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Category:ANNUAL OPERATING REPORT
MONTHYEARML20205K0191998-12-31031 December 1998 Annual Rept for 1998 for Nuclear Engineering Teaching Lab. with ML20217N7801997-12-31031 December 1997 1997 Annual Rept for Univ of Tx at Austin ML20217M8041997-12-31031 December 1997 Corrected Replacement Page 3-13 to University of Texas, 1997 Annual Rept ML20137A5711996-12-31031 December 1996 1996 Annual Rept for Nuclear Engineering Teaching Lab Jj Pickle Research Campus ML20101J3411995-12-31031 December 1995 Annual Rept 1995 Nuclear Engineering Teaching Lab Jj Pickle Research Campus Univ of Tx at Austin ML20081K1031994-12-31031 December 1994 Annual Rept 1994 Nuclear Engineering Teaching Lab Jj Pickle Research Campus Univ of Tx at Austin 1998-12-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20205K0191998-12-31031 December 1998 Annual Rept for 1998 for Nuclear Engineering Teaching Lab. with ML20237C8171998-08-14014 August 1998 Ro:On 980521,discovered That argon-41 CAM Exceeded Argon CAM Alarm Level.Caused by Sudden Increase in Gaseous Level. Reactor Was Shutdown & Subsequent Analysis of Air Particulate Filter Determined Presence of Fission Products ML20249B7711998-06-17017 June 1998 Ro:On 980426,noted Failure to Meet TS 6.2.2a for Meeting Frequency & Subsequent Failure to Meet Part of TS 6.2.4. Caused by Reorganization of Lab.Licensee Will Reorganize Nuclear Reactor Committee W/New Chairman ML20217N7801997-12-31031 December 1997 1997 Annual Rept for Univ of Tx at Austin ML20217M8041997-12-31031 December 1997 Corrected Replacement Page 3-13 to University of Texas, 1997 Annual Rept ML20137A5711996-12-31031 December 1996 1996 Annual Rept for Nuclear Engineering Teaching Lab Jj Pickle Research Campus ML20101J3411995-12-31031 December 1995 Annual Rept 1995 Nuclear Engineering Teaching Lab Jj Pickle Research Campus Univ of Tx at Austin ML20081K1031994-12-31031 December 1994 Annual Rept 1994 Nuclear Engineering Teaching Lab Jj Pickle Research Campus Univ of Tx at Austin ML20085D1931991-05-31031 May 1991 Univ SAR Amend Pages for Rev 1.01 ML20073R1101991-05-31031 May 1991 Rev 1.01 to SAR ML20073E7201991-04-15015 April 1991 Rev 0 to QA Plan ML20065S1421990-11-21021 November 1990 Rev 0 to QA Plan ML20235Y3961989-02-24024 February 1989 Safety Evaluation Supporting Extension of Const Completion Date of Triga Mark II Reactor to 891231 ML20127E8131985-05-31031 May 1985 Safety Evaluation Report Related to the Construction Permit and Operating License for the Research Reactor at the University of Texas.Docket No. 50-602. (University of Texas) ML20100L9251984-11-30030 November 1984 Triga Reactor Facility,Nuclear Engineering Teaching Lab, Univ of Texas at Austin 1998-08-14
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! Table 3-8
- Annual Summary of Personnel Radiation Doses Received Within the NETL Reactor Facility Average Annual Dose * (mrem)
Personnel Students VisitorsW-Whole Body,DDEW 0 (M) 0.0002 0 (M) i Extremities,SDEW l
15 2.0 N/A (M)
Lens ofeye,LDEW 0 (M) 0.0002(6) N/A M
- Greatest Individual Dose (mrem) -
Personnel Students - VisitorsW Whole Body,DDE 0 (M) 0.003W 0 (M)
Extremities,SDE 80 30 N/A, (M)
Lens of eye,LDE 0 (M) 0.003W N/A (M)
Total Person-mrem for Group Personnel Students VisitorsW Whole Body,DDE O (M) . 0.003W 0 (M)
Extremities,SDE 150 30.003 N/A (M) ',
Lens of eye,LDE : .
0 (M) 0.003W N/A (M)
(1) "M" indicates that each of the beta-ganuna or neutron dosimeters during the reporting period was less than the vendor's minimum measurable quantity of 10 mrem for x- and gamma rays .
and thermal reutrons, 40 mrem for energetic betas, 20 mrcm for fast neutrons. "N/A" indicates that there was no extremity monitoring conducted or required for the group.
(2) DDE applies to external whole-body exposure and is the dose eq tivalent at a tissue depth of I cm(1000 mg/cm2),
(3) SDE applies to skin or extremity external exposure, and is the dose equivalent at a tissue depth of 0.007 cm (7 mg/cm2) averaged over an area of I cm2,
"(4) LDE applies to the external exposure of tic eye lens and is taken as the dose equivalent at a tissue depth of 0.3 cm (300 mg/cm2 ).
i (5) Pocket ionization chambers (PICS) are issued to persons who enter radioactive l materials /restncted areas for periods of short duration, i.e., a few hours or days annually. A l- total of 273 issuance cards were filled out, and none recorded a postive dose value.
(6) Exposure calculated from tritium bioassay. The tritium source was state license material for a t neutron genemtor.
9805050142 980428 PDR ADOCK 05000602 R PDR
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