ML20091B995
| ML20091B995 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos Nuclear Center |
| Issue date: | 12/31/1991 |
| From: | Cunningham G, Danni Smith GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9204020227 | |
| Download: ML20091B995 (9) | |
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20555 Attontion:
Document Control Desk Reference License R-33, tocket 50-73 Gentlement Enclosed are three signed copies of Annual Report No. 32 for the General Electric Nuclear Test Reactor.
Sincerely, kb sf A
1 G.- E. Cunningham Senior Licensing Engineer (510) 862-4330.
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,I 9204020227 911231 PDR ADOCK 05000073 R
4 GENERAL ELECTRIC NUCLEAR TEST REACTOR ANNUAL REPORT NO. 32 l
LICENSE R-33 DOCKET 50-73
-GE NUCLEAR ENERGY VALLECITOS NUCLEAR-CENTER PLEASANTON,-CA 94566
4 CENERAL ELECTRIC NUCLEAR TEST REACTOR ANNUAL REPORT NO. 32 I.
INTRODUCTION This report summarizes the operation, changes, tests, experiments, and major maintenance at the Nuclear Test Reactor (NTR) which were authorized pursuant to License R-33 and 10CFR50, Section 50.59, for the period January 1,1991, through December 31, 1991.
II.
GENERAL A.
The reactor was operated at or above critical for 804.46 hours5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br />; 380 startups were made. There were four scrams during this r3 port period.
Total plant operation e-qualed 3.216 M'Jd in 1991.
B.
The average radiation exposure to facility personnel was 1.8 Rem.
C.
There were no occurrences during 1991 that required notification of the h"AC.
D.
There were no notices of violation issued as the result of NRC inspections.
III.
ORCANIZATION There were no organizational changes in 1991.
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NTR Annual Report No. 32 IV.
FACILITY CRANGES, TESTS, EXTERIMENTS AND PROCEDLRE CHANGES APPROVED BY THE FACILITY MANAGER A.
Facility Chances Pursuant to 10CFR50.59(a), the Facility Manager authorized the follo*iing facility changes in 1991.
1.
Motion Detector Circuit Descrirtion:
The control circuit for the reactor control room motion detector was modified s:> that the tamper switches associated with the detector head will activate an alarm in the security building when the bypass switch is in the " BYPASS" position.
Previously, placing the bypass switch in the " BYPASS" position when the room was occupied would additionally bypass the tamper switches.
Safety Analysis: This revision was in cor.formance with the reactor security plan and did increase th(- security provided.
The r ater i
was checked for proper operation after the change.
i 2.
Hirh Ternerature Scram Test Switch
/
Lescription:
Tnis change authorized a relocation of the existing test switch to an area with a lower background radiation.
Safety Analvris: This change in location reduces the radiation exposure for those performing the test.
The switch was tested after the change.
3.
Low Flow Bypass Int e r rup t. ex
==
Description:==
The low flow bypass relay may be reset at low power conditions.
When this occurs, the scram bypass is activated and the low ficw scram can be tested only when the bypass relay is remcved. This change authorized the installation of a momentary contact test switch to allow easy testing of the low flow scram.
Safety Analysis: This switch retains the same scram logic and function.
Failure of the switch would conservatively cause a reactor scram and not prevent one.
The switch was tested after installation.
2
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(
NTR Annual Rep. ort No. 32 B.
.':rtia Pursuant to 10CFR50.59(a), there were no special tests performed during 1991 v1.ich required the approval of the Facility Manager.
C.
Experin>ents Pursuant to 10CFR50.59(a). the Facility Manager authorized the following new experiments in 1991.
1.
Depicted U-238 Irradiation Egirrintion: A previously approved irradiation was authorized to be irradiated in a second irradiation facility.
I Safety Analytis: The reactivity worth of the experiment and the radiological effects resulting from handling and potential accidents were determined to be negligible.
2.
F-Ray of Lithium-Filled Tube Descrintion:
Lithium filled metallic tubes were approved for neutron radiography.
Safetv Analysis:
The lithium tubes were filled in an inert atmosphere and nealed in tubes which were leak tested. Appropriata fire extinguishers were available in the area, the tubes were kept away from water, and the storage area was labeled " Flammable Solid" and " Dangerous When Wet".
3.
Lutetium Oxide Irradiation Descrintion: A 0.3-gram nample of lutetium oxide was approved for irradiation.
Safety Analvcis: The reactivity worth of the sample and potential radiation exposure and radiolog! cal hazacds were all determined to be negligible.
4 Sodium Salt Irradiation Descrintion: This change authorized the irradiation of 0.05 gm of a sodium salt (carbonate, oxalate, acetate and chloride).
Safety Analysi s : The reactivity worth of the experiment and the radiological effects resulting from handling and potential accidents were determined to be negligible.
3
l NTR Annual Report No. 32 C.
Experiments (Continued) 5.
Source Rance Monitor (SRM) Test
==
Description:==
This change authorized the testing of an SRM with 10%
of the U 235 of a previous test.
SafetyAna1Ysis:
The reactivity effect, the radiological effects resulting from handling, and potential accidents were determined to be negligible.
D.
Procedures There were four changes to procedures.
Pursuant to 10CFR50. 59(a), the Facility Manager authorized the following procedure changes in 1991.
1.
ganual Poison Sheet. Modification Descripti2n: This change authorized removing two strips of cadmium (instead of just one) when modifyinc. a Manual Poison Sheet and deleting the suberitical multiplication plots.
Egfety Ansivsis:
Experience has shown that two cadmium strips may s
be removed at one time while maintaining reactor excess reactivity within limits.
The critical position was still predicted and verified prior to startup.
The reactivity change of the Manual Poison Sheet modifications has been well predicted.
2.
Operntfory_Recuest Form (OR FA
==
Description:==
The ORF was replaced by the Engineering Release (ER).
This replacement standardizes the form used by all groups on site,
~
Enferv Analysis The replacement was administrative only. The function, reviews, audits and record retention remain unchanged.
Procedures were revised, 3,
Advanced Nuclear Aonlications Irradiation
==
Description:==
This change authorized the delegation of certifying the contents of routine Departmant of Defense classified irradiations from the group manager to the technicians preparing the samples.
Safetv Analysis:
The certification is unchanged. The sample preparers are fully knowledgeable of sample contents, 4
h.
I,'. '
' INTR' Annual Report No. 32 D.
Procedures- (Continued) 4.-
Ouarterly DositteteIn JF
==
Description:==
This change authorized the use of TLD's instead of filia to monitor beta and gamma exposure for_ personnel issued a quarterly dosimeter. Thie change does not affect reactor operations personne1' who are issued monthly-dositneters.
Safety Analysis: The TLD's provide the equivalent exposure and documentation as the film badges.
V.
MAJOR FREVENTIVE OR CORRECTIVE MAINTENANCE There were no inajor preventive or corrective maintenance activities perfortned in'1991, VI.
UNSCHEDULED SIIUTDOWNS There were four (4) unscheduled shutdowns during this report period. These are cummarized below.
A.
The reactor was manually shut down when one control rod failed to rerpond to switch actuation. The'inotor starter capacitor was determined to have failed.
The capacitor was: replaced-and tested satisfactorily, Lost time was 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 43 minutes.
B.
A reactor scrazn occurred'on twofof-three picoammeter trip'because of a spurious: condition. The instruments were reset and the reactor restarted.
Lost time was 11 minutes.
-C.-
A reactoriseram occurred while.the reactor vns operating for low power testing and-the " Cooling Flow Needed" relay tripped spuriously.
Since the primary pump was secured for the: low power testing, a scram was initiated. Testing-had jrst been completed so no operating time was lost.
D.
A reactor scram occurred when an AC power dip was caused in the incoming utility.line.- Lost time amounted to 18 tainutes.
5
NTE Annual Report No. 32 VII.
RADIA'rION LEVELS AND SAMPLE RESULTS AT ON. AND uFF-SITE MONITORING STATIONS The data below are from samplc and dosimeter results accumulated during 1991.
Except for the NTR stack data, these data are for the entire VNC site and include the effects of operations other than the NTR.
$TR Stnck d
A.
Total airborne releases (stock emissions) for 1991 are as follows, Alpha Particulate, < 0.36 pCi (predominantly radon-thoron daughter products)
Beta Camma Particulate, < 0.99 pCi Iodine 131, 14.1 9C1 Noble Gaces, 1,54 x 102 31 Noble Sas activities recorded from the NTR stack integrate both background readings and the actual releases.
The background readings may account for 40 to 50% of the indicated release, B,
Air Monitors (Yearly average of all meteorological stations.)
Four environmental air monitoring statiens are positioned approximately 90 degrees apart around the operating facilities of the site, Each c
station is equipped with a membrane filter which is changed weekly and analyzed for gross alpha and groas beta gamma.
Alpha Concentration:
Maximum
< l.1 x 10' pCi/cc (predominantly radon thoron Average
< 4.3 x 10'1 pCi/cc Leta Concentration:
<2.2x10}fpCi/cc Maximum Average
< 4.3 x 10 pC1/cc C,
Gammn Padiation The yearly dose results for the year 1991 as determined from evaluation of site perimeter TLD environmental monitoring dosimeters showed acceptable levels.
D.
Vetetation No alpha, beta or gamma activity attributable to activities at the NTR facility was found on or in vegetation in the vicinity of the site.
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[TRAnnualReportNo.32L
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E.-
Water
- There was_no release-of radioactivity in water or_to the ground water
. greater than those limita specified in 10CFR20 Appendix B. Table =II, iColumn 2.
- P.
Q.ff-Site Samples _taken off the_ site indicate normal background for the area.
-VIII.
RADIATION EXPOSURE 4-.
The highest annual dose to NTR Operations personnel was 2 16 Rem, and the
-i Iowest was 1,63 Rem.
The average dose was 1.84 Rem per person.
k IX.
CONCLUSIONS p
'The_overall operating experience _of the Nuclect Test Reactor reflects another
-year'of--safe and efficient operations, There were no reportable events.
GENERAL ELECTRIC COMPANY Irradiation Processing
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By _()
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R. Smith, Manager Nuclear Test' Reactor.
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