ML112220605

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Response to Enforcement Action EA-03-197 from Firstenergy Nuclear Operating Co. Entitled,Emergency Service Water Pump Coupling Failure
ML112220605
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 12/17/2003
From:
FirstEnergy Nuclear Operating Co
To:
NRC/RGN-III
References
EA-03-197
Download: ML112220605 (27)


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Desired Outcome

  • Ensure a consistent understanding of the issue
  • Present the causes and corrective actions
  • Discuss further actions
  • Present results from updated safety assessment

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Background

  • Repairs completed well within the discretionary period

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Root Cause Evaluated

  • Evaluated the environment/application
  • Conducted a detailed laboratory analysis
  • Performed a detailed stress analysis *
  • Fracture mechanics were evaluated

Root Cause Conclusion

- Improper installation due to inadequate procedure

- Susceptible material

- Environment considered in design/operation

  • Corrective actions address both installation and material

Extent of Condition Examined

  • Safety and non-safety related pumps were included
  • Similarities in configuration, couplings, and maintenance instructions were examined

- ESW Pump "8" - found to be identical

- ESW Pump "e" - similar

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Corrective Actions ESWPumps

  • Pump operability has been assured
  • Further actions will be taken to assure continued reliability *

- ESW Pump "A" rebuild in 2004

- ESW Pump "8" inspect in 2004, rebuild in 2007

- ESW Pump "e" rebuild in 2004

Corrective Actions Procedures and Material

  • Revision of procedures for ESW pumps
  • Material upgrades for all ESW pumps *

- New requirements for heat treatment, hardness, and documentation

- 100% NDE of coupling sleeves e

Collective Significance Review Process

  • Systematic evaluation of a collection of documented events or conditions
  • Multidiscipline Review Team formed November 3, 200;3
  • Scope includes four mitigating system equipment failures over last year

Collective Significance Review - Matrix Matrix used - Categories/Facts

  • Problem category examples:

- Procedure guidance *

- Training

- Material deficiencies

- Design deficiencies

  • Problem fact examples:

- Event type

- Organization

- Cause code FENOC 'I'C'i ::;,- 'i~'i-!,-:t:r :-'111 If) ClUplillCi f "if:I,)


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Collective Significance Review - Results Areas for Improvement Two collective issues identified during common cause evaluation

- Electrical/Mechanical maintenance instruction deficiencies

- Procedure "use" categories not pre-determined

Content of Procedures

Conclusion:

  • Procedures were root or contributing causes
  • Actions:
  • 75 maintenance instructions will be systematically assessed
  • Results of assessment will determine need for comprehensive procedure upgrade
  • Interim - Safety related procedures will be reviewed as part of the work planning

Use of Procedures

Conclusion:

  • Procedure use categories not assigned Actions:
  • Interim - maintenance instructions will be "In Field Reference"
  • "Use" category will be identified in
  • maintenance instructions

Collective Significance Review - Summary Common causes are understood Comprehensive actions are being taken Systematic assessment will be used to adjust scope and timeliness

Summary - Cause and Corrective Actions Root and contributing causes are understood Corrective actions are comprehensive Extent of condition and extent of cause are being addressed

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Initial Safety Assessment Initial characterization of incremental core damage and large early release probabilities (ICCDP and ICLERP)

  • ICCDP (including internal events) = 2.03E-6
  • ICCDP (seismic, fire, and external flooding) = negligible

Safety Assessment Basis. for Initial Assesstnent

  • Level 1 PSA model used

- Includes all failure modes

- Simplified assumptions due to model and computer capabilities (no time dependence between event failures)

- No consideration given to the time dimension relative to the ESW Pump "A" coupling failure Basis for Updated Assessl71ent

  • The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> mission time was partitioned *
  • Only the applicable scenarios based on this event were considered
  • Human Reliability Analysis (HRA) was performed

Results of Updated Safety Assessment Updated characterization of incremental core damage and large early release probabilities (ICCDP and ICLERP)

  • ICCDP (including internal events) = 8.5E-7  !
  • ICCDP (seismic, fire, and external flooding) = 1.2E-7 I:
  • ICLERP = <1.0E-7 (qualitatively)

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Conclusion:

  • ICCDP (including external events) = 9.7E-7
  • ICLERP <1.0E-7 (qualitatively)

Low safety significance using a more detailed and accurate evaluation method

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