ML20205K863
| ML20205K863 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos Nuclear Center |
| Issue date: | 12/31/1985 |
| From: | Cunningham G, Danni Smith GENERAL ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8604020615 | |
| Download: ML20205K863 (9) | |
Text
.
A CENERAL ELECTRIC NUCLEAR TEST REACTOR ANNUAL REFORT NO. 26 LICENSE R-33 DOCKET 50-73 8604020615 851231 gDR ADOCM 05000073 PDR NUCLEAR TECHNOLOGIES & FUEL DIVISION e CENERAL ELECTRIC COMEANY VALLECITOS NUCLEAR CENTER, PLEASANTON, CALIFORNIA 94566 l
T, - '\\ '
1
G GENERAL ELECTRIC NUCLEAR TEST REACTOR ANNUAL REPORT NO. 26 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 1,1985, through December 31, 1985.
II.
CENERAL A.
The reactor was operated at or above critical for 650.05 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. A total of 390 startups was made. No scrams c: curred during this report period.
Total plant operation equalled 2.46 MW days in 1985.
B.
The average radiation exposure to facility personnel was 2.209 Rem.
C.
There were no occurrences during 1985 that required notification of the NRC.
III.
ORGANIZATION In July,1985, the Level 2 management responsibilities were transferred from the Manager, Advanced Nuclear Applications, to the Manager, Engineering and Support. Services.
In December, 1985, the Level 1 and Level 2 management r-aponsibilities.were combined under the Manager, Nuclear Test Reactor.
L. e7 3 management remained unchanged.
s 4
NTR Annual Report No. 26 IV.' CHANCES, TESTS AND EXPERIMENTS APPROVED BY THE FACILITY MANAGER A.
Channes Pursuant to 10CFR50.59(a), the Facility Manager authorized the following changes during 1985.
1.
Manual Poison Sheet (MPS) Shield Plur Locks Descriotion:
Padlocks were removed from the manual poison sheet shield plugs and were replaced with positive full-enclosure latches.
Safety Analysis:
The latches provide an adequate degree of-protection because of strict access control to the reactor cell and because the previously installed restraints on_the MPS's require a special tool and knowledge to remove the MPS's.
2.
Vallecitos Nuclear Center Site Dgscriotion:
Changes to cite facilities including the locations of the fire truck and various administrative offices were authorized.
Safety Analysis:
The changes reflect the updated status of the site buildings and the fact that Lake Lee is ao longer dry.
Failure.of the dam and release of its content would not impact the NTR; therefore, filling the lake does not present an unreviewed safety question. Relocation of personnel and the fire truck has no safety significance to NTR.
3.
Reactor Cell Air Conditioner Descriotion:
The reactor cell air conditioner has not been used since 1976, and it is planned to remove the unit.
Safety Analysis: There is no safety implication in removing the air conditioner.
It has not been in service for nine years and is not needed.
4.
NTR Fuel Descriotion: New values for the amount of fuel per disc and fuel burnup were approved, and the agount of U-235 present was changed to reflect fuel burnup.
Safety Analysis:
The original description in the SAR was confusing.
The new information clarified and updated and has no safety implication.
2-
,z
-NTR Annual Report No. 26 5.
Im N Oneration Descriotion: The maximum set point of the Log N High Power Trip was changed from 138 kW to 150 kW (if used).
Safety Analysis: The Log N power trip no longer is needed as the picommmeters provide the required overpower protection. The Log N high power trip will be retained as a diverse backup to the picommmeters.
The Log N trip was eliminated from the Technical Specifications during license renewal negotiations with the NRC.
6.
_ Reactor Power Descriotion: The maximum high power trip point setcing was changed from 138 kW to 125 kW, and a maximum authorized power of 100 kW was specified.
Safety Analvsis: The NTR license states that "the licensee may operate the reactor at power levels not in excess of 100 kilowatts (thermal)". The maximum high power trip set point specified in the Technical Specifications is 125 kW.
This limit was adopted.
7.
Nucienore Irradiator Descriotion: The Nuclepore irradiator was removed from the NTR facility and shipped off site for disposal.
?
Safety Analysis: The removal of thn experiment equipment was performed in accordance with applicable procedures and standards.
8.
Safety Related Systems - Information Descriotion: The table of reactor safety system instrumentation.
and trip points was updated'to reflect accepted changes negotiated with the NRC during the license renewal process.
I Safety Analysis: 'All changes that were made were reviewed and accepted by the NRC during license renewal. The table was' changed to be consistent with the approved Technical Specifications.
9.
Nuclear Instrument Ranne i
Descriotion: The required operating range upper limit for the picoammeters and the Log N were changed to 125%.
-Safety Analysis: The previously required limit of 150% on the picos is unnecessary. A scram set point of < 125% is ra tired, and so a large part of the meter would not be used.
For th og N,' a high level scram is not required, so the 150% operating _nge limit is not required..
k NTR Annual Report No. 26 10.
Administration Descriotion: This CA involves minor changes that were made in the administrative r3quirements'of the NTR.
The Operations Supervisor position was eliminated, and the need for an SRO to be present during the first startup each day was eliminated. The Unit Manager position-was made optional.
Safety Analysis: There is still one level of management-(see Section III of this report for later information) below the facility manager. This level optionally may be called manager or supervisor. The responsibilities of the supervisor have been reassigned. A senior licensed operator.(SRO) must be readily available on call for consultation in case any unusual circum-stances are encountered. These changes are consistent with the Technical Specifications.
11.
Definitions Descriotion: The definitions of certain words or terms different than in Section 1.4 of the'SAR were approved.
Safety Analysis: The new definitions were approved by the NRC during license renewal and make the definitions listed in the SAR consistent with the definitions in the Technical Specifications.
12.
Safety Rod Timer t
l Descriotion:
The previously portable safety rod timer unit was installed permanently in the console.
Safety Analysis: There are no hazards introduced by this change.
13.
Erg:ess Scram Relav Test Buttons l
Descriotion: Relocation of the process scram test buttons and the complete removal of the experiment scram switches were authorized.
l l
Safety Analysis: This change does not involve an unreviewed safety question. Operational switches were relocated, and unused switches were removed.
14.
Stack LCRM Alarm
==
Description:==
This change provided a lock.in feature requiring manual reset whenever a high stack particulate activity alarm occurs.
(
Safety Analysis: This change will prevent noise spikes from i
causing momentary undetected alarms which may not be traceable.
i 4
"d -
NTR Annual Report No. 26 15.
Primary Vent Valve.
Descrintion: This CA authorized replacement of a manually operated toggle valve on the primary coolant vent system with an electrically operated solenoid. valve.
~Safetv-Analysis: This permits remote operation of the valve, thus reducing operator radiation exposure. The valve will be "normally closed" to prevent inadvertent opening on loss of power.
B.
Tests Pursuant to'10CFR50.59(a), there were no special tests performed-during 1985 which required the' approval'of the facility manager.
'C.
Exneriments
~
There was a total of 725 individual experiments reviewed, approved, and perfora d in 1985.
Two experiment type approvals (ETA's) were reviewed and approved by the
. facility manager during 1985.. They are described below.
1.
ANA Samnle Irradiation Descriotion: The existing experiment type approval was modified to reflect the fact that the Manager, ANA, no longer is the NTR facility manager.
Safety Anrivsis: The non-routine experiment approval form will be modified'to require the signature of the new facility manager.
This change is administrative only.
'2.
Cobalt Pellet Irradiation Descriotion:
Irracliation of small quantities of cobalt was evaluated and approved by the facility manager.
Safety Analysis: Dose rates, potential for contamination release, heat generation, etc., were analyzed and found to be acceptable.
The irradiation of cobalt pellets was the only new experiment performed during 1985.
5
E.
9 NTR Annual Report No. 26 V.
MAJOR PREVENTIVE OR CORRECTIVE MAINTENANCE There were no problems during 1985 that required major maintenance.
VI.
UNSCHEDULED SHUTDOWNS There were no scrams or unscheduled shutdowns in 1985.
VII. RADIATION LEVELS AND SAMPLE RESULTS AT ON-AND OFF-SITE MONITORING STATIONS The data below are from sample and dosimeter results accumulated during 1985.
Except for the NTR stack data, these data are for the entire VNC site and include the effects of operations other than the NTR.
1.
NTR Stack. Total airborne releases (stack emissions) for 1985 are as follows.
Alpha Particulate
< 0.1546 pCi (predominantly radon thoron daughter products)
Beta-Camma Particulate 0.881 pCi Iodine-131
<25.92 pCi Noble Gases 1.535 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 released.
2.
Air Monitors (yearly average of all meteorological stations).
Four environmental air monitoring stations are positioned approximately 90*
apart around the operating facilities of the site.
Each station is equipped with a membrane filt'r which is changed weekly and analyzed for i
gross alpha and gross beta-gamma.
Alpha Concentration:
I Maximum
< 5.90 x 10'15 pCi/cc (predominantly radon-thoron i
Average
< 3.05 x 10'15 pCi/cc Beta Concentration:
Maximum
< 3.20 x 10 is pCi/cc Average
< 4.70 x 10'1* pCi/cc i
! t
a.
.NTR Annual Report No. 26 3.
Gamma Radiation. The yearly dose results for the year 1985 as determined from evaluation of. site perimeter TLD environmental monitoring dosimeters showed readings within normal background.
4.
Vegetation. 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.
5.
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.
6.
Off-site. Samples taken off the site indicate normal background for the area.
VIII. RADIATION EXPOSURE The highest annual exposure to NTR Operations personnel.was 2,660 mrem, and the lowest was 1,600 rRes. The average exposure was 2,209 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 ene ensuing years.
GENERAL ELECTRIC COMPANY Irradiation Processing Operation By
\\'
m bcA h
m D. R. Smith, dhnager Nuclear Test Reactor -
g-t?
d
. GENERAL $ ELECTRIC NUCLEAR ENERGY BUSINESS OPERATIONS GENERAL ELECTRIC COMPANY e VALLECTOS NUCLEAR CENTER e PLEASANTON, CAUFOD.NIA 94566 March 26, 1986 Dr. H. R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Reference:
License R-33, Docket 50-73
Dear Dr. Denton:
_ Enclosed are three signed and forty conformed copies of Annual Report No. 26 for the General Electric Nuclear Test Reactor.
Sincerely, l-C. E. Cunningham Senior Licensing Engineer (415) 862-4330
/ca Enclosures p
.-