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LER 82-078/03L-0:on 820918 & 20,RCS Dose Equivalent I-131 Concentration Exceeded 1.0 Uci/G steady-state Limit.Caused by RCS Dose Equivalent I-131 Spiked to Max of 1.76 Uci/G
	ML20027C533
Person / Time
Site:	Cook
Issue date:	10/05/1982
From:	Palmer R; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20027C529	List: ML20027C528; ML20027C530; ML20027C533;
References
	LER-82-078-03L-01, LER-82-78-3L-1, NUDOCS 8210180129
	Download: ML20027C533 (6)
	v • d • e

LICENSEE EVENT REPORT CONTROL eLOCK- l

,, l l l l l@ (PLEASE PRINT CR TYPE ALL RE!UIRED INFORMATl!N) to lil8 lu i 9 11L8CENsEE lD ICCOD;f C 12 l@l0 l0 l- l0 34 lb l0 l0 l0 l0 l- l0 l0 jgj4 l1 l1 ;1 gi lg; LICENSE NUMoEM lg 23 J6 LicENbE TYPE JO 5 7 L A I b6 CON'T IoI51 57,,5 60 [.1_j@l 0 l 5 l 01010 l 311 l 6 l@l 0 l 9 l 1 l8 l 8 l2 l@l1 l 0 l0 l 5 l 8 l2 l@

8 61 DOCKE T NUMBER 68 6J EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES O'o Io i2i lFOLLOWING A REACTOR TRIP AT 1918 HOURS ON SEPTEMBER 18,1982 THE REACTOR COOLANT g tosail SYSTEM (RCS) DOSE EQUIVALENT (DOSEQ) 10 DINE-131 CONCENTRATION EXCEEDED THE ,

Io i. i i 1.0 uCi/ gram STEADY STATE LIMIT OF TECHNICAL SPECIFICATION 3.4.8. THE 10 DINE ,

io is1 l LEVELS REMAINED IN EXCESS OF TECHNICAL SPECIFICATION LIMITS UNTIL 0500 HOURS ;

io is l l ON SEPTEMBER 19, 1982. THE PUBLIC HEALTH AND SAFETY WERE NOT AFFECTED. PREVIOUS I

' Io Iii 1 0CCURRENCES OF A SIMILAR NATURE INCLUDE: 50-315/76-059,78-026;50-316/81-049, ,

i o is i I 82-004,013,018,067,075.

t

' CE'E '^SE CO s'sCiEE COMeoNENT CooE su'sC7 - suSEE 1o191 lC lG l@ lX l@ y@ l Z l Z l Z l Z l 7 l Z lg g[oEg gg tE O ,ajg.,RO 18 l2l EvENTv AR Vi*r's RE, EN " "'

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41 lNl@ lZl@ l Z l 9 l 9 l 947 l@

40 42 43 44 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h li1oll ON SEPTEMBER 18, 1982, FOLLOWING A REACTOR TRIP, THE RCS DOSEQ-I-131 SPIKED TO A i

li lij l MAXIMUM 0F 1.76 uCi/ gram. PRIOR TO THE REACTOR TRIP, THE RCS DOSEQ-I-131 WAS i i,,2i l AVERAGING 9.5 x 10 2 uti/aram. (SEE ATTACHED SUPPLEMENT) I lilai l I i L.L.11.1 I i l 'sT'A'N7s* . POWER OTHER STATUS @ SC Y discovery DESCRIPTION 32

I i i s I L9 l@ 1010 10 l@l NA l [B_j@l ROUTINE CHEMICAL ANALYSTS l

'JTiv,Tv CaTENT *

a l

KELEAsED OF RELE ASE AMOUNT of ACTIVITY LOCATION OF HELEASE 1 i I a' I 'LI.1 @ LZ.J@l NA ,_l l NA l

,ERso~~a E xFoJEs " * "

~UM.ER mE oEsCR,,T,0~ @

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b@!'o NA, , l 8210100129 821005 '

80 is otsCnietiON@ PDR ADOCK 05000316 NRC USE ONLY ,

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68 69 lllllllllllll5 80 = -

NAME OF PREPARER e n A. Pa ker pggyg W) E-N 2 _

/

ATTACHMENT TO LER# 82-078/03L-0 SUPPLEMENT TO CAUSE DESCRIPTION THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF APPENDIX A TECHNICAL SPECIFICATIONS 3.4.8 AND 6.9.1. ON SEPTEMBER 18, 1982, THE DOSE EQUIVALENT 10 DINE-131 ACTIVITY IN THE UNIT 2 REACTOR C0OLANT SYSTEM WAS FOUND OUT OF SPECIFICATION.

AT 1918 HOURS ON SEPTEMBER 18,1982, THE UNIT EXPERIENCED A REACTOR TRIP.

LABORATORY ANALYSIS AT 2120 HOURS ON SEPTEMBER 18, 1982, INDICATED THE RE-ACTOR COOLANT DOSE EQUIVALENT 10 DINE-131 CONCENTRATION HAD EXCEEDED THE TECHNICAL SPECIFICATION LIMITS OF 1.0 pCi/ gram, *THE DOSE EQUIVALENT 10 DINE-131 ACTIVITY SPIKED TO A MAXIMUM 0F 1.76 pCi/ gram AT THIS TIME.

THE REACTOR COOLANT SYSTEM DOSE EQUIVALENT IODINE REMAINED AB0VE TECHNICAL SPECIFICATION LIMITS UNTIL 0500 HOURS ON SEPTEMBER 19. 1982.

AT 2313 HOURS ON SEPTEMBER 18, 1982, THE REACTOR WAS AGAIN TAKEN CRITICAL AND POWER ASCENSION STARTED. A SECOND REACTOR TRIP OCCURRED AT 0417 HOURS ON SEPTEMBER 20, 1982, AT APPR0XIMATELY 18% POWER. THE UNIT WAS AGAIN TAKEN CRITICAL AT 0916 HOURS ON SEPTEMBER 20, 1982. A THIRD REACTOR TRIP OCCURRED AT 1054 HOURS ON SEPTEMBER 20, 1982, AT APPROXIMATELY 12% POWER.

RCS DOSEQ-I-131 SPIKED AFTER EACH REACTOR TRIP, BUT DID NOT EXCEED THE 1.0 pCi/ gram TECHNICAL SPECIFICATION LIMIT. CVCS LETDOWN PURIFID Ki' FLOW WAS MAINTAINED THROUGH0UT THE TRANSIENTS. ALL SUBSEQUENT DOSE EQUlVALENT IODINE ANALYSIS INDICATED DECREASING LEVELS OF I0 DINE. IODINE ?CLEASE 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 y

o ALL TIMES DURING THE TRANSIENT. ALL APPLICABLE 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; THERE-FORE, UNITS OF pCi/ gram AND pCi/cc ARE CONSIDERED INTERCHANGEABLE.

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