U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation
United States Office of Nuclear Reactor Regulation
Nuclear Regulatory Commission Office of Nuclear Reactor Regulation (미국)
Office of Nuclear Reactor Regulation program office of the United States Nuclear Regulatory Commission
VIAF ID: 132498999 ( Corporate )
Permalink: http://viaf.org/viaf/132498999
Preferred Forms
- 110 _ _ ‡a Nuclear Regulatory Commission ‡b Office of Nuclear Reactor Regulation (미국)
- 110 2 _ ‡a Office of Nuclear Reactor Regulation ‡c program office of the United States Nuclear Regulatory Commission
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- 110 2 _ ‡a U.S. Nuclear Regulatory Commission. ‡b Office of Nuclear Reactor Regulation
- 110 2 _ ‡a United States ‡b Office of Nuclear Reactor Regulation
4xx's: Alternate Name Forms (10)
5xx's: Related Names (1)
Works
Title | Sources |
---|---|
Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 | |
Environmental impact statement for the construction permit for the SHINE medical radioisotope production facility : final report. | |
Generic aging lessons learned for subsequent license renewal (GALL-SLR) report : draft report for comment. | |
Generic environmental impact statement for license renewal of nuclear plants. | |
Guidelines for inservice testing at nuclear power plants : inservice testing of pumps and valves and inservice examination and testing of dynamic restraints (snubbers) at nuclear power plants : final report | |
Investigations of reported plant and animal health effects in the Three Mile Island area | |
Knowledge and abilities catalog for nuclear power plant operators : pressurized water reactors : draft report for comment | |
National report for the Convention on Nuclear Safety | |
NRC views and analysis of the recommendations of the President's Commission on the Accident at Three Mile Island | |
Nuclear Reactor Regulation technical newsletter | |
Operator licensing examination standards for power reactors : draft report | |
Proceedings of the ... NRC/ASME Symposium on Valves, Pumps, and Inservice Testing | |
Public comments, final report | |
Radioactive effluents from nuclear power plants. | |
Reassessment of NRC's dollar per person-rem conversion factor policy : draft report for comment. | |
Regarding Indian Point Nuclear Generating Unit nos. 2 and 3 ; draft report for comment | |
Regarding South Texas project, units 1 and 2 | |
Related to the license renewal of Davis-Besse Nuclear Power Station | |
Safety culture common language | |
Safety evaluation report related to the operation of Watts Bar Nuclear Plant, unit 2. | |
Sequoyah Nuclear Plant Units 1 and 2 | |
Standard review plan for review of subsequent license renewal applications for nuclear power plants : final report. | |
Status of safety issues at licensed power plants. | |
Study on post tensioning methods | |
Systematic evaluation program, status summary report | |
Technical bases for changes in the subsequent license renewal guidance documents NUREG-2191 and NUREG-2192. | |
Topical report review status | |
Two thousand two Davis-Besse reactor pressure vessel head degradation knowledge management digest | |
United States operating experience with thermally treated alloy 600 steam generator tubes through December 2013 | |
Validation of SCALE 5 decay heat predictions for LWR spent nuclear fuel | |
WASH-1400 : the reactor safety study : the introduction of risk assessment to the regulation of nuclear reactors | |
Waterford Steam Electric Station, Unit 3 |