ML20235P103
| ML20235P103 | |
| Person / Time | |
|---|---|
| Site: | 05000262 |
| Issue date: | 09/29/1987 |
| From: | Stohlton J Brigham Young University, PROVO, UT |
| To: | Alexander Adams Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20235P105 | List: |
| References | |
| NUDOCS 8710070174 | |
| Download: ML20235P103 (2) | |
Text
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1 Brigham Young University m
John B. Stohlton In
!xecutive Vice President September 29, 1987 t
Alexan)derAdams,Jr.,ProjectManager Standardized and Non-Power h.-
. Reactor Project Directorate
' q Division of Reactor Projects III, IV,
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s V and Special Projects Office of Nuclear Projects' y'
United States Nuclear Regulatory Commission T
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{ Washington, D.C. 20555 di
Dear Hr. Adems:
j In. reply,to your letter dated August 26, 1987, I havej
- prepared the following infortnation:
1, The present radiological status of the reactor, as of September 28, 1987, is as follows:
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No detectable gamma radiation encountered in the facility, nor at the surface of the reactor utilizing.a '
Victoreen Model 470A detector.
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No detectable neutron flux, utilizing a Vidtoreen i
neutron detector.
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.. No removable alpna contamination, utilizing swipes and t
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s a-scintillation counter.
'No detectable beta contamination., utilizing an Eberline PRM-4A instrument with a HP-260 probe.
Measurements were taken from the floor, the top of the
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reactor,.and the surface of the reactor near each port.
TLD dosimetry monitors' recorded 0, 17,.and 10 millirems during the J
quarter from April to June,1987.
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'2.
The Radiation safety: Committee has determined that the l
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, shielding water will not be removed until after the Pu/Be source has been removed.
3.
Under current license provisions, Sectio'n II.D.1./
monitoring will only be performed during opsration 6f l
the' reactor.
Since operation is no longer possible I
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with. the current configuration (fuel has. been removed),
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q the license requires no moni toring.
Therefor, our proposal to utilize TLD monitors is a somewhat more.
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stringentEpractice than would be required under. the i
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present Technical Specifications.
This seems prudent 1
as a means of documenting' potential exposure rates in j
or near the reactor facility.
This measure is also
_9 deemed both reasonable and sufficient since the
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facility is 'no longer in use.
Hence,- there is only 1
-infrequent exposure-potential to university or comunity personnel.
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The Technical Specifications have been rewritten in accordence with ANSI /ANS 15.1 -'1982.
The operational checks',3and monitoring sections found in license sectionrJ3.C.jand);D. were facluded insofar as they remain 3ppliciple to our reactor.
I trust tharthis' info'3rmationis. sufficient to answer your questions.
We look forwand t6 hearing from you.
Sincerely.
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C../ / 4C 06Cn4.%ET Executive Vice-President Brigham Young University I
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