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Submits Special Rept W/Charts Re Coolant Iodine Activity Which Exceeded Tech Specs.Caused by Two Scrams & Increase in Fission Product Inventory in Coolant from Leaking Fuel Element.Leaking Bundles Will Be Removed During Next Outage
	ML20125D515
Person / Time
Site:	Brunswick
Issue date:	01/03/1980
From:	Tollison A; CAROLINA POWER & LIGHT CO.
To:	;
References
	ASEP-80-12, NUDOCS 8001140343
	Download: ML20125D515 (6)
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Carolina Power & Light Company x.. .. ; a -, . . , . . , -

Brunswick Steam Elcetric Plant P. O. Box 458 Southport, N. C. 28461 January 3, 1980 FILE: B3516.2 SERIAL: 3SEP/80-12 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Co= mission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 LICENSE NO. DPR-62 DOCKET NO. 50-324 SPECIAL REPORT PER TECHNICAL SPECIFICATIONS 6.9.2c

Dear Mr. O'Reilly:

At 0855 on November 19, 1979, Unit No. 2 scrammed following approximately two months of high power operation. During the subsequent startup, the reactor scrammed again at 0425 on Nove=ber 20, 1979. Coolant iodine activity, already increasing after the first scram, exceeded the Technical Specification limit of 0.2 pC1/gm I131 , dose equivalent. The maximum iodine activity was 0.414 pC1/gm.

Reactor po'wer was held to < 10% until the iodine activity returned within specifications. High coolant activity was caused by the two reactor scrams and subsequent increase in fission product inventory in the coolant coming from a leaking fuel element. The Unit No. 2 fuel bundles will be sipped during the next refueling cutage and the leaking bundles removed from the core. This event was reported on December 6, 1979, with LER 2-79-99.

Very truly yours, 4 Nh - .

. A. C. To111 son, Jr., General Manager Brunswick Steam Electric Plant JLK/RMP/bd Encfosures 90017239 cc: Mr. R. A. Hartfield 9 yMr. V. Stello 007 8001140 } 4

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1 i l l 1 01 03 05 07 00 11 13 15 17 19 21 23 :S 27 29 31 33 35 37 39 41 43 45 47 49 51 ENCLOSURE 2 ', .

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ORE bA>J- U P OY SINGS

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.90017242 ENCLOSURE 2

\

OFF-GAS ANALYSES

~

Prior to the incident, the following Unit 2 Steam Jet Air Ejector (SJAE) off-gas levels were measured:

DATE. REACTOR OFF-GAS POWER (%) uci/sec at SJAE 11/ 2/79 91.4 16,666 11/.9/79 90.8 16,316 11/16/79 93.2 17,700 During the incident, the reactor was either sub-critical.or at <10% power;-

consequently, off-gas levels were quite low during this time period

(<1000uct/sec.). After returning to power operation, an off-gas analysis was performed on Unit 2:

DATE REACTOR OFF-GAS POWER (%) uci/sec at SJAE 11/26/79 95.3 24,396 All of these off-gas levels are within the applicable Technical Specifica-tion limits.

90017243

+_

Enclosure 3

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" TOTA 1. ~TrME IN EXCESS OP o.ap(i/ m. 9 I-131 A>se EGutVALEeJT - 13,3 ffgs, ,

4 -. I" Reac4er Scram occurred af- ~ 02SS on 88h9179 44- a"* Reac4or Scra m occurred a f- 04as ow. # # /ao/>y9 ENCLOSURE 4 s s

ML20125D515

Text

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