ML18219C206

Licensee Event Report RO 50-315/78-000 Re Out of Specification of Dose Equivalent Iodine-131 Activity

ML18219C206
Person / Time
Site:	Cook
Issue date:	04/04/1978
From:	Shaller D Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
Download: ML18219C206 (25)

Text

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INFORMATION DISTRIBUTION SYSTEN (BIDS)'EGULATORY DISTRIBUTION FOR INCONING NATERIAL 50-315 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 04/04/ 78 NRC IN 5 NI PWR DATE RCVD: 04/10/7 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 LICENSEE EVENT REPT (RO 50-315/78-000> ON 01/07/78 CONCERNING REACTOR PWR ON UNIT 1 REDUCED SLOWLY TO 8/. PWR AND THE REACTOR TRIPPED FRON 8/... W/ATT SUPPORTING INFO.

PLANT MANE: COOK UNIT 1 REVIEWER DISTRIBUTOR DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INITIAL: ~

INITIAL: X JN INCIDENT REPORTS

<DISTRIBUTION CODE A002)

FOR ACTION: BR C ~rH 4W/4 ENCL INTERNAL: REG FILE++W/ENCL NRC PDR4+W/ENCL NIPC~~~W/3 ENCL SCHROEDER / IPPOL I TO~4 W/ENCL NOVAK/CHECK+~W/ENCL HOUSTON4~W/ENCL GRINES++WfENCL KNIGHT+4WfENCL BUTLER++W/ENCL MANAUER+~~W/ENCL TEDESCO++W/ENCL EISENHUT4 ~W/ ENCL BAER4~W/ENCL SHAO~+WfENCL VOLLNER/BUNCH+~W/ENCL KREGER/ J. COLLINS'W/ENCI ROSA4+Wf ENCL K SEYFRIT/ IE~~+WfENCL LPDR S ST. JOSEPH NI +4W/ENCL TIC++WfENCL NSIC4+WfENCL ACRS CAT B++W/16 ENCL COPIES NOT SURiITTED PER REGULATORY GUIDE 10.1 DISTRIBUTION'TR 45 ENCL 45 CONTROL NOR: 78101+47$

SIZE: 2P+iP+9P

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~laaMa c IIMIAI'VA8t NICHIGAPJ POPPY CObfPAIIIY DONALD C. COOK NUCLEAR PLANT P.o. Box 458, Bridgman, Michignn 40106 (616) 465-5001 Apri l 4, 1978 Operating License C.

50-315 DPR-58'ocket 8 CIRC

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CUC C-CPM Yir. J. G. Keppler, Regional Director m~

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Office of Inspection and Enforcement Ag)~

~m W QQ U. S. Nuclear Regulatory Coiimission Region III m CD 799 Roosevelt Road G".en Ellyn, Ill. 60137 CD

Dear Yir. Keppler:

This report is submitted persuant to the requirement of Appendix A Technical Specifications 3.4.8 and 6.9.1. On January 7, 1978 the dose equivalent iodine-131 activity was found out of specification.

At 1400 on January 7, 1978 reactor 'power on Unit 1 was reduced slowly to 8% p'ower and the reactor tripped from 8Ã. Power reduction was done for a scheduled repair/investigation outage.

Routine surveillance at 2100 January 7, 1978 showed that the dose equivalent iodine-131 had spi ked with a maximum value noted of 1.1 p Ci/gram.*

Reactor power had been varied considerably the previo s week with no evidence of iodine spiking noted. During power reduct n CVCS purifi-cation flow through the mixed bed demineralizer was app ximately 75 gpm, as it had been for the majority of the week. No degassin operations were associated with this occurrence.

Analysis of the reactor coolant prior to this excursion had shown dose equivalent iodine-131 to range from 9. 12 x 10 p Ci/g to 2.80 x 10 Ci/g during the period of numerous power changes. Analysis at 0500 on 1-8-78 showed the iodine-131 had decreased to 0.539 pCi/g with dose equivalent iodine-131 at 0.675'Ci/g. This activity continued to decrease even during power ascension on 1-9-78. Once stable at. 100% dose equiva-lent iodine-131 remained constant at approximately 2.3 x 10 2 pCi/g.

Iodine release at this time period is consistant with data reported in llestinghouse Electric Corporation HCAP-8637 "Iodine Behavior under transient conditions in the Pressurized 1llater Reactor". Dose equivalent iodine-131 values were in the "Acceptable Operation" portion of Technical Ofo0/7 PD

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Apri 1 4, 1978 Hr. J. G..Keppler Page 2 Specification Figure 3.4.1 at all times during the transient. Fuel burnup by core region is indicated'in the attached table; This report does not meet the 30 day Technical Specification reporting requirement. This is presently under investigation and a Licensee Event Report will be submitted describing the findings and resolutions.

• Coolant samples are brought to ambient conditions before counting; therefore, units of pCi/gram and pCi/cc are interchangeable.

Very truly yours, D. Y. Shaller Plant Hanager attachments cc: R. l9. Jurgensen J. E. Dolan R. Kilburn R. F. Kroeger R. J. Yollen, BPI K. R. Baker, RO:III P. M. Steketee, Esq.

R. C. Callan

.R. Walsh, Esq.

G. Olson J=. Stietzel PNSRC File G. Charnoff, Esq.'.

H. Hennigan Dir, IE (20 copies)

Dir, HIPC (2 copies)

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Fornt No. DIMP 7030 RPT 001-I

i 0 IANA AND MICHIGAN POWER CONPAf'ALD C. COOK NUCLEAR PLANT Iodine S ike Followin Power Transient - Januar 7 1978 This report. is submitted persuant to the requirement of Appendix A Technical Specifications 3.4.8 and 6.9 l. On January 7, 1978 the dose equivalent iodine-131 activity was found out of specification.

At 1400 on January 7, 1978 reactor power on Unit 1 was reduced slowly to 85 power and the reactor tripped from 8X. Power reduction was done for.a scheduled repair/investigation outage.

Routine surveillance at 2100 on January 7, 1978 showed that the dose equivalent iodine-131 had spiked with a maximum value noted of 1.1 p Ci/gram.*

Reactor power had been varied considerably the previous week with no evidence of iodine spiking noted. During power reduction CYCS purifi-cation flow through the mixed bed demineralizer was approximately 75 gpm,

.as it had been for the majority of the week. No degassing operations were associated with this occurrence.

Analysis of the reactor coolant prior to this excursion had shown dose equivalent iodine-131 to range from 9.12 x 10- pCi/g to 2.80 x 10 Ci/g during the period of numerous power changes. Analysis at 0500 on 1-8-78 showed the iodine-13') had decreased to 0.539 pCi/g with dose equivalent iodine-131 at 0.675 gCi/g.. This activity continued to decrease even during power ascension on 1-9-78. Once stable at 100/ dose equiva-lent iodine-131 remained constant at approximately 2.3 x 10-z pCi/g.

Iodine release at this time period is consistant with data reported in Westinghouse Electric Corporation WCAP-8637 "Iodine Behavior under transient conditions in the Pressurized Water, Reactor". Dose equivalent iodine-131 values were in the "Acceptable Operation" portion of Technical Specification Figure 3.4.1 at all times during the transient. Fuel burnup by core region is indicated in the attached table.

• Coolant samples are brought to ambient conditions before counting; therefore, units of qCi/gram and.pCi/cc are interchangeable.

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