evaluations via the FP and CAP.

Description.

Additional inspection is warranted to determine whether a performance FP 100903 for the RHR/CS vault condition. Specifically, further inspection is warranted to determine whether NextEra staff properly implemented the Seabrook structures monitoring program for the acceptance and review of structural evaluations potentially impacting the functionality of the CEB and RHR/CS vault, as currently documented in open PODs. (URI 05000443/2015-01, Issue of Concern Regarding Implementation of the Seabrook Structures Monitoring Program and Structural Evaluations of the CEB and RHR/CS Vault)

4OA5 Other Activities

Operation of an ISFSI at Operating Plants (60855 & 60855.01)

a. Inspection Scope

The -term operation and monitoring of their ISFSI, and verified that activities were being performed in accordance with the Certificate of Compliance (CoC), TSs, regulations, and site procedures.

The inspectors reviewed any changes to the10 CFR Part 72.212 evaluation as well as associated Part 72.48 and 50.59 screenings related to dry cask storage.

The inspectors performed tours of the ISFSI pad to assess the material condition of the pad. The inspectors also verified that transient combustibles were not being stored on the ISFSI pad or in the vicinity of the HI-STORMS. The inspectors verified that Seabrook was performing daily HI-STORM surveillances in accordance with TS requirements, in addition to the periodic monitoring of the condition of the pad HI-STORM exterior surfaces.

program associated with fuel characterization and selection for storage from the last ISFSI loading campaign in 2013. The inspectors verified that the criteria meets the conditions for cask and canister use as specified in the CoC. The inspectors also confirmed that physical inventories were conducted annually and were maintained as required by the regulations.

The inspectors reviewed radiological records from the last ISFSI loading campaign to confirm that radiation and contamination levels measured on the casks were within limits specified by the TS and consistent with values specified in the final safety analysis report.

The inspectors reviewed RP procedures associated with ISFSI operations. The inspectors also reviewed annual environmental reports to verify that areas around the ISFSI pad and the ISFSI site boundary were within limits specified in 10 CFR Part 20 and 10 CFR Part 72.104. The inspectors verified that radiation surveys of the ISFSI pad were performed in accordance with site procedures.

The inspectors reviewed CAP ARs, and the associated follow-up actions associated with ISFSI operations to ensure that issues were entered into the CAP, prioritized, and evaluated commensurate with their safety significance.

b. Findings

No findings were identified.

4OA6 Meetings, Including Exit

On January 21, 2016, the inspectors presented the inspection results to Mr. Dean Curtland, Site Vice President, and other members of the Seabrook Station staff. The inspectors verified that no proprietary information was retained by the inspectors or documented in this report.

4OA7 Licensee-Identified Violation

The following The finding The inspectors determined that this finding is of very low safety significance (Green) in accordance with IMC 0609, Appendix A, Exhibit 2, Mitigating Systems, because the finding did not involve the loss or degradation of equipment or function specifically designed to mitigate a seismic initiating event. NextEra completed the required examinations on October 14, 2015.

ATTACHMENT:

SUPPLEMENTARY INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

D. Curtland, Site Vice President

R. Dodds, Plant General Manager

C. Adams, Operations Training Manager (Acting)

K. Boehl, Senior Rad Protection Analyst

V. Brown, Senior Licensing Engineer

D. Currier, Emergency Planning Manager

K. Douglas, Maintenance Director

D. Flahardy, Radiation Protection Manager

A. Giotas, Chemistry Analyst

S. Hamel, NDE Level III

D. Hickey, Radiation Protection Supervisor

J. Kennish, Instructor

D. Loch, Reactor Vessel Upper Head Inspection Lead

R. Mauer, SG Data Analyst

G. Mikos, Project Manager

D. Merrill, Simulator Support Supervisor

M. Nadeau, RP Analyst

W. Neal, ANII

M. Ossing, Licensing Manager

J. Packer, MSIP Project Manager

K. Randall, Reactor Engineering

D. Ritter, Site Operations Director

D. Robinson, Chemistry Manager

D. Slavon, ISI Program Manager

T. Smith, Radiation Protection Supervisor

D. Strand, RP Manager

C. Thomas, Licensing Engineer

K. Thompson, SG Engineer

T. Vassalo, MPR staff

S. Wellhoffer, Nurse Manager RN

LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED

Opened

05000443/2015004-01 URI Issue of Concern Regarding Implementation of the Seabrook Structures Monitoring Program and structural evaluations of the CEB and RHR/CS Vault (Section 4OA2.5)

Section 1R01: Adverse Weather Protection

Procedures

OP-AA-102-1002, Seasonal Readiness, Revision 9

OP-AA-102-1002-F01, Cold Weather Data Sheets, Revision 0

Condition Reports

02071737

02075786

02093279

02096190

02098538

02099933

Maintenance Orders/Work Orders

40266470

40334413

40334716

40353490

40410503

Miscellaneous

BM-Winter-Ready, Cold Weather Preventive Maintenance Activity Memo to Chief Operating Officer, Seasonal Readiness

Winter 2015, September 24, 2015

Section 1R04: Equipment Alignment

Procedures

OS1002.02, Operation of Letdown, Charging, and Seal Injection, Revision 48 OS1012.03, Primary Component Cooling Water Loop A Operation, Revision 23 OS1012.04, Primary Component Cooling Water Loop B Operation, Revision 26 OS1013.04, Residual Heat Removal Train B Startup and Operation, Revision 28 OS1016.01, Service Water System Fill and Vent, Revision 18 OS1212.01, PCCW System Malfunction, Revision 13

Condition Reports

01943964

01955559

01961777

02038084

02038084

02043141

02055074

02079841

02083248

02083834

02088009

02092165

02092171

Maintenance Orders/Work Orders

40311084

40418154

40419867

Maintenance Requests/Work Requests

94096827

94117626

94117629

94127549

Miscellaneous

Seabrook Component Cooling System Detailed Systems Text, Revision 9

Section 1R05: Fire Protection

Procedures

FP2.2, Control of Combustible Materials, Revision 20

Miscellaneous

Seabrook Station Fire Protection Pre-Fire Strategies, Volume I, C-F-1-Z Seabrook Station Fire Protection Pre-Fire Strategies, Volume I, C-F-2-Z Seabrook Station Fire Protection Pre-Fire Strategies, Volume I, C-F-3-Z Seabrook Station Fire Protection Pre-Fire Strategies, Volume I,

CB-F-1A-A Seabrook Station Fire Protection Pre-Fire Strategies, Volume I,

CB-F-1G-A Seabrook Station Fire Protection Pre-Fire Strategies, Volume II, SEPS-F-1-0

Section 1R07: Heat Sink Performance

Procedures

PEG-268, Heat Exchanger and NRC

GL 89-13 Program, Revision 0

Condition Reports

01957744

02037230

02050993

02075755

02080499

02081299

02083447

02094198

Miscellaneous

Evaluation of

DG-E-42B Tube Plugging

Section 1R08: Inservice Inspection

Procedures

ES15-01-03, Seabrook Unit 1 Reactor Vessel Nozzle MSIP Dissimilar Metal Weld Centerline Locating and Marking Field Services Procedure, Revision 0, 7/31/2017 Seabrook Station Engineering Procedure ES15-01-04, Revision 0, 7/24/2017; Title: Seabrook Unit 1 Reactor Vessel Nozzle Mechanical Stress Improvement Process Field Service Procedure, July 24, 2017 Seabrook Station Engineering Procedure ES10-01-32, Revision 2, 7/24/2017; Title: Remote Inservice Examination of Reactor Vessel Nozzle to Safe End, Nozzle to Pipe and Safety End to Pipe Welds Using the Nozzle Scanner, June 30, 2017 Seabrook Unit 1 Reactor Vessel Nozzle Mechanical Stress Improvement Process Field Service Procedure, July 24, 2017 Seabrook Station Engineering Procedure ES1807.050, Revision 1, Visual Examination (VE) For CRDM Inspections, ASME Code Case N-729-1 Seabrook Station Engineering Procedure ES10-01-32, Revision 2, Remote Inservice Examination of Reactor Vessel Nozzle to Safe End, Nozzle to Pipe and Safe End to Pipe Welds Using the Nozzle Scanner, June 30, 2017 Seabrook Station Engineering Procedure ES10-01-31, Revision 3, ET Examination of Reactor Vessel Pipe Welds Inside Surface, August 31, 2017 Seabrook Station Engineering Procedure ES1807.050, Revision 1A; Visual Examination (VE) Procedure for Reactor Vessel Upper Head (RVUH) Penetration Inspections (N-729-1) Seabrook Station Administrative Procedure

MA 10.3, Revision 15, Boric Acid Corrosion Control Program Seabrook Engineering Department Instructions (EDI) BORIC ACID EVALUATIONS, EDI No. 30560, Revision 0 Seabrook Chemistry Procedure CS0905.08, Revision 8; Response To A Primary-to-Secondary Leak Seabrook Station Engineering Department Procedure ES1807.050, Revision 1; Visual Examination (VE) Procedure for CRDM Inspections (N-729-1)

Seabrook Station Engineering Department Procedure ES1807.037, Revision 4; Visual Examination (VE) Procedure for BMI Inspection (N-722-1) Seabrook Station Engineering Department Instruction

CDI-018, Revision 4; Primary-To-Secondary Leak Rate Monitoring Below 1 GPD Seabrook Station Engineering Procedure ES10-01-31, Revision 3; ET Examination of Reactor Vessel Pipe Welds Inside Surface, August 31, 2017

Condition Reports

00207921

01934094

01954739

01956858

01956974

01958294

01958658

01959231

01960060

01960192

01960662

01962130

01967763

01968281

01977393

01979332

01980333

01981302

01981663

01985049

01985507

01995292

02005943

02010624

02013631

02017775

02020023

02023008

02025166

02030144

02032984

02038340

02038887

02039668

02042461

02044332

02044452

02044899

02045365

02049171

02051868

02058610

02059112

02065121

02065815

02069165

02070738

02072120

02073698

02073706

02073711

02073712

02073714

02073720

02073720

02073740

02079633

02079633

02079633

02079633

02079690

02081530

02081530

20133359

Documented Boric Acid Leaks and Evaluations

01751940

01751948

01954739

01954894

01956887

01958294

01958658

01960060

01960192

01967763

01968281

01969662

01979332

01981302

01981663

01985507

02005943

02013359

02013631

02017775

02020023

02023008

02025166

02039668

02043261

02043789

02044332

02044452

02044772

02044772

02044899

02045365

02073706

02073711

02073712

02073714

02073720

02073720

02078055

02078097

02078112

02078117

02078120

02078121

02078124

02078128

02078130

02078133

02078134

02078135

02078139

02078140

02078143

02078145

02078146

02078268

02078274

02078472

02078700

02078839

02079208

02079236

02079241

02079247

02079278

02079287

02079290

02079294

02079297

02079303

02079318

02079325

02079330

02079333

02079336

02079341

02079342

02079343

02079349

02079353

02079360

02079361

02079363

02079366

02079367

02079372

02079375

02079377

02079380

02079381

02079385

02079389

02079393

02079394

02079398

20278063

Self-Assessments Quick Hit Assessment Report,

AR 02004668, Seabrook: Engineering Programs Quick Hit / Department Assessment Report,

AR 2024069, Fleet Steam Generator Program Self-Assessment; 7/30/15 Focused Self-Assessment

AR 1773622; Chemistry Sampling and Analysis Program, 8/15/12 Focused Self-Assessment

AR 02050220; Maintenance Implementation of Welding Program, 9/15/15 Quick Hit Assessment Report,

AR 01950056, Seabrook/Engineering Programs

Materials, OR16 Inservice Inspection (ISI) NRC Inspection, 3/24/14 Quick Hit Assessment Report,

AR 01725016, Seabrook Engineering Programs

Materials, Title: Integration of the Alloy 600 Program Into Inservice Inspection Engineering Evaluations Design Changes and SG Procedures: Engineering Evaluation

EE-09-016 Revision 0; Engineering Evaluation Flaw Indications In Reactor Vessel Safe End Welds.

By H.W. Mentel-Seabrook Station, October 22, 2009 Engineering Change (EC)

281842, Revision 0 Design Change Package Form MSIP, 15 Pages Document/PCR/EC#281724, Revision 0, 10 CFR Applicability Determination Form, 5 Pages Steam Generator Degradation Assessment for Seabrook OR17 Refueling Outage, Revision 1,

SG-SGMP-15-10, October 2015 Steam Generator Degradation Assessment for Seabrook OR17 Refueling Outage, Revision 2,

SG-SGMP-15-10, October 2015 Seabrook OR16 Condition Monitoring Assessment and Final Operational Assessment, April 2014,

SG-SGMP-15-10 Seabrook Appendix H & I Techniques, Fall 2015 Inspection;

MRS-TRC-2286, October 2015

EC-284861, Revision 0; Evaluation #EE-14-013, Revision 1; Seabrook Unit 1, Title: Reactor Vessel Head Effective Degradation Years (EDY) & Re-Inspection Years (RIY) for Cycle 17 ACR # 96-1258; Adverse Condition Report,

69034975, Cause Determination and corrective actions for 1996 leaks from SG B and SG C, 11/25/96 Seabrook OR17 Condition Monitoring Assessment and Final Operational Assessment, November 2015,

SG-SGMP-15-20, Revision 0

NDE Data Reports: Examination data sheets related to seven reactor vessel nozzle dissimilar metal welds as follows:

RC-RPV-SE-301-121-338-deg-D;

RC-RPV-SE-302-121-293 deg-C;

RC-RPV-SE 302-121-247-deg-B;

RC-RPV-SE-301-121-202-deg-A;

RC-RPV-SE-302-121-113 deg-G;

RC-RPV-SE-301-121-67-deg-F;

RC-RPV-SE-301-121-22 deg-E Data Sheet 15-VT-041, CRDM structural support, VT3 examination10-15-15 ES1807.037 Form A:

Visual Examination of BMI Penetrations and RPV Bottom Head

UNSAT due to Residue/Deposits or Wastage Detected (CR written to sample residue, clean residue and reinspect penetrations); VT Inspector Notes for each penetration (16 pages) and pictures of each penetration (105 pages)(11/3/15) ES1807.037 Form A: Visual Examination of BMI Penetrations and RPV Bottom Head after cleaning and re-inspection- SAT; (16 pages) and pictures of each penetration (11/6/15) Data Sheet 15-UT-001(5 pages), FW Elbow to pipe, Class 2, Thermal Fatigue Exam Data Sheet 15-UT-002(5 pages), FW Elbow to pipe, Class 2, Thermal Fatigue Exam Data Sheet 15-VT3-041(6 pages), CRDM STRUCTURAL SUPPORT Inspection, Class 1 IWE

VT-1 Re-Examination of a previously identified Containment Dome Anomaly/Indication Seabrook Nuclear Power Plant Unit 1 Refueling Outage OR17, Post MSIP Reactor Vessel Nozzle DM Weld Examination Summary, October 12 through October 22, 2015

Repair Replacement Activity WO EC282581

Miscellaneous

NUREG-0313, Revision 2, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, W.S. Hazelton; W.H. Koo, Title: Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping NRC Bulletin 2003-02:

Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity, August 21, 2003

Westinghouse

NSAL-14-6, 9/24/2014, Subject: Reactor Coolant Pump Turning Vane Bolt Cracking and Failures Code Case N-722-1, Additional Examinations for PWR Pressure Retaining Welds In Class 1 Components Fabricated with Alloy 600/82/182 MaterialsSection XI, Division 1 Code Case N-729-1, Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration WeldsSection XI, Division 1 Code Case N-770-1, Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation ActivitiesSection XI, Division 1 EPRI Technical Report 2011, Steam Generator Management Program: Primary-to-Secondary Leak Guidelines, Revision 4 Seabrook Station Reference Manual; Steam Generator Maintenance Reference, SGRE Revision 20, 3/10/14 Seabrook Station, Steam Generator Eddy Current Data Analysis Guideline Manual, Revision 7, 4/4/2014 NextEra Energy Program Description,

ER-AP-121, Revision 2; Steam Generator Integrity, 9/2/15 Apparent Cause Evaluation for AR 00207921

Section 1R11: Licensed Operator Requalification Program

Procedures

TR-AA-104, NEXTERA Energy Fleet Licensed Operator Continuing Training Program,

Revision 7

TR-AA-220-1004, Licensed Operator Continuing Training Annual Operating and Biennial

Written Exams, Revision 1

TR-AA-230-1004, SAT Implementation, Revision 5

TR-AA-230-1005, SAT Evaluation, Revision 2

TR-AA-230-1007, Crew-Specific Simulator Plan, Revision 3

Condition Reports

01917736

01923551

01954983

01966222

01987175

01988101

01994628

02012298

02014014

02015273

02022491

02022755

02024157

02027235

02038184

02040722

02042410

02046889

02050058

02054056

Miscellaneous

ACAD 10-001, February 2010, Revision 0 ANS 3.4-1983 Focused Area Self-Assessment Report

2058898 LORT Training Program Description, December 2012

NT 3744, Simulator Transient Tests, Revision 17 NRC Information Notice

IN 2004-20 NRC Information Notice

IN 94-14 NRC Information Notice

IN 91-08 NRC Regulatory Guide 1.134 NRC Regulatory Guide 1.8 Requalification Training Program Annual Examination Sample Plan 2015 Seabrook Transient Tests 1 through 11

Section 1R12: Maintenance Effectiveness

Procedures

ES1807.025, Inservice Inspection (ISI) Visual Examination Procedure, Revision 6 EX1805.03, Snubber Functional Test, Revision 12 LS0557.19, 480 Vac K600 Electrically Operated Breaker Refurbishment, Revision 15 MS0515.08, Paul-Munroe 2300, 2400 and 2500 Hydraulic Snubber Maintenance, Revision 4 MS0515.12, Cooling Tower Primary Fan and Gear Reducer Maintenance, Revision 5 MS0517.05, Installation of Pipe Supports, Revision 3

PEG-24, Maintenance Rule Goal Setting and Monitoring, Revision 8

PEG-45, Maintenance Rule Program Monitoring Activities, Revision 17

Condition Reports

02065121

02071704

02081775

02083296

02093663

02094577

02099774

Maintenance Orders/Work Orders

40289589

40353703

40379186

40410443

40418627

Miscellaneous

EE-10-010, Maintenance Rule PRA Basis Document PRA Risk Ranking and Performance Criteria Based on

SSPSS-2009, dated March 2011 Maintenance Rule Functional -6481-1) in High

Alarm

Not Valid NUMARC 93-01, Industry Guidelines for monitoring the Effectiveness of Maintenance at

Nuclear Power Plants, Revision 2 Radiation Monitoring System Health Report

SBK-L-15183, Seabrook Station Technical Specification Special Report

Radiation Monitor

Inoperable Greater Than 7 Days

Section 1R13: Maintenance Risk Assessments and Emergent Work Control

Procedures

ODI101, Guarded Equipment Recommendations for Refueling Outages, Revision 16

OP-AA-102-1003, Guarded Equipment, Revision 9

Condition Reports

02079027

02087297

02087302

Miscellaneous

LCOTR Log on October 8, 2015 Seabrook Station Shutdown Condition Status Report for 10/8/15 OCC Turnover at 0500

Section 1R15: Operability Determinations and Functionality Assessments

Procedures

PI-AA-104-1000, Corrective Action, Revision 3

Condition Reports

02044332

02080495

02080584

02081530

02082377

02082510

02083255

02083422

02084748

02084825

02085161

02085433

02098607

Maintenance Orders/Work Orders

94131854

Miscellaneous

2004 ASME Boiler and Pressure Vessel Code,Section XVI Engineering Evaluation Documenting Integrity of the Containment Liner Plate dated

October 28, 2015 NRC Information Notice 2014-07: Degradation of Leak-Chase Channel Systems for Floor Welds of Metal Containment Shell and Concrete Containment Metallic Liner Seabrook Station UFSAR Westinghouse Letter

LTR-RC-15-47, Operability Assessment for Ball Bearings Primary Side

Loose Parts at Seabrook Unit 1

Drawings

1-MS-B20582, Main Steam System Emergency Feedwater Pump Supply Detail, Revision 21 9763-F-805139, Containment Liner Floor Leak Chase System Piping Arrangement, Revision 10

Section 1R18: Plant Modifications

Procedures

EN-AA-205-1100, Design Change Package, Revision 13

EN-AA-203-1201, 10 CFR Applicability of 10

CFR 50.59 Screening Reviews, Revision 4 ES1807.025, Form B,

VT-2 Visual Examination Form, Revision 6 ES1850.012, Air Operated Valve Program Procedure, Revision 4 ES1810.206, Charging System

Charging Pump Discharge Pipe ISI System Leakage Test,

Revision 2 OX1408.06, Controlled Leakage Monthly Surveillance, Revision 7 OX1456.01, Charging Pump A & B Quarterly Flow and Valve Stroke Test And 18 Month

Remote Position Indication Verification, Revision 21

SM7.20, Control of Time Critical Actions and operator Response Times, Revision 8

Condition Reports

01973578

02041778

02041838

02042131

02079830

02087598

02090399

Maintenance Orders/Work Orders

40339187

40367789

Miscellaneous

50.59 Evaluation No. 15069, Revision 0

Calculation #CS145705, Revision 2 DBDEFW01, Emergency Feedwater System Design Basis Document, Revision 6 EC282453, Revision 0

EC282474, Revision 1 ES15-01-18, Radiographic Examination in Accordance with ASME Section V, Article 2, Rev. 0

Instruction Book 205, Reactor Coolant Pump Model W-11012-A1 (93-A1), Revision 5 MISTRAS Radiographic Inspection Report, 3INCH-SCH160-10132015, dated 10/14/15

PWROG-14006-P, Implementation Guide for the generation III Westinghouse Shutdown Seal,

Revision 0-B Seabrook Emergency Feedwater System Detailed Systems Text, Revision 10 Westinghouse

LTR-RES-14-104, Shutdown Seal Purge Volume, Coastdown Time and Material

Properties for Seabrook Station, dated October 13, 2014 Westinghouse

LTR-RES-14-126, Impact on the Seismic Evaluation by Installing the SHIELD at

Seabrook Station, dated November 13, 2014 Westinghouse

LTR-SEE-I-14-61, Downstream Effects Evaluation of an Inadvertent Actuation of the RCP Shutdown Seal at Seabrook Unit 1, dated December 4, 2014

Drawings

1NHY250000, Rev. 81, Data Sheets for Motor and Air Operated Valves and Dampers

Section 1R19: Post-Maintenance Testing

Procedures

LS0557.19, 480 VAC K-600 Electrically Operated Breaker Refurbishment, Revision 15 LX0556.113, 1-EDE-B-1-D 18-Month Technical Specification Battery Surveillance, Revision 3 OX1410.04, Post Refueling Pre-Startup Rx Trip Breaker Surveillance, Revision 10 OX1413.03, B Train RHR Quarterly Flow and Valve Stroke Test, and 18 Month Valve Stroke

Observation, Revision 13 OX1413.05, RHR Cold Shutdown Valve Testing, Revision 7 OX1413.08,

RH-P-8B Comprehensive Pump Test, Revision 10A OX1416.03, Monthly Cooling Tower Fan Operability Test, Revision 10 OX1436.13, Turbine Driven Emergency Feedwater Pump Post Cold Shutdown or Post

Maintenance Surveillance and Comprehensive Pump Test, Revision 29

Condition Reports

01647943

01837698

02069435

02071668

02083213

02083832

02085868

02085922

02090725

02091049

Maintenance Orders/Work Orders

40103650

40289589

40310982

40310991

40310993

40311461

40311466

40315437

40369086

40421948

40436813

40436853

Miscellaneous

1-NHY-31017, Sheet EG2a, 125VDC Bus 1-SWG-11D Distr Pnl 1-PP-111D Schedule,

Revision 8 1-NHY-310042, Sheet 2, 125VDC Vital Distribution System One Line Diagram, Revision 4 1-NHY-310942, Sheet E04/10, Process Protection Cabinet Power Supply

MM-CP-4 Cable

Schematic, Revision 0 1-NHY-310949, Sheet E01/2a, Solid State Protection System Cabinet

MM-CP-12 Schematic

Diagram, Revision 5 1-NHY-310949, Sheet E02/4a, Solid State Protection System Cabinet

MM-CP-13 Schematic

Diagram, Revision 5

Section 1R20: Refueling and Other Outage Activities

Procedures

AD-AA-101-1004, Work Hour Controls, Revision 16

EX1808.014, Containment Enclosure Building Integrity 18 Month Surveillance, Revision 10 IS1682.222, Spent Fuel Pool Level Calibration, Revision 7

ODI-101, Attachment D, Outage Status Sheet, Revision 16 ON1090.04, Containment Entry, Revision 30

OP-AA-102-1003, Guarded Equipment, Revision 9 OS1000.02, Plant Startup From Hot Standby to Minimum Load, Revision 31

OS1000.04, Plant Cooldown From Hot Standby to Cold Shutdown, Revision 51 OS1000.07, Approach to Criticality, Revision 13

OS1000.09, Refueling Operation, Revision 30

OS1000.10, Operation at Power, Revision 31

OS1000.14, Reactor Coolant System Evacuation and Fill, Revision 22

OS1000.14, Reactor Coolant System Evacuation and Fill, Revision 23 OS1001.02, Draining the Reactor Coolant System for Vessel Head Removal, Revision 19

OS1013.03, Residual Heat Removal Train A Startup and Operation, Revision 31

OS1013.04, Residual Heat Removal Train B Startup and Operation, Revision 28

OS1015.18, Setting Containment Integrity for Mode IV Entry, Revision 10 OX1406.12, 18 Month Containment and Containment Spray Recirculation Sump Surveillance,

Revision 11 OS1436.19, 18 Month ATWS Mitigation System Auto Actuation Surveillance, Revision 9

OX1426.34, Diesel Generator 1A 36 Month Operability Surveillance, Revision 17

RS1737, Post Refueling Low Power Physics Testing, Revision 7

Condition Reports

02005438

02074905

02080584

02080921

02080921

02082510

02084164

02088138

02097832

Maintenance Orders/Work Orders

40273392

40312116

40339169

40339170

40367789

40416945

Miscellaneous

Cycle 18 Core Map, dated 10/17/15

Drawing 9763-F-805139, Containment Liner Floor Leak Chase System Piping Arrangement,

Revision 10 Engineering Change

281724, Revision 0

Engineering Change

284624, Revision 0

LTR-PAFM-15-104, Seabrook SG & RCP Support Shim Gap Measurement Process Flowchart

LTR-PAFM-15-017, Seabrook SG & RCP Support Shim Gap Re-Shim Guidance PRA Evaluation

PRAE-15-011,

AR 2057299, OR17 Outage Schedule Shutdown Risk Review

AT-01.13 Mode Hold / Milestone Reports Report

SBK 15-013, Seabrook Nuclear Oversight Report, dated 11/19/15 Westinghouse Letter,

LTR-RVHP-15-56, Seabrook SG & RCP Support Option 2 Shim

Adjustments Post MSIP, dated October 20, 2015 Westinghouse Letter,

LTR-ISE-15-039, Power Ascension Shim Gap Monitoring Plan for

Seabrook Station Unit 1 During OR17, dated October 22, 2015

Section 1R22: Surveillance Testing

Procedures

ES1850.003, Motor Operated Valve Performance Monitoring, Revision 10 LS0569.16, Diagnostic Testing of Rising Stem MOVs, Revision 23

LS0569.17, Diagnostic Testing of Rising Stem MOVs Using the Torque Thrust Cell, Revision 17

OX1402, CVCS Cold Shutdown and Refueling Interval Valve Test, Revision 13 OX1456.81, Operability Testing of IST Valves, Revision 23

Condition Reports

02004690

02083866

Maintenance Orders/Work Orders

40312073

40312078

40321086

40414003 40414014

Section 1EP2: Alert and Notification System Evaluation

Procedures

EP-AA-101-1000, Nuclear Division Drill and Exercise Procedure, Revision 13

EP-AA-102, NextEra Energy Alert and Notification System, Revision 0 SIR10,

WPS-3000 and

WPS-4008 Siren Bi-Weekly Functional Test, Revision 4 SIR11,

WPS-3000 and

WPS-4008 Siren Annual Maintenance, Revision 2 SIR45, State Siren Activation Control System Annual Maintenance and Testing, Revision 4 SIR76, Local Town Siren Activation Control System Annual Maintenance and Testing,

Revision 4

Miscellaneous

Seabrook Station ANS Maintenance and Testing records, August 2013

December 2015 Seabrook Station Nuclear Power Plant Alert and Notification System Design Report,

Addendum 7, June 2013 Seabrook Station Radiological Emergency Plan, Revision 69

Section 1EP3: Emergency Response Organization Staffing and Augmentation System

Procedures

NM11700, Emergency Preparedness Responsibilities of Primary, Subject-to-call, and

Secondary, Emergency Response Organization members, Revision 35

Miscellaneous

2014 3rd Quarter Emergency Response Organization Notification Test Results 2014 4th Quarter Emergency Response Organization Notification Test Results 2015 3rd Quarter Emergency Response Organization Notification Test Results 2015 4th Quarter Emergency Response Organization Notification Test Results E-Plan Personnel Expiration Report

14 day look ahead dated December 4, 2015 ERO Staffing Succession Planning dated December 8, 2015 Radiological Emergency Preparedness Drill and Exercise Manual, Revision 41 Seabrook Station Emergency Response Manual, Revision 122 Seabrook Station On-Shift Staffing Analysis Report, Revision 1 Seabrook Station Radiological Emergency Plan, Revision 69 Weekly ERO Pager Test, and Quarterly ERO Call-In Drill, results, January 2012

June 2013

Section 1EP4: Emergency Action Level and Emergency Plan Changes

Procedures

ER1.1, Classification of Emergencies, Revision 55

ER1.2, Emergency Plan Activation, Revision 64

ER5.3, Operation of the Raddose-V, Revision 33

ER5.4, Protective Action Recommendations, Revision 34

Miscellaneous

Radiological Emergency Plan (SSREP), Revision 69

Section 1EP5: Maintaining Emergency Preparedness

Procedures

EN-AA-203-1201, 10 CFR Applicability of 10

CFR 50.59 Screening Reviews, Revision 4

EP-AA-100-1002, Emergency Preparedness Change Review Committee Guideline, Revision 2

EP-AA-100-1007, Evaluation of the Change to the Emergency Plan, Supporting Documents and Equipment (10CFR 50.59(a)), Revision 3

SM7.28, Seabrook Equipment Important to Emergency Response, Revision 2

Condition Reports

01890396

01937133

02005383

02005487

02023560

02025317

02030373

02031036

02032420

02052946

02052947

02052947

02068065

Miscellaneous

Benchmark Report on Use of Teams in the ERO,

AR 02062157 EP Readiness Assessment for INPO Evaluation,

AR 02014862 Formal Benchmark Report on VC Summer Emergency Preparedness,

AR 01928502 Quick Hit Assessment Report on EP NRC Inspection Readiness,

AR 02004700 Quick Hit Assessment Report on EAL Classification Timing,

AR 01898102 Quick Hit Assessment Report on ERO Self-Assessment,

AR 02004700

SEP 2014016, Seabrook Station

CFE 14-05 Report

SEP 2015003, Seabrook Station

CFD 15-01 Report

SEP 2015016, Seabrook Station

CFD 15-02 Report Seabrook Nuclear Oversight Report,

SBK 13-012 Seabrook Nuclear Oversight Report,

SBK 14-008 Seabrook Nuclear Oversight Report,

SBK 15-007 Seabrook Station Development of Evacuation Time Estimates 2014, Final Report, Revision 0 Seabrook Station Development of Evacuation Time Estimates 2015, Final Report, Revision 0 Seabrook Station Radiological Emergency Plan, Appendix D, letters of Agreement with Emergency Response Organization, Revision 60

Section 2RS1: Radiological Hazard Assessment and Exposure Controls

Procedures

HD095817, Performance of Routine Radiological Surveys, Revision 13 HD0955.50, Far West

REM-500 Operation, Revision 6 HN0960.10, Radiological Requirements for Entry Beneath Reactor Vessel, Revision 31

HN0960.17, Radiological Controls for Transfer of Spent Fuel between the Containment and the

Spent Fuel Pool, Revision 4

OA 13-007 Pre-Planned Posting and Survey Instructions, Revision 0

RP-AA-102-1001, Area Radiological Surveys, Revision 1

RP-AA-103-1001, Posting Requirements for Radiological Hazards, Revision 2

RP-AA-103-1002, High Radiation Area Controls, Revision 3

RP-AA-107-1001, Radioactive Material Receipt, Revision 2

RP-AA-107-1003, Unconditional and Conditional Release of Material, Revision 1

Condition Reports

02075677

02075678

02078744

02078869

02081011

02092044

Miscellaneous

Air Sample Results15-491 Transfer Canal FSB, October 4, 2015 Air Sample Results15-515 CTMT Reactor Cavity, October 7, 2015 Air Sample Results15-683 CTMT Reactor Cavity, October 20, 2015 Air Sample Results 15- Air Sample Results15-778 CTMT Reactor Cavity during Decontamination, October 30, 2015 HD0958.19 Form A Dosimetry Abnormality Occurrence Report, ED Dose Alarm Badge Number

6494, November 2, 2015 HD0958.19 Form A Dosimetry Abnormality Occurrence Report, ED Dose Alarm Badge Number

6478, November 5, 2015 HD0958.19 Form A Dosimetry Abnormality Occurrence Report, ED Dose Alarm Badge Number

6564, November 3, 2015 HD0958.19 Form A Dosimetry Abnormality Occurrence Report, ED Dose Alarm Badge Number

6045, November 5, 2015 HD0958.19 Form A Dosimetry Abnormality Occurrence Report, Lost TLD Badge Number 6584,

October 20, 2015 HD0958.03 Form A Personnel Contamination Report, Facial Contamination Badge Number

5937, October 19, 2015

HSYM-085

YRD-20-YD100, Radioactive Material Storage Building Rad Survey M-20151203-1,

December 3, 2015

HSYQ-001C Radiac Calibration Facility Survey M-20151021-34, October 21, 2015

HSYQ-001D C Vans & RM Trucks Survey M-20151102-8, November 2, 2015 HSYQ066A

FSB-21-FB202 Fuel Storage Building Survey M-20151101-9, November 1, 2015 HX0958.23 Figure 1, Non Exempt Source Index by Location, September 10, 2015 SB Radioactive Source Leak Test Survey M-20150910-3, September 10, 2015

Section 2RS2: Occupational

ALARA Planning and Controls

Procedures

RP15.4, Use and Control Temporary Shielding, Revision 12

RP-AA-104, ALARA Program, Revision 2

RP-AA-104-1000, ALARA Implementing Procedure, Revision 5

Condition Reports

02079857

02089191

02061478

02082603

02082386

02085254

Miscellaneous

Next Era,

OR 17 ALARA and Station Dose Performance, December 8, 2015 Next-Era, ALARA Review Board Meeting

ARB 15-06 Presentation, December 4, 2015

RP-AA-104-1000-F2 Pre Job ALARA Review ALARA Package No. 15-16 RCP Tie Rod and

Shim, October 25, 2015

Section 4OA1: Performance Indicator Verification

Procedures

CS0917.02, Gaseous Effluent Releases, Revision 14 CX0917.01, Liquid Effluent Releases, Revision 20

EPDP-03, Emergency Preparedness Performance Indicators, Revision 25 HD0958.33, Performance of Radiation Protection Supervisory Plant Walkdowns, Revision 6 JD0999.910, Reporting Key Performance Indicators per

NEI 99-02, Revision 7

Condition Reports

02092877

02079246

02079779

02082355

Miscellaneous

SBK-PRAE-15-001, Seabrook MSPI Basis Document Update 2014, Revision 0

LIC-15004, Performance Indicator Data, 4th Quarter 2014

LIC-15015, Performance Indicator Data, 1st Quarter 2015

LIC-15026, Performance Indicator Data, 2nd Quarter 2015

LIC-15-032, Performance Indicator Data, 3rd Quarter 2015 Alert Notification System PI data, December 2014

December 2015 DEP PI data, December 2014

December 2015 ERO Drill Participation PI data, December 2014

December 2015 NextEra - Seabrook Station 2014 Annual Radioactive Release Report, April 24, 2015

CP4.1B GEW Sample Collection Data, Permit Number 15-321 Steam Generator Blowdown, August 13, 2015

CP4.1B GEW Sample Collection Data, Permit Number 15-316, Plant Vent, August 15, 2015 CS0908.01 Form F

Radioactive Effluent Dose Assessment Report 2015, December 9, 2015 CS0917.02 Form C GEW Containment Purge Release Permit 15-409 Containment Purge,

September 28, 2015 CX0917.01, Form C LEW Release Data, Permit Number 15-433, Waste Test Tank,

October 7, 2015 CX0917.01, Form C LEW Release Data, Permit Number 15-438, Turbine Building Sump,

October 6, 2015 CX0917.01, Form C LEW Release Data, Permit Number 15-319, Groundwater, July 31, 2015 JD0999.910 Figure 1 Occupational Exposure Occurrence, October, November and December

2014, January 12, 2015 JD0999.910 Figure 1 Occupational Exposure Occurrence, January, February and March 2015,

April 2, 2015 JD0999.910 Figure 1 Occupational Exposure Occurrence, April, May and June 2015,

December 2, 2015 JD0999.910 Figure 1 Occupational Exposure Occurrence, July, August and September, 2015, October 15, 2015

Section 4OA2: Problem Identification and Resolution

Procedures

EN-AA-203-1001, Operability Determinations/Functionality Assessments, Revision 21

PI-AA-104-1000, Corrective Actions, Revision 6

PI-AA-207-1000, Station Self-Evaluation and Trending Analysis, Revision 5

Condition Reports

01664399

01929460

01936340

01972065

01977373

01977456

01990185

01991967

01995588

01999679

02000523

02002668

02002750

02004749

02007975

02011136

02013241

02014325

02014325

02018118

02031149

02034198

02039025

02044627

02063563

02070871

02078215

02078215

02085144

02085147

Maintenance Orders/Work Orders

01191454

40274351

40279910

40314207

40320492

40325682

40345801

Work Requests

94098872

94106748

Miscellaneous

dated March 17, 2015

Maintenance Department Rework Assessment dated January 9, 2015 Maintenance Department Rework Assessment dated May 29, 2015 Operations Department Station Self-Evaluation and Trending Analysis Report, 2nd quarter 2015 Operations Department Station Self-Evaluation and Trending Analysis Report, 3rd quarter 2015

Section 4OA5: Other Activities

Procedures

Seabrook Station Instrumentation & Controls Procedure, Dry Fuel Storage HSM Temperature

Monitoring System Calibration Check, IS3600.401, Revision 3 Seabrook Station Radiation Protection Procedure, Performance of Routine Radiological

Surveys, HD0958.17, Revision 13 Seabrook Station Radiation Protection Procedure, DFS Radiological Controls, HX3950.85,

Revision 7 Seabrook Station Security Procedure, Protected Area, DFS, and Vehicle Barrier System

Inspections, GN1322.00, Revision 39

Condition Reports

01898310

01949316

01970650

02036364

02040234

02042227

02059136

02060075

02096511

Calculations

Calc No:

SBK-1FJF-13-014, Rev. 2, Seabrook Station- Irradiated Fuel Assembly Selection for

Second Dry Cask Loading Campaign

Miscellaneous

Action Request Report, AR Number

02050994, Concrete Inspection at DFS Area, 05/29/2015 Activity Documentation Sheet,

HEN-Q6, Evaluate Quarterly Environmental and Protected Area

TLD Results Second Quarter 2015 DFS Lessons Learned 2013 Evaluation for Blind Spike TLD Test

BS-13-08-28 Neutron Test Outside of Tolerance for

AR01949316

Health Physics Study/Technical Information Document 13-007, Determination of Dry Fuel

Storage Neutron Correction Factor for Global TLDs 09/2013

HSYQ-001M Dry Fuel Storage Surveys, 10/17/2013 through 11/03/2015 Nuclear Engineering Department Discipline Standard,

STD-F-040, Revision 6, Nuclear Fuel, Dry

Cask Storage Fuel Assembly Assignments, August 2013 Personnel Contamination Report for

AR01898310, 08/21/2013 Pre and Post-Job ALARA Review 13-01, Rev. 0, Dry Fuel Transfer Pool to Pad and Associated

Tasks for 8 Casks Radiation Work Permit, 15-0023, Dry Fuel Storage Area Maintenance/Inspection Activities,

03/02/2015, Revision 01 Seabrook 2013 ISFSI Demonstration Exercise Plan, 06/2013 Tech Spec and Commitment Logs, DFS Daily Temperature or Visual Inspection July 14, 2015 through October 25, 2015

LIST OF ACRONYMS

ADAMS Agencywide Documents Access and Management System

ALARA as low as reasonably achievable

ANS Alert and Notification System

AR action request

ASME American Society of Mechanical Engineers

ASR alkali-silica reaction

CAP corrective action program

CEB containment enclosure building

CFR Code of Federal Regulations CoC Certificate of Compliance

CR condition report

CRDM control rod drive mechanism

CS containment spray

CT cooling tower

EAL emergency action level

EC eddy current

EDG emergency diesel generator

EP emergency preparedness

ERF Emergency Response Facility

ERO Emergency Response Organization

FEA finite element analysis

FP Foreign Print

FSEL Ferguson Structural Engineering Laboratory

IMC Inspection Manual Chapter

ISFSI independent spent fuel storage installation

ISI inservice inspection

JPM job performance measure

MR maintenance rule

MRC Management Review Committee

NCV non-cited violation

NDE non-destructive examination

NEI Nuclear Energy Institute

NRC Nuclear Regulatory Commission

OR refueling outage

PI performance indicator

POD Prompt Operability Determination

RCE root cause evaluation

RCS reactor coolant system

RG Regulatory Guide

RHR residual heat removal

RP radiation protection

SG steam generator

SSC structure, system, and component

SW service water

TS technical specification

URI unresolved item

VCT volume control tank WO work order