ML20212E268

Special Rept 87-01:on 870130,dose Equivalent I-131 of RCS Found to Be 1.53 Uci/G.Caused by Fuel Cladding Defects. Appropriate Sampling & Analysis Performed Until Activity Restored within Limits

ML20212E268
Person / Time
Site:	Callaway
Issue date:	02/27/1987
From:	Randolph G UNION ELECTRIC CO.
To:	Berlinger C, Mccracken C NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
87-01, 87-1, ULNRC-1452, NUDOCS 8703040308
Download: ML20212E268 (5)

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CeRaway Plant February 27, 1987 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attention C. Berlinger C. McCracken ULNRC-1452 Gentlemen:

DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 FACILITY OPERATING LICENSE NPF-30 SPECIAL REPORT 87-01 REACTOR COOLANT SPECIFIC ACTIVITY IN EXCESS OF TECHNICAL SPECIFICATION 3.4.8 LIMITATION The enclosed Special Report is submitted pursuant to

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Technical Specification 3.4.8 concerning the Reactor Coolant specific activity in excess of Technical Specification limitations.

At G. L. Randolph Manager, Callaway Plant "D 5 W JRPe/TPS/JMK/dra Enclosure cc: Distribution attached 8703040308 070227 PDR ADOCK 05000483 PDR S

b S'. $j MaMg Adfress P.O Box 62Q Fulton, MO 65251

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.cc distribution for ULNRC-1452-Mr. Paul O'Connor. (2 copies) . Manager, Electric Department Office.of Nuclear Reactor Regulation Missouri Public Service Commission U.S. Nuclear Regulatory Commission P. O. Box 360 .

t Ma il Stop P-316 Jefferson City, M0~ 65102

-7920 Norfolk Avenue Bethesda,~MD. 20014 Mr. O. Maynard

, Wolf Creek Nuclear Operating Corp.

P. O. Box 411 American Nuclear Insurers Burlington, KS 66839 c/o Dottie Sherman, Library The Exchange Suite 245 Mr. J. O. Cernak 270 Farmington Avenue- CFA Inc.

Farmington, CT 06032 3356 Tanterra Circle Brookville, MD 20833 Mr. N. P. Goel

.Bechtel Power Corporation Records Center SNUPPS Project Institute of Nuclear Power Operations 15740 Shady Grove Road Suite 1500 Gaithersburg, MD 20877-1454 1100 Circle 75 Parkway Atlanta, GA 30339 NRC Resident Inspector Mr. Merlin Williams-D. F. Schnell (400) Supt. of Regulatory Quality &

R. J. Schukai (470) Administrative Services S. E.~ Miltenberger Wolf Creek Nuclear Operating Corp.

J. F. McLaughlin P. O. Box 411 J. E. Davis (Z40SR) Burlington, KS 66839 (240SR) (w/c)

D. W. Capone /R. P. Wendling (470)

F. D. Field (480) .

A. P. Neuhalfen '

A. C. Passwater/D. E. Shafer/D. J. Walker (470)

G. A. Hughes Z40.03-(QA Record)

J.1M. Price J. R. Peevy M. E. Taylor

, H. Wuertenbaecher, Jr. (100) 3: S. L. Auston (470)(NSRB)

S. J. Bellers/J. D. Sch GLR Chrono t 3456-0021.6 3456-0260 Z40ULNRC G56.37 N. Date (Sandra Auston) (470)

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4 SPECIAL REPORT 87-01 REACTOR COOLANT SPECIFIC ACTIVITY IN

-EXCESS OF TECHNICAL SPECIFICATION 3.4.8 LIMITATION

-ThisE Special Report is being submitted in accordance with Technical

. Specification;(T/S) 3.4.8,'which requires a report be submitted when-the specific activity of the Reactor Coolant System (RCS) is greater thi ,

1.0 microcurie per gram '(UCi/gm) Dose Equivalent I-131.

oOn 1/30/87 at 0809 CST the dose equivalent I-131 of the RCS was sampled and found to be 1.53 pCi/gm.. The value during normal operation for the past two months has been'approximately .02 pCi/gm. This increase'in activity followed a planned shutdown of the reactor for maintenance activities. The cause of the high dose equivalent I-131 level is fuel cladding' defects. Licensed operators entered the applicable action statement as follows:

"With the specific activity of the reactor coolant greater than 1.0 microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microCuries per gram of gross radioactivity, perform the sampling and analysis requirements of Item 4.a) of table 4.4-4 until the specific activity of the reactor coolant is restored to within its limits ..."

Appropriate sampling and analysis requirements were performed until 1720 CST on 1/30/87, at which time the RCS specific activity was restored within limits.

The following information is provided per T/S 3.4.8 Action Statement requirements:

a) Reactor power history is as follows:

From 1/28/87 at 0809 CST to 1/29/87 at 1800 CST, reactor power was at 100%.

From 1/29/87 at 1800 CST to 1/30/87 at 0358 CST, reactor power was decreased from 100% to 0% at a rate of 10% per hour.

On 1/30/87 at 0358 CST, the reactor was shutdown. Power remained at 0% for the duration of the time that the dose equivalent I-131 (DEI-131) limit was exceeded. c b) The results of the isotopic analysis for radiciodine are:

SPECIAL REPORT 87-01 Page 2 Date Time DEI-131 I-131 I-132 I-133 1-134 I-135 (pci/gm) (pCi/gm) (pCi/gm) (pCi/gm) (pCi/gm) (pCi/gm) 1/30/87 0200 .048 .034 .034 .036 .014 .027 1/30/87 0809 1.53 1.22 .300 1.02 .005 .336 1/30/87 0855 1.54 1.22 .281 1.05 .003 .327 1/30/87 1003 1.62 1.29 .255 1.09 .000 .312 1/30/87 1100 1.56 1.25 .233 1.04 .000 .283 1/30/87 1203 1.44 1.16 .207 .935 .000 .242 1/30/87 1305 1.30 1.05 .183 .829 .000 .200 1/30/87 1517 1.13 .925 .169 .675 .000 .143 1/30/87 1720 .984 .817 .165 .564 .000 .105 c) The cleanup flow through the Chemical Volume and Control System mixed bed demineralizer was at 120 gallons per minute for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to exceeding 1 pCi/gm DEI-131. The cleanup flow remained at 120 gpm while the DEI-131 was above 1 pCi/gm.

d) The Volume Control Tank was on a continuous vent of 0.7 cubic feet per minute for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the DEI-131 exceeding 1 pCi/gm except for 0130 CST to 0512 CST on 1/30/87 at which time the continuous vent was secured. This is the only degassing operation that occurred.

e) The DEI-131 exceeded 1 pCi/gm for 9.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> from 0809 to 1720 on 1/30/87.

Also provided for your information is a time line graph comparing the power level, I-131 specific activity and I-133 specific activity.

Fuel cladding defects have been previously identified when the DEI-131 exceeded 1 pCi/gm on 8/25/86. This event was reported via Special Report 86-07, ULNRC-1374, dated 9/23/86.

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