ORAM-SENTINEL{trademark} demonstration at Fitzpatrick. Final report

Technical Report · Mon Jun 01 04:00:00 EDT 1998

OSTI ID:354974

Lee, L K ^[1]; Anderson, V M; Mohammadi, K ^[2]; Scanlan, M A ^[3]

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1. ERIN Engineering and Research, Inc., Campbell, CA (United States)
2. ERIN Engineering and Research, Inc., Walnut Creek, CA (United States)
3. ERIN Engineering and Research, Inc., Exton, PA (United States)

New York Power Authority, in cooperation with EPRI, installed the ORAM-SENTINEL{trademark} software at James A. Fitzpatrick (JAF) Nuclear Power Plant. This software incorporates models of safety systems and support systems that are used for defense-in-depth in the plant during outage and on-line periods. A secondary goal was to include some pre-analyzed risk results to validate the methodology for quantitative assessment of the plant risks during proposed on-line maintenance. During the past year, New York Power Authority personnel have become familiar with the formal computerized Safety Assessment process associated with on-line and outage maintenance. The report describes techniques and lessons learned during development of the ORAM-SENTINEL model at JAF. It overviews the systems important to the Safety Function Assessment Process and provides details on development of the Plant Transient Assessment process using the station emergency operating procedures. The assessment results are displayed by color (green, yellow, orange, red) to show decreasing safety conditions. The report describes use of the JAF Probabilistic Safety Assessment within the ORAM-SENTINEL code to calculate an instantaneous core damage frequency and the criteria by which this frequency is translated to a color indicator.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (United States); ERIN Engineering and Research, Inc., Campbell, CA (United States); ERIN Engineering and Research, Inc., Walnut Creek, CA (United States); ERIN Engineering and Research, Inc., Exton, PA (United States)
• Sponsoring Organization: Electric Power Research Inst., Palo Alto, CA (United States)
• OSTI ID: 354974
• Report Number(s): EPRI-TR--110505
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
ENGINEERED SAFETY SYSTEMS
FITZPATRICK REACTOR
O CODES
REACTOR MAINTENANCE
RISK ASSESSMENT
SAFETY ANALYSIS