ML25197A058
| ML25197A058 | |
| Person / Time | |
|---|---|
| Issue date: | 07/16/1975 |
| From: | Kerr W Advisory Committee on Reactor Safeguards |
| To: | Anders W NRC/Chairman |
| References | |
| Download: ML25197A058 (1) | |
Text
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS NUCLEAR:REGULATORY COMMISSION WASHINGTON, D. C. 20555 JUL 1 6 1975 Honorable William A. Anders Chairman U. S. Nuclear Regulatory Commission Washi.Igton, D. C. 20555
Subject:
REPORT ON LOFT FACILITY
Dear Mr. Anders:
At its 183rd meetirg, July 10-12, 1975, the Advisory Committee on Reactor Safeguards reviewed the safety of operation of the Loss of Fluid Test (LOFT) facility for the proposed experi~ental mode involvir.g primary system blowdown into a pressure suppres~-ion tank. Subcommittee meetirg s on this project were held on July 9, 1915, and on July 25, 1973.
Members of the Committee visited the facility on July 24, 1973. In its review, the Cormnittee had the benefit of discussions with representatives of the Energy Research and Development Administration (ERDA), Aerojet Nuclear Corporation, and the Nuclear Regulatory Corrnnission (NRC).
The Corrmittee also had the benefit of the documents listed. The Committee reported previously on the construction of LOFT on A1..gust 28, 1964.
At that time, different experimental objectives ex:isted for LOFT.
The LOFT facility is located in southeastern Idaho on the 894 square mile site of the Idaho National Er.gineerirg Laboratory, which is approxi-mately 30 miles from Idaho Falls. The test reactor is located in Test Area North, which has a daytime population of about 2100.
The nuclear steam supply system is mounted on the Mobile Test Assembly (MTA), which was initially assembled at the Technical Support Facilities (TSF) and then transported by rail to the LOFT containment vessel. The reactor is rated at 55 MW(t), and has the capability of beir.g trans-ported back to the TSF.
The current purpose of LOFT is to serve as a vehicle for conductir.g integrated LOCA-ECCS test pr~rams. The NRC Staff has reviewed only that phase of the overall experL~ental pro.;rcuu for which the primary system is caused to blow down into the pressure suppression tank rather than into the containment. Also, the NRC Staff has not evaluated safety matters related to movir:g the MTA out of the containment.
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Honorable William JUL 1 6 1975 LOFT was designed and constructed over a considerable period of time and does not meet current NRC requirements in all aspects. The NRC Staff has recommended that several specific areas be addressed by ERDA as part of ERDA's responsibility for the safe operation of the facility.
The Committee wishes to call particular attention to the importance of proper requalification of LOFT systems and components after severe transient tests and the establishment of an effective administrative apparatus for review of the continued safe operation of the plant, keepirg in mind the needs for the experimental information beirg soi.ght.
The ACRS reccgnizes that from the very nature of the facility, the: pro-bability of an accident in LOFT may be greater than for a typical commercial reactor. However,.the total power is relatively low and operation is intermittent; also, the site is remote and emergency pla.nn.irg is kept in a state of readiness.
The ACRS believes that, in light of the above considerations, operation of LOFT in the pressure suppression mode for the proposed blowdown experiments should not pose an undue risk to the public heal th and safety.
Tb~
Committee recommends that other experimental pre.grams for LOFT be r*~iewed and evaluated for safety by ERDA, and by the NRC Staff if appropriate, maintainir:g a proper balance between the safety questions arisirg from a particular proposed experimental prcgram and the need for the information to be gained.
REFEREHCFS:
Sincerely yours, (Jfl~
W. Kerr Chairman
- 1. Aerojet Nuclear Company, Final Safety Analysis Report (FSAR),
Vols. 1-3, for LOFT IntQ.sral Test System, March 29, 1974.
- 2. Supplements 1 & 1A to FSAR.
- 3. Aerojet Nuclear Company, LOFT Int~ral Test System - Design Basis Report, January, 1974.
- 4. U.S. Nuclear Regulatory Commission, Safety Evaluation of the Loss of Fluid Test Facility, May, 1975.
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