|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20195B6691998-11-10010 November 1998 Safety Evaluation Supporting Amend 17 to License R-106 ML20199G0331998-01-28028 January 1998 Safety Evaluation Supporting Amend 16 to License R-106 ML20246D1071989-08-15015 August 1989 Safety Evaluation Supporting Amend 10 to License R-106 ML20149M7101988-02-11011 February 1988 Safety Evaluation Supporting Amend 9 to License R-106 ML20125C5651979-12-18018 December 1979 Safety Evaluation Supporting Amend 4 to License R-106 1998-11-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20195B6691998-11-10010 November 1998 Safety Evaluation Supporting Amend 17 to License R-106 ML20155E8121998-06-30030 June 1998 Annual Rept of Oregon State Univ Radiation Center & Triga Reactor for 970701-980630 ML20203K5281998-03-0202 March 1998 RO 33732:on 980217,OSTR Failed to Shut Down When Console Manual Scram Button Was Pushed.Caused by Spring Return Switch Failed to Return Completely to Operate Position. Console Key Switch Cleaned & Relubricated ML20236K7251998-02-20020 February 1998 RO 33732:on 980217,manual Scram Failure Occurred.Caused by Spring Return Key Switch Failing to Return Completely to Operate Position & Wiring Change Difference.Removed & Cleaned Switch & Performed Encl 10CFR50.59 Evaluation ML20236K7301998-02-20020 February 1998 Osu Triga Reactor (OSTR) Changes,Tests & Experiments Evaluated Under Provisions of 10CFR50.59 ML20199G0331998-01-28028 January 1998 Safety Evaluation Supporting Amend 16 to License R-106 ML20217A7451997-09-0505 September 1997 Ro:On 970812,questioned Whether OSTR Matl Balance Rept Date of 970728 Was Date Completed or Date Not to Be Exceeded. Caused by Reactor Administrator'S Pressure of Work Load. Completed OSTR Matl Balance Rept ML20236F4761997-06-30030 June 1997 Corrected Table V.B.2 for 1996-1997: Monthly Summary of Gaseous Effluent Releases to Annual Rept of or State Univ Radiation Ctr & Triga Reactor for Period July 1996 - June 1997 ML20212D4531997-06-30030 June 1997 Annual Rept of Oregon State Univ Radiation Ctr & Triga Reactor,960701-970630 ML20138G7651996-12-23023 December 1996 Ro:On 961203,staff Performed Irradiations W/O Following Procedural Controls.On 961216,staff Prepared Shipment of Irradiated Fission Track Samples W/O Following Procedures. Caused by Staff Error.Staff Counseled ML20134E4181996-06-30030 June 1996 Annual Rept of Oregon State Univ Radiation Ctr & Triga Reactor for Period 950701-960630 ML20093M9851995-06-30030 June 1995 Annual Rept of Oregon State Univ Radiation Ctr & Triga Reactor June 1994-June 1995 ML20094B3621995-06-30030 June 1995 Annual Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 for Period Jul 1994 - June 1995 ML20078C1511994-06-30030 June 1994 Annual Rept of or State Univ Radiation Ctr & Triga Reactor, 930701-940630 ML20059C4431993-06-30030 June 1993 Annual Rept of or State Univ Radiation Ctr & Triga Reactor,920701-930630 ML20059H5841993-06-30030 June 1993 Annual Rept of Changes,Tests & Experiments Performed Under 10CFR50.59 for 920701-930630 ML20128G9901993-02-0101 February 1993 Ro:Discovered That Reactor Not Pulsed Semiannually to Compare Fuel Temp Measurements & Peak Power Levels W/Levels of Previous Pulses of Same Reactivity Value.Chart Listing Semiannual Surveillance & Maint Items Encl ML20116J2381992-06-30030 June 1992 Annual Rept of Changes,Tests & Experiments Performed Under Provisions of 10CFR50.59 for Oregon State University Triga Reactor (Ostr) ML20116D0111992-06-30030 June 1992 Annual Rept of Oregon State Univ Radiation Center & Triga Reactor for Jul 1991 - June 1992 ML20079P0261991-11-0404 November 1991 Annual Rept of Changes,Tests & Experiments Performed Under Provisions of 10CFR50.59 for Oregon State Univ Triga Reactor for Jul 1990-June 1991 ML20085L0731991-06-30030 June 1991 Annual Rept of Oregon State Univ Radiation Ctr & Triga Reactor,Jul 1990-June 1991 ML20029A7541991-02-25025 February 1991 Followup RO Per 910215 Telcon:On 910215,water Level in Reactor Tank Lower than Normal.Caused by Water Running Out from Under Concrete Block Shield Surrounding Demineralizer Tank.Barrier Dam Constructed Across HX Room ML20062H7911990-11-27027 November 1990 Annual Rept of Changes,Tests & Experiments for Jul 1989 - June 1990 Under 10CFR50.59 ML20058F2241990-06-30030 June 1990 Annual Rept of Oregon State Univ Radiation Ctr & Triga Reactor, for Jul 1989 - June 1990 ML19327C0421989-10-31031 October 1989 Amend 5 to, SAR for Oregon State Triga Reactor (Ostr). ML19325C7001989-10-0202 October 1989 Annual Rept of Changes,Tests & Experiments Performed Under Provisions of 10CFR50.59 for Triga Reactor,For Jul 1988 - June 1989 ML20246D1071989-08-15015 August 1989 Safety Evaluation Supporting Amend 10 to License R-106 ML20012A0901989-06-30030 June 1989 Annual Rept of Oregon State Univ Radiation Ctr & Triga Reactor Jul 1988 - June 1989. ML20005D6031989-06-30030 June 1989 Annual Rept of Oregon State Univ Radiation Ctr & Triga Reactor Jul 1988 - June 1989. ML20245B3461989-04-17017 April 1989 Ro:On 890406,during Routine Pulsing Operation,Blue Pen Which Records Linear & Peak Power Went off-scale.Caused by Omission of 100-ohm Resistor Normally Placed Across Console Terminals.Operators Reprimanded & Procedures Changed ML20204G1161988-09-30030 September 1988 Annual Rept of Changes,Tests & Experiments for Oregon State Univ Triga Reactor for Jul 1987 - June 1988 ML20235D0601988-06-30030 June 1988 Annual Rept of Oregon State Univ Radiation Ctr & Triga Reactor Jul 1987 - June 1988 ML20154J2511988-05-17017 May 1988 RO Re Jan 1988 Event in Which Procedures Consistent W/New NRC Policy Used Rather than Exact Written Procedures.Reactor Operations Committee Meeting on 880513 Preceeded Info for Review.Staff Instructed to Use Exact Procedures ML20150C8761988-03-15015 March 1988 Requalification Program for Licensed Operators of Oregon State Univ Triga Reactor (Ostr) ML20149M7101988-02-11011 February 1988 Safety Evaluation Supporting Amend 9 to License R-106 ML20235R1021987-09-28028 September 1987 Annual Rept of Changes,Tests & Experiments Performed Under Provisions of 10CFR50.59 for Oregon State Univ Triga Reactor (Ostr), for Jul 1986 - June 1987 ML20235E7421987-06-30030 June 1987 Oregon State Univ Triga Reactor Annual Rept ML20197B2941986-10-0303 October 1986 Annual Rept of Changes,Tests & Experiments for Jul 1985 - June 1986,per 10CFR50.59 ML20138J9471985-10-0404 October 1985 Changes to Facility,To Facility Procedures & to Reactor Experiments for Jul 1984 - June 1985 ML20133N3991985-06-30030 June 1985 Oregon State Univ Triga Reactor Annual Rept, for Reporting Period Jul 1984 - June 1985 ML20080L2971983-09-19019 September 1983 Annual Rept of Changes,Tests & Experiments Made Under 10CFR50.59 for Triga Reactor,Jul 1982 - June 1983 ML20071N4021983-05-25025 May 1983 Ro:On 830523,discovered Insp of Transient Control Rod Not Conducted Since 810317.Caused by Misinterpretation of Tech Specs.Surveillance Time Intervals Will Be Modified Per Ansi/Ans 15.1-1982 Guidelines ML20003G2551981-04-17017 April 1981 Ro:On 810414,continuous Control Rod Withdrawal Occurred, Resulting in Net Insertion of 80 Cents Reactivity Worth. Caused by Failure of Safety Rod Up Switch.Operations Instructions Bulletin Written Re Possible Recurrence ML19340D3771980-12-19019 December 1980 Ro:On 801212,reactor Operated for Approx 1-h W/ Nonfuctioning Air Pump on Reactor Top Continuous Air Particulate Radiation Monitor.Caused by Loosely Fitting Power Plug &/Or Loose Fuse Holder Connection ML19337A7821980-08-31031 August 1980 or State Univ Triga Reactor Annual Rept for Jul 1979-June 1980 ML19310A3861980-06-0303 June 1980 Ro:On 800520,while Performing Routine Pulses,One of Five Pulses Produced Peak Power & Measured Fuel Temp Beyond Expectation for 2.55 Dollar Reactivity Insertion. Apparently Caused by 2.75 Dollar Reactivity Insertation ML20125C5651979-12-18018 December 1979 Safety Evaluation Supporting Amend 4 to License R-106 ML19290A0801979-06-30030 June 1979 Annual Operating Rept for Jul 1978-June 1979 1998-06-30
[Table view] |
Text
_ . ._ _ _ _ _ _ . . . _ _ . _ . _ _ . . _ _ . _ _ . _ _ _ _ _ _ _ . _ _ _ . _ _ _
c
~
[pue:gk UNITED STATE 8
,. g NUCLEAR REGULATORY COMMISSION o, WASHINGTON. 0.C. Soses 4001 i k***** ,
l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ~1 l SUPPORTING AMENDMENT NO.17 TO i
AMENDED FACILITY OPERATING LICENSE NO. R-108 OREGON STATE UNIVERSITY I DOCKET NO. 50-243 I
1.0 INTRODUCTION
J By letter dated July 27,1998, as supplemented on September 30,1998, Oregon State
~ University (OSU or the licensee) submitted a request for amendrnent of the Technical
. Specifications (TSs), Appendix A, to Amended Facility Operating License No. R-106 for the OSU TRIGA Research Reactor (OSTR). The requested amendment would clarify the quantity and type of material in experiments that could be released in the unlikely event of an experiment failure.
I 2.0 EVALUATION The licensee has requested amendment of TS 3.8 e, concerning limitations on experiments.
TS 3.8 e, and the bases of the TS currently read:
- e. Where the possibility exists that the failure of an experiment (except fueled experiments) under (1) normal operating conditions of the experiment or reactor,-(2) credible accident conditions in the reactor, or (3) possible accident conditions in the experiment, could release radioactive gases or aerosols to the reactor bay or the unrestricted area, the quantity and type of material in the experiment shall be limited such that the airborne concentration of radioactivity in the reactor bay and the unrestricted area will not exceed the applicable regulatory concentration limits in 10 CFR Part 20, assuming 100% of the gases or aerosols escape from the experiment.
Bases
- e. This specification is intended to reduce the likelihood that airborne radioactivity in excess of the limits in Appendix B of 10 CFR Part 20 will be released to the reactor bay and unrestricted area surrounding the OSTR.
9811160238 981110 PDR P
ADOCK 05000243 pg
< l. . . . - . , - . , _ - _ - -- , -- .
- . - _ - . . . - ~ . - . - ~ . - - . . _ - - .-..-- _._.---. .
l l.
i _
c,' 2-The licensee has proposed that the TS and bases be amended to read:
l
- e. Where the possibility exists that the failure of an experiment (except
!. fueled experiments) under (1) normal operating conditions of the experiment or reactor, (2) credible accident conditions in the reactor, or (3) possible accident conditions in the experiment could release radioactive gases or aerosols to the reactor bay or the unrestricted area, the quantity and type of material in the experiment shall be limited such that the airborne radioactivity in the reactor bay or the unrestricted area will not result in exceeding the applicable dose limits in 10 CFR 20, assuming 100% of the gases or aerosols escape from the experiment.
Bases
- e. This specification is intended to meet the purpose of 10 CFR 20 by reducing the likelihood that released airborne radioactivity to the reactor bay or unrestricted area surrounding the OSTR will result in exceeding the total dose limits to an individual as specified in 10 CFR 20.
The licensee has proposed clarifying the TS by basing the TS on dose instead of concentrations of radioactive material. The purpose of this TS is to limit doses to members of the public and the OSTR staff to 10 CFR Part 20 limits in the unlikely event that an experiment were to fail and release airborne radioactive material into the reactor l confinement and subsequently to the environment. Doses to members of the reactor staff and members of the public from accidents at research reactors are limited to the doses given in 10 CFR Part 20 because 10 CFR Part 100 is not applicable to research reactors.
The current TS is based on radioactivity concentrations. For occupational exposures, the annual limit on intake (All) is the annual intake that would result in either a committed effective dose equivalent of 5 rem (stochastic All) or a committed dose equivalent of 50 rem to an organ or tissue (non stochastic All). The derived air concentration values in Table 1 of Appendix B to 10 CFR Part 20 are based on dividing the ALI by 2000 working hours per year and is intended to control chronic occupational exposures. For non-occupational exposure (members of the public), the effluent concentrations given in Table 2 of Appendix B to 10 CFR Part 20 are equivalent to the radionuclide concentration, which, if inhaled continually over the course of a year, would produce a total effective dose -
equivalent of 0.05 rem. The licensee's proposed wording would be based on dose limits directly.
l The licensee is concerned that the TS as currently written could be interpreted to limit releases to the instantaneous concentration of airborne radioactive material in the reactor confinement and unrestricted areas. This interpretation would ignore the time integral aspects of the concentration limits given in 10 CFR Part 20, as discussed above. For a
- particular experiment failure event, it is possible to exceed the concentration limits in 10 CFR Part 20, while the resulting dose would be a small fraction of the dose limits.
i l'
l-i
. -- - ~,- . . - . . - ,- , - . . , - - - -. - - - .
- .. - .----~ - - - _ . . . - - -.--..-. - . -. --
i 4,* The NRC staff notes that the proposed wording of the TS is more encompassing because a TS based on dose would also include consideration of radiation shine from a cloud of radioactive material. This proposed change to the TSs is acceptable to the staff because the dose to members of the reactor staff and members of the public from the accidental failure of experiments will be within the limits given in 10 CFR Part 20 and because the proposed wording clarifies the TS.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves changes in the installation or use of a facility component located l within the restricted area as defined in 10 CFR Part 20 or changes in inspection and I surveillance requirements. The staff has determined that this amendment involves no j l significant increase in the amounts, and no significant change in the types, of any effluents j that may be released off site, and no significant increase in individual or cumulative i occupational radiation exposure. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
l 4.0 fablCLUSION The staff has concluded, on the basis of the considerations discussed above, that (1) because the amendment does not involve a significant increase in the probability or
- consequences of accidents previously evaluated, or create the possibility of a new or different kind of accident from any accident previously evaluated, and does not involve a l significant reduction in a margin of safety, the amendment does not involve a significant i
hazards consideration; (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed activities; and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or the health and safety of the public.
l
- Principal Contributor: A. Adams, Jr.
l Date:
I' I
l
)
)
I l
t l
-- - _ . .