IR 05000277/2017004

Peach Bottom Atomic Power Station - Integrated Inspection Report 05000277/2017004 and 05000278/2017004 and Exercise of Enforcement Discretion

ML18033A046
Person / Time
Site:	Peach Bottom
Issue date:	02/01/2018
From:	Erin Carfang Division Reactor Projects I
To:	Bryan Hanson Exelon Generation Co
Carfang E
References
EA-17-207 IR 2017004
Download: ML18033A046 (40)

Text

[Type here] February 1, 2018 EA-17-207 Mr. Bryan Hanson Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT: PEACH BOTTOM ATOMIC POWER STATION - INTEGRATED INSPECTION REPORT 05000277/2017004 AND 05000278/2017004 AND EXERCISE OF ENFORCEMENT DISCRETION

Dear Mr. Hanson:

On December 31, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Peach Bottom Atomic Power Station, Units 2 and 3. On January 12, 2018, the NRC inspectors discussed the results of this inspection with Mr. Matthew Herr, Plant Manager, and other members of your staff. The results of this inspection are documented in the enclosed report. The NRC inspectors did not identify any finding or violation of more than minor significance. The inspectors also reviewed Licensee Event Report 05000278/2017-001-00, which described the details associated with a reactor coolant system pressure boundary leak from a 1-inch socket welded recirculation system instrumentation line on the Unit 3 'B' recirculation line. Although this constituted a violation of technical specifications involving the reactor coolant system pressure boundary, the NRC concluded that the issue was not within Exelon's ability to foresee and correct, Exelon's actions did not contribute to the degraded condition, and the actions taken were reasonable to address the issue. As a result, the NRC did not identify a performance deficiency. A risk evaluation was performed, and the issue was determined to be of very low safety significance (Green). Based on the results of NRC's inspection and assessment of this issue, I have been authorized, after consultation with the Director, Office of Enforcement, and the Regional Administrator, to exercise enforcement discretion, in accordance with NRC's Enforcement Policy Section 2.2.4, "Using Traditional Enforcement of Disposition Violations Identified at Power Reactors," and Section 3.10, "Reactor Violations With No Performance Deficiencies." This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and the NRC's Public Document Room in accordance with 10 Code of Federal Regulations (CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding."

Sincerely,/RA/ Erin E. Carfang, Acting Branch Chief Reactor Projects Branch 4 Division of Reactor Projects Docket Nos. 50-277 and 50-278 License Nos. DPR-44 and DPR-56

Enclosure:

Inspection Report 05000277/2017004 and 05000278/2017004

w/Attachment:

Supplementary Information cc w/encl: Distribution via ListServ

ML18033A046 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP R1/DRP R1/DRP NAME JHeinly/JH SBarber/SB ECarfang/EC MMcLaughlin/MM DATE 01/29/18 01/30/18 02/01/18 01/30/18 1 Enclosure U. S. NUCLEAR REGULATORY COMMISSION REGION I Docket Nos. 50-277 and 50-278 License Nos. DPR-44 and DPR-56 Report No. 05000277/2017004 and 05000278/2017004 Licensee: Exelon Generation Company, LLC Facility: Peach Bottom Atomic Power Station, Units 2 and 3 Location: Delta, Pennsylvania Dates: October 1, 2017 through December 31, 2017 Inspectors: J. Heinly, Senior Resident Inspector G. Stock, Acting Senior Resident Inspector B. Smith, Resident Inspector J. Cassata, Health Physicist J. DeBoer, Emergency Preparedness Inspector, DRS J. Kulp, Senior Reactor Inspector B. Dionne, Senior Health Physicist Approved By: Erin E. Carfang, Acting Branch Chief Reactor Projects Branch 4 Division of Reactor Projects 2

SUMMARY

Inspection Report 05000277/2017004 and 05000278/2017004; 10/01/2017 - 12/31/2017; Peach Bottom Atomic Power Station (PB), Units 2 and 3; Integrated Inspection Report. This report covered a three-month period of inspection by resident inspectors, and announced baseline inspections performed by regional inspectors. The Nuclear Regulatory Commission's (NRC) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 6. No findings were identified during this inspection.

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REPORT DETAILS

Summary of Plant Status Unit 2 began the inspection period at 100 percent rated thermal power (RTP). On October 18, 2017, operators performed a downpower to 57 percent RTP to perform planned waterbox cleaning. On October 19, 2017, operators returned the unit to 100 percent RTP. On December 15, 2017, operators performed a downpower to 40 percent RTP to perform waterbox cleaning, turbine control valve testing, and troubleshooting on the 'A' reactor recirculation pump upper and lower bearing oil level systems. On December 17, 2017, operators returned the unit to 100 percent RTP and remained at 100 percent RTP except for brief periods to support planned testing and control rod pattern adjustments.

Unit 3 began the inspection period at 86 percent RTP in end-of-cycle coastdown for refueling outage (RFO) P3R21. On October 22, 2017, operators commenced a shutdown from 78 percent RTP and entered into RFO (P3R21). On November 6, 2017, the Unit 3 mode switch was placed in start-up and the main generator was synchronized to the electrical grid on November 7, 2017. On November 9, 2017, Unit 3 was returned to 100 percent RTP and remained at 100 percent RTP until the end of the inspection period except for brief periods to support planned testing and control rod pattern adjustments.

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R01 Adverse Weather Protection

Winter Readiness - Seasonal Extreme

a. Inspection Scope

The inspectors reviewed PB's readiness for the cold weather conditions during the week of October 13, 2017. The review focused on the high-pressure service water (HPSW) system, the emergency cooling tower, the circulating water pump house, and associated support equipment. The inspectors reviewed the Updated Final Safety Analysis Report (UFSAR), technical specifications (TSs), and the corrective action program (CAP) to determine the temperatures or other seasonal weather conditions that could challenge these systems. The review ensured PB's personnel had prepared adequately for the weather-related challenges. The inspectors reviewed station procedures, including PB's seasonal weather 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.

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: Unit 2 and Unit 3 standby gas treatment on October 26, 2017 Unit 3 'B' shutdown cooling on October 26-27, 2017 Unit 3 reactor core isolation cooling (RCIC) on November 6, 2017 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, TS, work orders (WOs), issue reports (IRs), and the impact of ongoing work activities on redundant trains of equipment in order to identify conditions that could have impacted the system's 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 Exelon 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 the week of October 30, 2017, the inspectors performed a complete system walkdown of accessible portions of the Unit 3 high-pressure coolant injection (HPCI) system to verify the existing equipment lineup was correct. The inspectors reviewed operating procedures, surveillance tests (STs), drawings, equipment line-up check-off lists, 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 system to verify as-built system configuration matched plant documentation, and that system components and support equipment remained operable. The inspectors confirmed that systems and components were aligned correctly, free from interference from temporary services or isolation boundaries, environmentally qualified, and protected from external threats. The inspectors also examined the material condition of the components for degradation and observed operating parameters of equipment to verify that there were no deficiencies. Additionally, the inspectors reviewed a sample of related IRs and WOs to ensure Exelon appropriately evaluated and resolved any deficiencies.

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 Exelon 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 (OOS), degraded or inoperable fire protection equipment, as applicable, in accordance with procedures.

Unit 3 main condenser (PF-78) on October 24, 2017 Unit 3 main steam isolation valve (MSIV) room (PF-29) on October 25, 2017 Unit 3 drywell (PF-32) on October 26, 2017 Unit 3 torus (proper) (PF-13C) on October 30, 2017 Unit 2 refuel floor (PF-57) on November 30, 2017 Unit 3 refuel floor (PF-55) on November 30, 2017

b. Findings

No findings were identified.

1R08 In-service Inspection

a. Inspection Scope

From October 30, 2017 to November 3, 2017, the inspectors conducted an inspection and review of in-service inspection (ISI) activities in order to assess the effectiveness of Exelon's program for monitoring degradation of the reactor coolant system (RCS) boundary, risk-significant piping boundaries, and the containment system boundaries during the PB Unit 3 21st RFO. Non-destructive Examination and Welding Activities (IP Section 02.01) The inspectors observed a sample of in-process non-destructive examinations (NDE), reviewed completed documentation, and interviewed Exelon personnel to verify that the NDE activities performed as part of the fourth interval, third period, of the PB Unit 3 ISI program were conducted in accordance with the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 2001 Edition with the 2003 Addenda. For augmented examinations, the inspectors verified that activities were performed in accordance with Exelon's augmented inspection program and procedures, and with any applicable industry guidance documents.

The inspectors verified that indications and defects, if present, were dispositioned in accordance with the ASME Code or an NRC-approved alternative, and verified that relevant indications were compared to previous examinations to determine if any changes had occurred. Activities included a review of ultrasonic testing (UT), magnetic particle testing (MT), dye penetrant testing (PT), radiographic testing, and visual testing (VT). The inspectors reviewed certifications of the NDE technicians performing the examinations and verified that the inspections were performed in accordance with qualified NDE procedures and industry guidance. For UT activities, the inspectors also verified the calibration of equipment used to perform the examinations. The inspectors verified that the test results were reviewed and evaluated by certified Level III NDE personnel and that the parameters used in the test were in accordance with the limitations, precautions, and prerequisites specified in the test procedure. ASME Code Required Examinations: Direct observation of the manual UT weld 10-IB-19 in the residual heat removal (RHR) system. Direct observation of the manual UT of welds 12-13-11, 12-13-12, and 12-13-13 in the reactor water cleanup (RWCU) system. Documentation review of manual UT of welds 12-14-11, 12-14-12, and 12-14-13. Direct observation of the PT/VT of socket welds RTV-3-02A-5449A/W-1 and HV-3-02A-5A/W-22 in the reactor recirculation system. Documentation review of the VT (VT-3) of reactor pressure vessel (RPV) stabilizing bars at 270 and 315 degrees (F-A/F.1.40). Documentation review of the MT of the N3 reinforcing plate (N3-(RP)-A).

Documentation review of the MT of welded attachment RHRHX-A-LS (IA) on the A RHR heat exchanger (HX).

Documentation review of the RT of welds 12-13-12, 12-13-13, and 12-13-11A following repair activities. Other Augmented, License Renewal or Industry Initiative Examinations: Direct observation of the manual UT of non-safety related RWCU welds 12-13-12 and 12-13-13 and documentation review for welds 12-14-12 and 12-14-13 satisfying Generic Letter (GL) 88-01 requirements. Document review of the remote enhanced VT records of the reactor vessel internals during in-vessel visual inspection activities in accordance with BWRVIP-03. Specifically, the inspectors reviewed the core spray (CS) sparger bracket welds, feedwater end bracket welds, steam dryer supports, and jet pump components, including the main wedges and the wedge hold down system components. Review of Previous Indications The inspectors did not review any previous indications because there were no relevant indications from the previous RFO that required evaluation for continued service at this time.

Welding on Pressure Boundary Systems The inspectors reviewed the risk-significant pressure boundary welding activity, including the associated NDE, of the installation of a new 4-inch elbow and associated piping as a corrective action (CA) following discovery of an intergranular stress corrosion cracking indication in weld 12-13-12 in the RWCU system. Specifically, the scope of the activity was to remove and replace a 4-inch elbow and other attached piping which were affected by the indication. The inspectors performed a documentation review of the welding activities to verify that the welding, RT/PT/VT examinations, and final acceptance were performed in accordance with the ASME Code requirements. The inspectors reviewed the welding procedure to ensure it contained the required essential and supplemental essential weld variables and that those variables were within the ranges demonstrated by the supporting qualification record. The repair was performed under WO 4596010. Identification and Resolution of Problems (IP Section 02.05) The inspectors reviewed a sample of PB Unit 3 CA reports, which identified NDE indications, deficiencies, and other non-conforming conditions since the previous RFO and during the current outage. The inspectors verified that non-conforming conditions were properly identified, characterized, evaluated, and that CAs were identified and entered into the CAP for resolution.

b. Findings

No findings were identified.

1R11 Licensed Operator Requalification Program and Licensed Operator Performance

.1 Quarterly Review of Licensed Operator Requalification Testing and Training (1 sample)

a. Inspection Scope

The inspectors observed licensed operator requalification training on October 2, 2017, which involved the mitigation of a scenario with a primary containment leak, anticipated transient without scram (ATWS), and entry into the emergency operating procedures (EOPs). The inspectors evaluated operator performance in the control room simulator during the training and verified completion of risk significant operator actions, including the use of abnormal and EOPs. The inspectors assessed the clarity and effectiveness of communications, implementation of actions in response to alarms and degrading plant conditions, and the oversight and direction provided by the control room supervisor. The inspectors verified the accuracy and timeliness of the emergency classifications made by the shift manager and the TS action statements entered by the shift technical advisor. Additionally, the inspectors assessed the ability of the crew and training staff to identify and document crew performance problems.

b. Findings

No findings were identified.

===.2 Quarterly Review of Licensed Operator Performance in the Main Control Room (1 sample)

a. Inspection Scope

The inspectors observed and reviewed the licensed operator performance from the main control room during the Unit 3 start up activities on November 7, 2017. The inspectors observed use of and compliance with procedures, crew communications, interpretation, diagnosis, and understanding of plant alarms, use of human error prevention techniques, documentation of activities, and management oversight of the evolution to verify that the crew was following procedures and plant expectations for conduct of operations. The inspectors observed control room briefings and power changes. Additionally, the inspectors observed power changes 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.

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a. Inspection Scope

The inspectors reviewed the samples listed below to assess the effectiveness of maintenance activities on structures, systems, and components (SSCs) performance and reliability. The inspectors reviewed system health reports, CAP documents, maintenance WOs, and maintenance rule (MR) basis documents to ensure that Exelon 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 Code of Federal Regulations (CFR) 50.65 and verified that the (a)(2) performance criteria established by the Exelon staff was reasonable. As applicable, for SSCs classified as (a)(1), the inspectors assessed the adequacy of goals and (CAs) to return these SSCs to (a)(2) status. Additionally, the inspectors ensured that Exelon staff was identifying and addressing common cause failures that occurred within and across MR system boundaries.

Unit 2 and Unit 3 quality control program during the week of November 13, 2017 Unit 2 and Unit 3 a(3) assessment during the week of November 27, 2017 Unit 3 reactor pressure boundary function during the weeks of December 4, and 11, 2017

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 Exelon 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 Exelon personnel performed risk assessments as required by 10 CFR 50.65(a)(4) and that the assessments were accurate and complete. When Exelon performed emergent work, the inspectors verified that operations personnel promptly assessed and managed plant risk. The inspectors reviewed the scope of maintenance work and discussed the results of the assessment with the station's probabilistic risk analyst to verify plant conditions were consistent with the risk assessment. The inspectors also reviewed the TS requirements and inspected portions of redundant safety systems, when applicable, to verify risk analysis assumptions were valid, and applicable requirements were met.

Unit 3 reactor cavity flood-up activity (reduced inventory) on October 24, 2017 Unit 3 reactor cavity drain down activity (reduced inventory) on November 3, 2017 Unit 3 containment de-inerted on November 8, 2017 Unit 2 'D' RHR heat exchanger relief valve maintenance on November 27, 2017 Unit 2 startup transformer outage on December 4, 2017

b. Findings

No findings were identified.

1R15 Operability Determinations and Functionality Assessments

a. Inspection Scope

The inspectors reviewed operability determinations (ODs) for the following degraded or non-conforming conditions based on the risk significance of the associated components and systems: Unit 3 jet pump wedge measurements out-of-tolerance on October 31, 2017 Unit 3 'A' safety/relief valve solenoid disconnected wire on November 1, 2017 Unit 3 shutdown cooling snubber test failures on November 6, 2017 Unit 2 and Unit 3 E-3 emergency diesel generator (EDG) turbo air inlet and exhaust gas temperatures outside of acceptable range on November 14, 2017 The inspectors evaluated the technical adequacy of the ODs 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 Exelon's evaluations to determine whether the components or systems were operable. The inspectors confirmed, where appropriate, compliance with bounding limitations associated with the evaluations, including compliance with IST requirements. Where compensatory measures were required to maintain operability, such as in the case of operator workarounds, the inspectors determined whether the measures in place would function as intended and were properly controlled by Exelon.

b. Findings

No findings were identified.

1R18 Plant Modification

Permanent Modifications

a. Inspection Scope

The inspectors evaluated the following two modifications: Unit 3 digital electro-hydraulic control during the week of November 13, 2017 Unit 3 digital feedwater during the week of November 20, 2017 The inspectors reviewed 10 CFR 50.59 documentation and post-modification testing results, and conducted field walkdowns of the modifications to verify that the permanent modifications did not degrade the design bases, licensing bases, and performance capability of the affected system.

b. Findings

No findings were identified.

1R19 Post-Maintenance Testing

a. Inspection Scope

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

Unit 3 E-13 bus undervoltage relay replacement on October 28, 2017 Unit 2 and Unit 3 E-1 EDG governor tuning on November 1, 2017 Unit 3 HPCI outboard steam isolation valve maintenance on November 1, 2017 Unit 3 'B' MSIV 86B stroke timing following poppet modification on November 1, 2017 Unit 3 'A' CS injection valve maintenance on November 2, 2017 Unit 3 RCIC valve stroke testing following outage inspection test on November 5, 2017 Unit 3 HPCI 150 pound flow test during outage start-up following HPCI maintenance on November 9, 2017

b. Findings

No findings were identified.

1R20 Refueling and Other Outage Activities

Unit 3 RFO (P3R21)

a. Inspection Scope

The inspectors reviewed the station's work schedule and outage risk plan for the Unit 3 P3R21 RFO, conducted October 23, 2017 to November 7, 2017. The inspectors reviewed Exelon's development and implementation of outage plans and schedules to verify that risk, industry experience, previous site-specific problems, and defense-in-depth were considered. During the outage, the inspectors observed portions of the shutdown and cooldown processes and monitored controls associated with the following outage activities: Configuration management, including maintenance of defense-in-depth, commensurate with the outage plan for the key safety functions and compliance with the applicable TSs when taking equipment OOS Implementation of clearance activities and confirmation that tags were properly hung and that equipment was appropriately configured to safely support the associated work or testing Installation and configuration of reactor coolant pressure, level, and temperature instruments to provide accurate indication and instrument error accounting Status and configuration of electrical systems and switchyard activities to ensure that TSs were met Monitoring of decay heat removal operations Impact of outage work on the ability of the operators to operate the spent fuel pool cooling system Reactor water inventory controls, including flow paths, configurations, alternative means for inventory additions, and controls to prevent inventory loss Activities that could affect reactivity Maintenance of secondary containment as required by TSs Fatigue management Refueling activities, including fuel handling and fuel receipt inspections Tracking of startup prerequisites, walkdown of the drywell (primary containment) to verify that debris had not been left which could block the emergency core cooling system suction strainers, and startup and ascension to full power operation Identification and resolution of problems related to RFO activities

b. Findings

No findings were identified.

1R22 Surveillance Testing

a. Inspection Scope

The inspectors observed performance of STs and/or reviewed test data of selected risk-significant SSCs to assess whether test results satisfied TSs, the UFSAR, and Exelon 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 STs: Unit 3 'A' CS injection valve local leak rate testing (LLRT) on October 24, 2017 Unit 3 inboard and outboard MSIV LLRTs for containment isolation valves on October 25, 2017 Unit 3 'A' standby liquid control biennial comprehensive in-service test (IST) on October 29, 2017 Unit 2 and Unit 3 E-33 loss of offsite power (LOOP)/loss-of-coolant accident (LOCA) testing on November 2, 2017

b. Findings

No findings were identified. Cornerstone: Emergency Preparedness

1EP4 Emergency Action Level and Emergency Plan Changes

a. Inspection Scope

Exelon implemented various changes to the PB Emergency Action Levels (EALs), Emergency Plan (EP), and Implementing Procedures. Exelon had determined that, in accordance with 10 CFR 50.54(q)(3), any change made to the EALs, EP, 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 50 Appendix E.

The inspectors performed an in-office review of all EAL and EP changes submitted by Exelon as required by 10 CFR 50.54(q)(5), including the changes to lower-tier EP implementing procedures, to evaluate for any potential reductions in effectiveness of the EP. 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. The specific documents reviewed during this inspection are listed in the Attachment.

b. Findings

No findings were identified.

1EP6 Drill Evaluation

Emergency Preparedness Drill/Simulator Evaluation/Observation

a. Inspection Scope

The inspectors evaluated the shift manager/emergency director's emergency preparedness implementation during a licensed operator out-of-the-box simulator training on October 2, 2017, which involved an ATWS and primary containment failures. The inspectors observed emergency response operations in the simulator to determine whether event classifications and notifications were performed in accordance with approved procedures. The inspectors also attended the control room simulator drill critique to compare inspector observations with those identified by Exelon staff in order to evaluate whether Exelon staff were properly identifying emergency preparedness weaknesses and entering them into the CAP.

b. Findings

No findings were identified.

RADIATION SAFETY

Cornerstone:

Occupational and Public Radiation Safety

2RS0 1 Radiological Hazard Assessment and Exposure Controls

a. Inspection Scope

The inspectors reviewed Exelon's performance in assessing and controlling radiological hazards in the workplace. The inspectors used the requirements contained in 10 CFR 20, TS, applicable regulatory guides (RGs), and the procedures required by TS as criteria for determining compliance. Radiological Hazard Assessment The inspectors conducted independent radiation measurements during walk-downs of the facility and reviewed the radiological survey program, air sampling and analysis, continuous air monitor use, recent plant radiation surveys for radiological work activities, and any changes to plant operations since the last inspection to verify survey adequacy of any new radiological hazards for onsite workers or members of the public. Instructions to Workers The inspectors reviewed radiation work permit (RWP) controls and use in high radiation areas and locked high radiation areas. The inspectors observed containers of radioactive materials and assessed whether the containers were labeled and controlled in accordance with requirements. The inspectors verified follow-up investigations of actual radiological conditions for unexpected radiological hazards were performed.

Contamination and Radioactive Material Control The inspectors observed the monitoring of potentially contaminated material leaving the radiological controlled area and inspected the methods and radiation monitoring instrumentation used for control, survey, and release of that material.

Radiological Hazards Control and Work Coverage The inspectors evaluated in-plant radiological conditions and performed independent radiation measurements during facility walkdowns and observation of radiological work activities. The inspectors assessed whether posted surveys; RWPs; worker radiological briefings and radiation protection job coverage; the use of continuous air monitoring, air sampling and engineering controls; and dosimetry monitoring were consistent with the present conditions.

Radiation Worker Performance and Radiation Protection Technician Proficiency The inspectors evaluated radiation worker performance with respect to radiation protection work requirements. The inspectors evaluated radiation protection technicians in performance of radiation surveys and in providing radiological job coverage.

b. Findings

No findings identified.

2RS0 2 Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls

a. Inspection Scope

The inspectors assessed Exelon's performance with respect to maintaining occupational individual and collective radiation exposures ALARA. The inspectors used the requirements contained in 10 CFR 20, RGs 8.8 and 8.10, TSs, and procedures required by TSs as criteria for determining compliance. Radiological Work Planning The inspectors selected the following radiological work activities based on exposure significance for review: RWP No. 506, Drywell Scaffolding Activities RWP No. 510, Main Steam Safety Relief Valve Activities RWP No. 515, Drywell Under-vessel Equipment Maintenance RWP No. 548, Drywell Recirculation Pump Seal and Motor Activities RWP No. 901 Reactor Disassembly/Reassembly Activities For each of these activities, the inspectors reviewed: ALARA work activity evaluations, exposure estimates, exposure/contamination reduction controls, results achieved (dose rate reductions, actual dose), person-hour estimates and results achieved.

Verification of Dose Estimates and Exposure Tracking Systems The inspectors reviewed the current annual collective dose estimate; basis methodology; and measures to track, trend, and reduce occupational doses for ongoing work activities. The inspectors evaluated the adjustment of exposure estimates and planning of work.

Implementation of ALARA and Radiological Work Control The inspectors reviewed radiological work controls and ALARA practices during the observation of in-plant work activities. The inspectors verified use of shielding, contamination controls, airborne controls, RWP controls, and other work controls were consistent with ALARA plans. The inspectors also verified that the ALARA staff was involved with emergent work activities and were revising both dose estimates and ALARA controls in the associated RWPs/ALARA plans, as appropriate.

b. Findings

No findings were identified.

2RS0 3 In-Plant Airborne Radioactivity Control and Mitigation

a. Inspection Scope

The inspectors reviewed the control of in-plant airborne radioactivity and the use of respiratory protection devices in these areas. The inspectors used the requirements in 10 CFR 20, RG 8.15, RG 8.25, NUREG/CR-0041, TS, and procedures required by TS as criteria for determining compliance. Engineering Controls The inspectors reviewed operability and use of both permanent and temporary ventilation systems and the adequacy of airborne radioactivity radiation monitoring in the plant based on location, sensitivity, and alarm set-points. Use of Respiratory Protection Devices The inspectors reviewed the adequacy of Exelon's use of respiratory protection devices in the plant to include applicable ALARA evaluations, respiratory protection device certification, respiratory equipment storage, air quality testing records, and individual qualification records. Problem Identification and Resolution The inspectors evaluated whether problems associated with the control and mitigation of in-plant airborne radioactivity were identified at an appropriate threshold and addressed by Exelon's CAP.

b. Findings

No findings were identified.

2RS0 4 Occupational Dose Assessment

a. Inspection Scope

The inspectors reviewed the monitoring, assessment, and reporting of occupational dose. The inspectors used the requirements in 10 CFR 20, RGs, TSs, and procedures required by TSs as criteria for determining compliance.

External Dosimetry The inspectors reviewed: onsite storage of dosimeters; the use of "correction factors" to align electronic personnel dosimetry results with national voluntary laboratory accreditation program dosimetry results; dosimetry occurrence reports; and CAP documents for adverse trends related to external dosimetry. Internal Dosimetry The inspectors reviewed: internal dosimetry procedures; whole body counter measurement sensitivity and use; adequacy of the program for whole body count monitoring of plant radionuclides; adequacy of the program for dose assessments based on air sample monitoring and the use of respiratory protection; and internal dose assessments for any actual internal exposure. Special Dosimetric Situations The inspectors reviewed: Exelon's worker notification of the risks of radiation exposure to the embryo/fetus; the dosimetry monitoring program for declared pregnant workers; external dose monitoring of workers in large dose rate gradient environments; and dose assessments performed since the last inspection that used skin dose or neutron dose assessments. Problem Identification and Resolution The inspectors evaluated whether problems associated with occupational dose assessment were identified at an appropriate threshold and properly addressed in the CAP.

b. Findings

No findings were identified.

4OA1 Performance Indicator Verification

.1 Mitigating System Performance Index (MSPI) (12 samples)

a. Inspection Scope

The inspectors reviewed Exelon's submittal of the MSPI for the following systems for the period of July 1, 2016, through September 30, 2017: Unit 2 and Unit 3 MSPI - Safety System Functional Failures (MS05) Unit 2 and Unit 3 MSPI - Emergency AC Power Systems (MS06) Unit 2 and Unit 3 MSPI - HPCI Systems (MS07) Unit 2 and Unit 3 MSPI - RCIC Systems(MS08) Unit 2 and Unit 3 MSPI - RHR Systems (MS09) Unit 2 and Unit 3 MSPI - Cooling Water Systems (MS10) To determine the accuracy of the performance indicator (PI) data reported during those periods, the inspectors used definitions and guidance contained in Nuclear Energy Institute (NEI) Document 99-02, "Regulatory Assessment PI Guideline," Revision 7. The inspectors also reviewed Exelon's operator narrative logs, CRs, MSPI derivation reports, 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 Exelon's submittals for the occupational radiological occurrences PI for the period of October 1, 2016 through September 30, 2017. The inspectors used PI definitions and guidance contained in NEI 99-02, Revision 7, to determine the accuracy of the PI data reported. The inspectors reviewed 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 and very 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 TSs/Offsite Dose Calculation Manual (ODCM) Radiological Effluent

Occurrences (1 sample)

a. Inspection Scope

The inspectors reviewed licensee submittals for the radiological effluent TS/ODCM radiological effluent occurrences for PI for the period of October 1, 2016 through September 30, 2017. The inspectors used PI definitions and guidance contained in NEI 99-02, Revision 7, to determine if the PI data was reported properly. The inspectors reviewed the public dose assessments for the PI for 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.

4OA2 Problem Identification and Resolution

.1 Routine Review of Problem Identification and Resolution Activities

a. Inspection Scope

As required by Inspection Procedure (IP) 71152, "Problem Identification and Resolution," the inspectors routinely reviewed issues during baseline inspection activities and plant status reviews to verify that Exelon entered issues into the CAP at an appropriate threshold, gave adequate attention to timely CAs, 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 IR screening meetings. The inspectors also confirmed, on a sampling basis, that, as applicable, for identified defects and non-conformances, Exelon performed an evaluation in accordance with 10 CFR Part 21.

b. Findings

No findings were identified.

.2 Annual Sample: Validation of Emergency Pump Structure Flood Protection

a. Inspection Scope

The inspectors performed an in-depth review of Exelon's evaluation and CAs related to validating Exelon's emergency pump structure was adequately protected from an external flood as documented in IRs 2708422 and 2711402. Specifically, the NRC had identified several vulnerabilities related to structure in-leakage, bypassing flood barriers, and the testing of credited sump pumps.

The inspectors assessed Exelon's implemented and planned CAs to evaluate whether Exelon staff appropriately identified, characterized, prioritized, and corrected problems associated with this issue. The inspectors compared the actions taken to the requirements in Exelon procedure PI-AA-125, "CAP Procedure," and the PB Fire Protection Program. The inspectors also reviewed associated documents, conducted interviews with station personnel, and completed field walkdowns to gain an understanding of the implemented and planned CAs associated with this issue.

b. Findings and Observations

No findings were identified. On August 25, 2016, the NRC identified a potential flood flow path from outside the emergency pump structure via an open 2-inch vent line through the diesel driven fire pump storage tank overfill line and out the flame arrestor located within the emergency pump structure. The vent opening was located below the external flood level found in PB special event procedure, SE-4, "Flood," Revision 42. Exelon generated IR 2708422 and implemented CAs to appropriately cap the vent line, revise SE-4 to provide additional guidance, and calculate the in-leakage of the bypass during the maximum external flood and verify the in-leakage would not exceed the sump pump removal capacity, As a result of additional questions from the IR 2708422 review, Exelon's senior leadership team at PB met on August 31, 2016, to develop an action plan to ensure adequate flood protection features existed for the emergency pump structure. IR 2711402 was generated and specified several CAs to be completed. Exelon performed a holistic review of the emergency pump structure by performing a reassessment of post-Fukushima inspections, including walking down penetrations, inspecting seals, and reviewing all systems that interacted with the pump structure to determine if any additional flood vulnerabilities existed, similar to the one identified in IR 2708422. Exelon also performed a review of its programmatic controls to ensure routine maintenance did not inadvertently disable flood protection features without proper controls. Furthermore, Exelon determined the design basis in-leakage of the pump structure and revalidated the sump pump removal capacity. The inspectors reviewed Exelon's holistic review of the emergency pump structure external flooding revalidation as well as the CAs performed. The inspectors independently walked down the pump structure and reviewed a sampling of Exelon's seal inspections. Finally, the inspectors reviewed the calculation of in-leakage for the pump structure, the test performed of the sump pump capacity, and verified that the equipment within the structure would remain operable during a design basis external flood. The inspectors found that Exelon's CAs were sufficient for the identified deficiencies.

.3 Semi-Annual Trend Review

a. Inspection Scope

The inspectors performed a semi-annual review of site issues to identify trends that might indicate the existence of more significant safety issues. As part of this review, the inspectors included as appropriate, repetitive or closely related issues documented by Exelon in trend reports, site PIs, major equipment problem lists, system health reports, MR assessments, and maintenance or CAP backlogs. The inspectors also reviewed Exelon's CAP database for the third and fourth quarters of 2017 to assess CRs written in various subject areas (equipment problems, human performance issues, etc.), as well as individual issues identified during the NRC's daily CR review (Section 4OA2.1). The inspectors reviewed Exelon's quarterly trend report for the third and fourth quarters of 2017 in the departments of operations, engineering, and maintenance to verify Exelon personnel were appropriately evaluating and trending adverse conditions in accordance with applicable procedures.

b. Findings and Observations

No findings were identified. The inspectors evaluated a sample of issues and events that occurred over the course of the third and fourth quarters of 2017 to determine whether issues were appropriately considered as emerging or adverse trends. The inspectors verified that these issues were addressed within the scope of the CAP or through department review. The evaluation did not reveal any new trends that could indicate a more significant safety issue. The inspectors assessed that Exelon personnel were identifying trend issues at a low threshold and entering them into the CAP for resolution and were appropriately prioritizing investigation reviews. The inspectors noted minor adverse trends identified by Exelon staff in the areas of CA process implementation (04040983), thermal overload failures (04030605, 04034958), supplemental workforce performance gaps (04062291), and issues associated with operator medical requirements (04065158). There were no adverse safety consequences as a result of these low-level trend issues. Based on the overall results of the semi-annual trend review, the inspectors determined that Exelon was properly identifying adverse trends at Peach Bottom before they became more significant safety problems. The inspectors independently evaluated the deficiencies noted above for significance in accordance with the guidance in Inspection Manual Chapter (IMC) 0612, Appendix B, "Issue Screening," and Appendix E, "Examples of Minor Issues." The inspectors determined these conditions were deficiencies of minor significance and, therefore, are not subject to enforcement action in accordance with the NRC's Enforcement Policy.

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

(Closed) Licensee Event Report (LER) 05000278/2017-001-00: Reactor Pressure Boundary Leakage Due to Weld Failure in 1-inch Diameter Instrument Line

a. Inspection Scope

On October 23, 2017, during initial walkdown of the containment at the start of the Unit 3 RFO, a leak was identified in a socket weld for a 1-inch diameter pressure transmitter instrument line. The line is connected to discharge piping for the 'B' recirculation pump and is part of the ASME Class 1 primary coolant system pressure boundary. Because the leak was misting, the leakage rate could not be quantified. The apparent cause evaluation (ACE) determined that cause of the crack in the instrument line weld was caused by lack of fusion defects on the inside diameter of the fitting and propagated by normal vibration of the pipe. The affected section of the pipes and fitting were replaced by new pipe and fitting and replaced with a new socket weld with a 2x1-weld profile, which reduces susceptibility to vibration-induced failures. The LER and associated evaluations and follow-up actions were reviewed for accuracy, the appropriateness of CAs, violations of requirements and potential generic issues. This LER is closed.

b. Findings

Description.

On October 23, 2017, during initial walkdown of the containment at the start of the Unit 3 RFO, a leak was identified in a socket weld for a 1-inch diameter pressure transmitter instrument line. The line is connected to discharge piping for the 'B' recirculation pump and is part of the ASME Class 1 primary coolant system pressure boundary. Because the leak was misting, the leakage rate could not be quantified. Additionally, Exelon determined that this leakage constituted a violation of the Unit 3, TS 3.4.4, "RCS Operational Leakage," that requires that there be no pressure boundary leakage. The condition was reported in event notification 53031, as required by 10 CFR 50.72(b)(3)(ii)(A), because it represented a degradation of a principal safety barrier. Exelon evaluated the flaw and determined the cause of the RCS pressure boundary leakage was that a crack developed in the weld material of an instrument line socket weld which was caused by lack of fusion defects on the inside diameter of the welded fitting and propagated by normal vibrations of the piping. The inspectors reviewed the LER and Exelon's ACE of the event. The inspectors reviewed the event information and leakage data over the previous cycle and concluded that reactor pressure boundary leakage reasonably began on an unknown date before October 23, 2017, during the operating cycle but more than 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> prior to the October 23, 2017, shutdown. However, the inspectors determined that the existence of RCS pressure boundary leakage was not within Exelon's ability to foresee and correct and, therefore, was not a performance deficiency (PD). Specifically, the 1-inch socket welds in the recirculation system instrument lines are exempt from periodic examination as described in ASME Section XI Section IWB-1220, "Components Exempt from Examination." The inspectors screened the significance of the condition using IMC 0609, Appendix A, "The Significance Determination Process For Findings At-Power," and determined that the condition represented very low safety significance (Green), because it would not result in exceeding the RCS leak rate for a small LOCA and would not have likely affected other systems used to mitigate a LOCA.

Enforcement.

TS 3.4.4.a requires, in part, that RCS operational leakage shall be limited to no pressure boundary leakage. If pressure boundary leakage exists, the TS 3.4.4.C limiting condition for operation action statement requires Unit 3 to be in at least hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Contrary to the above, for a period that began on an unknown date that was very likely more than 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> before October 23 2017, and ending on October 23, 2017, RCS pressure boundary leakage existed, and Exelon did not place Unit 3 in at least hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

This issue is considered within the traditional enforcement process because there was no PD associated with the violation of NRC requirements. IMC 0612, "Power Reactor Inspection Reports," Section 03.22 states, in part, that traditional enforcement is used to disposition violations receiving enforcement discretion or violations without a PD. The NRC Enforcement Policy, Section 2.2.1 states, in part, that, whenever possible, the NRC uses risk information in assessing the safety significance of violations. Accordingly, after considering that the condition represented very low safety significance, the inspectors concluded that the violation would be best characterized as Severity Level IV under the traditional enforcement process. However, the NRC is exercising enforcement discretion (EA-17-207) in accordance with Section 3.10 of the NRC Enforcement Policy, which states that the NRC may exercise discretion for violations of NRC requirements by reactor licensees for which there are no associated PD. In reaching this decision, the NRC determined that the issue was not within the licensee's ability to foresee and correct; the licensee's actions did not contribute to the degraded condition; and the actions taken were reasonable to identify and address the condition. Furthermore, because the licensee's actions did not contribute to this violation, it will not be considered in the assessment process or the NRC's action matrix.

4OA6 Meetings, Including Exit

On January 12, 2018, the inspectors presented the inspection results to Matthew Herr, Plant Manager, and other members of Exelon's staff. The inspectors verified that no proprietary information was retained by the inspectors or documented in this report.

ATTACHMENT:

SUPPLEMENTARY INFORMATION

KEY POINTS OF CONTACT

Exelon Generation Personnel

P. Navin, Site Vice President

M. Herr, Plant Manager

N. Alexakos, Emergency Preparedness Manager

J. Armstrong, Regulatory Assurance Manager

D. Baracco, Radiation Protection Manager

J. Bullen, GE UT Level II

C. Crabtree, Chemistry Groundwater Engineer

D. Dullum, Regulatory Assurance Engineer

S. Griffith, Manager Site Security

G. Gustofson, Exelon NDE Supervisor

J. Hawkins, Exelon NDE Supervisor

D. Henry, Operations Director

S. Hess, Engineering Director

B. Holmes, Radiation Protection Manager

D. Hornberger, Chemistry/Radwaste

P. Kester, Senior Design Engineer

B. Miller, Fire Protection Engineer

M. Rector, Engineering Response Team Manager

M. Retzer, Senior Manager Systems Engineering

R. Ridge, Health Physicist

R. Riley, Radwaste Shipper

Z. Setzer, GE PT Level II

J. Stenclik, Chemistry Supervisor

M. Weidman, Work Management Director

T. Wickle, Senior Design Manager

LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED

Closed

05000278/LER-2017-001-00 LER Reactor Pressure Boundary Leakage Due to Weld Failure in 1-inch Diameter Instrument Line (Section 4OA3)

LIST OF DOCUMENTS REVIEWED

• -- Indicates NRC-identified

Section 1R01: Adverse Weather Protection

Procedures

WC-AA-107, Seasonal Readiness, Revision 18

Section 1R04: Equipment Alignment

Procedures

SO 10.1.B-2, RHR System Shutdown Cooling Mode Manual Start, Revision 51ST-O-023-300-3, HPCI Pump, Valve, Flow and Unit Cooler Functional and IST Without Vibration Data Collection, Revision 12

Drawings

6280-M-361, Sheet 4, RHR System, Revision 74

DBN-23-MI-203-7, Sheet 0001, HPCI 23DBN-10IN from

MO-16 to Turbine Stop Valve, Revision 1 M-1-S-36, Sheet 06, Elementary Diagram HPCI System, Revision 76

IRs

4058653

4060179

Miscellaneous

BWROG-TP-14-016, HPCI Steam Admission Valve Leakage, Revision 0

Section 1R05: Fire Protection

Procedures

CC-AA-211, Fire Protection Program, Revision 8

RT-O-037-351-2, Transient Combustibles Inspection

PF-13C, Unit 3 RX BLDG Torus Room, Revision 5

PF-32, Unit 3 RX BLDG Drywell Area, Revision 6

PF-55, Unit 3 RX BLDG Refuel Floor - Elevation 234'0, Revision 5

PF-57, Unit 2 RX BLDG Refuel Floor - Elevation 234'0, Revision 6

IRs *4068725

Section 1R08: In-Service Inspection

Procedures

ER-AA-330-009, ASME Section XI Repair/Replacement Program, Revision 13

ER-AA-330-009, ASME Section XI Repair/Replacement Program, Revision 13

ER-AA-335-001, Qualification and Certification of NDE Personnel, Revision 10

ER-AA-335-002, PT Examination, Revision 9

ER-AA-335-003, MT Examination, Revision 8

ER-AA-335-003, UT Measurement of Material Thickness and Interfering Conditions, Revision 7GEH-PDI-UT-1, PDI Generic Procedure for the Ultrasonic Examination of Ferritic Welds, Version 11

GEH-PDI-UT-2, PDI Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds, Revision 11

GEH-VT-204, Procedure for In-vessel Visual Inspection (IVVI) of BWR 4 RPV Internals, Revision 17 M-065-005, Mechanical Snubber Testing on Model 100/150 Snubber Test Machine, Revision 10 M-065-014, Hydraulic Snubber Performance Testing, Revision 15

MA-PB-793-001, Visual Examination of Containment Vessels and Internals, Revision 3

Drawings

6280-ISI-354, Sheet 2, ASME Section XI ISI Boundaries, RWCU System, Revision 8 6280-M-353, Sheet 4, Reactor Recirculation Pump System, Revision 59

DCA-10-MI-303-9-B, Sheet 1,

RHR 10DCA-24" from MO25B to 28" Recirculation Pump Discharge, Revision 1

DE-12-MI-303-6, Sheet 1, RWCU Return from Regen HX to Valve

MO-68, Revision 2ISI-203-RV-04, Sheet 1, ISI Component Drawing RPV Details, Revision 0 M-100-J-12-128-4, Sheet 1,

ISO-3-12-113, Revision 6 M-296, Sheet 63, Critical Small Piping Isometrics Inside Drywell #3, Revision 7 M-296, Sheet 74, Critical Small Piping Isometrics Inside Drywell #3, Revision 6

WOs

4705157

4705244

4702689

4596010

4705157

4705244

CRs 2560404

2561005

2561844

4065691

4068143

4070332

2569613

4070216

4067473

4069476

4068703

4068776

4068789

4068795

4068937

4068946

4069248

4069249

4069251

4069252

Miscellaneous

0249070-12, OPEX Evaluation: NRC

IN 2015-04, Fatigue in Branch Connection Welds, dated June 25, 2015 386HA480, GE Hitachi Nuclear Entergy Written Practice, Certification of NDE Testing Personnel, Revision 27

BOP-PT-17-033, Liquid Penetrant Examination of Existing Tee/Pipe (Existing Leak Detected),

RTV-3-02A-5449B, dated October 24, 2017

BOP-PT-17-054, Liquid Penetrant Examination of 1 inch Pipe/Fitting,

RTV-3-02A-5449B/Root Valve 3BP034, dated November 2, 2017

BOP-PT-17-059, Penetrant Test Record for

RTV-3-02-5A/W23, dated November 2, 2017

BOP-PT-17-060, Penetrant Test Record for

RTV-3-02A-5449A/W2, dated November 2, 2017

BOP-PT-17-061, Liquid Penetrant Examination of Elbow End Preps for Welds 12-13-12 and 12-13-13, dated November 2, 2017

BOP-PT-17-062, Liquid Penetrant Examination of Pipe/Fitting, W22 Final Valve to Pipe (HV-3-02A-5A/W-22), dated November 2, 2017

BOP-PT-17-063, Liquid Penetrant Examination of Pipe/Fitting, W1 Final Valve to Pipe (RTV-3-02A-5449A/W-1), dated November 2, 2017

BOP-PT-17-064, Liquid Penetrant Examination of 4-inch Existing Pipe for Weld 12-13-12, dated November 3, 2017

BOP-PT-17-065, Liquid Penetrant Examination of 4-inch Existing Pipe for Weld 12-13-13, dated November 3, 2017

BOP-PT-17-066, Liquid Penetrant Examination of 4-inch Existing Pipe for New 4 inch Elbow, Pup Piece End Preps for W12-13-12 & 12-13-13, dated November 3, 2017

BOP-PT-17-072, Liquid Penetrant Examination of Pipe (New)/4 inch Elbow (New), Final Weld 12-13-12, dated November 4, 2017

BOP-PT-17-073, Liquid Penetrant Examination of 4-inch RWCU Pipe Replacement, dated November 24, 2017

BOP-PT-17-076, Liquid Penetrant Examination of Welds 12-13-13 Pipe to Elbow and 12-13-11A Pipe to Pipe, dated November 4, 2017

EN 53031, Leakage Identified on 1-inch Line Socket Weld for the 'B' Recirculation Pump, dated October 23, 2017

EPRI Performance Demonstration Initiative Program PDI Generic Procedure (PDI-UT-1) for the Ultrasonic Examination of Ferritic Pipe Welds for Examiner 336, dated February 13, 2013 EPRI Performance Demonstration Initiative Program PDI Generic Procedure (PDI-UT-2) for the Ultrasonic Examination of Austenitic Steel Pipe Welds for Examiner 336, dated February 13, 2013 EPRI Performance Demonstration Initiative Program PDI Generic Procedure (PDI-UT-3) for the Ultrasonic through Wall Sizing in Pipe Welds for Examiner 336, dated February 13, 2013 EPRI Performance Demonstration Initiative Program PDI Generic Procedure (PDI-UT-1) for the Ultrasonic Examination of Ferritic Pipe Welds for Examiner 554, dated February 13, 2013 EPRI Performance Demonstration Initiative Program PDI Generic Procedure (PDI-UT-10) for the Ultrasonic Examination of Dissimilar Metal Welds for Examiner 554, dated February 13, 2013 EPRI Performance Demonstration Initiative Program PDI Generic Procedure (PDI-UT-2) for the Ultrasonic Examination of Austenitic Steel Pipe Welds for Examiner 554, dated February 13, 2013 Exelon Letter, Submittal of the ISI Owner's Activity Report OAR) for the 20th Refueling Outage for Unit 3, dated January 20, 2016 GE Hitachi Certificate of Qualification for Certification Number 0638, dated October 23, 2017 GE Hitachi Certificate of Qualification for Certification Number 0735, dated September 27, 2017 GE Hitachi Certificate of Qualification for Certification Number 2138, dated September 27, 2017 GE Hitachi Certificate of Qualification for Certification Number 1995, dated January 23, 2017 GE Hitachi Certificate of Qualification for Certification Number 2053, dated March 29, 2017 GE Hitachi Certificate of Qualification for Certification Number 1829, dated August 12, 2016 GE Hitachi Certificate of Vision Acuity Record for Certification Number 0638, dated October 16, 2017 GE Hitachi Certificate of Vision Acuity Record for Certification Number 0735, dated February 13, 2017 GE Hitachi Certificate of Vision Acuity Record for Certification Number 2138, dated January 19, 2017 GE Hitachi Certificate of Vision Acuity Record for Certification Number 1995, dated January 20, 2017 GE Hitachi Certificate of Vision Acuity Record for Certification Number 2053, dated November 18, 2016 GE Hitachi Certificate of Vision Acuity Record for Certification Number 1829, dated October 19, 20167 GE Nuclear Examination Summary Sheet 10-IB-19 Pipe Bend to Elbow, dated October 6, 2017 GEH Certificate of Qualification for Examiner 0227, LIII

VT-1,

VT-3 limited to IVVI, dated September 27, 2017 GEH Certificate of Qualification for Examiner 0502, LIII

VT-1,

VT-3 limited to IVVI, dated September 27, 2017 GEH Certificate of Qualification for Examiner 1624, LIII

VT-1,

VT-3 limited to IVVI, dated September 27, 2017 GEH Visual Acuity Record for Examiner 0227, dated August 28, 2017 GEH Visual Acuity Record for Examiner 0502, dated January 12, 2017 GEH Visual Acuity Record for Examiner 1624, dated August 23, 2017

GL 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, dated

January 25, 1988

GL 88-01, Supplement 1, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, dated February 4, 1992

IN 5-04, Fatigue in Branch Connection Welds, dated April 24, 2015

IN 95-16, Vibration Caused by Increased Recirculation Flow in a Boiling Water Reactor, dated March 9, 1995 INR PB3R21, IVVI 17-02-R2, Jet Pump 11-20

WD-1 and Rod Wear Loop A, dated November 1, 2017 INR PB3R21, IVVI 17-04, Steam Dryer Support Shims, dated October 27, 2017 INR PB3R21, IVVI 17-09, CS Sparger Bracket 05 at 136 degrees, dated October 29, 2017 INR PB3R21, IVVI 17-10, Feedwater End Bracket at 355 degrees, dated October 29, 2017

MT-17-012, Magnetic Particle Examination of N3 Reinforcing Plate (N3 (RP)-A), dated October 29, 2017

MT-17-013, Magnetic Particle Examination of Welded Attachment

RHRHX-A-LS(IA), dated October 29, 2017 PBT05.G03, PB Units 2&3 ISI Program Plan Fourth Ten-Year Inspection Interval, Revision 5 PECO Energy letter, PB, Units 2 and 3,

GL 88-01, Supplement 1, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping," dated May 24, 1995 Philadelphia Electric Company letter, Response to NRC

GL 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping" for PB, dated August 2, 1988

RIS 2010-06, NRC Regulatory Issue Summary 2010-06 ISI and Testing Requirements of Dynamic Restraints (Snubbers), dated June 1, 2010 RT Report for Weld 12-13-11A, dated November 3, 2017 RT Report for Weld 12-13-12, dated November 3, 2017 RT Report for Weld 12-13-13, dated November 3, 2017 USNRC letter, RWCU System Weld Inspections at PB, Units 2 and 3 (TAC NOS. M92442 and M92443), dated September 15, 1995 USNRC letter, Response to

GL 88-01 (TAC NOS. 69150 and 69151), RE: PB, Units 2 and 3, dated March 27, 1990

UT-17-052, Pipe to Elbow for Weld 12-14-13, dated November 1, 2017

UT-17-054, Pipe to Elbow for Weld 12-14-12, dated November 1, 2017

UT-17-055, Pipe to Elbow for Weld 12-13-12 Sizing Data, dated October 31, 2017

UT-17-056, Pipe to Elbow for Weld 12-13-13, dated October 30, 2017

UT-17-057, Pipe to Elbow for Weld 12-13-12, dated October 30, 2017 Vendor Personnel NDE Certification Review Attribute List for GE Certification Number 0638, dated October 21, 2017 Vendor Personnel NDE Certification Review Attribute List for GE Certification Number 0735, dated October 11, 2017 Vendor Personnel NDE Certification Review Attribute List for GE Certification Number 2138, dated October 21, 2017

VT-17-065, Visual Examination of Pipe Hanger, Support or Restraint (VT-3) for RPV Stab Bar at 270 Degrees, dated October 27, 2017

VT-17-066, Visual Examination of Pipe Hanger, Support or Restraint (VT-3) for RPV Stab Bar at 315 Degrees, dated October 27, 2017 Welder Information Data Sheet for

WO 4705157,

HV-3-02-5A, dated October 29, 2017 Welder Information Data Sheet for

WO 4705157,

HV-3-02A-5449A, dated October 29, 2017

Section 1R11: Licensed Operator Requalification Program

Procedures

GP-3-3, Normal Plant Shutdown, Revision 8

Section 1R12: Maintenance Effectiveness

Procedures

ER-AA-310-1005, MR - Dispositioning Between A1 and A2, Revision 7

IRs

1118530

2563769

4068120

4077304

4078626

4078978 *4079492 *4079500

4082286

Miscellaneous

10

CFR 50.65 (a)(3), Periodic Assessment of MR Program, PB, Units 2 and 3, dated April 2015 through March 2017 MR System Basis Document Function 4-1-1 dated November 28, 2017 Plant Manager Debriefs dated December 15, 2017 Expert Panel Meeting Agenda

Section 1R13: Maintenance Risk Assessments and Emergent Work Control

Procedures

WC-AA-101-1006, On-line Risk Management and Assessment, Revision 2

Miscellaneous

Loss of Off-site Power "What If" Schedule dated October 2017 Loss of Secondary Containment "What If" Schedule dated October 2017 Operation with a Potential for Draining the Reactor Vessel "What If Schedule" dated October 2017 Outage Configurations dated October 2017 Outage Integrated Assessments P3R21 Decay Heat Curve P3R21 Decay Heat Removal P3R21 Inventory Control P3R21 Paragon Shutdown Safety Overview P3R21 Shutdown Safety Profile Time to Boil - RPV Time to Boil - Fuel Pool Unit 3 Shutdown Safety Review dated October 22, 2017

1R15: Operability Determinations and Functionality Assessments

Procedures

IC-11-00342, Alignment and Tuning of Woodward Governor Controls for EDGs, Revision 11

OP-AA-102-105-1001, PB Priority Work List

ST-O-023-300-3, HPCI Pump, Valve, Flow and Unit Cooler Functional and IST Without Vibration Data Collection, Revision 12

ST-O-052-213-2, E-3 Diesel Generator Slow Start Full Load and IST Test, Revision 24

ST-O-052-703-2, E-3 Diesel Generator 24 Hour Endurance Test, Revision 22

ARs

0966085

1508893

Drawings

6280-M-365, HPCI System, Revision 63 6280-M-366, HPCI Pump Turbine Details, Revision 57

IRs

0075403

2444679

3995230

4000453

4000578

4033575

4050431

4053424

4053452

4053511

4054022

4055985

4064414

4064440

4065552

4068914

4074369

WO 4706129

WR 1369477

Miscellaneous

DNA History Plot PEA MRC Agenda for Wednesday, October 4, 2017 Unit 3 HPCI ACMP

Section 1R18: Plant Modifications

Procedures

LS-AA-104-1001, 50.59 Review Coversheet, Revision 4

LS-AA-104-1003, 50.59 Screening Form, Revision 4

LS-AA-104-1004, 50.59 Evaluation Form, Revision 6

RT-O-01D-421-3, Main Turbine Overspeed Test, Revision 04

WO 04596806

IRs

4066216

4066479

4068050

4068060

4068074

4068091

4069936

4070268

4070610

4071256

4072188

4072189

4072190

4072694

Miscellaneous

EC 556341 Unit 3 Digital Feedwater Level and Speed Control Replacement

EC 556054, Unit 3 - Digital Electro-hydraulic Control, Revision 02

ECR 15-00170, PB Unit 3 DEHC Parent ECR

ECR 15-00171, PB Unit 3 DEHC Pre-Outage Installation Work

Section 1R19: Post-Maintenance Testing

Procedures

ER-AA-302-1006, Motor-Operated Valve Maintenance and Testing Guidelines, Revision 15

MA-AA-716-012, PMT, Revision 23 SI3K-54-E13-XXC4, Calibration Check of E-13 4kV Bus Undervoltage and Sequential Loading Relays, Revision 0

ST-O-013-200-3, RCIC Flow Rate at Less Than or Equal to 175 PSIG, Revision 18

ST-O-013-301-3, RCIC Pump, Valve, Flow and Unit Cooler Functional and IST withVibration Data Collection, Revision 49

ST-O-023-200-3, HPCI Flow Rate at Less Than or Equal to 175 PSIG Steam Pressure, Revision 19

IRs

4065554

4068070

4068123

4068666

4068908

4069927

4070531

4071246

4072133

4072432

WOs

2844920

4175009 4252258

Section 1R20: Refueling and Outage Activities

Procedures

GP-3-3, Normal Plant Shutdown, Revision 8

LS-AA-119, Fatigue Management and Work Hour Limits, Revision 12

IRs

4067104

4068051

4071076

Drawings

6280-9-7863, Drywell Penetrations, Revision 3 6280-C2-29-13, Drywell Shell Stretchout, Revision 10 6280-C2-87-4, Drywell Penetrations, Revision 2 6280, S-52, Containment Vessels - Requirements Drywell - Penetrations, Revision 26

Section 1R22: Surveillance Testing

Procedures

ST-O-011-400-3, Standby Liquid Control System 'A' LOOP Injection Test, Revision 10

ST-O-054-753-3, E-33 4Kv Bus Undervoltage Relays and LOCA/LOOP Functional Test, Revision 26 ST/LLRT 30.01A.02, MSIV LLRT, Revision 15 ST/LLRT 30.14.01, LLRT CS 'A' LOOP, Revision 15 ST/LLRT 30.14.01, LLRT CS 'A' LOOP, Revision 15A

IRs

4067087

4067092

Miscellaneous

LLRT Work Schedule

PEA-Outage Master P3R21

Section 1EP4: Emergency Action Level and Emergency Plan Changes

Miscellaneous

EP-AA-1007, Addendum 3 EALs for PB, Revision 5

EP-AA-1007, Radiological EP Annex for PB, Revision 32

Section 2RS01:

Radiological Hazard Assessment and Exposure Controls

Procedures

RP-AA-300, Radiological Survey Program, Revision 15

RP-AA-301, Radiological Air Sampling Program, Revision 10

RP-AB-460, Traversing In-Core Probe Area Access/ Radiological Controls, Revision 4

IRs

4064024

4064906

4065677

4065710

4066107

Documents

2017 Contamination Control Self-Assessment,

AR3992174, September 22, 2017 2017 Control of Radioactive Material Self-Assessment,

AR3992171, September 22, 2017 BHI Energy Contractor Training Presentation, "PB Outage Kickoff," October 23, 2017 LHRA Key Logs,

RP-11-460, Attachment 10, October 24, 2017

RP-AA-301, Attachment Multiple Air Sample Sheet for Drywell, October 25, 2017

RP-AA-4002, PB 3 Radiation Protection Outage Readiness Assessment, October 17, 2017

Section 2RS02:

Occupational As Low As Reasonably Achievable Planning and Control

Procedures

RP-AA-203, Exposure Control and Authorization, Revision 5

RP-AA-400-1003, Work Group Radiological Excellence Plans, Revision 3

RP-AA-400-1004, Emergent Dose Control and Authorization, Revision 9

RP-AA-400-1006, Outage Exposure Estimating and Tracking, Revision 7

RP-AA-402, Radiation Protection Dose Excellence Planning Process, Revision 8

RP-AA-441, Total Effective Dose Equivalent ALARA Evaluation, Revision 7

RP-AA-462, Controls for Radiological Operations, Revision 13

RP-AA-463-1001, Fuel Surveillance Guidance, Revision 3

RP-AA-1015, Control of Drinking Water Stations in Radiologically Controlled Areas, Revision 2

RP-AB-462, Access Controls during Drywell Power Entries, Revision 0

RP-AB-462-100-F-07, Drywell Power Entry Authorization/ Access Controls at PB, Revision 0

RP-PB-552, Shielding Program, Revision 3

Documents

Combined ALARA Plan/ Micro-ALARA Plan,

PB-C-17-00548,17-548, 3 'A' Recirculation Motor Replacement Combined ALARA Plan/ Micro-ALARA Plan,

PB-C-17-510,17-510, Unit 3 DW MSRVS Replacement Combined ALARA Plan/ Micro-ALARA Plan,

PB-C-17-511,17-511, Unit 3 DW Valve Activities Combined ALARA Plan/ Micro-ALARA Plan,

PB-C-17-515,17-515, Unit 3 Shoot Out Steel, Torque CRDs and Tip Tubing Activities Combined ALARA Plan/ Micro-ALARA Plan,

PB-C-17-519,17-519, Unit 3 Drywell Insulation Removals and Installs Combined ALARA Plan/ Micro-ALARA Plan,

PB-C-17-509 17-509, Unit 3 Drywell MSIVs Combined ALARA Plan/ Micro-ALARA Plan,

PB-C-17-512,17-512, Unit 3 Drywell CRDs GEH/ IDEA Machine, Leveling Tray Preps,

VT-2 Exams, and CRD Exchange Combined ALARA Plan/ Micro-ALARA Plan,

PB-C-17-511,17-511, Unit 3 Drywell Valve Activities Combined ALARA Plan/ Micro-ALARA Plan,

PB-C-17-506,17-506, Unit 3 Drywell Scaffold with Associated Activities Combined ALARA Plan/ Micro-ALARA Plan,

PB-C-17-901,17-901, Unit 3 Refuel Floor - Disassemble and Reassemble Reactor Shield Blocks, Drywell Head, Mirror Insulation, Head Piping, and Reactor Head

NOSA-PEA-17-06 (AR4014238), PB Radiation Protection Audit Report, July 19, 2017 PB3R21 Daily ALARA Report, October 24, 2017 PB3R21 Flush Plan, October 23, 2017 PB3R21 Radiation Protection Shield Package Plan, October 23, 2017 SASC/ SAC Meeting Minutes, SAC Meeting#17-08, May 30, 2017 SASC/ SAC Meeting Minutes, SAC Meeting#17-10, August 15, 2017 SASC/ SAC Meeting Minutes, SAC Meeting#17-14, August 25, 2017

SASC/ SAC Meeting Minutes, SAC Meeting#17-15, August 29, 2017 SASC/ SAC Meeting Minutes, SAC Meeting#17-16, September 15, 2017 Station ALARA Committee Meeting Minutes, October 25, 2017

TSP-021-17, Temporary Shielding Permit

WO 429759602/03, Unit 3 DW, October 24, 2017

Section 2RS03:

In-plant Airborne Radioactivity Control and Mitigation

Procedures

RP-AA-224, Committed Effective Dose Equivalent Dose Tracking Using Lapel Air Samplers, Revision 2

RP-AA-441, Total Effective Dose Equivalent ALARA Evaluation, Revision 7

RP-AA-444, Controlled Negative Pressure Fit Testing, Revision 7

RP-AA-825-1011, Inspection and Use of the Mururoa V4 F1 R Air Supplied Suit, Revision 3

RP-AA-825-1014, Operation and Operation of the 3M Versaflo

TR-300 PAPR System, Revision 4

RP-AA-825-1014-F-02, Use of the 3M M-100 Series Versaflo Faceshield, Revision 1

RP-AA-825-1014-F-09, Use of the 3M V-100 Series Versaflo Air Regulators with L-905 SG Weld Helmet, Revision 0

RP-AA-825-1014-F-10, Use of the 3M V-100 Series Versaflo Air Regulators with M-407 Hood, Revision 0

RP-AA-825-1014-F-11, Use of the 3M V-100 Series Versaflo Air Regulators with S-807 Hood, Revision 0

RP-AA-870-1001, Set-up and Operation of Portable Air Filtration Equipment, Revision 7

RP-AA-870-1002, Use of Vacuum Cleaners in Radiological Controlled Areas, Revision 8

RP-AA-870-1003, Testing Portable HEPA Filter Units, Revision 5

RP-PB-445, Controlled Negative Pressure Fit Testing, Revision 3

CRs 04023622

4017820

Miscellaneous

2017 Respiratory Protection Self-Assessment,

AR03954853, September 22, 2017

RP-AA-441 Attachment 3 - TEDE ALARA Evaluation, RWP

PBC-C16-509, Unit 3 Drywell 135', MSIV In-body Value Work.2 RAD, October 19, 2017

RP-AA-441 Attachment 3 - TEDE ALARA Evaluation, RWP

PBC-C17-512, Unit 3 Drywell CRD Activities Torque/ Detorque GEH/IDEA Machine, Level Tray Preps, September 13, 2017

RP-AA-441 Attachment 3 - TEDE ALARA Evaluation, RWP

PBC-C17-515, Unit 3 Drywell Shoot Out Steel and Associated Work to Include Tip Tubing Activities(500K - Wet/Misting), September 13, 2017

RP-AA-441 Attachment 3 - TEDE ALARA Evaluation, RWP

PBC-C17-901, Unit 3 US FF (P3R21) Rx Disassembly/ Reassembly, April 14, 2017

RP-AA-441 Attachment 3 - TEDE ALARA Evaluation, RWP

PBC-C17-548, Unit 3 Drywell Recirc Seal Activities (50K), September 18, 2017

RP-AA-441 Attachment 3 - TEDE ALARA Evaluation, RWP

PBC-C17-548, Unit 3 Drywell Recirc Seal Activities (50K dry), September 18, 2017

RP-AA-441 Attachment 3 - TEDE ALARA Evaluation, RWP

PBC-C16-510 Unit 3 Drywell Main Steam Relief Valve Activities, September 13, 2017

Section 2RS04:

Occupational Dose Assessment

Procedures

RP-AA-210, Dosimetry Issue, Usage and Control, Revision 27

RP-AA-210-1004, Shallow Dose Equivalent Program Review, Revision 0

RP-AA-211, Personnel Dosimetry Performance Verification, Revision 13

RP-AA-232-1001, Calibration Verification of Whole Body Counting Systems Using APEX In-vivo, Revision 1

RP-AA-233, Quality Control Operations for Canberra Whole Body Counters Using APEX In-vivo, Revision 0

RP-AA-250, External Dose Assessments from Contamination, Revision 7

RP-AA-270, Prenatal Radiation Exposure, Revision 8

RP-AA-280, Occupational Exposure Reporting, Revision 10

RP-AA-350, Personnel Contamination Monitoring, Decontamination and Reporting, Revision 18

CAs

2737459

2737616

3981040

4045649

4059740

Miscellaneous

APEX-InVivo QA Full Parameters Report, Fastscan Lower Calibration Check,

QA 1103167QA

5101313, October 23, 2017

APEX-InVivo QA Full Parameters Report, Accuscan II Summed Calibration Check,

QA 1103167QA

5101313, October 23, 2017

APEX-InVivo QA Full Parameters Report, Fastscan Lower Background Check,

October 23, 2017

APEX-InVivo QA Full Parameters Report, Accuscan II Background Check, October 23, 2017 NVLAP Certificate of Accreditation to ISO/IEC 17025:2005; NVLAP Lab Code 100518-0

PEA-12-002, ARGOS Whole Body Monitor Passive Monitor Study (No Gamma Detectors) at PB, November 15, 2012

RP-AA-232 Attachment 1, Fastscan "Sample" Whole Body Count Log, October 23, 2017

RP-AA-232 Attachment 1, Accuscan "Sample" Whole Body Count Log, October 23, 2017

RP-AA-270 Attachment 3, Declaration of Pregnancy,

EID 026268, October 19, 2017

Section 4OA1: Performance Indicator

Procedures

LS-AA-2001, Collecting and Reporting of NRC PI Data, Revision 14

LS-AA-2150, Monthly Data Elements for RETS/ODCM Radiological Effluent Occurrences, Revision 5

IRs

2733962

2735496

2736932

4011324

4062440

Miscellaneous

Consolidated Data Entry Report PI Value Report for Radiation Exposure Control Effectiveness, for 4th Qtr. 2016, January 11, 2017 Consolidated Data Entry Report PI Value Report for Radiation Exposure Control Effectiveness, for 1st Qtr. 2017, April 12, 2017 Consolidated Data Entry Report PI Value Report for Radiation Exposure Control Effectiveness, for 2nd Qtr. 2017, July 12, 2017 Consolidated Data Entry Report PI Value Report for Radiation Exposure Control Effectiveness, for 3rd Qtr. 2017, October 12, 2017

MSPI Margin - Unit 2 MSPI Margin - Unit 3 PB Dosimetry Report: RWP entries with Individual Daily Dose >50 mrem/day 1st Qtr. 2017, September 15, 2017 PB Dosimetry Report: RWP entries with Individual Daily Dose >50 mrem/day 2nd Qtr. 2017, September 15, 2017 PB Dosimetry Report: RWP entries with Individual Daily Dose >50 mrem/day 3rd Qtr. 2017, September 15, 2017

PB 2016 Annual Radioactive Effluent Release Report, April 28, 2017 Safety System Performance Indicator

ST-C-095-865-2, Data Sheet 1 Total Dose Calculations for 1st Quarter 2017, May 2017

ST-C-095-865-2, Data Sheet 1 Total Dose Calculations for 2nd Quarter 2017, July 2017

ST-C-095-865-2, Data Sheet 1 Total Dose Calculations for 3rd Quarter 2017, October 2017

Section 4OA2: Problem Identification and Resolution

IRs *2666345 *2708422

2711402

4005630

4008467

4009214

4011785

4030605

4034958

4040983

4054804

4056254

4060092

4061791

4062291

4065158

4067382

4067854

4074196

4079390

Procedures

PI-AA-120, Issue Identification and Screening Process, Revision 6

PI-AA-1001, Performance Improvement Integrated Matrix, Revision 3

Miscellaneous

EC 618329, Determination of Discharge Flow Rate of Circ Water Pump Structure Sump Pumps (0AP201 and 0BP201) Engineering Trend Report for the Third and Fourth Quarters 2017 Maintenance Trend Report for the Third and Fourth Quarters 2017 Operations Trend Report for the Third and Fourth Quarters 2017

Section 4OA3: Follow-up of Events and Notices of Enforcement Discretion

IR 4065691

Miscellaneous

Engineering CAP Evaluation

4065691, Steam Leak at Weld Upstream of

RTV-3-02A-5449B at Top of Tee Fitting, dated December 15, 2017 Event Notification 53031, Leakage Identified on 1-inch Line Socket Weld for the B Recirculation Pump, dated October 23, 2017

LER 2017-001-00, Pressure Boundary Leakage Due to Weld Failure in 1-inch Diameter Instrument Line, dated December 21, 2017 PB TS 3.4.4, RCS Operational Leakage, Amendment 214

PEA-62046, Failure Analysis of Socket Weld at Tee Fitting, Ref. CR:

04065691, dated December 13, 2017

LIST OF ACRONYMS

ACE apparent cause evaluation

ALARA as low as reasonably achievable

ASME American Society of Mechanical Engineers

ATWS anticipated transient without scram

CA corrective action

CAP corrective action program

CFR Code of Federal Regulations

CR condition report

CS core spray

EAL emergency action level

EDG emergency diesel generator

EOP emergency operating procedure

EP emergency plan

GL generic letter

HPCI high pressure coolant injection

HPSW high pressure service water

HX heat exchanger

IMC inspection manual chapter

IP inspection procedure

IR issue report

ISI in-service inspection

IST in-service test

LER licensee event report

LLRT local leak rate testing

LOCA loss-of-coolant accident

MR maintenance rule

MSIV main steam isolation valve

MSPI mitigating system performance index

MT magnetic particle testing

NDE non-destructive examination

NEI Nuclear Energy Institute

NRC Nuclear Regulatory Commission

OD operability determinations

ODCM offsite dose calculation manual

OOS out of service

PARS publicly available records

PB Peach Bottom Atomic Power Station

PD performance deficiency

PI performance indicator

PMT post-maintenance testing

PT dye penetrant testing

RCIC reactor core isolation cooling

RCS reactor coolant system

RFO refueling outage

RG regulatory guide

RHR residual heat removal

RPV reactor pressure vessel

RTP rated thermal power

RWCU reactor water cleanup

RWP Radiation work permit

SSC structure, system, and component

ST surveillance test

TS technical specification

UFSAR Updated Final Safety Analysis Report

UT ultrasonic testing

VT visual testing WOs work orders