ML16032A095: Difference between revisions
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| number = ML16032A095 | | number = ML16032A095 | ||
| issue date = 02/01/2016 | | issue date = 02/01/2016 | ||
| title = | | title = Ir 05000277/2015004 and 05000278/2015004: Peach Bottom Atomic Power Station - Integrated Inspection Report (October 1 - December 31, 2015) | ||
| author name = Schroeder D L | | author name = Schroeder D L | ||
| author affiliation = NRC/RGN-I/DRP/PB4 | | author affiliation = NRC/RGN-I/DRP/PB4 | ||
Revision as of 00:58, 13 February 2018
| ML16032A095 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/01/2016 |
| From: | Schroeder D L Reactor Projects Region 1 Branch 4 |
| To: | Bryan Hanson Exelon Nuclear |
| SCHROEDER, DL | |
| References | |
| IR 2015004 | |
| Download: ML16032A095 (43) | |
See also: IR 05000277/2015004
Text
February 1, 2016
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 05000277/2015004 AND 05000278/2015004
Dear Mr. Hanson:
On December 31, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed an 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 January 15, 2016, with Mr. Pat Navin, Peach Bottom Plant Manager, and other members of your staff. NRC Inspectors examined activities conducted under your license as they relate to safety and The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. The inspectors documented one finding of very low safety significance (Green) in this report. This finding involved a violation of NRC requirements. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy. If you contest the NCV in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at PBAPS. 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 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/ Daniel L. Schroeder, 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 05000277/2015004 and 05000278/2015004
w/Attachment:
Supplementary Information cc w/encl: Distribution via ListServ
SUMMARY
IR 05000277/2015004, 05000278/2015004, 10/01/2015 12/31/2015; Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3; Surveillance Testing. This report covered a three-month period of inspection by resident inspectors, and announced baseline inspections performed by regional inspectors. The inspectors identified one non-cited violation (NCV), which was of very low safety significance (Green). The significance of most findings is indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and (SDP),d June 2, 2011. Cross-Within Cross-December 19, 2013. All violations of NRC requirements are July 09, 2013. The described in NUREG-5.
Cornerstone: Mitigating Systems
- Green.
The inspectors identified a non-cited violation (NCV) of very low safety significance of 10 Code of Federal Regulations (CFR) Part 50, Appendix B, Criterion III, Design Control, for not ensuring that the adequacy of PBAPS emergency diesel generator (EDG) lubrication oil (LO) supply was designed to withstand the effects of natural phenomena. Specifically, additional LO, evaluated by PBAPS to meet their EDG technical specification (TS) mission time of seven days of continuous operation, was housed in a non-class I structure that would be unable to withstand the effects of natural phenomena. PBAPS entered the issue into the correction action program (CAP) as issue report (IR) 02603369 and took immediate corrective actions to relocate the LO reserve inventory from their of the radwaste building, which is a seismic class I structure The finding is considered more than minor because it is associated with the Protection Against External Factors attribute of the Reactor Safety Mitigating Systems cornerstone and adversystems that respond to initiating events to prevent undesirable consequences (i.e., core damage). The inspectors evaluated the significance of this finding using IMC 0609 (Green) because the finding is a design deficiency which did not result in an actual loss of functionality of the EDGs. This finding did not have a cross-cutting aspect because the most significant contributor of the performance deficiency (PD) occurred during the 1994 conversion to improved technical specifications (ITS) and, thus, was not reflective of current plant performanceprocess would evaluate for natural phenomena considerations such as seismic, tornado, flood, etc. (Section 1R22)
Other Findings
None.
4
REPORT DETAILS
Summary of Plant Status Unit 2 began the inspection period at 100 percent rated thermal power (RTP). On December 13, 2015, Unit 2 commenced a shutdown from 100 percent RTP and entered into a forced outage to repair packing on the 2 C inboard main steam isolation Valve (MSIV). On December 15, 2015, the Unit 2 reactor mode switch was placed in start-up and the main generator was synchronized to the electrical grid on December 17, 2015. On December 18, 2015, Unit 2 was returned to 100 percent RTP, and remained at 100 percent RTP until the end of the inspection period. Unit 3 began the inspection period in a refueling outage (RFO) (P3R20). On October 21, 2015, the Unit 3 reactor mode switch was placed in start-up and the main generator was synchronized to the electrical grid on October 22, 2015. On October 25, 2015, Unit 3 was returned to 89 percent power (the pre-extended power uprate (EPU) 100 percent power limit). On November 24, 2015, Unit 3 down powered from 92 percent RTP to 77 percent RTP to perform breaker maintenance on the 3 A condensate pump. Unit 3 returned to 92 percent RTP later that same day. On December 3, 2015, Unit 3 raised power to the full 100 percent RTP EPU limit after final NRC approval for power ascension. Unit 3 remained at 100 percent RTP until the end of the inspection period.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R01 Adverse Weather Protection
.1 Readiness for Impending Adverse Weather Conditions (1 sample)
a. Inspection Scope
October 2, 2015, resulting from Hurricane Joaquin. The inspectors reviewed the implementation of PBAPS' adverse weather preparation procedures before the onset of the adverse weather condition. The inspectors walked down the north substation, EDGs, and output transformer yard system availability. The inspectors verified that operator actions defined in Preadiness of essential systems. The inspectors discussed readiness and staff availability for adverse weather response with operations and work control personnel. Documents reviewed for each section of this inspection report are listed in the Attachment.
b. Findings
No findings were identified.
===.2 Winter Readiness Seasonal Extreme (1 sample)
a. Inspection Scope
The inspectors reviewed readiness for the cold weather preparations on December 11, 2015. The review focused on the EDGs, the river water intake structure travelling screens, emergency cooling tower (ECT), circulating water pump house, and associated support equipment. The inspectors reviewed the Updated Final Safety Analysis Report (UFSAR), TSs, and the CAP to determine the temperatures or other seasonal weather conditions that could challenge these systems. The review ensured PBAPS personnel had prepared adequately for the weather-related challenges. The inspectors reviewed station procedures, including 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 (71111.04Q
2 samples)
a. Inspection Scope
The inspectors performed partial walkdowns of the following systems: residual heat removal (RHR) following the cross-tie modification on October 20, 2015 Unit 3 reactor core isolation cooling (RCIC) following restoration after the RFO on October 21, 2015 The inspectors selected these systems based on their risk-significance relative to the Reactor Safety cornerstones at the time they were inspected. The inspectors reviewed applicable operating procedures, system diagrams, the UFSAR, TSs, work orders (WOs), IRs, and the impact of ongoing work activities on redundant trains of equipment in order to identify conditions that could have impacted the system 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 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 September 28, 2015, the inspectors performed a complete system walkdown of accessible portions of the Unit 3 automatic depressurization system and associated Unit 3 safety relief valves (SRVs) 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 PBAPS 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 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 out-of-service (OOS), degraded or inoperable fire protection equipment, as applicable, in accordance with procedures.
Unit 3 recirculation pump motor generator (MG) set room and adjustable speed drive (ASD) trailer on October 1, 2015 Unit 3 torus space on October 19, 2015 Unit 3 outboard MSIV room on October 20, 2015 Units 2 and 3 cable spreading room on October 30, 2015 Units 2 and 3 main control room on November 5, 2015
b. Findings
No findings were identified.
1R07 Heat Sink Performance
a. Inspection Scope
RHR/high pressure service water (HPSW) heat exchanger (HX) during the week of November 2, 2015, to determine its readiness and availability to perform is safety functions. The inspectors reviewed the design basis for -13, Service Water System Requirements Affecting Safety-Related Equipment. The inspectors reviewed the results of the most recent thermal performance monitoring test (performed February 12, 2015), the most recent internal visual inspection, including tube sheet partition plate inspection and eddy current testing (performed February 12, 2015), and trend assessment based on comparison with previous inspections and performance tests. The inspectors discussed the results of the most recent inspection with engineering staff. The inspectors verified that PBAPS initiated appropriate corrective actions for identified deficiencies. The inspectors also verified that the number of tubes plugged within the HX did not exceed the maximum amount allowed.
b. Findings
No findings were identified.
1R08 In-service Inspection Activities
a. Inspection Scope
The inspectors reviewed Exelon staff implementation of in-service inspection (ISI) program activities for monitoring degradation of the reactor coolant system boundary, risk significant piping and components, and containment systems during the PBAPS Unit 3 20th RFO. The inspection was completed onsite September 21 to 28, 2015, followed by in-office review October 8 to 9, 2015. The sample selection for this inspection was based on the inspection procedure objectives and risk priority of those pressure retaining components in systems where degradation would result in a significant increase in risk. The inspectors observed in-process non-destructive examinations (NDE), reviewed documentation, and interviewed Exelon personnel to verify that the NDE activities performed as part of the fourth interval, third period, of the Peach Bottom 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 2002 and 2003 Addenda. NDE and Welding Activities The inspectors performed direct observation of NDE activities in process and reviewed documentation of completed examinations listed below. Activities included review of ultrasonic testing (UT), radiographic testing (RT), and visual examination (VT).
The inspectors reviewed certifications of the NDE technicians performing the examinations and verified that the inspections were performed in accordance with approved 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 of the N4E nozzle-to-vessel weld in the feedwater system. Direct observation of the manual UT of the N4E nozzle inner radius and bore in the feedwater system. Documentation review of the manual UT of the reactor pressure vessel closure head studs (Studs 47-92). Documentation review of the RT of two pipe-to-flange welds (10-2XC020-11 and -12) and one pipe-to-pipe weld (10-2DC20-29), 20-inch diameter, performed as part of a modification activity in the RHR system. Direct observation of the VT of the drywell (i.e., containment) interior and exterior penetrations and surfaces. The inspectors independently examined the condition of the drywell interior liner surfaces at all floor elevations, including the moisture barrier drywell VT records and compared those to the inspector walkdowns. Review of Previous Indications Accepted by Evaluation The inspectors did not review any previous indications because there were no relevant indications from the previous outage that required evaluation for continued service. Repair/Replacement Activities Including Welding Activities The inspectors reviewed the modification package associated with engineering change 11-00376, which implemented plant changes as part of the EPU project. Specifically, the scope of the modification was to install a piping cross-RHR system in order to increase the containment cooling capability following a postulated design basis event. The inspectors performed a direct observation of the welding activities associated with two piping welds (10-2XC020-11 and -12) in progress and performed a documentation review of one completed weld (10-2DC20-29) to verify that welding and applicable NDE activities were performed in accordance with ASME code requirements. The inspectors reviewed the weld procedure and weld information data sheet, and also reviewed the radiography data sheets for final acceptance of the welds. The modification was performed under WOs C0255830 and C0255936.
Identification and Resolution of Problems The inspectors reviewed a sample of PBAPS Unit 3 corrective action 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 corrective actions 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 a licensed operator requalification training scenario for the site area on November 9, 2015. The inspectors evaluated operator performance during the simulated event and verified completion of risk significant operator actions, including the use of abnormal and emergency operating procedures. The inspectors assessed the clarity and effectiveness of communications, implementation of actions in response to alarms and degrading plant conditions, and the oversight and direction provided by the control room supervisor. The inspectors verified the accuracy and timeliness of the emergency 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 (2 samples)
a. Inspection Scope
The inspectors observed and reviewed the licensed operator performance from the main control room during the reactivity evolutions listed below. 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.
Unit 3 plant startup and heat up from RFO 3R20 on October 20 and 21, 2015 Unit 2 plant shutdown and cooldown for a forced outage to repair a packing leak on
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.
Unit 3 recirculation system and ASDs on November 4, 2015
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 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.
Elevated risk, Unit 3 operation with a potential for draining the reactor vessel (OPDRV) during local power range monitor swaps on October 1, October 5, and October 6, 2015 Elevated risk, Unit 2 E-43 bus outage on October 13, 2015 Elevated risk, Unit 3 containment not fully inerted during plant startup on October 21, 2015
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 standby liquid control (SBLC) test in which an explosive (squib) valve did not appear to fire correctly on October 8, 2015 Unit 3 reactor water cleanup class 1 piping below minimum wall thickness on October 8, 2015 Unit 3 MSIV snubbers low oil identified in reservoirs on October 9, 2015 Unit 3 high-pressure coolant injection (HPCI) drain valve leaking by on October 22, 2015 Operator workarounds (OWAs) on November 5, 2015 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 nents or systems were operable. The inspectors confirmed, where appropriate, compliance with bounding limitations associated with the evaluations, including compliance with in-service testing requirements. Where compensatory measures were required to maintain operability, such as in the case of OWAs, the inspectors determined whether the measures in place would function as intended and were properly controlled by PBAPS. Based on the review of selected OWAs listed above, the inspectors verified that PBAPS identified OWAs at an appropriate threshold and addressed them in a manner that effectively managed OWA-related adverse effects on operators and SSCs.
b. Findings
No findings were identified.
1R18 Plant Modifications
Permanent Modification
a. Inspection Scope
The inspectors evaluated the following modification listed below: Unit 3 reactor recirculation pump and ASDs modification on November 2 to November 5, 2015 The inspectors verified that the design bases, licensing bases, and performance capability of the affected systems were not degraded by the modifications. In addition, the inspectors reviewed modification documents associated with the upgrade and design change. The inspectors also reviewed 10 CFR 50.59 documentation, post-modification testing results, procedure revisions, training documentation, and conducted field walkdowns of the modifications.
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 points were performed and checked, and that results adequately demonstrated restoration of the affected safety functions.
(CS) valve local leak rate test (LLRT) following valve maintenance on October 4, 2015 Unit 3 HPCI vacuum relief valves LLRTs following maintenance on October 5, 2015 Unit 3 RCIC overspeed trip test following maintenance outage on October 15, 2015 Unit 3 PMT following crosstie modification on October 19, 2015 Unit 3 emergency auxiliary transformer following maintenance outage on November 19, 2015 Unit PMT following maintenance on November 20, 2015 inboard MSIV stroke timing following repacking on December 16, 2015
b. Findings
No findings were identified.
.1 Unit 3 Refueling Outage (3R20) (1 sample)
a.
b.
No findings were identified.
===.2 Unit 2 Forced Outage (1 sample)
a. Inspection Scope
The inspectors observed a Unit 2 forced outage following elevated unidentified reactor coolant system (RCS) leakage, conducted December 13 to 15, 2015. The elevated
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 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 and routine tests: standby liquid control (SBLC) test on October 15, 2015 Unit 3 HPCI low pressure test on October 21, 2015 Unit 3 Unit common, E-2 EDG monthly test on November 9, 2015 Unit 2 RCS unidentified leakage surveillance on December 7, 2015
b. Findings
Introduction.
The inspectors identified a NCV of very low safety significance of 10 CFR Part 50, Appendix B, Criterion III, Design Control, for not ensuring that the EDG LO supply was designed to withstand the effects of natural phenomena. Specifically, additional LO, evaluated by PBAPS to meet their EDG TS mission time of seven days of continuous operation, was housed in a non-seismic Class 1 structure that was not designed to withstand the effects of natural phenomena.
Description.
On November 9, 2015, the inspectors reviewed IR 02583825, concerning loss of LO inventory in the E-2 EDG LO storage tank during an E-2 EDG monthly ST. The IR documented in its basis for operability that total LO inventory onsite was within TS limits. In 1994, PBAPS converted from custom to ITS. During the ITS conversion, the NRC requested PBAPS to evaluate the EDG LO consumption rate to determine if inventory requirements met their intended design. In response to the request for information, PBAPS evaluated, under evaluation A0784276, the oil consumption rate to be 2.0 gallons per hour based both on vendor specifications and conservatism recommended by the vendor since LO consumption is affected by the quality of the oil used and engine wear. PBAPS identified that the EDGs required additional inventory to meet their design requirements because of the consumption rate, capacity of the in-room storage (i.e., LO tank, associated piping, and LO sump), and seven day continuous operational design requirement. TS 3.8.3 requires a LO inventory of 350 gallons per EDG to be operable. The TS bases states that LO stored in the onsite warehouse can be credited towards achieving the required inventory. PBAPS performs a monthly verification of EDG lubrication oil to satisfy their TS requirement. The inspectors independently walked down the additional identified that the LO may become unavailable during a natural phenomena event.
The EDGs are part of the standby safety power supply system. PBAPS 8.5.2.4, Class I structure, and located such that the equipment is protected against other natural hermore, UFSAR , in part, capable of operating continuously for a period of seven days without any offsite Class I structures and are protected against other alternating current power supply design conforms to the intent of Institute of Electrical and Electronics Engineers (IEEE) Criteria for Class 1E Electrical Systems for Nuclear Power Genethe standby power supply shall consist of all components from the stored energy to the connection to the distribution systems supply breaker (e.g., generators and excitation equipment; all auxiliary systems and appurtenances.) This standard was subsequently approved as IEEE Standard 308-IEEE Standard Criteria for Class 1E Electric contains an identical description of a standby power supply. The IEEE standard also lists design basis events in Section 2 and in Table 1 to include the natural phenomena (i.e., seismic, flood, tornado, etc.) to which the Class 1E Electric Systems must remain functional under the conditions produced by the design basis events.
The inspectors questioned whether the LO stored in the warehouse was adequately protected and would remain available for replenishment into the EDG system following natural phenomena. The inspectors questioned how PBAPS ensured the integrity of the LO barrels to maintain the LO free from containments that might be introduced during a flood, and to prevent loss of the oil if the containers were damaged during a seismic event or tornado. The inspectors also questioned the accessibility of the barrels, and the feasibility of transporting the barrels from the warehouse to the EDG building during natural phenomena. The inspectors identified that since the warehouse was not a seismic Class I structure, there is not reasonable assurance that the LO would be available for replenishment following a seismic event. and seismic event procedures and found no instructions or preparations to relocate the required LO barrels in the event of natural phenomena. No additional design documentation was identified approving the warehouse as an acceptable storage location. As a result, PBAPS entered the issue into the CAP as IR 02603369 and took immediate corrective actions to relocate the LO reserve inventory from the warehouse to radwaste building, which is listed in the UFSAR Appendix C.1.2 as a seismic Class I structure. PBAPS specified a corrective action in IR 02603369 to evaluate a long term storage location and to enhance their severe weather and natural phenomena procedures.
Analysis.
-related function of the EDG lubrication system was not susceptible to natural phenomena was a performance deficiency (PD). Specifically, barrels of LO for makeup to the EDGs credited towards the TS 3.8.3 requirement of 350 gallons on site were stored in a warehouse that is not a seismic Class I structure and would not be protected from natural phenomena specified This PD was considered more than minor because it is associated with the Protection Against External Factors Attribute of the Reactor Safety Mitigating Systems cornerstone, ensuring reliability and capability of systems that respond to initiating events to prevent undesirable consequences (i.e., core damage).
The inspectors evaluated the significance of this finding using IMC 0609 Appendix A, SDP The inspectors determined that this finding was of very low safety significance (Green) because the finding is a design deficiency which did not result in an actual loss of functionality of the EDGs.
This finding did not have a cross-cutting aspect because the most significant contributor of the PD occurred during the 1994 conversion to ITS and, thus, was not reflective of current plant performance.
engineering change request (ECR) process would evaluate for natural phenomena considerations such as seismic, tornado, flood, etc.
Enforcement.
, in part, that measures shall be established to assure that applicable regulatory requirements and the design basis as specified in the license are correctly translated into specifications, drawings, procedures, and instructions, and that measures shall also be established for the selection and review for suitability of application of materials, parts, equipment, and processes that are essential to the safety-related functions of the SSCs. Contrary to the above, PBAPS did not establish measures to review for suitability of materials and processes that are essential to the safety-related functions of SSCs. Specifically, PBAPS did not withstand the effects of natural phenomena. Because this finding is of very low safety significance, and PBAPS has entered it into their CAP (IR 02603369), this violation is being treated as an NCV, consistent with section 2.3.2a Policy. (NCV 05000277/278/2015004-01, Failure to Ensure Design Basis of EDG Lubrication System) Cornerstone: Emergency Preparedness
1EP6 Drill Evaluation
Emergency Preparedness (EP) Drill/Simulator Evaluation/Observation
a. Inspection Scope
The inspectors evaluated the shift manager\during a licensed operator annual requalification training scenario on November 9, 2015. 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 Radiation Safety (OS)
2RS1 Radiological Hazard Assessment and Exposure Controls
a. Inspection Scope
he inspectors reviewed performance in assessing and controlling radiological hazards in the workplace. The inspectors used the requirements contained in 10 CFR 20, TSs, applicable Regulatory Guides (RGs), and the procedures required by TSs as criteria for determining compliance.
Inspection Planning
The inspectors reviewed the performance indicators for the occupational exposure cornerstone, radiation protection (RP) program audits, and reports of operational occurrences in occupational radiation safety since the last inspection.
Radiological Hazard Assessment The inspectors reviewed recent plant radiation surveys and any changes to plant operations since the last inspection to identify any new radiological hazards for onsite workers or members of the public. Contamination and Radioactive Material Control The inspectors observed themonitoring of potentially contaminated material leaving the radiological control area and inspected the methods and radiation monitoring instrumentation used for control, survey, and release of that material. The inspectors selected several sealed sources from inventory records and assessed whether the sources were accounted for and were tested for loose surface contamination. The inspectors evaluated whether any recent transactions involving nationally tracked sources were reported in accordance with requirements. Radiological Hazards Control and Work Coverage The inspectors evaluated in-plant radiological conditions and performed independent radiation measurements during facility walk-downs and observation of radiological work activities. The inspectors assessed whether posted surveys, radiation work permits (RWPs), worker radiological briefings, the use of continuous air monitoring and dosimetry monitoring were consistent with the present conditions. The inspectors examined the control of highly activated or contaminated materials stored within the spent fuel pools and the posting and physical controls for selected high radiation areas (HRAs), locked high radiation areas (LHRAs) and very high radiation areas (VHRA) to verify conformance with the occupational exposure control effectiveness performance indicator. Risk-Significant HRA and VHRA Controls The inspectors reviewed the controls and procedures for HRAs, VHRAs, and radiological transient areas in the plant.
Problem Identification and Resolution The inspectors evaluated whether problems associated with radiation monitoring and exposure control were identified at an appropriate threshold and properly addressed in the CAP.
b. Findings
No findings were identified.
2RS2 Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls
a. Inspection Scope
he inspectors assessed performance with respect to maintaining occupational individual and collective radiation exposures ALARA. The inspectors used the requirements contained in 10 CFR 20, applicable RGs, TSs, and procedures required by TSs as criteria for determining compliance.
Inspection Planning
The inspectors conducted a review of collective dose history and trends; ongoing and planned radiological work activities; radiological source term history and trends; and ALARA dose estimating and tracking procedures. Radiological Work Planning The inspectors selected the following radiological work activities based on exposure significance for review: RWP PB-C-15-00823, Feed Water Heater Replacement (3AE003 & 3CE003) RWP PB-C-15-822, Unit 3 High Pressure Turbine Disassembly, 1000 mrad, Heavy Work, High Efficiency Particulate Air & Wet Surface RWP PB-C-15-00510, Drywell Main Steam SRV Activities RWP PB-C-1500513, Control Rod Drive Exchange, Effective Dose Equivalent Monitoring Required For each of these activities, the inspectors reviewed: ALARA work activity evaluations, exposure estimates, and exposure reduction requirements. Problem Identification and Resolution The inspectors evaluated whether problems associated with ALARA planning and controls were identified at an appropriate threshold and properly addressed in the CAP.
b. Findings
a.
b.
2RS5 Radiation Monitoring Instrumentation
a. Inspection Scope
During September 28 October 2, 2015, the inspectors reviewed performance in assuring the accuracy and operability of radiation monitoring instruments used to protect occupational workers and for effluent monitoring and analysis. The inspectors used the requirements in 10 CFR 20, 10 CFR 50, Appendix I; TSs; Offsite Dose Calculation Manual (ODCM); RGs; applicable industry standards; and procedures required by TSs as criteria for determining compliance. Inspection Planning The inspectors reviewed records of in-service survey instrumentation and procedures for instrument source checks and calibrations.
Walkdowns and Observations The inspectors conducted walk-downs of plant area radiation monitors, continuous air monitors and radioactive gaseous and liquid effluent monitoring systems. The inspectors reviewed the calibration and source check status of various portable radiation survey instruments and contamination detection monitors for personnel and equipment. Calibration and Testing Program For the following radiation detection instrumentation, the inspectors reviewed the current detector and electronic channel calibration, functional testing results and alarm set-points: portal monitors; personnel contamination monitors; small article monitors; portable survey instruments; area radiation monitors; electronic dosimetry; air samplers; and continuous air monitors. b.
2RS6 Radioactive Gaseous and Liquid Effluent Treatment
a. Inspection Scope
During September 28 October 2, 2015, the inspectors reviewed the treatment, monitoring, and control of radioactive gaseous and liquid effluents. The inspectors used the requirements in 10 CFR 20, 10 CFR 50, Appendix I; TS; ODCM; applicable industry standards; and procedures required by TSs as criteria for determining compliance. Groundwater Protection Initiative (GPI) Implementation The inspectors reviewed: groundwater monitoring results; changes to the GPI program since the last inspection; anomalous results or missed groundwater samples; leakage or spill events including entries made into the decommissioning files (10 CFR 50.75(g)); and evaluation of any positive groundwater sample results, including appropriate stakeholder notifications and effluent reporting requirements. b.
OTHER ACTIVITIES
4OA1 Performance Indicator (PI) Verification
.1 Mitigating Systems Performance Index
a. Inspection Scope
Index (MSPI) for the period of October 1, 2014 through September 30, 2015.
Unit 2 and Unit 3 HPCI (MS07) Unit 2 and Unit 3 RCIC (MS08) Unit 2 and Unit 3 RHR (MS09) Unit 2 and Unit 3 cooling water (MS10) To determine the accuracy of the PI data reported during those periods, the inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, 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.
b. Findings
No findings were identified.
4OA2 Problem Identification and Resolution
.1 Routine Review of Problem Identification and Resolution Activities
a. Inspection Scope
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. The inspectors also confirmed, on a sampling basis, that, as applicable, for identified defects and non-conformances, PBAPS performed an evaluation in accordance with 10 CFR Part 21.
b. Findings
No findings were identified.
.2 Annual Sample:
Trend of Leaks in the ESW and HPSW System Piping (1 sample)
a. Inspection Scope
The inspectors performed an in-corrective actions associated with CR ESW Pinhole Leak on Supply cifically, a through-wall leak developed on an ESW pipe fitting, which resulted in both subsystems of ESW being declared inoperable and an entry into the action statement associated with TS 3.7.2. The inspectors also reviewed leaks and wall thinning conditions identified in the HPSW system. Both the ESW and HPSW systems use the Susquehanna River as a water source for providing cooling to various safety-related plant components. yses, extent of condition (EOC) reviews, compensatory actions, and the prioritization and appropriately identifying, characterizing, and correcting problems associated with the leak and whether the planned or completed corrective actions were appropriate. The CAP and the requirements of 10 CFR 50, Appendix B. The inspectors interviewed engineering personnel to discuss the results of the cause evaluation and to assess the effectiveness of the implemented corrective actions. The inspectors also conducted walkdowns of the accessible portions of the ESW and HPSW systems to observe the general material conditions of the piping and associated components.
b. Findings and Observations
No findings were identified.
Exelon staff determined the apparent cause of the emergency service water (ESW) elbow leak was due to under deposit pitting corrosion and microbiologically influenced corrosion in raw water (i.e., river water) piping, which was increased by flow effects in this particular location. Specifically, deposits formed on the inside of the pipe from silt and microbiological organisms associated with the untreated river water that led to isolated pitting corrosion under the deposits and subsequently a pinhole leak. For the ESW elbow leak, Exelon staff determined that there was one contributing cause due to inadequate understanding of failure consequence and probability, which resulted in a lower examination priority. The inspectors concluded that Exelon staff conducted an appropriate review to identify the likely causes of the piping leak. The inspectors also concluded that Exelon staff identified the EOC, which included all safety-related raw water piping in Peach Bottom Units 2 and 3. Immediate corrective actions included an evaluation of the component for operability and structural integrity, scheduling for replacement of the leaking component, and routine monitoring for any changes in leakage. The inspectors noted that Exelon utilized ASME Code Case N-513-3 to evaluate the leak, which allows temporary acceptance and operation of the component until replacement at the next RFO. Exelon staff was required to submit a relief request to the NRC because Code Case N-513-3 is limited to the evaluation of piping and does not include elbows, fittings, or other non-pipe components. Exelon staff implemented further corrective actions, which included a review of the raw water piping database to address the risk ranking factors and consequences; revision of ER-AA-5400- to include additional guidance on risk ranking of piping with potential integrity threats; evaluation of corrosion rates based on results of this leak and EOC inspections; and a review of other elbows and fittings most susceptible to integrity concerns.
The inspecsample of pipe locations currently being monitored for wall thickness, to verify that Exelon staff were adequately tracking and prioritizing pipes for inspection and replacement. The inspectors noted that the raw water corrosion engineer utilized a supplemental database, which incorporated additional parameters for establishing corrosion rates, estimating remaining life, and scheduling future inspections. The inspectors also reviewed another Peach Bottom specific tool that used risk ranking for large sections of system piping rather than individual pipe locations in order to prioritize vulnerable sections of piping for future replacement. In addition, the inspectors reviewed currently ongoing and planned raw water piping projects to verify that Exelon staff were proactively mitigating piping integrity issues. One recent project involved the replacement of high risk-based piping at the ESW pumps discharge. While there were no chemistry control corrective actions identified in the apparent cause evaluation, the inspectors noted that there is a planned project in the review process to evaluate potential combinations of chemistry controls and cleaning for internal pipe corrosion. The inspESW elbow leak as well as other related raw water issues was commensurate with the safety significance, was timely, and included appropriate compensatory actions. The inspectors concluded that completed and planned actions were reasonable to correct the problem and help prevent reoccurrence.
.3 Annual Sample:
Review of Unit 2 Torus Coating Defects (1 sample)
a. Inspection Scope
The inspectors reviewed corrective actions completed by Exelon staff as a consequence of CR ,R .report to identify, prioritize and resolve the causes of the coating defects, rust, and pitting. The inspectors also reviewed results of torus examinations on a sampling basis for the previous PBAPS Unit 2 RFOs back to 2006, and Unit 3 RFOs back to 2007. The inspectors determined if the completion of corrective actions was in a timely manner commensurate with the safety significance of the issue. The inspectors considered if any delays in implementation were justified based on the safety significance of the issue. The inspectors considered if any permanent corrective actions required significant time to implement and if interim corrective actions and/or compensatory actions were identified and implemented to minimize the problem and/or mitigate its effects until the permanent action could be implemented. The inspectors reviewed the actions taken to determine if the actions resulted in the correction of the identified problem. In the case of this condition, the inspectors determined if the corrective action taken would preclude repetition. Finally the inspectors reviewed operating experience to determine if it was adequately evaluated for applicability, and applicable lessons learned were communicated to appropriate organizations and implemented.
b. Findings and Observations
No findings were identified.
The corrective action of the coating defects and pinpoint rust in the torus belly band area, was to continue to monitor this area for further degradation. Exelon staff took into account operability, consideration of EOC and cause, generic implications, common cause, and previous occurrences. This corrective action was reviewed by the inspectors commensurate with the safety significance. The corrective action for the pit with a depth of 126 mils was to determine if the pit impacted operability and to repair and recoat the area. Exelon staff took into account the EOC by reviewing prior inspection reports for the area associated with the pit to determine if other pits, in the immediate area which had been repaired previously, could impact the integrity of the newly discovered pit. Exelon staff took into consideration generic implications, common cause, and previous occurrences. This corrective action was reviewed by the inspectors to determine if the classification and prioritization of the The inspectors interviewed station personnel involved in developing the monitoring and identification of contributing causes of the problem. The inspectors ascertained if the documented information was reported to appropriate levels of management. The inspectors reviewed the corrective action to determine if the corrective action was appropriately focused to correct the problem (and to address the root and contributing causes for significant conditions adverse to quality). The inspectors review determined Exelon staff established a defined threshold to assure that no pit would threaten the torus minimum wall thickness prior to the torus recoat activity. The threshold was sufficient to ensure that the torus pressure boundary remained acceptable. The inspectors determined the threshold included a corrosion allowance for all uncoated pits based on actual corrosion data and the planned recoat schedule. The inspectors determined that pits with depths exceeding the defined threshold were evaluated by Exelon engineering staff and were coated to assure no further degradation.
The inspectors determined the actions of monitoring, analysis, and recoating resulted in the correction of the identified problem. The inspectors determined the actions maintained the safety barrier integrity by assuring the torus wall thickness was above the design minimum requirement.
.4 Semi-Annual Trend Review (1 sample)
a. Inspection Scope
The inspectors performed a semi-annual review of site issues to identify trends that might indicate the existence of more significant safety concerns. As part of this review, the inspectors included repetitive or closely-related issues documented by PBAPS in trend reports, site PIs, priority work lists, system health reports, MR assessments, and maintenance or CAP backlogs. The inspectors also reviewed CAP database for the third and fourth quarters of 2015 to assess IRs written in various subject areas (equipment problems, human performance issues, etc.), as well as individual issues identified during the NRCs daily CR review (Section 4OA2.1). The inspectors reviewed the quarterly trend report for the third quarter of 2015, conducted under PI-AA-125-1005, Coding and Analysis Manual, Revision 0, 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 evaluated a sample of CRs generated over the course of the past two quarters by departments that provide input to the quarterly trend reports. The inspectors determined that, in most cases, the issues were appropriately evaluated by PBAPS staff for potential trends and resolved within the scope of the CAP. The inspectors did identify repeated occurrences regarding a lack of awareness in the travel path of check valve swing arms in safety-related systems which did or could have impacted system operability. The inspectors identified three occurrences where PBAPS obstructed the travel path of check valve swing arms identified in IRs 1680741, IR 2519751, and IR 2559874. PBAPS initiated IR 2574611 to document the inspectors concern and evaluate how to increase awareness of the travel path of safety-related check valve swing arms.
The inspectors also noted and discussed with PBAPS staff ongoing minor adverse trends in rigor and attention to detail in CAP products, including apparent cause evaluations and work group evaluations, and in configuration control with tasks However, the inspectors determined 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 operability problems.
4OA3 Follow-Up of Events and Notices of Enforcement Discretion
(Closed) Licensee Event Report (LER) 05000/277-2-15-001: Condition Prohibited by TS Due to Insufficient Remote Shutdown System Surveillance Testing The NRC determined on September 4, 2015, that insufficient surveillance requirement (SR) 3.3.3.2.1 testing was being performed for certain functions from the remote shutdown system (RSS) panel. Subsequently, during surveillance testing performed on September 16, 2015, operations personnel identified that the RCIC system steam admission valve (MO-2-13-131) would not open when operated from the RSS panel. Prompt troubleshooting performed on September 16, 2015, identified that a wire within the RSS panel associated with the logic for the MO-2-13-131 valve was not connected. This condition did not impact the normal operation of the MO-2-13-131 valve from the MCR, nor did it impact the automatic function of the MO-2-13-131 valve for licensed events. Only the manual open function of the valve from the RSS panel (located outside of the control room) was affected. The disconnected wire was re-landed and the MO-2-13-131 was verified to operate properly from the RSS panel. The cause of the event was previous insufficient RSS panel testing that did not detect this disconnected wire. Surveillance test procedures of the RSS panel functions have been upgraded. A Green NCV of TS 5.4.1a was identified and documented in the 2015003 inspection report (NCV 05000277/278/2015003-01, Incomplete Testing of Components from the Remote Shutdown Panel). This LER is closed.
4OA5 Other Activities Extended Power Uprate (EPU) Closure and Summary
a. Inspection Scope
On August 25, 2014, the NRC approved PBAPS License Amendments Nos. 293 and 296 for an approximately 12.4-percent EPU at Units 2 and 3 and issued the associated safety evaluation (ADAMS package ML122860201). The inspectors have observed and reviewed selected activities throughout the phased EPU implementation on both units. The inspectors have determined, based on a sample review of these activities and comparison of records and tests with the current licensing documents, that Exeloncommitments have been met regarding the PBAPS Unit 2 and Unit 3 EPU and that Exelon has fully implemented the EPUs within its approved implementation timelines.
As required by IP 71004, Power Uprate, all inspection sample requirements for the power uprate on Unit 2 and Unit 3 have been verified completed and recorded, consistent with the inspection plan. This entry provides a summary of all inspection samples associated with implementation of and as required by IP 71004. Inspection Sample Inspection Procedure (IP) Inspection Report Operator Simulator Scenario 71111.11, 71004 2014004 Operator Simulator Scenario 71111.11, 71004 2014005 EC/FAC 71004 2014005 Integrated Plant Evolutions 71004 2014005 Major Plant Tests 71111.20, 71004 2014005 CST Standpipe Modification 71111.17, 71004 2015002 Unit 2 HPSW Cross-tie Modification 71111.17, 71004 2015002 -tie Modification PMT 71111.19, 71004 2015004 MOV 71111.21, 71004 2015002 Unit 3 SBLC IST 71111.22, 71004 2015004
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
Quarterly Resident
Exit Meeting Summary
On January 15, 2016, the inspectors presented the inspection results to Mr. Pat Navin, Peach Bottom Plant Manager, and other members of the PBAPS 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 Company Personnel
- M. Massaro, Site Vice President
- P. Navin, Plant Manager
- J. Armstrong, Regulatory Assurance Manager
- G. Cilluffo, Raw Water Corrosion Engineer
- D. Dullum, Regulatory Assurance Engineer
- J. Hawkins, Exelon NDE Level III
- B. Holmes, Radiation Protection Manager
- H. McCroy, Radiation Protection Technical Support Manager
- B. Smith, (Acting) Senior Resident Inspector
- L. Micewski, (Acting) Senior Resident Inspector
- B. Reyes, (Acting) Senior Resident Inspector
- J. Patel, (Acting) Resident Inspector
- S. Barber, Senior Project Engineer
- N. Floyd, Reactor Inspector
- C. Graves, Health Physicist
- C. Highley, Project Engineer
- D. Kern, Senior Reactor Inspector
- M. Modes, Reactor Inspector
- D. Orr, Senior Reactor Inspector
- A. Turilin, Project Engineer
LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED
Opened/Closed
- 05000277/278/2015004-01 NCV Failure to Ensure Design Basis of Emergency Diesel Generator Lubrication System (Section 1R22)
Closed
- 05000277/2-15-001 LER Condition Prohibited by TS Due to Insufficient Remote Shutdown System Surveillance Testing (Section 4OA3)
LIST OF DOCUMENTS REVIEWED
Section 1R01: Adverse Weather
Procedures
- MA-PB-1003, Winter Readiness and Storm Response Guidelines for the Peach Bottom Facility, Revision 11
- OP-AA-108-111-1001, Severe Weather and Natural Disaster Guidelines, Revision 13
- OP-PB-108-111-1001, Preparation for Severe Weather, Revision 13
- RT-I-066-200-2, Heat Trace System Testing, Revision 11
- RT-O-040-620-2, Outbuilding HVAC and Outer Screen Inspection for Winter Operation, Revision 22
- RT-O-040-630-2, Winterizing Procedure, Revision 14
- WC-AA-107, Seasonal Readiness, Revision 16
- IRs
- 01610850
- 02481268
Miscellaneous
- Memo from M. Massaro to T. Dougherty, Certification of 2015-2016 PBAPS Winter Readiness, dated October 29, 2015
Section 1R04: Equipment Alignment
Procedures
- ARC-325 30C203B D-1, B RHR Pump Auto Start
- SO 13.1.B-3 COL, RCIC System Control Board Lineup, Revision 3 SI3M-2-SRV-XXMM, Instrument Check of SRV Position Indicators, Revision 8 SI3T-2-SRV-XXF2, Channel Functional Check of MSRV MSSV Thermocouples, Revision 2
Section 1R05: Fire Protection
Procedures
- CC-AA-201, Plant Barrier Control Program, Revision 2
- CC-AA-209, Fire Protection Program Configuration Change Review, Revision 5
- CC-AA-211, Fire Protection Program, Revision 6
- LS-AA-128, Regulatory Review of Proposed Changes to the Approved Fire Protection Program,
- Revision 2
- OP-AA-201-009, Control of Transient Combustible Material, Revision 17
- PF-12C, Unit 3 Recirculation Pump MG Set Room Pre-Fire Strategy Plan, Revision 7
- PF-117, Unit 3 Turbine Building, Emergency Battery Switchgear - Revision 10
- PF-78H, Turbine Building Common, Cable Spreading and Computer Rooms - Revision 9
- RT-O-57A-745-1, Balance of Plant and Miscellaneous Battery Monthly Check, Revision 16
- RT-O-100-505-2, Emergency Operating Procedure Tool Inventory, Revision 39
Drawings
- Drawing No. E-1313, Sheet 47D, Lighting Symbol, Notes & Details, Revision 1 Drawing No. 6260-E-1069, Sheet 1, Lighting, Communications & Power Layout
- Control Room, Revision 18
ARs
- AR 951114951114: AR 2022234
Miscellaneous
Section 1R07: Heat Sink Performance
Procedures
- ER-AA-340-1002, Service Water HX Inspection Guide, Revision 6
- CRs 01619316
Miscellaneous
- 2nd Trimester, 2015 PBAPS
- GL 89-13 Program Health Report
- PM-0589, RHR HX Performance Evaluation, Revision 5 RHR System Periodic Review Meeting Notes dated March 27, 2015
- RT-O-010-660-2, RHR HX Performance Test, Performed February 12, 2015
- RT-X-010-661-2, RHR HX Performance Calculation Test, Performed March 25, 2015
WOs
- R0963795
Section 1R08: In-service Inspection
Procedures
- 100-RT-001, Radiographic Examination in Accordance with ASME Section V, Article 2,
- Revision 8 386HA480, GE Hitachi Nuclear Energy Written Practice for Certification of Nondestructive Test Personnel, Revision 26
- GEH-PDI-UT-5, PDI Generic Procedure for Straight Beam Ultrasonic Examination of Bolts and Studs, Revision 6.1
- GEH-UT-300, Procedure for Manual Examination of Reactor Vessel Assembly Welds, Revision 12
- GEH-UT-311, Procedure for Manual Examination of Nozzle Inner Radii and Bore, Revision 19
- MA-PB-793-001, Visual Examination of Containment Vessels and Internals, Revision 2
- ST-N-080-900-3, Visual Examinations of Drywell and Torus Surfaces, Revision 4
Drawings
- 6280-ISI-401, Sheet 4, ASME Section XI ISI Boundaries Drywell I.D. Roll-out and Penetrations, Revision 0
- CRs 01559490
- 02557950
- 02558014
- 02558524
WOs
- C0255830
- C0255936
- C0255941 R1208385
Miscellaneous
- April 29, 2015 Completed Procedure
- ST-N-080-900-3 with Attached ASME IWE/IWL Visual Exam NDE
- Reports, dated October 15, 2013
- ECR 11-00376, RHR Cross-Tie Modification for EPU - Unit 3 A/C Trains, Revision 6 Focused Area Self-Assessment for ISI Program, dated September 3, 2015 GE Customer Notification Form 004, dated September 26, 2015 GE Customer Notification Form 006, dated September 28, 2015 IHI Reactor Vessel NDE Project Plan, Revision 0 Multiple VT Data Reports for ASME IWE/IWL Drywell Interior and Exterior from Procedure
- MA-PB-793-001, dated October 2015 Owner's Activity Report for the 19th RFO for Unit 3, dated January 21, 2014 Owner's Activity Report for the 20th RFO for Unit 2, dated March 3, 2015 Peach Bottom ISI Program Plan for the 4th 10-Year Inspection Interval, Revision 4 Report
- September 27, 2015 Report
- 010705, UT Data Sheet for RPV Studs 47-92, dated September 23, 2015 RPV Stud Qualification for NDE Personnel, dated September 24, 2015 RT Data Sheet for Weld 10-2DC20-29, dated September 30, 2015 RT Data Sheet for Weld 10-2XC020-11, dated October 2, 2015 RT Data Sheet for Weld 10-2XC020-12, dated October 2, 2015 Weld Information Data Sheet for 10-2DC20-29, dated September 28, 2015 Weld Information Data Sheet for 10-2XC020-11 and -12, dated September 28, 2015 Weld Traveler 212824-TR-308 for 10-2DC20-29, dated September 28, 2015
- WPS-01-01-TS-200, Weld Procedure Specification for Manual GTAW/SMAW of P1 Metals, Revision 9
Section 1R11: Licensed Operator Requalification Program
Procedures
- OP-AA-101-115, Senior Management of the Operating Crews, Revision 4
Miscellaneous
- PSEG-0235R Scenario 1, Group 1/ATWS
- PSEG-0235R Scenario 2, Turbine Trip/ATWS Peach Bottom Unit 3 BOC Startup Checklists Peach Bottom Unit 2 BOC Startup Checklists
Section 1R12: Maintenance Effectiveness
Procedures
- ER-AA-200-1001, Equipment Classification, Revision 1
ARs
- 02459304
- CRs 02455787
- 02459304
- 02459304-05
Miscellaneous
- PI-AA-125-1003, Apparent Cause Investigation Report (Equipment), Revision 2
Section 1R13: Maintenance Risk Assessments and Emergent Work Control
Procedures
- OP-AA-108-117, Protected Equipment Program, Attachment 1
- Protected Equipment Work
- Approval Form September 25, 2015, B and D CS, Revision 4
Miscellaneous
- EGM 11-003, Revision 2, Memo to William Dean from Roy Zimmerman, dated
- December 13, 2013
WOs
- C0254584
Miscellaneous
- Paragon Risk Profiles, October 1, 2015
Section 1R15: Operability Evaluations
Procedures
- OP-AA-102-103, OWA Program, Revision 4
- ST-O-011-405-, Revision 12
- OP-AA-102-103, OWA Program, Revision 4
- 02574110
- CRs 02561427
- 02563769
- 02574110
WOs
- C0256242
Drawings
- LR-M-358, Standby Liquid Control System, Sheet 1, Revision 0 P&I Diagram, ESW and HPSW Systems
Miscellaneous
- OWA Board Meeting Minutes, dated March 19, 2014 OWA Board Meeting Minutes, dated April 29, 2014 OWA Board Meeting Minutes, dated June 17, 2014 OWA Board Meeting Minutes, dated October 1, 2014 OWA Board Meeting Minutes, dated December 30, 2014 OWA Board Meeting Minutes, dated March 26, 2015 OWA Board Meeting Minutes, dated June 26, 2015
Section 1R18: Plant Modifications
Procedures
- CC-AA-102, Design Input and Configuration Change Impact Screening, Revision 28
- CC-AA-103, Configuration Change Control for Permanent Physical Plant Changes, Revision 27
- CC-AA-104, Document Change Requests, Revision 16
- CRs 02577302
- 02577693
- 02579116
- 02581643
- 02581644
- 02581240
- 02582201
- Modifications ECR:
- PB 13-00338, Unit 3 Recirculation MG Replacement
- Outage Phase, Revisions 0, 1, 3, and 4 ECR:
- PB 13-00340, Unit 3 Reactor Recirculation MG Set Decommissioning, Revision 0 ECR:
- PB 13-00341, Unit 3 Replacement of Reactor Recirculation System MGs with ASDs (Pre-Outage P3R20 Work Scope), Revision 0, 1, 2, and 3 ECR:
- PB 14-00356, ASD Structure, Revisions 0, 1, and 2
- N-PB-ENG-CT-1502B, Recirculation Adjustable Speed Drives (ASD), Revision 0
- PLORT-1409C, Licensed Operator Training for ASD Modification to Unit 3 Reactor Recirculation System, Revision 0
- PSEG-0234R, ASD Operations Training Guide, Revision 0 Siemens Water-Cooled III, High Availability Variable Frequency Drive, Revision 0
Miscellaneous
- MAT
- PB 13-00338-1-3, Unit 3 Adjustable Speed Drive (ASD) Uncoupled Recirculation Pump Motor Modification Acceptance Test, Revision 0 MAT
- PB 13-00338-2-3, Unit 3 ASD Coupled Recirculation Pump Motor Modification Acceptance Test dated October 20, 2015 MAT
- PB 13-00338-3-3, Unit 3 ASD Power Ascension Modification Acceptance Test, Revision 0 MAT
- PB 13-00341-1-3, Unit 3 ASD Cooling Water Modification Acceptance Test dated September 24, 2015
Section 1R19: Post-Maintenance Testing
Procedures
- ST/LLRT 30.01A.02, MSIV LLRT, Revision 14 , Revision 14 ST/LLRT 30.23.08, LLRT HPCI Vacuum Relief Valves, Revision 6
- RT-O-013-240-3, RCIC Overspeed Trip Test Using Aux Steam, Revision 1
- ST-O-032-301-3, HPSW Pump, Valve and Flow Functional and Inservice Test, Revision 31
- IC-C-11-2009, Field Testing of Power Transformers, Revision 0
- MA-AA-716-004, Complex Troubleshooting Data Sheet A, Revision 12
- MA-AA-716-004, Support/Refute Method, Revision 13
- MA-AA-716-012, PMT, Revision 20
ARs
- C0256126
- R1271865
- R1122613
- A1930510 A1546929 A1484162
- A1049047
- A1678925
- A1600928 A1891126 A1975865
- 01171049
- 02600713
- CRs 02561049
- 02561375
- 02570399
- 02587931
- 025888888
- 025888889
- 02589442
- 02589443
- 02590036
- 02599822
WOs
- R1128367
- R1128369
- R1274711
- R1018560
- R1018560 R1018560
- R0901395
- C0172705
- R1056916
- R1249350
Miscellaneous
- RHR P3R20 Planning Punchlist, Revision 8, dated March 10, 2015
Section 1R20: Refueling Outage
Procedures
- OP-AA-108-108, Attachment 1, Engineering Department Start-Up Checklist, Revision 18
- OP-AA-108-108, Attachment 9, Emergency Exceptions Checklist, Revision 18
ARs
- A1930510 A1546929 A1484162 A1049047 A1678925 A1600928 A1891126 A1975865
- 02600713
- 01171049
- CRs 02494904
- 02561427
- 02600168
- 02599822
WOs
- R1274711
- R1018560
- R1018560
- R1018560
- C0172705
- R1056916
- R1249350
- R0901395
- C0172705
- R1056916
- R1249350
Section 1R22: Surveillance Testing
Procedures
- EP-AA-1007, Addendum 3, Revision 0
- MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD-000 Through 5 Motor Operated Valves, Revision 10
- MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD-000 Through 5 Motor Operated Valves, Revision 11
- PI-AA-120, Issue Identification and Screening Process, Revision 3
- SE-1 Bases,
- SE-1 Plant Shutdown from the Remote Shutdown Panel
- Bases, Revision 22
- SE-1 Procedure,
- SE-1 Plant Shutdown From the Remote Shutdown Panel
- Procedure,
- Revision 22
- SO 13.7.A-2, Recovery From RCIC System Isolation or Turbine Trip, Revision 14
- ST-O-033-750-2, ESW Pump Remote Shutdown Panel Test, Revision 0
- ST-O-052-412-2, E-2 Diesel Generator Fast Start and Full Load Test, Revision 23
- ST-O-052-202-2, E-2 Diesel Generator Slow Start and Full Load Test, Revision 21
- ST-O-003-901-2, CRD Pump Remote Shutdown Panel Test, Revision 0
- ST-O-003-901-3, CRD Pump Remote Shutdown Panel Test, Revision 0
- ST-O-011-405-3, Standby Liquid Control System B Loop Injection Test, Revision 12
- ST-O-013-201-2, RCIC Alternative Control Panel Test, and Remote Shutdown Panel Test,
- Revision 5
- ST-O-013-201-2, RCIC Alternative Control Panel Test, and Remote Shutdown Panel Test,
- Revision 6
- ST-O-013-201-3, RCIC Alternative Control Panel Test, and Remote Shutdown Panel Test,
- Revision 5
- ST-O-013-301-2, RCIC Pump, Valve, Flow and Unit Cooler Functional and In-service Test,
- Revision 45
- ST-O-013-750-3, Emergency Shutdown Control Panel Test, Revision 7
- ST-O-013-750-2, Emergency Shutdown Control Panel Test, Revision 8
- ST-O-013-750-2, Emergency Shutdown Control Panel Test, Revision 9
- ST-O-023-200-, Revision 17
ARs
- A1978308
- 02414219 A2012485 A2015148
- CRs 02012485
- 02413679
- 02414219
- 02526507
- 025500445
- 02551342
- 02551348
- 02556042
- 02556608
- 02556651
- 02556526
- 02555841
- 02558858
- 02556564
- 02575136
Drawings
- M-1-S-42, Electrical Schematic Diagram RCIC System, Revision 75
- SE-10, Alternative Shutdown, Revision 20 6280-M-365 6280-M-366
Miscellaneous
- Appendix A Surveillances Limitorque Technical Update 14-01, Issue Date: August 25, 2014 Remote Shutdown System 3.3.3.2, PBAPS Unit 3, Amendment No. 281 Remote Shutdown System B 3.3.3.2, PBAPS Unit 2, Revision No. 0
- Remote Shutdown System 3.3.3.2, General Electric BWR/4 STS, 3.3.3.2-1, Revision 4.0 Position Paper for Justifying Compliance with LCO 3.3.3.2, Remote Shutdown System Surveillance Requirement SR 3.3.3.2.1 (IR 2526507) Unit 2 Limiting Conditions for Operation, Surveillance Requirements, Amendment No. 184 TSCR 93-16, PBAPS Current TSs Comparison Document
- TS 3.6.1.3 TS 3.8.1
- STI-28, Shutdown From Outside the Control Room
- ARC-0AC097 B-6, Revision 6
Section 1EP6: Drill Evaluation
Procedures
- OP-AA-101-115, Senior Management of the Operating Crews, Revision 4
Miscellaneous
- PSEG-0235R Scenario 1, Group 1/ATWS
- PSEG-0235R Scenario 2, Turbine Trip/ATWS
- PB-C-15-00823, Feedwater Heater Replacement (3AE003 & 3CE003)
- Wet Surface RWP
- PB-C-15-00510, DW Main Steam SRV Activities RWP
- PB-C-1500513, CRD Exchange, EDE Monitoring Required
Section 2RS5: Radiation Monitoring Instrumentation
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
Section 2RS6: Radioactive Gaseous and Liquid Effluent Treatment
Procedures
- CY-AA-130-205-F-02, Tritium, Gross Alpha, and Gross Beta Sample Preparation for Scintillation Counting, Revision 2
- CY-AA-170-000, Radioactive Effluent and Environmental Monitoring Programs, Revision 6
- CY-AA-170-1000, Radiological Environmental Monitoring Program and Meteorological Program Implementation, Revision 8 ODCM, Revision 15
Section 4OA1: Performance Indicator Verification
Procedures
- ER-AA-2008, MSPI Monitoring and Margin Evaluation, Revision 4
- LS-AA-2200, MSPI Data Acquisition and Reporting, Revision 5
- LS-AA-2200, Reactor Core Isolation Data Sheets, October 2014
- September 2015, Revision 5, Attachment 3
- LS-AA-2200, High Pressure Injection Data Sheets, October 2014
- September 2015,
- Revision 5, Attachment 2
- CRs 02426670
- 02412767
- 02413412
- 02412748
- 02411606
- 02409746
Procedures
- ER-AA-5400, Underground (Buried) Piping and Raw Water Corrosion Program (UPRWCP) Guide, Revision 8
- ER-AA-5400-1001, Raw Water Corrosion Program Guide, Revision 8
- PI-AA-125-1005, Coding and Analysis Manual, Revision 0
Drawings
- 6280-M-315, Sheet 1, P&ID ESW and HPSW Systems, Revision 83 6280-M-315, Sheet 4, P&ID ESW and HPSW Systems, Revision 56
- CRs 01411997
- 01680741
- 01695675
- 02407173
- 02411498
- 02413128
- 02427541
- 02489386
- 02494904
- 02519751
- 02520612
- 02559874
- 02568856
- 02574611
Miscellaneous
- Apparent Cause Investigation Report titled "ESW Pinhole Leak on Supply Elbow to Unit 2 Ring Header" (AR 01695675), dated October 15, 2014 Apparent Cause Investigation Report Titled, "HPSW Pipe Below Minimum Required Thickness" (AR 01411997), dated September 27, 2012 PVP2014-28781, Piping Corrosion Rate & Remaining Life Basis: Commercializing
- Conservatism in First Time Inspections, Revision 0 Third and Fourth Quarter 2015 Station Trend Reports Technical Evaluation
- CC-AA-309-101, 2407173-2, Pit evaluation
- LER 05000/277-2-15-001:
- Condition Prohibited by TS Due to Insufficient Remote Shutdown System ST