ML031010299

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Enclosures to 04/01/2003 Waterford End-of-Cycle Meeting Summary. Includes Attendance List & Copy of Slides Presented
ML031010299
Person / Time
Site: Waterford Entergy icon.png
Issue date: 04/01/2003
From:
NRC Region 4
To:
References
Download: ML031010299 (38)


Text

ENCLOSURE 1 END-OF-CYCLE MEETING ATTENDANCE UCENSEE/FACILITY Entergy Operation, Inc. (EQI)

Waterford S DATE/TIME April 1, 2003 6:30 p.m. -

LOCATION St Charles Parish Courthouse Council Chambers NAME (PLEASE PRIni ORGANIZATION f4bo 7MT 61-s-ol i-9ad'ts

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END-OF-CYCLE MEETING ATTENDANCE LICENSEE/FACILITY Entergy Operation, Inc. (E01)

Waterfor 3.l D)ATE/TIME April 1, 2003 6:30 p.m..l LOCATION St Charles Parish Courthouse Coundil Chambers PRINT

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ENCLOSURE 2 Nuclear Regulatory Commission ANNUAL PERFORMANCE ASSESSMENT OF WATERFORD 3 April 1, 2003

NRC Meeting Purpose

  • Meeting with Licensee and Public
  • Inform Public of Plant Performance
  • Review NRC and Industry Activities

NRC Meeting Guidelines

  • Registration Table
  • Handouts
  • Questions and Answers
  • Feedback Forms

NRC Performance Goals

  • Maintain public safety and protect the environment 8 Enhance public confidence
  • Improve:

Effectiveness Efficiency Realism of processes and decision making

  • Reduce unnecessary regulatory burden

Regional Organization Reinal, Administ~ratorl Ri V

Director~

Division of Reactor Projects Division of Reactat DeptyeDrecor Res hident I GbpectorS:Ch Chef l

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fhef iChief Chief Branch Branch Branch

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Waterford 3

Meeting Agenda

  • Regulatory Oversight
  • Findings ai
  • Additional Assessment Focus Areas
  • Questions and Answers

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Regulatory Oversight Process I--.

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Overall NRC Effort 3000 1561 X Headquarters -2378 2378

  • Regional - 1561
  • Resident - 3000 Total hours - 6939 ItR REttt4

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Comprehensive Oversight Program NRC's PUBLIC HEALTH AND SAFETY Overall AS A RESULT OF, CIVILIAN NUCLEAR REACTOR SafetyOPRTN Mission Strategic Performancel IREACOR i

PLANT Areas SAFETY AFEYr IRITY w

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NRC Oversight Activities

  • Provide assurance plants are:

- Operating safely

- Complying with regulations

  • Based on a logical and sound framework
  • Inspections focused on key safety areas
  • Utilizes objective performance indicators
  • Assessment process triggers regulatory actions

Reactor Oversight Process Strategic Performance areas Safety Cornerstones E i

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Baseline Inspection Program

  • Gathers objective evidence of plant safety
  • Conducted at all plants
  • Focuses on safetymsignificant

- systems

- components

- activities

- events top REQ,,t A

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Baseline Inspection Program

  • Inspection reports describe significant findings and non-compliance
  • Inspection reports are publicly accessible wvww.NRC.gov/readingmrm/adams.html

Event Follow-up and upplemental Inspections

  • Review events for significance
  • Follow-up significant inspection findings
  • Determine causes of performance declines 0 Provide for graduated response 0

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Reactor Oversight Process Safety Significance

- very low WHITE

.U YELLOfWf m low to moderate

- substantial

- high

Performance Indicator ragrm

  • Licensee monitors key safety parameters
  • Data supplied to NRC quarterly e Performance indicator data posted on the NRC website www. N RC.gov/N RR/OVERSI G HTIASSESSI WAT3/wat3 chart.html by REGaL

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Performance Indicators Unplanned Scrams per 7000 critical hours 1Q102 0

5 10 15 20 25 Thresholds:

White >3.0, Yellow >6.0, Red >25.0 Unplanned scrams per 7000 critical hours 2Q/02 3Q/02 4Q/02 Actual scrams 0

0 0

Critical hours 1806.0 2208 2209 Indicator value 0

0 0

Key Aspects of the Assessment Progra

  • Objective review of licensee
  • "AAction Matrix" to determine response in three areas:

Inspection

- Management Involvement

- Regulatory Actions performance agency

  • Plant specific assessment letters
  • Information on NRC public web site PEA Rt R ZGS

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Plant Safety Performance Summary

  • Performance Indicator Results
  • Inspection Results

Inspection Results NRC and Licensee identified inspection findings were of very low safety significance No special or supplemental inspections necessary Substantive crosscutting issue (Problem Identification and Resolution)

Substantive Crosscutting Issue Long-standing degraded conditions not always fully addressed S ymptomatic conditions existed for extended periods before being identified and corrected X Some degraded conditions not effectively evaluated and corrected e Problems identified in both mitigating systems and barrier cornerstones R

Performance Indicator Results The 18 performance indicators were within the Licensee Response Band

ROP Action Matrix Summary for 2002 Licensee Regulatory Degraded Multilpe.

Unacceptable

Response

Cornerstone Repeitive6 Performance 0; ;

A 0 0 00Degraded0

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Nationwide 59 33 7

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Region IV 13 5

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0 (Note: Nationwide number does not include Davis Besse)

Assessment Conclusion

  • Licensee effectively managed:

- Reactor safety

- Radiation safety

- Plant security

  • Waterford-3 operated in a manner that protected the health and safety of the public P,2 REG4

LICENSEE RESPONSE

Additional Focus Areas INRC Responds As-Needed

Nuclear Industry Issues

  • Security at Nuclear Power Plants pS Rea&

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Post DaviSMBesse Licensee Actions

  • Visual Inspection of Reactor Vessel Head Penetrations NRC Actions
  • Observation of Licensee Inspections and Examinations
  • Independent Inspection pRRE 0IJ 0

security & Safeguards Update Creation of Office of Nuclear Security and Incident Response

  • Top-to-Bottom Review of Security Program Initiated
  • Issuance of Orders/interim Compensatory Measures c Verification of Licensee Action on ICMs

Security & Safeguards Update e Proposed Revisions to Design Basis Threats Pending Orders on Fatigue/Guard:

Training

  • Initiation of Pilot Program for Force-on-Force Exercises
  • Issuance of Access Authorization Order ARG>'

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Future Outlook

- Not new

- Licensee's taking advantage of improved power measurement techniques E Better analytical methods demonstrate that reactor power can be increased without significant reductions in safety margin e NRC has approved more than 80 applications to increase reactor power

  • Approximately 51 applications for power uprates expected over next 5 years b

Future OUtl0

- A recent initiative

- Applications for 14 units have been approved 16 applications are currently under review v Early Site Permits Three applications expected in 2003

Conclusions

  • Assured Public Safety
  • Flexible/Predictable Response
  • Risk-Informed Programs 41CI.:,A Rea",

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Contacting the NI C

  • Report an Emergency:

(301) 816-5100 (collect)

  • Report a Safety Concern:

(800) 695-7403 or Allegation@nrc.gov

  • General Information or questions:

www.nrc.gov Select "What We Do"

>I efai REC& -1 Ad"I O

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Contacts for Additional Information

  • Regional Public Affairs Officer

- Victor Dricks

- Phone: (817) 860 - 8128&

  • State Liaison Officer

- William (Bill) Maier

- Phone: (817) 860 - 8267 st R EQ&4