ML20149N118
| ML20149N118 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos File:GEH Hitachi icon.png |
| Issue date: | 12/31/1987 |
| From: | Cunningham G, Titus G GENERAL ELECTRIC CO. |
| To: | NRC |
| References | |
| NUDOCS 8803010294 | |
| Download: ML20149N118 (6) | |
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l GENERAL ELECTRIC TEST REACTOR (DEACTIVATED) b l
ANNUAL REPORT NO. 29 l i
LICENSE TR-1 !
DOCKET 50-70 9
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NUCLEAR OPERATIONS e GENERAL ELECTRIC COMPANY f VALLECITOS NUCLEAR CENTER, PLEASANTON, CALIFORNIA 94566 j A$2Cl
- 88' A88 D Has!a70 /
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CENERAL ELECTRIC TEST REACTOR
, (DEACTIVATED)
ANNUAL REPORT No. 29 l
4 The General Electric Company has maintained the General Electric Test Reactor (CETR) in a deactivated status under the authority of Amendment No. 14 to License TR 1, Docket 50 70, issued February 5,1986. This annual report summarizes the status of the facility for the period January 1,1987, to December 31, 1987, as required by Technical Specification 6.6.1 to License TR-1.
I.
SUMMARY
The facility remains in essentially the same condition described in Annual Report No. 28. Entry into the reactor building was made for routine radiation surveys and a generci check of conditions throughout the building.
II. STATUS A. Maintenance There were no major preventive or corrective maintenance activities having safety significance performed during 1987.
B. Changes The following changes were authorized by the Facility Manager pursuant to 10CFR50.59(a) and completed in 1987,
- 1. Cooling Tower Survey
Description:
A radiation / contamination survey of the GETR cooling tower was performed by outside contractor personnel.
Safety Analysis: The levels of radioactivity in the tower are very low and present no hazard.
- 2. Reactor Buildinc Repairs Descrintion: The asphaltic / cork exterior building coating had loosened in places. Those areas were scraped and sprayed with a fibrated asphaltic coating.
Safety Analysis: Levele of radioactive material encountered were very low and presented no hazard, j l
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, CETR Annutl R2 port No. 29 B. Changes (Corcinued)
- 3. Pipine Rearrancement De s c r in t ion '.- The reactor building surp pump effluent line was rerouted from Tank 103 to Tank 115. Tank 115 is an above-ground tank as opposed to Tank 103 which is below ground. The drain lines from the Building 200 sinks and showers that drained to Tank 103 were isolated from the tank by a locked valve, as they will not gravity feed to Tank 115. These facilities were deactivated by shutting off the potable water and installing covers over the drain openings.
Safety Analysis: The above ground tank is easier to monitor for any leakage. The sink and shower are no longer used.
- 4. Sampling of Cooline Tower Pipes Descriotion: Two 2-inch diameter specimens were removed from the cooling tower piping for radiological analysis.
Safety Analysis: The level of radioactivity in the pipes is small.
The holes in the pipes were sealed with aluminum sheeting and RTV.
- 5. Stack Particulate Monitor Descriotion: The existing GETR stack sampling system cannot provide the rample flow necessary for isokinetic sampling. An analysis was performed to establish the sampling error caused by anisokinetic flow in the GETR stack sampling system.
Safety Analysis: Establishment of the correction factor assures proper calculation of stack sample results.
- 6. CETR Barrel Storage Area Draggiotion: A six foot-high chain link fence was constructed to include the barrel storage area and Tank 115 within the GETR Tank Farm.
Safety Analysis: The area was previously delineated with chain and stanchions. The fence provides superior access control.
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GETR Annucl Rsport No. 29 III. RADIATION LEVELS AND SAMPLE RESULTS AT ON AND OFF-SITE MONITORING STATIONS The data below are from sample and dosimeter results accumulated during 1987.
Except for the GETR stack data, these data are for the entire VNC site and include the effects of operations other than the GETR.
A. GETR Stack Total airborne releases (stack emissions) for 1987 are as follows.
Alpha Particulate, < 0.146 pCi (predominantly radon thoron daughter products)
Beta-Gam:na Particulate, < 2.02 pCi B. Air Menitors (Yearly average of a:1 meteoro6gicC =tations.)
Four environmental air monitoring stations are positione>. approximately 90 degrees apart around the operating facilities of Ge site. Each station is equipped with a membrane filter which is changed weekly and analyzed for gross alpha and gross beta-gamma.
Alpha Concentration:
Maximum < 4.5 x 10'1 pCi/cc (predominantly radon thoron Average < 2.93 x 10' pCi/cc Beta Concentration:
Maximum < 8.1 < 10 4 pCi/cc Average < 2.99 x 10 pCi/cc C. Gamma Radiation The yearly dose results for the year 1987 as determined from evaluation of site perimeter TLD environmental monitoring dosimeters showed readings within background. ;
D. Veretation No alpha, beta or gamma activity attributable to activities at the GETR facility was found on or in vegetation in the vicinity of the site.
E. Off-Site l Samples taken off the site indicate normal background for the area.
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. GETR Annual R:; port No. 29
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IV. CCNCLUSION The conditions at the GETR reflect a year of safe shutdown conditions.
GENERAL ELECTRIC COMPANY Irradiation Processing
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By:
4 W. Titus, Manager Reactor Operations 6 Support Services 4
GENERAL $ ELECTRIC NUCLEAR ENERGY SUSINESS OPERATONS GENEPAL ELECT 10C CCMPANY e VALLECTOS NUCLEAR CENTER
- PLEASANTON, CADFORNIA 94566 '
February 24, 1988 .
P U. S. Nuclear Regulatory Commission i Washington, D.C. 20555 Attention: Document Control Desk
Reference:
License TR-1, Docket 50-70 .
Gentlement Enclosed are three signed copies of Annual Report No. 29 for the General Electric Test Reactor.
Sincerely, Yb G. E. Cunningham Senior Licensing Engineer (415) 862-4330
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Enclosures b
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