ML20085J376

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Annual Operating Rept for Oct 1982 - Sept 1983
ML20085J376
Person / Time
Site: Kansas State University
Issue date: 10/07/1983
From: Faw R
KANSAS STATE UNIV., MANHATTAN, KS
To: John Miller
Office of Nuclear Reactor Regulation
References
NUDOCS 8310130090
Download: ML20085J376 (2)


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Department of Nuclear Engineering l I

I KA2qERAIS Ward Hall Manhattan, Kansas 66506

-w 913-532-5624 October 7, 1983 l

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Standardization and Special Projects Board ATTN: James R. Miller Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C. 20555 RE: Docket 50-188 License R-88 Gentlemen:

Pursuant to 10CFR50.59(b), the following items are submitted for the Kansas State University TRIGA MkII Nuclear Reactor Facility for the interval 1 Oct. 82 - 30 Sep. 83.

A. Changes in the Facility On 16 Dec. 82, the conductivity monitoring system for the primary coolant was replaced by a Foxboro Model 910 Conductivity Monitoring System. The specifications, replacement procedure, and testing procedure were approved on 8 Dec. 82 by the Reactor Safeguards Committee, who found that the replacement involved no unreviewed safety questions and could be accomplished with no risk to the integrity of the reactor or to the safety of personnel.

B. Changes in Procedures A revision of Procedure 1 (Control Rod Inspection) was approved by the Reactor Safeguards Committee on 14 Oct.

82. The original version " recommended" that, subsequent to inspection, control-rod drop times be measured 10 times.

The revised version " requires" at least 3 measurements as part of an operational check. The committee found that the change posed no risk to the integrity of the reactor or to the safety of personnel.

On 14 Oct. 82, the Reactor Safeguards Committee approved a revision of the Facility Emergency Plan (submitted to the Nuclear Regulatory Commission on 19 Oct. 82). The Committee found that implementation of the Plan posed no risk to the integrity of the reactor or to the safety of personnel.

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l Standardization and Special Projects Board October 7, 1983 Page 2 1

On 15 April 83, the Reactor Safeguarda Committee approved Emergency Procedures 6-14 for interim use, pending NRC approval of the Facility Emergency Plan. The Committee found that implementation of the Procedures posed no threat to the integrity of the reactor or to the safety of personnel.

C. Tests and Experiments on 14 Oct. 82, the Reactor Safeguards Committee approved an addendum to Experiment 11 (Flux Traverse Using In-Core Flux Probe). The addendum permits use of a flux probe such as a fission or ionization chamber, in addition to wires or foils, in the measurement of thermal-neutron flux densities within the reactor core. The Committee determined that the action involved no significant risk to the integrity of the reactor or to the safety of personnel.

Sincerely, Richard E. Faw, Director KSU Nuclear Reactor Facility REF:mb cc: U.S. N.R.C. (Region IV)

KSU Reactor Safeguards Committee

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