IR 05000334/2015004

IR 05000334/2015004 & 05000412/2015004 - Beaver Valley Power Station - Integrated Inspection Report (October - December 2015)

ML16088A388
Person / Time
Site:	Beaver Valley
Issue date:	03/29/2016
From:	Kennedy S R NRC/RGN-I/DRP/PB6
To:	Richey M FirstEnergy Nuclear Operating Co
KENNEDY, SR
References
IR 2015004
Download: ML16088A388 (35)

Text

March 29, 2016

Mr. Marty Richey Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station P. O. Box 4 Shippingport, PA 15077

SUBJECT: BEAVER VALLEY POWER STATION INTEGRATED INSPECTION REPORT 05000334/2015004 AND 05000412/2015004

Dear Mr. Richey:

On December 31, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Beaver Valley Power Station, Units 1 and 2. The enclosed inspection report documents the inspection results, which were discussed on January 27, 2016, with Mr. M. Richey, site vice president, and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. This report documents one finding of very low safety significance (Green). The finding involved a violation of NRC requirements. However, because of the very low safety significance, and because it has been entered into your corrective action program, the NRC is treating the finding as a non-cited violation, consistent with Section 2.3.2.a of the NRC Enforcement Policy. If you contest the non-cited violation 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 Beaver Valley Power Station. In addition, if you disagree with the cross-cutting aspect assigned to any finding, or a finding not associated with a regulatory requirement in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region I, and the NRC Resident Inspector at Beaver Valley Power Station.

M. Rickey -2- In accordance with Title 10 of the Code of Federal Regulations (CFR) 2.390 of the NRCs the Publicly Available Records component of thManagement 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/ Silas R. Kennedy, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos.: 50-334 and 50-412 License Nos.: DPR-66 and NPF-73

Enclosure:

Inspection Report 05000334/2015004 and 05000412/2015004

w/Attachment:

Supplementary Information cc w/encl: Distribution via ListServ

ML16088A388 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP NAME JKrafty/noncurrence via email SRK SShaffer/ SWS SKennedy/ SRK DATE 03/28 /16 03/28 /16 03/28 /16 1 Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION I Docket Nos.: 50-334 and 50-412 License Nos.: DPR-66 and NPF-73 Report No.: 05000334/2015004 and 05000412/2015004 Licensee: FirstEnergy Nuclear Operating Company (FENOC) Facility: Beaver Valley Power Station, Units 1 and 2 Location: Shippingport, PA 15077 Dates: October 1, 2015 to December 31, 2015 Inspectors: J. Krafty, Senior Resident Inspector B. Reyes, Resident Inspector T. Lamb, Acting Resident Inspector P. Kaufman, Senior Reactor Inspector R. Rolph, Health Physicist J. DeBoer, Emergency Preparedness Inspector H. Gray, Senior Reactor Inspector Approved By: Silas R. Kennedy, Chief Reactor Projects Branch 6 Division of Reactor Projects 2

SUMMARY

IR 05000334/2015004, 05000412/2015004; 10/01/215 12/31/2015; Beaver Valley Power Station, Units 1 and 2; Maintenance Effectiveness. This report covered a three-month period of inspection by resident inspectors and announced inspections performed by regional inspectors. Inspectors identified a finding of very low safety significance (Green) which was a non-cited violation (NCV). The significance of most findings is indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined , April 29, 2015. Cross-cutting aAspects Within Cross-4, 2014. All violations of NRC requirements are dispositioned February 4, 2015program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-

Cornerstone: Mitigating Systems

Green.

The inspectors identified an NCV of Title 10 of the Code of Federal Regulations (CFR) 50.65 auxiliary feedwater (AFW) system against licensee-established goals. Specifically, FENOC did not identify and properly account for a maintenance preventable functional failure (MPFF) of the turbine driven auxiliary feedwater (TDAFW) pump, which demonstrated that performance of the Unit 1 AFW system was not being effectively controlled through appropriate preventive entering this issue into their corrective action program, re-evaluating and classifying the TDAFW pump failure as a MPFF, performing a 10 CFR 50.65 (a)(1) evaluation of the Unit 1 AFW system, and placing the system in (a)(1) status. The performance deficiency was determined to be more-than-minor because it was associated with the Equipment Performance attribute of the Mitigating Systems cornerstone, and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Additionally, example 7.d from IMC 0612 Appendix E details that a performance deficiency is more than minor if equipment performance problems were such that effective control of performance through appropriate preventive maintenance under (a)(2) could not be demonstrated. This finding was determined to be of very low safety significance (Green) since it was not a deficiency affecting the design or qualification of a mitigating structure, system, or component (SSC), it did not represent the loss of a system and/or function, it did not represent an actual loss of function of at least a single train or two separate safety systems out-of-service for greater than its technical specifications allowed outage time, and it did not represent an actual loss of a non-technical specification equipment designated as high safety-greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This finding has a cross-cutting aspect in Human Performance, Avoid Complacency, because FENOC failed to consider the extent of condition and their causes following the failure of the Unit 1 TDAFW pump on January 6, 2014 [H.12]. (Section 1R12)

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REPORT DETAILS

Summary of Plant Status Unit 1 operated at or near 100 percent power for the entire inspection period.

Unit 2 began the inspection period shutdown in refueling outage 2R18. Following the completion of refueling and maintenance activities, operators commenced a reactor startup on October 29, 2015, and reached 100 percent power on November 2, 2015, and remained at or near 100 percent power for the remainder of the inspection period.

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R01 Adverse Weather Protection

Readiness for Seasonal Extreme Weather Conditions

a. Inspection Scope

The inspectors performed a review of readiness for the onset of seasonal cold temperatures. The review focused on the Unit 1 and Unit 2 intake structures and the equipment in the Unit 2 safeguards building. The inspectors reviewed the technical specifications, and the corrective action program to determine what temperatures or other seasonal weather could challenge these systems, and to ensure FENOC personnel had adequately prepared for these 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. Documents reviewed for each section of this inspection report are listed in the Attachment.

b. Findings

No findings were identified.

1R04 Equipment Alignment

.1 Partial System Walkdowns

a. Inspection Scope

The inspectors performed partial walkdowns of the following systems: Unit 2 No. 1 emergency diesel generator while the No. 2 emergency diesel generator was out of service for scheduled maintenance on October 9, 2015 Unit 2 recirculation spray system following the performance of a full-flow surveillance test on October 20, 2015 Unit 2 charging system following maintenance on thDecember 2, 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 Updated Final Safety Analysis Report (UFSAR), technical specifications, condition reports, 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 staff had properly identified equipment issues and entered them into the corrective action program for resolution with the appropriate significance characterization.

b. Findings

No findings were identified.

.2 Full System Walkdown

a. Inspection Scope

On October 19 through 23, 2015, the inspectors performed a complete system walkdown of accessible portions of the Unit 2 low head safety injection system to verify the existing equipment lineup was correct. The inspectors reviewed drawings and equipment line-up check-off lists to verify the system was aligned to perform its required safety functions. The inspectors also reviewed electrical power availability and hanger and support functionality. The inspectors performed field walkdowns of accessible portions of the systems to verify system components and support equipment were aligned correctly and operable. The inspectors examined the material condition of the components and observed operating parameters of equipment to verify that there were no deficiencies. Additionally, the inspectors reviewed system health reports and a sample of related condition reports and work orders to ensure FENOC 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 FENOC controlled combustible materials and ignition sources in accordance with administrative procedures. The inspectors verified that fire protection and suppression equipment was available for use as specified in the area pre-fire plan, and passive fire barriers were maintained in good material condition. The inspectors also verified that station personnel implemented compensatory measures for out of service, degraded, or inoperable fire protection equipment, as applicable, in accordance with procedures.

Unit 2 East Cable Vault, Fire Area CV-2, on October 26, 2015 Unit 2 Cable Tunnel Fan Room, Fire Area CT-1, on December 2, 2015

b. Findings

No findings were identified.

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

a. Inspection Scope

its readiness and availability to perform its safety functions. The inspectors reviewed the design basis for the component and verified commitments to NRC Generic Letter 89-13-Related Equipment. The inspectors reviewed the results of the recent inspection of the heat exchanger and compared it to a previous inspection in order to determine if there was a degrading trend. The inspectors discussed the results of the inspection with engineering staff and reviewed pictures of the as-found conditions. The inspectors verified that FENOC initiated appropriate corrective actions for identified deficiencies. The inspectors also verified that the number of tubes plugged within the heat exchanger did not exceed the maximum amount allowed.

b. Findings

No findings were identified.

1R08 In-service Inspection - Beaver Valley Unit 2

==

a. Inspection Scope

The inspectors conducted a review of FENOCs implementation of in-service inspection (ISI) program activities for monitoring degradation of the reactor coolant system (RCS) boundary, risk significant piping and components, and containment systems during the Beaver Valley Power Station (BVPS), Unit 2 refueling outage 2R18) The sample selection was based on the inspection procedure objectives and risk priority of those pressure retaining components in these systems where degradation would result in a significant increase in risk. The inspectors observed in-process non-destructive examinations (NDE), reviewed documentation, and interviewed FENOC personnel to verify that the NDE activities performed as part of the BVPS Unit 2 ISI program were being conducted, in accordance with the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI, 2001 Edition, 2003 Addenda.

NDE and Welding Activities (IMC Section 02.01) The inspectors performed observations of NDE and reviewed records of the NDE activities listed below: Ultrasonic test (UT) - pressurizer nozzle-to-vessel welds 2RCS*PRE21-N-10 and 2RCS*PRE21-N-12, RCS 2RCS-007-F03 valve to pipe weld, RCS safe-end to elbow weld 2RCS-007-F04 Visual inspection of Unit 2 containment liner coating; The inspectors reviewed a sample of NDE technician certifications and verified the inspections were performed in accordance with approved procedures and the results were reviewed and evaluated by a certified Level III NDE individual. The inspectors reviewed UT examination data records of RCS hot and cold leg safety injection system piping welds 2SIS-006-24-1 and 2SIS-006-15-1 conducted to implement an industry initiative in accordance with the MRP-Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch examinations were conducted in conformance with FENOC procedures. Repair/Replacement Consisting of Welding Activities The inspectors reviewed the welding activity and weld data sheets associated with replacement of 2-inch Kerotest globe valve BV-RCS-5 to verify that the welding and applicable NDE activities were performed in accordance with ASME Code requirements. Pressurized Water Reactor Reactor Pressure Vessel Upper Head Penetration Inspection Activities The inspectors observed portions of the remote bare metal visual examination (VT-2) of the exterior surface of the Unit 2 reactor pressure vessel upper head penetration to confirm appropriate inspection coverage was achieved and to verify that no boric acid leakage or wastage had been observed. The inspectors directly observed remotely portions of the Unit 2 reactor pressure vessel upper head penetration control rod drive mechanism (CRDM) nozzle J-groove weld UT examinations to verify that they were being performed in accordance with requirements of 10 CFR Part 50.55a(g)(6)(ii)(D) and ASME Boiler and Pressure Vessel Code Case N-729-Requirof the reactor vessel head pressure boundary.

The inspectors reviewed the recordable indications identified by UT of CRDM nozzle penetrations No. 37 and No. 53 J-groove welds on the Unit 2 reactor pressure vessel upper closure head during refueling outage 2R18 that had been accepted by evaluation for continued service. The inspectors verified that the dye-penetrant examinations confirmed that the indications were not surface connected.

Boric Acid Corrosion Control (BACC) Inspection Activities The inspectors reviewed the BACC program and implementing BVPS procedures, discussed the program with the boric acid program owner and sampled photographic and visual inspection records of boric acid observed on safety significant piping and components inside the containment structure during walk downs conducted by FENOC personnel to verify that boric acid leakage was being appropriately identified and non-conforming conditions of boric acid leaks were documented in the corrective action program with a focus on areas that could cause degradation of safety significant components. The inspectors reviewed a sample of boric acid evaluations to verify that they were properly dispositioned consistent with the requirements of the ASME Code and 10 CFR 50, Appendix B, Criterion XVI.

Steam Generator (S/G) Tube Inspection Activities The inspectors observed a sample of the BVPS S/G eddy current tube examinations to verify that they were performed in accordance with Unit 2 Technical Specification 5.5.5.2 and the Steam Generator Program and reviewed a sample of the indications identified in the S/G tubes to verify that they were consistent with the potential degradation mechanisms documented in the Beaver Valley Unit 2

==2R18 Steam Generator Degradation Assessment Report SG-SGMP-15-14, dated August 17, 2015. The inspectors reviewed the S/G tube eddy current test results to verify that no primary-to-secondary leakage occurred over the operating cycle, in-situ pressure testing was properly performed, and tubes which exhibited degradation and did not meet the acceptance criteria were properly plugged using the alternate repair criteria per Generic Letter 95--Based Repair Criteria for Westinghouse Steam Generator Tubes the S/G tube examination screening criteria was in accordance with the Electric Power Research Institute (EPRI) Steam Generator Guidelines and flaw sizing was in accordance with the EPRI examination technique specification sheet.

b. Findings

No findings were identified.

1R11 Licensed Operator Requalification Program

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.1 Quarterly Review of Licensed Operator Requalification Testing and Training

a. Inspection Scope

The inspectors observed licensed operator simulator training on November 19, 2015, which included a loss of an offsite source of electrical power, a letdown leak, spurious turbine trip causing a reactor trip, failure of select components to automatically start or open as required, and loss of heat sink. The inspectors evaluated operator performance during the simulated event and verified completion of risk significant operator actions, including the use of abnormal and emergency operating procedures. The inspectors assessed the clarity and effectiveness of communications, implementation of actions in response to alarms and degrading plant conditions, and the oversight and direction provided by the control room supervisor. The inspectors verified the accuracy and timeliness of the emergency classification made by the shift manager and the technical specification action statements entered by the shift manager. Additionally, the inspectors assessed the ability of the crew and training staff to identify and document crew performance problems.

b. Findings

No findings were identified.

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

a. Inspection Scope

The inspectors observed the draining of the Unit 2 RCS to six inches below the reactor vessel flange on October 1, 2015. The inspectors observed infrequently performed test or evolution briefing to verify that the briefing met the criteria specified in procedure NOBP-OP-0007, or EvolutiRevision 5. Additionally, the inspectors observed test performance to verify that procedure use and crew communications met established expectations and standards.

b. Findings

No findings were identified.

=

a. Inspection Scope

The inspectors reviewed the samples listed below to assess the effectiveness of maintenance activities on SSC performance and reliability. The inspectors reviewed system health reports, corrective action program documents, maintenance work orders, and maintenance rule basis documents to ensure that FENOC was identifying and properly evaluating performance problems within the scope of the maintenance rule.

For each sample selected, the inspectors verified that the SSC was properly scoped into the maintenance rule in accordance with 10 CFR 50.65 and verified that the (a)(2) performance criteria established by FENOC staff was reasonable. As applicable, for SSCs classified as (a)(1), the inspectors assessed the adequacy of goals and corrective actions to return these SSCs to (a)(2). Additionally, the inspectors ensured that FENOC staff was identifying and addressing common cause failures that occurred within and across maintenance rule system boundaries.

Unit 1 AFW system on November 22, 2015 Unit 1 and 2 periodic assessment of maintenance rule program on December 14, 2015

b. Findings

Introductionfailure to monitor the performance of the Unit 1 AFW system against licensee-established goals. Specifically, FENOC did not identify and properly account for an MPFF of TDAFW pump, which demonstrated that performance of the Unit 1 AFW system was not being effectively controlled through appropriate preventive maintenance.

Description.

On March 23, 2015, the inspectors were performing a routine review of potential discrepancy when a failure of the TDAFW pump was classified as a condition monitoring failure (CMF) rather than a MPFF. The TDAFW pump was started during the performance of a surveillance test on November 1, 2013, following a Unit 1 refueling outage. After approximately two minutes, the TDAFW pump was shutdown from the main control room due to excessive condensate leakage reported by the field operators. Condensate was drained from the steam lines and the TDAFW surveillance test was re-performed on November 2, 2013. The TDAFW pump was shutdown from the main control room, this time after one hour and 22 minutes due to excessive hunting of the governor observed in the field. Operations removed a clearance that they believed was the source of water intrusion into the steam lines. Again, on November 2, 2013, the surveillance test for the TDAFW pump was performed and the pump was declared operable after 18 minutes of operation. FENOC classified the failure of the TDAFW pump on November 2, 2013, as a CMF. Following a Unit 1 reactor trip on January 6, 2014, the TDAFW pump automatically tripped after one hour and 49 minutes of operation due to governor oscillations. FENOC launched an investigation to determine the cause of the TDAFW pump failure. The licensee determined that the cause of the TDAFW pump oscillations and subsequent failure was due to an improperly set governor needle valve. The needle valve was incorrectly adjusted during installation of a new TDAFW pump governor in the refueling outage just prior to the pump being declared operable on November 2, 2013. The TDAFW pump failure on January 6, 2014, was classified as a MPFF. The inspectors concluded that the TDAFW pump failure on November 2, 2013, should have been re-evaluated and classified as a MPFF rather than a CMF because the cause of the TDAFW pump failures, the improperly set governor needle valve, was present during the failures on November 2, 2013, and on January 6, 2014. The inspectors discussed this observation with FENOC engineering personnel on March 23, 2015.

-evaluated the TDAFW pump failure that occurred on November 2, 2013, and determined that the criteria and on September 21, 2015, FENOC concluded that the AFW system would be placed in (a)(1) status for a combination of TDAFW pump MPFFs, motor-driven AFW pump MPFFs, and CMFs. The inspectors concluded that FENOC should have evaluated the AFW system for (a)(1) status upon the second TDAFW pump failure occurring on January 6, 2014.

Analysis.

The inspectors determined that failure to identify that the performance of the Unit 1 AFW system was not being effectively controlled through appropriate preventive maintenance and failure to monitor the equipment against licensee-established goals in accordance with 10 CFR 50.65 was a performance deficiency that was within the capability of FENOC to foresee and correct and should have been prevented. The performance deficiency was determined to be more-than-minor in accordance with IMC associated with the Equipment Performance attribute of the Mitigating Systems cornerstone, and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, FENOC did not properly classify the November 2, 2013, failure of the TDAFW pump, which when properly classified, caused the maintenance rule performance criteria for the AFW system to be exceeded. As a result, the AFW system was evaluated and placed in 10 CFR 50.65 (a)(1) status for a combination of TDAFW pump MPFFs and motor-driven AFW pump MPFFs and CMFs. Additionally, example 7.d from IMC 0612 Appendix E, iciency is more than minor if equipment performance problems were such that effective control of performance through appropriate preventive maintenance under (a)(2) could not be demonstrated. In accordance with June 19, 2012, and Exhibit 2 of Process (SDP) for Findings At-, the inspectors determined that this finding is of very low safety significance (Green) since it was not a deficiency affecting the design or qualification of a mitigating SSC, it did not represent the loss of a system and/or function, it did not represent an actual loss of function of at least a single train or two separate safety systems out-of-service for greater than its technical specifications allowed outage time, and it did not represent an actual loss of a non-technical specification equipment designated as high safety-significant in accordance rogram for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This finding has a cross-cutting aspect in Human Performance, Avoid Complacency, because FENOC failed to consider the extent of the condition and their causes following the failure of the Unit 1 TDAFW pump on January 6, 2014 [H.12].

Enforcement.

10 CFR 50.65 (a)(1), requires, in part, that the holders of an operating license shall monitor the performance of SSCs within the scope of the rule as defined by 10 CFR 50.65 (b), against licensee-established goals, in a manner sufficient to provide reasonable assurance that such SSCs are capable of fulfilling their intended functions. 10 CFR 50.65 (a)(2) states, in part, that monitoring as specified in 10 CFR 50.65 (a)(1) is not required where it has been demonstrated that the performance of an SSC is being effectively controlled through appropriate preventive maintenance, such that the SSC remains capable of performing its intended function. Contrary to the above, from January 6, 2014 until September 21, 2015, FENOC failed to monitor the equipment against licensee-established goals when the performance of the Unit 1 AFW system had not been effectively controlled through appropriate preventive maintenance. Specifically, FENOC did not identify and properly account for a MPFF of the TDAFW pump occurring on November 2, 2013. issue into their corrective action program, re-evaluating and classifying the TDAFW pump failure as a MPFF, performing a 10 CFR 50.65 (a)(1) evaluation of the Unit 1 AFW system, and placing the system in (a)(1) status. Because this finding was of very low corrective action program as condition report (CR) 2016-00884, this violation is being treated as a NCV, consistent with Section 2.3.2 of the NRC Enforcement Policy. (NCV 05000334/2015004-01, Inadequate Maintenance Rule Monitoring of the Auxiliary Feedwater System)

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

Unit 2 yellow shutdown risk (decay heat removal) due to natural circulation not available on October 1, 2015 Unit 2 yellow shutdown risk (containment closure controls) due to supplemental leak collection and release system not available on October 12, 2015 Unit 1 yellow online risk due to alternate intake structure bay cleaning on November 23, 2015

b. Findings

No findings were identified.

1R15 Operability Determinations and Functionality Assessments

a. Inspection Scope

The inspectors reviewed operability determinations for the following degraded or non-conforming conditions: Unit 2 power operated relief valve (2RCS-PCV456) heat tracing non-functional on October 28, 2015 Unit 2 gas voids in emergency core cooling system piping on November 10, 2015 Unit 1 and 2 control room air in-leakage exceeded acceptance criteria on December 4, 2015 Unit 2 pressurizer power-operated relief valves (2RCS-PCV456 and 2RCS-PCV455D) lifting during surveillance testing on December 17, 2015 The inspectors selected these issues based on the risk significance of the associated components and systems. The inspectors evaluated the technical adequacy of the operability determinations to assess whether technical specification 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 technical specifications and UFSAR to 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 properly controlled by FENOC. The inspectors determined, where appropriate, compliance with bounding limitations associated with the evaluations.

b. Findings

No findings were identified.

1R18 Plant Modifications

Temporary Modifications

a. Inspection Scope

The inspectors reviewed the temporary modifications for cooling to the Unit 2 battery rooms 2-1, 2-2, 2-3, and 2-4 to determine whether the modifications affected the safety functions of systems that are important to safety. The inspectors reviewed 10 CFR 50.59 documentation and post-modification testing results, and conducted field walkdowns of the modifications to verify that the temporary modifications did not degrade the design bases, licensing bases, and performance capability of the affected systems.

b. Findings

No findings were identified.

1R19 Post-Maintenance Testing

a. Inspection Scope

The inspectors reviewed the post-maintenance tests for the maintenance activities listed below to verify that procedures and test activities 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.

Unit 2 No. 2 emergency diesel generator following planned maintenance on October 12, 2015 Unit 2 diverse and flexible coping strategies piping modifications to the service water system and primary plant demineralized water storage tank on October 14, 2015 and actuator replacement on October 26, 2015 erated relief valve, 2RCS*PCV456, following valve overhaul on October 30, 2015

b. Findings

No findings were identified.

1R20 Refueling and Other Outage Activities

a. Inspection Scope

Unit 2 maintenance and refueling outage 2R18, which was conducted September 26 through October 30, 2015. The inspectors reviewed development and implementation of outage plans and schedules to verify that risk, industry experience, previous site-specific problems, and defense-in-depth were considered. During the outage, the inspectors observed portions of the shutdown and cooldown processes and monitored controls associated with the following outage activities: Configuration management, including maintenance of defense-in-depth, commensurate with the outage plan for the key safety functions and compliance with the applicable technical specifications when taking equipment out of service Implementation of clearance activities and confirmation that tags were properly hung and that equipment was appropriately configured to safely support the associated work or testing Installation and configuration of reactor coolant pressure, level, and temperature instruments to provide accurate indication and instrument error accounting Status and configuration of electrical systems and switchyard activities to ensure that technical specifications were met Monitoring of decay heat removal operations Impact of outage work on the ability of the operators to operate the spent fuel pool cooling system Reactor water inventory controls, including flow paths, configurations, alternative means for inventory additions, and controls to prevent inventory loss Activities that could affect reactivity Maintenance of secondary containment as required by technical specifications Refueling activities, including fuel handling and fuel receipt inspections Fatigue management Tracking of startup prerequisites, walkdown of the primary containment to verify that debris had not been left which could block the emergency core cooling system suction strainers, and startup and ascension to full power operation Identification and resolution of problems related to refueling outage activities

b. Findings

No findings were identified.

1R22 Surveillance Testing

a. Inspection Scope

The inspectors observed performance of surveillance tests and/or reviewed test data of selected risk-significant SSCs to assess whether test results satisfied technical specifications, the UFSAR, and FENOC procedure requirements. The inspectors verified that test acceptance criteria were clear, tests demonstrated operational readiness and were consistent with design documentation, test instrumentation had current calibrations and the range and accuracy for the application, tests were performed as written, and applicable test prerequisites were satisfied. Upon test completion, the inspectors considered whether the test results supported that equipment was capable of performing the required safety functions. The inspectors reviewed the following surveillance tests: 2BVT 1.21.2, Trevitest Method for Main Steam Safety Valve Setpoint Check, Revision 12 on October 8, 2015 2BVT 1.47.5, Type C Leak Test (2SIS*MOV842), Revision 20 on December 16, 2015 (containment isolation valve)

b. Findings

No findings were identified. Cornerstone: Emergency Preparedness 1EP4 Emergency Action Level and Emergency Plan Changes (IP 71114.04 1 Sample)

a. Inspection Scope

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

b. Findings

No findings were identified

RADIATION SAFETY

Cornerstone:

Occupational and Public Radiation Safety

2RS3 In-Plant Airborne Radioactivity Control and Mitigation

a. Inspection Scope

The inspectors reviewed the control of in-plant airborne radioactivity through the use of engineering controls, respiratory protection devices, and self-contained breathing apparatus (SCBA) to verify airborne concentrations are being controlled consistent with as low as is reasonably achievable (ALARA) and that the use of respiratory protection does not pose an undue risk to the wearer. The inspectors reviewed operability and use of both permanent and temporary ventilation systems; and the adequacy of airborne radioactivity radiation monitoring in the plant based on location, sensitivity, and alarm setpoints. The inspectors reviewed the adequacy of FENOC use of respiratory protection devices in the plant to include applicable ALARA evaluations, respiratory protection device certification, respiratory equipment storage, air quality testing records, and individual qualification records. The inspectors reviewed the following: status and surveillance records for three SCBAs staged for use during emergencies, SCBA procedures and maintenance test records, procedures for refilling and transporting of SCBA air bottles, SCBA mask size availability, and the qualifications of personnel performing service and repair of this equipment.

b. Findings

No findings were identified.

2RS4 Occupational Dose Assessment

a. Inspection Scope

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

Internal Dosimetry The inspectors reviewed: internal dosimetry procedures; whole body counter measurement sensitivity and use, adequacy of the program for whole body count monitoring of plant radionuclides, adequacy of the program for dose assessments based on air sample monitoring and the use of respiratory protection, and internal dose assessments for any actual internal exposures.

Special Dosimetric Situations The inspectors reviewed: to the embryo/fetus; the dosimetry monitoring program for declared pregnant workers; external dose monitoring of workers in large dose rate gradient environments; and dose assessments performed since the last inspection that used multi-badging, skin dose or neutron dose assessments.

b. Findings

No findings were identified.

2RS7 Radiological Environmental Monitoring Program (REMP)

a. Inspection Scope

The inspectors reviewed the REMP to validate the effectiveness of the radioactive gaseous and liquid effluent release program. The inspectors reviewed or observed the following items in order to determine compliance. BVPS 2013 and 2014 annual radiological environmental operating reports REMP program audits Sample collection, monitoring, and dose measurement stations (e.g., thermoluminescent dosimeter, air monitoring, vegetation, milk) Calibration and maintenance records for air sample and dosimetry measurement equipment Environmental sampling of the effluent release pathways specified in the Offsite Dose Calculation Manual (ODCM) Meteorological tower instrument local and control room data readouts Meteorological instrument operability status and calibration results Missed and anomalous environmental samples reported in the annual radioactive environmental monitoring report Positive environmental sample results Groundwater monitoring program of selected potential leaking SSCs 10 CFR 50.75(g) records of leaks, spills, and remediation since the previous inspection Changes to the ODCM due to changes to the land use census, long-term meteorological conditions, and modifications to the environmental sample stations Environmental sample laboratory analysis results, and measurement detection sensitivities Results of the laboratory quality control program audit, and the inter-and intra-laboratory comparison program results

b. Findings

No findings were identified.

4OA1 Performance Indicator Verification

.1 Mitigating Systems Performance Index (4 samples)

a. Inspection Scope

The inspectors reviewed submittal of the Mitigating Systems Performance Index for the following systems for the period of October 1, 2014, through September 30, 2015: Unit 1 emergency alternating current (AC) power system Unit 2 emergency AC power system Unit 1 high pressure injection system Unit 2 high pressure injection System To determine the accuracy of the performance indicator data reported during those periods, the inspectors used definitions and guidance contained in nuclear energy institute (NEI) Document 99-7. The inspectors also reviewed condition reports, mitigating systems performance index derivation reports, event reports, and NRC integrated inspection reports to validate the accuracy of the submittals.

b. Findings

No findings were identified.

.2 Radiological Effluent Technical Specifications/ODCM Radiological Effluent Occurrences

(1 sample)

a. Inspection Scope

The inspectors reviewed submittals for the radiological effluent technical specifications/ODCM radiological effluent occurrences performance indicator for the 1st quarter 2014 through the 4th quarter 2014. To determine the accuracy of the performance indicator data reported during those periods, the inspectors used definitions and guidance contained in NEI Document 99- condition reports, public dose assessments, gaseous and liquid effluent summary data and the results of associated offsite dose calculations to validate the accuracy of the submittals.

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 FENOC entered issues into the corrective action program 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 corrective action program and periodically attended condition report screening meetings.

b. Findings

No findings were identified.

.2 Annual Sample:

Maintenance Rule Program Implementation Corrective Actions

a. Inspection Scope

The inspectors performed an in-depth review of apparent cause analysis and corrective actions associated with CR 2015-00267 for failure to adequately implement risk management actions (RMAs). implement a contingency plan resulted in an increase in the duration of an elevated risk condition. The inspectors assessed problem identification threshold, cause analyses, extent of condition reviews, compensatory actions, and the prioritization and timeliness of corrective actions to determine whether FENOC was appropriately identifying, characterizing, and correcting problems associated with this issue and whether the planned or completed corrective actions were appropriate. The inspectors compared the actions taken to the requirements of corrective action program and 10 CFR 50, Appendix B. In addition, the inspectors performed field walkdowns and interviewed engineering personnel to assess the effectiveness of the implemented corrective actions.

b. Findings and Observations

FENOC determined the apparent cause to be a failure of NOP-OP-1007, assign clear ownership and responsibility for completion of the RMAs. corrective actions included the preparation of a communication package addressing the RMAs and controls requirements of NOP-OP-1007 and discussion of the package with maintenance and construction, operations, and work management departments. Corrective action five included a revision of NOP-OP-1007 to define the process and ownership for identifying RMAs that need to be implemented and corrective actions six through eight included a discussion of the changes to the departments previously listed. Corrective actions five through eight were not performed and closed in June and July of 2015, when FENOC determined that station procedure 1/2-ADM-0804, On-Line Risk Assessment and Managementidentifying RMAs and concluded that changes to fleet procedure NOP-OP-1007 were not necessary. 1/2-ADM-0804 The following are examples that should be performed by the work groups (work centers) to reduce the duration of the work activityand lists several RMAs. The inspectors determined that the guidance in 1/2-ADM-0804 does not sufficiently address the implementation of RMAs. Specifically, 1/2-ADM-0804 does not identify who in the work group is responsible nor does the procedure establish a process for the implementation of RMAs.

The inspectors concluded that the corrective actions for CR 2015-00267 did not adequately address the apparent cause; however, a revision to NOP-OP-1007, effective December 15, 2015, was made outside of the corrective actions for the condition report. Changes included a requirement for the lead work group to develop a risk management plan, for yellow and orange risk activities, that has to be reviewed by the work week senior reactor operator and approved by the manager of site operations prior to the commencement of work. The inspectors concluded that the revision to NOP-OP-1007 adequately assigns ownership and responsibility for the completion of RMAs.

a.

b.

4OA6 Meetings, Including Exit

On January 27, 2016, the inspectors presented the inspection results to Mr. M. Richey, site vice president, and other members of the BVPS 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

Licensee Personnel

M. Richey Site Vice President E. Larson Site Vice President C. McFeaters Director, Site Operations

N. Adams Plant Operator G. Alberti Steam Generator Project M. Banko Environmental Supervisor G. Buck ISI/NDE, Level III Contractor

G. Cacciani Safety Analysis Engineer C. Casto Advance Nuclear Specialist E. Crosby Radiation Protection Manager T. DiLeo Supervisor, Fuel Handling

R. Dinello Environmental Field Specialist A. Dometrovich Regulatory Compliance J. Fontaine ALARA Supervisor J. Gallagher Maintenance Rule Coordinator E. Grabski Radiation Protection Technician (Trainee) D. Hardaway Radiation Protection Technician R. Hayward Design Engineer D. Heck Staff Engineer, Technical services

T. Heimel ISI/NDE, Level III Contractor

M. Jansto System Engineer D. Jones IST Engineer M. Kienzle System Engineer M. Manoleras Director, Engineering

J. Miller Fire Marshall T. Miller Fleet Access Authorization Specialist L. Musgrave Staff Nuclear Engineer, ISI

J. Ostrowski Heat Exchanger Program Engineer M. Ressler Design Engineer C. Sacha Supervisor Radiation Protection Services J. Saska Radiation Protection Technician (Trainee) S. Sawtschenko Emergency Preparedness Manager C. Scarpone Radiation Protection Technician P. Seidel Nuclear Specialist (Trainee) H. Tremblay Auxiliary Feedwater System Engineer E. Thomas Supervisor, Regulatory Compliance

D. Wacker Regulatory Compliance Z. Warchol Supervisor, Plant Engineering G. Woolsey Shift Manager

LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED

Opened/Closed

05000334/2015004-01 NCV Inadequate Maintenance Rule Monitoring of the Auxiliary Feedwater System (Section 1R12)

Section 1R01: Adverse Weather Protection

Procedures

1OST-45.11A, Cold Weather Protection Verification

Performed in September and October, Revisions 1 and 2 2OM-45D.3.C, Power Supply and Control Switch List, Revision 12 2OST-45.11A, Cold Weather Protection Verification

Performed in September and October, Revision 3

Section 1R04: Equipment Alignment

Procedures

2OM-11.3.B.1, Valve List

2SIS, Revision 16 2OM-11.3.C, Power Supply and Control Switch List, Revision 9 2OM-13.1.B, Summary Description, Revision 3 2OM-13.1.C, Major Components, Revision 4 2OM-13.1.D, Instrumentation and Control, Revision 4 2OM-13.3.B.2, Valve List

2RSS, Revision 8 2OM-13.3.C, Power Supply and Control Switch List, Revision 9 2OM-36.3.B.1, Valve List

2EDG, Revision 7 2OM-36.3.B.1, Valve List

2EDG, Revision 7

2OM-36.3.B.2, Valve List

2EGA, Revision 15

2OM-36.3.B.3, Valve List

2EGF, Revision 10

2OM-36.3.B.4, Valve List

2EGO, Revision 9

2OM-36.3.B.5, Valve List

2EGS, Revision 11

2OM-36.3.C.8, Power Supply and Control Switch List, Diesel Generator 2-1, Revision 12 2OM-7.3.B.1, Valve List

2CHS, Revision 33

Condition Reports

2012-17121

2014-07156

2015-12933

2015-14269 2013-04884

2014-18414

2015-13292

Drawings

RM-0411-001, Valve Oper No Diagram, Low/High Head Safety Injection, Revision 23

RM-0413-001, Valve Oper No Diagram, Recirculation Spray System, Revision 12

RM-0436-001, Valve Oper No Diagram Diesel Fuel Oil, Revision 7

RM-0436-002, Valve Oper No Diagram Diesel Air Intake, Exh & Vacuum, Revision 4

RM-0436-003, Valve Oper No Diagram Diesel Starting Air, Revision 20

RM-0436-004A, Valve Oper No Diagram Diesel Cooling System, Revision 12

RM-0436-005A, Valve Oper No Diagram Diesel Generator Lube Oil, Revision 7

Miscellaneous

ECP 14-0734-002, Remove the Temporary system that Added Fluid from 2CHS-TK21A/B to 2SIS-TK21B, Revision 3 Maintenance Rule System Basis Document, Unit 2, System 11, Revision 5 Unit 2 Safety Injection System Health Report 2015-1

Section 1R05: Fire Protection

Procedures

1/2-ADM-1906, Control of Transient Combustible and Flammable Materials, Revision 1 2OM-44A.1.B, Area Ventilation Systems - Control Area Description, Summary Description, Revision 1 2OM-44A.1.C, Area Ventilation Systems - Control Area Description, Major Components, Issue 4 Revision 0

Condition Reports

2015-16806

2015-16817

Drawings

10080-RM-444A-1, Valve Oper No Diagram Control Bldg Ventilation System, Revision 8

Miscellaneous

2701.620-000-026, Detailed Fire Modeling Report

Fire Compartment 2-CB-1, Revision B 2701.620-000-051, Fire Risk Evaluation of Instrument and Relay Room (2-CB-1), Revision A 2PFP-AXLB-773, Cable Tunnel Fan Room, Fire Area

CT-1, Revision 1 2PFP-MSCV-735, East Cable Vault, Fire Area

CV-2, Revision 3

Section 1R07: Heat Sink Performance

Work Order

200581440

Miscellaneous

1/2-ADM-2106.F01, Heat Exchanger Inspection Report, Revision 6

Section 1R08: In-service Inspection - Beaver Valley Unit 2

Procedures

1/2-ADM-2036, BVPS ASME XI Pressure Testing Program, Revision 3 1/2-ADM-2039, BVPS ISI Ten-Year Plans, Revision 15 1/2-ADM-2051, BVPS Control of NDE Calibration Standards, Revision 0 1/2-ADM-2096, Alloy 600/690 Management Program, Revision 13 1/2-ADM-2099, Primary Containment ISI Program, Revision 3

ISIE-ECP-2, Steam Generator Examination Program, Revision 23

NDE-GP-105, Evaluation of PSI/ISI Flaw Indications, Revision 10

NDE-VT-502, Leakage Examination Requirements, Revision 10

NDE-VT-510, Visual Inspection for Evidence of Boric Acid, Revision 17

NOBP-CC-5761, Conduct of Dissimilar Metal Weld Ultrasonic Examinations, Revision 0

NOP-CC-5710, ASME Section XI Inservice Inspection (ISI) Program, Revision 1

NOP-CC-5714, Review, Evaluation and Reporting of ISI or PSI NDE Data, Revision 0

NOP-ER-2001, Boric Acid Control Program, Revision 11 PCI Energy Services Procedure Specification 43

MN-GTAW/SMAW, Revision 8 WesDyne Procedure

WDI-SSP-1236, Reactor Vessel Head Penetration Remote Visual Inspection for Beaver Valley Unit 2, Revision 0 Wesdyne Procedure

WDI-SSP-1237, Liquid Penetrant Examination of CRDM Penetration Nozzle Weld Overlays at Beaver Valley, Revision 0 WesDyne Procedure

WDI-STD-1040, Procedure for Ultrasonic Examination of Reactor Vessel Head Penetrations, Revision 11 WesDyne Procedure

WDI-STD-1041, Reactor Vessel Head Penetration Ultrasonic Examination Analysis, Revision 11

NDE Records Liquid Penetrant Examination Report, Unit 2 Reactor Vessel Head CRDM J-Groove Weld Reports, CRDM Penetrations #37 and #53, dated October 12, 2015 UT Examination Report No.

UT-15-1076, Reactor Coolant SysInjectionWeld 2SIS-006-24-1, dated October 8, 2015 UT Examination Report No.

UT-15-1080, Reactor Coolant System

InjectionWeld 2SIS-006-15-1, dated October 8, 2015 UT Examination Report No.

UT-15-1087, Reactor Coolant System, Valve to Pipe Weld 2RCS-007-F03, dated October 8, 2015 UT Examination Report No.

UT-15-1089, Reactor Coolant System, Safe-End to Elbow Weld2RCS-007-F04, dated October 8, 2015 UT Examination Report No.

UT-15-1092, Pressurizer Nozzle-to-Vessel Weld 2RCS*PRE21-N-10, dated October 8, 2015

UT Examination Report No.

UT-15-1094, Pressurizer Nozzle-to-Vessel Weld 2RCS*PRE21-N-12, dated October 8, 2015 UT Report Data Sheet,

DMW-R18-CP02-037-01, Reactor Vessel Upper Head Penetration #37, dated October 13, 2015 UT Report Data Sheet,

DMW-R18-OH01-53-01, Reactor Vessel Upper Head Penetration #53, dated October 13, 2015

WDI-SSP-1236, Reactor Vessel Head Penetration Remote Visual Inspection for Beaver Valley Unit 2, Revision 0, dated October 9, 2015

Miscellaneous

Beaver Valley Unit 2 2R18 Steam Generator Degradation Assessment

SG-SGMP-15-14, dated August 17, 2015 EPRI Report,

IR-2015-640, Independent Evaluation of Beaver Valley Unit 2 Reactor Vessel Closure Head Penetrations 37 & 53, dated October 2015 FENOC Letter, BVPS Unit 2 Request for Relief Relating to 10 CFR Part 50.55a Alternative Examination for Reactor Vessel Safe-End Welds, March 11, 2013

Westinghouse Letter

LTR-PAFM-15-07, Engineering Assessment of Indication in Beaver Valley Unit 2, Penetrations 37 and 53, dated October 16, 2015

Condition Reports

2015-12034

2015-12682

2015-12842

2015-13347 2015-12656

2015-12695

2015-13345

Section 1R11: Licensed Operator Requalification Program

Procedures

2LOCT-FR.H.1.001, E-0 Reactor Trip or SI,

FR-H.1 Loss of Secondary Heat Sink,

ES-0.1 Reactor Trip Response, Revision 0 2OM-6.4.I, Draining the RCS for Refueling, Revision 27

Section 1R12: Maintenance Effectiveness

Procedures

NOP-ER-3004, FENOC Maintenance Rule Program, Revision 2

Condition Reports

2012-06833

2013-17723

2013-17800

2014-00177 2014-02358

2015-07158

2015-07271

2015-08401 2015-09612

2015-10184

2015-11285

2015-11854

Miscellaneous

1DBD-24B, Design Basis Document for Auxiliary Feedwater System, Revision 5 Periodic Assessment of Maintenance Rule Program, Beaver Valley Power Station, September 24, 2012 through April 18, 2014 Unit 1 System 24B Maintenance Rule System Basis Document, Revision 7

Section 1R13: Maintenance Risk Assessments and Emergent Work Control

Procedures

1/2-ADM-0804, On-Line Risk Assessment and Management, Revision 13

NOP-OP-1005-03, Beaver Valley Key Shutdown Defense-in-Depth Turnover Checklist, Revision 13

NOP-OP-1005-04, Key Shutdown Defense in Depth Function Status, Revision 7

NOP-OP-1007, Risk Management, Revision 21

Miscellaneous

Beaver Valley Key Shutdown Defense-in-Depth Turnover Checklist Defense-in-Depth Protected Equipment List, 10/12/2015 Weekly Maintenance Risk Summary for the Week of November 23, 2015, Revision 1

Section 1R15: Operability Determinations and Functionality Assessments

Procedures

2OM-6.4.Q, Isolation of a Power Operated Relief Valve, Revision 21 2OM-6.4.R, Restoring an Isolated Power Operated Relief Valve to Service, Revision 18 2OST-6.6, PORV Isolation Valve Test and Position Check, Revision 22 3BVT 1.44.05, Control Room Envelope Air In-Leakage Test, Revision 4 3BVT01.11.04, Void Monitoring, Revision 12

Condition Reports

2015-14539

2015-14668

2015-16299

2015-16435 2015-16499

2015-16557

2015-16779

2015-17132 2015-17162

Miscellaneous

10080-N-757, Beaver Valley Piping Void Determination, Revision 0 10080-UR(B)-487, Site Boundary, Control Room and Emergency Response Facility Doses Following a Loss-of-Coolant Accident based on Core Uprate, an Atmospheric Containment and Alternate Source Terms, Revision 1 2506.510-001-006, Operation and Maintenance Instructions for Solenoid Power Operated Relief Valve, Revision 4 BVPS Engineering

Memorandum

115614, Unit #2 PORV Block Valve Testing Results in PORV Cycling Under Certain Conditions, February 16, 1998

ERS-JTL-99-008, Safety Analysis of the Radiological Consequences of a Waste Gas System Rupture DBA at BVPS Unit 2, Control Room, EAB, and LPZ Doses, Revision 2

ERS-JTL-99-014, Safety Analysis of the Radiological Consequences of a Waste Gas System Rupture DBA at BVPS Unit 1, Control Room, EAB, and LPZ Doses, Revision 1

Section 1R18: Plant Modifications

Procedures

NOP-CC-2003, Engineering Changes, Revision 20

Miscellaneous

ECP 12-0180-000

Temporary Cooling for Unit 2 Battery Rooms 2-1, 2-3, 2-2, and 2-4, Revision 4

Unit 2 Area Ventilation Systems

Misc. System Health Report 2015-01

Section 1R19: Post-Maintenance Testing

Procedures

1/2CMP-75-MCB-1E, Testing of Westinghouse and Cutler Hammer molded Case Circuit Breakers, Revision 15 1BVT 2.30.1, River Water Pump (1WR-P-1A) Head Capacity Curve, Revision 17 1OST-30.2, Reactor Plant River Water Pump 1A Test, Revision 55 2OST-30.13A, Train A Service Water System Full Flow Test, Revision 38 2OST-6.8, Pressurizer PORV Stroke Test, Revision 18

Condition Reports

2015-13244

2015-14014

2015-14462 2015-14465

2015-14552

2015-14630

Maintenance Orders/Work Orders

200418384

200584749

200585204

200607740

200607741

200609878

200610169

Miscellaneous

ECP-11-0618-000, Unit 2 Service Water System Replacement Motor Operated Butterfly Valve

2SWS-MOV102A, Revision 9

ECP-11-0618-001, Unit 2 Service Water System Replacement Motor Operated Butterfly Valve

2SWS-MOV102A, Revision 4

Section 1R20: Refueling and Other Outage Activities

Procedures

1/2RP-2.7, Reactor Vessel Head Removal/Reactor Vessel Head Lift Rig Checkout, Revision 17 2OM-20.4.H, Draining the Refueling Cavity to the RWST, Revision 26 2OM-52.4.R.1.F, Station Shutdown from 100% Power to Mode 5, Revision 30 2OM-6.4.I, Draining the RCS for Refueling, Revision 27 2OST-47.2B, Containment Close Out Inspection, Revision 16 2RST-2.1, Initial Approach to Criticality after Refueling, Revision 15 2RST-2.2, Core Design Check Test, Revision 17

Condition Reports

2015-13255

2015-13256

2015-13413 2015-13439

2015-13440

2015-14522

Miscellaneous

2R18 Fatigue Assessments EmpCenter Work Schedules Unit 2 Reactor Operator, Instrument and Controls Technician and Fire Brigade Member, Unit Reactor Operator and Senior Reactor Operator

Section 1R22: Surveillance Testing

Procedures

2BVT 1.21.2, Trevitest Method for Main Steam Safety Valve Setpoint Check, Revision 12

Condition Reports

2015-14460

2015-14501

Section 1EP4: Emergency Action Level and Emergency Plan Changes

Emergency Plan Beaver Valley Emergency Preparedness Plan, Appendix B Revision 16 Beaver Valley Emergency Preparedness Plan, Appendix G Revision 28 Beaver Valley Emergency Preparedness Plan, Appendix G Revision 29 Beaver Valley Emergency Preparedness Plan, Section 1 Revision 24 Beaver Valley Emergency Preparedness Plan, Section 4 Revision 30 Beaver Valley Emergency Preparedness Plan, Section 6 Revision 31 Beaver Valley Emergency Preparedness Plan, Section 8 Revision 23 Beaver Valley Emergency Preparedness Plan/Implementing Procedures

Effective Index Revision 160

Procedures

1/2-EPP-I-2, Unusual Event, Revision 43 1/2-EPP-I-3, Alert, Revision 40 1/2-EPP-I-4, Site Area Emergency, Revision 40 1/2-EPP-I-5, General Emergency, Revision 41 1/2-EPP-IP-1.1, Notifications, Revision 51 1/2-EPP-IP-1.7, Emergency Response Organizations Teams, Revision 24 1/2-EPP-IP-2.6, Environmental Assessment and Dose Projection Controlling Procedure, Revision 51

1/2-EPP-IP-4.1, Offsite Protective Actions, Revision 31

EPP-I-1a, Recognition and Classification of Emergency Conditions, Revision 17

Section 2RS1: Radiological Hazard Assessment and Exposure Controls

Procedures

1/2-HPP-3.03.007, Transfer of Highly Radioactive Material from Plant Systems to Solid Waste, Revision 4 1/2-HPP-3.07.001, Contamination Survey Methods, Revision 7 1/2-HPP-3.07.002, Radiation Survey Methods, Revision 7

BVBP-RP-0016, Survey Requirements during Plant Transients, Revision 1

NOP-OP-4001, Radiation Protection Program, Revision 3

NOP-OP-4002, Conduct of Radiation Protection, Revision 5

NOP-OP-4101, Access Controls for Radiologically Controlled Areas, Revision 11

NOP-OP-4104, Job Coverage, Revision 6

NOP-OP-4107, Radiation Work Permit (RWP), Revision 14

NOP-OP-4114, Radiological Controls for Highly Radioactive and Irradiated Components of Materials, Revision 1

NOP-OP-4502, Control of Radioactive Material, Revision 3

NOP-OP-4601, Contamination Control Program, Revision 5

Condition Reports

2014-11720

2015-06389

2015-07641

2015-10204

2015-10410

2015-10416

Section 2RS2: Occupational

ALARA Planning and Controls

Procedures

NOP-OP-

Miscellaneous

-7-2015

Section 2RS3: In-plant Airborne Radioactivity Control and Mitigation

Procedures

1/2-HPP-

1/2-HPP--4 Continuous Air Monitor, Revision 9 1/2-HPP-Revision 3

NOP-OP-

NOP-OP-

Condition Reports

2015-07630

2015-07729

2015-09895

2015-10006

2015-11405

Section 2RS4: Occupational Dose Assessment

Procedures

NOP-OP-

NOP-OP-

Condition Reports

2015-06490

2015-08174

Section 2RS7: Radiological Environmental Monitoring Program

Procedures

1/2-ENV-02.01, Radiological Environmental Monitoring Program, Revision 14 1/2-ENV-03.01, Environmental Sampling, Revision 9 1/2-ENV-03.02, Maintenance and Calibration of Automatic Water Sampling Equipment, Revision 3 1/2-ENV-03.03, Maintenance and Calibration of

AVS-28A Environmental Sampler, Revision 2 1/2-ENV-03.04, Land Use Census, Revision 2 1/2-ODC-1.01, ODCM: Index, Matrix and History of ODCM Changes, Revision 21 1/2-ODC-2.01, ODCM: Liquid Effluents, Revision 15 1/2-ODC-2.02, ODCM: Gaseous Effluents, Revision 6 1/2-ODC-2.03, ODCM: Radiological Environmental Monitoring Program, Revision 6 1/2-ODC-2.04, ODCM: Information Related to 40

CFR 190, Revision 2 1/2-ODC-3.01, ODCM: Dispersion Calculation Procedure an Source Term Inputs, Revision 1 1/2-ODC-3.02, ODCM: Bases for ODCM Controls, Revision 3 1/2-ODC-3.03, ODCM: Controls for RETS and REMP Programs, Revision 13

Condition Reports

2013-00160

2013-00777

2013-03554

2013-05707 2013-06015

2013-09908

2013-10952

2013-12495 2013-15774

2014-00685

2014-11925

2014-15056

Miscellaneous

MIS-C-14-08-Beaver Valley Power Station Meteorological Program for January through December 31, 2014, Air Sampler Maintenance and Calibration Records Station # Air Sampler Pump Serial #

Date/Time 32

6127 022-33

April 15, 2013 / 0911 46.1

6121 022-33

April 12, 2013 / 1229 47

6118 022-33

April 12, 2013 / 1356 32

6127 022-33

October 21, 2013 / 0902 46.1

6121 022-33

October 21, 2013 / 1408 47

6125 022-33

October 16, 2013 / 1624 32

6127 022-33

April 14, 2014 / 0908 46.1

6121 022-33

April 9, 2014 / 1332 47

6118 022-33

April 9, 2014 / 1332 32

6127 022-33

October 13, 2014 / 0908 46.1

6121 022-33

October 13, 2014 / 0844 47

6118 022-33

October 17, 2014 / 0950

Section 4OA1: Performance Indicator Verification

Condition Reports

2014-15809

2015-00212

2015-00893

2015-05847

2015-11473

Miscellaneous

Mitigating System Performance Index Basis Document Beaver Valley Power Station Unit 1 Mitigating System Performance Index Basis Document Beaver Valley Power Station Unit 2 Unit 1 Chemical and Volume Control System Health Report 2015-1 Unit 1 Emergency Diesel Generators System Health Report 2015-1 Unit 2 Chemical and Volume Control System Health Report 2015-1 Unit 2 Emergency Diesel Generators System Health Report 2015-1

Section 4OA2: Problem Identification and Resolution

Procedures

NOP-LP-2001, Corrective Action Program, Revision 37

NOP-OP-1007, Risk Management, Revision 21

NOP-OP-1007, Risk Management, Revision 22

NOP-WM-0001, Work Management Process, Revision 9

Condition Reports

2013-09813

2014-02424

2014-10282

2014-10358 2014-12354

2015-00267

2015-01708

2015-04793 2015-05842

2015-07001

2015-07188

2015-08623 2015-08837

2015-13004

Maintenance Orders/Work Orders

200450273

200517968

Miscellaneous

BV-2015-0179, LOCT CRC Review of

CR-2015-04793, Revision 0

BV-2015-712,

CR-2015-04793 Increase Risk Awareness/Risk Perception, Revision 0

OTGC-201505OER_BV3, 2015 Cycle 5 Operating Experience Review, Revision 0

LIST OF ACRONYMS

AC alternating current

ADAMS Agencywide Documents Access and Management System

AFW auxiliary feedwater

ALARA as low as is reasonably achievable

ASME American Society of Mechanical Engineers

BACC boric acid corrosion control

BVPS Beaver Valley Power Station

CFR Code of Federal Regulations

CMF condition monitoring failure

CR condition report

CRDM control rod drive mechanism

EPRI Electric Power Research Institute

FENOC FirstEnergy Nuclear Operating Company

IMC Inspection Manual Chapter

ISI in-service inspection

MPFF maintenance preventable functional failure

NCV non-cited violation

NDE non-destructive examination

NEI Nuclear Energy Institute

NRC Nuclear Regulatory Commission

ODCM Offsite Dose Calculation Manual

ODSCC outside diameter stress corrosion cracking

RCS reactor coolant system

REMP radiological environmental monitoring program

RMA risk management actions S/G steam generator

SCBA self-contained breathing apparatus

SSC structure, system, or component

TDAFW turbine driven auxiliary feedwater

UFSAR Updated Final Safety Analysis Report

UT ultrasonic test VT visual test