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Tools Used to Collect, Screen, Communicate and Analyze Operating Experience (OpE) Data. Improving Nuclear Safety Through Operating Experience Feedback Cologne, Germany May 30, 2006. Mary Jane Ross-Lee, Chief Operating Experience Branch. NRC OpE Program Objectives.
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Tools Used to Collect, Screen, Communicate and Analyze Operating Experience (OpE) Data Improving Nuclear Safety Through Operating Experience Feedback Cologne, Germany May 30, 2006 Mary Jane Ross-Lee, Chief Operating Experience Branch
NRC OpE Program Objectives • OpE is collected, evaluated, communicated, and applied to support the NRC’s goal of ensuring safety • OpE is used to improve the effectiveness, efficiency, and realism of NRC decisions • Stakeholders are provided with timely, accurate, and balanced information
NRC Reactor OpE • Program supports regulatory decision-making in our core programs • Licensing • Oversight • Incident Response • Rulemaking • Physical Security • Based on inter-dependent model where all organizations work toward applying OpE
Reactor OpE Review Process • Current OpE Program launched January 2005 • Centralized screening organization • Various sources of OpE collected • Screening of domestic and international OpE in accordance with established guidelines • Evaluation of screened-in items by Clearinghouse team and technical staff • Communication with stakeholders • Analysis/trending of all OpE • Application of OpE lessons learned
Reactor OpE ProgramInput-Output Overview Informing Stakeholders International OpE Generic Communications Morning Reports OpE Briefings COMMunications Web Page Incident Reporting System (IRS) Internal Nuclear Event Scale (INES)* OpE Clearinghouse Collection Screening Communication Evaluation Application Influencing Agency programs Domestic OpE: Industry Daily Events Reports* Plant Status Reports* Licensee Event Reports* Part 21 Reports* Inspection Licensing Domestic OpE: NRC Taking Regulatory Actions Inspection Findings* Morning Reports* Preliminary Notifications* Regional Project Calls Studies/Trends Rulemaking Information Request Storage * - available to public
Reactor OpE Program - 2005 • Over 1000 specific OpE items screened • 127 OpE COMMunications to technical experts • 30 OpE issues evaluated and closed • 7 OpE senior management briefings • All daily reports evaluated for INES rating • 66 Generic Communications (e.g., IN, GL, RIS) issued • 30 technical groups formed to review OpE
International Activities • International Nuclear Event Scale (INES) • All daily Event Notifications (10 CFR 50.72s) rated with INES • Level 2 or higher is communicated internationally • 2 events submitted in 2005 • Incident Reporting System (IRS) • Relevant Generic Communications submitted to IRS • IRS reports are reviewed in screening process • 20 US reports submitted in 2005 out of 70 total
Information Technology Tools • OpE Information Gateway • Single web access point to multiple databases • Dataset assumptions and limitations explained • Improved OpE search capabilities • @Operating Experience Community • Web-based communication forum • Subscription notification to over 30 topical groups • Provides links to related documents • Searchable records
Technical Review Group (TRG) • Agency-wide initiative to supplement Clearinghouse screening • Clearinghouse processes over 1000 items • Technical experts have more specific knowledge • Identifies issues that were overlooked • 30 TRGs created covering various technical areas with members from key offices and regions • Groups consisted of: Pumps & Valves, Fuel, Electrical, Piping, etc.
What Does the TRG Review? • Each TRG reviews relevant OpE data sources specific to the technical discipline. • OpE data sources include: • OpE COMMs which are emailed to members and posted on the OpE Community Forum • Inspection Findings • Licensee Event Reports • International OpE • Part 21 reports • INPO SEE-IN documents
TRG Output • TRG reviews OpE in their area over the last 6 months • From the initial review, several issues were identified • 3 Generic Documents Initiated • Information Notice (IN) on diesel generator problems including corrosion issues and wear caused by non-lubricated starts • IN on emergency preparedness siren system failures caused by a single siren failure providing continuous feedback signal • IN on silt, biofouling and debris causing blockage and equipment failure • 2 High Priority Followups • Flow induced vibration problems • Reactor coolant pressure boundary degradation mechanisms • 12 Open Items
TRG Benefits • Previously unidentified issues or trends identified • NRC technical experts used for review • Increased the use of OpE in the technical groups and the regional offices • Minimal resources required for benefit gained
Accident Sequencer Precursor • Established 1979, in Office of Research • Staff reviews LERs to identify potential precursors • Three agency programs assess risk – ASP, SDP, M.D 8.3 • Challenges of ASP - timeliness for analysis, looking at graded approach
Upcoming OpE Activities • Developing international ties in the areas of new reactor construction • Improving OpE search capabilities
Publicly Available OpE • Reports Associated with Events (http://www.nrc.gov/reading-rm/doc-collections/event-status/) • Power Reactor Status • Event Notification Report • Morning Report • Part 21 Reports • Preliminary Notifications • Generic Communications (http://www.nrc.gov/reading-rm/doc-collections/gen-comm/index.html) • Bulletins • Generic Letters • Information Notices • Regulatory Issue Summaries
References (in ADAMS) http://www.nrc.gov/reading-rm/adams.html • Management Directive 8.7 (ML043570013) • MD 8.7 Handbook (ML043570032) • NRR Office Instruction LIC-401 (ML050130014) • Reactor Operating Experience Task Force Report (ML033350063) • Plan for Implementing Reactor Operating Experience Task Force Report (ML041180024)
Recent OpE Examples Quad Cities ERV Vibration Issues Palo Verde Shutdown Cooling Isolation Valve Vibration
Recent OpE Example 1 • Vibration-Induced Failure of Electromatic Relief Valves (ERVs) at Quad Cities • Quad Cities 1 and 2 • Generic Electric Boiling Water Reactors • Mark I containment • Commercial operation started in 1973 • Extended power uprate (EPU) of 17.8% (446 Mwt) approved in 2001
Event Summary – Unit 2 • December 30, 2005: Internal damage of the ERV actuator found; plant shutdown initiated • Significant wear and loose parts identified on remaining 3 actuators • January 14, 2006: Unit 2 shutdown for inspection of the actuator pivot plate bolts (due to Unit 1 issue)
Event Summary – Unit 1 • December 31, 2005: Unit 1 decreased to pre-EPU power due to Unit 2 issue • January 6, 2006: plant shutdown initiated • Three ERVs had unsuccessful stroke tests or inspection results • January 15, 2006; Unit 1 shutdown for inspection of the turnbuckle (Unit 2 had weld cracking)
As-found Conditionsof ERV Parts Actuator Plunger Post Plunger Roller
Safety Significance • Degraded capability for overpressure protection/depressurization • Preliminary risk assessment: Conditional Core Damage Probability = 2.7E-6 • Three Green Findings
NRC Response • Close monitoring by resident inspectors • Preliminary Notification - January 17, 2006 • Special Inspection - January 9 through February 7, 2006 • Internal communications of the event • Issue For Resolution: Screened-in for operating experience follow-up
Recent OpE Example 2 • Shutdown Cooling Isolation Valve Vibration at Palo Verde 1 • Palo Verde 1 • Combustion Engineering Pressurized Water Reactor • Commercial operation started in 1986
Event Summary • Vibration problem since 2001 • Worsened following steam generator replacement • December 2005: Vibration of Train A shutdown cooling suction line reached administrative limit • Plant reduced power to less then 35%
Event Summary cont. • The licensee has attempted several modifications to reduce the vibration, but none have been fully successful • added masses • added supports • added heating blankets • installed a flow distribution plate • Since March 17, 2006: Plant maintenance outage ongoing
Safety Significance • Degraded shutdown cooling train • Shutdown cooling system used for low pressure heat removal • Significant operational constraint
NRC Response • Close monitoring by resident inspectors • Internal communications of the event • Issue For Resolution: Screened-in for operating experience follow-up