ML20087L425
| ML20087L425 | |
| Person / Time | |
|---|---|
| Site: | 05000054 |
| Issue date: | 12/31/1983 |
| From: | Strack R UNION CARBIDE CORP. |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8403270198 | |
| Download: ML20087L425 (7) | |
Text
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.s ANNUAL REPORT FOR 1983 FOR THE UNION CARBIDE NUCLEAR REACTOR (UCNR)
DOCKET 50-54, LICENSE R-81 A.
FACILITY MODIFICATIONS AND LICENSE CHANGES 1.
One silver indium cadmium control rod was replaced.
Installa-tion of this rod completes the transition to new control rods incorporating a thicker tin-nickel surface plating and a l
strengthened. rod to piston connection.
2.
The 6 inch line between the primary system and the 100,000 gallon storage tank was replaced.
3 The Physical Security Plan entitled " Physical Security Plan for the Union Carbide Corporation Facility at Tuxedo, New York" was approved by the NRC and incorporated into the R-81 License (Amendment 20).
4.
The R-81. License was amended (Amendment 19) to allow reactor startup with two normal power level channels.
B.
PROCEDURES MANUAL The following is a listing of the major changes to the Facilities Procedures Manual.
DS-02 Control and Safety Setpoints - Data changed to show period scram alarm to be audible as well as visual.
RM-03 Reactor Start Up - Required sta'rtup channels changed to reflect Tech Specs Amendment requi ring only two normal power level channels.
RM-04 Reactor Operation - New procedure added for single pull FPM stringer target transfers.
Reactor Components - New Procedure added for use of external rod RM-09 magnet power supply designed for reactor maintenance during shutdown periods.
RM-12 Tl Sump - New Procedure describing Bldg. 2 ground water coIIec-tion system and requi red responses to alarms.
Reactor Console Checklist - Additional channel checks included RS-01 in checklist.
. Electronic Equipment Test List - Additional startup channel i
RS-03 checks added and readability improved.
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9-PROCEDURES MANUAL (CONTINUED)
Reactivity and Core Checklist - Changed to reflect rearranged
- RS-04 sample irradiatico positions.
Reactor Restart Checklist - Modified to include required RS-06 monthly channel checks.
Daily Checklist - Contaminated waste water storage tank level RS-11 check added.
RS-14 Power Data Sheet - Log N Period, Count rate channel and core exit temperature checks -added.
Charcoal Filter Efficiency Checks - Procedure changed to RS-31 include more detail.
Control Rod Calibration - Rod drop calibration modified to allow RS-33 calibrations regardless of previous reactor operating history.
Fission Chamber Calibration - Modified to include calibration RS-37 requirements on spare fission chambers.
Flow Meter Calibration - Frequency of test included on RS-39 calibration sheet.
.RS-44' Rod Scram Time Measurements - Maximum magnet release time added and definition of scram time clarified.
Bridge Excursion monitor calibration - Procedure modi fied to RS-47
.a110w calibration with a new type NBS radiation source or its equivalent.
RS-48 Tl Sump Check - New procedure for testing Bldg. 2 ground water collection alarm system.
Evacuation Horn Test - New Procedure for functional testing of RS-49 Bldg. 1 and BIdg. 2 evacuation horns.
4 General - Additions and changes to data on emergency roster EP-01 telephone listing.
Access Control to Buildings 1 & 2 - Additions and changes in EP-14 individuals authcrized access to " controlled access area".
, C.
ORGANIZATIONAL CHANGES The following is the Union Carbide Corporation Reactor Administra-tion Organization:
Business Manager Technical Radiochemi cals Consultant J.J. McGove rn K.D. George I
i Nuclear 5afeguards Manager Health, Safety Mana ge r Nuclear Operations Committee
& Envi ronmental Affai rs C.J. Konne rth W.G.
Ruzicka C.J. Konnerth. Chm. t l
I Reactor Supervisor Facility Engineer Project Engineer H.P. Supervisor H.C. Hart J.A.
Franzen L.C. Thelin R.A. Strack Chief Reactor Operator S.E. Lupinskt f
D.
SUMMARY
OF UNSCHEDULED SHUTDOWNS The following Is a IIsting of unscheduled shutdowns occurring during 1983.
Type of Shutdown Numbe r Cause Power Outage 14 Commercial Power Failure False Signal 8
Log N 2
Safety Ampli fier 1
Simultaneous Manual Scram & Pump Failure Scram 3
Momentary Loss of Magnet Current Equipment Failure 7-Rod Magnet Failure Causing Automatic 4
Loss of Magnet Current Shutdown i
UI C Failure 2
Safety Amplifier o
-4
SUMMARY
OF UNSCHEDULED SHUTDOWNS- (CONTINUED),
Automatic Safety 2
Core exit flapper opened above allowed Action initiated -
power setpoint causing automatic scram.
- 0perator Error 1
Log N period scram during sample move-ment due to shadowing.
Operator initiated 2
in core FPM target failure
- Manual Shutdown 1
-Console relay shorted from spilled liquid.
1 Received Area radiation and stack alarms.
1 Chemical reaction in stored peroxide creating steam in pump room.
1 Loss of building high pressure air.
I Loss of area radiation alarm system power supply.
I Replacement of noisy pump failure relay.
1 Loss of Hot Lab exhaust fan.
E.
POWER GENERATED Total _ power generated in 1983 was 41,011 megawatt hours.
The reactor was operated on a seven day a week schedule with refueling and main-tenance shutdowns about once every one or two weeks.
F.
ROUTINE TESTS CONDUCTED The reactor surveillance program has revealed no significant nor un-expected trends in reactor systems performance during the past year with tests yielding routine results.
G.
FUEL 17 standard and 4 control fuel elements, containing aluminide (U-A1x) fuel matrix manufactured by CERCA (France), were received by Union Carbide Nuclear Reactor 'In 1983. Twenty-four spent fuel elements were shipped to ' Idaho for reprocessing, e
H.
PERSONNEL RADIATION EXPOSURES-Sixteen members of the Reactorg0perations Staff and. two members of the Health' Physics Staff received exposures in excess of 25% of the recommended-Ilmit In 1983. These doses-ranged from 1.26 rem to.3.93
~
irem with the overal1 ~ average for these Individuals being 2.44 rem.
A part' of this exposure was due to maintenance support for Hot Lab-oratory = 0perations which is licensed under New York' State Radicactive
. Materials License -729-0322.
NoLvisitors to the facility received exposures greater than 25% of
- . that permitted.
1.
OFFSITE RELEASES OF RADIATION 1.
Radioactivity released In' Air Effluent from the site.
a.
Nob le ' Gases isotope Quantity Released (Curies)
Kr-83m 327.9 Kr-85m 962.0 Kr 87.4 Kr-88 1246.4
+
-Xe-133m 327.9 Xe-133 10670.6 i
Xe-135m 2186.6 Xe-135 6055.9 Kr 1.3 L
^
' Total Noble Gas Release 21866 Ci l
Average Concentration of Noble Gases in Stack.2.9 x 10-5 uCi/cc b.
lodines l
lsotope Quality Released -(Curies)
I l-125 1.41 Ci 1-131 3.17 Ci i'
L Average Concentration in Stack
(-
I-125 1.90 x 10-9 uCl/cc i
1-131 4.28 x 10-9 uCi/cc E
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p..
2.
Radioactivity released in Liquid Effluent from the site.
Gross Beta Activity 0.0005 C1 (Sr-90 Equivalent)-
.3.
Particulate radioactivity released from the site.
. The average concentration of particulate radioactivity released dur-Ing 1983 was 6.29 x 10-12 uti/cc. This activity consisted of the following approximate isotopic breakdown.
Particulate isotope Percent of Total Activity 136Cs 1.5 103Ru 41.2 137,
8.6 c
95 34.2 Z r.
95 14.5 Nb 4.
Calculated doses to a critical individual in the unrestricted area, From releases of iodine during 1983 a.
Dose via Infant inhalation at Laurel Ridge 0.43 mrem from lodine-131 0.15 mrem from lodine-125 b.
'From releases of noble gas during 1983
-1.00 mrem total body dose at Laurel Ridge which is nearest residential area For all site effluent releases approximately 95% result from Hot Labor-atory operations under NYS License 729-0322.
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Gn Q49 UNION CARBIDE CORPORATION P.O. BOX 324. TUXEDO,NEW YORK 10907 MEDICAL PRODUCTS DIVISION TELEPHONE NUMBEA: (G14) 351 2131 March 20,1984 U. S. Nuclear Regulatory Commission Di rector, Division of. Project and Resident Programs King of Prussia, Pa 19406 Att Mr. Richard W. Starostecki
Subject:
Annual Reporti Docket 50-54 License R-81
Dear Mr. Starosteck!:
The following Annual Operating Summary for Union Carbide's Sterling Forest 3eactor for the year 1983 is herewith submitted.
S i nce re ly,
RAS:ltm Robert A ack Enclosure Reactor Supervisor cc:
U.S. Nuclear Regulatory Commission Director Office of Nuclear Reactor Regulation Division of Licensing l
Washington, D. C.
20555 I
U.S. Nuclear Regulatory Commission Director r
l Office of Inspection F. Enforcement l
.D._.C. 20555 J t
I American Nuclear insurers 270 Farmington Avenue Farmington, Ct 06032 l
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