ML041340392
| ML041340392 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/12/2004 |
| From: | NRC/RGN-III |
| To: | |
| References | |
| Download: ML041340392 (22) | |
Text
D.C. Cook Performance Meeting Supplemental Inspection - Inspection Procedure 95002 Exit Meeting Nuclear Regulatory Commission - Region III Lisle, Illinois May 12, 2004
NRC Representatives l Patrick Hiland, Acting Deputy Division Director, DRP
- (630) 829-9601 l Brian Kemker, Senior Resident Inspector
- (269) 465-5353 l Ivy Netzel, Resident Inspector
- (269) 465-5353 l Eric Duncan, Branch Chief
- (630) 829-9628 l Steve Burton, Inspection Procedure 95002 Team Leader
- (763) 295-2066
Agenda l Review of Reactor Oversight Process l Discussion of D.C. Cook Performance l Inspection Procedure 95002 Inspection Results l Licensee Response and Remarks l NRC Closing Remarks l NRC Available to Address Public Questions
NRC Performance Goals l Maintain safety and protect the environment l Enhance public confidence l Improve effectiveness, efficiency, and realism of processes and decision making l Reduce unnecessary regulatory burden
Regulatory Framework PUBLIC HEALTH AND SAFETY AS A RESULT OF CIVILIAN NRCs Overall NUCLEAR REACTOR Safety Mission OPERATION Strategic REACTOR RADIATION Performance SAFEGUARDS SAFETY SAFETY Areas PUBLIC OCCUPATIONAL INITIATING MITIGATING BARRIER EMERGENCY PHYSICAL Cornerstones RADIATION RADIATION EVENTS SYSTEMS INTEGRITY PREPAREDNESS PROTECTION SAFETY SAFETY HUMAN SAFETY CONSCIOUS PROBLEM IDENTIFICATION PERFORMANCE WORK ENVIRONMENT AND RESOLUTION Cross-Cutting Areas
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response
Significance Threshold Performance Indicators Green: Only Baseline Inspection White: May increase NRC oversight Yellow: Requires more NRC oversight Red: Requires more NRC oversight Inspection Findings Green: Very Low safety issue White: Low to moderate safety issue Yellow: Substantial safety issue Red: High safety issue
Action Matrix Concept Licensee Regulatory Degraded Multiple/Rep. Unacceptable Response Response Cornerstone Degraded Performance Cornerstone Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions
Purpose of Todays Meeting l Provide a public forum for the discussion of D.C. Cook performance l NRC to discuss D.C. Cook performance issues identified during the IP 95002 inspection l D.C. Cook management will respond to the information presented and inform the NRC of new or existing programs to maintain or improve their performance
D.C. Cook Performance Summary l AEP has operated D.C. Cook in a manner that preserves public health and safety. All cornerstone objectives are being met.
l Unit 1 is in the Regulatory Response column of the Action Matrix.
l Unit 2 is in the Degraded Cornerstone column of the Action Matrix. Two Unit 2 White performance indicators at the end of the assessment period represented a moderate degradation in safety performance.
l One substantive cross-cutting issue in the Problem Identification and Resolution area remains open.
l NRC continues to conduct baseline inspections at D.C. Cook for the assessment period and performed a supplemental inspection to review the White performance indicators.
White Performance Indicators l Two Unit 2 White performance indicators in the Initiating Events cornerstone were identified during the 2003 assessment period placing Unit 2 in the Degraded Cornerstone column of the Action Matrix.
l A White performance indicator in the Unplanned Scrams Per 7000 Critical Hours area was identified in 4Q03.
l A White performance indicator in the Scrams With Loss of Normal Heat Removal area was first identified in 2Q03 and updated in 4Q03 to reflect crossing the Green/White threshold in 3Q02.
D.C. Cook Performance Indicators PUBLIC HEALTH AND SAFETY AS A RESULT OF CIVILIAN NRCs Overall Safety Mission NUCLEAR REACTOR OPERATION Strategic REACTOR RADIATION Performance SAFEGUARDS Areas SAFETY SAFETY OCCUPATIONAL PUBLIC Cornerstones INITIATING MITIGATING BARRIER EMERGENCY PHYSICAL RADIATION RADIATION EVENTS SYSTEMS INTEGRITY PREPAREDNESS PROTECTION SAFETY SAFETY Emergency AC Occupational RETS/ODCM Unplanned Reactor Coolant Drill/Exercise Protected Area Power System Exposure Control Radiological Scrams System Leakage Performance Equipment Unavailability Effectiveness Effluent Performance Scrams With Loss High Pressure Personnel Reactor Coolant ERO Drill Indicators of Normal Heat Injection System Screening System Activity Participation Removal Unavailability Program Heat Removal FFD/Personnel Unplanned Power Alert and System Reliability Changes Notification System Unavailability Program Residual Heat Removal System Unavailability Safety System Functional Failures
D.C. Cook Supplemental Inspection Activities l A Supplemental Inspection to review the Scrams With Loss of Normal Heat Removal White performance indicator was conducted in accordance with IP 95001, Inspection For One or Two White Inputs in a Strategic Performance Area, and was completed on November 21, 2003.
l A Supplemental Inspection to review the White finding in the Public Radiation cornerstone of the Radiation Safety Strategic Performance Area in accordance with IP 95001 is in progress and scheduled to be completed next week.
D.C. Cook Supplemental Inspection Activities l A Supplemental Inspection to collectively review the Scrams With Loss of Normal Heat Removal and Unplanned Scrams Per 7000 Critical Hours White performance indicators was conducted from April 19 to April 30, 2004 l Inspection conducted in accordance with IP 95002, Inspection For One Degraded Cornerstone Or Any Three White Inputs On A Strategic Performance Area
D.C. Cook Inspection Procedure 95002 Inspection Objectives l To provide assurance that the root causes and contributing causes are understood for the individual and collective performance issues.
l To independently assess the extent of condition and the extent of cause for the individual and collective performance issues.
l To provide assurance that licensee corrective actions for the performance issues are sufficient to address the root causes and contributing causes, and to prevent recurrence.
D.C. Cook Inspection Procedure 95002 Inspection Results l The issues were inspector-identified and self-revealing l The issues were evaluated from a risk perspective l Prior trends were not evaluated with respect to the collective nature of the scrams l Prior opportunities for identifying the causal factors for the scrams were not recognized l A systematic method was used for evaluating the causal factors l The evaluation was completed at a level of detail commensurate with the safety significance of the issue
D.C. Cook Inspection Procedure 95002 Inspection Results l Corrective actions to address the contributing causes were appropriate l Integration of corrective action items with the recovery plan was inconsistent l Traditional schedules for completion & measures for success had not been established l Key performance indicators and managerial controls were established that could be effective in managing the corrective actions l The inspectors extent of condition and extent of cause review identified no significant deficiencies
D.C. Cook Inspection Procedure 95002 Inspection Results Summary l Proper integration of the recovery plan and the corrective action program is paramount to ensure success with correcting the identified causal factors l Of the causal factors identified, a common denominator was an ineffective corrective action program l Plant events not collectively evaluated to identify corrective actions to improve plant performance
Licensee Response and Remarks Joseph Jensen Site Vice-President Indiana Michigan Power Company
Contacting the NRC l Report an emergency u (301) 816-5100 (call collect) l Report a safety concern:
u (800) 695-7403 u Allegation@nrc.gov l General information or questions u www.nrc.gov u Select What We Do for Public Affairs
Reference Sources l Reactor Oversight Process u http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html l Public Electronic Reading Room u http://www.nrc.gov/reading-rm.html l Public Document Room u 1-800-397-4209 (Toll Free)
Public Comment Opportunity