ML051230390

Public Meeting Slides Prairie Island End-of-Cycle Plant Performance Assessment

ML051230390
Person / Time
Site:	Prairie Island
Issue date:	04/12/2005
From:	NRC/RGN-III
To:
References
Download: ML051230390 (21)

Text

Prairie Island Annual Assessment Meeting Reactor Oversight Program - CY 2004 Nuclear Regulatory Commission - Region III Lisle, IL

Purpose of Todays Meeting

! A public forum for discussion of the licensees performance

! NRC will address Prairie Island performance issues discussed in the March 2, 2005 annual assessment letter

! Licensee Remarks

Agenda

! Introduction

! Review of Reactor Oversight Process

! National Summary of Plant Performance

! Discussion of Plant Performance Results

! Licensee Remarks

! NRC Closing Remarks

! NRC available to address public questions

NRC Representatives

! Mark A. Satorius, Director, Division Reactor Projects (DRP)

- (630) 829-9600

! Steven Reynolds, Deputy Director, DRP

- (630) 829-9600

! David Passehl, Branch Chief

- (630) 829-9872

! Mahesh (Mac) Chawla, Project Manager, NRR

- (301) 415-8371

! John Adams, Senior Resident Inspector

- (651) 388-8209

! Duane Karjala, Resident Inspector

- (651) 388-8209

! Thomas Tongue, Senior Project Engineer

- (630) 829-9613

Region III Organization Jim Caldwell Regional Administrator Geoffrey Grant Deputy Regional Administrator Mark A. Satorius Cynthia D. Pederson Director Division of Reactor Projects Director Division of Reactor Safety Steve Reynolds Roy Caniano Deputy Director Deputy Director David Passehl Regional Specialists Branch Chief Prairie Island Project Engineer Resident Inspectors Thomas Tongue John Adams Duane Karjala

NRC Performance Goals

! Safety: Ensure protection of the public health and safety and the environment

! Security: Enhance the secure use and management of radioactive materials

! Openness: Ensure openness in our regulatory process

! Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely

! Management: Ensure excellence in agency management to carry out the NRCs strategic objective

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

Examples of Baseline Inspections

! Equipment Alignment ~92 hrs/yr

! Triennial Fire Protection ~200 hrs every 3 yrs

! Operator Response ~125 hrs/yr

! Emergency Preparedness ~80 hrs/yr

! Public Radiation Protection ~100 hrs every 2 yrs

! Worker Radiation Protection ~100 hrs/yr

! Corrective Action Program ~200 hrs every 2 yrs

! 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 Mgmt. Involvement with Licensee Mgmt.

Increasing Regulatory Actions

National Summary of Plant Performance Status at End of CY 2004 Licensee Response 78 Regulatory Response 21 Degraded Cornerstone 0 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total Units 102

• Davis-Besse is in IMC 0350 process

National Summary

! Performance Indicator Results (at end of CY 2004)

< Green 1834

< White 6

< Yellow 0

< Red 0

! Total Inspection Findings (CY 2004)

< Green 778

< White 11

< Yellow 0

< Red 0

Prairie Island Assessment Results (Jan 1 - Dec 31, 2004)

Licensee Response Column

! All Inspection Findings were Green.

< Very Low Significance

! All Performance Indicators were within the Green band.

Prairie Island Inspection Activities (Jan 1 - Dec 31, 2004)

! Baseline Inspection

! Unit 1 Refueling and Steam Generator Replacement Outage

Prairie Island Inspection Activities (Jan 1 - Dec 31, 2004)

Completed Baseline Inspections Routine Integrated Inspections

! Triennial Fire Protection Inspection

! Maintenance Rule Inspection

! Modifications and 10 CFR 50.59 Inspection

! Emergency Preparedness Inspection

! Radiation Protection Inspection

! Licensed Operator Requalification Inspection

Prairie Island Inspection Activities (Jan 1 - Dec 31, 2004)

Completed Other Inspections TI 2515 / 152 RPV Lower Head Inspection

! TI 2515 / 153 Reactor Containment Sump Blockage

! TI 2515 / 154 Spent Fuel Material and Accounting Inspection

! TI 2515 / 156 Offsite Power System Operational Readiness Inspection

! Steam Generator Replacement Inspection

Prairie Island Annual Assessment Summary January 1- December 31, 2004 Summary of Findings

! Cornerstone: Initiating Events

< Two green findings

! Cornerstone: Mitigating System

< Three green findings

! Cornerstone: Barrier Integrity

< Five green findings

Prairie Island Annual Assessment Summary January 1- December 31, 2004

! NMC operated Prairie Island in a manner that preserved public health and safety

! All cornerstone objectives were met

! In 2005, NRC plans baseline inspections

Licensee Response and Remarks Joe Solymossy Site Vice President

Contacting the NRC

! Report an emergency

< (301) 816-5100 (call collect)

! Report a safety concern:

< (800) 695-7403

< Allegation@nrc.gov

! General information or questions

< www.nrc.gov

< Select What We Do for Public Affairs

Reference Sources

! Reactor Oversight Process

< http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html

! Public Electronic Reading Room

< http://www.nrc.gov/reading-rm.html

! Public Document Room

< 1-800-397-4209 (Toll Free)