ML021010147

Annual Assessment Meeting Slides

ML021010147
Person / Time
Site:	Beaver Valley
Issue date:	04/09/2002
From:	Rogge J NRC/RGN-I/DRP/PB7
To:
References
M-02-21
Download: ML021010147 (32)

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, is/are to be placed 04/09/2002 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) 05000334,05000412 Plant/Facility Name Beaver Valley Power Station TAC Number(s) (if available)

Reference Meeting Notice 02-21 Purpose of Meeting (copy from meeting notice)

NRC Staff and FENOC mgt will discuss the results of the NRC's assessment of the safety performance at Beaver Valley for the period 04/01/01 - 12/31/01.

NAME OF PERSON WHO ISSUED MEETING NOTICE--

TITLE John F. Rogge Chief, Projects Branch 7 OFFICE USNRC 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 Nuclear Regulatory Commission - Region I King of Prussia, PA YA, 7ýý

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

NRC Representatives

"* John Rogge, Branch Chief, Division of Reactor Projects

- (610)337-5146

"* David Kern, Senior Resident Inspector

- (724) 643-2000

" Galen Smith, Resident Inspector

- (724) 643-2000

"* Neil Perry, Senior Project Engineer

- (610) 337-5225

"* Jeffrey Herrera, Reactor Engineer

- (610) 337-5399

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

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 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

Reactor Oversight Process Significance Threshold NRC Regulatory Response I

Examples of Baseline Inspections

" Equipment Alignment

" Annual Fire Protection

" Triennial Fire Protection

" Operator Response

"* Plant security

" Emergency preparedness

"* Rad release controls

" Worker radiation protection

" Corrective action program "U Corrective action program

_ 80 hrs/yr 35 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 inspection 200 hr every 2 yrs

Green:

White:

Yellow:

Red:

Green:

White:

Yellow:

Red:

Significance Threshold 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

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

Response

Response Cornerstone Cornerstone Performance

Substantive Cross Cutting Issue

"* Common cause of inspection findings o Human performance SProblem 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

National Summary of Plant Performance End of Calendar Year 2001 Licensee Response Regulatory Response Degraded Cornerstone Multiple/Repetitive Degraded Cornerstone Unacceptable Total Plants 73 25 4

1 0

103

National Summary

• Performance Indicator Results (4th Qtr Calendar Yr 2001)

SGreen 1834 SWhite 8

SYellow 0

SRed 0

• Total Inspection Findings (April 2001 - December 2001) o Green 660 SWhite 23 SYellow 2

S Red 0

Beaver Valley Inspection Activities (Jan 1 - Dec 31, 2001)

• 5700 hours0.066 days <br />1.583 hours <br />0.00942 weeks <br />0.00217 months <br /> of inspection related activity

• Two resident inspectors performing inspections

• 16 inspections by regional inspectors o-Included 4 team inspections

• Inspection Findings o-14 findings of very low safety significance

Plant Performance Summary 4th Quarter 2001, Unit 1 http://WWW.NRC.GOV/NRR/OVERSIGHT/ASSESS/BVI/bv lchart.html Performance Indicators Last Modified: March 1. 2002

Plant Performance Summary 4th Quarter 2001, Unit 1 Most Significant Inspection Findings Findnýwfth o -ncln coordesignationI hi:qatr7ýi;qu te wo t~rii-Nýfindfnfining th-ý Rey*

thi urý Sr*

in di n c4#

st]fi n ig 101 101 101 101

Plant Performance Summary 4th Quarter 2001, Unit 2 http://WWW.NRC.GOV/NRR/OVERSIGHT/ASSESS/BV2/bv2_chart.html Performance Indicators

-V -

Y Reactor Coolant

,System Loýýakage

Plant Performance Summary 4th Quarter 2001, Unit 2 Most Significant Inspection Findings 4Q02001 3Q02001 2Q02001 0Q1200I Mficeianeous I

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Beaver Valley Annual Assessment (April 1 - Dec 31, 2001)

"* Operated safely

"* Fully met all cornerstone objectives

"* Licensee Response Band of Action Matrix All Inspection Findings of very low safety significance (Green)

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

"* NRC Plans to conduct baseline inspections

Reference Sources

" Reactor Oversight Process Shttp

//www.nrc.gov/NRR/OVERSIGHT/AS SES S/index.html

"- Public Electronic Reading Room Shttp

//www.nrc. gov/reading-rm/adams. html

"* Public Document Room "0 1-800-397-4209 (Toll Free)

" Region I Public Affairs Office SNeil Sheehan or Diane Screnci S1-800-432-1156 (Toll Free)

B VPS Senior Management Team

"* Lew Myers, Senior Vice President

"* Bill Pearce, Plant General Manager

& Bob Donnellon, Director, Maintenance

• Fred vonAhn, Director, Engineering

• Marc Pearson, Director, Services & Projects e Jim Lash, Director, Personnel Development FENOC I.

Desired Outcomes

"* Operational Performance Improvements Continue to be Addressed

"* Plant Materiel Condition Continues to Improve

• Corrective Action Program - Building Block for Improving both Reliability and Safety Margin

• Investing In Long Term Initiatives with Full Potential Program and Personnel Initiatives FENOC Operations Improvements

"* Operations Resource Plan for Operational Excellence

"* Outage Performance

"* Operational Safety

- Worker Dose Reductions 2.o,

- Minimizing On-Line Risk

- Industrial Safety FENOC

Engineering - Improving Plant Safety Margin

• tatent Issues Review Program 9 Corrective Action Program e Formal Root Cause Investigation Training 9 Major Equipment Design Improvements

- PSA Model Update

- River Water Pumps

- Charging Pumps

- Residual Heat Removal Pump FENOC Maintenance - Improving Materiel Condition

° Preventive Maintenance

• Corrective Maintenance

• Major Equipment Reliability Program

• Maintenance Rule A-1 Systems

• Maintenance Training FENOC

Achieving Our Potent/al

• Human Performance Initiatives

• Self Assessment Program 9 INPO Assist Visits & Benchmarking a Full Potential Program

- Containment Conversion, Power Uprate, S/G & Vessel Head Replacement

- Partnering with Westinghouse FENOC I

Conclusions

"* Pleased with Assessment that all Objectives were Met

"* Continue with Materiel Condition Improvements

"* Continue to Address Human Performance

- Continue to Focus on Strong Management Involvement and Technical Competence to Find and Address Latent Issues FENOC

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