IR 05000244/2012003
| ML12205A301 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/23/2012 |
| From: | Glenn Dentel Reactor Projects Branch 1 |
| To: | Joseph Pacher Constellation Energy Nuclear Group |
| References | |
| IR-12-003 | |
| Download: ML12205A301 (28) | |
Text
UNITED STATES July 23, 2012
SUBJECT:
R.E. GINNA NUCLEAR POWER PLANT - NRC INTEGRATED INSPECTION REPORT 05000244/2012003
Dear Mr. Pacher:
On June 30, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your R.E. Ginna Nuclear Power Plant. The enclosed inspection report documents the inspection results, which were discussed on July 17, 2012, with you and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings were identified.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Glenn T. Dentel, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket No. 50-244 License No. DPR-18
Enclosure:
Inspection Report No. 05000244/2012003 w/ Attachment: Supplementary Information
REGION I==
Docket No.: 50-244 License No.: DPR-18 Report No.: 05000244/2012003 Licensee: Constellation Energy Nuclear Group, LLC Facility: R.E. Ginna Nuclear Power Plant, LLC Location: Ontario, New York Dates: April 1 to June 30, 2012 Inspectors: N. Perry, Senior Resident Inspector D. Dodson, Resident Inspector K. Cronk, Project Engineer J. Furia, Senior Health Physicist P. Kaufman, Senior Reactor Inspector Approved by: Glenn T. Dentel, Chief Reactor Projects Branch 1 Division of Reactor Projects Enclosure
SUMMARY OF FINDINGS
IR 05000244/2012003; 04/01/2012 - 06/30/2012; R.E. Ginna Nuclear Power Plant, LLC (Ginna); Routine Integrated Inspection Report This report covered a three-month period of inspection by resident inspectors and announced inspections performed by regional inspectors. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4, dated December 2006.
No findings were identified.
REPORT DETAILS
Summary of Plant Status
R.E. Ginna Nuclear Power Plant, LLC (Ginna) began the inspection period operating at full rated thermal power and operated at full power for the entire period.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R01 Adverse Weather Protection (71111.01 - Two samples)
.1 Readiness for Seasonal Extreme Weather Conditions
a. Inspection Scope
The inspectors performed a review of Ginnas readiness for the onset of seasonal high temperatures. The review focused on the intermediate building (auxiliary feedwater (AFW) pumps and rod control cabinets) and the vital battery rooms. The inspectors reviewed the Updated Final Safety Analysis Report (UFSAR), technical specifications (TSs), control room logs, and the corrective action program (CAP) to determine what temperatures or other seasonal weather could challenge these systems, and to ensure Ginna personnel had adequately prepared for these challenges. The inspectors reviewed station procedures, including Ginnas 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 hot weather conditions. Documents reviewed for each section of this inspection report are listed in the Attachment.
b. Findings
No findings were identified.
.2 Summer Readiness of Offsite and Alternate Alternating Current (AC) Power Systems
a. Inspection Scope
The inspectors performed a review of plant features and procedures for the operation and continued availability of the offsite and alternate AC power system to evaluate readiness of the systems prior to seasonal high grid loading. The inspectors reviewed Ginnas procedures affecting these areas and the communications protocols between the transmission system operator and Ginna. This review focused on changes to the established program and material condition of the offsite and alternate AC power equipment. The inspectors assessed whether Ginna established and implemented appropriate procedures and protocols to monitor and maintain availability and reliability of both the offsite AC power system and the onsite alternate AC power system. The inspectors evaluated the material condition of the associated equipment by interviewing the responsible system manager, reviewing condition reports (CRs) and open work orders (WOs), and walking down portions of the offsite and AC power systems including the transformer yard.
b. Findings
No findings were identified.
1R04 Equipment Alignment
.1 Partial System Walkdowns (71111.04Q - Four samples)
a. Inspection Scope
The inspectors performed partial walkdowns of the following systems:
B emergency diesel generator (EDG) while the A EDG was out of service (OOS)on April 17, 2012 Service water (SW) system while the D SW pump was OOS for motor replacement on May 22, 2012 A spent fuel pool (SFP) cooling system while the B train was OOS on June 1, 2012 A EDG while the B EDG was OOS on June 18, 2012 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, CRs, and the impact of ongoing work activities on redundant trains of equipment in order to identify conditions that could have impacted system performance of their intended safety functions. The inspectors also performed field walkdowns of accessible portions of the systems to verify system components and support equipment were aligned correctly and were operable. The inspectors examined the material condition of the components and observed operating parameters of equipment to verify that there were no deficiencies.
The inspectors also reviewed whether Ginna 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 (71111.04S - One sample)
a. Inspection Scope
On May 25, 2012, the inspectors performed a complete system walkdown of accessible portions of the containment spray (CS) system to verify the existing equipment lineup was correct. The inspectors reviewed operating procedures, drawings, equipment lineup 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, hangar and support functionality, and operability of support systems. The inspectors performed field walkdowns of accessible portions of the systems to verify system components and support equipment were aligned correctly and operable. The inspectors examined the material condition of the components and observed operating parameters of equipment to verify that there were no deficiencies.
Additionally, the inspectors reviewed a sample of related CRs to ensure Ginna appropriately evaluated and resolved any deficiencies.
b. Findings
No findings were identified.
1R05 Fire Protection
Resident Inspector Quarterly Walkdowns (71111.05Q - Six samples)
a. Inspection Scope
The inspectors conducted tours of the areas listed below to assess the material condition and operational status of fire protection features. The inspectors verified that Ginna 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 OOS, degraded, or inoperable fire protection equipment, as applicable, in accordance with procedures.
A EDG room upon restoration of A EDG on April 19, 2012 Relay room with suppression system OOS on May 10, 2012 Transformer yard with suppression system OOS on May 10, 2012 Intermediate building main steam header floor on May 11, 2012 Intermediate building controlled side top floor on June 27, 2012 Standby AFW building on June 28, 2012
b. Findings
No findings were identified.
1R11 Licensed Operator Requalification Program and Licensed Operator Performance
(71111.11 - Two samples)
.1 Quarterly Review of Licensed Operator Requalification Testing and Training
a. Inspection Scope
The inspectors observed licensed operator simulator training on April 17, 2012, which included a failed level indicator, a natural gas leak in the protected area, and the failure of select components to automatically start as required. 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 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
a. Inspection Scope
The inspectors observed and reviewed operators placing normal letdown in service and removing excess letdown from service on May 2, 2012, and turbine-driven AFW (TDAFW) pump quarterly inservice testing (IST) and temporary power reduction to 99 percent on May 21, 2012. The inspectors observed pre-shift briefings and reactivity control briefings to verify that the briefings met the criteria specified in Ginna procedure CNG-OP-1.01-1000, Conduct of Operations, Revision 00600, and CNG-OP-3.01-1000, Reactivity Management, Revision 00700. Additionally, the inspectors observed test performance to verify that procedure use, crew communications, and coordination of activities between work groups similarly met established expectations and standards.
b. Findings
No findings were identified.
1R12 Maintenance Effectiveness (71111.12 - Two samples)
a. Inspection Scope
The inspectors reviewed the samples listed below to assess the effectiveness of maintenance activities on structure, system, and component (SSC) performance and reliability. The inspectors reviewed system health reports, CAP documents, and maintenance rule basis documents to ensure that Ginna 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 Ginna 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 Ginna staff was identifying and addressing common cause failures that occurred within and across maintenance rule system boundaries.
Turbine generator system (TGS) turbine lube oil piping failure on October 11, 2011 A component cooling water (CCW) pump motor replacement modification on June 13, 2012
b. Findings
No findings were identified.
1R13 Maintenance Risk Assessments and Emergent Work Control (71111.13 - Four samples)
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 Ginna 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 Ginna personnel performed risk assessments as required by 10 CFR 50.65(a)(4) and that the assessments were accurate and complete. When Ginna performed emergent work, the inspectors verified that operations personnel promptly assessed and managed plant risk.
The inspectors reviewed the scope of maintenance work and discussed the results of the assessment with the stations 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.
Planned maintenance on the A EDG on April 16, 2012 Elevated risk during emergent maintenance on the A EDG fuel oil transfer pump on April 24, 2012 Unplanned maintenance on air-operated valve 110A with the normal boration flow path OOS on April 25, 2012 Unplanned maintenance on the city water system causing it to be OOS on June 6, 2012
b. Findings
No findings were identified.
1R15 Operability Determinations and Functionality Assessments (71111.15 - Five samples)
a. Inspection Scope
The inspectors reviewed operability determinations for the following degraded or non-conforming conditions:
A EDG fuel oil transfer pump suction check valve failed to close on April 25, 2012 A EDG fuel oil transfer pump suction check valve failed to close on May 4, 2012, revision 1 A motor-driven AFW flow indicator reading below zero on May 14, 2012 TDAFW low oil trip setpoint too high on May 21, 2012 A EDG fuel oil transfer pump lowering trend in discharge pressure on June 28, 2012 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 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 Ginnas 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 Ginna. The inspectors determined, where appropriate, compliance with bounding limitations associated with the evaluations.
b. Findings
No findings were identified.
1R18 Plant Modifications (71111.18 - One sample)
Permanent Modifications
a. Inspection Scope
The inspectors evaluated a modification to the steam line radiation monitoring system (RMS) implemented by engineering change package (ECP) 11-001040, Upgrade Steam Line Radiation Monitors R-31 and R-32. The inspectors verified that the design bases, licensing bases, and performance capability of the affected system were not degraded by the modification. In addition, the inspectors reviewed modification documents associated with the upgrade and design change including replacement of the existing steam line radiation monitoring equipment and data acquisition module with new monitoring equipment consisting of detectors, local processing and display units, and a new main steam line radiation monitor panel. The inspectors also reviewed revisions to the emergency plan implementing procedures (EPIPs) and interviewed engineering personnel to ensure the procedures could be reasonably performed.
b. Findings
No findings were identified.
1R19 Post-Maintenance Testing (71111.19 - Four samples)
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.
C safety injection (SI) pump and valve planned maintenance on April 3, 2012 A EDG fuel oil transfer pump planned maintenance on April 18, 2012 Diesel fire pump battery replacement on May 9, 2012 A CCW pump motor replacement on June 13 and 14, 2012
b. Findings
No findings were identified.
1R22 Surveillance Testing (71111.22 - Five samples)
a. Inspection Scope
The inspectors observed performance of surveillance tests and/or reviewed test data of selected risk-significant SSCs to assess whether test results satisfied TSs, the UFSAR, and Ginna 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:
STP-O-16QT, AFW Turbine Pump - Quarterly, Revision 00700, Attachment 8, Governor Valve (V-9519E) Manual Stroking, on May 14, 2012 STP-O-16QT, AFW Turbine Pump - Quarterly, Revision 00700, on May 21, 2012 (IST)
STP-O-12.6B, Diesel Generator (D/G) Fuel Oil Transfer Pump B Test, Revision 00401, on May 30, 2012 (increased frequency test)
STP-O-12.2, EDG B, Revision 01001, on May 31, 2012 (IST)
STP-O-12.6A, D/G Fuel Oil Transfer Pump A Test, Revision 00500, on June 20, 2012 (increased frequency test)
b. Findings
No findings were identified.
Cornerstone: Emergency Preparedness
1EP6 Drill Evaluation (71114.06 - One sample)
a. Inspection Scope
The inspectors evaluated the conduct of a routine Ginna emergency drill on April 24, 2012, to identify any weaknesses and deficiencies in the classification, notification, and protective action recommendation development activities. The inspectors observed emergency response operations in the simulator and the technical support center (TSC)to determine whether the event classification, notifications, and protective action recommendations were performed in accordance with procedures. The inspectors also attended the station drill critique to compare inspector observations with those identified by Ginna staff in order to evaluate Ginnas critique and to verify whether Ginnas staff was properly identifying weaknesses and entering them into the CAP.
Additionally, the inspectors observed the annual test of the emergency sirens on May 12, 2012. The inspectors verified that deficiencies were entered into Ginnas CAP.
b. Findings
No findings were identified.
RADIATION SAFETY
Cornerstone: Public Radiation Safety and Occupational Radiation Safety
2RS8 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and
Transportation (71124.08 - One sample)
a. Inspection Scope
From April 16 to 20, 2012, the inspectors conducted the following activities to verify Ginna effectively implemented their programs for processing, handling, storage, and transportation of radioactive material. The inspectors used the requirements of 10 CFR Parts 20, 61, and 71; 10 CFR Part 50 Appendix A, Criterion 63, Monitoring Fuel and Waste Storage; and Ginnas procedures required by the TSs/process control program (PCP) as criteria for determining compliance.
The inspectors reviewed the solid radioactive waste system description in the UFSAR, the PCP, and the recent radiological effluent release report for information on the types, amounts, and processing of radioactive waste disposed.
The inspectors reviewed the scope of quality assurance (QA) audits since the last inspection.
Radioactive Material Storage The inspectors selected areas where containers of radioactive waste were stored and verified that the containers were labeled in accordance with 10 CFR 20.1904, Labeling Containers, or controlled in accordance with 10 CFR 20.1905, Exemptions to Labeling Requirements, as appropriate.
The inspectors verified that the radioactive materials storage areas were controlled and posted in accordance with the requirements of 10 CFR Part 20, Standards for Protection Against Radiation. For materials stored or used in the controlled or unrestricted areas, the inspectors verified that they were secured against unauthorized removal and controlled in accordance with 10 CFR 20.1801, Security of Stored Material, and 10 CFR 20.1802, Control of Material Not in Storage, as appropriate.
The inspectors verified that Ginna had established a process for monitoring the impact of long-term storage (e.g., buildup of any gases produced by waste decomposition, chemical reactions, container deformation, loss of container integrity, or re-release of free-flowing water) sufficient to identify potential unmonitored, unplanned releases, or nonconformance with waste disposal requirements. The inspectors selected containers of stored radioactive materials and verified that there were no signs of swelling, leakage, and deformation.
Radioactive Waste System Walkdown The inspectors selected liquid and solid radioactive waste processing systems and walked down accessible portions of systems to verify and assess that the current system configuration and operation agree with the descriptions in the UFSAR, offsite dose calculation manual, and PCP.
The inspectors selected radioactive waste processing equipment that was not operational and/or was abandoned in place and verified that Ginna had established administrative and/or physical controls to ensure that the equipment would not contribute to an unmonitored release path and/or affect operating systems or be a source of unnecessary personnel exposure. The inspectors verified that Ginna had reviewed the safety significance of systems and equipment abandoned in place in accordance with 10 CFR 50.59, Changes, Tests, and Experiments.
The inspectors reviewed the adequacy of any changes made to the radioactive waste processing systems since the last inspection. The inspectors verified that changes from what was described in the UFSAR were reviewed and documented in accordance with 10 CFR 50.59, as appropriate.
Waste Characterization and Classification The inspectors selected processes for transferring radioactive waste resin and/or sludge discharges into shipping/disposal containers. The inspectors verified that the waste stream mixing, sampling procedures, and methodology for waste concentration averaging were consistent with the PCP and provided representative samples of the waste product for the purposes of waste classification as described in 10 CFR 61.55, Waste Classification.
For those systems that provide tank recirculation, the inspectors verified that the tank recirculation procedure provided sufficient mixing.
The inspectors verified that Ginnas PCP correctly described the current methods and procedures for dewatering waste.
The inspectors selected radioactive waste streams and verified that Ginnas radiochemical sample analysis results were sufficient to support radioactive waste characterization as required by 10 CFR Part 61, Licensing Requirements for Land Disposal of Radioactive Waste. The inspectors verified that Ginnas use of scaling factors and calculations to account for difficult-to-measure radionuclides was technically sound and based on current 10 CFR Part 61 analysis.
For the waste streams selected above, the inspectors verified that changes to plant operational parameters were taken into account to maintain the validity of the waste stream composition data between the annual or biennial sample analysis update and verified that waste shipments continued to meet the requirements of 10 CFR Part 61.
The inspectors verified that Ginna had established and maintained an adequate QA program to ensure compliance with the waste classification and characterization requirements of 10 CFR 61.55 and 10 CFR 61.56, Waste Characteristics.
Shipment Preparation and Records The inspectors observed shipment packaging, surveying, labeling, marking, placarding, vehicle checks, emergency instructions, disposal manifest, shipping papers provided to the driver, and Ginnas verification of shipment readiness. The inspectors verified that the requirements of any applicable transport cask certificate of compliance had been met. The inspectors verified that the receiving licensee was authorized to receive the shipment packages.
The inspectors verified that the shippers were knowledgeable of the shipping regulations and that shipping personnel demonstrated adequate skills to accomplish the package preparation requirements for public transport with respect to Ginnas response to NRC Bulletin 79-19, Packaging of Low-Level Radioactive Waste for Transport and Burial, dated August 10, 1979, and 49 CFR Part 172, Hazardous Materials Table, Special Provisions, Hazardous Materials Communication, Emergency Response Information, Training Requirements, and Security Plans, Subpart H, Training. The inspectors verified that Ginnas training program provided training to personnel responsible for the conduct of radioactive waste processing and radioactive material shipment preparation activities.
The inspectors selected non-excepted package shipment records and verified that the shipping documents indicated the proper shipper name, emergency response information including a 24-hour contact telephone number, accurate curie content, volume of material, appropriate waste classification, transport index, and UN number.
The inspectors verified that the shipment placarding was consistent with the information in the shipping documentation.
Problem Identification and Resolution The inspectors verified that problems associated with radioactive waste processing, handling, storage, and transportation were being identified by Ginna at an appropriate threshold, were properly characterized, and were properly addressed for resolution in the CAP. The inspectors verified the appropriateness of the corrective actions for a selected sample of CRs that involved radioactive waste processing, handling, storage, and transportation.
The inspectors reviewed the results of selected audits performed since the last inspection of this program and evaluated the adequacy of Ginnas corrective actions for issues identified during those audits.
b. Findings
No findings were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator Verification
.1 Safety System Functional Failures (One sample)
a. Inspection Scope
The inspectors sampled Ginnas submittals for the Safety System Functional Failures performance indicator (PI) for the period of July 1, 2011, through March 31, 2012. To determine the accuracy of the PI data reported during those periods, inspectors used definitions and guidance contained in the Nuclear Energy Institute (NEI) Document 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 6, and NUREG-1022, Event Reporting Guidelines 10 CFR 50.72 and 10 CFR 50.73." The inspectors reviewed Ginnas operator narrative logs, operability assessments, CRs, event reports, and NRC integrated inspection reports to validate the accuracy of the submittals.
b. Findings
No findings were identified.
.2 Reactor Coolant System (RCS) Specific Activity and RCS Leak Rate (Two samples)
a. Inspection Scope
The inspectors reviewed Ginnas submittal for the RCS specific activity and RCS leak rate PIs for the period of April 1, 2011, through March 31, 2012. To determine the accuracy of the PI data reported during those periods, the inspectors used definitions and guidance contained in NEI Document 99-02. The inspectors also reviewed RCS sample analysis and control room logs of daily measurements for RCS leakage, and compared that information to the data reported by the PI. Additionally, the inspectors observed surveillance activities that determined the RCS identified leakage rate, and chemistry personnel taking and analyzing an RCS sample.
b. Findings
No findings were identified.
4OA2 Problem Identification and Resolution (71152 - One sample)
.1 Routine Review of Problem Identification and Resolution Activities
a. Inspection Scope
As required by Inspection Procedure 71152, Problem Identification and Resolution, the inspectors routinely reviewed issues during baseline inspection activities and plant status reviews to verify that Ginna entered issues into the CAP at an appropriate threshold, gave adequate attention to timely corrective actions, and identified and addressed adverse trends. In order to assist with the identification of repetitive equipment failures and specific human performance issues for follow-up, the inspectors performed a daily screening of items entered into the CAP and periodically attended CR screening meetings.
b. Findings
No findings were identified.
.2 Semi-Annual Trend Review
a. Inspection Scope
The inspectors performed a semi-annual review of site issues, as required by Inspection Procedure 71152, Problem Identification and Resolution, to identify trends that might indicate the existence of more significant safety issues. In this review, the inspectors included repetitive or closely related issues that may have been documented by Ginna outside of the CAP, such as trend reports, PIs, major equipment problem lists, and maintenance or CAP backlogs. The inspectors also reviewed Ginnas CAP database for the first and second quarters of 2012 to assess CRs 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 Ginnas quarterly trend presentation for the first quarter of 2012 conducted under CNG-CA-1.01-1007, Performance Improvement Program Trending and Analysis, Revision 00300, to verify that Ginna personnel were appropriately evaluating and trending adverse conditions in accordance with applicable procedures.
b. Findings and Observations
No findings were identified.
The inspectors evaluated a sample of issues and events that occurred over the course of the past 2 quarters to objectively determine whether issues were appropriately considered or ruled as emerging or adverse trends. The inspectors verified that these issues were addressed within the scope of the CAP or through department review and documentation in the quarterly trend presentation for overall assessment. For example, the inspectors noted that Ginna personnel had appropriately identified risk assessment model issues as a monitored trend with ongoing corrective actions to address this long-standing issue.
The inspectors also observed an apparent increase in the number of door seal deficiencies. The inspectors discussed this increase with Ginna staff who indicated that each door seal deficiency was unique and preventive maintenance was set up to address future issues; therefore, no trend CR was initiated or needed.
4OA3 Follow-Up of Events and Notices of Enforcement Discretion (71153 - One sample)
Plant Event
a. Inspection Scope
For the plant event listed below, the inspectors reviewed and/or observed plant parameters, reviewed personnel performance, and evaluated performance of mitigating systems. The inspectors communicated the plant event to appropriate regional personnel, and compared the event details with criteria contained in Inspection Manual Chapter 0309, Reactive Inspection Decision Basis for Reactors, for consideration of potential reactive inspection activities. As applicable, the inspectors verified that Ginna made appropriate emergency classification assessments and properly reported the event in accordance with 10 CFR Parts 50.72 and 50.73. The inspectors reviewed Ginnas follow-up actions related to the event to assure that Ginna implemented appropriate corrective actions commensurate with their safety significance.
Loss of offsite power circuit 767
b. Findings
No findings were identified.
4OA5 Other Activities
NRC Temporary Instruction (TI) 2515/182: Review of the Industry Initiative to Control Degradation of Underground Piping and Tanks, Phase 1
a. Inspection Scope
Ginnas buried piping and underground piping and tanks program was inspected in accordance with paragraphs 03.01.a through 03.01.c of TI 2515/182 and was found to meet all applicable aspects of NEI Document 09-14, Guideline for the Management of Underground Piping and Tank Integrity, Revision 1, as set forth in Table 1 of the TI.
b. Findings and Observations
No findings were identified. The status of TI 2515/182, Phase 1, is complete.
4OA6 Meetings, Including Exit
Exit Meeting On July 17, 2012, the inspectors presented the inspection results to Mr. Joseph Pacher, Vice President, and other members of the Ginna staff. The inspectors verified that no propriety information was retained by the inspectors or documented in this report.
ATTACHMENT:
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- J. Pacher Vice President, Ginna
- D. Bierbrauer Manager, Nuclear Safety and Security
- J. Bowers General Supervisor, Radiation Protection
E. Dean III Plant General Manager
- S. Doty Manager, Maintenance
- M. Geckle Manager, Training
- K. McLaughlin General Supervisor, Shift Operations
- T. Mogren Manager, Engineering Services
- T. Paglia Manager, Operations
- S. Preston Director, Performance Improvement Unit
- S. Snowden General Supervisor, Chemistry
- J. Wells General Supervisor, Engineering Programs
- S. Wihlen Manager, Integrated Work Management
LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED
Discussed
- 05000244/2515/182 TI Review of the Industry Initiative to Control Degradation of Underground Piping and Tanks, Phase 1 (Section 4OA5)