ML041120201
| ML041120201 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 04/09/2004 |
| From: | US Dept of Commerce, National Institute of Standards & Technology (NIST) |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NBSR 14 NISTIR 7102 | |
| Download: ML041120201 (10) | |
Text
NISTIR 7102 Safety Analysis Report (SAR) for License Renewal for the National Institute of Standards and Technology Reactor - NBSR NBSR 14
On the cover: A 3-D representation of the NBSR reactor core and internals.
Graphic Image by Paul Kopetka
NISTIR 7102 April 2004 U.S. DEPARTMENT OF COMMERCE Donald L. Evans, Secretary TECHNOLOGY ADMINISTRATION Phillip J. Bond, Under Secretary of Commerce for Technology NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY Arden L. Bement, Jr., Director Safety Analysis Report (SAR) for License Renewal for the National Institute of Standards and Technology Reactor - NBSR NBSR 14
Certain commercial entities, equipment, or materials may be identified in this document in order to describe an experimental procedure or concept adequately. Such identification is not intended to imply recommendation or endorsement by the National Institute of Standards and Technology, nor is it intended to imply that the entities, materials, or equipment are necessarily the best available for the purpose.
TABLE OF CONTENTS ACRONYMS PREFACE CHAPTER 1
NIST CENTER FOR NEUTRON RESEARCH & NBSR CHAPTER 2
SITE CHARACTERISTICS CHAPTER 3
DESIGN OF STRUCTURES, SYSTEMS, AND COMPONENTS CHAPTER 4
REACTOR DESCRIPTION CHAPTER 5
REACTOR COOLANT SYSTEMS CHAPTER 6
ENGINEERED SAFETY FEATURES CHAPTER 7
INSTRUMENTATION AND CONTROL SYSTEMS CHAPTER 8
ELECTRICAL POWER SYSTEMS CHAPTER 9
AUXILIARY SYSTEMS CHAPTER 10 EXPERIMENTAL FACILITIES AND SERVICES CHAPTER 11 RADIATION PROTECTION AND WASTE MANAGEMENT CHAPTER 12 CONDUCT OF OPERATIONS CHAPTER 13 ACCIDENT ANALYSES CHAPTER 14 TECHNICAL SPECIFICATIONS CHAPTER 15 FINANCIAL QUALIFICATIONS CHAPTER 16 OTHER LICENSE CONSIDERATIONS CHAPTER 17 DECOMMISSIONING
ACRONYMS AC air conditioning ALARA as low as reasonably achievable ANS American Nuclear Society ANSI American National Standards Institute ASME American Society of Mechanical Engineers ATWS anticipated transients without scram BNL Brookhaven National Laboratory BOC beginning of cycle (fuel)
BOCA Building Officials & Code Administrators CDE committed dose equivalent CEDE committed effective dose equivalent CFR U.S. Code of Federal Regulations CHF critical heat flux CHFR critical heat flux ratio CR control room DAC derived air concentration DBA design basis accident DNB departure from nuclear boiling EOC end of cycle (fuel)
EOF emergency offsite facility EOP emergency operating procedure EPA Environmental Protection Agency EPG emergency procedure guideline EPZ emergency planning zone ESF engineered safety feature GDC General Design Criteria HEPA high efficiency particulate absorber HEU high enriched uranium HVAC heating, ventilation, and air conditioning I&C instrumentation and control IAEA International Atomic Energy Agency IEEE Institute of Electrical and Electronics Engineers LCO limiting condition operation LER licensee event report LEU low enriched uranium LOCA loss-of-coolant accident LSSS limiting safety system setting MCC motor control center MCHFR Minimum Critical Heat Flux Ratio MCNP Monte Carlo Neutron Photon (computer code)
MCR main control room MHA maximum hypothetical accident NCNR NIST Center for Neutron Research NEMA National Electrical Manufacturers Association NIST National Institute of Standards & Technology NPP nuclear power plant
NRC Nuclear Regulatory Commission NRR Office of Nuclear Reactor Regulation (NRC)
NBSR National Bureau of Standards Reactor OL operating license PIC pocket ion chamber PRA probabilistic risk assessment RCS reactor coolant system REM Roentgen Equivalent Man RG regulatory guide (NRC)
SAC Safety Audit Committee SAR safety analysis report SEC Safety Evaluation Committee SGTR steam generator tube rupture SL safety limit SRP Standard Review Plan SSC structure, system, and component SU startup SUNY State University of New York TLD Thermo-Luminescent Dosimeters TS technical specification UL Underwriters Laboratory V&V verification and validation
PREFACE This Safety Analysis Report (SAR) of the National Institute of Standards and Technology Reactor, NBSR, describes the facility and contains all of the latest modifications made to it as of January 1, 2004. This report is being submitted to the US Nuclear Regulatory Commission (NRC) in support of the License Renewal Application for the NBSR. This SAR is given NIST document number NBSR 14 and is a complete revision to the previous Final Safety Analysis Report on the National Bureau of Standards Reactor that was submitted to NRC as document NBSR 9.
Dennis Brady of the NCNR contributed substantially to writing this SAR. He also directed the Brookhaven National Laboratory effort to coordinate, edit and act as technical reviewer for the report. He managed the contract with URS Corporation for the seismology, geology and hydrology analysis and the contract with EnviroTech Sensors Inc. for the meteorology analysis. Special thanks are given to Dr. J. Michael Rowe, Director of NCNR, who supervised the preparation of the report and contributed substantially in the area of accident analysis. Mike is retiring after directing the NCNR for the past 15 years.
The many individuals who contributed to the preparation of the SAR are noted below.
NCNR Personnel:
Jim Boyd Mike Rowe Dennis Brady Les Slaback Dave Brown Mahesh Suthar Peter Gehring Sy Weiss Tom Myers Robert Williams Wade Richards Brookhaven National Laboratory:
Lap Cheng Jim Higgins Richard Deem Maryann Julian David Diamond Mano Subudhi Ed Grove Ken Sullivan Al Hanson Mike Villaran Guest Researchers from Israel:
Menashe Gazit Hanoch Hirshfeld EnviroTech Sensors, Inc.:
John D. Crosby URS Corporation:
David Fenster Nasser Massoudi Jerry Kashatus Seymour H. Weiss, Chief Reactor Operations and Engineering