Analysis of core damage frequency, Surry, Unit 1 internal events appendices
- E.I. Services, Kent, WA (USA)
- Sandia National Labs., Albuquerque, NM (USA)
This document contains the appendices for the accident sequence analyses of internally initiated events for the Surry Nuclear Station, Unit 1. This is one of the five plant analyses conducted as part of the NUREG-1150 effort by the Nuclear Regulatory Commission. NUREG-1150 documents the risk of a selected group of nuclear power plants. The work performed is an extensive reanalysis of that published in November 1986 as NUREG/CR-4450, Volume 3. It addresses comments from numerous reviewers and significant changes to the plant systems and procedures made since the first report. The uncertainty analysis and presentation of results are also much improved. The context and detail of this report are directed toward PRA practitioners who need to know how the work was performed and the details for use in further studies. The mean core damage frequency at Surry was calculated to be 4.0E-5 per year, with a 95% upper bound of 1.3E-4 and 5% lower bound of 6.8E-6 per year. Station blackout type accidents (loss of all AC power) were the largest contributors to the core damage frequency, accounting for approximately 68% of the total. The next type of dominant contributors were Loss of Coolant Accidents (LOCAs). These sequences account for 15% of core damage frequency. No other type of sequence accounts for more than 10% of core damage frequency.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research; Sandia National Labs., Albuquerque, NM (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 7146808
- Report Number(s):
- NUREG/CR-4550-Vol.3-Rev.1-Pt.2; SAND--86-2084-Vol.3-Rev.1-Pt.2; ON: TI90011058
- Country of Publication:
- United States
- Language:
- English
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