ML18219D822

Furnishing Report Pursuant to Appendix a Tech Spec Concerning on 3/7/1978 Dose Equivalent Iodine-131 Activity in Reactor Coolant System

ML18219D822
Person / Time
Site:	Cook
Issue date:	04/04/1978
From:	Shaller D Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co), American Electric Power Service Corp, American Electric Power Company
To:	James Keppler NRC/RGN-III
References
Download: ML18219D822 (15)

Text

ug Pi(4g'EGULATORY INFORMATION DISTRIBUTION SYSTEM<RIDS)DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 04/04/78 NRC IN 8c MI PWR DATE RCVD: 04/24/78 DOCTYPE: LETTER NOTARIZED:

NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FURNISHING REPT PURSUANT TO APPENDIX A TECH SPEC 3.4.8 8(6.5'.1 CONCERNING ON 03/07/78 THE DOSE EQUIVALENT IODINE-131 ACTIVITY IN UNIT 1 REACTOR COOLANT SYSTEM WAS FOUND OUT OF SPECIFICATION...

W/ATT SUPPORTING INFO.PLANT NAME: COOK-UNIT 1 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:~~DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS++++++%~<+++~+++~~

GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.(DISTRIBUTION CODE AQOi)FOR ACTION: INTERNAL: EXTERNAL: BR CHIEF SCHWENCER++W/7 ENCL~G F LE~~W/ENCL HANAUER~~W/ENCL E I SENHUT+4 W/ENCL BAER++W/ENCL EE84+W/ENCL J.MCGOUGH>+M/ENCL LPDR S ST.JOSEPH'I<<W/ENCL TI C++W/ENCL ,NS I C4 4W/ENCL;ACRS CAT B+%N/16 ENCL NRC PDR++W/ENCL OELD+<LTR ONLY CHECK4+W/ENCL SHA0%4W/ENCL BUTLER++M/ENCL J COLLINS+<W/ENCL Save~auea,/<pP~~i m f/DuS~m E>CC.+o YArc'~/++7

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LTR ENCL~SIZE: 2P+6P CONTROL NBR: 781150033.1 NR~END I I I I t I"t t t II I I" I t t e lt II I oi o er4can/iEleotrlo INDIANA&MICHIGAN PDNER COMPANY DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 (616)465-5901 Nr.J.G.Keppler, Regional Director Office of Inspection and Enforcement U.S.Nuclear Regulatory Comission Region III 799 Roosevelt Road Glen Ellyn, Il 60137 April 4, 1978 Operating License DPR-58;"" Docket 0 50-315~t'I CD P1 Cll<<-1 M f%w c'i~l IQ D)l ll Rtv tel CA~cjl~A7"5 CD

Dear Mr.Keppler:

This report is submitted persuant to the requirement of Appendix A Technical Specification 3.4.8 and 6.9.1, On l1arch 7, 1978, the dose equivalent iodine-131 activity in Unit 1 reactor coolant system was found out of specification.

At 1003 on March 7, 1978 Unit 1 reactor tripped from 1005 power.Immediately following the trip, letdown purification flow was increased to its maximum.Analysis at 1130 on March 7, 1978, indicated dose equivalent iodine-131 at 1.025.pCi/cc.Maximum dose equivalent iodine-131 concentration was detected at 1345 to be 1.046 pCi/cc*~Dose equi-valent iodine-131 remained out of specification until 1440.All ad-ditional sample analysis indicated the reactor coolant dose equivalent iodine-131 remained in specification and was decreasing.

No additional spiking was noted during the subsequent reactor startup.No degassing operations were associated with this event.Iodine release at this time period is consistent with data reported in Westinghouse Electric Corporation WCAP-8637,"Iodine Behavior under Transient Conditions in the Pressuirzed Water Reactor".Dose equivalent iodine-131 values were in the"Acceptable Operation" portion of Technical APR 6 1978 781150033 goo I\J~I 0"~*4 o b I, April 4, 1978 Mr.J.G.Keppler Page Two Specification Figure 3,4.1 at all times during the transient.

Fuel burnup by core region and all additional data is indicated in the attached table/graphs.

• Coolant samples are brought to.ambient conditions prior to counting, therefore, units of pCi/g and pCi/cc are considered interchangeable.

Very truly yours,+c~D.V.Shaller Plant Manager attachments cc: R.W.Jurgensen J.'.Dolan R.Kilburn R.F..Kroeger R.J.Vol 1 en, BPI K.R.Baker, RO: III P.W.Steketee, Esq.R.C.Callan R.Walsh, Esq.G.Olson J.Stietzel PNSRC File G.Charnoff, Esq.J.M.Hennigan Dir, IE (20 copies)Dir, MIPC (2 copies)

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HARCH 7, 1978 UNIT NO.1 CYCLE NO.2 Fuel Burnup by Core Reason REGION NO.BURNUP FOR PERIOD (~D(WU)CUHULATI VE BURNUP (teD/mu)ENERGY FOR PERIOD (BTU)CUNULAT I VE ENERGY (BTU).0.1799E+04 0.2053E+04 0.2802E+05 0.2397E+05 0.1871E+04

.0.9543E+04 0.4267E+13 0.4290E+13 0.4867E+13 0.2176E+14 0.6681E+14 0.5685E+14 CORE TOTAL 0.1908E-:04 0.2067E+05 0.1342E+14 0.1454E+15

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