ML030780346
| ML030780346 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/17/2003 |
| From: | NRC Region 1 |
| To: | |
| Shared Package | |
| ml030650398 | List: |
| References | |
| Download: ML030780346 (22) | |
Text
NRC Reactor Oversight Program Annual Assessment Meeting Seabrook Power Station Nuclear Regulatory Commission - Region I King of Prussia, PA
Agenda Business
< Introduction
< Review of Reactor Oversight Process
< National Results
< Seabrook Results
< NRC Security Update
< Licensee Response and Remarks Public Comments and Questions
Region I Organization Radiation Protection Specialists Security Specialists John White Branch Chief Director Division of Reactor Safety Richard Crlenjak Deputy Director Wayne Lanning Colleen Picciotto Felicia Hinson Incident Response Center Glenn Dentel Javier Brand Seabrook Resident Inspectors Kenneth Jenison Martha Barillas Shani Lewis Project Engineers Stephen M. Schneider Paul Cataldo Silas Kennedy Kevin Mangan Millstone Resident Inspectors Branch Chief Brian J. McDermott Director Division of Reactor Projects John Rogge Acting Deputy Director A. Randolph Blough Regional Administrator James Wiggins Deputy Regional Administrator Hubert Miller
Reactor Oversight Process Safety Cornerstones Baseline Inspection Results Significance Threshold Action Matrix Significance Threshold Performance Indicator Results Regulatory Response Strategic Performance Areas
Examples of Baseline Inspections
- Equipment Alignment
~90 hrs/yr
- Triennial Fire Protection
~200 hrs every 3 yrs
- Operator Response
~125 hrs/yr
~80 hrs/yr
- Rad Release Controls
~100 hrs every 2 yrs
- Worker Radiation Protection
~100 hrs/yr
- Corrective Action Program
~250 hrs every 2 yrs
- Corrective Action Case Reviews ~60 hrs/yr
Examples of Performance Indicators
- Scrams with Loss of Normal Heat Removal
- Unplanned Power Changes
- Emergency AC Power System Safety System Unavailability
- Alert and Notification System Reliability
Significance Threshold Performance Indicators Green:
Baseline Inspections White:
May increase NRC oversight Yellow:
Requires more NRC oversight Red: Requires more NRC oversight Inspection Findings Green:
Very low safety significant issue White:
Low to moderate safety significant issue Yellow: Substantial safety significant issue Red:
High safety significant issue
Action Matrix Concept Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions Licensee
Response
Regulatory
Response
Degraded Cornerstone Multiple/Rep.
Degraded Cornerstone Unacceptable Performance
National Summary of Plant Performance Status at End of 2002 Licensee Response 75 Regulatory Response 24 Degraded Cornerstone 2
Multiple/Repetitive Degraded Cornerstone 1
Unacceptable 0
- Davis Besse is in IMC 0350 process Total Plants*
102
National Summary
- Performance Indicator Results (at end of 2002)
< Green 1835
< White 5
< Yellow 0
< Red 0
- Total Inspection Findings (2002)
< Green 783
< White 30
< Yellow 1
< Red 2
Seabrook Assessment Results January 1 - December 31, 2002
- Operated safely
- Met all cornerstone objectives
- Licensee Response Column on Action Matrix
- NRC will conduct baseline inspections in 2003
Seabrook Assessment Results (continued)
Cross-Cutting Issues
- NRC removed the substantial cross-cutting issue designation for Problem Identification &
Resolution
< Confirmed progress through resident and team inspections
< Demonstrated improvement by a decrease in significance and number of findings
Seabrook - Performance Indicators www.nrc.gov/NRR/OVERSIGHT/ASSESS/SEAB1/seab1_chart.html#pi_section
Performance Indicator
Seabrook Inspection Activities January 1 - December 31, 2002
- 5500 hours0.0637 days <br />1.528 hours <br />0.00909 weeks <br />0.00209 months <br /> of inspection related activities
- 2 resident inspectors on-site
- 17 regional inspector visits
- 5 team inspections
< Permanent Plant Modifications
< Fire Protection
< Special Inspection Team
< Problem Identification & Resolution
< Emergency Preparedness Exercise
Seabrook - Inspection Results
Inspection Findings January 1 - December 31, 2002
- 7 inspection findings of very low safety significance (Green)
- 4 of the 7 inspection findings related to the Emergency Diesel Generators (EDGs)
- EDGs provide backup power to emergency equipment
NRC Security Program Update
- Interim Compensatory Measures (February 2002)
< Required by NRC Order
< Increased Patrols
< Augmented Security Capabilities
< Added Barriers and Posts
< Enhanced Personnel Screening for Access
- Office of Nuclear Security and Incident Response (April 2002)
- Threat Advisory and Protective Measure System (August 2002)
< Five threat levels corresponding to the Homeland Security Advisory System
NRC Security Program Update (continued)
- Access Authorization Order (January 2003)
- Force-on-Force Exercises (February 2003)
- Revised Design Basis Threat (TBD)
- Training Order (TBD)
- Fatigue Order (TBD)
NRC Representatives
- Brian McDermott, Chief, Projects Branch 6 & Incident Response, Region I (610) 337-5233
- John White, Chief, Radiation Safety & Safeguards, Region I (610) 337-5114
- Victor Nerses, Project Manager, Office of Nuclear Reactor Regulation (301) 415-1484
- Glenn Dentel, Senior Resident Inspector, Seabrook Resident Office (603) 474-3589
- Javier Brand, Resident Inspector, Seabrook Resident Office (603) 474-3580
- Neil Sheehan, Public Affairs Officer, Region I (610) 337-5331
Reference Sources
- Reactor Oversight Process
< http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html
- Public Electronic Reading Room
< http://www.nrc.gov/reading-rm/adams.html
- Public Document Room
< 1-800-397-4209 (Toll Free)
End of Presentation