ML021020371
| ML021020371 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/11/2002 |
| From: | Rogge J NRC/RGN-I/DRP/PB7 |
| To: | |
| References | |
| 02-022 | |
| Download: ML021020371 (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 04/11/2002 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) 05000219 Plant/Facility Name Oyster Creek Nuclear Generating Station TAC Number(s) (if available)
Reference Meeting Notice No.02-022 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 OC 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 Reactor Oversight Program - Cycle 2 Nuclear Regulatory Commission - Region I King of Prussia, PA 1
Agenda
" 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 2
Region I Organization I
John Rogge Branch Chief I
W. Lanning Director Division of Reactor Safety R. Crlenjak Deputy Director Regional Specialists I
Three Mile Island Resident Inspectors Daniel Orr Craig Smith Project Engineers Oyster Creek Beaver Valley Neil Perry Resident Inspectors Resident Inspectors Jeffrey Herrera Laura Dudes David Kern Steve Schaffer Steve Dennis Galen Smith 3
H. Miller Regional Administrator J. Wiggins Deputy Regional Administrator A. Blough Director Division of Reactor Projects Brian Holian Deputy Director
NRC Representatives
" Brian Holian, Deputy Director, Division of Reactor Projects
- (610) 337-5080
"* John Rogge, Branch Chief, Division of Reactor Projects
- (610)337-5146
" Laura Dudes, Senior Resident Inspector (609) 693-0702
"* Steve Dennis, Resident Inspector
- (609) 693-0702
"* Robert Summers, Senior Project Engineer
- (610) 337-5282
"* Jeffery Herrera, Reactor Engineer
- (610) 337-5399 4
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
" 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 5
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 6
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 7
NRC Reactor 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 8
Reactor Oversight Process Significance Threshold 9
NRC Regulatory Response
Examples of Baseline Inspections
" Equipment Alignment
" Annual Fire Protection
" Triennial Fire Protection
" Operator Response
"* Plant security
"* 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 S40 hours/yr S60 hrs/yr S100 hrs every 2 years S125 hrs/year 10% every inspection S200 hr every 2 yrs 10
Significance Threshold Green:
White:
Yellow:
Red:
Green:
White:
Yellow:
Red:
Performance Indicators 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 11
Action Matrix Concept Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions 12 Licensee Regulatory Degraded Multiple/Degraded Unacceptable
Response
Response Cornerstone Cornerstone Performance
Substantive Cross Cutting Issue
"* Common cause of inspection findings o 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 13
National Summary of Plant Performance End of Calendar Year 2001 Licensee Response Regulatory Response Degraded Cornerstone Multiple/Repetitive Degraded Cornerstone Unacceptable Total Plants 14 73 25 4
1 0
103
National Summary m Performance Indicator Results 4th Qtr Calendar Green White SYellow "Red Yr 2001 1834 8
0 0
m Total Inspection Findings (April 2001 - December 2001)
Green White SYellow SRed 660 23 2
0 15
Oyster Creek Annual Assessment (April 1 - Dec 31, 2001) 16
Oyster Creek Inspection Activities (Jan 1 - Dec 31, 2001)
- 4700 hours0.0544 days <br />1.306 hours <br />0.00777 weeks <br />0.00179 months <br /> of inspection related activity
- Two resident inspectors
- 12 inspections by regional inspectors
- Included 3 team inspections
- Inspection Findings 13 findings of very low safety significance 1 finding of low to moderate safety significance 17
Plant Performance Summary 4th Quarter 2001 http://www.nrc.gov/NRR/OVERSIGHT/AS SES S/OC/oc-chart.html Evets Rs e
ac Itegriy Irerdes Raito Radiation a dae tio Safeguards SafetySafety Occupational Public Events Sy7stems Integrity Preparedness Sfty SafeyPoeto Performance Indicators 18 D i Piz tio nnlv 11 PKliýbll'ity -
- F T-WL,3 M (L-
Plant Performance Summary 4th Quarter 2(
Reactor Safety 301 Radiation Safeguards Safety Sfgad Radiaton Radiation Physical Safety Safety Protection Most Significant Inspection Findings
- INCo, T7 r, 7
- 4oooo, te H,,
quwl Wseineous3 Additional Inspection & Assessment Information
- Assessment Repors/Inspection Plans:
4Q/2001 30/2001 20/2001 10/2001 Cross Reference Of Assessment Reports
- List of Inspection Reports
- List of Assessment Letters/Inspection Plans 19 FF1-111 - - -
ýsC~ rw (1) ]
Oyster Creek 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 Physical Protection cornerstone
"* All Performance Indicators requiring no additional NRC oversight (Green)
"* Supplemental inspection completed
"* NRC Plans to conduct baseline inspections 20
Oyster Creek Annual Assessment Inspection finding (Physical Protection Cornerstone)
, Weakness in the response strategy observed in one of four force-on-force excercises A follow-up inspection reviewed AmerGen's assessment and corrective actions 21
Oyster Creek Annual Assessment dfM~a~
t..............
.wa Previous substantive cross-cutting issue in Problem Identification and Resolution Identified in Last Annual Assessment Letter SCorrective actions implemented SImprovement noted SRecent findings no longer constitute a substantive cross-cutting issue SContinued inspection through the baseline inspection program 22
Reference Sources
'.Reactor Oversight Process 0 http://www.nrc. gov/NRR/OVERS I GHT/A S S ES S/index.html
" Public Electronic Reading Room 0 http ://www.nrc.gov/reading-rm/adams.html
"* Public Document Room
" 1-800-397-4209 (Toll Free)
" Region I Public Affairs Office SNeil Sheehan or Diane Screnci 1-800-432-1156 (Toll Free) 23
ATTENDANCE LIST FOR APRIL 11, 2002 MEETING BETWEEN NRC STAFF AND AMERGEN ENERGY COMPANY, LLC TO DISCUSS THE RESULTS OF THE NRC'S ASSESSMENT OF THE SAFETY PERFORMANCE AT OYSTER CREEK NUCLEAR GENERATING STATION FOR THE PERIOD 04/01/01 - 12/31/01.
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ATTENDANCE LIST FOR APRIL 11, 2002 MEETING BETWEEN NRC STAFF AND AMERGEN ENERGY COMPANY, LLC TO DISCUSS THE RESULTS OF THE NRC'S ASSESSMENT OF THE SAFETY PERFORMANCE AT OYSTER CREEK NUCLEAR GENERATING STATION FOR THE PERIOD 04/01/01 - 12/31/01.
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