ML19276E074
| ML19276E074 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 02/23/1979 |
| From: | Mowry W GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | Goller K NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 38-1033, NUDOCS 7903020287 | |
| Download: ML19276E074 (6) | |
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GENERAL AToMc COMPANY P O. 80X 81608 SAN DIEGO. CAllFORNIA 92138 In Reply (7W "S*"
February 23, 1979 Refer To:
38-1033 Mr. Karl R. Goller Assistant Director for Operating Reaccors Directorate of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Facility License R-38; Docket 50-89 Submittal of Annual Report (3 cent-s)
Dear Mr. Goller:
The following is a routine annual report required by the applicable Technical Specifications. The present report covers the operation for the year 1978.
The numbered sections below are those referred to in Section 9.6e.
Part 1 A brief narrative summary of (1) operating experience (including experiments performed), (2) changes in facility design, performance, characteristics and operating procedures related to reactor safety occurring during the reporting period, and (3) results of surveillance tests and inspections.
(1) The Mark I reactor was operated during the year to provide 25 pulses and steady-state irradiations for nunerous experiments. The operations included: activation analysis, uranium analysis using delayed neutron activation analysis (DNAA), neutron radiography, King furnace high-temperature studies of reactor fuel, numerous irradiations of samples or pieces of equipment, and training exercise for operator trainees.
(2) No changes in facility design occurred in this year.
(3) The surveillance tests and inspections were performed as required by Sections 3.0, 4.0, and 5.0 of the Technical Specifications.
Some re-sults are presented below.
Fuel Surveillance The fuel was inspected visually and for bending and length changes on December 15, 1978.
One element was found to have stretched dur-ing the last year to a length that exceeds the limit in the Techni-cal Specifications.
It has been permanently removed from further reactor service.
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Karl R. Goller 38-1033 Control Rod Surveillance The visual inspection for deterioration was performed on December 15, 18, 1978. All rods were found to be in satisfactory condition.
Pulsing System Surveillance The mechanical components of the pulsing system (pulse control rod, air piston, lip seal, anvil, and accumulator) were inspected, cleaned as required, lubricated, and reassembled on June 26 and December 15, 1973.
Reactor Safety Systems As specified in the Technical Specifications, Channel Tests of the reactor safety system channels, Channel Calibrations of the Power Level monitoring channels, Calibration of the Tenperature measuring channels, Channel Checks of the power-level measuring channels, and Channel Checks of the fuel-element temperature measuring channels were perfo rmed. The tests were performed at least as often as required, and the results were satisfactory.
In no case was a required safety channel scram found to be operating outside the specified safety limits.
The reactor power-level monitoring channels were calibrated at least monthly during the reporting period, the most recent on December 18, 1978.
Four of these monthly tests required changes in the calibration of at least one channel by an amount greater than 5% but less than 10%.
The monitor and survey systems were under surveillance during the report-ing period. The frequency of calibrations was as indicated below.
Continuous Air Monitor Alarm setpoints were checked daily. The system was calibrated, semi-annually with three U-235 sources in front of detector (600 cts / min, 1500 cts / min, and 5500 cts / min).
Eberline Area Monitors Operation is checked daily; response to a source is observed weekly to activate alarms; calibration is performed semiannually with a 4 mci Cs-137 source.
Part 2 A tabulation showing the energy generated by the reactor (in megawatt-hours).
The energy generated in 1978 by the Mark 1 was 49,709,54 kilowatt-hours (49. 71 megawatt-hours).
Karl R. Goller 38-1033 Part 3 The number of emergency shutdowns and inadvertent scrams, including the effect, if any, on the safe operation of the reactor, and the reasons for any correc-tive maintenance required, if any.
A total of seven inadvertent scrams occurred in 1978 during an estimated 1000 separate startups and operations. A list of the scrams according to cause, date, and corrective maintenance (if needed) follows.
It may be noted that none of the seven scrams occurred primarily as a reactor oper-ator error.
(1) An external scram occurred due to a noise spike into the auxiliary Keithley channel (2/8/78).
(2) An error in setup by the King furnace operator caused an external scram fron the voltage scram circuit (2/13/78).
(3) An external scram was caused uhen a broken helium supply line caused an underpressure trip in the King furnace No. 2.
The protective cir-cuits performed as intended as a result of the loss of helium pressure.
The reactor core was never in danger (5/16/78).
(4) A scram was caused by a brief power outage at the Facility (8/29/78).
(5) The helium supply bottle for the King furnace No. 4 emptied during the run, thus reducing the required overpressure. This caused a low-pressure scram as required by the Specifications. No damage to any component or the reactor was expected and none occurred (9/21/78).
(6) While performing a delayed neutron assay of a fuel sample with a low reactor power (< 3 kW), the rabbit containing the sample stuck in the reactor core because the air solenoid jacmed. The operator scrarned the reactor to prevent excessive activitation of the sample. No radi-ation problems resulted (9/22/78).
(7) An external scram occurred during a King furnace run when low helium pressure caused a low-pressure scram (10/1/78).
Part 4 Discussion of the major mainteI ance operations performed during the period, including the effects, if any, on the safe operation of the reactor, and the reasons for any corrective maintenance required.
(1) The power switch for the Linear and Log Recorder was moved from its regular exposed location to a position inside the recorder cabinet to prevent an inadvertent recorder shutoff which, if it occurred during a run, would leave the operator without an indication from the Linear and Log channels (1/19/78).
Karl R. Coller 38-1033 (2) The Mark I ventilation fan pulley was changed for one of larger diam-eter to provide greater air flow (2/21/78).
(3) The RM-14 water activity monitor developed a problem in which no audible or visual indication was given. The problem was found to be an open resistor in the high-voltage power supply and a short to ground in the high-voltage oscillator circuit. The unit was recalibrated. A temporary RM-14 was installed as a replacement during the repair (2/10/78).
(4) The Shim Rod would not drive out of the core. The trouble was in the magnet up-limit switch which was intermittent (2/10/78).
(5) During the reactor console semiannual calibration, the following cir-cuits required repairs before necessary calibrations could be achieved:
(a) The NV circuit needed a new resistor to replace one that changed value through age; (b) Another resistor was changed, this one in the Mode Switch.
This was a 5.5 megohm resistor chunged to a 6.5 megohm (4/24/78).
(6) The Reg Rod motor drive failed when a capacitor shorted and a circuit-limiting resistor opened in the motor circuit (8/15/78).
(7) A rabbit sample failed to return from the reactor when an air solenoid valve stuck. The trouble was traced to a sticking Teflon plunger.
Sub-sequent machining of the plunger corrected the problem (9/22/78).
(8) At the time of the reactor shutdown, the reactor console power switch stuck in the Off position (i.e., in a Doin position). This prevented turning the reactor On une next day. The problem was dirt which wedged around the plactic switch button. Preventive maintenance and cleaning were p_rformed on this switch as well as on the rest of the control switches on the rod control panel (11/20/78).
(9) The semiannual and annual checklists were completed satisfactorily ex-cept for one fuel element that was found in December 1978 to have stretched beyond the 0.5-in Technical Specifications limits. This element (#3543) was permanently removed from further service and will eventually be re-moved from the Facility.
Part 5 A summary of each change to the facility or procedures, tests, and experiments carried out under the conditions of Section 50.59 of 10 CFR 50.
There were no 50.59 changes made to the facility.
Karl R. Goller 38-1033 Changes to the operating procedures are as follows:
(1) A change to the Operating Procedures provides for a " duty senior re-actor operator" to be available by phone if operations are conducted by a reactor operator with no senior operator in the Facility (1/16/78).
(2) The condicions for performing a calorimetric power calibration were clarified and the power level at which the calibration begins was changed to correctly state about 200 kW (3/15/78).
(3) The chain of responsibility from the TRIGA Facility to the GAC vice president in charge was clarified.
The major effect of this is the identification of personnel on the Emergency Notification List (3/17/78).
No experiments or tests were carried out under 10CFR50.59 this year.
Part 6 A summary of the nature and anount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee as measured at or prior to the point of such release or discharge.
During the calendar year 1978, 0.093 curies of Argon 41 were released from the facility to the atmosphere.
All liquid and solid wastes are transferred to GAC's SNM-696 licensed Waste Processing Facility for ultimate disposal by a licensed disposal vendor.
Part 7 A description of any environmental surveys performed outside the facility.
There have been no significant changes to the Environmental Surveillance Program for 1978.
See reference 38-675 dated February 24, 1976, Facility License R-38; Docket 50-89, Submittal of Annual Report, Attacirment I, General Atomic Company Environnental Surveillance Program. The results of this program are submitted in our Semiannual Effluent Report.
Part 8 A summary of radiation exposures received by facility personnel and visitors, including the dates and time of significant exposure, and a brief summary of the results of radiation and contamination surveys perforned within the facility.
Karl R. Goller 38-1033 Facility Personnel Whole Body Exposures for the Year 1978:
(REM)
Number of Employees Monitored High Low Average 4
1.506 0.160 0.737 Nonfacility CAC Personnel Whole Body Exposures for the Year 1978:
(REM)
Number of Employees Monitored High Low Average 171 0.260 0.030 0.011 Contractor Personnel Whole Body Exposures for the Year 1978:
(REM)
Number of Persons Monitored Hich Low Average 156 3.020 0.020 0.069 Visitor Whole Body Exposures for the Year 1978:
(REM)
Number of Persons Monitored Average 297 0.000 Routine Wipe Surveys 2
High Wipe 609 6 DPM/100 cm Average Wipe 11 S DPM/100 cm2 Low Wipe
<1 S DPM/100 cm Routine Radiation Measurements High 9.5 Rem /hr at 1 foot (irradiated fuel element)
Average 100 mrem /hr at ~ 2 inches Low
<0.lmRem/hr at 2 inches Should you desire additional information concerning the above, please let me know.
Very truly yours, f
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William R. Mowry Licensing Administrator Nuclear Materials Control Division URM:hes cc:
R. H. Engelken, U.S. NRC, Region V