ML17326A597

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Aeo 80-002/04X-0:on 800314,total of 0.871 Ci Xe-133 & 2.37 X 10-4 Ci I-131 Released from Unit 1 Vent Stack During Valving of Unit 2 Failed Fuel Detector.Caused by Leak in Fuel Detector.Failed Fuel Detector & Safety Valves Isolated
ML17326A597
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 03/24/1980
From: Shaller D
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
References
NUDOCS 8003310341
Download: ML17326A597 (3)


Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR;8003310341 DOC ~ DATE! 80/03/24 NOTARIZED:

NO FACIL~

~

Donald C,

Cook Nuclear Power P 1 ant E

Uni t 1P Indiana 50"316~ onald C ~

Cook Nuclear Power

. Plant Uni t 2E Indiana A

T&RTNAM AUTHOR AFF II.IATION SHALLERlD~ V, Indiana 8 Michigan Electric Co, RECIP ~ NAME RECIPIENT AFFILIATION DOCKET ¹ 05000315 05000316

SUBJECT:

AEO 80 002/04x 0:on 800314Ptotal of 0,871 Ci Xe 133 2'7 x

10 6 Ci I

131 feleased from unit 1 vent stack during valving of Unit 2 failed fuel aetector,Caused by leak in fuel detector, Failed fuel detector 8 safety valves isolated, DISTRIBUTION CODE:

C003S COPIES RECEIVED:LTR. g ENCL + SIZE:~

TITI E: Environ ~ Event/Abnormal Occurence NOTES:MS-C~ ~>

d<<M2lKQ RECIPIENT COPIES REC IP IENI ID CODE/"lAME LTTH EN L

ID CODE/V4'iE ACTION:

05 BC d/8 W I 7

COPIES LTTR ENCL INTERNAL:

0 Rf G FILE 12 E

15 TA/EDO 17 EEB 19 EN VI SPEC BR 21 DIR -DSE

--*----E.X-TERNAL:.03 LPDR 22 ACRS 1

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1 1

1 1

1 02 NRC PDR 14 OELD 16 MPA 18 CRQCKERPL ~

20 EFFL TR SYS AEOD 04 NSIC APR

> ]999 0

TOTAL NUMBER OF COPIES REQUIRED!

LTTR

?3 ENCL

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IMIAPJA 8r NIGHIGAIIIECECTHIC CDNPANY DONALDC. COOK NUCLEAR PLANT

.P.O. Box 468, Bridgman, Michigan 49106 (61S) 4654901 March 24, 1980 Mr. J.G. Keppler, Regional Director Ozfice of Inspection and Enforcement United States Nuclear. Regulatory Commission Region III 799 Roosevelt Road.

Glen Ellyn, IL 60137

Dear Mr. Keppler:

Operating Licenses DPR-58 and DPR-74 Docket Nos.

50-315 and 50-316 ISO No. 80-032/04K-0 The following report is being submitted as required by the Appendix B Techni-cal Specifications, Section 5.4.2. 1, and describes the cause and corrective action of the incident which was verbally reported to Mr. R.E.

Masse, NRC Region III Inspector, at 1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br /> on March 14, 1980.

During valving in the Unit 2 Failed Fuel Detector, the sampling line was overpressurized causing the safety valve on the system to relieve.

The reactor coolant water dischaxged from this safety valve, drained to the clean sump tank which vented radioactive gas to the Unit 1 vent stack.

This release was detected by the stack radiogas monitor R-26 with the alarm alerting the operatoxs of a possible leak.

Further investigation identified a leak coming from the Unit 2 Failed Fuel Detector which was immediately isolated.

The Unit 1 vent radiogas monitor returned to background levels after isolating the safety valve.

Gas was released from the vent from 1020 to 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on March 14, 1980.

A total of 0.871 Ci of Xe-133 was released at a rate of 7.74 X 10-4 Ci/Sec.

This is 1.3 percent, of the Technical Specification Appendix B Instantaneous Release Rate Limit Section 2.4.3.a.l.

Also released

were, 2.37 X 10-6 Ci of I-131, at a xate of 9.87 X 10-10 Ci/Sec.

which is 0.015 percent of Technical Specification Appendix B Instantaneous Release Rate Limit Section 2.4.3.a.2.

This occurrence had no effect on the health and safety of the public.

Sinc~ely, D.V. Shaller Plant Manager

/bab cc:

See Attached Distribution 800$sl 0 +9 i;.

Hr. J.G. Keppler March 24, 1980 Page 2 of 2 cc:

J.E.

Dolan R.S. Hunter R.H. Jurgensen R.F. Kroeger R.E. Ktlburn R.E. Kxsse RO:III R.C. Callen MPSC G. Charnoff, Esp.

G. Olson J..f. Hennigan U. Lavallee EPRI PNSRC J.F. Stietzel E.L. Townley Dir., IE (20 copies)

Dir., HIPC (2 copies)

Directora"e of Licensing