ML20247B218
| ML20247B218 | |
| Person / Time | |
|---|---|
| Site: | University of Utah |
| Issue date: | 06/30/1989 |
| From: | Gehmlich D, Sandquist G UTAH, UNIV. OF, SALT LAKE CITY, UT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8909120387 | |
| Download: ML20247B218 (28) | |
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- Document Control Center U.S. Nuclear Regulatory Commission ~
Washington,D.C. 20555 .
Gentlemen : ,
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Enclosed you will find a copy of the Annual Operating Report for the University of Utah'
~ TRIGA Reactor, License R-126, Docket 50-407, for the period July 1,1988 through June 30, 1989. This repon fulfills Technical Specification 6.10 (5).
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If you have any questions concerning the report please contact the staff at the facility.
Sincerely, m- , .
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. Dietrich K. Gehmlich ,
ReactorAdministrator 1 k
Conege of 0.ngineering Office of the Dean 8909120387 890630 7 Y 2202 Merriti Engineering Building
_PDR:
R ADOCK.0500 Salt lake Oty, Utah 84H2 [
Telephone (801) 5814911 I
FAX (5801) 581-8692 'l
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The University of Utah TRIGA Reactor AnnualOperating Report for the period 1 July i A8 through 30 June 1989 A. NARRATIVE.
- 1. Operating Experience.
The TRIGA Reactor was critical 107.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and generated 6922.7 kWh of thermal energy during this reporting year. The reactor was used for educational demonstrations, laboratory experiments, systems tests, power measurements, and sample irradiations. The mactor was not operated from 1 July 1988 through 7 November 1988 as directed by NRC.
Operations resumed 8 November 1988 following the satisfactory implementation of additional administrative support by the Licensee.
- 2. Changes in Facility Design.
A Continuous Airborne-radiation Monitor (CAM) was installed in the TRIGA control console August 30,1988. A thin end-window, beta- and gamma-sensitive Nal detector previously connected to just the strip-chart recorder located in the front Radiochemistry Laboratory (Merrill Engineering Building [MEB] 1205-F) monitors air exhausted from University of Utah Nuclear Engineering laboratory (UUNEL) and provides the signal to the CAM. The CAM is equipped with both visual and aural alarms and has been calibrated to trip at 50% of the maximum pemiissible concentration (MPC) of argon-41.
An airborne-particulate sampler was installed in the exhaust duct of the ventilation system from September 16 - 19,1988. Particulate am collected on a two-inch fiberglass filter medium facing the direction of air flow through the duct. Gas samples may be obtained by insening an activated charcoal canister into the sampler immediately behind the particulate filter. The sampler is situated so that the filter is visible to the NaI detector of the CAM.
Filters are replaced and analyzed monthly; the monthly inspection procedures have been revised to accommodate data logging. Implementation of the CAM / particulate-sampling system brings the Licensee into full compliance with TRIGA Technical Specifications regarding the function of the Radiation Monitoring System.
A switch which enables the lights of the reactor room (MEB 1205-E) to be operated from the laborator' sssroom (MEB1205) was installed October 20,1988. The switch was suggested by a tiversity Police Officer during annual familiarization training conducted in June,1988. Ths , witch allows officers responding to emergency alarms to visually inspect the reactor area before facility personnel have arrived to permit access to the reactor room and the radiochemistry laboratories (MEB 1205-F and -G).
On January 31,1989, a new lock was installed in the reacter room door as requested by R.J. Everett, Chief of the Security and Emergency Preparedness Section for NRC Region IV. Keys to the lock are nonreproducible and are strictly controlled by the University Keyshop. A plug was inserted into the lock of the emergency exit between the back Radiochemistry Laboratory (MEB 1205-G) and the Thermal Science Laboratory (MEB 1156). This action allows the door to be opened only from the inside of UUNEL for i emergency egress.
A fast-neutron irradiator was constructed and emplaced along the southwest face of the
University of Utah TRIGA Reactor
, 1988-89 Annual Operating Report page 2 reactor core on February 27,1989. ' Die irradiator was designed to allow for the irradiation of experiments with minimal moderation while providing some attenuation of gamma radiation. The irradiator is constructed of aluminum and consists of a water-tight box filled with lead-brick shielding. Experimental samples are loaded into an aluminum sample holder which is then manually inserted into the irradiator. A desired neutron fluence is delivered to the samples by subsequent operati&1 of the reactor.
An auxiliary reactor-power-level detection assembly was fabricated from aluminum to house a fission chamber and a compensated ion chamber acquired from the Northrup Corporation in 1985. The assembly was installed on the northwest face of the reactor core on June 15,1989. The compensated ion chamber was connected to the Series /1 computer to provide an additional power level monitoring channel; the fission chamber will be connected to the computer at a later date. Calibration of the software reading the detector signalis now in progress.
- 3. Surveillance Tests.
(Documentation of all surveillance activities is retained and stored by the facility.)
- a. Contml Rod Worths.
Core Configuration #19 8 November 1988 Safety Rod $1.87 Shim-safety Rod $1.53 Regulating Rod $0.38 Excess Reactivity $1.22 Shutdown Margin $0.69 Core Configuration #21 14 November 1988 Safety Rod $2.13 Shim-safety Rod $1.51 Reguladng Rod $0.28 Excess Reactivity $1.02 Shutdown Margin $0.77 Core Configuration #21 23 November 1988 Safety Rod $2.03 Shim-safety Rod $1.70 Regulating Rod $0.29 Excess Reactivity $1.47 Shutdown Margm $0.52
- b. Control Rod Inspection. I The Biennial Control Rod Inspection is scheduled for December,1989. Rod drop times weie measured on 11/8/88,11/14/88, and 11/23/88. All rod drop times were less than 0.8 secondsm
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University of Utah TRIGA Reactor
. 1988-89 AnnualOperating Report page 3
- c. Reactor Power Level Instrumentation.
Calorimetric power calibrations were performed on 11/15/88,2/7/89. 2/22/89, and 2/23/89. The following results were obtained.
_ Daig Meter Readine Actual PowerImel 11/15/88 85 kW 85.4 kW 02/07/89 90 kW 92.5 kW 02/22/89 90 kW 97.9 kW 02/23/89 90 kW 89.2 kW
- d. FuelInspection.
The Biennial Fuel Inspection is scheduled for December,1989. Six defective fuel elements have been identified as possibly contributing to the release of fission products during reactor operation (see below in the section pursuant to 10 CFR 50.59). The elements have been removed from the reactor core and are now in storage. Subsequent reactor operations have demonstrated that the source of the leakage has been removed and the problem has been resolved.
- e. FuelTemperature Calibration.
Fuel temperature circuits were calibrated on 11/08/88 and 2/13/89. The circuits were calibrated to less than a 5 *C ermr over the range 20 *C to 500 *C.
- f. Reactor Safety Committee Audits.
Reactor Safety Committee (RSC) member J. M. Byrne audited the maintenance and operational activities of the facility during September,1988 and April,1989. Copies of these reports are included in the appendix.
University of Utah Radiation Safety Officer (RSO) and RSC member K. J. Schiager prepared an audit report of radiation safety and monitoring at UUNEL. A copy of this report is included in the appendix.
- g. Environmental Surveys.
RSO K. J. Schlager reported to the RSC a maximum total exposure of 40 millirem per quarter to environmental dosimeters located at various positions surrounding UUNEL for the period July 1,1988 through March 31,1989.
B. ENERGY OUTPUT.
The reactor was critical for 107.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and produced 0.288 megawatt-days (6922.7 kilowatt-hours) of energy during this reporting period. Since initial criticality, the reactor has been critical a total of 1,803.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> with an accumulated total energy output of 4.51 megawatt-days (108,166.6 kilowatt-hours).
C. INADVERTENT SCRAMS.
University of Utah TRIGA Reactor
. 1988-89 AnnualOpenting Report page 4 There were five inadvertent SCRAMS while the mactor was critical during the current reporting xriod. The type, cause, and action taken by the operations staff of each SCRAM are outlined elow:
Ouantity Tyne Cause Action 1 High IAg Signal spike while recalibrating Cautioned personnel.
Power channelduring operation.
Channel 2 Linear Signal spike during Restart.
Power switching power level (2).
Channel 1 Magnet Current Interruption of current Restart.
Failure caused by power fluctuation.
I High-level Radioactive sample Cautioned personnel.
Radiation removed fmm reactor.
Alarm D. MAJOR MAINTENANCE.
Exhausted ion-exchange resin in the 2-cubic-feet mixed-resin bed of the pool-water-purification system was replaced with new DOWEX MR-3 Nuclear Grade resin on October 18,1988. The spent resin was dried and placed in storage containers pending transfer to the U of U Radiological Health Department (RHD) for disposal. On June 20,1989, spent resin from auxiliary demineralized tanks was removed, dried, and stored in containers pending disposal.
The empty tanks are being stored in the reactor room until needed. A total of approximately 10.5-cubic-feet of resin is being stored in UUNEL until transfer for dispos:d.
The conducting foil of the intrusion detection system which circumscribes the windows between the reactor room and interior portions of UUNEL (i.e., the TRIGA control room
[MEB 1205-D], the laboratory classroom [MEB 1205-C], and the Chief Reactor Supervisor's office [MEB 1205-A] was replaced during September,1988. The system was carefully inspected after receiving spurious alarms on November 23 and 25. A loose connection between the solid-core copper wire and the foil was discovered on the safety-glm windows between the control room and the reactor room. These windows undergo a great deal of deflection whenever the ventilation system is turned on. This cycling of window motion and vibration with ventilation system operation apparently caused the foil-wire junction to deteriorate and led to occasional false alarms anytime the electrical current through the system was momentarily interrupted. The junctions were repaired by sandwiching the copper wire between two layers of foil thereby making a much better connection. There have been no spurious alarms since this repair was made. The junctions are inspected regularly to prevent recurrence of this problem.
The northwest corner of the Counting Laboratory (MEB 1205-C) was decontaminated during l May,1989. The contamination was caused many years ago by an accidental discharge of a small amount of cobalt-60 contaminated water from the pneumatic sample-transfer system.
Although the contamination existed at very low levels, it had been a chronic source of interference to spectmscopy because of the close proximity to the gamma-radiation detection 1
University of Utah TRIGA Reactor
, 1988-89 AnnualOperating Report page 5 i
equipment. The cobalt had been absorbed by the wooden bench on which the intrinsic ]
germanium detector was located and resulted in the formation of several " hot spots" of Co-60 ;
activity. Some Co-60 was also absorbed by the sheetmck behind the bench and in some cracks j between the linoleum floor tiles. These hot spots were identified and removed by carefully 1 excising the contaminated material. The wooden bench wrs replaced by a similar, uncontaminated bench since the countertop had small areas of unremovable contamination. In addition, contaminated valves and plastic pipe which deliver compressed air to propel samples i within the pneumatic transfer apparatus were replaced. All contaminated materials were collected and will be transferred to RHD for disposal. A subsequent survey of the area by {
RHD has indicated a significant reduction in Co-60 activity.
E. CHANGES, TESTS, AND EXPERIMENTS PURSUANT TO 10 CI': 50.59.
As of the end of the reporting period, the current membership of the Reactor Safety Committee (RSC) as designated by the Licensee is as follows:
Dietrich K. Gehmlich, Reactor Administrator Gary M. Sandquist, Nuclear Engineering Laboratory Director Keith J. Schiager, Radiation Safety Officer Kevan C. Crawford, Reactor Supervisor John S. Bennion James M. Byrne Vern C. Rogers As reported in the 1987-88 Annual Operating Report, UUNEL staff detected in November, 1987, the presence of fission pmducts in the coolant following reactor operations as a result of leakage by defective TRIGA fuel. A program was implemented to identify the source of the leakage by exchanging fuel from the core with fuel in storage. Following the exchange, the reactor was operated as allowed by TRIGA Technical Specification 4.4(3) which permits short-term operation to assist in finding leaking fuel elements. A sample of the coolant was then taken and analyzed for the presence of previously observed fission-product gases, e.g.,
Kr-85m, Kr-87, and Xe-138. After exchanging nearly one half of the fuel elements in the core and observing no decrease in the activity released by the defective fuel,it became apparent that several defective elements may be contributing to the leakage. A new identification program was devised to sample water directly above each fuel element in the core while the reactor was operating at a constant power level. The sampled water was then pumped around a germanium crystal to detect areas of high Kr-85m activity as a function of core position. Included in the appendix is a memorandum to the Reactor Safety Committee (RSC) which explains in detail the program and its results. Six possible defective fuel elements were identified using this procedure and were removed fmm the reactor core. Subsequent reactor operations have shown no evidence of any fission-product leakage. The RSC reviewed the results of the experiments performed to identify the source of the leakage and concluded that this problem had been satisfactorily resolved.
The compensating voltage to the compensated ion chamber of the Hi Log Power Channel was increased from -14 to -44 volts by the Reactor Supervisor on June 20,1989. This change was made to achieve a balanced compensation in the chamber.
The RSC has reviewed and approved several NEL pmcedures which were modified to .rpdate and correct any deficiencies. The NEL staff continues to review and update facility documentation to assure compliance with applicable regulations.
University of Utah TRIGA Reactor
. 1988-89 Annual Operating Repon page 6 F. RADIOACTIVEEFFLUENTS.
- 1. Liquid Waste - Total Activity Released: 2.84 pCi On January 13,17, and 18,1989, shielding water in the North Fuel Storage Pit was recirculated through an ion-exchange resin bed to remove trace amounts of cobalt-60 and cesium-137 contamination. The water was then analyzed by the University of Utah Radiological Health Department for activity content and detennined to be below d :tectable limits. A sample counted using a 5-inch NaI(TI) detector was determined to consei ratively contain approximately 11 nanocuries per liter. A total of 183.5 liters of the waste water was further diluted by the ratio 10:1 and disposed of by pumping to the sanitary sewer system. Assuming that the total activity cf the water was due to Co-60 yields an estimated 2.1 pCi of Co-60 released to the environment.
Removal of spent ion-exchange resin from the pool-water-demineralizing system yielded 76 liters of water containing 0.74 pCi of Co-60. Since the concentration of the Co-60 was well below 10 CFR 20 Appendix B limits for release to unrestricted areas, the waste was discharged to the sanitary sewer system.
- 2. Gaseous Waste - Negligible.
The TRIGA Reactor was operated for 107.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> at power levels up to approximately 90 kW. At this power level argon-41 production is negligible. The minimum detectable concentration of Ar-41 for the stack monitor has been found to be one-third of 10 CFR 2.0 appendix B limits for release to unrestricted areas. The average annual calculated concentration of Ar-41 generated during operations is estimated at 1.63 x 10-2 pCi/ml which is 0.4% of the MPC for this radionuclides. The total amount of radioactivity released was estimated at 53.5 pCi. A monthly summary of gaseous releases is given in Table I.
Table I.
Summary of Monthly Gaseous Radioactive Effluent 1 July 1988 through 30 June 1989 Month Estimated Release ( uCi) j July 0.0 August 0.0 September 0.0 October 0.0 November 8.4 l December 7.1 l January 8.1 February 10.7 March 3.6 i April 4.6 l May 5.5 June 5.5 Total activity of gaseous effluent- 53.5 pCi
- 3. Solid Waste - Total Activity: 5 mci
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University of Utah TRIGA Reactor
~' "
. 1988-89 Annual Operating Report
. .page 7 Six bags of contaminated waste consisting primarily of cleaning supplies contaminated with Co-60 with a total estimated activity of 5 mci were transferred to RHD for disposal. The waste was compacted by RHD to a volume of 0.5 cubic feet and placed in a 55-gallon steel drum with other wastes generated by University users of radioactive materials. The drum and its contents was shipped to RAMP Industries in Denver, Colorado on March 23,1989 11
- for final disposition.
Approximately 10.5 cubic feet of solid waste was generated by the facility during the I reporting period. This waste consists of low-level decontamination materials, debris removed from the reactor tank during cleaning, spent ion-exchange resin from the l pool-water purification system, and other wastes that have accumulated over previous years. The waste is being analyzed both qualitatively and quantitatively for radioactivity L
content in preparation of transfer to RHD for disposal and is being stored in the Controlled Access Area of the facility.
G. RADIATION EXPOSURES.
Personnel with duties in the reactor laboratory on either a regular or occasional basis have been issued a film-badge dosimeter by the University of Utah Radiological Health Departarnt. The duty category r.nd monitoring period of personnel are summarized below:
Name Monitorine Period Duty Catecorv G. M. Sandquist 7/88-6/89 regular J. S. Bennion 7/88-6/89 regular T. C. Gansauge 7/88-6/89 regular K. C. Crawford 9/88-6/89 regular M. Tolle 7/88-12/88 terminated V. Tang . 7/88-6/89 terminated C. Henderson 7/88-6/89 occasional B. Rogers 6/88-8/88;1/89-3/89 regular .
M. Slaughter 12/88-6/89 occasional S. McCormick 1/89-6/89 occasional G. Smith 5/89 occasional B. Hardy 6/89 occasional R. Lines 6/89 regular B. Hanson 6/89 regular G. Brewer 6/89 regular Dose Equivalent summary for Reporting Period:
Measured Doses 7/1/88 - 5/31/89 Doses: 10 mrem average; 30 mrem highest measured.
Dose Eauivalent Limits Maximum Permissible Dose Equivalent = 5000 mrem / year (1250/quaner).
Minimum Detectable per Monthly Badge = 10 mrem.
Of the 522 visitors to the facility under the DOE Reactor Sharing Program for the reporting year, no visitor received a measurable dose. Therefore, the average and maximum doses I
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i, + University of Utah TRIGA Reactor
.. 1988-89 AnnualOperating Report page 8 are all within NRC guidelines. A summary of whole body exposures is presented in Table II.
Table II.
Summary of Whole Body Exposures 1 July 1988 thmugh 31 Msy 1989 Estimated whole body exposure Number ofindividualsin range (rems): each range:
No Measurable Dose 11 Ixss than 0.10 4 0.10 to 0.25 0 0.25 to 0.50 0 0.50 to 0.75 0 0.75 to 1.00 0 1.00 to 2.00 0 2.00 to 3.00 0 3.00 to 4.00 0 4.00 to 5.00 0 Greater than 5 0 Total number of individuals reponed- 15 H. LABORATORY SURVEYS.
Monthly surveys of the facility were conducted by the University of Utah Radiological Health Department during the reporting period. Some of these surveys have identified minor removable contamination sources which were immediately cleaned. The surveys have indicated no increase in radiation levels over previous years. Records of surveys are retained by the facility.
I. ENVIRONMENTAL SURVEYS.
The Air Monitoring Station, operated by the Environmental Protection Agency and located i outside the reactor building, has indicated no unusual changes in radiation or radioactive l material concentrations during the reporting period. J
)
Environmental sutveys conducted quarterly by the University of Utah Radiological Health Department indicated no unusual dose rates in the areas smounding the Merrill Engineering Building, which houses the reactor facility, or anywhere on the University of Utah campus.
Prepared by: John S. Bennion, Senior Reactor, Engineer Date: 23 August 1989 8/2 . - b 8f'# Date: eMMA M.
Submitted by- y
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,Universit of Utah TRIGA Reactor 1988-89 AnnualOperating Report page 9 L
r APPENDIX
- 1. September 30,1988 Audit Report by J. M. Byrne.
- 2. April 11,1989 Audit Report by J. M. Byrne.
- 3. August 8,1989 Audit Report by K. J. Schlager.
- 4. 1988-9 Radiation Monitoring Summary by K. J. Schiager,
- 5. January 3,1989 Memorandum to Reactor Safety Committee by J. S. Bennion.
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- j. TO : . Reactor Safety Committee
'VIA: Dietrich Gehmlich, Reactor Administrator FROM:- Jim Byrne -
I' DATE: . September 30, 1988
SUBJECT:
=U OF U REACTOR SAFETY COMMITTEE AUDIT REPORT A. Subject of Audit: TRIGA Operations and Maintenance '
- 1. -Frequency: Semi-Annual
- 2. Performed by: J.M. Byrne -
- 3. Date: 9/29/88 4 '. -
Review Period: 1/31/88 to 9/29/08
- 5. Target date next~ audit: 1/31/88 B. Performance' Specifications and
References:
1.
TRIGA TECH. SPEC (TTS) 6.5.5. Audits. requires the RSC or a subcommittee thereof to audit reactor operations semi-annually at ' intervals not to exceed eight months. The audit 'shall' include' operating records, ' inspection of reactor operating areas, and review of unused or abnormal events.
2.
'TTS 6.'8 Operatina Procedure _g requires operating procedures for reactor start-up, operation, shutdown, and maintenance.
-3. TTS 6.9 facility Operatino Records requires records of normal reactor operation be kept for five years.
C. Implementing Procedures:
- 1. The UUNEL Facility Operations Manual (FOM) contains
. procedures on TRIGA Reactor Check Out, operations, shutdown, maintenance, calibration, fuel change, etc. I was not able to review the FOM because it was in the process of ' being revised and the computer ate several chapters.
- 2. The Comprehensive Reactor Review and Safety / Operations Evaluation Plan (Page 36) lists RSC audits for the following:
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- a. Op3 rational Rrcorda ;
.-- -1. Maintenance Log *
- 11. Master Log 111. Operational Log iv. Inspection and Procedures Log
- b. Inspect Reactor Operating Areas
- c. Unusual or Abnormal Events
- d. Radiation Exposures This audit covers items a. through c. Keith Schlager covers item d.
D. Records Sources:
- 1. Preliminary Check Out Sheets B1 and B2
- 2. Critical Approach and Termination Check Sheet B3 j
- 3. Operations Log #20 '
- 4. Master Log-
- 5. Inspection and Procedures Log
- 6. Maintenance Log
~7. RSC Log
- 8. Semi-Annual Checks Log E. Determine whether all requirements are covered by implementing procedures and whether all procedures are met and documented.
- 1. All action items from the previous Maintenance Activity Audit (2/18/88) were dealt with by the RSC in its 5/25/88 meeting. The only action item outstanding was the Maintenance Log Procedure containing a standard for entries in the Log. This form (NEL-019) was approved by the RSC at its 7/27/88 meeting and is now in placa.
- 2. The recommendations of the previous Operations Audit (2/19/88) were reviewed and approved by the RSC at the 5/25/88 meeting. Some of these items have not yet been resolved as discussed below:
- a. Recommendation 1 - documentation of the "other person" for reactor operation.
Check Sheet B1 has been modified to include a place for the signature of the "other person." I was unable to verify if the FOM has been modified to include the training or qualification standard for this individual
- b. Recommendation 2 - drift of the Hi Log Channel.
The Maintenance Log (9/21 to 23/88) contains a description of a 40-hour test of the Hi Log which showed 'no drift. Staff believes drift has been corrected by replacement of a capacitor and resoldering loose connections (previously referenced in the Maintenance Log). Note in the Log indicated operators should closely monitor the Hi Log upon reactor start-up and long-term operation.
4.
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c'. RacommInd2tien 3 #rGd p:n# readinga on B1-6 Low Log
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Recommendation 4 - review of Ted Spec. question on i Operations Log-#20 page 34 and Master Log 1/11/88.
.c These items have not been responded to.
- 3. The Maintenance Log was reviewed for compliance with TS 6.8 and FOM 4.2.3 and 4.5.8 (These are sections from my version of the FOM).
The entries in the Maintenance Log continue to improve.
There are references to 10CFR50.59 Quality Assurance review and that safety systems are verified operable prior - to return to service.
I could not find, however, any indication that the RS or RSO had reviewed the maintenance activity on a reactor safety system prior to commencement of the activity as required by the 'new procedure NEL 019.
Maintenance activities are currently being performed by a SRO so perhaps a separate approval is not required, but the purpose of this requirement is to see that a determination is made prior to a maintenance activity of: (a) whether.a safety system is involved, and (b) how will the safety system be effected by the maintenance activity?
4.
A new continuous air monitor has been installed (9/16 to 19/88) with readout on the reactor console. TS 4.3.3 require both an area radiation monitoring system and a continuous air monitoring system and specifies that these systems will be calibrated biennially and verified operable on a monthly basis. TS 3.4 also requires that Ar" released from the facility not exceed 4 X lo a uci/ml averaged over one year. The Maintenance Log indicates that these systems have not been, and should be calibrated.
- 5. The Master Log was reviewed. This Log is now being used to record activities in the Nuclear Lab and the duplication previously noted is being eliminated. There were numerous references in the Log to spurious alarm signals, causing responses from Campus Security, both on and off hours.
This has hopefully been fixed by replacing the metallic tape on the windows as noted n the Maintenance Log. If this has not solved the problem of spurious alarms, then an atalysis of the alarm system should be accomplished and a report made to the RSC on solutions to this problem.
- 6. The Operations Log #20 was reviewed for compliance with the Tech. Specs. No abnormal or unusual occurrences were noted. The TRIGA Reactor was shutdown by the NRC (notice received from J. Brophy 3/31/88.
- 7. When the Reactor is started up after approval from the NRC and the RSC, semi-annual surveillance checks should be run.
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- 8. The investigation on whothar incraccing the 'osttings on tha.
Stcrt-up Count Roto Intorlock would racult in tha actuntion j]
of the interlock when the neutron source is removed from i the core (RSC Minutes- -11/16/87 Para. 5) is still an open ,
item.
- 9. Review of.the Maintenance Log, Operations Logs, and Semi-Annual checks Log indicates the following:
CONTROL ROD WORTH CALIBRATION Date 3/17/88 8/25/88 3/25/87 Safety $1.82 $1.81 $1.91 Shim $1.77 $1.34 $1.74 ,
Reg. $ .39 $ .44 N/A l Shutdown Margin $1.11 $ .61 $ .57 Excess Reactivity $1.05 $1.17 $1.17 Core Configuration 19 19 19 Is the variation in reactivity for the same core configuration due to the movement of individual fuel elements, or problems with measurement? Is the Shim position indicator involved?
F. Recommendations
- 1. The RSC should follow upon items E.2. a. and c. above.
- 2. The RSC should review whether a prior analysis of safety system maintenance is required when an SRO or RS performs
. the work (E.3. above).
- 4. Semi-Annual Checks should be run when the reactor is started up again.
- 5. The RS should be asked for an analysis and explanation of the data anomalies in E.8. above.
- 6. In E.2.b. above, there is a note in the Maintenance Log that operators should watch for drift in the Hi Log Channel. In the letter from D. K. Gehmlich to J. M. Taylor on 8/25/88 there is reference to operators being instructed to watch for notes in the Maintenance Log on core changes.
I recommended some sort of an " Operator's Information Sheet" to be kept at the TRIGA control console which would be kept up to date by the operators and SRO's which would include this kind of "new development"/"what to watch for" information.
- 7. The revision of the FOM should be completed soon after the new RS arrives. {
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MEMO L
TO: - ' Reactor Safety Committee VIA: Dietrich Gehmlich, Reactor Administrator FROM: Jim Byrne DATE: April 11, 989
SUBJECT:
U OF U REACTOR SAFETY COMMI'1 TEE AUDIT REPORT A. Subject of Audit: TRIGA Operations and Maintenance
- 1. Frequency: Semi-Annual
- 2. Performed by: J.M. Byrne F
, 3.
- 4. -
Date: 4/4/89 Review Period: 9/29/88 to 4/4/89
- 5. Target date next audit: 9/1/89 B. Performance Specifications and
References:
1.
TRIGA TECH.. SPEC (TTS) 6.5.5 Audits requires the RSC or a subcommittee thereof to audit reactor operations semi-annually at intervals not to exceed eight months. The audit. shall include o inspection of reactor operating areas,perating' records, events. and review of unused or abnormal 2.
TTS 6.8 Operatina Procedures requires operating procedures for reactor start-up, operation, shutdown, and maintenance.
3.
TTS 6.9 Facility Operatina Records requires records of normal reactor operation be kept for five years.
C. Implementing Procedures: '
- 1. The UUNEL Facility Operations procedures Manual (FOM) contains on TRIGA Reactor Check Out, operations, shutdown, maintenance, calibration, fuel change, etc. The FOM is in the prcv ess of being revised and will be reviewed in the future.
2.
The Comprehensive. Reactor Review and Safety / Operations Evaluation Plan (Page 36) lists RSC audits following: for the i
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- Cperaticnal R:ccrdo
- s' *', *
- i. Maintenance Log
- c 11. Master Log i+-
_iii.. Operational-Log
- iv.
Inspection and Procedures Log
- b. . Inspect ~ Reactor Operating Areas-c.
Unusual or Abnormal Events
- ci . Radiation Exposures
' item Thisd. audit covers ' items a. through c. Keith Schlager covers D. Records Sources:
- 1. Preliminary Check Out Sh'ets e B1 and B2.
2.
Critical Approach and Termination Check Sheet B3
- 3. Operations Log (20 and (21
~4. Master Log 5.
-Inspection and Procedures Log
- 6. Maintenance Log
- 7. RSC. Log
- 8. Semi-Annual Checks Log E.
Determine whether all requirements are covered by implementing
. procedures and whether all procedures are met and documented.
Perfor1a inspections and review for abnormal occurrences, etc.
1.
Recommendations' reviewed. from the previous audit (9/30 were These recommendations have been cons /88) by idered y the RSC and by and large have been implemented. I have reviewed while the RSCeach we discussed Minutes of thesince this audit and . find that recommendations, a number of issues remain unresolved in the record. The issues are:
a.
(9/30/88. F2) The issue of whether approval for a proposed maintenance activity should be- from an SRO or RS the. other than that person proposing and performing activity, (i.e. a second person involved in the safety analysis) was not resolved in the-Minutes, and I cannot remember if we dealt with it;
- b. (9/30/88 F6) An " Operators Information Sheet" to inform o of maintenance activities, core changes, perators and the like, resolved in the Minutes.was recommended, but was not and More on this in this audit; c.
(9/30/88 F7) Revision of the FOM remains an open item.
2.
Performed made inspection the following observations: of the reactor operating areas and a.
Rear doors to reactor bay were locked;
, b. AGN dismantling proceeding; l
- '4 *
.c . ]
~' New w2tcrproof c0n3 C
- for drtretera
- in tallotient rondy fcr i' .
d._
The new window tape for alarm system appears to have solved spurious alarm problem; e.
The and fast neutron irradiator is in place in core tank; f.
The fuelcabinet.
storage element handling tool was locked in the Question: Have the keys and locks for reactor bay been changed as per RSC Minutes 1/4/89 and the new PSP?
3.
Reviewed chart. Operators Logs $20 and #21, on the recorder strip No unusual or abnormal events were noted. The explanation of the purpose of each run is pretty cryptic.
On 1/5/89 detailed entries on maintenance probably should be Log.Maintenance Log and only referenced in the operations explained.The purpose of the fuel movement on 1/24/89 is not The drift of the Hi Log channel has been reduced considerably, but still is evident on long reactor runs.
4.
The Master Log was reviewed.
investigation entry were documented inThe was 12/27/89. the'fuel leakLog.
Master detector and The last Question: Should the Master Log entries like this be in the
! Maintenance Iog or undergo the same kind of prior review as maintenance activities?
- 5. The Maintenance Logs were reviewed. The last entry in the old bound notebook log was 11/28/88.
The new Maintenance Log looseleaf with form NEL-022 had two entries; one on 2/3/89, the otheronon the2/7/89, Linear Power Channel grounding problem, and on thermocouple.
- 6. The Procedures Log was reviewed.
The semi-annual checks were required performed by the after RSC.TRIGA start-up from URC shutdown, as 11/23/88. Thermocouple Rod drops on 11/8, 11/14, and Calibration 11/8/88, and 2/13/89.
Thermal power calibration 2/23/89. 11/15/88, 2/7/89, 2/22/89 and I could not find a record on Power Meter 7.
Calibration form NEL 013 for calibration on 2/22/89.
The RSC logs were reviewed.
The logs were not up-to-date with all RSC actions and form approvals, such as the Facility Air Monitor Calibration Report, the 1/15/89 Experiment M-1, 11/30/88 Authorization E-l Minutes, etc. and Modification Authorization Question:
Is the the RSC Lab, Nuclear Master Log (there should be two) kept in or both? '2.:. Reactor Administrator's office,
- l. .. F.
~ Recommendations f r consid:rt. tion cf the RSCt l 1.
It v;uld irprova tho cicrity of the Operations Log if an j
explanation of the purpose of the reactor run or other activity was given at the outset, such as:
- a. Irradiator run for samples from ; or
- b. Fuel movement to change core from configuration to configuration in order to increase reactivity. The FOM should reflect this standard.
2.
With respect to the Master Log and the Maintenance Log, it is recommended that the RSC consider the following:
a.
Assign someone (other than myself), or a subcommittee, to and determine if the ought to be Master Log continued; andis a worthwhile concept b.
Establish management procedures within the Nuclear Engineering Laboratory to insure that the Maintenance Log andare above) the Master Log (if it is to be retained in (a) kept up-to-date, and all significant activities are entered in these logs. It is further recommended that the entries be done as the activities are weekly.
in progress and that the management review be
- 3. With respect to continued reactor operation, it is recommended that the RSC request that the Laboratory Director provide the Committee with a timetable for " plans for modification and improvement of the instrumentation and control system" (RSC Minutes 10/11/88, 8.h.ii.)
4.
It is recommended Compliance Schedulethat the RSC consider implementing the Scott Cimas and Compliance Calendar sections of
" Comprehensive Reactor Reviews and Safety alternative / Operations thereto, Ivaluation Plan" or some reasonable audit reminders and follow-thru.and making specific assignments for 5.
It is recommended review of the Minutesthat the RSC establish a procedure for actions, such as the August and other important Committee 4, 1988 response of the Committee to the NRC National Violations and Deviation, and to ensure follow-up on questions, documentation, and commitments made. analysis requested,
. .. . +
.-. THE( ,_)
URIVERSITY
" UTAH i
REACTOR SAFETY COMMITTEE AUDIT REPORT A. Sub.iect of Audit: RADIATION SAFETY
- 1. Period reviewed: 7 July 1987 - 30 June 1989 2.. Date performed: 8 August 1989
- 3. Frequency: Semiannual
- 4. Performed by: Keith J. Schlager, RSO
- 5. Target date for next audit: 31 January 1990 B. Performance Specifications and
References:
- 1. TRIGA Technical Specification (TTS) 6.5.5(4) requires the Reactor Safety Committee to audit radiation exposures at the facility and adjacent environs semiannually.
- 2. TTS 3.7(1) requires an environmental radiation monitoring program to measure the integrated radiation exposure in and around the environs of the facility on an annual basis.
- 3. University of Utah, Radiation Safety Manual _, June 1983.
C. Jmolementino Procedures:
- 1. Section 4.4 of the Facility Operations Manual (FOM) addresses operational radiation protection and environmental radiation monitoring.
- 2. University of Utah Radiation Procedures and Records:
RPR 201, Radiation User Personal Data RPR 205, Bioassay Criteria and Procedures RPR 206, Personal Exposure / Incident Investigation Report D. Records sources:
All of the following records are filed at the office of the Radiological Health Department, 100 Orson Spencer Hall:
- 1. All records of personal monitoring for external i
or internal radiation ex retained permanently.posure are filed by individuals and
- 2. Reports of regular contamination and exposure-rate surveys by the Radiological Health Department staff are filed by responsible users (Gary M. Sandquist for the Nuclear Engineering Laboratory) and maintained for a minimum of three (3) years.
Radiologicalllealth Department Sal take City Utah 12 (801) 581 6141
. . . 2.
Radiation Safety, 7/1/88 - 6/30/89 Page 2
- 3. Environmental radiation monitoring results are reported to the Radiation Safety Committee as well as to the Reactor Safety Committee. The permanent record is maintained as an attachment to the minutes of the Radiation Safety Committee, which are filed with the University Archivist.
E. Adeouacy of Procedures and Records:
- 1. Radiation and Contamination Surveys The facility survey records ar e thorough and complete.
During the period covered by this report, substantial ;
improvements in exposure and contamination control have been observed during routine radiation surveys. The receiving end of the pneumatic sample transfer system in the Counting Laboratory (1205C) had previously been an area of chronic contamination. This area has been thoroughly cleaned and improved; the contamination problems have been eliminated. The excellent control of contamination and exposure rctes are reflected in the fact that there have been no personal contamination incidents and no measured radiation doses exceeding 30 millirem during the past year.
- 2. Individual Exposure Monitorino Individual dosimetry records are complete and accurate.
l Personnel with routine or repetitive duties in the l
' Nuclear Engineering Laboratory are issued individual radiation dosimeters. All individuals are issued beta-gamma film badges for whole-body monitoring, two individuals al so have neutron badges for whole-body monitoring, a few individuals also have been issued TLD finger badges for extremity monitoring. The individuals listed below were provided individual dosimeters during all or part of the period covered by this report.
The dosimetry results for June 1989 were not available at the time this report was prepared. For the period 7/1/88 - 5/31/89, 9 individuals were monitored. Of the 9 monitored individuals, 5 received no exposures above the 4 minimum detection individuals received limit (10 mrem measurable / month exposures);of the 20other
- 30 mrem for the ll-month period.
One individual received a neutron badge reading of 50?O mrem for November 1988 that was investigated and determined to be erroneous. An Investigation Report
y .. .,
i j .
Radiation. Safety, 7/1/88 - 6/30/89 Page 3
~dated 26 dosimetry personal January 1989 file. is on file in the individual's
- 3. Environmental Monitorino L
In response to the audit of radiation exposures and monitoring performed in July 1987, six environmental u monitoring stations were established for recording any radiation exposures from airborne radioactivity or from deposition of contamination on surrounding surfaces.
Three of theBuilding, Engineering six stations wherearethe on the roof reactor of Merrill is housed ,
and I three are on adjacent buildings (see attached map),. I One environmental TLD badge is placed at each station during-each calendar quarter. Since a control badge cannot be placed at each location, the reported net ,
readings each would not represent the true net exposures at location. Rather than use the control badge to obtain net are reported. values, the total readings for each'iocation ,
The average value of all exposures l recorded during for each station. normal quarters is used as the background .
(
At the time this report was prepared, ;
the dosimeters from the first quarter of 1988 had been lost and the results for the second 1 not yet been received from the vendor. quarter of 1989 had Consequently, the results five previouslistedquarters.
below are total (not net) readings for #
1 u
Station location Average (Range) I mrem /ouarter .
Merrill Engineering, NW corner Merrill Engineering, NE corner 30 (20-40)
Herrill Engineering, SE corner 36 (30-40) ,
Energy & Mineral Research Center 34 (20-50)
- Building 80 (Campus Planning) 40 (30-40) l Kennecott Research Center 44 (40-50) i 38 (30-50)
F. Recommendations:
The decontamination of laboratory areas and the decommissioning of the AGN-201 reactor have resulted in some radioactive wastes.
as soon as practical. These should be labeled and disposed of radiation protection are highly effective.Otherwise, the current efforts toward l
)
n THEt s UMVERSITY
" UTAH 8 August 1989 T0: Dietrich K. Gehmlich Reactor Administrator FROM: Keith J. Schiager p Radiation Safety Officer M
SUBJECT:
Summary of Radiation Safety and Monitoring at the Nuclear Engineering Laboratory for 1 July 1988 - 30 June 1989.
This summary performed includes a review of area and radiation surveys by the Radiological Health Department, individual radiation monitoring results and environmental radiation monitoring performed during the indicated period.
Radiation and Contamination Surveys During the period covered by this report, improvements in exposure and contamination control substantial have been observed during routine radiation surveys. The receiving end of the (1205C pneumatic sample transfer system in the Counting Laboratory area h)as been thoroughly cleaned and improved;had previously been a the contamination problems have been eliminated. The excellent control of contamination and exposure rate.* are reflected in the fact that there have been no personal contamination incidents and no measured radiation doses exceeding 30 millirem during the past year.
s Radiological Health 1. artment Salt take t U ah 112 (801) 581 4341
6 Radiation Safety, 7/1/88 - 6/30/89 Page 2 Individual Exposure Monitorina Personnel with routine or repetitive duties in the Nuclear Engineering Laboratory are issued individual radiation dosimeters.
All individuals ai Issued beta-gamma film badges for whole-body monitoring, two indiv. duals also have neutron badges for whole-body monitoring, a few individuals also have been issued TLD finger badges for extremity monitoring. The individuals listed below were provided individual dosimeters during all or part of the period covered by this report.
The dosimetry results for June 1989 were not available at the time this report was prepared. For the period 7/1/88 - 5/31/89, 5 of the 9 monitored persons received no exposures above the minimum detection limit (10 arem/ month); the other 4 individuals received measurable exposures of 20 -
30 mrem for the ll-month period.
Monitoring hoe Period Gary Sandquist 7/88-6/89 Kevan Crawford 10/88-6/89 Todd Gansauge 7/88-6/89 John Bennion 7/88-6/89 Melinda Tolle 7/88-12/88 Ning Tang 7/88-6/89 l Cynthia Henderson 7/88-6/89 i David Slaughter 12/88-6/89 Sharon McCormick 1/89-6/89 Raymond Lines 6/89 Brady Hanson 6/89 Byron Hardy 6/89 i George Brewer 6/89 f l Note: One individual received a neutron badge reading of 5030 aren for November 1988 that was investigated and determined to be erroneous. An Investigation Report dated 26 January 1989 is on file in the individuat's personal dosimetry file.
1 i
l lh \
o
' Radiation Safety, 7/1/88 - 6/30/8g Page 3 Environmental Monitorina Six environmental monitoring stations were established in July 1987 fer recording any radiation exposures from airborne radioactivity or from deposition of contamination on surrounding surfaces. ThreeL of the six stations .are on the roof of Merrill
. Engineering Building, where the reactor is housed, and three ars on adjacent buildings (see attached map).
One environmental TLD badge is placed at each station during each calendar quarter.- Since a control badge cannot be placed at
- each location, the reported net readings would not represent the true net exposures at each location. Rather than use the control badge to obtain net values, the total readings for each location are reported. The average value of all exposures recorded during.
normal quarters is used as the background for each station. At the time this report was prepared, the results for.the second quarter of 198g had not yet been received from the vendor; the results listed below are total (not net) readings .for five previous quarters.
Average (Range)
Station location- aren/auarter Merrill Engineering, NW corner 30 (20-40)
Merrill Engineering, NE corner' 36 (30-40)
Merrill Engineering, SE corner 34 (20-50)
Energy & Mineral Research. Center 40 (30-40)
Building 80 (Campus Planning) 44 (40-50)
Kennecott Research Center 38 (30-50)
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+ .- ,
MEMORANDUM To: Reactor Safety Committee (RSC)
Froai:
J. Benniony Date: January 3,1989
Subject:
Status of leakage of Fission Products from Defective TRIGA Fuel Elements On 10/20/87, reactoroperations staff discovered the presence of a trace amount cesium-137 in the ion-exchange resin of the reactor water purification system during routine monitoring of th demineralized tanks. De cesium indicated a possible leakage of fission products from damage corroded TRIGA fuel and motivated a search for its source. Confirmation of the leakage was achieved on or about 11/11/87 with the demonstration that the majority of the activity contained in reactor water samples obtained subsequent to short (i.e., one to two hours in length) reactor operations was due to relatively shon-lived noble gases, e.g., Kr-85m i (t n = 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />), Kr-87 (t in = 76 minutes), and Xe-138 (ti n = 14 minutes).
At that time, a program was devised and approved by the RSC to isolate defective fuel elements by exchanging incore fuel elements with those in storage. Each reactor operation was preced swapping carefully chosen fuel elements in conformance with 'lRIGA Technical Specification
( 4.4(3) which allows short-term opention of the reactor to assist in determining the source of the fission-product leakage. Water samples from the TRIGA tank were obtained following the reactor run and analyzed to ascertain if the source had been removed by the fuel exchange. After I exchanging nearly one half of the fuel elements in the reactor core no evidence of any decrease in the amount of activity released by defective fuel had been observed thereby indicating that mult elements might be involved.
When reactor operations were resumed following facility shutdown by NRC and required surveillance was completed on 11/15/88, a new program was implemented to identify the source of the leakage. The new procedure involved the direct sampling of water convected along each fuel c!cment while operating the reactor at constant power level. The sampling apparatus consisted of an approximately 2-1/2 inch diameter funnel attached to 50 feet of 1/8-inch 1.D. tygon tubing. De tubing extended from the top of the reactor core (location of the sampling funnel) to the counting laboratory where the tubing was wrapped around the intrinsic germanium deactor, connected to a peristaltic pump, and drained into a large bucket. The flow rate of the water was adjusted to about one foot-per-second which allowed for the decay of any nitrogen-16 produced by the (n.p) reaction with oxygen. Convected water from each fueled position of the reactor core was continuously sampled by manually positioning the funnel directly above the trifluted portion of the element during constant 90 kW reactor power output. The funnel was held over each fuel position for at least one minute and the time during which each position was sampled was carefully recorded so that locations of high activity could be precisely located.
He feasibility of the procedure was demonstrated on 11/22/88. It was decided at that time that the Kr-85m gamma photon energy 151 kev would be a good indicator of relative activity since this species had been easily observed in all water samples analyzed since detection of the leakage ne TRACOR Multichannel Analyzer was used in the scaler mode to follow the activity of the 151 kev photon as a function of core position and sampling time. On 11/29/88, the entire core (except 3 positions made inaccessible because of the pneumatic sample transfer terminus) was sampled several regions of high Kr-85m activity were noted. On 12/1/88, the suspected regions were more
RSC Memorandum January 3,1989
, page 2 C*
O elements were exchanged with fuel in storage which good condition. De reactor was again operated on 12/6/88 and after approximat energy production a gross tank water sample was obtained. Although spectrosco water showed appeared that the source had not been completely climinated, the amount to have decreased.
The entire core was again sampled on possibly generating krypton. 12/20/88 and four core positions were identified as condition from storage. On These elements were exchanged with additional fuel in good obtained at about 180 kWh. Analysis of this sample indic contamination. A hardcopy of that water sample is presented at the top of the n s spectrum may be compared to the spectrum of a water sample taken on i1/15/88 du power calibration for nearly identical operating time (see bottom figure). Several featur spectra are to be noted. First, note in the top figure the disappearance of the peaks belo which are identified with the noble Second, note that Ar-41 production (gases and their daughter products (e.g., Cs-138 and see peak at ~1293 kev)is nearly constant for both spectra as the recorded decays are both approximately 3500 for the 30 minute counting inte . ,
next three largest peaks in the top spectrum (excluding the argon and the Si1 kev ann result from the activation of magnesium, manganese small quantities in clean TRIGA water.
The Reactor Supervisor identified the elements removed duiing the sampling surrounding the regulating control rod in 1986. At that time, a severe corrosion pr discovered when the fuel and control rods underwent biennial inspection. Com regulating rod were so badly corroded that the entire assembly had to be removed The magnet casing had failed and allowed wuer to enter into the magnetic wind was identified as the origin of the corrosion. He cormsion had also spread to the a causing several c!cments to freeze to the core grid structure disassembled and the top grid plate machined to provide a greater clearanc fuel inspection noted seveal fuel elements with lengthwise brown streaks. These from the core.were noted during the 1988 fuel inspection. At this time all of the suspect A review of the results obtained from the sampling program has led the operation confidently believe that the source of the leakage has been identified and removed core. Although the six suspected elements have been removed it has not been asce the elements have contributed to the leakage. With removal of the defectivei operations will be performed to prevent any future possiblel l
It should be noted that both the Airborne Particle Monitor (APM) canister (which has been installed and operated with the APM to provide nuc{
information) have been sampling all atmospheric releases throught the exhaust d!
1988. No release above background has been seen with the APM (i.e., gros counting) nor has the charcoal filter showed any activity attributable to fF.sion prod subjected to gamma spectroscopy analysis. His evidence has confirmed previou that the fisson atmosphere from the product facility. activity released into the TRIGA tank water was not esc .
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