ML20214J177

Annual Operating Rept for 1986

ML20214J177
Person / Time
Site:	05000054
Issue date:	12/31/1986
From:	Ruzicka W CINTICHEM, INC.
To:	Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8705270678
Download: ML20214J177 (6)

Text

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'I ClNTICHEM, INC.

a wholly owned subsidiary of Medi-Physics, Inc. P.O. BOX 818. TUXEDO NEW YORK 10987 [914] 3 51-2131'

-March 31, 1987 U. S. Nuclear Regulatory Commission Director, Division'of Project and Resident Programs King of Prussia, PA 19406 Attention: ' Mr. Richard W. Starostecki

SUBJECT:

ANNUAL REPORT: DOCKET 50-54 LICENSE R

Dear Mr. Starosteckt:

The following Annual Operating Summary for Cintichem, Inc.'s Sterling Forest Reactor for the year 1986 is herewith submitted.

Sincerely,

.k  %'"

W. G. Ruzicka Manager of Nuclear Operations WGR: mag Enclosure cc: U. S. Nuclear Regulatory Commission Director Of fice of Nuclear Reactor Regulation Division of Licensing Washington, DC 20555 U. S. Nuclear Regulatory Commission Director Division of Fuel Cycle and Material Safety Washington, DC 20555 l U. S. Nuclear Regulatory Commission ,

Director '

Office of Inspection and Enforcement Washington, DC 20555 American Nuclear Insurers 270 Farmington Avenue Farmington, CT 06032 52 ek p i

e W E ANNUAL REPORT FOR 1986 FOR THE ClNTICHEM. INC. NUCLEAR REACTOR DOCKET 50-54. LICENSE R-81 A. FACILITY MODIFICATIONS AND LICENSE CHANGES

.1. Beam tube number four and it's experiment was removed and a short beam tube was installed in its place.

2. The #5 beam tube experiment was removed and an identical replacement was installed. The associated production glove box was replaced by an improved unit.

3. The cadmium lined Irradiation facility, installed last year, was removed from the southwest side of the core tower.

4. In preparation for a new north face sIIIcon irradiation facility:

a. The north pool sweep duct was relocated,

b. The regulating rod counter balance weight was relocated.

c. The reactor Ion chamber shelf was replaced with one of smaller dimensions and uncompensated ion chamber containment can diameters were decreased.

d. Two north pneumatic tube facIIItles were removed and three new pneumatic tube facilities were Installed on the south side of the core.

5. The new north face silicon Irradiation facility was Installed.

B. PROCEDURES MANUAL The foflowIng is a listing of the major changes to the FactiItles Procedures Manual.

RM-04-07 Pool water pH specifications changed to match technical spectfIcations.

RM-06-01 Same as RM-04-07.

RS-02-02 Beam tube vent alarm checks no longer required. (All are flooded.)

EP-01-04 Emergency roster Iist updated.

EP-04-11 Access control list for controlled access area updated.

XG-01-05 Fueled experiment acceptance criteria check added.

XG-02-01-11 Procedures rewritten - New design glove box installed.

4

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DOCKET 50-54 LICENSE R-81 ' March 31, 1987 C.

SUMMARY

OF UNSCHEDULED SHUTDOWNS The following is a listing of unscheduled shutdowns occurring during 1986.

Tvoe of Shutdown Number Cause Power Outage 10 Commercial Power Failure.

False Signal 9 Log N.

28 Momentary Loss of magnet current.

1 Flapper actuator rod disturbed unintentionally.

7 False safety scrams related to UIC can and shelf modifications.

Equipment Failure 2 Rod magnet failure.

Causing Automatic 2 Blown magnet fuses.

Shutdown Automatic Safety 1 Log N period scram during sample movement Action-Initiated due to shadowing.

Operator Error 2 Power increased above allowed power with flow

< 2000 gpm.

1 Log N period scram from sample stringer tube movement.

1 Low pool level scram during power reduction for sample change.

1 High flux scram from disconnecting and reconnecting spare U.l.C. signal cable.

Operator initiated 4 Objects dropped above or on core.

Manual Shutdown 1 Log-N channel erratic or falling to respond properl y.

1 Stack monitor maintenance required.

1 Accidental trip of excursion monitor and evacuation sequence.

1 Log-N recorder chart drive required maintenance.

1 Preparing to reset Hot Laboratory main exhaust fan.

D. POWER GENERATED Total power generated in 1986 was 40,380.82 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.

1. *~ DOCKET 50-54 LICENSE R-81 March 31, 1987 E. 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.

F. FUEL Eleven standard and seven control fuel elements, containing uranium oxide-aluminum (U3 0 8-AI) fuel matrix manufactured by Babcock and Wilcox (Virginia), were received by Cintichem, Inc. Nuclear Reactor in 1986.

There were no spent fuel shipments this year.

1 G. PERSONEL RADI AT10N EXPOSURES Nine members of the Reactor Operations Staf f and three members of the Health Physics Staff received exposures in excess of 25% of the recommended limit in 1986. These doses ranged from 1.38 rem to 2.48 rem with the overall average for these individuals being 1.71 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.

H. OFFSITE RELEASES OF RADI ATION

1. Radioactivity released in Air Effluent from the site.

a. Noble Gases Isotope Quantity Released (Curles)

Kr-83m 458.6 Kr-85m 1,285.3 Kr-87 123.3 Kr-88 1,673.0 Xe-133m 445.5 Xe-133 14,176.1 Xe-135m 2,879.2 Xe-135 8,056.6 Kr-85 1.7 Ar-41 1.110.5 Total Noble Gas Release 30,209.8*

• 0nly 1.7 Cl of the 30,210 Ci has a half life greater than eight days.

Average concentration of Noble Gases in ' stack was 4.06 x 10-5uCI/cc.

Average concentration of Noble Gas with a half life greater than eight days was 2.28 x 10-9uCI/cc.

.. , .. + ,. - , . . . - - . . . . .

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DOCKET 50-54 L1 CENSE R-81 * . March 31,;1987

b. lodines ,

Isotope ,

Ouantity Released (Curles)

.1-125 2.'48 CI 1-131~

3.93 Cl 1 .

2-

~ Average Concentration.In Stack l-125 3.34 x 10-9 uCI/cc I-131 5.26 x 10-9 uCi/cc

. 2. Radioactivity released in Liquid Effluent-from the site.-

Gross Beta Activity 0.0007 Cf.

13. Particulate radioactivity released

from the site.

l The average concentration of - particulate radioactivity _ released i during 1986 was t.09 x 10-11 uCI/cc. This activity consisted of the j following approximate isotopic breakdown.

i 1 Particulate isotope Percent of Total Activity '

136 Cs 1.5

!' 103 Ru 41.2 137 Cs 8.6 l 95 Zr 34.2 '

95 Nb 14.5 -

i 4. Calculated doses to a critical Individual in the unrestricted area.

I

a. From releases of lodine'during 1986 Dose via child inhalation at Laurel Ridge i 0.71 mrem from lodine-131 Dose via adult inhalation at Laurel Ridge.

) 0.33 mrem from lodine-125

b. From release of noble gas during 1986

1.70 mrem total body dose at Laurel Ridge >

which is nearest residential area.

For all site effluent releases approximately 95% result from Hot Laboratory operations under New York State License 729-0322.

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