ML020930547
| ML020930547 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| 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 announcedthe 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 proprietarymaterials.
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) (ifavailable)
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 NRC FORM 658 (9-1999) PRINTED ON RECYCLED PAPER This form was designed using InForms
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: 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
Examples of Baseline Inspections
" Equipment Alignment S70 hrs/yr
" Annual Fire Protection S35 hrs/yr
" Trienniel Fire Protection
-200 hrs every 3 yrs
" Operator Response 125 hrs/yr
"*Plant security 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />s/yr
" Emergency preparedness 60 hrs/yr
"*Rad release controls 100 hrs every 2 years
" Worker radiation protection 125 hrs/year
" Corrective action program 10% every inspecton
" Corrective action program 200 hr every 2 yrs
Action Matrix Concept T
Licensee Regulatory Degraded Multiple/Degraded Unacceptable Response Response Cornerstone Cornerstone Performance Pefomac I
Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions
National Summary of Plant Performance End of Calendar Year 2001 Licensee R esponse 73 Regulatory Response 25 Degraded Cornerstone 4 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total Plants 103
National Summary mPerformance Indicator Results 4th Qtr Calendar Yr 2001 Green 1834 SWhite 8 SYellow 0 Red 0 mTotal Inspection Findings (April 2001 - December 2001)
Green 660 SWhite 23 SYellow 2 Red 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 mTwo resident inspectors performing resident inspections m15 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 from previous assessment period "counted" in the 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 Occupational E, oý-UrQ Control S or A ns'UVitfi 11L r,-ýz ERO Drill Of N 0 rrr, a I'H e at, ý Petý-,onnl Participation 7 S cre e r, in fog ra rn (C U n p 11.1,,,,ýýd _P ha n q Last Modified: January 24, 2002
Plant Performance Summary 4th Quarter 2001 Most Significant Inspection Findings 4012001 301200-1 [Finingwfhj It,
ýtl s I 2Q/2001 ,ofidg 111151-2 1:11d.,
-ýrE-r 10o2001 InspegcionI-eI Additional Inspection & Assessment Information
- Assessment Reports/Inspection Plans:
- List of Inspection Reports 4 0/2001 1 List of Assessment Letters/Inspection Plans 3Q/2001 20/2001 10/2001
-*1 Cross Reference Of Assessment Reports Last Modified: February 13, 2002
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 Electronic Reading Room "http://www.nrc.gov/reading-rm/adams.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