ML20211Q512
| ML20211Q512 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos Nuclear Center |
| Issue date: | 12/31/1986 |
| From: | Cunningham G GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 27, NUDOCS 8703030113 | |
| Download: ML20211Q512 (7) | |
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i GENERAL ELECTRIC NUCLEAR TEST REACTOR ANNUAL REPORT NO. 27 LICENSE R-33 DOCKET 50-73
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NUCLEAR SYSTEM 5 TECHNOLOGIES OPERATION e GENERAL ELECTRIC COMPANY VALLECITOS NUCLEAR CENTER, PLEASANTON, CALIFORNIA 94566 nh
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t GENERAL ELECTRIC NUCLEAR TEST REACTOR j.
ANNUAL REPORT NO. 27 J
I.
INTRODUCTION I
This report summarizes the operation, changes, tests, experiments, and maj or maintenance at the Nuclear Test Reactor (NTR) which were authorized pursuant to i
License R-33 and 10CFR50, Section 50.59, for the period January 1, 1986,
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through December 31, 1986.
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II.
CENERAL A.
The reactor was operated at or above critical for 739.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Four-hundred-and-eight startups were made.
Two scrams occurred during this report period. Total plant operation equaled 2.876 MW days in 1986.
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B.
The average radiation exposure to facility personnel was 2.92 Rem.
C.
There were no occurrences durir.g 1986 that required notification of the NRC.
III.
ORGANIZATION There were no organizational changes in 1986.
IV.
CHANGES, TESTS, AND EXPERIMENTS APPROVED BY THE FACILITY MANAGER A.
Changes l
Pursuant to 10CFR50.59(a), the Facility Manager authorized the following i
changes in 1986, i
1.
Continuous Air Monitor (CAM) l t
Descrintion: The instrumentation and recorder in the reactor cell CAM system were replaced, i
Safety Analysis: The log count rate meter was calibrated, the capability of the recorder to follow the instrument verified, and the
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detection efficiency calculated prior to use.
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1 NTR Annual Raport No. 27 A.
Chances (Continued) 2.
Remote Shutter Timers
==
Description:==
Remote timers for the south cell and north neutron beam shutters were installed in parallel with existing timers located at the reactor control console.
Safety Analysis: The original safety interlocks and functions were t.ot changed.
3.
Pico H.V. Meter Relavs Descrintion:
External meter relays in a redundant trip circuit with internal loss of H.V. trips from the picoammeters (linear power level channel) were removed. The meters remain in service as voltage indicators.
Safety Analysis: An unneeded redundant relay was bypassed. The undervoltage scram remains actuated by the picoammeter internal relay.
4.
Primary Flow Transmitter
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Description:==
The differential pressure transmitter and relay used to measure primary water flow and provide loss of flow scram protection were replaced with a new transmitter and relay.
Sa fety Analysis:
The new transmitter is better than the old unit.
It does not use vacuum tubes, and the accuracy is i0.25% compared to 0.5% for the replaced unit.
The new scram relay will also perform as well as or better than the old unit.
5.
Primary Vent Valve
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Description:==
A 1/4-inch manual valve was installed in parallel with the solenoid operated valve on the primary coolant vent system. This valve will permit venting of the primary system should the solenoid valve fail in the closed position, i
Safety Analysis:
Failure of the valve or valve leakage has no j
significant safety consequences.
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e NTR Annuc1 R2 port No. 27 B.
Tests Pursuant to 10CFR50.59(a), there were no special testa perforted durirg 1986 which required the approval of the Facility Mana.',e r.
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C.
Experiments There werc 790. individual experiments reviewed, approved, sad perforced in 1986. Three experiment type approvals ware reviewed and approved.
Two were for irradiations'and one for B-10 chamber calibrations.
These are discussed belou.
1.
Iodine Irradiations
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Description:==
Approval was given to perform irradiations of encapsulated iodine samples containing less than a picocurie of I-129.
Safety Annivsis: The irradiations were pe'rformed using existing s.
tools. The total dose to the irradiated capsules was calculated.
Analysis of the amounts and types of radioactive isotopes formed during irradiation shows an insignificant potential radiological hazard.
2.
B-10 Chamber Test
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Description:==
A B-10 lined proportional counter was used to test a preamplifier and source range monitor.
S a fe ty Analysis: The only potential hazard of this test was low-level radiation from the irradiated counter. Reactor operators manipulated the B-10 chamber while customer personnel did the instrument testing remotely out of the radiation area.
3.
UTR Irradiation of Na-23 Descrintion:
Sodium salt in the form of NANO (double polyethylene 3
encapsulation) was irradiated to produce Na-24 for use in the calibration of an intrinsic germanium high resolution gamma detection system at another VNC facility.
Safety Analysis:
Irradiation was performed using existing tools and procedures.
Polyethylene is unaffected by irradiation at the low exposure experienced by these irradiations.
The activity produced was approximately 3 mC1.
V.
MAJOR PREVENTIVE OR CORRECTIVE MAINTENANCE There were no major preventive or corrective maintenance items performed during 1986.
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NTR Annual Report No. 27 VI.
UNSCHEDULED SHUTDOWNS Two' scrams occurred during 1986.
One scram was due to an operator picoammeter (linear power level channel) range change switching error during sample change for a' reactivity measurement test.
The second was due to a spurious trip on one p$aoammeter channel and a simultaneous trip during range change switching on an'ther chanael.
o VII.
RADIATION LEVELS AND SAMPLE RESULTS i
AT ON-AND OFF-SITE MONITORING STATIONS i'
The data below are from sample and dosimeter results accumulated during 1986.
Exk;ept for the NTR stack data, these data are for the entire VNC site and include the effects of operations other than the NTR.
A, NTR Stack Total airborne releases (stack emissions) for 1986 are as follows.
Alpha Particulate
< 0.0717 pCi (predominantly radon-thoron
- N Beta-Gamma Particulate 0.741 pCi Iodine-131
<18.9 pCi Noble Cases 1.404 x 102 Ci Noble gas activities recorded from the NTR stack integrate background readings with the actual releases which may account for 40 to 50% of the activity r.eleased.
B.
Air Monitors (Yearly average of all meteorological stations.)
Four environmental air monitoring stations are positioned approximately 90 degrees apart around the operating facilities of the site.
Each station is equipped with a membr.ane filter which is changed weekly and analyzed for gross alpha and gross beta-gamma.
Alpha Concentration:
-15 Maximum
< 4.9 x 10 pCi/cc (predominantly radon-thoron
-15 Average
< 3.48 x 10 pCi/cc l
Beta Concentration:
Maximum
< 1.3 x 10'I pci/cc
-14 Average
< 3.9 x 10 pCi/cc 1
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NTR Annual Report No. 27 C.
Gamma Radiation The yearly dose results for the year 1986 as determined from evaluation of site perimeter TLD environmental monitoring dosimeters showed normal background.
D.
Venetation No alpha, beta or gamma activity attributable to activities at the NTR facility was found on or in vegecation in the vicinity of the site.
E.
Water 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.
F.
Off-Site i
Samples taken off the site indicate normal background for the area.
VIII.
RADIATION EXPOSURE The highest annual exposure to NTR Operations personnel was 3,230 mrem, and the lowest was 2,395 mrem. The average exposure was 2,920 mrem per person.
There was no significant exposure to outside (non-operations) personnel.
IX.
CONCLUSIONS The overall operating experience of the Nuclear Test Reactor reflects another year of safe and efficient operations. There were no unusual occurrences or reportable events. Updated equipment and procedures should provide increased reliability in the ensuing years.
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I GENERAL ELECTRIC COMPANY Irradiation Processing Operation By m
D. R. Smith, ManageY' '
Nuclear Test Reactor i
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l GENERAL $ ELECTRIC NUCLEAR ENERGY BUSINESS OPERATIONS i
GENERAL ELECTRIC COMPANY e VALLECTOS NUCLEAR CENTER e PLEASANTON, CAllFORNIA 94566 i
February 23, 1987 i
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U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Document Control Desk
Reference:
License R-33, Docket 50- 73 Gentlemen:
t Enclosed are three signed copies of Annual Report No. 27 for the General Electric Nuclear Test Reactor.
Sincerely, j
7 M[h G.
E. Cunningham Senior Licensing Engineer l
(415) 862-4330
/ca Enclosurec I
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