ML061090490

Annual Assessment Meeting Summary Slides 04/12/06

ML061090490
Person / Time
Site:	Prairie Island
Issue date:	04/12/2006
From:	NRC/RGN-III
To:
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Download: ML061090490 (19)

Text

Prairie Island Annual Assessment Meeting Reactor Oversight Program - CY 2005 Nuclear Regulatory Commission - Region III Welch, MN.

April 12, 2006

Purpose of Todays Meeting A public forum for discussion of the licensees performance NRC will address the licensee performance issues identified in the annual assessment letter Licensee will be given the opportunity to respond to the information in the letter and inform the NRC of new or existing programs to maintain or improve their performance

Agenda z Introduction z Review of Reactor Oversight Process z National Summary of Plant Performance z Discussion of Plant Performance Results z Licensee Response and Remarks z NRC Closing Remarks z Break z NRC available to address public questions

Region III Organization James Caldwell Regional Administrator Geoff Grant Deputy Regional Administrator Mark Satorius Cynthia Pederson Director Division of Reactor Projects Director Division of Reactor Safety Steve West Anne Boland Deputy Director Deputy Director Richard Skokowski Regional Specialists Branch Chief Prairie Island Project Engineer Resident Inspectors Desiree Smith John Adams Duane Karjala

NRC Representatives z Mahesh Mac Chawla, Project Manager, NRR

- (301) 415-8371 z John Adams, Senior Resident Inspector

- (651) 388-8209 z Duane Karjala, Resident Inspector

- (651) 388-8209 z Desiree Smith, Project Engineer

- (630) 829-9500 z Richard Skokowski, Branch Chief

- (630) 829-9620

NRC Performance Goals z Safety: Ensure protection of the public health and safety and the environment z Security: Ensure the secure use and management of radioactive materials z Openness: Ensure openness in our regulatory process z Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely z Management: Ensure excellence in agency management to carry out the NRC strategic objective

Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response

Examples of Baseline Inspections z Equipment Alignment ~80 hrs/yr z Triennial Fire Protection ~200 hrs every 3 yrs z Operator Response ~125 hrs/yr z Emergency Preparedness ~80 hrs/yr z Rad Release Controls ~110 hrs every 2 yrs z Worker Radiation Protection ~90 hrs/yr z Corrective Action Program ~250 hrs every 2 yrs z Corrective Action Case Reviews ~60 hrs/yr

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

National Summary of Plant Performance Status at End of CY 2005 Licensee Response 84 Regulatory Response 12 Degraded Cornerstone 4 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 103

National Summary z Performance Indicator Results (at end of CY 2005)

Green 1850 White 4 Yellow 0 Red 0 z Total Inspection Findings (CY 2005)

Green 849 White 10 Yellow 1 Red 0

Prairie Island Assessment Results (Jan 1 - Dec 31, 2005) z Licensee Response Action Matrix Column with no greater than green findings/PIs z No supplemental inspections were conducted z With assistance from regional inspectors the residents reported a total of eighteen (18) findings of very low safety significance (GREEN)

Prairie Island Inspection Activities (Jan 1 - Dec 31, 2005)

There was one refueling outage for Unit 2 from May 5 thru 31 which involved the replacement of the reactor vessel head

Prairie Island Inspection Activities (Jan 1 - Dec 31, 2005)

A Safety System Design and Performance Capability inspection (SSDPC) was performed in June A Heat Sink Biennial inspection was conducted in July A Problem Identification and Resolution (PI&R) was conducted in August

Prairie Island Annual Assessment Summary January 1 - December 31, 2005 z NMC operated Prairie Island Units 1 & 2 in a manner that preserved public health and safety z All cornerstone objectives were met. All findings were of very low safety significance (GREEN) z NRC plans baseline inspections at Prairie Island for the remainder of the assessment period

Licensee Response and Remarks Tom Palmisano Site Vice President Prairie Island Power Station

Contacting the NRC z Report an emergency (301) 816-5100 (call collect) z Report a safety concern:

(800) 695-7403 Allegation@nrc.gov z General information or questions www.nrc.gov Select What We Do for Public Affairs

Reference Sources z Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html z Public Electronic Reading Room http://www.nrc.gov/reading-rm.html z Public Document Room 1-800-397-4209 (Toll Free)