Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2, (Docket Nos. 50-390 and 50-391), Tennessee Valley Authority. Supplement No. 9
Technical Report
·
OSTI ID:10155809
This report supplements the Safety Evaluation Report (SER), NUREG- 0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), and Supplement No. 8 (January 1992) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items, and proposed license conditions identified in the SER.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Reactor Regulation
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 10155809
- Report Number(s):
- NUREG--0847-Suppl.9; ON: TI92016385
- Country of Publication:
- United States
- Language:
- English
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Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391)
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Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50--390 and 50--391)
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Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 15
Technical Report
·
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OSTI ID:87067
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200
210700
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
AUXILIARY SYSTEMS
DESIGN
ENERGY CONVERSION
ENGINEERED SAFETY SYSTEMS
LOSS OF COOLANT
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR INSTRUMENTATION
REACTOR LICENSING
REACTOR OPERATORS
REACTOR SAFETY
REGULATION AND LICENSING
SAFETY REPORTS
SEISMIC EFFECTS
SITE CHARACTERIZATION
TRAINING
WATTS BAR-1 REACTOR
WATTS BAR-2 REACTOR
210200
210700
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
AUXILIARY SYSTEMS
DESIGN
ENERGY CONVERSION
ENGINEERED SAFETY SYSTEMS
LOSS OF COOLANT
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR INSTRUMENTATION
REACTOR LICENSING
REACTOR OPERATORS
REACTOR SAFETY
REGULATION AND LICENSING
SAFETY REPORTS
SEISMIC EFFECTS
SITE CHARACTERIZATION
TRAINING
WATTS BAR-1 REACTOR
WATTS BAR-2 REACTOR