IR 05000277/2014003
| ML14219A599 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/07/2014 |
| From: | Bower F L Reactor Projects Region 1 Branch 4 |
| To: | Pacilio M J Exelon Generation Co |
| Bower F L | |
| References | |
| IR-14-003 | |
| Download: ML14219A599 (30) | |
Text
August 7, 2014 Mr. Michael 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 - NRC INTEGRATED INSPECTION REPORT 05000277/2014003 AND 05000278/2014003
Dear Mr. Pacilio:
On June 30, 2014, the U. S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The enclosed inspection report documents the inspection results, which were discussed on July 25, 2014, with Mr. Michael Massaro, Peach Bottom Site Vice President, and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings were identified.
In accordance with Title 10 of the Code of Federal Regulations (CFR) 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any), will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records component of the NRC's Agencywide Documents Access 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 4 Division of Reactor Projects Docket Nos: 50-277, 50-278 License Nos: DPR-44, DPR-56
Enclosure:
Inspection Report 05000277/2014003 and 05000278/2014003
w/Attachment:
Supplementary Information cc w/encl: Distribution via ListServ
Mr. Michael
SUMMARY OF FINDINGS
IR 05000277/2014003, 05000278/2014003; 04/01/2014 - 06/30/2014; Peach Bottom Atomic
Power Station (PBAPS), Units 2 and 3. This report covered a three-month period of inspections by resident inspectors and announced inspections performed by regional inspectors. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 5, dated February 2014. Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity None
Other Findings
None
REPORT DETAILS
Summary of Plant Status
Unit 2 began the inspection period at 100 percent rated thermal power (RTP). On May 16, 2014, operators reduced RTP to approximately 57 percent to perform planned main turbine valve testing, main steam isolation valve testing, and control rod drive (CRD) hydraulic control unit (HCU) maintenance. The unit was returned to 100 percent RTP on May 17, 2014. The unit remained at 100 percent RTP through the end of the inspection period.
Unit 3 began the inspection period at 100 percent power. On May 30, 2014, operators reduced power to approximately 25 percent to perform a planned summer readiness load drop. The planned work included main condenser water box cleaning, 'A' reactor feedpump repairs, main turbine electro-hydraulic control (EHC) power supply troubleshooting, main turbine valve testing, and control rod scram time testing. The unit was returned to 100 percent RTP on June 2, 2014. The unit remained at 100 percent RTP through the end of the inspection period.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R01 Adverse Weather Protection
.1 Summer Readiness of Offsite and Alternate AC Power Systems (1 sample)
a. Inspection Scope
On May 27 - 29, 2014, the inspectors performed a review of plant features and procedures for the operation and continued availability of the offsite and alternate AC power systems to evaluate the readiness of the systems prior to seasonal high grid loading. The inspectors reviewed PBAPS' procedures related to these areas and the communication protocols between the transmission system operator and PBAPS. This review focused on changes to the established program and material condition of the offsite and alternate AC power equipment. The inspectors assessed whether PBAPS established and implemented appropriate procedures and protocols to monitor and maintain availability and reliability of both the offsite AC power system and the onsite alternate AC power system. Documents reviewed for each section of this inspection report are listed in the Attachment.
b. Findings
No findings were identified.
.2 Readiness for Seasonal Extreme Weather Conditions (1 sample)
a. Inspection Scope
On June 17, 2014, the inspectors performed a review of PBAPS' readiness for the onset of seasonal high temperatures. The inspectors walked down the EDG enclosure, the cooling water intake structure, and cooling ponds to ensure system availability. The inspectors verified that operator actions defined in PBAPS' adverse weather procedure maintained the readiness of essential systems. The inspectors discussed readiness and staff availability for adverse weather response with operations and work control personnel.
b. Findings
No findings were identified.
1R04 Equipment Alignment
Partial System Walkdowns (71111.04Q - 3 samples)
a. Inspection Scope
The inspectors performed partial walkdowns of the following systems: Unit 3 'B' CRD pump with the Unit 3 'A' CRD pump out-of-service (OOS) on April 14, 2014 E-1, E-2, E-3, and E-4 EDGs with the Unit 3 auxiliary emergency transformer OOS on April 16, 2014 E-1, E-2, and E-3 EDG's with the E-4 EDG OOS for an overhaul on May 7, 2014 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, technical specifications (TSs), work orders (WOs), condition reports (CRs), and the impact of ongoing work activities on redundant trains of equipment in order to identify conditions that could have impacted system performance of their 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 PBAPS staff had properly identified equipment issues and entered them into the corrective action program (CAP) for resolution with the appropriate significance characterization.
b. Findings
No findings were identified.
1R05 Fire Protection
Resident Inspector Quarterly Walkdowns (71111.05Q - 5 samples)
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 PBAPS controlled combustible materials and ignition sources were controlled 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 OOS, degraded or inoperable fire protection equipment, as applicable, in accordance with procedures.
Unit 3 refuel floor spent fuel pool on May 18, 2014 Unit 2 refuel floor independent spent fuel storage installation on May 19, 2014 Unit 2 and Unit 3 MCR on May 23, 2014 Unit 2 main and auxiliary transformers on June 27, 2014 Unit 3 main and auxiliary transformers on June 27, 2014
b. Findings
No finds were identified
1R07 Heat Sink Performance
a. Inspection Scope
The inspectors reviewed the Unit 2 'A' turbine building closed cooling water (TBCCW) heat exchanger (HX) on May 27 - 29, 2014, to determine its readiness and availability to perform its safety functions. The inspectors reviewed the design basis for the component and verified PBAPS' commitments to NRC Generic Letter 89-13. The inspectors reviewed the results of the previous inspections of the 'A' TBCCW HX. The inspectors discussed the results of the most recent inspection with engineering staff and reviewed pictures of the as-found and as-left conditions. The inspectors verified that PBAPS initiated appropriate corrective actions for identified deficiencies.
b. Findings
No findings were identified.
1R11 Licensed Operator Requalification Program
.1 Quarterly Review of Licensed Operator Requalification Testing and Training
(1 sample)
a. Inspection Scope
The inspectors observed a licensed operator simulator portion of an emergency preparedness drill on April 21, 2014, which included a loss of offsite power (LOOP)followed by a station blackout (SBO) scenario. The inspectors evaluated operator performance during the simulated event and verified completion of risk significant operator actions, including the use of abnormal and emergency operating procedures.
The inspectors assessed the clarity and effectiveness of communications, implementation of actions in response to alarms and degrading plant conditions, and the oversight and direction provided by the control room supervisor. The inspectors verified the accuracy and timeliness of 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 MCR (1 sample)
a. Inspection Scope
The inspectors observed licensed operator performance in the MCR for Unit 3 power accession on June 2, 2014. The inspectors observed reactivity manipulations to verify that they were performed in a safe and controlled manner and included the appropriate level of peer verification and supervisory oversight.
b. Findings
No findings were identified.
.3 Licensed Operator Requalification Program
a. Inspection Scope
On June 9, 2014, one NRC region-based inspector conducted an in-office review of results of licensee-administered annual operating tests for 2014 for PBAPS, Units 2 and 3 operators. The inspection assessed whether pass rates were consistent with the guidance of NRC Manual Chapter 0609, Appendix I, and "Operator Requalification Human Performance SDP." The review verified that the failure rate (individual or crew)did not exceed 20 percent.
0 out of 66 operators failed at least one section of the annual exam. The overall individual failure rate was 0 percent.
0 out of 10 crews failed the simulator test. The crew failure rate was 0 percent.
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 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 PBAPS 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 that the (a)(2) performance criteria established by the PBAPS 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) status. Additionally, the inspectors ensured that PBAPS staff was identifying and addressing common cause failures that occurred within and across MR system boundaries.
Building structures on May 1 - 2, 2014 Unit 2 'A' TBCCW entering a(1) status on May 28 - June 27, 2014
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 PBAPS 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 PBAPS personnel performed risk assessments as required by 10 CFR 50.65(a)(4)and that the assessments were accurate and complete. When PBAPS 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 yellow risk, reactor core isolation cooling (RCIC) outage on April 21-24, 2014 Unit 2 and Unit 3 yellow risk, E-4 EDG OOS and high pressure service water emergency cooling tower return motor-operated valve, MO-2803 OOS on May 5, 2014 Unit 2 yellow risk, 'A', 'B', 'C', and 'D' 125 VDC battery rooms and 20D021 125 DC Bus and 20D022 125 VDC bus with E-4 EDG OOS on May 6, 2014 Unit 2 and Unit 3 yellow risk, 'A' standby gas on May 27, 2014 Unit 2 and Unit 3 green risk, fire system OOS on June 16, 2014
b. Findings
No findings were identified.
1R15 Operability Determinations and Functionality Assessments
a. Inspection Scope
The inspectors reviewed six operability determinations (ODs) for the following degraded or non-conforming conditions:
SE-16 grid emergency 500 kV loss of indication on April 1, 2014 Adverse Condition Monitoring Plan on Unit 2 leaking feed pump relief valve on May 1, 2014 Alternate shutdown E-2 and E-4 broken wires on May 16-19, 2014 E-2 and E-4 EDG alternate shutdown degraded on May 23, 2014 Unit 2 and Unit 3 emergency service water (ESW) 'A' minimum pipe wall thickness on May 29, 2014 Unit 2 oil leak on main generator output breaker (circuit breaker - 225) on June 25, 2014 The inspectors selected these issues based on the risk significance of the associated components and systems. The inspectors evaluated the technical adequacy of the ODs to assess whether TS operability was justified properly 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 PBAPS' evaluations to determine whether the components or systems were operable. Where compensatory measures were required to maintain operability, the inspectors determined whether the measures in place would function as intended and were controlled properly by PBAPS. The inspectors determined, where appropriate, compliance with bounding limitations associated with the evaluations.
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 ensured system operability and functional capability. The inspectors reviewed the test procedure to verify that the procedure adequately tested the safety functions that may have been affected by the maintenance activity, that the acceptance criteria in the procedure was consistent with the information in the applicable licensing basis and/or design basis documents, and that the procedure had been properly reviewed and approved. The inspectors also witnessed the test or reviewed test data to verify that the test results adequately demonstrated restoration of the affected safety functions.
E-4 EDG after fire in the exhaust manifold on April 17, 2014 ST-O-013-301-3, "Unit 3 RCIC Pump, Valve, and Flow Test," after RCIC was returned to service on April 25, 2014 'B' ESW pump after check valve repair on April 30, 2014 SO 10.3.B-2, "RHR System 'B' LOOP Filling and Venting," after the Unit 2 'B' RHR HX was returned to service ST-O-023-301-2, "Unit 3 High Pressure Coolant Injection (HPCI) After Flow Controller Replaced," on June 25, 2014
b. Findings
No findings were identified.
1R22 Surveillance Testing
a. Inspection Scope
(5 routine surveillances; 2 IST samples) The inspectors observed performance of surveillance tests (STs) and/or reviewed test data of selected risk-significant SSCs to assess whether test results satisfied TSs, the UFSAR, and PBAPS 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:
RT-R-003-961-3, "CRD Friction Monitoring - Settle and Full Stroke Insertion Testing," on April 2, 2014 SI2P-2-128-A1CQ, "Calibration Check of Reactor Vessel Pressure Instruments Test," on April 7, 2014 RT-O-023-750-2, "Unit 2 HPCI Alternate Panel Test," on May 19, 2014 ST-O-023-301-2, "HPCI Unit 2 Pump, Valve and Flow Test," on May 28, 2014 ST-O-010-306-2, "B RHR LOOP Pump, Valve, Flow, and Unit Cooler Functional and Inservice Testing," on June 4, 2014 ST-O-020-560-2, "Reactor Coolant Leakage Test," on June 18, 2014 ST-O-011-301-3, "Standby Liquid Control Pump Functional Test for Inservice Testing," on June 27, 2014
b. Findings
No findings were identified. Cornerstone: Emergency Preparedness
1EP6 Drill Evaluation
Emergency Preparedness Drill/Simulator Evaluation/Observation
a. Inspection Scope
The inspectors evaluated the shift manager\emergency director's EP implementation during a licensed operator annual requalification simulator exam and technical support center on April 21, 2014. 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 PBAPS staff in order to evaluate whether PBAPS staff was properly identifying emergency preparedness weaknesses and entering them into the CAP.
b. Findings
No findings were identified.
RADIATION SAFETY
Cornerstone:
Occupational/Public Radiation Safety (PS)
2RS1 Radiological Hazard Assessment and Exposure Controls
a. Inspection Scope
During the week of May 19 - 23, 2014, the inspectors reviewed PBAPS' performance in assessing the radiological hazards in the workplace associated with licensed activities and the implementation of appropriate radiation monitoring and exposure control measures for both individual and collective exposures. The inspectors used the requirements in 10 CFR Part 20 and guidance in Regulatory Guide (RG) 8.38, "Control of Access to High and Very High Radiation Areas for Nuclear Plants," the TSs, and PBAPS' procedures required by TSs as criteria for determining compliance.
Inspection Planning
The inspectors verified that PBAPS is properly identifying and reporting performance indicators (PIs) for the Occupational Radiation Safety cornerstone and identifying those PDs that were reportable as a PI and which may represent a substantial potential for overexposure of the worker.
Instructions to Workers The inspectors selected containers of radioactive materials and verified that they were labeled and controlled.
Contamination and Radioactive Material Control The inspectors observed several locations where PBAPS monitors material leaving the radiologically controlled area (RCA), and inspected the methods used for control, survey, and release from these areas. The inspectors verified that the radiation monitoring instrumentation had appropriate sensitivity for the type(s) of radiation present.
The inspectors reviewed PBAPS' criteria for the survey and release of potentially contaminated material. The inspectors verified that there was guidance on how to respond to an alarm that indicated the presence of radioactive material.
The inspector reviewed PBAPS' procedures and records to verify that the radiation detection instrumentation was used at its typical sensitivity level based on appropriate counting parameters.
The inspectors selected sealed sources from PBAPS' inventory records that present the greatest radiological risk. The inspectors verified that sources are accounted for and had been verified to be intact.
The inspectors verified that any transactions involving nationally tracked sources were reported.
b. Findings
No findings were identified.
2RS2 Occupational As Low As Reasonably Achievable Planning and Controls
a. Inspection Scope
During the week of May 19 - 23, 2014, the inspectors assessed performance with respect to maintaining individual and collective radiation exposures As Low As Reasonably Achievable (ALARA). The inspectors used the requirements in 10 CFR Part 20, RG 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Plants will be ALARA," RG 8.10, "Operating Philosophy for Maintaining Occupational Radiation Exposure ALARA," the TSs, and PBAPS' procedures required by TSs as criteria for determining compliance.
Inspection Planning
The inspectors reviewed pertinent information regarding plant collective exposure history, current exposure trends, and ongoing or planned activities in order to assess current performance and exposure challenges. The inspectors determined the plant's three-year rolling average collective exposure.
The inspectors determined the site-specific trends in collective exposures and source term measurements. The inspectors reviewed site-specific procedures associated with maintaining occupational exposures ALARA, which included a review of processes used to estimate and track exposures from specific work activities.
Source Term Reduction and Control Using PBAPS records, the inspectors determined the historical trends and current status of significant tracked plant source terms known to contribute to elevated facility aggregate exposure. The inspectors determined that PBAPS was making allowances and developing contingency plans for expected changes in the source term as the result of changes in plant fuel performance issues or changes in plant primary chemistry. Problem Identification and Resolution The inspectors verified that problems associated with ALARA planning and controls were being identified by PBAPS at an appropriate threshold and were properly addressed for resolution in the licensee's CAP.
b. Findings
No findings were identified.
2RS5 Radiation Monitoring Instrumentation
a. Inspection Scope
During the week of May 19 - 23, 2014, the inspectors verified that PBAPS was ensuring the accuracy and operability of radiation monitoring instruments that are used to (1) monitor areas, materials, and workers to ensure a radiologically safe work environment and (2) detect and quantify radioactive process streams and effluent releases. The inspectors used the requirements in 10 CFR Part 20, 10 CFR Part 50 Appendix A - Criterion 60, "Control of Release of Radioactivity to the Environment,"
and Criterion 64, "Monitoring Radioactive Releases," 10 CFR 50 Appendix I, "Numerical Guides for Design Objectives and Limiting Conditions for Operation to meet the Criterion "ALARA" for Radioactive Material in Light-Water - Cooled Nuclear Power Reactor Effluents," 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operations," NUREG 0737, "Clarification of Three Mile Island Corrective Action Requirements," the TSs/Offsite Dose Calculation Manual, applicable industry standards, and PBAPS' procedures required by TSs as criteria for determining compliance.
Walkdowns and Observations The inspectors selected portable survey instruments in use or available for issuance. The inspectors checked calibration and source check stickers for currency, and assessed instrument material condition and operability.
The inspectors observed PBAPS staff performance as they demonstrated source checks for various types of portable survey instruments. The inspectors determined that high-range instruments were source checked on all appropriate scales.
The inspectors walked-down area radiation monitors (ARMs) and continuous air monitors (CAMs) and determined that they were appropriately positioned relative to the radiation sources or areas they were intended to monitor.
The inspectors selected personnel contamination monitors (PCMs) and small article monitors (SAMs) and verified that the periodic source checks were performed in accordance with the manufacturer's recommendations and PBAPS procedures.
Calibration and Testing Program The inspectors reviewed the methods and sources used to perform whole body counter (WBC) functional checks before daily use of the instrument. The inspectors determined that check sources were appropriate and align with the plant's isotopic mix.
The inspectors reviewed WBC calibration reports completed since the last inspection to verify that calibration sources were representative of the plant source term and that appropriate calibration phantoms were used.
The inspectors selected samples of PCMs and SAM used on site, and verified that the alarm set-point values were adequate to ensure that licensed material is not released from the site.
The inspectors reviewed calibration documentation for each instrument selected and discussed the calibration methods with the licensee to determine consistency with the manufacturer's recommendations. For portable survey instruments and ARMs, the inspectors reviewed detector measurement geometry and calibration methods, and had PBAPS demonstrate use of its instrument calibrator.
The inspectors selected portable survey instruments that did not meet acceptance criteria during calibration or source checks. The inspectors verified that PBAPS had taken appropriate corrective action for instruments found out of calibration. For these instruments, the inspectors verified that PBAPS had evaluated the possible consequences of instrument use since the last successful calibration or source check.
The inspectors reviewed the current output values for PBAPS' portable survey and ARM instrument calibrator units. The inspectors verified that PBAPS periodically measured calibrator output over the range of the instruments used through measurements by ion chamber/electrometer. The inspectors verified that the measuring devices had been calibrated by a facility using National Institute for Standards and Technology traceable sources and that correction factors for these measuring devices were properly applied by PBAPS in its output verification.
The inspectors reviewed PBAPS' 10 CFR Part 61, "Licensing Requirements for Land Disposal of Radioactive Waste," source term to determine if the calibration sources used were representative of the types and energies of radiation encountered in the plant.
b. Findings
No findings were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator Verification
Reactor Coolant System (RCS) Specific Activity and RCS Leak Rate
a. Inspection Scope
The inspectors reviewed PBAPS' submittal for the RCS specific activity and RCS leak rate PIs for both Unit 2 and Unit 3 for the period of April 1, 2013, through March 31, 2014. To determine the accuracy of the 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 RCS sample analysis and control room logs of daily measurements of RCS leakage, and compared that information to the data reported by the PI.
Additionally, the inspectors observed chemistry technician surveillance activities that determined the RCS identified leakage rate, and discussed the chemistry RCS sampling data and analysis.
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 PBAPS 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 condition report screening meetings.
b. Findings
No findings were identified.
.2 Semi-Annual Trend Review (1 Semi-Annual Trend sample)
a. Inspection Scope
The inspectors performed a semi-annual review of site issues, as required by IP 71152, "Problem Identification and Resolution," to identify trends that might 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 PBAPS outside of the CAP, such as trend reports, PIs, major equipment problem lists, system health reports, MR assessments, and maintenance or CAP backlogs. The inspectors also reviewed PBAPS' CAP database for the six month period covering January 1, 2014 through June 30, 2014, to assess CRs written in various subject areas (equipment problems, human performance issues, etc.), and individual issues identified during the NRC's daily CR review (Section 4OA2.1). The inspectors reviewed the PBAPS' trend report for the first quarter of 2014, conducted under LS-AA-125-1005, "Coding and Analysis Manual," to verify that PBAPS personnel were appropriately evaluating and trending adverse conditions in accordance with applicable procedures.
b. Findings and Observations
No findings were identified.
The inspectors noted minor adverse trends identified by PBAPS in the areas of maintenance work package closure and material handling/rigging, but noted that there were no adverse safety consequences as a result of these low level trends. Based on the overall results of the semi-annual trend review, the inspectors determined that PBAPS was appropriately identifying and entering issues into the CAP, adequately evaluating the identified issues, and properly identifying adverse trends before they became more safety significant problems.
.3 Annual Sample: Peach Bottom Unit 3 Fuel Channel Bow Indications (1 sample)
a. Inspection Scope
The inspectors reviewed Exelon's current corrective actions and evaluations that documented a channel bowing issue for one fuel cell (IR 1572562). The review was focused on the cause of the most recent Unit 3 channel bow issue and any extent of condition criteria that may also apply to Unit 2. Unit 3 control rod 38-59 actual scram time was within the TS allowable limits; but exceeded the Exelon and General Electric (GE) criteria for the reduced scram time margin. The inspectors reviewed the control rod test data that was recorded using procedure RT-R-003-961-3, "CRD Friction Monitoring - Settle and Full Stroke Insertion Testing," on April 2, 2014. This was the first indication of channel bow problems at PBAPS in several years. The inspectors also interviewed multiple reactor engineering and nuclear fuels personnel.
b. Findings and Observations
No findings were identified. The inspectors concluded that the susceptible control rod drive (CRD) mechanisms were tested properly and PBAPS documented the continued operability of all Unit 2 and Unit 3 CRD scram times. The inspectors determined that Peach Bottom has satisfactorily implemented the GE recommended channel bowing action plan for the years since the last channel bow problem identified at PBAPS.
4OA3 Followup of Events and Notices of Enforcement Discretion
Onsite Fatality Non-Work Related
a. Inspection Scope
On June 10, 2014, a non-work related on-site fatality as a result of natural causes occurred at PBAPS. The fatality was not related to the health and safety of the public or on-site personnel. Specifically, a contract truck driver was found non-responsive in a truck in the parking lot. The individual was outside of the radiological controlled area and no radioactive material or contamination was involved. The location of the parking lot is outside of the protected area but within the owner controlled area. An Event of Potential Public Interest notification was completed. PBAPS made an event notification system (ENS) report due to a fatality on-site. This ENS notification was in response to a notification to another government agency in accordance with 10 CFR 50.72(b)(2)(xi). Exelon notified the NRC Resident Inspector, the Emergency Management Agencies in Pennsylvania and Maryland, the Pennsylvania State Police, and to the surrounding counties.
b. Findings and Observations
No findings were identified.
4OA5 Other Activities
Buried Piping, TI-2515/182, Phase 2 (1 sample)
a. Inspection Scope
Exelon's buried piping and underground piping and tanks program was inspected in accordance with paragraphs 03.02.a of the Temporary Instruction (TI) 2515/182, and it was confirmed that activities which correspond to the completion dates, specified in the program, which have passed since the Phase 1 inspection was conducted, have been completed.
Exelon's buried piping and underground piping and tanks program was inspected in accordance with paragraph 03.02.b of the TI and responses to specific questions found in www.nrc.gov/reactors/operating/ops-experience/buried-pipe-ti-phase-2-insp-req-2011-11-16.pdf were submitted to NRC headquarter's staff.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
Quarterly Resident
Exit Meeting Summary
On July 25, 2014, the resident inspectors presented the inspection results to Mr. Michael Massaro, Peach Bottom Site Vice President, and other PBAPS staff, who acknowledged the results. 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 Company Personnel
- M. Massaro, Site Vice President
- P. Navin, Plant Manager
- N. Alexakos, Emergency Preparedness Manager
- J. Armstrong, Regulatory Assurance Manager
- D. Baracco, ALARA Manager
- R. Bolding, Respiratory Physicist
- C. Cilluffo, Buried Piping and Tanks Program Engineer
- D. Dullum, Exelon Senior Regulatory Engineer
- B. Hennigan, Operations Training Manager
- M. Herr, Operations Director
- R. Holmes, Radiation Protection Manager
- F. Leone, Chemistry Manager
- T. Moore, Site Engineering Director
- B. Reiner, Training Director
- R. Ridge, Supervisor, Radiological Instruments
- P. Simmons, Security Manager
- D. Striebig, Emergency Preparedness Coordinator
- M. Weidman, Work Management Director
NRC Personnel
- F. Bower III, Branch Chief
- S. Hansell, Senior Resident Inspector
- B. Smith, Resident Inspector
- J. Furia, Senior Health Physicist
- J. Heinly, Resident Inspector, Three Mile Island Resident Inspector
- T. O'Hara, Reactor Engineer
- D. Silk, Senior Operations Engineer
LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED
Opened/Closed
None
Opened
None
Closed
- None
- Discussed/Updated None
- Attachment
LIST OF DOCUMENTS REVIEWED
- -- Indicates NRC-identified
Section 1R01: Adverse Weather
Procedures
- OP-PB-108-111-1001, Preparation for Severe Weather, Revision 13
- OP-AA-108-111-1001, Preparation for Severe Weather, Revision 12
- OP-AA-108-107-1001, Station Response to Grid Capacity Conditions, Revision 4
- CRs 01652716, Weather Seal Degraded on Conduit at Cable Penetration
- 01652737, Packing Leak Identified
- 01653816, Unit 3 195' Turbine Building Fan Room Water Intrusion Due to Rain
- 01653830, Water Leaking Into Receiving Dock from the Exterior Doors
- 01653943, Water Leak from Ceiling @ Exit Portals in MAF
- 01653953, Water Leaking from Ceiling in CAS
- 01654218, Excessive Rain Water Inputs to Sewage Treatment Plant
- 01655274, Water Intrusion into E-2 EDG Bay
Section 1R04: Equipment Alignment
- CRs 1652763, EDG Material Condition Improvement Plan
Section 1R05: Fire Protection
Procedures
- PI-AA-125, Corrective Action Procedure, Revision 0
- PI-AA-125-1006, Investigation Techniques Manual, Revision 0
- SE-10, Attachment 6, 4 KV Alternative Shutdown Panel Setup and Transfer of 125V Battery Charger 2BD003 to Alternate Power Source, Revision 6
Miscellaneous
- SE-10 Plant Shutdown from the Alternate Shutdown Panels - Bases, Revision 23 PBAPS Fire Protection Plan, Revision 16
- PBAPS Fire Protection Plan, Revision 19
Section 1R07: Heat Sink Performance
Procedures
- ER-AA-340-1002, Service Water HX Maintenance Guide, Revision 6
- ER-AA-340-2000, Balance of Plant HX Inspection, Testing and Maintenance Guide
- M-C-TCSS-05, HX Maintenance Practices, Revision 2
- Attachment
- CRs 01665830, Replacement Needed for the Unit 3 'B' TBCCW HX
Section 1R11: Licensed Operator Requalification Program
Miscellaneous
- EP-PB-TSC-17 Emergency Preparedness Drill Scenario
Section 1R12: Maintenance Effectiveness
Procedures
- ER-AA-310-1001, MR Scoping, Revision 4
- ER-AA-310-1002, MR Functions - Safety Significance Classification, Revision 3
- ER-AA-310-1004, MR - Performance Monitoring, Revision 11
- ER-AA-310-1005, MR - Dispositioning Between A1 and A2, Revision 7
- ER-PB-310-1010, MR Implementation, Revision 6
- WC-AA-101, Attachment 6, Unavailability Guidelines, Revision 21
- CRs 01642793, NOS ID:
- Expectations Regarding Documentation of Work
- 01646116, MR Review Completed Late for
- 01654034, Received 2 'A'/2 'C' Battery Ground Alarm 220 F-1
- 01654054, E-4 Diesel Generator Building Roof Leaking
- 01676905, MRFF: System 40D IR Classified as a Functional Failure
Section 1R13: Maintenance Risk Assessments and Emergent Work Control
Procedures
- OP-AA-201-012-1001, On-line Fire Risk Management, Revision 1
- OP-PB-108-101-1002, Attachment A, PBAPS Protected Equipment Tracking Sheet
- ER-AA-600, Risk Management, Revision 7
Miscellaneous
- Paragon Risk Tool Daily Protected Area Logs
Section 1R15: Operability Evaluations
Procedures
- MA-AA-716-050-1000, Condenser Air In-Leakage Testing Guide and Limits, Revision 3 SO 5.7.A-3, Main Condenser Vacuum Leak Monitoring and Search, Revision 10
- CRs 01639851,
- SE-16 "Grid Emergency" Procedure Entered
- 01652157, Steam/Water Leak from
- RV-2-06C-2141B
- 01662767, Functional Test of Alternate Shutdown Control Transfer Isolation Switch Doesn't
- Test Control Power Circuit
- IRs
- 1652157, Suction Relief Valve for Reactor Feed Pump 2BP001
Miscellaneous
- ACMP for Unit 2 Feed Pump Relief Valve Leakage
Section 1R19: Post-Maintenance Testing
Procedures
- IR 01648311, Describes a Small Fire Observed Under the Opposite Control Side Ring Catcher Insulation on E-4 EDG during a Surveillance Run,
- Revision 27
- SO 13.1.A-3, RCIC System Alignment for Automatic or Manual Initiation, Revision 14 M-013-003, RCIC Pump Maintenance, Revision 3
- M-C-700-314, PECO Nuclear Horizontal Machine Shaft Alignment Rotalign Pro System, Revision 1
- ST-O-013-301-3, RCIC Pump, Valve, Flow and Unit Cooler Functional and In-service Test,
- Revision 42
- ST-O-023-301-3, HPCI Pump, Valve, Flow and Unit Cooler Functional and In-service Test, Revision 63
ARs
- 01331025
- 1914789, Unit 3 RCIC Pump Vibration
- CRs 01651578, Loss of Indicated Oil Level in Trico Oiler during RCIC
- PVF 01651737, Rupture Disc
- 01670017, Engineering Lesson Learned:
- Field Inspections during the 2BE024 RHR Decon
(C0252509) in WW1424
- IRs
- 01650713
Miscellaneous
eSOMS, E-4 EDG, dated April 17, 2014
eSOMS, Restoration of Unit 2 'B' RHR HX and Pump After Decontamination, dated June 11,
- 2014 to June 12, 2014 Unit 2 TS 3.5.1, TRM 3.11, Restore Low Pressure ECCS Injection Subsystem to Operable Status within 7 Days, 2 'B' RHR HX Decontamination
- 14000771
- Post-Work Questionnaire, WO
- C0249410 - Replace Pump Bearings/Inspect Bearing Housings Information Notice 2001-19:
- Improper Maintenance and Reassembly of Automatic Oil Bubblers
WOs
- C0249410, Replace Pump Bearings/Seals Attachment
Section 1R22: Surveillance Testing
Procedures
- RT-O-023-750-2, HPCI Functional Test from Alternative Control Panels, Revision 21
- RT-R-003-961-3, CRD Friction Monitoring - Settle and Full Stroke Insertion Testing, Revision 6
- SI2P-2-128-A1CQ, Calibration Check of Reactor Vessel Pressure Instrument PS 2-2-128A, Revision 19
- ST-O-010-306-2, 'B' RHR LOOP Pump, Valve, Flow, and Unit Cooler Functional and Inservice
- Test, Revision 39
- ST-O-011-302-3, Standby Liquid Control Pump Functional Comprehensive Test for IST, Revision 1
- ST-O-020-560-2, Reactor Coolant Leakage Test, Revision 13
- ST-O-020-560-3, Reactor Coolant Leakage Test, Revision 15
- CRs 01641787, Unit 3 Control Rod 58-23 Insert Speed Needs Verification
- 01641789, Unit 3 Control Rod 02-23 Insert Speed Needs Verification
- 01641785, Unit 3 Control Rod 38-03 Insert Speed Needs Verification
- 01644152, Found
- PS-2-02-128A Out-of-Calibration Low during
- SI-2P-2-128-A1CQ
- 01662890, Unit 2 HPCI PV&F Not Performed As Scheduled
- 01668110, Unit 2 SBLC Tank Sample Analyses Unexpected Results
- 01668127, Unit 3 SBLC Tank Sample Analyses Unexpected Results
Drawings
- P&I Diagram, RHR System, Sheet 1, 6280-M-361, Revision 84 P&I Diagram, RHR System, Sheet 2, 6280-M-361, Revision 70
Miscellaneous
- Peach Bottom Overview Report, dated June 2, 2014
Section 1EP6: Drill Evaluation
Miscellaneous
- EP-PB-TSC-17 Emergency Preparedness Drill Scenario
Section 2RS2: Occupational
- ALARA Planning and Controls
Section 2RS5: Radiation Monitoring Instrumentation
Miscellaneous
- PEA-12-002, ARGOS Whole Body Monitor Passive Monitoring Study (No Gamma Detectors) at PBAPS, Revision 0
- RP-AA-1010, Technical Analysis of Canberra
- ARGOS-5AB Radon Rejection
- Parameters, Revision 1
- PEA-13-001, Technical Justification for Performing Calibrations of the Thermo
- Scientific
- PM-12 Gamma Portal Monitor at Six Inches at PBAPS, Revision 1
- RT-H-099-930-2, Evaluation of Plant Radioisotopes and Energies, Revision 2
- ST-H-099-820-2, Radioactive Source Accountability & Leak Test, Revision 7
- Attachment
Procedures
- RP-AA-700-1501, Operation and Calibration of the Model
- SAM-9/11 Small Articles Monitor, Revision 1
- RP-AA-700-1214, Operation and Calibration of the
- PCM-1B Personnel Monitor, Revision 1
- RP-AA-700-1240, Operation and Calibration of the Canberra
- ARGOS-5 Personnel Contamination Monitor, Revision 2
- RP-AA-700-1239, Operation and Calibration of the
- SAM-12 Small Articles Monitor, Revision 1
- RP-AA-700-1235, Operation and Calibration of the
- PM-12 Portal Monitor, Revision 1
- RP-AA-700-1401, Operation and Calibration of Eberline Model
- PM-7 Personnel Contamination Monitor, Revision 1 Canberra Calibration of the Canberra Fastscan WBC System at the Plant Entrance and Radiological Lab of the PBAPS, Report Date: August 7, 2013
Section 4OA1: Performance Indicator Verification
Procedures
- LS-AA-2001, Collecting and Reporting of NRC PIs Data, Revision 14
- LS-AA-2090, Monthly Data Elements for NRC RCS Specific Activity, Revision 4
- LS-AA-2100, Monthly Data Elements for NRC RCS Leakage, Revision 5
- ST-O-020-560-2, Reactor Coolant Leakage Test (sample of completed test records),
- Revision 13
- ST-O-020-560-3, Reactor Coolant Leakage Test (sample of completed test records),
- Revision 15
- ST-C-095-820-2, Determination of Dose Equivalent µCi/g I-131 in Primary Coolant, Revision 4
- ST-C-095-820-3, Determination of Dose Equivalent µCi/g I-131 in Primary Coolant, Revision 4
- ST-C-095-864-2, Off Gas Monitor Response and Release Rate Verification by a Grab Sample,
- Revision 2
- ST-C-095-864-3, Off Gas Monitor Response and Release Rate Verification by a Grab Sample,
- Revision 2
Miscellaneous
- BI PI data - 2nd Quarter 2013 through the 4th Quarter 2014
Section 4OA2: Identification and Resolution of Problems
- CRs 01587659, NOS ID:
- Post-job WO Closure Deficiencies
- 01643034, Work Package Closure / Deficiency
- 01647667, WO Deficiencies Identified During Package Closure
- 01649804, Training:
- Requested Training / Package Closure
- Program and System Health Reports PBAPS Equipment Reliability Webpage: System IQ and Plant IQ PBAPS Top 10 Plant Health Issues List Peach Bottom Station Trend Review, 1Q14 Analysis
- Attachment
Procedures
- PI-AA-120, Issue Identification and Screening Process, Revision 0
Section 4OA3: Follow-up of Events and Notices of Enforcement Discretion
(IRs)/CRs
- 01669813,
Miscellaneous
- Peach Bottom Offsite Notification, Non-Work Related On-Site Fatality, dated June 10, 2014
Section 4OA5: Other Activities
Procedures
- ER-AA-5400-1002, Underground Piping & Tank Examination Guide, Revision 6
- ER-AA-5400-1003, Buried Piping & RAW Water Corrosion Program (BPRWCP)
- PIs, Revision 5
- PB-12-0144, 2013 Buried Piping Inspections, Buried Pipe and RAW Water Systems
- ER-AA-102, Buried Piping Program Providing a Structure for Common Approach to
- Resolution of Buried Pipe Issues, Revision 3
- ER-AA-102-1000, Buried Piping Examination Procedure Provides Guidance for Monitoring External Corrosion Control and Mitigation, Revision 1
- NES-MS-15.2, Request for Engineering Standard for Determining Reasonable Assurance of
- Structural Integrity and/or Leakage Integrity for Buried Piping, 9/14/10
- MAG-CG-409, PECO NUCLEAR, Determination of Measurement Areas for the
- Detection of Corrosion in RAW Water Piping Systems, Revision 3
- GUL 204:2012, Guided Ultrasonics Ltd., Standard Practice for the Deployment of gPIMS
- Using the Wavemaker Pipe Screening System, Revision 4
- AD-AA-101-F-09, Fleet Standard Document - Corporate Approval Form,
- 10/25/11 "Buried Piping and RAW Water Corrosion Program Guide, Revision 0
- ER-AA-5400, BPRWCP Guide Exelon Nuclear,
- ER-AA-3001, Revision 6, Long Term Asset Management (LTAM) Strategies, Revision 5
- Engineering Change Requests ECR PB13-00120 000, 3/11/13, Subject: Buried Piping Initiative Excavation Location Ten
- Buried Piping Inspection Reports Exelon Generation, Buried Piping Ultrasonic Examination Report from WO #
- CO247608-24, location 2-08HE-06-01-01-CT-PO1, Off Gas to Main Stack, 6/3/13 (2 pages) Exelon Generation, RAW Water Corrosion Ultrasonic Examination Report Form, WO #
- C0247608-24, location 2-08HE-06-01-01-CT-PO1, Off Gas to Main Stack, 6/10/13,
(1 page)
- 247608-24, location 2-08HE-06-01-01-CT-PO1, 6/10/13, (1 page) Exelon Generation, Buried Piping Ultrasonic Examination Report Form, WO #
- C0247608-24, location 2-08HE-06-01-01-CT-PO4, 6/10/13, (2 pages)
- Exelon Generation, Buried Piping Ultrasonic Examination Report Form, WO #
- C0247608-25,
- Location 3-08HE-06-02-01-CT-PO1, Off Gas to Main Stack, 6/10/13, (2 pages)
- Attachment
- Exelon Generation, Buried Piping Ultrasonic Examination Report Form, WO #
- C0247608-25, location 3-08HE-06-02-01, 6/10/13, (2 pages) Exelon Generation, Buried Piping Ultrasonic Examination Report Form, WO #
- C0247608-27, location 3-8EHE-24-04-01-D1-PO1, (Mech. & SPE to Main Stack,
- 6/18/13, (2 pages)
- Exelon Generation, Buried Piping Ultrasonic Examination Report Form, WO #
- C0247608-28, location 0-9-AHE-36-01-01-D1-PO1, Standby Gas Common, 6/19/13,
(2 pages) Mistras Report PB2 & PB3, 7/15/13, Long Range Guided Wave Ultrasonic Pipe Screening
- Results Technical Report AM3705-505586, 49HE-36", Common, 8HE-6" Unit 2; 8HE-6" Unit 3 15HE-24", Excavation Site 10, 6/25 - 6/29, 2013, (16 pages)
- UESI Nuclear Services, Evaluation Report & Inspection Repair Report, 1/31/13 2014, PBAPS, (19 pages) Report Number
- NUC 2013133.00, Revision 1, Submitted January 1, 2013, Exelon Nuclear, Conducted Pipe Evaluations in Excavation #10
ARs
- 01137854
- 01138619
- 01139646
- 01141622
- 01255149
- 01232678
- 01235815
- 01232678
- 01235819
- 01235822
- 01235823
- 01235827
- 01235829
- 01235833
- 01235837
- 01235840
- 01279994
- 01279996
- 279999
- 01280000
- IRs
- 01590000
- 01599369
- 01599367
- 01453261
- 01455781
- 01515096
- Program/System Health Reports Buried Piping Program and RAW Water Corrosion Program Health Report, Controlling Document (ER-AA-5400), 4th Quarter 2013, Status Yellow
- Buried Piping Program and RAW Water Corrosion Program Health Report,
- Controlling Document (ER-AA-5400), 1st Quarter 2014, Status White
Miscellaneous
- NRC
- TI 2515/182, 11/17/11; Review of the Implementation of the Industry Initiative to Control Degradation of Underground Piping and Tanks EPRI document, Recommendations for an Effective Program to Control the Degradation of
- Buried Pipe, December 2008
- NEI 09-14 (Initial Issue), November 2009 Guideline for the Management of Underground Piping and Tank Integrity
- NEI 09-14, December 2010 Guideline for the Management of Underground Piping and Tank
- Integrity, Revision 1
- NEI 09-14, Guideline for the Management of Underground Piping and Tank Integrity, Revision 2
- NEI 09-14, April 2013 Guideline for the Management of Underground Piping and Tank Integrity, April 2013, Revision 3
- EPRI-2010-409, Inspection Methodologies for Buried Piping and Tanks
- AR 00213052, NEI
- Buried Pipe Initiative of Action Items which Address Attributes detailed Table 1 of
- TI 2515/182 Check-In Self-Assessment - NRC Buried Piping
- TI-182 Inspection, Phase 1,
- 10/23/12
- Check-In Self-Assessment - Readiness for NRC Phase 2 Inspection Associated with Underground Piping and Tanks (TI 2515/182) 1/29/14
- Attachment
LIST OF ACRONYMS
TI temporary instruction
Attachment
UFSAR Updated Final Safety Analysis Report
Vdc volts direct current
WGE work group evaluation