ML051400179
| ML051400179 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/12/2005 |
| From: | Arthur Burritt NRC Region 1 |
| To: | |
| Burritt A RGN-I/DRP/PB7/610-337-5069 | |
| Shared Package | |
| ML050750437 | List: |
| References | |
| %dam200604 | |
| Download: ML051400179 (25) | |
Text
Oyster Creek Station Annual Assessment Meeting Reactor Oversight Program - CY 2004 Nuclear Regulatory Commission - Region 1 King of Prussia, PA May 12, 2005
Agenda
- Introductions
- Review of Reactor Oversight Process
- National Summary of Plant Performance
- Discussion of Plant Performance Results
- AmerGen Response and Remarks
- NRC Closing Remarks
- Break
- NRC available to address public questions
Purpose of Todays Meeting
- NRC will address licensee performance as identified in our annual assessment
- AmerGen will respond to our assessment and inform the NRC of new or existing programs to maintain or improve performance
- NRC comments on security & public involvement
- NRC will respond to questions from the public after the discussion with AmerGen
NRC Representatives
- Randy Blough, Director Division of Reactor Safety
- (610) 337-5126
- Dr. Ronald Bellamy, Branch Chief Division of Reactor Projects
- (610) 337-5226
- Richard Barkley, Senior Project Engineer
- (610) 337-5065
- Robert Summers, Senior Resident Inspector
- (609) 693-0702
NRC Performance Goals
- Safety: Ensure protection of 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 Baseline Inspection Performance Indicator 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
- 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
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 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
Oyster Creek Station Assessment Results (Jan 1 - Dec 31, 2004)
- Operated safely
- In the Regulatory Response Column of the Action Matrix for all four quarters of 2004
- Substantive cross-cutting issue identified in the area of Problem Identification and Resolution
- NRC will conduct baseline inspections in 2005 plus a supplemental inspection of the EP White finding
Oyster Creek Station Performance Indicators Oyster Creek Inspection Findings www.nrc.gov/NRR/OVERSIGHT/ASSESS/ then click OC
Oyster Creek Inspection Activities (Jan 1 - Dec 31, 2004)
- 5,300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> of inspection-related activities
- 2 resident inspectors assigned to the site
- 14 regional inspections by technical specialists
- 1 team inspection - Problem Identification and Resolution
- Inspection Findings
- Fifteen findings of very low safety significance (Green)
- Two findings of low safety significance (White) 3/4 One not finalized until March 2005
Substantive Cross-Cutting Issue
- ROP relies on early identification & correction of problems before they become significant
- Issues involve (cross-cut) multiple ROP cornerstones
- Three factors must exist for the NRC to identify a cross-cutting issue:
- Multiple Green or safety significant inspection findings within the 12 month assessment period
- Causal factors have a common theme (e.g., PI&R - identification) as indicated by >3 findings
- NRCs concern with licensees scope of efforts or progress in addressing the cross-cutting deficiency
Oyster Creek Station Assessment Summary (Jan 1 - Dec 31, 2004)
- Operated safely
- Preserved Public Health and Safety
- Opened a PI&R substantive cross-cutting issue
- Will be reevaluated in early August 2005
Oyster Creek Station Planned Inspections (Jan 1 - Dec 31, 2005)
- Ten regional inspector visits scheduled
- Two team inspections scheduled
- Safety System Design Inspection
- Triennial Fire Protection Team
- One supplemental inspection of the EP White finding
AmerGen Response and Remarks Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC
NRC Security Program Update Full implementation of four Orders issued in 2003:
- Access Authorization Order (January 2003)
- Training Order (April 2003)
- Fatigue Order (April 2003)
- Revised Design Basis Threat Order (April 2003)
- Changes to Site Security plans to incorporate the requirements of the orders were reviewed and approved
- Expanded Force-on-Force Exercises (ongoing)
- New NRC Security Baseline Inspection Program initiated (February 2004)
Ways for the Public To Become Informed &
Involved in the Regulatory Process Examples
- Participate in NRC Public Meetings
- Sign up to be on our mailing list
- Visit the NRC website on a regular basis
- Publically comment on proposed licensing actions or file a Petition for Rulemaking
- 10 CFR 2.206 petition process
- Contact the NRC via E-mail, mail or phone to address questions or areas of concern
- Participate in open NRC/industry symposiums
- Freedom of Information Act (FOIA) requests
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)
- Public Comment & Involvement in Rulemaking http://ruleforum.llnl.gov/
- NRC brochure: Protecting Our Nation http://www.nrc.gov/reading-rm/doc-collections/nuregs/brochures/br0314/
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
BREAK Open Inspection Regional Onsite Administrator Exit Meeting(s) Report(s)
Inspection(s) Letter Issued (Inspections) Issued**
Advisory Safety Committee on ACRS Letter Review Reactor Safeguards Issued**
Open Review License Renewal Exit Meetings Application** (Audits) submitted to NRC Safety Safety Evaluation Evaluation and Audits Report Open Issued**
Meetings on Safety Issues Public NRC Decision Information Environmental Hearings* On Meeting Analyses and Application**
Onsite Audit Local, State, Local, State, Environmental Tribal, and Federal Tribal, and Federal Review Government Government Officials Officials
- If a request for hearing is granted