ML071010247

EOC Summary Meeting Slides

ML071010247
Person / Time
Site:	Prairie Island
Issue date:	04/03/2007
From:	NRC/RGN-III
To:
References
Download: ML071010247 (20)

Text

Prairie Island Annual Assessment Meeting Reactor Oversight Program - CY 2006 Nuclear Regulatory Commission - Region III Welch, MN April 3, 2007

Purpose of Todays Meeting Provide a public forum for discussion of the licensees performance NRC will address the licensee performance as described 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 (DRP) Director Division of Reactor Safety (DRS)

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 John Adams, Senior Resident Inspector

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

- (651) 388-8209 z Mahesh Chawla, Project Manager, Nuclear Reactor Regulation

- (301) 415-8371 z Richard Skokowski, Branch Chief, DRP

- (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 NRCs strategic objectives

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 Radiological 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: Baseline Inspection only 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 2006 Licensee Response 70 Regulatory Response 24 Degraded Cornerstone 6 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 103

National Summary z Performance Indicator Results (at end of CY 2006)

Green 1843 White 11 Yellow 0 Red 0 z Total Inspection Findings (CY 2006)

Green 676 White 13 Yellow 0 Red 0

Prairie Island Assessment Results (Jan 1 - Dec 31, 2006) z Safety performance for 2006 at Prairie Island Units 1 and 2 was within the Licensee Response column of the NRC Action Matrix.

Safety Significant Findings or PIs No safety significant findings or Performance Indicators (PIs) were identified for this assessment period.

Prairie Island Inspection Activities (Jan 1 - Dec 31, 2006)

There were a total of 14 findings during this assessment period with two in initiating events, seven in mitigating systems, one in barrier integrity, three in occupational radiation safety, and one in public radiation safety.

One Severity Level III Violation for a failure to provide complete or accurate information.

Prairie Island Inspection Activities (Jan 1 - Dec 31, 2006)

Unit 1 had a refueling outage from April 28 - June 7, 2006 during which 110 radiation workers were contaminated when steam generator manways were opened. A filter discharge hose slipped off the intake because it was loosely attached with wire wrap, and the steam generator vented into containment.

A Unit 2 refueling outage occurred from November 14 - December 15, 2006 with no issues of significance noted.

Prairie Island Annual Assessment Summary January 1 - December 31, 2006 z NMC operated Prairie Island Units 1 & 2 in a manner that preserved public health and safety z All cornerstone objectives were met with only Green findings identified and all PIs indicating performance requiring no additional oversight z At this time the NRC plans only baseline inspections at Prairie Island for calendar year 2007

Licensee Response and Remarks Thomas J. Palmisano Site Vice President Prairie Island Nuclear Generating 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)