ML031190602

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Slides for Annual Assessment Meeting
ML031190602
Person / Time
Site: Beaver Valley
Issue date: 04/29/2003
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NRC Region 1
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Download: ML031190602 (17)
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Beaver Valley Annual Assessment Meeting Reactor Oversight Program - Cycle 3

-41 Nuclear Regulatory Commission - Region I King of Prussia, PA Agenda

  • Introduction
  • Review of Reactor Oversight Process
  • National Summary of Plant Performance
  • Discussion of Plant Performance Results
  • Licensee Response and Remarks
  • General Topics: Security Update and Self-Improvement Efforts
  • NRC Closing Remarks
  • Break
  • NRC available to address public questions

NRC Representatives

  • A. Randolph Blough, Director, Division Reactor Projects

- (610) 337-5230

  • John Rogge, Acting Deputy Division Director, DRP

- (610)337-5146

  • Tim Colburn, Project Manager, NRR

- (301)415-1402

  • Dave Kern, Senior Resident Inspector

- (724) 643-2000

- (724) 643-2000

  • Richard Barkley, Senior Project Engineer

- (610) 337-5065

- (610) 337-5225 Region I Organization l- HubErt"1tfter l E

Regional Administrator James Wiggins Deputy Regional Administrator EA.Rando~ps- Wfflnrij~rrg Director Division of Reactor Projects Director Division of Reactor Safety John Rogge Richard Crienjak Acting Deputy Director Deputy Director

= Neil-t rr -RegfonatSaecialists-Acting Branch Chief B Ie=eyn uPrqjeCtEinesrg Resident Inspectors Richard Barkley David Kern Jorge Hemandez Galen Smith

Reactor Oversight Process I

, Ct;Action

' f l 0jMatrix d0' If IIdI I Regulatory Response IL 0 Examples of Baseline Inspections
  • Equipment Alignment -92 hrs/yr
  • Triennial Fire Protection -200 hrs every 3 yrs
  • Operator Response A125 hrs/yr
  • Rad Release Controls 100 hrs every 2 yrs
  • Worker Radiation Protection -100 hrs/yr
  • Corrective Action Program -200 hrs every 2 yrs
  • Corrective Action Case Reviews -60 hrs/yr

S iF Ij Significance Threshold Performance Indicators Green: Only Baseline Inspection White: May increase NRC oversight Yellow: Requires more NRC oversight Red: Requires more NRC oversight Insnection Findings g . _ w Green: Very Low safety issue White: Low to moderate safety issue Yellow: Substantial safety issue Red: High safety issue Action Matrix Concept Licensee Regulatory Degraded Multiple/Rep. Unacceptable Response Response Cornerstone Degraded Performance Cornerstone I>

Z > =I>

Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions I

National Summary of Plant Performance Status at End of ROP Cycle 3 Licensee Response 75 Regulatory Response 24 Degraded Cornerstone 2 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total Plants 102

  • Davis-Besse is in IMC 0350 process National Summary
  • Performance Indicator Results (at end of ROP Cycle 3)
  • Green 1835 White 5
  • Yellow 0
  • Red 0
  • Total Inspection Findings (ROP Cycle 3)

I Green 783

. White 30

. Yellow 1

  • Red 2

Beaver Valley Assessment ResulIts (Jan 1 - Dec 31, 2002)

Regulatory Response column of the Action Matrix for 2002 due to a White finding in the Emergency Preparedness area (cornerstone objectives fully met)

I *Supplemental inspection performed Feb. 24-28, 2003, of causal assessment/corrective actions for the White Finding BVUnit 1 -Performance Indicators WWW.NRC.GOV then click Reactor Oversight Process Reactor on SvrsghtP s Safety Safety Barrier F[ gaEm a7~7 fL~ f77Z7ya Eyateta Mgang bntegrnty j jJo Saiew Performance Indicators bp_"24~ Aik JIQM,9 Ltant IM ,

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Performance Indicator - BV Unit 1 Unplanned Scrams per 7000 Critical Hrs a a C a a a 0 -

5 - I 28 2.8 10 -

15 -

20 -

Thresholds: White > 3.0 Yellow > 6.0 Red > 25.0 BV Unit 2 -Performance Indicators WWW.INRC.GOV then click Reactor OversighftPr

.. A;

s. _. . A<

-e-s Reactor Radiation Safeguards Safety §Safety e y m n P 1Padiation Safety IPrafetyon Performance Indicators

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I

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Performance Indicator - BV Unit 2 I I Drill/Exercise Performance N N i

N N a a a a a a N N a a I'll i

100.0% -6m 90.0% 2%

80.0%

70.0%

60.0%

50.0%

Thresholds: White < 90.0% Yellow < 70.0%

Beaver Valley Inspection Activities (Jan 1 - Dec 31, 2002)

. 5264 hours0.0609 days <br />1.462 hours <br />0.0087 weeks <br />0.002 months <br /> of inspection related activities

  • 18 regional inspector visits
  • Included 3 team inspections
  • Inspection Findings 10 findings of very low safety significance (Green)
  • 1 finding of low to moderate significance (White)

I I

BV Unit 1 -Inspection Results I

t Rdaon Segard Saft OccupPtiotl l Pubic Sael ll R Saoto fetysn Protect ron l

- Most Significant Inspection Flndings 4Q2002 BsatWl2 M MW M

2Q02002 1012002 lM W W=

Additlonal Inspection &Assessment Inform

  • Assessment Reports/inspection Plans:
  • List of Inspection Reports 4Q/2002
  • List of Assessment Letters/nspection Plans 3Q/2002 i

BV Unit 2 -Inspection Results

9. -i Reactor Radiation Sfgad Safety I SafetyIa

. Pt b i Miratn Iniiain Bare mtec Rdain Pyra

<ieinl i

I Most Slgnrificant Inspection Findings -

4012002 Ne 31 U 1 1.!iWF 10~

i 3i : "

3Q02002 i

P 0 Rba ,E i

IQ/2002 tq 2 0 W::t)i Additional Inspection & Assessment Information

  • Assessment Reports/inspection Plans + List of Inspection Reports 4012002 + List of Assessment Letters/inspection Plans

Beaver Valley Annual Assessment Summary January 1, 2002 - December 31, 2002 FENOC operated Beaver Valley Units 1 & 2 in a manner that preserved public health and safety

  • All cornerstone objectives were met with only one White finding identified (EP performance deficiency with PHADs inoperability)
  • NRC currently plans baseline inspections at BV for the remainder of the assessment period Licensee Response and Remarks Mark Bezilla Site Vice President, Beaver Valley Units 1 & 2 First Energy Nuclear Operating Company

NRC Security Program Update

  • NRC has issued Orders (February 2002):
  • Increased Patrols o Augmented Security Capabilities
  • Added Barriers and Posts

[ Enhanced Personnel Screening for Access

  • Enhanced Security Awareness
  • Office of Nuclear Security and Incident Response Formed (April 2002)
  • Threat Advisory and Protective Measure System (August 2002):
  • NRC established five level threat advisory and protective measure system based on Homeland Security Advisory System NRC Security Program Update (continued)
  • Access Authorization Order (January 7, 2003)
  • Force-on-Force Exercises (February 2003)
  • Training Order (TBD)
  • Fatigue Order (TBD)
  • Design Basis Threat (TBD)

Emergency Response

  • Office of Nuclear Security and Incident Response has primary responsibility
  • Typical other federal agencies involved:

- Federal Emergency Management Agency

- Department of Energy

- Environmental Protection Agency

- Federal Bureau of Investigation NRC Self-Improvement Efforts

.I.1111~~~,~ ., . . . S ASH= : = = _-~~-" - "~-,,~~ . ..... --. ... I - - - .S =

  • Security Enhancements I

I

  • Performance Indicator Program
  • Davis-Bes,(Bse Lessons Learned Task Force

Reference Sources

  • Public Document Room 1-800-397-4209 (Toll Free)

Simplified Pressurized Water Reactor Containmernt p -

R IS/G RTurbine nMain K G~i7 Ce r RCPI ReaLtor Coolant RCPJ .

Feedwater System ,

Pump

BEAVER VALLEYPLANTANNUAL ASSESSMENT MEETING - April 22, 2003 FENOC a.C-w.kS atu Cot~

BVPS Presenters

  • Mark Bezilla - Site Vice President
  • Jim Lash - Plant General Manager
  • Bob Donnellon - Director, Maintenance/Work Management
  • Fred von Ahn - Director, Engineering/Projects FENOC 1

lDesired Outcomes

  • Operational Improvement
  • Improving Materiel Condition
  • Corrective Action Program - Building Block for Improving both Reliability and Safety Margin
  • Investing in Long Term Initiatives with the Plant and our People FENOC

, =;I-~.

Operational Improvement

  • Safety

-Safety Culture/Safety Conscious Work Environment

- Emergency Preparedness

- Security

- Radiological/Industrial

  • Human Performance Initiatives

Maintenance Improving Materiel Maintenance - Improving materiel Condition

  • Preventive Maintenance
  • Corrective Maintenance
  • Major Equipment Reliability Program FENOC 17,l117 Engineering - Improving Plant Safety
  • Corrective Action Program
  • Latent Issues Review Program
  • Problem Solving and Decision Making
  • Full Potential Program

- Unit 1 Steam Generator and Vessel Head Replacement

- License Renewal FENOC 3

Summary

  • All Cornerstone Objectives were Met

. Safe and Reliable Operation

  • Materiel Condition Improvements
  • Human Performance
  • Strong Management Involvement and Technical Competence to Find and Address Issues FENOC 4

TOTAL P.05

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