ML19347C655
| ML19347C655 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 02/25/1980 |
| From: | Mowry W GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | Goller K Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19347C654 | List: |
| References | |
| 67-1149, NUDOCS 8101050028 | |
| Download: ML19347C655 (5) | |
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ctNERAL AT0*C CoWPANY Po sozom^d in Rep 1v
%3 February 25, 1980 Refer To: 67-1149 EO AWONA MW Mr. Karl R. Coller Ass.stant Director for Operating Reactors Directorate of Licensing U.S. Nuclear Regulatory Co==1ssion Washington, D.C. 20555
Subject:
Facility License R-67; Docket 50-163 Submittal of Annual Report (3 copies)
Dear Mr. Goller:
The following is an annus1 report for the Mark F reactor prepared in the sa=e for=at as that required for the ihrk I (R-38). While the Technical Specifications for Mark F require no annual report, the numbered sections below are the sections referred to, for exa=ple, in Section 9.6e of the Technical Specifications of the R-38 (Docket 50-89) reactor.
Part 1 A brief narrative surrnry of (1) operating experience (including experimen;s perfor=ed), (2) changes in facility design, perfor=ance characteristics and operating procedures related to reactor safety occurring during the report-ing period, and (3) results of surveillance tests and inspections.
1.
The Ibrk F reactor (R-67) was operated during the year to provide steady-state irradiation for numerous experiments. No pulses were performed. The steady-state operations included irradiations of sa=ples of pieces of equipment, production of cold neutrons for neutron radiography, and reactor training exercises.
During this year, significant experiences associated with Mark F operation being reported are:
(a) The LEU and MEU fuel tests that were started in 1977 have continued to be successful. Six such fuci ele =ents occupied the B-ring =ost of the year 1979.
All have survived the tests with no evidence of problems and are still in the core at the start of 1980.
(b) For =ost of 1979, neutron radiography was perfor=ed using a cryogenic source of cold neutrons. This operation accounted for =ost of the reactor usage.
2.
No changes were made to the Facility in 1979.
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Karl R. Coller 67-1149 3.
Surveillance tests and inspections uere perforced as required by Sections 4.0, 5.0, and 6.0 of the Mark 7 Technical Specifications.
Summary results are presented below.
Fuel Surveillance The FLIP fuel was inspected visually and for bending and length changes on 7/23/79.
All elements were satisfactory for continued service.
In addition, the special fuel test pins were inspected frequently. All passed the required tests.
Control Rod Surveillance The visual inspection for deterioration was conducted on July 23, 1979. All control rods were found to be satisfactory. The fueled followers located on some of the control rods were inspected for bend and found to be satisfactory.
Pulsing System Surveillance The mechanical components of the pulsing system (pulse control rod, air piston, lip seal, anvil, ard accumulator) were inspected, cleaned as required, lubricated and reinstalled on January 29, 1979. The mechanical ec=ponents of the pulsing system were inspected again on July 25, 1979.
Reactor Safety Surveillance 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 Temperature and Channel Checks of the fuel-elenent terperature-eessuring channels were perforced. The tests were perforced 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 conitoring channels were calibrated at least conthly during the reporting period. Three of these monthly tests required changes in the calibration of at least one channel by an amount greater than 5%
but less than 15%.
The monitor and survey syste=s were under surveillance during the reporting period. The frequency of calibrations was as indicated below.
Continuous Air Monitor Alarm setpoints were checked daily. The system was calibrated semiannually with three U-235 sources in front of the detector (600 ets/ min, 1500 ets/=in, and 5500 ces/ min).
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Karl R. Goller 67-1149 Eberline Area Monitors Operation is checked daily; response to a source is observed weekly to activate alar =s; calibration is perfor=ed se=1 annually with a 4 mci CS-137 source.
Part 2 A tabulation showing the energy generated by the reactor (in =egawatt-hours).
The energy generated in 1979 by the Mark F was 653.71 =egawatt-hours.
Part 3 The nu=ber of e=ergency shutdowns and inadvertent scra=s, including the ef-fect, if any, on the safe operation of the reactor, and the reasons for any corrective =aintenance required, if any.
No inadvertent scra=s occurred on Mark 7 this year.
Part 4 Discussion of the =ajor =aintenance operations perforced during the period, including the effect (if any) on the safe oper: tion of the reactor, and the reasons for any corrective =aintenance required.
1.
End bearing in pu=p =otor for de=ineralizer systa= failed.
Replaced 3/23/79.
2 Difficulty was e:cperienced with retention of the shroud can on one of the LEU test ele =ents during routine di=ensional =easure=ents.
Re= oval and reinstallation of the shroud apparently resulted in correct operation of the spring detent, 7/19/79 - 7/20/79.
3.
The position indicator potentiometer failed in the regulating rod drive. The drive was replaced by a spare and repairs =ade on the old unit, 7/26/79.
4 The regulating rod drive unit put in service 7/26 was re=oved and overhauled completely, 8/3/79.
5.
The de=ineralizer pu=p failed due to failure of its journal bearing. The bearing was replaced and the punp returned to service the following day, 10/23/79.
6.
The demineralizer pu=p =otor burned out and was replaced, 11/1/79.
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Karl R. Coller 67-1149 Part 5 A suc=ary of each change to the facility or procedures, tests, and experi-ments carried ouc under the conditions of 10 CFR 50.59 is as follows:
(1) No changes to the facility, or procedures and there were no 10 CFR 50.59 tests or experi=ents.
Part 6 A sum =ary of the nature and a=ount of radioactive effluents released or dis-charged to the environs beyond the effective control of the licensee as meas-ured at or prior to the point of such release or discharge.
During the calendar year 1979, 1.233 curies of Argon 41 were released from the facility to the at=osphere.
All liquid and solid wastes are transferred to CAC's SNM-696 licensed Waste Processing Facility for ultimate disposal by a licensed disposal vendor.
Part 7 A description of any environ = ental surveys perfor=ed outside the facility.
There have been no significant changes to the Environ = ental Surveillance Program for 1979.
See reference 38-675 dated February 24, 1976, Facility License R-38; Docket 50-89, Submittal of Annual Report, Attachment I, Cen-eral Ato=ic Conpany Environmental Surveillance Program. The results of this program are submitted in our Semiannual Effluent Report.
Part 8 A sum =ary of radiaticn exposures received by facility personnel and visitors, including the dates and time of significant exposure, and a brief sum =ary of the results of radiation and contamination surveys perfor ed within the facil-ity.
Facility Personnel Whole Body Exuosures for the Year 1979: (REM)
Nu=ber of E=plovees Monitored Hich Low Average 4
1.469 0.050 0.628 Nonfacility GAC Perscnnel Uhole Body Exposures for the Year 1979:
(REM)
Number of E=ployees Monitored Hich Low Average 114 2.417 0.000 0.078
Karl R. Coller 67-1149 Contractor Personnel Whole Body Exposures for the Year 1979:
(RDI)
Number of Persons Monitored High Low Average 45 1.660 0.000 0.070 Visitor Whole Body Exposures for the Year 1979:
(PIM)
Number of Persons Monitored High Low Average 18 0.030 0.000 0.003 Routine Wipe Surveys High Wipe 407 S DPM/100 c=2 Average Wipe
<25 S DPM/100 cm Low Wipc 0 S DPH/100 c=2 Routine Radiation Measurements High 1 Rem /hr at 1 foot Average 20 mrem /hr at contact Low
<0.5 cRem/hr at contact Should you desire additional information concerning the above, please let =e know.
Very truly yours, tw Willian R. Mowry Licensing Ad=inistrator Nuclear Materials Control Division WRM:hes cc:
R. H. Engelken, U.S. NRC, Region V O