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LER 82-004/03L-0:on 820116,RCS Dose Equivalent I-131 Concentration Exceeded 1.0 Uci/G steady-state Limit & Unit Experienced 100% Trip
	ML20041B269
Person / Time
Site:	Cook
Issue date:	02/11/1982
From:	Palmer R; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20041B265	List: ML20041B264; ML20041B269; ML20041B271; ML20041B273;
References
	LER-82-004-03L, LER-82-4-3L, NUDOCS 8202230454
	Download: ML20041B269 (5)
	v • d • e

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14 JS RE* ORT DATE 60 EVENT DESCRIPTION AND PROBABLE CONSEQUEi4CES h f a TTl I FOLLOWING A REACTOR TRIP, THE REACTOR COOLANT SYSTEM (RCS) DOSE EQUIVALENT (DOSEQ) I j o i3i l IODINE I-131 CONCENTRATION EXCEEDED THE 1.0 uCi/ gram STEADY STATE LIMIT OF TECHNICAL l AN UNUSUAL EVENT WAS DECLARED AT 2103 HOURS ON JANUARY 16, 1982,1

[ol43l SPECIFICATION 3.4.8.

in isl l DUE TO THE IODINE VALVES EXCEEDING THE STEADY STATE LIMITS. THE UNUSUAL EVENTl WAS iO is l l TERMINATED AT 0740 HOURS ON JANUARY 17, 1982, WHEN T'E IODINE VALUES WERE WITHIN l lo!;Il SPECIFICATION. PREVIOUS SIMILAR OCCURRENCES INCLUDE: 50-315/78-026,76-059; l l

ioisi 1 50-316/81-049.

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44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l i i o 1 1 ON JANUARY 16, 1982, FOLLOWING A TRIP FROM 100% POWER THE RCS DOSEQ-I-131 SPIKED T0 l 1iiii 1 2.04 pCi/ gram. PRIOR TO THE TRIP, RCS DOSEQ-I-131 WAS AVERAGING ~6 x 10-2 uCi/ gram. I i,i,il FOLLOWING THE TRIP THE UNIT WAS RETURNED TO FULL POWER OPERATION AT 1230 HOURS ON 1 i , l,i l JANUARY 18, 1982, AND THE RCS I0 DINE VALUES LEVELED OUT AT APPR0XIMATELY 8 x 10-2 ii ia i l uCi/ gram. (SEE ATTACHED SUPPLEMENT). i

2 ST WS "GPOWER OTHER STATUS IS O RY DISCCNERY DESCRIPTION NA l l Ii' I5 l lG l@ l 0 l 0 l 0 l@l l B l@l ROUTINE CHEMICAL ANALYSIS ACTIVITY CONTENT RELE ASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE NA l l NA l li 16 l Iz l @ l zl@l PERSONNEL E XPOS 4ES NUMBER TYPE D E SCRIP TIO N l

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ATTACHMENT TO LER# 82-004/03L-0 SUPPLEMENT TO CAUSE DESCRIPTION THIS REPORT IS SUBMITTED PERSUANT TO THE REQUIREMENTS OF APPENDIX A TECHNICAL SPECIFICATIONS 3.4.8 AND 6.9.1 ON JANUARY 16, 1982, THE DOSE EQUIVALENT 10 DINE-131 ACTIVITY IN THE UNIT 2 REACTOR COOLANT SYSTEM WAS FOUND OUT OF SPECIFICATION.

AT 1717 HOURS ON JANUARY 16, 1982, THE UNIT EXPERIENCED A 100% TRIP.

LABORATORY ANALYSIS AT 1830 HOURS ON JANUARY 16, 1982, INDICATED THE REACTOR COOLANT DOSE EQUIVALENT 10 DINE-131 CONCENTRATION HAD SPIKED TO A MAXIMUM 0F 2.04 pCi/cc.* THE DOSE EQUIVALENT 10 DINE-131 ACTIVITY REMAINED OUT OF SPECIFICATION UNTIL 0530 HOURS ON JANUARY 17, 1982. ALL SUBSEQUENT ANALYSIS INDICATED THE REACTOR COOLANT ACTIVITY TO BE DECREASING IN I0 DINE ACTIVITY.

THE UNIT WAS RETURNED TO CRITICALITY ON JANUARY 17, 1982, AT 0112 HOURS AND POWER WAS SLOWLY INCREASED. FULL POWER OPERATION WAS ACHIEVED AT 1230 HOURS ON JANUARY 18, 1982. CVCS LETDOWN PURIFICATION FLOW WAS MAINTAINED AT THE MAXIMUM OBTAINABLE THROUGHOUT THIS INCIDENT.

IODINE RELEASE AT THIS TIME PERIOD IS CONSISTENT WITH DATA REPORTED IN WESTINGHOUSE ELECTRIC CORPORATION WCAP-8637, " IODINE BEHAVIOR UNDER TRANSIENT CONDITIONS IN THE PRESSURIZED WATER REACTOR". DOSE EQUIVALENT 10 DINE-131 VALUES WERE IN THE " ACCEPTABLE OPERATION" PORTION OF TECHNICAL SPECIFICATION FIGURE 3.4-1 AT ALL TIMES DURING THE TRANSIENT. ALL APPLI-CABLE TECHNICAL SPECIFICATION ACTION ITEMS WERE MET DURING THIS TIME.

FUEL BURNUP BY THE REGION AND ALL ADDITIONAL DATA, AS REQUIRED BY TECHNICAL SPECIFICATION 3.4.8, IS FOUND IN THE ATTACHMENTS.

COOLANT SAMPLES ARE BROUGHT TO AMBIENT CONDITIONS PRIOR TO COUNTING; THEREFORE, UNITS OF pCi/ GRAM AND pCi/cc ARE CONSIDERED INTERCHANGEABLE.

(sATTAUjMENT TO LER# 82-OLN O3L-0

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ML20041B269

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