ML20072P364

Annual Operating Summary,1982

ML20072P364
Person / Time
Site:	05000054
Issue date:	03/28/1983
From:	Ruzicka W UNION CARBIDE CORP.
To:	Thomas C Office of Nuclear Reactor Regulation
References
NUDOCS 8304040220
Download: ML20072P364 (7)

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• O UNION CARBIDE CORPORATION MEDICAL PRODUCTS DIVISION P. O. BOX 324. TUXEDO.NEW YOAK 10987 TELEPHONE NUMBER: (914)351-2131 March 28, 1983 U.S. Nuclear Regulatory Commission Division of Reactor Licensing Washington, D.C. 20555 Attention: Mr. Cecil Thomas, Branch Chief Operating Reactors Branch of Division of Operating Reactors

Subject:

Annual Report: Docket 50-54 License R-81

Dear Mr. Thomas:

The following Annual Operating Summary for Union Carbide's Sterling Forest Reactor for the year 1982 is herewith submitted.

Sincerely, b.b , %h W. G. Ruzicka Reactor Supervisor Enclosure cc: Director, I & E Director, Region 1 of I & E fokO (1304040220 830328 PDR ADOCK 05000054 PDR R

ANNUAL REPORT FOR 1982 FOR THE

-UNION CARBIDE NUCLEAR REACTOR (UCNR)

DOCKET 50-54, LICENSE R-81 A. FACILITY MODIFICATIONS AND LICENSE CHANGES

1. Four silver indium cadmium reactor control rods were replaced. The new control rods incorporate a thicker tin-nickel surface plating and a strengthened rod to piston connection.

2. Radiation monitoring equipment was installed in Buildings 1 and 2, to upgrade the criticality monitoring system.

3. New fission product molybdenum target stringers were installed to allow single targets to be individually installed and removed from the core.

4. The R-81 License was amended to allow a larger percentage of core flow to be used for cooling in core experiments.

5. The R-81 License was changed to allow single encapsulation of in core fueled experiments.

6. The Union Carbide Nuclear Reactor Emergency Plan was revised to comply with new NRC standards for emergency preparedness. This updated plan was submitted to the NRC for approval.

B. PROCEDURES MANUAL The following is a listing of the major changes to the Facilities Procedures Manual.

AD-01 Procedures Manual Distribution List - the Manager of Maintenance and Engineering added to listing.

AD-0 6 Organization chart updated to reflect present organization s tructure.

RM-03 Reactor control setpoints changed:

RM-04 RM-06 - Low reactor flow rate scram setpoint changed from 1800 to RS-02 2000 gpm.

RS-01

- High pool temperature alarm setpoint changed from ll20 F to 1150F,

- High core delta T changed from 160F to a variable setpoint adjustable downward from 16 0 F as core flow is adjusted.

-A new Log N reverse vs. pool temperature setpoint adjustment table has been established to reflect reverse setpoint changes as pool temperature changes.

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PROCEDURES MANUAL '(CONTINUED) ~

RM Ventilation System Procedure - changed to provide a method of transferring control from the auxilliary hot lab exhaust fan back I

to the main exhaust fan to avoid an interruption of hot cell ventilation.

RM-10 Fuel Inventories - changed to clarify requirement to periodically inventory facility fission chambers.

RM-ll Safety Regulations - modified to include new requirements for operators to wear life preserver vests when working on ' pool ledges.

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EP-01 Emergency' Telephone Listing - new NRC telephone number added as a backup if King of Prussia or Bethesda numbers cannot be' reached.

EP-03 Reactor Radiation Alarms - changed to-reflect new CAM setpoints and alarms; new guidance added for operator action in the event of an unexplained CAM or stack monitor alarm.

EP-12 Security Procedure - activation of intrusion alarm procedure changed to include Building 2 crane lockout.

EP-13 Security Procedure - Assistant Chief Reactor Operator added to list of authorized individuals authorized access.

EP-14 Access Control - procedure issued to address access to the -

licensed controlled area.

I RS-02 Process Equipment Checklist - added step to take radiation-reading between primary heat exchanger bundles to monitor heat exchange crud buildup.

RS-46 Reactor Equipment Calibration Checks - data sheets added.

RS-47

! XG-02 Xenon Irradiation Procedure -

changed to reflect recent modifications to production rig.

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SU'4 MARY OF UNSCHEDULED SHUTDOWNS (CONTINUED)

Automatic Safety Action Initiated - Operator _ Error 1 Core exit flapper opened above allowed power-setpoint causing automatic scram .

1 Guide tube inadvertently lifted during flux scans causing automatic scram 1 Operator accidentally pushed remote scram button causing reactor shutdown Operator Initiated Manual Shutdown 3 Spot on core 1 Visual inspection of core identifies bent fuel element. Reactor shut-down and fuel element replaced 1 Reactor shut down to investigate unexplained Building 1 CAM alarm E. POWER GENERATED Total power generated in 1982 was 38,858 megawatt hours. The reactor was operated on a seven day a week schedule with refueling and maintenance shutdowns about once every one or two weeks.

F. ROUTINE TESTS CONDUCTED The reactor surveillance program has revealed no significant nor unexpected

trends in reactor systems performance during the past year with tests

! yielding routine results, i

G. FUEL Five fuel elements, containing aluminide (U-Alx) fuel matrix manufactured

, by CERCA (Franc e) , were received by the Union Carbide Nuclear Reactor in 1982. Twenty-four spent fuel elements were shipped to Idaho for reprocessing.

SUMMARY

OF UNSCHEDULED SHUTDOWNS (CONTINUED)

Automatic Safety Action Initiated - Operator Error 1 Core exit flapper opened above allowed power setpoint causing automatic scram 1 Guide tube inadvertently lifted during flux scans causing automatic scram 1 Operator accidentally pushed remote scram button causing reactor shutdown Operator Initiated Manual Shutdown 3 Spot on core 1 Visual inspection of core identifies bent fuel element. Reactor shut down and fuel element replaced 1 Reactor shut down to investigate unexplained Building 1 CAM alarm E. POWER GENERATED Total power generated in 1982 was 38,858 megawatt hours. The reactor was operated on a seven day a week schedule with refueling and maintenance shutdowns about once every one or two weeks.

F. ROUTINE TESTS CONDUCTED The reactor surveillance program has revealed no significant nor unexpected trends in reactor systems performance during the past year with tests yielding routine results.

G. FUEL Five fuel eler.ents, containing aluminide (U-Alx ) fuel matrix manufactured by CERCA (France) , were received by the Union Carbide Nuclear Reactor in 1982. Twenty-four spent fuel elements were shipped to Idaho for reprocessing.

1 H. PERSONNEL RADIATION EXPOSURES Eleven members of the Reactor Operations Staff and five members of the Health Physics Staff received exposures in excess of 25% of the recommended limit in 1982. These doses ranged from 1.33 rem to 4.24 rem with the overall average for these individuals being 2.83 rem.

A part of this exposure was due to maintenance support for Hot Laboratory Operations which is licensed under New York State Radioactive Materials License 729-0322.

No visitors to the facility received exposures greater than 25% of that permitted.

I. OFFSITE RELEASES OF RADIATION

1. Radioactivity released in Air Effluent from the site.

a. Noble Gases Isotope Quantity Released (Curies)

Kr-83m 373.4 Kr-85m 1095.5 Kr-87 99.5 Kr-88 1419.3 Xe-133m 373.4 Xe-133 12151.2 Xe-135 2490.0 Xe-135 6896.2 Kr-85 1.5 Total Noble Gas Release 24900 Ci Average Concentration of Noble Gases in Stack 3.3 x 10-5 uCi/cc

b. Iodines Isotope Quality Released (Curies)

I-125 2.55 Ci I-131 5.92 Ci Average Concentration in Stack I-125 3.41 x 10~9 uCi/cc I-131 7.94 x 10-9 uCi/cc i

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2. Radioactivity released in Liquid Effluent from the site.

Gross Beta Activity 0.0005 Ci (Sr-90 equivalent)

3. Particulate radioactivity released from the site.

The average concentration of particulate radioactivity released during 1982 was 8.65 x 10-12 uCi/cc. This activity consisted of the following approximate isotopic breakdown.

Particulate Isotope Percent of Total Activity 136 Cs 1.5 103 Ru 41.2 137Cs 8.6 95 Zr 34.2 95Nb 14.5

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

a. From releases of iodine during 1982 Dose via infant inhalation at Laurel Ridge 0.60 mrem from Iodine-131 0.18 mrem from Iodine-125

b. From releases of noble gas during 1982 0.08 arem total body dose at Laurel Ridge which is nearest residential area.

I For all site effluent releases approximately 95% result from Hot Laboratory operations under NYS License 729-0322.

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