ML20125D515
| 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) | |
Text
e 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 907 yMr. V. Stello 0
8001140 }
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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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U 900i7241 qona RMos k
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
+_
Unsr 2 REne roa-cootanr zoo,na Arantisus r*30 ITj Ci/mi) I%Ci/ [ IhG3=l[ Th(4b8) NYm(eo#o7,I(e 1
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j ii/aA 02o5
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it/wM ooso 1992.E-3
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13,3 ffgs,
" TOTA 1. ~TrME IN EXCESS OP 9
4 -.
I" Reac4er Scram occurred af- ~ 02SS on 88h9179 44-a"*
Reac4or Scra m occurred a f-04as ow.
- # /ao/>y9 j
ENCLOSURE 4 s
s