HFBR: Review of the technical specifications against the FSAR

Technical Report · Thu Jan 25 04:00:00 EST 1990

DOI:https://doi.org/10.2172/113765· OSTI ID:113765

Rao, D V; Ross, S B; Claiborne, E R; Darby, J L; Clark, R A ^[1]

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1. Science and Engineering Associates, Inc., Albuquerque, NM (United States)

The purpose of this review is to determine the adequacy of the High Flux Beam Reactor (HFBR) Technical Specifications for 40 MW operation by comparison with the HFBR Final Safety Analysis Report, particularly the accident analyses chapter. Specifically, the Technical Specifications were compared against the Design Basis Accident (DBA) Analyses presented in the Addendum to the HFBR FSAR for 60 MW Operation. The 60 MW DBA analyses was used since it is more current and complete than the analyses presented in the original FSAR which is considered obsolete. A listing of the required systems and equipment was made for each of the accidents analyzed. Additionally, the Technical Specification instrument setpoints were compared to the DBA analyses parametric values. Also included in this review was a comparison of the Technical Specification Bases against the FSAR and the identification of any differences. The HFBR Operations Procedures Manual (OPM) was also reviewed for any inconsistencies between the FSAR or the Technical Specifications. Upon completion of this review it was determined that the Technical Specifications are well written and the items commented on should not delay the low power restart (40 MW). Additionally, the OPM is also well written and does not require further modification before restart.

• Research Organization: Los Alamos National Lab., NM (United States); Science and Engineering Associates, Inc., Albuquerque, NM (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 113765
• Report Number(s): LA-SUB--95-175-A:1; SEA--90-500-02-A:1; ON: DE96000822
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
DESIGN BASIS ACCIDENTS
EVALUATION
HEAT TRANSFER
HFBR REACTOR
HYDRAULICS
LOSS OF COOLANT
RADIATION PROTECTION
REACTOR CONTROL SYSTEMS
REACTOR OPERATION
REACTOR SAFETY
REACTOR START-UP
SAFETY ANALYSIS