Component design bases - A template approach

Conference · Tue Jan 01 00:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5860807

Pabst, L F ^[1]; Strickland, K M ^[2]

---

1. Florida Power and Light Co., Juno Beach (United States)
2. Acorn Technical Services, Inc., Miami, FL (United States)

A well-documented nuclear plant design basis can enhance plant safety and availability. Older plants, however, often lack historical evidence of the original design intent, particularly for individual components. Most plant documentation describes the actual design (what is) rather than the bounding limits of the design. Without knowledge of these design limits, information from system descriptions and equipment specifications is often interpreted as inviolate design requirements. Such interpretations may lead to unnecessary design conservatism in plant modifications and unnecessary restrictions on plant operation. In 1986, Florida Power and Light Company's (FP and L's) Turkey Point plant embarked on one of the first design basis reconstitution programs in the United States to catalog the true design requirements. As the program developed, design basis users expressed a need for additional information at the component level. This paper outlines a structured (template) approach to develop useful component design basis information (including the WHYs behind the design).

• OSTI ID: 5860807
• Report Number(s): CONF-910603-; CODEN: TANSA
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 63; Conference: Annual meeting of the American Nuclear Society (ANS), Orlando, FL (United States), 2-6 Jun 1991; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
DESIGN
INFORMATION SYSTEMS
PWR TYPE REACTORS
AVAILABILITY
DOCUMENTATION
ENGINEERED SAFETY SYSTEMS
MODIFICATIONS
PROCUREMENT
REACTOR COMPONENTS
REACTOR MAINTENANCE
REACTOR OPERATION
REACTOR SAFETY
RELIABILITY
RISK ASSESSMENT
SPECIFICATIONS
ENRICHED URANIUM REACTORS
MAINTENANCE
OPERATION
POWER REACTORS
REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled