Text

Annual Assessment Meeting Slides
	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)
	v • d • e

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 attachedcopy of meeting handout materials, will be sent to the Document Control Desk on the same day of the meeting; underno 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 04/11/2002 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) (ifavailable)

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 NRC FORM 658 (9-1999) PRINTED ON RECYCLED PAPER This form was designed using InForms

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 H. Miller Regional Administrator J. Wiggins Deputy Regional Administrator I

A. Blough W. Lanning Director Division of Reactor Projects Director Division of Reactor Safety Brian Holian R. Crlenjak Deputy Director Deputy Director I

John Rogge Regional Specialists Branch Chief I

Three Mile Island Project Engineers Oyster Creek Beaver Valley Resident Inspectors Neil Perry Resident Inspectors Resident Inspectors Daniel Orr Jeffrey Herrera Laura Dudes David Kern Craig Smith Steve Schaffer Steve Dennis Galen Smith 3

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 NRC Regulatory Response 9

Examples of Baseline Inspections

" Equipment Alignment S70 hrs/yr

" Annual Fire Protection S35 hrs/yr

" Triennial Fire Protection -200 hrs every 3 yrs

" Operator Response - 125 hrs/yr

"*Plant security S40 hours/yr

" Emergency preparedness S60 hrs/yr

"*Rad release controls S100 hrs every 2 years

" Worker radiation protection S125 hrs/year

" Corrective action program 10% every inspection

" Corrective action program S200 hr every 2 yrs 10

Significance Threshold Performance Indicators Green: 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 11

Action Matrix Concept Licensee Regulatory Degraded Multiple/Degraded Unacceptable Response Response Cornerstone Cornerstone Performance Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions 12

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 73 Regulatory Response 25 Degraded Cornerstone 4 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total Plants 103 14

National Summary mPerformance Indicator Results 4th Qtr Calendar Yr 2001 Green 1834 White 8 SYellow 0 "Red 0 mTotal Inspection Findings (April 2001 - December 2001)

Green 660 White 23 SYellow 2 SRed 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 a daetio Safeguards SafetySafety Evets eRs ac Itegriy Irerdes Raito Radiation Occupational Public Events Sy7stems Integrity Preparedness Sfty SafeyPoeto Performance Indicators Di Piz tio nnlv 11 PKliýbll'ity -

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Plant Performance Summary 4th Quarter 2(301 Reactor Radiation Safeguards Sfgad Safety Safety Radiaton Radiation Safety Safety Physical Protection Most Significant Inspection Findings INCo,

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Wseineous3 Additional Inspection & Assessment Information

Assessment Repors/Inspection Plans: *List of Inspection Reports 4Q/2001

List of Assessment Letters/Inspection Plans 30/2001 20/2001 10/2001

Cross Reference Of Assessment Reports 19

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 IGHT/A SSES 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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