Mary Jane Ross-Lee, ChiefOperating Experience Branch

Tools Used to Collect, Screen, Communicate and Analyze Operating Experience (OpE)

Data

Improving Nuclear Safety ThroughOperating Experience Feedback

Cologne, GermanyMay 30, 2006

May 30, 2006 2

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

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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

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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

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Reactor OpE ProgramInput-Output Overview

Collection

Screening

Communication

Evaluation

Application

Incident Reporting System(IRS)

Internal Nuclear Event Scale(INES)*

International OpE

Daily Events Reports*Plant Status Reports*

Licensee Event Reports*Part 21 Reports*

Domestic OpE: Industry

Inspection Findings*Morning Reports*

Preliminary Notifications*Regional Project Calls

Studies/Trends

Domestic OpE: NRC

OpE ClearinghouseGeneric Communications

Morning ReportsOpE Briefings

COMMunicationsWeb Page

Informing Stakeholders

InspectionLicensing

Influencing Agency programs

RulemakingInformation Request

Taking Regulatory Actions

Storage

* - available to public

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Overview of OpE Process – 4 Phases

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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

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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

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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

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OpE Community Posting

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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.

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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

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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

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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

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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

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ASP Search Results

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Upcoming OpE Activities

Developing international ties in the areas of new reactor construction

Improving OpE search capabilities

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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

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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

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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

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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)

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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)

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Shown installed in Drywell

Actuator

Pilot Valve

ERV

Electromatic Relief Valve

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As-found Conditionsof ERV Parts

Plunger

Actuator

Post Plunger Roller

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Safety Significance

Degraded capability for overpressure protection/depressurization

Preliminary risk assessment: Conditional Core Damage Probability = 2.7E-6

Three Green Findings

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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

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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

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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%

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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

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Affected valve

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Safety Significance

Degraded shutdown cooling train Shutdown cooling system used for low

pressure heat removal

Significant operational constraint

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NRC Response

Close monitoring by resident inspectors

Internal communications of the event

Issue For Resolution: Screened-in for operating experience follow-up

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Questions & Comments