Safety evaluation report related to Babcock and Wilcox Owners Group Plant Reassessment Program: (Final report)

Technical Report · Sun Nov 01 00:00:00 EST 1987

OSTI ID:5744946

After the accident of Three Mile Island, Unit 2, nuclear power plant owners made a number of improvements to their nuclear facilities. Despite these improvements, the US Nuclear Regulatory Commission (NRC) staff is concerned that the number and complexity of events at Babcock and Wilcox (B and W) nuclear plants have not decreased as expected. This concern was reinforced by the June 9, 1985 total-loss-of-feedwater event at Davis-Besse Nuclear Power Station and the December 26, 1985 overcooling transient at Rancho Seco Nuclear Generating Station. By letter dated January 24, 1986, the Executive Director for Operations (EDO) informed the Chairman of the B and W Owners Group (BWOG) that a number of recent events at B and W-designed reactors have led the NRC staff to conclude that the basic requirements for B and W reactors need to be reexamined. In its February 13, 1986 response to the EDO's letter, the BWOG committed to lead an effort to define concerns relative to reducing the frequency of reactor trips and the complexity of post-trip response in B and W plants. The BWOG submitted a description of the B and W program entitled ''Safety and Performance Improvement Program'' (BAW-1919) on May 15, 1986. Five revisions to BAW-1919 have also been submitted. The NRC staff has reviewed BAW-1919 and its revisions and presents its evaluation in this report. 2 figs., 34 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Reactor Regulation
• OSTI ID: 5744946
• Report Number(s): NUREG-1231; ON: TI88900167
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
EVALUATION
REACTOR SAFETY
COMPUTERIZED CONTROL SYSTEMS
FEEDWATER
HUMAN FACTORS
LOSS OF COOLANT
MAINTENANCE
PUMPS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR OPERATORS
RISK ASSESSMENT
SENSITIVITY ANALYSIS
STEAM GENERATORS
TRAINING
VALUES
ACCIDENTS
BOILERS
CONTROL SYSTEMS
COOLING SYSTEMS
ENERGY SYSTEMS
HYDROGEN COMPOUNDS
OPERATION
OXYGEN COMPOUNDS
PERSONNEL
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled