ML18219D824

Furnishing Report Pursuant to Appendix a Technical Specification Concerning 1/7/1978 Dose Equivalent Iodine-131 Activity

ML18219D824
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: ML18219D824 (18)

Text

4 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS >

DISTRIBUTION FOR INCOMING MATERIAL 50-3i5 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 04/04/78 NRC IN 5 MI PWR DATE RCVD: 04/24/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR i ENCL i FURNISHING REPT PURSUANT TO APPPENDIX A TECH SPECS 3. 4. 8 5 6. 9. i CONCERNING'N Oi/07/78 THE DOSE EQUIVALENT IODINE-13i ACTIVITY WAS FOUND OUT OF SPECIFICATION... W/ATT SUPPORTING INFO.

Pt ANT NAME: COOK UNIT REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:

+++>+4++>++>+>+>+ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.

(DISTRIBUTION CODE A001)

FOR ACTION: CHIEF SCHWENCER44W/7 ENCL INTERNAL: REG ILES +W/ENCL NRC PDR4+W/ENCL

+>W/2 ENCL OELDw+LTR ONLY HANAUER+4W/ENCL CHECK44W/ENCL E I SENHUT+4W/ENCL SHA0~%W/ENCL BAER4+W/ENCL BUTLER~~W/ENCL EEB+>W/ENCL J COLL INS++W/ENCL J. MCGOUGH4+W/ENCL seoeomae/ ippo~r~ c~L EXTERNAL'R l4OOS 7-o u 80@ L LPDR S jVov4g ST. JOSEPH'I >>W/ENCL TICKS< W/ENCL g p) I +i< ~ t=dC (.

NS IC+>W/ENCL VEb8SM C.ot" c.

ACRS CAT B4+W/16 ENCL gg~gME.p ev& H E.~<

f get aeR cQce

{Zo 0 Qgp~Rl l C.QCL .

DISTRIBUTION:

SIZE: 2P+iOP LTR ~ ENCL ~ CONTROL NBR: 78ii 0 3 THE END

I II 4 I

II I

I I'

~ 1 I H I I

.1 I

1 11

Op

~y><+ /NDIANA 8 NICHIGAI(V PD SER CDII/IPAI(IY DONALD C. COOK NUCLEAR PLANT P.o. Box 468, Bridgman, Michigan 49106 (616) 4654901 April 4, 1978 Operating License DPR-58;; ~1 Docket 8 50-315 rn C7 chic))

A7 Mr. J. G. Keppler, Regional Director Office of Inspection and Enforcement 7g )

U. S. Nuclear Regulatory Commission Cv Region III C')

MC 799 Roosevelt Road B Glen Ellyn, Ill. 60137 CA why

Dear Mr. 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/ power and the reactor tripped from 8%. 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 )1 Ci/gram.*

Reactor power had been varied considerably the previous week with no evidence of iodine spiking noted. During power reduction CVCS 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 3

)1 Ci/g to 2.80 x 10 )1 C)/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 0.675'1Ci/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 ll 4('R 1 0 (gy8 ~o H

f 781150g32 ((

Apr i 1 4, 1978 Mr. 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. V. Shaller Plant Manager ms attachments cc: R. W. Jurgensen J. E. Dolan R. Kilburn R. F. Kroeger R'. J. Vollen, 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)

'i BURNUP FOR PERIOD (%ID/NTU)

CORE REGION 10-'1-77*.to 1-18-78 4 (D) 0.767.2 x 10~

2 (B) 0.2622 x 105 3 (c) 0.2192 x 105

NO. 34D.L412 DIETZGEN GRAPH PAPER EUGENE DIETEGEN CO.

SEMI LOGARITHMIC MADE IN U. 8 A 4 CYCLES X 12 DIVISIONS PER INCH Cb 5 G MQIO hl Q 4 G 5 M SO

'I)

~ ~

0 8 '5

NO. 340 L412 DIETZGEN GRAPH PAPER EUGENE DIETZGEN CO.

MADC IN U. S. A.

SEMI LOGARITHMIC 4 CYCLES X 12 DIVISIONS PER INCH C

~ q C'Much ~

'9 e (o~ \

6 ~ ~

W& 4A t~~

gW

'I y ~ yh P~<

yo) o -- ~ )

t 1

J

~ ~

I H

4 Q

~p

~ ~ -+ ~

-t 0'=

I

.~

~l <<t P

4- ~- I

~I

~ 4

• = -

~

(yi"

~r~~ t~

V I

't ~ f ~4~ a..~

<<k 4

'I J

4 t

~+~ W ~ ~

3

~

D RO rr sw4+ ~ + v tbyw~~kl f ~op 4W

~

~

a-l.

~ ~f 47 /BOO /~ ~-~ tP C~

/~

H e

/JSO pctd

-'-"-/-.4 78;. ]-~- 7g ]-@-7C r-f-7f (-(o.-7f.

(I)"R No.

K)OOÃbklLE) C.CO)aIK Date I- . I i'2)

Time <~0<

HUCLSA,E O'ILAH'r (3) Category A B D E COOKIIMV(OOH RIPIY (4) Classified By ~~~

TO: Plant Manager LER DUE BY /~. (5) AO/I'AEO o.

(6) Item Reported On Dose E@utoalenh (7) Plant Conditions Z-Ial in+be UnA 4 lt C. S. rsol oP Unit ~I Mode ~ Testing '( )Yes ( ~o gpss ficctIton Unit ¹2 Mode Testing ( )yes ( )No (8) Description of Condition 4'100 on I- 7-7S Qs dose e o>oalcnk Z 18 I 4e recc4rr coo(oak sc)sk rn urQs Zond

• r be I. I~wc;/ce 4is cans Allrro/srt, unit I +.P grsri ~8Po ponsv a4 Irfg(

( ) Additional Pages Reported By (9) Corrective Action Taken By (10) Off-Site Notification Made By (Complete Telephone Records 8 Attach)

( ) AEPSC ( )'I 8 M ( ) NRC ( ) Michigan (~ot Applicable (I 'I) Investigation Assigned To I~ < ~~A~ p/rP (12) Investigation Report mX she inu~~g~o~~

I

( ) Additional Pages Completed By (13) Preventive Action Taken 5 ~< iQ75cF/~.

( ) Additional Pages Dept. Head Approval (14) PNSRC Review: Date Comments:

(15) Distribution:

Plant Mgr., Asst. Plant Mgr., QA Supv., PNSRC Secretary, AEPSC Manager Q.A. Dept. Head of Orig. Dept.

Form No. DMP 7030 RPT 001-$

Instru~tioni'or 'Uii

1. Condition Report No. assigned by Q.A. Supervisor,'uty Staff Supervisor, Plant Manager or Assistant Plant Manager.

H

2. Date and Time completed by originator.

3. Category assigned by Plant Manager, Assistant Plant Manager, Operations Supervisor or Duty Staff Supervisor.

I

4. Classified By signature of classifier.

5. AO/AEO No. assigned by Q.A. Supervisor after review of Condition Report by PNSRC.

6. Item Reported On completed by originator.

7. Plant Condition completed by originator.

8. Description of Condition completed by originator.

9. Corrective Action completed by whoever takes the action.

NOTE:

1. Corrective Action is the action taken to 1) restore the system, compon-ent or structure to. a normal condition or 2) to place the plant in a safe and stable condition u'ntil permanent corrective action can be identified and accomplished.

2. If a Job Order was written, provide the number. If a Temporary Change Sheet was initiated, provide the number.

3. If no Corrective Action was required, enter NA and sign it.

10. Off-Site Notification completed by classifier. If not applicable, the classifier should enter his initials in that block.

11. Investigation Assignment completed by the classifier.

12. Investigation Report completed by individual conducting the investigations.

13. Preventive Action Taken completed by individual who completes the preventive action.

NOTE: Preventive action is that action taken in addition to the Corrective Action Taken, to identify the root cause of the condition and the measures taken to prevent recurrence of the condition.

14. PNSRC Review completed by PNSRC.

15. Distribution made by QA Supervisor or Duty Staff Supervisor a) after comple-tion through item 11, b) by QA Supervisor after original is reviewed by PNSRC.

~ ~

IANA AND MICHIGAN POWER COMPA DONALD 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 6.9.1. 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% power and the reactor tripped from 8L. 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 pow'er had been varied considerably the previous week with no evidence of iodine spiking noted. During power reduction CVCS 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 z p 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 pCi/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-~ 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 pCi/gram and qCi/cc are interchangeable.

BURNUP FOR PERIOD (MllD/tlTU)

CORE REGION 10'-1-77 to 1-18-78 4 (D) 0.7672 x 104 2 (B) 0.2622 x 105 3 (c) 0.2192 x 106

~ ~ i L

a

~ ~ ~ I

~ I ~ I 0 I I I I

/0 ~

B v

a o

zA Q Ol N

4l z 0

X<

>Z a

~>

zo 0

8 L v II.

L o Z

II o II Q g III zI a2

~ III

>aa 0 N

NEx

~~tA. 4I

~ I

~ J a o o

a Z 0 B

~ I ~

~ I ~ I

4 I I I

(O Q

8 v

0 0

zi 0N ol I

~z 0

~M 24 4I Cl I

I (g I) 9 8

IZ Z

0 2

Z I4 0 I4 0 E III2 2Z0

~ I-0~QI I

4I 0 0 0

0 JN nXx III CI ~ ~ ~ ~

4I

~ J 0

0 0 0 !0 ~IQ 8

V k ~

C~

yVI

I, I t

4 y$ -