ML020870172

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1) 03/26/2002 Limerick Generating Station Unit 1 & 2 Annual Assessment Meeting Slides Presented by Region I. 2) 03/26/2002 Limerick Generating Station Slides for NRC Public Meeting Presented by Exelon
ML020870172
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 03/26/2002
From: Shanbaky M
Reactor Projects Region 1 Branch 4
To:
Exelon Generation Co
References
02-016
Download: ML020870172 (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 03/26/2002 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) 05000352 and 05000353 Plant/Facility Name Limerick Generating Station Units 1 and 2 TAC Number(s) (if available)

Reference Meeting Notice 02-016 Purpose of Meeting (copy from meeting notice)

The NRC staff and Exelon management will discuss the results of NRC's assessment of the safety performance of Limerick for the period of April - December 31, 2001.

NAME OF PERSON WHO ISSUED MEETING NOTICE TITLE Dr. Mohamed Shanbaky Branch Chief OFFICE Region I DIVISION Division of Reactor Projects BRANCH Branch 4 Distribution of this form and attachments:

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

Annual Assessment Meeting Reactor Oversight Program - Cycle 2 Nuclear Regulatory Commission -Region I King of Prussia, PA

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

Region I Organization H. Miller Regional Administrator J. Wiggins Deputy Regional Administrator A. Blough

]W.

Lanning Director Division of Reactor Projects Director Division of Reactor Safety, Brian Holian R. Crlenjak SDeputy Director Deputy Director Mohamed Shanbaky Other Regional Specialists M Branch ChBef Branch Chief-n R

Peach B to Pr ec En Ine r

Lim erick Susquehanna Resident Inspectors Donm F

Ire Resident Inspecttors' Resident IspectoS Anthony McMurtray Joseph!n Tair r BrtS M

Hnsello Mike Buckley Shriramn lyer Blake Welling John Richmond

NRC Representatives

"* Brian Holian, Deputy Director, Division of Reactor Projects

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

  • Mohamed Shanbaky, Chief Reactor Projects Branch

- (mmsl@nrc.gov (610) 337-5209)

Chris Gratton, Project Manager, NRR

- (cxgl@nrc.gov (301) 415-1055)

Don Florek, Senior Project Engineer

- (djfl@nrc.gov (610) 337-5185)

Art Burritt, Senior Resident Inspector

- (albl@nrc.gov (610) 327-1344)

Blake Welling, Acting Senior Resident Inspector

- (bdw@nrc.gov (610) 327-1344)

Reference Sources

"* Reactor Oversight Process o http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html

"* Public Electronic Reading Room http://www.nrc.gov/reading-rm/adams.html

"* Public Document Room

  • 1-800-397-4209 (Toll Free)

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

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

Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Regulatory Response

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

"* Corrective action program S70 hrs/yr

- 35 hrs/yr

-200 hrs every 3 yrs S125 hrs/yr

-40 hours/yr

-60 hrs/yr

-100 hrs every 2 years

-125 hrs/year

-10% every inspection

-200 hr every 2 yrs

Significance Threshold ONFAMEM~m I

A-White:

Yellow:

White:

Yellow:

Performance Indicators 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

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

Substantive Cross Cutting Issue

  • Common cause of inspection findings SHuman performance SProblem Identification and Resolution Safety conscious work environment m Multiple inspection findings with a common cause m Multiple cornerstones m May be documented in an assessment letter
  • Focus licensee and NRC activities

National Summary of Plant Performance End of Calendar Year 2001 Licensee Response 74 Regulatory Response 24 Degraded Cornerstone 4

Multiple/Repetitive Degraded Cornerstone 1

Unacceptable 0

Total Plants 103

National Summary

  • Performance Indicator Results 4th Qtr Calendar Yr 2001 Gjreen 18 833t

, White 8

  • Yellow 0
  • Total Inspection Findings (April 2001 - December 2001)

Greens 660

' White 23 SYellow 2

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Limerick 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 Unit 1 and 2 Emergency Preparedness cornerstone

- One Inspection Finding of low to moderate safety significance (White) in Unit 2 Barrier Integrity cornerstone

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

"* Supplemental inspections to be performed

Limerick Inspection Activities (Jan 1 - Dec 31, 2001)

  • 5800 hours0.0671 days <br />1.611 hours <br />0.00959 weeks <br />0.00221 months <br /> of inspection related activity
  • Two resident inspectors performing resident inspections
  • 17 inspections by regional inspectors o Includes 4 team inspections
  • Inspection Findings 15 findings of very low safety significance 2 findings of low to moderate safety significance

Limerick I and 2 Performance Indicators 4Q/2001 http://www.nrc.goviNRR/OVERSIGHT/ASSESS/LIMI/liml l chart.html http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/LIM2/lim2 chart.html RcRadiation Safeguards SafetySafety Iniiatng M~tgatngBarier Emrgecy Occ-upationaP u Pb i~cT BareRadiation aito Events~~

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safety Pproht-c-ti-on Performance Indicators

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Limerick 2 Inspection Finding Summary http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/LIM2/lim2_chart.html "ROeacor I Radiation" Sareguas nitiating Alitigsting Barrier Emergency Radiation Radieton Pk/sicat Events Systems integrity Preparedness Safety Safety Most Significant Inspection Findings Additional Inspection & Assessment Information 4012001 30/2001 2Qf2001 I Qf2001 Ell

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Plans.:

40/2001 30/2001 2Q/2001 1Q/2001 Cross Reference OfAssossment Reports

  • 0- List of Inspection Reports List of Assessment Letters/Inspection Plans Lest Mhodied r

Merch 1. 2002

Emergency Preparedness Cornerstone

"* Unit 1 and 2 White finding - November 2001 Inadequate critique of an emergency preparedness drill

"* Supplemental inspection - planned for May 2002

"* Unit 1 and 2 Severity Level III Violation - October 2001 SFalse records and installation of improper jumpers by contractor personnel on several off-site sirens

"* Inspection activity completed o Actions were acceptable

Barrier Integrity Cornerstone

  • Unit 2 White finding - January 11, 2002 SInadequate measures to identify a degraded safety relief valve
  • Supplemental Inspection planned for June 2002

Potential Cross Cutting Issue Human Performance Thoroughness of Technical Evaluations

- Inadequate measures to identify a degraded safety relief valve (White)

Mitigating System

- Low standby liquid control relief valve set points (Green)

- Loose safety relief valve tail pipe studs (Green)

  • Exelon is addressing issues in their corrective action program

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Limerick Generating Station NRC Public Meeting March 26, 2002

INPO Performance Index Unit I = 100 Unit 2 =100 Station = 100 Best Quartile = 98.3 a

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Year 2001-Accomplishments

"+ Safe and Reliable Operation of the Units

"+ Industry Top Quartile Performance

- Industrial Safety

- Safety System Reliability Radiation Exposure

"+ Material Condition Improvements

- System Health Improvement Plan

- Plant Health Committee

- Project Review Committee

Emergency Preparedness Critique Corrective Actions

"+ Standards

"+ Instructor/Evaluator Training

"+ Procedure Improvements

"+ Follow-up Training/Evaluation

Siren Corrective Actions

"+ Contractor Oversight

"+ Equipment Upgrades

"÷ Performance Monitoring

2N Safety Relief Valve (SRV)

Corrective Actions

"+ 2N SRV Replaced

"+ Root Cause Determined

"+ Corrective Actions

-Valve Manufacturing Requirements

- Revised Performance Monitoring Criteria

"+ Additional Testing

Focus Areas

"+ Security

"+ Emergency Preparedness

"+ Human Performance

"+ Equipment Reliability

"+ Corrective Action Program