ML051400179

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NRC Slides for Annual Assessment Meeting with Amergen Regarding Oyster Creek Station
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
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Download: ML051400179 (25)


Text

Oyster Creek Station Oyster Creek Station Annual Assessment Meeting Annual Assessment Meeting Reactor Oversight Program Reactor Oversight Program -- CY 2004 CY 2004 Nuclear Regulatory Commission Nuclear Regulatory Commission -- Region 1 Region 1 King of Prussia, PA King of Prussia, PA May 12, 2005 May 12, 2005

Agenda Agenda

    • Introductions

Introductions

    • Review of Reactor Oversight Process Review of Reactor Oversight Process
    • National Summary of Plant Performance National Summary of Plant Performance
    • Discussion of Plant Performance Results Discussion of Plant Performance Results
    • AmerGen AmerGen Response and Remarks Response and Remarks
    • NRC Closing Remarks NRC Closing Remarks
    • Break Break
    • NRC available to address public questions NRC available to address public questions

Purpose of Todays Meeting Purpose of Todays Meeting

    • NRC will address licensee performance as NRC will address licensee performance as identified in our annual assessment identified in our annual assessment
    • AmerGen AmerGen will respond to our assessment and will respond to our assessment and inform the NRC of new or existing programs inform the NRC of new or existing programs to maintain or improve performance to maintain or improve performance
    • NRC comments on security & public NRC comments on security & public involvement involvement
    • NRC will respond to questions from the public NRC will respond to questions from the public after the discussion with after the discussion with AmerGen AmerGen

NRC Representatives NRC Representatives

    • Randy Randy Blough Blough, Director

, Director Division of Reactor Safety Division of Reactor Safety

-- (610) 337 (610) 337--5126 5126

-- (610) 337 (610) 337--5226 5226

    • Richard Barkley, Senior Project Engineer Richard Barkley, Senior Project Engineer

-- (610) 337 (610) 337--5065 5065

    • Robert Summers, Senior Resident Inspector Robert Summers, Senior Resident Inspector

-- (609) 693 (609) 693--0702 0702

NRC Performance Goals NRC Performance Goals

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

Reactor Oversight Process 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 Examples of Baseline Inspections

    • Equipment Alignment Equipment Alignment

~92 hrs/yr

~92 hrs/yr

    • Triennial Fire Protection Triennial Fire Protection

~200 hrs every 3 yrs

~200 hrs every 3 yrs

    • Operator Response Operator Response

~125 hrs/yr

~125 hrs/yr

~80 hrs/yr

~80 hrs/yr

    • Rad Rad Release Controls Release Controls

~100 hrs every 2 yrs

~100 hrs every 2 yrs

    • Worker Radiation Protection Worker Radiation Protection

~100 hrs/yr

~100 hrs/yr

    • Corrective Action Program Corrective Action Program

~250 hrs every 2 yrs

~250 hrs every 2 yrs

    • Corrective Action Case Reviews Corrective Action Case Reviews ~60 hrs/yr

~60 hrs/yr

Significance Threshold Significance Threshold Performance Indicators Performance Indicators Green Green::

Only Baseline Inspection Only Baseline Inspection White:

White:

May increase NRC oversight May increase NRC oversight Yellow Yellow::

Requires more NRC oversight Requires more NRC oversight Red Red::

Requires more NRC oversight Requires more NRC oversight Inspection Findings Inspection Findings Green Green::

Very Low safety issue Very Low safety issue White:

White:

Low to moderate safety issue Low to moderate safety issue Yellow Yellow::

Substantial safety issue Substantial safety issue Red Red::

High safety issue High safety issue

Action Matrix Concept Action Matrix Concept Licensee

Response

Regulatory

Response

Degraded Cornerstone Multiple/Rep.

Degraded Cornerstone Unacceptable Performance

  • Increasing Safety Significance
  • Increasing NRC Inspection Efforts
  • Increasing NRC/Licensee Management Involvement
  • Increasing Regulatory Actions

National Summary of Plant Performance National Summary of Plant Performance Licensee Response Licensee Response 78 78 Regulatory Response Regulatory Response 21 21 Degraded Cornerstone Degraded Cornerstone 00 Multiple/Repetitive Degraded Cornerstone Multiple/Repetitive Degraded Cornerstone 33 Unacceptable Unacceptable 00 Total Units 102*

Total Units 102*

  • Davis

National Summary National Summary Performance Indicator Results (at end of CY 2004)

Performance Indicator Results (at end of CY 2004)

Green Green 1834 1834 White White 66 Yellow Yellow 00 Red Red 00 Total Inspection Findings (CY 2004)

Total Inspection Findings (CY 2004)

Green Green 778 778 White White 11 11 Yellow Yellow 00 Red Red 00

Oyster Creek Station Oyster Creek Station Assessment Results Assessment Results

    • Operated safely Operated safely
    • In the Regulatory Response Column of the In the Regulatory Response Column of the Action Matrix for all four quarters of 2004 Action Matrix for all four quarters of 2004
    • Substantive cross Substantive cross--cutting issue identified in the cutting issue identified in the area of Problem Identification and Resolution area of Problem Identification and Resolution
    • NRC will conduct baseline inspections in 2005 NRC will conduct baseline inspections in 2005 plus a supplemental inspection of the EP White plus a supplemental inspection of the EP White finding finding (Jan 1 - Dec 31, 2004)

Oyster Creek Station Performance Indicators Oyster Creek Station Performance Indicators

Oyster Creek Inspection Findings Oyster Creek Inspection Findings www.nrc.gov/NRR/OVERSIGHT/ASSESS/ then click OC

Oyster Creek Inspection Activities Oyster Creek Inspection Activities

    • 5,300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> of inspection 5,300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> of inspection--related activities related activities
    • 2 resident inspectors assigned to the site 2 resident inspectors assigned to the site
    • 14 regional inspections by technical specialists 14 regional inspections by technical specialists
    • 1 team inspection 1 team inspection -- Problem Identification and Problem Identification and Resolution Resolution
    • Inspection Findings Inspection Findings

-- Fifteen findings of very low safety significance Fifteen findings of very low safety significance (Green)

(Green)

-- Two findings of low safety significance (White)

Two findings of low safety significance (White) 3/4 3/4 One not finalized until March 2005 One not finalized until March 2005 (Jan 1 - Dec 31, 2004)

Substantive Cross Substantive Cross--Cutting Issue Cutting Issue

    • ROP relies on early identification & correction of problems ROP relies on early identification & correction of problems before they become significant before they become significant
    • Issues involve (cross Issues involve (cross--cut) multiple ROP cornerstones cut) multiple ROP cornerstones
    • Three factors must exist for the NRC to identify a cross Three factors must exist for the NRC to identify a cross--

cutting issue:

cutting issue:

-- Multiple Green or safety significant inspection findings within Multiple Green or safety significant inspection findings within the the 12 month assessment period 12 month assessment period

-- Causal factors have a common theme (e.g., PI&R Causal factors have a common theme (e.g., PI&R -- identification) identification) as indicated by >3 findings as indicated by >3 findings

-- NRCs NRCs concern with licensees scope of efforts or progress in concern with licensees scope of efforts or progress in addressing the cross addressing the cross--cutting deficiency cutting deficiency

Oyster Creek Station Oyster Creek Station Assessment Summary Assessment Summary

    • Operated safely Operated safely
    • Preserved Public Health and Safety Preserved Public Health and Safety
    • Opened a PI&R substantive cross Opened a PI&R substantive cross--cutting issue cutting issue

-- Will be reevaluated in early August 2005 Will be reevaluated in early August 2005 (Jan 1 - Dec 31, 2004)

Oyster Creek Station Oyster Creek Station Planned Inspections Planned Inspections

    • Ten regional inspector visits scheduled Ten regional inspector visits scheduled
    • Two team inspections scheduled Two team inspections scheduled

-- Safety System Design Inspection Safety System Design Inspection

-- Triennial Fire Protection Team Triennial Fire Protection Team

    • One supplemental inspection of the EP White One supplemental inspection of the EP White finding finding (Jan 1 - Dec 31, 2005)

AmerGen AmerGen Response and Remarks Response and Remarks Oyster Creek Nuclear Generating Station Oyster Creek Nuclear Generating Station AmerGen AmerGen Energy Company, LLC Energy Company, LLC

NRC Security Program Update NRC Security Program Update Full implementation of four Orders issued in 2003:

Full implementation of four Orders issued in 2003:

    • Access Authorization Order (January 2003)

Access Authorization Order (January 2003)

    • Training Order (April 2003)

Training Order (April 2003)

    • Fatigue Order (April 2003)

Fatigue Order (April 2003)

    • Revised Design Basis Threat Order (April 2003)

Revised Design Basis Threat Order (April 2003)

    • Changes to Site Security plans to incorporate the Changes to Site Security plans to incorporate the requirements of the orders were reviewed and approved requirements of the orders were reviewed and approved
    • Expanded Force Expanded Force--on on--Force Exercises (ongoing)

Force Exercises (ongoing)

    • New NRC Security Baseline Inspection Program initiated New NRC Security Baseline Inspection Program initiated (February 2004)

(February 2004)

Ways for the Public To Become Informed &

Ways for the Public To Become Informed &

Involved in the Regulatory Process Involved in the Regulatory Process

    • Participate in NRC Public Meetings Participate in NRC Public Meetings

-- Sign up to be on our mailing list Sign up to be on our mailing list

    • Visit the NRC website on a regular basis Visit the NRC website on a regular basis
    • Publically Publically comment on proposed licensing actions or comment on proposed licensing actions or file a Petition for Rulemaking file a Petition for Rulemaking
    • Contact the NRC via E Contact the NRC via E--mail, mail or phone to address mail, mail or phone to address questions or areas of concern questions or areas of concern
    • Participate in open NRC/industry symposiums Participate in open NRC/industry symposiums
    • Freedom of Information Act (FOIA) requests Freedom of Information Act (FOIA) requests Examples

Reference Sources Reference Sources

    • Reactor Oversight Process Reactor Oversight Process http://

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

    • Public Document Room Public Document Room 11--800 800--397 397--4209 (Toll Free) 4209 (Toll Free)
    • Public Comment & Involvement in Rulemaking Public Comment & Involvement in Rulemaking http://

http://ruleforum.llnl.gov ruleforum.llnl.gov//

collections/nuregs/brochures/br0314/

collections/nuregs/brochures/br0314/

Contacting the NRC Contacting the NRC

    • Report an emergency Report an emergency

-- (301) 816 (301) 816--5100 (call collect) 5100 (call collect)

    • Report a safety concern:

Report a safety concern:

-- (800) 695 (800) 695--7403 7403

-- Allegation@nrc.gov Allegation@nrc.gov

    • General information or questions General information or questions

-- www.nrc.gov www.nrc.gov

-- Select What We Do for Public Affairs Select What We Do for Public Affairs

BREAK BREAK

Safety Safety Review Review Environmental Environmental Review Review Onsite Onsite Inspection(s)

Inspection(s)

Inspection Inspection Report(s)

Report(s)

Issued**

Issued**

Safety Safety Evaluation Evaluation and Audits and Audits Safety Safety Evaluation Evaluation Report Report Issued**

Issued**

ACRS ACRS Letter Letter Issued**

Issued**

Draft Draft Supplement Supplement To GEIS To GEIS Issued**

Issued**

Final Final Supplement Supplement To GEIS To GEIS Issued**

Issued**

NRC Decision NRC Decision On On Application**

Application**

Regional Regional Administrator Administrator Letter Issued Letter Issued License Renewal Application**

submitted to NRC Public Information Meeting Public Meetings on Scoping Public Meetings on Draft Hearings*

Open Meetings on Safety Issues Advisory Committee on Reactor Safeguards Review Open Exit Meeting(s)

(Inspections)

Scoping Process Local, State, Tribal, and Federal Government Officials Environmental Environmental Analyses and Analyses and Onsite Audit Onsite Audit Open Exit Meetings (Audits)

Local, State, Tribal, and Federal Government Officials

  • If a request for hearing is granted
    • Available at www.nrc.gov