ML20087L425

Annual Rept for 1983

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 l UNION CARBIDE NUCLEAR REACTOR (UCNR)

DOCKET 50-54, LICENSE R-81 l l

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 l 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.

RM-09 Reactor Components - New Procedure added for use of external rod 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.

RS-01 Reactor Console Checklist - Additional channel checks included in checklist.

RS-03 . Electronic Equipment Test List - Additional startup channel i

checks added and readability improved.

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9-PROCEDURES MANUAL (CONTINUED)

- RS-04 Reactivity and Core Checklist - Changed to reflect rearranged sample irradiatico positions. .

RS-06 Reactor Restart Checklist - Modified to include required monthly channel checks.

RS-11 Daily Checklist - Contaminated waste water storage tank level check added.

RS-14 Power Data Sheet - Log N Period, Count rate channel and core exit temperature checks -added.

RS-31 Charcoal Filter Efficiency Checks - Procedure changed to include more detail .

RS-33 Control Rod Calibration - Rod drop calibration modified to allow calibrations regardless of previous reactor operating history.

RS-37 Fission Chamber Calibration - Modified to include calibration requirements on spare fission chambers.

RS-39 Flow Meter Calibration - Frequency of test included on calibration sheet.

.RS-44' Rod Scram Time Measurements - Maximum magnet release time added and definition of scram time clarified.

RS-47 Bridge Excursion monitor calibration - Procedure modi fied to

.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.

RS-49 Evacuation Horn Test - New Procedure for functional testing of 4

Bldg. 1 and BIdg. 2 evacuation horns.

EP-01 General - Additions and changes to data on emergency roster telephone listing.

EP-14 Access Control to Buildings 1 & 2 - Additions and changes in 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 Manager Health, Safety Mana ge r Nuclear 5afeguards Nuclear Operations Committee & Envi ronmental Affai rs C.J . Konnerth . Chm. C.J. Konne rth W.G. Ruzicka t l I Project Engineer H.P. Supervisor Reactor Supervisor Facility Engineer L.C. Thelin H.C. Hart J.A. Franzen 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

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SUMMARY

OF UNSCHEDULED SHUTDOWNS- (CONTINUED) ,

Core exit flapper opened above allowed Automatic Safety 2 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 -Console relay shorted from spilled liquid.

1 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

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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

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' 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 3.17 Ci 1-131 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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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 137c , 8.6 95 Z r.

34.2 95 Nb 14.5

4. Calculated doses to a critical individual in the unrestricted area,

a. From releases of iodine during 1983 -

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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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 r

Director l Office of Inspection F. Enforcement l Washington .D._.C. 20555 J t

I American Nuclear insurers 270 Farmington Avenue Farmington, Ct 06032 l

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