ML19309C254
| ML19309C254 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos File:GEH Hitachi icon.png |
| Issue date: | 03/05/1980 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19309C246 | List: |
| References | |
| NUDOCS 8004080359 | |
| Download: ML19309C254 (5) | |
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GENERAL ELECTRIC TEST REACTOR ANNUAL REPORT NO. 21 License TR-1 Docket 50-70 l
80040803h
GENERAL ELECTRIC TEST REACTOR ANNUAL REPORT NO. 21 I.
INTRODUCTION This annual report, covering the period January 1,1979 to December 31, 1979 for the General Electric Test Reactor (GETR), is submitted in fulfillment of the requirements of Item 3.D(4) of License TR-1 and 10CFR50.59(b).
II.
OPERATING SUNtARY On October 24, 1977 the General Electric Test Reactor was ordered to remain shut down, following a routine outage, pending further order from the Nuclear Regulatory Commission. The order was based on an interpretation of the geology of the Livermore Valley as shown on the U.S. Geological Survey (USGS) open file report number 77-689 and a preliminary evaluation of evidence of faulting in a trench dug at the Vallecitos Nuclear Center. The reactor was shut down on October 27, 1977 and has remained in this condition through December 31, 1979.
III. STATISTICS 1.
Containment Building Evacuations and Isolations Date Cause Action 6-2-79 Spurious stack gas trip Building isolation, no building evacuation 2.
Personnel (as of December 31, 1979)
Operation Supervisors 4
Licensed Operations Supervisors 4
Shift Engineers O
Licensed Shift Engineers O
Shift Specialists 1
Licensed Shift Specialists 1
Reactor Operators 7
Licensed Reactor Operators 3
Licensed Senior Reactor Operators (includes Supervisors) 10 IV.
REACTOR AND SYSTEMS COMPLIANCE TESTS 1.
On February 2,1979, the data for the annual containment building leak test indicated a leak rate of approximately 3.1% of the actual free volume per twenty-four hour period. Leakage was discovered in the containment ventilation system exhaust duct isolation valves. Necessary adjustments were performed on the valves and a retest of the building resulted in a leak rate of 1.56% of the actual free volume per twenty-four hour period.
Maximum permitted leak rate is 1.71% of the actual free volume per twenty-four hour period.
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2.
The annual containment building leak test for 1980 was completed on December 21, 1979.
the measured leak rate was 1.49% of the actual free volume per twenty-four hour period. The maximum permitted leak rate is 1.71% of the actual free volume per twenty-four hour period.
3.
Performance tests were completed on the anti-siphon valves, the emergency recirculation systems, the vacuum relief system, the experiment exhaust system, the emergency diesel generator, and the poison injection system.
V.
MALFUNCTIObiS OF CONTROL AND SAFETY SYSTEMS The following malfunctions of safety systems occurred during 1979 Required reports were made to the NRC along with an analysis of the event and the correc-tive action performed. The events did not involve a release of radioactivity or exposure to personnel or the general public.
As described in Section IV.1 above, the initial containment building leak rate exceeded allowable limits. Necessary adjustments were completed.
V.
CHANGES AUTHORIZED BY MANAGER, REACTOR IRRADIATIONS Pursuant to 10CFR50.59(a) the Manager, Reactor Irradiations, authorized changes during the report period. These changes were authorized in accorda:Re with APED-5000-A, Paragraph 3.3.1.
The changes completed in 1979 are listed below.
1.
Auxiliary Hoist Overload Switch Installation Description of Change The 1000-lb auxiliary hoist on the polar crane was provided with a load cell to detect overloads and provide an electrical cutout.
Safety Analysis The mounting support was analyzed for strength. The power shut-off and alarm function is not part of the reactor safety circuit.
2.
HE 101 Shielding Description of Change Compact lead shielding was installed around the bottom flange of the primary heat exchanger to provide physical access to the heat exchanger seismic restraints as well as the necessary personnel radiation protection.
Safety Analysis A review of the seismic restraint analyses has shown that the new restraints are adequate to handle the additional mass of the new shielding.
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3 Diesel Fuel Day Tank Level Alarm Description of Change A level alarm was added to the Diesel Fuel Oil Supply System day tank in order to notify the control room operator of an abnormally low level.
Safety Ana'.ysis The 10<el alarm is actually a backup to the once-per-shift level check by the operating crew. If the automatic transfer pump fails to start and the visual check is missed, the low level condition would annunciate in the control room and corrective action could be taken.
4 Removal of Reactor Head Switches Description of Change The reactor head switches were removed because of high radiation exposure required for maintenance.
Safety Analysis Administrative procedures have been in place for several years to adequately prevent inadvertently adding reactivity to the core when the control rods are not seated. These procedures will remain in effect and have been expanded as a result of the head switch removal.
5.
Vacuum Relief System Maintenance Valves Description of Change Valves were added in the containment building vacuum relief system tank to facilitate maintenance and testing. Material specification changes were also made.
Safety Analysis The specifications for the added valves satisfy the original system specifi-cations.
Inadvertent operation of the valves does not interfere with the operability or alarm function of the system. The system was tested at the containment building test pressure following the change.
The material specification changes are compatible with the system and the operating environment, and do not degrade the system.
VII. CHANGE IN ORGANIZATION No changes were made in the structure of the GETR organization.
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VIII. SIGNIFICANT CHANGES IN PROCEDURES During 1979 the Standard Operating Procedures (SOPS) were periodically revised and updated. Two new SOPS were written and 26 changes were made to the SOPS.
In addition 6 new or revised Maintenance Procedures were written and 7 changes made.
II.
RADIATION LEVELS AND SAMPLE RESULTS AT ON-AND OFF-SITE MONITORING STATIONS The data below are from sample and dosimeter results accumulated during 1979 These data are for the entire VNC site and include the effects of operations other than the GETR. The type and locations of the samples are described in APED-5000-A.
1.
Air Monitors (yearly average of all stations)
Alpha Concentration Maximum 4.5 x 10-15 gCi/cc Average 3.52 x 10-15 Ci/cc Beta Concentration Maximum 8.8 x 10-13 uci/cc Average 1.00 x 10-13 Ci/cc 2.
Gamma Radiation. The integrated yearly dose results for the year 1979 as determine? from evaluation site perimeter environmental monitoring dosimeters showed no dosimeter readings in excess of normal dosimeter background (i.e., the background shown on duplicate TLDs stored in non-radiation areas at the VNC and at the facilities of the film dosimeter processor).
3.
Vegetation. No alpha, beta, or gamma activity attributable to the opera-tion of the GETR facility was found on or in vegetation in the vicinity of the site.
4.
Wa ter. There was no release of radioactivity in water or to the ground water greater than those limits specified in 10CFR20, Appendix B, Table II, Column 2.
5.
Off-site. Samples taken within a 2-mile radius of the site indicate normal background for the area.
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CONCLUSION r
i In our opinion, the over-all experience of the GETR reflects a year of safe shutdown conditions. We hope for resumption of operation in 1980.
i GENERAL ELECTRIC COMPANY Irradiation Processsing Operation By D. L. Gil(.iland, Manager Reactor Irradiations p
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