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{{#Wiki_filter:~0 f P/~/~+REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>DISTRIBUTION FOR INCQmING MATERIAL 50-3i5 ORG: SHALLER D V IN 8.MI PWR REC: KEPPLER J G NRC DOCTYPE: LETTER NQTARIZED:
{{#Wiki_filter:~                         0 fP/~/~+
NO ,
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>
DISTRIBUTION FOR INCQmING MATERIAL                                         50-3i5 REC:    KEPPLER  J G                          ORG:       SHALLER D V                   DOCDATE: 04/04/78 NRC                                            IN   8. MI PWR                     DATE RCVD: 04/1 1/78 DOCTYPE: LETTER         NQTARIZED: NO                                                     COPIES RECEIVED


==SUBJECT:==
==SUBJECT:==
LICENSEE EVENT REPT (RO 50-315l00-000>
LTR 1        ENCL i LICENSEE EVENT REPT (RO 50-315l00-000> ON 03/07/78 CONCERNING UNIT 1 REACTOR TRIPPED FRON i00/ P4JR AND DOSE EQUIVALENT IODINE-131 ACTIVITY IN UNIT                              i REACTOR COOLANT SYSTEM WAS FOUND OUT OF SPECIFICATION... W/ATT SUPPORTING INFO.
ON 03/07/78 CONCERNING TRIPPED FRON i00/P4JR AND DOSE EQUIVALENT IODINE-131 ACTIVITY REACTOR COOLANT SYSTEM WAS FOUND OUT OF SPECIFICATION...
PLANT NAME: COOK UNIT         1 4+w4+++4+w+~4Hs~++ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS REVIEWER DISTRIBUTOR INITIAL: X JH INITIAL:  ~
W/ATT INFO.DOCDATE: 04/04/78 DATE RCVD: 04/1 1/78 COPIES RECEIVED LTR 1 ENCL i UNIT 1 REACTOR IN UNIT i SUPPORTING PLANT NAME: COOK-UNIT 1 REVIEWER INITIAL: X JH DISTRIBUTOR INITIAL:~4+w4+++4+w+~4Hs~++
INCIDENT REPORTS                                                                                         N (DISTRlBUTION CODE A002>
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRlBUTION CODE A002>N FOR ACTION: INTERNAL: BR CHIE ENCER++W/4 ENCL REG FILE++W/ENC' SCHROEDER/I PPOL I TQ4H~W/ENCL NOVAK/CHECK+~W/ENCL'NIGHT++W/ENCL HANAUER+44J/ENCL E ISENHUT++W/ENCL SHAQ~~~W/ENCL KREGER/J.COLLINS4~+W/ENCL
FOR ACTION:       BR CHIE                       ENCER++W/4 ENCL INTERNAL:          REG FILE++W/ENC'                                 NRC PDR+wW/ENCL MIPC~~W/3 ENCL SCHROEDER/I PPOL I TQ4H~W/ENCL                    HOUSTON+4W/ENCL NOVAK/CHECK+~W/ENCL'NIGHT++W/ENCL EEB++W/ENCL BUTLER4~+W/ENCL HANAUER+44J/ENCL                                 TEDESCO+4W/ENCL E ISENHUT++W/ENCL                                 BAER~~W/ENCL SHAQ~~~W/ENCL                                     VOt LNER/BUNCH++W/ENCL KREGER/J.              COLLINS4~+W/ENCL          ROSA~~W/ENCL
'K SEYFR IT/IE~~I J/ENCL NRC PDR+wW/ENCL MIPC~~W/3 ENCL HOUSTON+4W/ENCL EEB++W/ENCL BUTLER4~+W/ENCL TEDESCO+4W/ENCL BAER~~W/ENCL VOt LNER/BUNCH++W/ENCL ROSA~~W/ENCL EXTERNAL: LPDR~S ST.JOSEPH, NI++W/ENCL TIC4~4W/ENCL NSIC~~~W/ENCL ACRS CAT 8~~~[Jli 6 ENCL COPIES NOT SUB'.'JITTED PER REGULATORY GUIDE 10~1 DISTRIBUTION:
                        'K  SEYFR      IT/IE~~IJ/ENCL EXTERNAL:         LPDR~S ST. JOSEPH, NI++W/ENCL TIC4~4W/ENCL NSIC~~~W/ENCL ACRS         CAT 8~~~[ Jli 6 ENCL COPIES NOT SUB'.'JITTED PER REGULATORY GUIDE 10 ~ 1 DISTRIBUTION:       LTR 45             ENCL 45                                 CONTROL NBR:        7810~001)
LTR 45 ENCL 45 S I ZE: 2P+iP+5P CONTROL NBR: 7810~001)THE END%%%0%4%%%%%%%%%%%%%%%%%%%%%5%%%  
S I ZE: 2P+iP+5P THE END %%%0%4%%%%%%%%%%%%%%%%%%%%%5%%%


RIlll.lWIN'f IWI'KQ in r'I~~cn r~~n Dl n fh CO April 4, 1978 Operating License DPR-58 Docket 8 50-315 etc~r'Alee~y IM/ANA 8 NICHIGAN POKER CONPANY DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 (616)465-5901 fan)cn~~(~CA Pl cn Cn~CU MC ED Nr.J.G.Keppler, Regional Director Office of Inspection and Enforcement U.S.Nuclear Regulatory Corrmission Region III 799 Roosevelt Road Glen Ellyn, Il 60137  
etc~
r'Alee~
RIlll.lWIN'fIWI'KQ in         fan)
IM/ANA8 NICHIGANPOKER CONPANY                                                  cn~
y DONALD C. COOK NUCLEAR PLANT                                   r 'I    ~(
                                                                                        ~CA P.O. Box 458, Bridgman, Michigan 49106 (616) 465-5901                                 ~ ~cn      Pl Cn cn r~ ~n Dl
                                                                                        ~CU MC n
fh          ED April 4, 1978            CO Operating License DPR-58 Docket 8 50-315 Nr. J. G. Keppler, Regional Director Office of Inspection       and Enforcement U. S. Nuclear Regulatory Corrmission Region   III 799 Roosevelt Road Glen Ellyn,   Il   60137


==Dear Nr.Keppler:==
==Dear Nr. Keppler:==
This report is submitted persuant to the requirement of Appendix A Technical Specification 3.4.8 and 6.9.1.On t1arch 7, 1978, the dose equivalent iodine-131 activity in Unit 1 reactor coolant system was found out of specification.
 
At 1003 on tiarch 7, 1978 Unit 1 reactor tripped from 100K 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.)1Ci/cc, f1aximum 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.
This report is submitted persuant to the requirement of Appendix A Technical Specification 3.4.8 and 6.9.1. On t1arch 7, 1978, the dose equivalent iodine-131 activity in Unit 1 reactor coolant system was found out of specification.
No additional spi king was noted during the subsequent reactor startup.Ho 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 7e 10200 P C t J C' Apri 1 4, 1978 Mr.J.G.Keppler Page Two Specification Figure 3.4.1 at all times during the transient.
At 1003 on tiarch 7, 1978 Unit 1 reactor tripped from 100K power.
Fuel burnup by core region and all additional data is indicated in the attached table/graphs.
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.)1Ci/cc, f1aximum 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 spi king was noted during the subsequent reactor startup. Ho degassing operations were associated with this event.
*Coolant samples are brought to ambient conditions prior to counting, therefore, units of pCi/g and pCi/cc are considered interchangeable.
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 7e 10200
Very truly yours,+a~D.V.Shaller Plant Manager attachments cc: R.W.Jurgensen J.E.Dolan R: Kilburn R.F-..Kr'oeger 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 (ZO copies)Dir, MIPC (2 copies)  
 
~MARCH 7, 1978 UNIT NO.1 CYCLE NO.2 Fuel Burnup by Cor e Reoi on REGION NO.BURNUP FOR PERIOD (teDr MTU)CUMULATIVE BURNUP (MHD/MTU)ENERGY FOR PERIOD (BTU)CUMULATIVE ENERGY (BTU)0.1871E+04 0.1799E+04 0.2053E+04 0.9543E+04 0.2802E+05 0.2397E+05 0.4267E+13 0'290E+13 0.4867E+13 0.2176E+14 0.668lf+14 0,5685E+14 CORE TOTAL 0.1908E+04 0.2067E+05 0.1342E+14 0.1454E+15  
P C
'/
t J C '
NO.34l L3IO DIETZGEN GRAPH PAPER j SEMI LOGARITHMIC 3 CYCI ES X I O DIVISIONS PER INCH DIETZGEN CORPORATION NAOC IH U~,A (3 Q 5 Ul 8 4 5 50 j NG.341 L3IG DIETZGEN GRAPH PAPER SEMI~LOGARITHMIC 3 CTCLES X IO DIVISIONS PER INCH PICTXGEN CORPORATION
 
$4ADC IN U,S,A, f)Vl 0 0 W Q 4 Ul 0I 4 0I Q 0 0 0 0 0 0 O 0 0  
Apri 1 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.
/4 j NO.34I-L310 DIETZDEN GRAPH PAPER (Q SEMI LOGARITHMIC 3 CYCLES X I 0 DIVISIONS PER INCH DIETZDEN CORPORATION HAOC IN U~,A 0-VI 0 0 Cv a p 4 I L'4 0 4 0 0 0 NO.34 I L3IO DIETZGEN GRAPH PAPER ('EMI LOGARITHMIC 3 CYCLES X 10 DIVISIONS PER INCH DIETZGCN CORPORATION NAQC IH U S,A I)Ul 0I 40 (II O 1 NO.341.L310 DIETZGEN GRAPH PAPER I SEMI LOGARITHMIC 3 CYCLES X 10 DIVISIONS PER INCH DIETZOEN CORPORATION NAOC IH U~*gI e w m o 0 0 5 4 5 9}}
* Coolant     samples   are brought to ambient conditions prior to counting, therefore, units of pCi/g       and pCi/cc are considered interchangeable.
Very truly yours,
+a~ D. V. Shaller Plant Manager attachments cc:   R. W. Jurgensen J. E. Dolan R: Kilburn R. F-.. Kr'oeger 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 (ZO copies)
Dir,   MIPC (2 copies)
 
                                              ~   MARCH 7, 1978 UNIT NO. 1 CYCLE NO. 2 Fuel Burnup by Cor e Reoi on REGION NO.     BURNUP        CUMULATIVE  ENERGY          CUMULATIVE FOR PERIOD      BURNUP   FOR PERIOD         ENERGY (teDr MTU)   (MHD/MTU)     (BTU)           (BTU) 0.1871E+04   0.9543E+04 0.4267E+13      0.2176E+14 0.1799E+04    0.2802E+05 0 '290E+13       0.668lf+14 0.2053E+04    0.2397E+05  0.4867E+13      0,5685E+14 CORE TOTAL     0.1908E+04   0.2067E+05 0.1342E+14       0.1454E+15
 
/
 
NO. 34l L3IO   DIETZGEN GRAPH PAPER SEMI LOGARITHMIC j DIETZGEN CORPORATION NAOC IH U ~,A (3
3 CYCI ES X I O DIVISIONS PER INCH Q 5 Ul 8 4 5 50
 
j NG. 341 L3IG DIETZGEN GRAPH SEMI ~ LOGARITHMIC PAPER 3 CTCLES X IO DIVISIONS PER INCH PICTXGEN CORPORATION
                                                $ 4ADC IN U,S,A, f)
W Q 4 Ul 0I 4 0I Q 0 Vl 0
0 0
0 0
0 0
O 0
0
 
/4 j NO. 34I-L310 DIETZDEN GRAPH PAPER SEMI LOGARITHMIC 3 CYCLES X I 0 DIVISIONS PER INCH (Q DIETZDEN CORPORATION HAOC IN U ~,A 0-VI 0
0 Cv a
p   4 I
L' 4
0 4
0 0
0
 
('EMI NO. 34 I L3IO DIETZGEN GRAPH PAPER LOGARITHMIC 3 CYCLES X 10 DIVISIONS PER INCH DIETZGCN CORPORATION NAQC IH U S,A I
                                                                )
Ul   0I 4 0 (II O
 
1 NO. 341.L310 DIETZGEN GRAPH PAPER   DIETZOEN CORPORATION I             SEMI LOGARITHMIC                 NAOC IH U ~
* 3 CYCLES X 10 DIVISIONS PER INCH gI                 0 e   w m o 0                       5 4   5 9}}

Latest revision as of 20:20, 2 February 2020

Licensee Event Report RO 50-315/00-000 Re Dose Equivalent Iodine-131 Activity in Reactor Coolant System
ML18219C205
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 04/04/1978
From: Shaller D
Indiana Michigan Power Co
To: James Keppler
NRC/RGN-III
References
Download: ML18219C205 (13)
v • d • e


Text

~ 0 fP/~/~+

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>

DISTRIBUTION FOR INCQmING MATERIAL 50-3i5 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 04/04/78 NRC IN 8. MI PWR DATE RCVD: 04/1 1/78 DOCTYPE: LETTER NQTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL i LICENSEE EVENT REPT (RO 50-315l00-000> ON 03/07/78 CONCERNING UNIT 1 REACTOR TRIPPED FRON i00/ P4JR AND DOSE EQUIVALENT IODINE-131 ACTIVITY IN UNIT i REACTOR COOLANT SYSTEM WAS FOUND OUT OF SPECIFICATION... W/ATT SUPPORTING INFO.

PLANT NAME: COOK UNIT 1 4+w4+++4+w+~4Hs~++ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS REVIEWER DISTRIBUTOR INITIAL: X JH INITIAL: ~

INCIDENT REPORTS N (DISTRlBUTION CODE A002>

FOR ACTION: BR CHIE ENCER++W/4 ENCL INTERNAL: REG FILE++W/ENC' NRC PDR+wW/ENCL MIPC~~W/3 ENCL SCHROEDER/I PPOL I TQ4H~W/ENCL HOUSTON+4W/ENCL NOVAK/CHECK+~W/ENCL'NIGHT++W/ENCL EEB++W/ENCL BUTLER4~+W/ENCL HANAUER+44J/ENCL TEDESCO+4W/ENCL E ISENHUT++W/ENCL BAER~~W/ENCL SHAQ~~~W/ENCL VOt LNER/BUNCH++W/ENCL KREGER/J. COLLINS4~+W/ENCL ROSA~~W/ENCL

'K SEYFR IT/IE~~IJ/ENCL EXTERNAL: LPDR~S ST. JOSEPH, NI++W/ENCL TIC4~4W/ENCL NSIC~~~W/ENCL ACRS CAT 8~~~[ Jli 6 ENCL COPIES NOT SUB'.'JITTED PER REGULATORY GUIDE 10 ~ 1 DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 7810~001)

S I ZE: 2P+iP+5P THE END %%%0%4%%%%%%%%%%%%%%%%%%%%%5%%%

etc~

r'Alee~

RIlll.lWIN'fIWI'KQ in fan)

IM/ANA8 NICHIGANPOKER CONPANY cn~

y DONALD C. COOK NUCLEAR PLANT r 'I ~(

~CA P.O. Box 458, Bridgman, Michigan 49106 (616) 465-5901 ~ ~cn Pl Cn cn r~ ~n Dl

~CU MC n

fh ED April 4, 1978 CO Operating License DPR-58 Docket 8 50-315 Nr. J. G. Keppler, Regional Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Corrmission Region III 799 Roosevelt Road Glen Ellyn, Il 60137

Dear Nr. Keppler:

This report is submitted persuant to the requirement of Appendix A Technical Specification 3.4.8 and 6.9.1. On t1arch 7, 1978, the dose equivalent iodine-131 activity in Unit 1 reactor coolant system was found out of specification.

At 1003 on tiarch 7, 1978 Unit 1 reactor tripped from 100K 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.)1Ci/cc, f1aximum 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 spi king was noted during the subsequent reactor startup. Ho 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 7e 10200

P C

t J C '

Apri 1 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,

+a~ D. V. Shaller Plant Manager attachments cc: R. W. Jurgensen J. E. Dolan R: Kilburn R. F-.. Kr'oeger 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 (ZO copies)

Dir, MIPC (2 copies)

~ MARCH 7, 1978 UNIT NO. 1 CYCLE NO. 2 Fuel Burnup by Cor e Reoi on REGION NO. BURNUP CUMULATIVE ENERGY CUMULATIVE FOR PERIOD BURNUP FOR PERIOD ENERGY (teDr MTU) (MHD/MTU) (BTU) (BTU) 0.1871E+04 0.9543E+04 0.4267E+13 0.2176E+14 0.1799E+04 0.2802E+05 0 '290E+13 0.668lf+14 0.2053E+04 0.2397E+05 0.4867E+13 0,5685E+14 CORE TOTAL 0.1908E+04 0.2067E+05 0.1342E+14 0.1454E+15

/

NO. 34l L3IO DIETZGEN GRAPH PAPER SEMI LOGARITHMIC j DIETZGEN CORPORATION NAOC IH U ~,A (3

3 CYCI ES X I O DIVISIONS PER INCH Q 5 Ul 8 4 5 50

j NG. 341 L3IG DIETZGEN GRAPH SEMI ~ LOGARITHMIC PAPER 3 CTCLES X IO DIVISIONS PER INCH PICTXGEN CORPORATION

$ 4ADC IN U,S,A, f)

W Q 4 Ul 0I 4 0I Q 0 Vl 0

0 0

0 0

0 0

O 0

0

/4 j NO. 34I-L310 DIETZDEN GRAPH PAPER SEMI LOGARITHMIC 3 CYCLES X I 0 DIVISIONS PER INCH (Q DIETZDEN CORPORATION HAOC IN U ~,A 0-VI 0

0 Cv a

p 4 I

L' 4

0 4

0 0

0

('EMI NO. 34 I L3IO DIETZGEN GRAPH PAPER LOGARITHMIC 3 CYCLES X 10 DIVISIONS PER INCH DIETZGCN CORPORATION NAQC IH U S,A I

)

Ul 0I 4 0 (II O

1 NO. 341.L310 DIETZGEN GRAPH PAPER DIETZOEN CORPORATION I SEMI LOGARITHMIC NAOC IH U ~

  • 3 CYCLES X 10 DIVISIONS PER INCH gI 0 e w m o 0 5 4 5 9
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