ML112220605
ML112220605 | |
Person / Time | |
---|---|
Site: | Perry |
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
- Emergency Service Water (ESW) Pump "A" coupling failed
- Enforcement discretion requested and granted (no net increase in risk)
- 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
- Stress corrosion cracking is the root cause
- 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
- ICLERP = 1.S6E-7
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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