ML020930547

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Meeting Between Nrc/Amergen Energy Mgt to Discuss Results of NRCs Assessment of TMI
ML020930547
Person / Time
Site: Crane Constellation icon.png
Issue date: 04/02/2002
From: Rogge J
NRC/RGN-I/DRP/PB7
To:
References
MN-02-020
Download: ML020930547 (26)


Text

NRC FORM 658 U.S. NUCLEAR REGULATORY COMMISSION (9-1999)

TRANSMITTAL OF MEETING HANDOUT MATERIALS FOR IMMEDIATE PLACEMENT IN THE PUBLIC DOMAIN This form is to be filled out (typed or hand-printed) by the person who announced the meeting (i.e., the person who issued the meeting notice). The completed form, and the attached copy of meeting handout materials, will be sent to the Document Control Desk on the same day of the meeting; under no circumstances will this be done later than the working day after the meeting.

Do not include proprietary materials.

DATE OF MEETING The attached document(s), which was/were handed out in this meeting, islare to be placed 04/02/2002 in the public domain as soon as possible. The minutes of the meeting will be issued in the near future. Following are administrative details regarding this meeting:

Docket Number(s) 05000289 Plant/Facility Name Three Mile Island Nuclear Station Unit 1 TAC Number(s) (if available)

Reference Meeting Notice No.02-020 Purpose of Meeting (copy from meeting notice)

The NRC staff and AmerGen Energy management will discuss the results of the NRC's assessment of the safety performance at TMI for the period 4/1 - 12/31/01 NAME OF PERSON WHO ISSUED MEETING NOTICE TITLE John F. Rogge Chief, Projects Branch 7 OFFICE Region I DIVISION Division of Reactor Projects BRANCH Projects Branch 7 Distribution of this form and attachments:

Docket File/Central File PUBLIC This form was designed using InForms NRC FORM 658 (9-1999)

PRINTED ON RECYCLED PAPER

Annual Assessment Meeting S0**

0* *,,,

C*K ' 0 Reactor Oversight Program - Cycle 2 Nuclear Regulatory Commission -Region I King of Prussia, PA

Agenda "m Introduction

" Review of Reactor Oversight Process

" Discussion of Plant Performance Results

" Licensee Response and Remarks

"* NRC Closing Remarks

" Meeting with the Licensee adjourned

"* NRC available to address questions from the public

NRC Representatives

" Hubert J. Miller, Regional Administrator, Region 1

- (hjml@nrc.gov (610) 337-5299

" Brian Holian, Deputy Director, Division of Reactor Projects

- (beh@nrc.gov (610) 337-5080)

  • John Rogge, Branch Chief, Division of Reactor Projects

- (jfr@nrc.gov (610) 337-5146)

"* J. Daniel Orr, Senior Resident Inspector

- (do@nrc.gov (717) 948-1165)

" Craig Smith, Resident Inspector

- (cxs 1 @nrc.gov (717) 948-1165)

"* Tim Colbum, NRR Project Manager

- (tgc@nrc.gov (301) 415-1402)

NRC Response to 9/11

" Highest Level of Security Maintained

" Comprehensive Review of Security

" Closely Coordinated Response With:

- Our Licensees

- FBI

- Military, State, and Local Agencies

- Intelligence Communities "U Issued Security Advisories

- Increased Patrols

- Augmented Security Capabilities

- Added Barriers and Posts

- More Limited Access

- Enhanced Security Awareness

"* Issued Order on Security

"* NRC Monitoring Enhanced Security

NRC Activities

" Ensure nuclear plants are designed, constructed, and operated safely

" Issue licenses for the peaceful use of nuclear materials in the U.S.

" Ensure licensees use nuclear materials and operate plants safely, and are prepared to respond to emergencies

NRC Performance Goals

" Maintain safety and protect the environment

" Enhance public confidence

" Improve effectiveness, efficiency, and realism of processes and decision making

" Reduce unnecessary regulatory burden

NRC Oversight Activities

" Provides assurance plants are operating safely and in accordance with the regulations

"* Risk informed process

" Objective indicators of performance

" Inspections focused on key safety areas

" Defines expected NRC and licensee actions

Reactor Oversight Process Significance Threshold

Significance Threshold Performance Indicators Green:

White:

Yellow:

Red:

Green:

White:

Yellow:

Red:

Only Baseline Inspection May increase NRC oversight Requires more NRC oversight Requires more NRC oversight Inspection Findings Very low safety issue Low to moderate safety issue Substantial safety issue High safety issue

Examples of Baseline Inspections

" Equipment Alignment

" Annual Fire Protection

" Trienniel Fire Protection

" Operator Response

"* Plant security

" Emergency preparedness

"* Rad release controls

" Worker radiation protection

" Corrective action program

" Corrective action program S70 hrs/yr S35 hrs/yr

-200 hrs every 3 yrs 125 hrs/yr 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />s/yr 60 hrs/yr 100 hrs every 2 years 125 hrs/year 10% every inspecton 200 hr every 2 yrs

Action Matrix Concept Licensee

Response

Regulatory

Response

Degraded Cornerstone

-

T Multiple/Degraded Cornerstone Pefomac Increasing Increasing Increasing Increasing Safety Significance NRC Inspection Efforts NRC/Licensee Management Involvement Regulatory Actions Unacceptable Performance I

National Summary of Plant Performance End of Calendar Year 2001 Licensee R Regulatory esponse

Response

Degraded Cornerstone Multiple/Repetitive Degraded Cornerstone Unacceptable Total Plants 73 25 4

1 0

103

National Summary m Performance Indicator Results 4th Qtr Calendar Yr 2001 Green SWhite SYellow Red m Total Inspection Findings (April 2001 - December 2001)

Green SWhite SYellow Red 1834 8

0 0

660 23 2

0

Three Mile Island Annual Assessment (April 1 - Dec 31, 2001)

Three Mile Island Inspection Activities (Jan 1 - Dec 31, 2001)

  • 5000 hours0.0579 days <br />1.389 hours <br />0.00827 weeks <br />0.0019 months <br /> of inspection related activity m Two resident inspectors performing resident inspections m 15 inspections by regional inspectors o Includes 4 team inspections
  • Inspection Findings 18 findings of very low safety significance 1 finding of low to moderate safety significance previous assessment period "counted" in the from assessment period from April 1 - December 31, 2001

Plant Performance Summary 4th Quart.er 2001 WWW.NRC.GOV/NRR/OVERSIGHT/ASSESS/TMI1/tmil chart.html Performance Indicators Last Modified: January 24, 2002 Occupational E,

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Plant Performance Summary 4th Quarter 2001 Most Significant Inspection Findings 4012001 301200-1

[Finingwfhj 2Q/2001

,ofidg 10o2001 InspegcionI-eI Additional Inspection & Assessment Information Assessment Reports/Inspection Plans:

4 0/2001 3Q/2001 20/2001 10/2001

-*1 Cross Reference Of Assessment Reports List of Inspection Reports 1 List of Assessment Letters/Inspection Plans Last Modified: February 13, 2002 It,

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Three Mile Island Annual Assessment (April 1 - Dec 31, 2001)

"* Operated safely

"* Fully met all cornerstone objectives

"* Regulatory Response Band of Action Matrix One Inspection Finding of low to moderate safety significance (White) in the Mitigating Systems cornerstone identified in previous assessment cycle and "counted" on March 31, 2001 Substantive cross-cutting issue in the human performance area (several green findings) identified in the Barrier Integrity, Mitigating Systems, and Initiating Events cornerstones

"* All Performance Indicators requiring no additional NRC oversight (Green)

"* NRC Plans to conduct baseline inspections

Three Mile Island Annual Assessment Substantive cross-cutting issue in Human Performance identified

" Procedure adherence

" Equipment monitoring This issue will be inspected through the baseline inspection program

Three Mile Island Annual Assessment Procedure adherence (Barrier integrity, Mitigating systems, and Initiating events cornerstones)

Several Green findings:

, Procedures controlling reactor coolant system temperature Component heatup and cooldown rates Alignment of plant components

Three Mile Island Annual Assessment Equipment monitoring (Mitigating Systems cornerstone)

Multiple Green findings:

Untimely initiation of corrective actions to evaluate a breaker failure Delays in reporting out-of-specification equipment parameters

, Inadequately established inservice test acceptance criteria

Reference Sources

,Reactor Oversight Process l http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/inde x.html

  • Public Document Room S1-800-397-4209 (Toll Free)

Substantive Cross Cutting Issue

" Common cause of inspection findings

, Human performance

, Problem Identification and Resolution Safety conscious work environment

" Multiple inspection findings with a common cause

" Common cause documented in an assessment letter

" Focus licensee and NRC activities