|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20149F3901997-07-15015 July 1997 Safety Evaluation Supporting Amend 14 to License R-83 ML20059G0301993-10-26026 October 1993 Safety Evaluation Supporting Amend 13 to License R-83 ML20151L6591988-03-23023 March 1988 Safety Evaluation Supporting Amend 11 to License R-83 1997-07-15
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20205Q3481998-12-31031 December 1998 Tx A&M Univ Sys Tx Engineering Experiment Station Nuclear Science Ctr 1998 Annual Rept. with ML20151W2321998-09-0808 September 1998 Ro:On 980826,facility Bldg Air Monitor (Fam Channel 4) Failed Daily Fam Alarm Checks Prior to Reactor Operation. Caused by Failed Alarm Relay.Staff Is Preparing Formal Written Procedures for Testing Configurations for Fam Sys ML20217A0891998-03-18018 March 1998 Ro:On 980218,potential Reactor Safety Failure Discovered W/ Reactor Shutdown.Caused by Manual Scram Function Bypassed by Sticking Reset Contact in Console Power key-switch. Protective Action Reset Switches Wired ML20217K1401997-12-31031 December 1997 Tx A&M Univ Sys Tx Engineering Experiment Station Nuclear Science Ctr 1997 Annual Rept ML20199C5371997-11-11011 November 1997 Ro:On 971030,shim Safety Number 2 Was Found to Be Binding & Became Stuck in Withdrawn Position & Control Rod Failed to Scram.Caused by Incorrect Spacing Between Hold Down Foot & Bundle top-handle.Procedure SOP-II-I Modified ML20149F3901997-07-15015 July 1997 Safety Evaluation Supporting Amend 14 to License R-83 ML20137Y0351997-04-16016 April 1997 Rev 4 to Nuclear Science Center Senior Reactor Operator & Reactor Operator Requalification Program ML20137H0541996-12-31031 December 1996 Tx A&M Univ Sys Tx Engineering Experiment Station Nuclear Science Center 1996 Annual Rept ML20129H5191996-10-30030 October 1996 Ro:On 961015,loss of Facility Power Occurred Causing Reactor Scram Due to Lack of Attention to Detail & Excessive Distractions to Operations.Startup Checklist Had Several Individual Instrument Checks Combined Into Single Items ML20115G5511995-08-31031 August 1995 Engineering Analysis of a Power Upgrade for Tx A&M Nuclear Science Ctr Reactor ML20082D5521994-12-31031 December 1994 Thirty-First Annual Progress Rept of Tx A&M Univ Nuclear Science Ctr, for Period of 940101-1231 ML20069H4271993-12-31031 December 1993 Thirtieth Annual Progress Rept of Nuclear Science Ctr Tx Engineering Experiment Station Tx A&M Univ Sys College Station,Tx ML20059G0301993-10-26026 October 1993 Safety Evaluation Supporting Amend 13 to License R-83 ML20094N5431991-12-31031 December 1991 Nuclear Science Center 28th Annual Rept,CY91 ML20079C2481991-06-10010 June 1991 Ro:On 910607,reactor Operated for 30 Minutes at 1 MW W/O Facility Air Monitors in Operation.Operator Removed from Watch Standing Duties.Final Rept Will Be Forwarded Upon Completion ML20066H1401991-02-0808 February 1991 Special Rept 90-01:on 910125,during Annual Fuel Insp of Operational Core VIII-A,fuel Elements 6502 & 8468 Failed to Pass go-no-go Gauge Test for Excessive Transverse Bend. Elements Replaced W/Spare & Fuel Bundles Relocated ML20070R9351990-12-31031 December 1990 Twenty-Seventh Progress Rept of Texas A&M Univ Nuclear Science Ctr Jan-Dec 1990 ML20070U0201990-12-31031 December 1990 Twenty-Sixth Progress Rept of Texas A&M Univ Nuclear Science Ctr,1990 ML20043F4391990-06-0404 June 1990 Revised Page 1 to Reactor Operator & Senior Reactor Operator Requalification Program,Rev Iii.Item 2.1.6 Changed to Include Physical Security Plan ML20012E0661990-03-0909 March 1990 RO 90-01:on 900228,reactor Operator Received Servo Fault Alarm.After Directed Shutdown,Complete Loss of Linear Power Channel Noted.Caused by Corroded Connector at Detector Leads.Connector Replaced.Part 21 Related ML20248J1691988-12-31031 December 1988 Twenty-Fifth Progress Rept of Texas A&M Univ Nuclear Science Ctr,Jan-Dec 1988 ML20151Y9031988-07-15015 July 1988 Review of Texas A&M Univ Nuclear Science Ctr - Beam Port Experiment ML20151L6591988-03-23023 March 1988 Safety Evaluation Supporting Amend 11 to License R-83 ML20148M5691987-12-31031 December 1987 Twenty-Fourth Progress Rept of Texas A&M Univ Nuclear Science Ctr,1987 ML20205Q8241986-12-31031 December 1986 Twenty-Third Progress Rept of Texas A&M Univ,Nuclear Science Ctr for 1986 ML20203B0091986-07-10010 July 1986 Ro:On 860708,no Rod Down Indication Received for Transient Rod Until Carriage Driven In,During Performance of Manual Scram for Reactor Shutdown.Caused by Malfunction of Reactor Safety Sys Component.Repairs Underway ML20199B1171986-06-0404 June 1986 Ro:On 860501,improper Handling of Experiment Discovered Which Could Have Resulted in Serious Operational Event. Caused by Insertion of $1.09 Reactivity.Postulated Accidents & Results & Related Info Encl ML20205Q2921986-05-16016 May 1986 Final Ro:On 860501,unanticipated or Uncontrolled Change in Reactivity Greater than One Dollar Occurred.Caused by Removal of Rotisserie from Face Water Notch.Proposed Changes to SOPs Developed as Listed ML20205J9311986-02-18018 February 1986 RO 86-01:on 860204,temp Recorder Providing LSSS Signal to Scram on High Fuel Temp Malfunctioned.Caused by Defective Motor Bearing.Bearing Replaced & Recorder Calibr ML20199G0441985-12-31031 December 1985 Twenty-Second Progress Rept of Texas A&M Univ Nuclear Science Ctr,1985 ML20137Y6291985-09-24024 September 1985 RO-85-04:on 850912,transient Rod Followed Cylinder Out During Positioning of Transient Rod Cylinder.Air Solenoid for Transient Rod Sys Not Functioning as Designed.Air Solenoid Disassembled,Cleaned & Reassembled ML20127M4151985-05-0909 May 1985 Ro:On 850508,during Restart Following Power Failure,Facility Air Monitoring (Fam) Sys Inoperable for 15 Minutes.Caused by Turning Off High Voltage to Detectors.Procedures Revised to Verify Fam Sys After Power Failure ML20113D5681985-01-21021 January 1985 RO 85-2;on 850111,safety Channel 1 Detector Failed During Reactor Operation.Caused by Loose Connector Pin Making Intermittent Contact.New Connector Installed & Detector Verified Operable Prior to Reinstallation ML20134Q1961985-01-11011 January 1985 Ro:On 850111,reactor Shut Down When Safety Channel 1 Did Not Respond Following Annual Reactor Maint.Cause Undetermined. Detector & Cabling Replaced ML20134P7391985-01-10010 January 1985 RO 85-1:on 850108,fuel Temp Recorder Indicated 600 F Instead of 720 F.Caused by Failure of Reactor Safety Sys Channel. Faulty Slide Wire & Contact Arm Replaced ML20134Q2081985-01-0808 January 1985 Ro:On 850108,fuel Temp Recorder Indicated 600 F Instead of 720 F After Reactor Power Returned to 1 MW Following Sample Positioning.Reactor Shut Down & Faulty Slide Wire & Contact Arm Replaced ML20100C9651984-12-31031 December 1984 Twenty-First Progress Rept of Texas A&M Univ Nuclear Science Ctr,1984 ML20090E1251984-07-0202 July 1984 RO-84-4:on 840626,reactor Operator Noted That Fuel Element Temp Recorder Did Not Correspond to Digital Indication as Shown on Doric Temp Readout.Cause Not Stated.Failure Spurious & Could Not Be Reproduced ML20090D7841984-06-26026 June 1984 Telecopy Ro:On 840626,fuel Elements Temp Recorder Failed to Respond Following Temporary Reduction in Reactor Power.Cause Not Stated ML20090E1241984-06-15015 June 1984 RO 84-3:on 840604,reactor Operator Observed That Safety Power Measuring Channel 2 Not Responding as Reactor Power Level Increased Beyond 30 Kw.Caused by Loose Safety Channel 2 Signal Cable.Connector Replaced ML20090E5141984-06-11011 June 1984 RO 84-2:on 840528,erratic Performance of Reactor Servo Control Not Noted in Log.Caused by Personnel Error.Operator Cautioned to Be More Observant While Taking Log Readings ML20134Q2511984-06-0505 June 1984 Ro:On 840604,during Startup,Reactor Shut Down When Channel 2 Not Indicating in Expected Power Range.Caused by Faulty Connector.Faulty Signal Cable Connector Replaced & Normal Operations Resumed ML20092N9211984-05-29029 May 1984 Ro:On 840528,operator Received Servo Fault Alarm & Linear Power Channel Indication Failed Low.Caused by High Voltage Supply for Linear Defector de-energized ML20084H6171984-04-0202 April 1984 Ro:On 840319,discovered That Performance of Weekly Electronic Maint Checks Not Performed During Previous Wk of Operation.Caused by Inadequate Procedural Controls ML20087N3381983-12-31031 December 1983 Twentieth Progress Rept of Texas A&M Univ,Nuclear Science Ctr,1983 ML20078P0111983-10-28028 October 1983 Ro:On 831004,high Power Scram Received During Initial Reactor Startup While Banking Shim Safety Control Rods After Reaching 1 MW Power.Caused by Operator Manipulation of Control Rods.Procedures & Proper Documentation Emphasized ML20024E1251983-04-30030 April 1983 Nineteenth Progress Rept of Texas A&M Univ Nuclear Science Ctr for 1982. W/830516 Ltr ML20071H9171983-04-30030 April 1983 Nineteenth Progress Rept of Tx A&M Univ Nuclear Science Ctr 1982 ML20076F0281983-04-30030 April 1983 Nineteenth Progress Rept of Texas A&M Univ Nuclear Ctr, 1982 ML20028E6911983-01-11011 January 1983 Telecopy Ro:On 830110,during Reactor Startup,Fuel Temp Not Tracking Although Normal Temp Indication Displayed.Reactor Shut Down.Caused by Failed Fuel Thermocouple.Reactor Switched to Second Thermocouple 1998-09-08
[Table view] |
Text
- . _ _ _ .
je"%,%
l p% UNITED STATES s* j 4'
NUCLEAR REGULATORY COMMISSION l
WASHINGTON. D.C. 2066Hooi
. . . . . ,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0. 14 TO FACILITY OPERATING LICENSE NO. R-83 TEXAS ENGINEERING EXPERIMENT STATION TEXAS A&M llNIVERSITY SYSTEM DOCKET NO. 50-128
1.0 INTRODUCTION
By letter dated April 15, 1997, as supplemented on May 26, 1997, the Texas Engineering Experiment Station (TEES licensee), requested that the scope o)/ Texas A&M University System (the f the reactor license be amended to
. clarify the possession and use of byproduct materials within the Nuclear Science Center (NSC), which is part of the TEES, and to allow possession of byproduct trash. material until they decay sufficiently to be disposed of as ordinary 2.0 EVALUATION The license was amended in October 1993 (Amendment No. 13) to allow possession of byproduct material that was within the NSC site boundary, and at that time was under the state license. This change was made because the State of Texas requested that their byproduct material within the NSC perimater be the responsibility of the reactor licensee. By so doing, the uncertainties that ,
arise as to which licensee is responsible for violations while the material is on the NSC site would be eliminated. Also, tracking of the material on the NSC site would be more efficient.
Amendment No. 13 accomplished this change by changing license condition II.B.(3) to read as follows:
Pursuant to the Act and 10 CFR, Chapter I, Part 30, " Rules of General
~
Applicability to Domestic Licensing of Byproduct Material," to receive, J possess, and use in amounts as required, any byproduct material without restriction to chemical or physical form, for analysis or instrument calibration but not to separate such byproduct material as may be produced by operation of the reactor.
l 1
I 9707220173 970715 PDR ADOCK 03000128 P PDR
4 It was 'noted in a recent inspection that some of the byproduct material that is now considered to be under the reactor license is not being used for
" analysis or instrument calibration" as license condition II.B.(3) requires.
The licensee has proposed to modify this license condition to better define the possession and use of byproduct material. The licensee states in his letter of April 15, 1997, that it would te impossible to operate the reactor and only produce radioactive material for " analysis and instrument calibration." Activated structures and experiment materials are produced in and around the reactor during the normal daily operations. Experimental devices that have failed or become obsolete are stored onsite for decay or possible reuse. During routine handling operations, an amount of low-level radioactive waste is produced and is stored at the facility. High-activity isotopes are regularly produced and shipped for commercial purposes. The licensee has proposed in his letter of May 26, 1997 to modify license condition II.B.(3) to read as follows: l Pursuant to the Act and 10 CFR, Chapter I, Part 30, " Rules of General Applicability to Domestic Licensing of Byproduct Material," to receive, possess, and use in amounts as required any byproduct material without restriction to chemical or physical form in connection with operation of the reactor that has a definite research and development purpose and any byproduct material generated by the licensed activities, but not to separate such byproduct material except for byproduct material produced in reactor experiments.
It is noted that the phrase " analysis or instrument calibration" has been replaced with "in connection with operation of the reactor that has a definite l research and development purpose." i This revision more accurately describes the possession and use of byproduct material at the NSC for reasons cited previously by the licensee. Also, the licensee is required to abide by the regulations in 10 CFR Parts 20 and 30, in addition to Technical Specifications dealing with experiments. Therefore, the i staff finds that the use of byproduct material as specified in the new '
II.B.(3) is acceptable.
In order to account for byproduct material at the NSC that is outside the scope of license condition II.B.(3) a new license condition is being proposed by the licensee as follows:
License Condition II.B.(7)
Pursuant to the Act and 10 CFR, Chapter I, Part 30, " Rules of General Applicability to Domestic Licensing of Byproduct Material," to possess and store for decay such byproduct material as are within the facility at the time of Amendment No.14.
i .
3 l
This-license condition is being proposed to account for material that was formally under the Texas State license that would not fit the definition of material that can be possessed and used under the new license condition II.B.(3). Some of this material was on the NSC site under the Texas State license since 1970 and the licensee misinterpreted the license condition in II.B.(3) approved in Amendment 13 to mean that this material could be possessed under that license condition. The licensee points nut that it is currently cost prohibitive to dispose this material in a commercial landfill.
The licensee requests that this license condition be added to allow storage l
snd decay of the byproduct material that is already on the NSC site. Future possession and use of byproduct material will be governed by the new license condition II.B.(3). -The staff notes that some of this material has been at.
the NEC since 1970, and since the licensee is required to abide by 10 CFR Parts 20 and 30, finds that this license condition is acceptable.
Finally, the licensee proposes to include in the license the provisinn for disposal of low level waste, which has decayed to acceptable levels, as ordinary waste as permitted by 10 CFR 35.92, and as is permitted in materials licenses. The staff finds this acceptable and is modifying license condition II.C to include the reference to'35.92.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change in a requirement with respect to the installation or use of facility components located within the restricted areas defined in 10 CFR Part 20. The staff has determined that this amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and-there is no significant increase in individual or cumulative 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.
4.0 CONCLUSION
The staff has concluded, based on 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 significant reduction in a margin of safety, the amendment does not involve a significant hazards consideration, (2) there.is reasonable assurance that the health and safety of the public will not be endangered by the proposed changes, 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 l the health and safety of the public.
L-l Principal Contributor: Theodore S. Michaels
! Date: July 15, 1997
. - - - .- - - . ._ _. . _ - - _ - . . , _ -