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. 14
Supplement No. 14 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation with additional information submitted by the applicant since Supplement No. 13 was issued, and matters that the staff had under review when Supplement No. 13 was issued.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Reactor Projects I/II
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 10197047
- Report Number(s):
- NUREG-0847-Suppl.14; ON: TI95004335
- Resource Relation:
- Other Information: PBD: Dec 1994
- Country of Publication:
- United States
- Language:
- English
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Technical Report
·
Wed Jan 01 00:00:00 EST 1992
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OSTI ID:10197047
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. 19
Technical Report
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Wed Nov 01 00:00:00 EST 1995
·
OSTI ID:10197047
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. 12
Technical Report
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Fri Oct 01 00:00:00 EDT 1993
·
OSTI ID:10197047
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
WATTS BAR-1 REACTOR
SAFETY ANALYSIS
WATTS BAR-2 REACTOR
REACTOR SAFETY
SAFETY REPORTS
REACTOR OPERATION
REACTOR LICENSING
REACTOR ACCIDENTS
PIPES
REACTOR COMPONENTS
DYNAMIC LOADS
SEISMIC EFFECTS
MECHANICAL STRUCTURES
REACTOR COOLING SYSTEMS
ENGINEERED SAFETY SYSTEMS
REACTOR INSTRUMENTATION
REACTOR CONTROL SYSTEMS
POWER SYSTEMS
ELECTRICAL EQUIPMENT
AUXILIARY SYSTEMS
RADIATION PROTECTION
TESTING
RELIABILITY
220900
210200
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
WATTS BAR-1 REACTOR
SAFETY ANALYSIS
WATTS BAR-2 REACTOR
REACTOR SAFETY
SAFETY REPORTS
REACTOR OPERATION
REACTOR LICENSING
REACTOR ACCIDENTS
PIPES
REACTOR COMPONENTS
DYNAMIC LOADS
SEISMIC EFFECTS
MECHANICAL STRUCTURES
REACTOR COOLING SYSTEMS
ENGINEERED SAFETY SYSTEMS
REACTOR INSTRUMENTATION
REACTOR CONTROL SYSTEMS
POWER SYSTEMS
ELECTRICAL EQUIPMENT
AUXILIARY SYSTEMS
RADIATION PROTECTION
TESTING
RELIABILITY
220900
210200
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED