ML19290B891
| ML19290B891 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/30/1978 |
| From: | INDIANA MICHIGAN POWER CO. |
| To: | |
| Shared Package | |
| ML17174B224 | List: |
| References | |
| FOIA-79-488 NUDOCS 7912140354 | |
| Download: ML19290B891 (14) | |
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I. INTRODUCTION This report discusses and summarizes the radioactive discharges from both Unit I and II of Donald C. Cook Nuclear Plant during the first six months of calendar year 1978. The format presented in Section 5.4.lB of " Appendix B Technical Specifications" -
preparing this document. for the aforementioned units has been followed in 17, Unit I started 1978 operating at 100% power. On January the unit was shutdown from 100% due to high conductivity in steam generators caused by acid getting into the condensate sys-tem while regenerating resin in the make-up plant. .
returned to service on January 19, 1978. During the Unit month I was of February, Unit I operated in the deicing mode, and for a period of 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> lost reserve power when an itsulator flashed over and ,
tripped breakers causing an unscheduled outage. No other major -
unscheduled outages occurred.
On April 6, 1978 during this reporting period, Unit I was Outage. removed from service to conduct the Cycle II/III Refueling -
to full service on Junebegan This outage on April 7th, and the unit was returned 24, 1978.
issued on December 23,The Unit II Facility Operating License, No. DPR-74, was 1977. Initial fuel loading commenced on December 26 and was completed on January 2, 1978. Post core loading tests were conducted throughout the month of February and initial criticality was achieved on March 10, 1978, after which the turbine / -
generator system was paralleled to the system on the same date.
On " arch 29, the Unit was made suberitical. Investi-gation condensers.
of condenser vacuum problems revealed failed tubes in "A" -
dump valves. Damage was caused by steam impingement from steam In preparation for a unit start-up, the steam leads were pressurized.
This outage continued until April 1, 1978.
service.
On April 19th, the Unit was once again removed from Cold shutdown was brought about for various maintenance .
and modification work.
the end of the month. Unit II remained out of service until the Another unplanned outage started ?!ay 19, 1978 due to .
an unidentified reactor coolant system leakage in excess of 1 gpm.
It was found that the failed fuel detector safety valve was leak-ing.
gpm toIsolating .158 gpm.the fuel detector reduced the leakage from 3.26 The unit was then kept out of service to perform n b;
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moisture separator reheater modifications and remained as such (
until June 1, 1978.
l The next major forced outage occurred in the month of I June, after severa,1 reoccurring low vacuum trips due to an im-pulse pressure effect on the low vacuum trip devices from an alternate drain line discharging on the immediate vicinity of the condenser vacuum sensing lines. The sensing valves were re- -
located to the opposite side of the condenser. Following the outage for moist ure separator reheater modifications, power ,
ascension testing continued and the unit attained 97% power.
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6 1578 178 .
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II.
RADIOACTIVE RELEASES from both Units I and II have been handled as joint respons rather than independently for the first six months of 1978.
' Appendix A presents this information in accordance with th e format cited in Section 5.41of Appendix B, Environmental Technical Speci-fication.
As in reports preceeding this one, the effluents were well within the limits set forth in Appendix B Environmental Tech Specification for to 10 CFR Part 50. the D.C. Cook Nuclear Plant and Appendix I l
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1 1578 179 :
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APPEttDIX A RADI0 ACTIVE RELEASE DATA .
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3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1978 LIQUID EFFLUENTS BATCH MODE Nuclides Released Unit 1_st Quarter _. ... ._. 2nd Quarter Stronium - 89 Ci <l.184 E-4 <l.911 E-4 Stronium - 90 Ci <l.018 E-4 <l.643 E-4
, Cesium - 134 Ci 1.229 E-1 1.251 E-1 Cesium - 137 Ci 1.395 E-1 1.331 E-1
> Iodine - 131 Ci 1.163 E-2 3.234 E-3 i
= -
I -
Cobalt - 58 Ci 5.594 E-2 1.038 E-1 Cobalt - 60 Ci 8.651 E-2 8.238 E-2 --
Iron - 59 Ci <l.626 E-4 7.742 E-4
, Zinc - 65 Ci <l.018 E-3 <l.382 E-3 Manganese - 54 Ci 1.573 E-2 1.094 E-2 -
, Chromium - 51 Ci 3.785 E-3 1.011 E-2
?_
Zirconium-niobium - 95 Ci 4.164 E-3 4.917 E-3 f
Holybolenum - 99 Ci <7.482 E-6 <l.207 E-5 Technetium - 99m Ci <5.628 E-5 <9.081 E-5 -
Barium-lanthanum - 140 Ci <3.468 E-4 <5.595 E-4
- Cerium - 141 Ci <l.031 E-4 <l.664 E-4 -
r _
Cesium - 136 Ci 5.635 E-4 7.840 E-4
, Sodium - 2 Ci 2.393 E-3 7.835 E-3 ~
Iodine - 1 3 Ci 4.436 E-4 1.242 E-4 f Cobalt - 57 Ci 7.028 E-5 1.862 E-4 -
'lirconium - 97 Ci 3.811 E-4 7.196 E-5 Silver - 110m Ci 1.603 E-4 1.557 E-3 Sb '-124 ' ~ Ci < 4.782 E-5 1.707 E-2 5 Ci < l.535 E-4 8.074 E-4 1578 181 A-1
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1978 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES
. Unit Est. Total 1st Quarter 2nd Quarter Error, %
FISSION AND ACTIVATION PRODUCTS Total release (not including tritium, gases, alpha) Ci 4.443 E-1 5.028 E-1 3.03 Average diluted concentration during period pCi/ml 2.359 E-8 2.017 E-8
. Percent of aoolicable limit % .338 .148
. TRITIUM
. Total release Ci 84.279 208.659 .260
. Average diluted concentration during period pCi/ml~
1.182 E-6 2.212 E-6 -
. Percent of acolicable limit % .039 .074 DISSOLVED AND ENTRAINED GASES Total release Ci 6.882 E-1 1.794 E-2
. Average diluted concentration -
.. during period 'uCi/ml 3.654* E-8 7.198* E-10 t Percent of aoolicable limit %
._ GROSS ALPHA RADIOACTIVITY Total release Ci <2.930~E-3 <9.577 E-3
- VOLUME OF WASTE RELEASED (PRIOR liters 3.2529 E 6 5.2490 E 6 2.00 TO DILUTION) l'iters- 1.8833 E 10 3.48
~
VOLUME OF DILUTION WATER USED 2.4919 E10 .
DURING PERIOD
% applicable limit 1578 182 A-2
EFFLUENT AND WASTE DISPOSAL SElilANNUAL REPDRT - 1978 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Units 1st ws N Eh t 1 FISSION AND ACTIVATION GASES Total release Ci 9.986 E 3 2.520 E 2 1.4 Average release rate for period u'C'i /Sec
~
1.284 E 3 3.205 E 1 Percent of technical specification limit % 6.15 0.19
_ 10 DINES Total iodine - 131 Ci 2.964 E-4 9.846 E-3 13.9 Average release rate for period ufi/Sec 3.812 E-5 1.25 E-3
. Percent of technical specification
_ limit : 0.007 .225 t_PARTICULATES Particulates with half-lives > 8 days Ci <l.771 E-3 9.637 E-2 18.0
. Average release rate for period uCi/ Sic <2.278 E-4 5.153 E-9 Percent of technical specification 9.28 E-7 limit %
L_3ross aloha raaloactivity Ci <3.160 E-12 < 3.16 E-12 L IRITIUM Total release Ci 6.840 E-1 1.312 E 1 2.0
- Average release 44- rate for period ECi'/S'e~c 8.796 E-2 1.669 E O Percent of technical specification -
limit .67 12.8 4
s 15'l8 1B3 A-3 J
i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL RC90RT - 1978 GASEOUS EFFLUENTS - ELEVATED Rr. LEASE CONTINUOUS MODE BATCH MODE Nuclides Released Uni t Ist Quarter 2 rd Quarter 1st Quarter 2rd O e s _
FISSION GASES Krypton - 85 Ci 6.979 E 1 5.462 E 1
- Krypton - 85m Ci 7.430 E-1 7.042 E-1 -
- Krypton - 87 Ci 1.221 E-1
! Krypton - 88 Ci 1.364 E O j Xenon - 133 Ci 4.173 E 2 7.340 E1 9.384 E 3 1.156 E 2 (Xenon - 135 Ci 4.009 E O 3.671 E 1 5.439 E O
- Xenon - 135m Ci
- Xenon - 138 Ci Ci 7.388 E 1 7.141 E-1
{ Xenon - 133m -
1 0
Total for Deniod Ci 4.213 E 2 7.340 E1 9.565 E3 1.786 E 2
.i 4 .
IIODINES Iodine - 131 Ci 2.122 E-4 7.850 E-4 8.424 E-5 9.061 E-3 .
' Iodine - 133 Ci 2.664 E-5 1.387 E-5 1.033 E-5
-Iodine - 135 Ci h:
htal for oeriod Ci 2.389 E-4 7.989 E-4 8.424 E-5 9.071 E-3 fPARTICULATES 1
Stratium - 89 Ci rStratium I - 90 Ci Cesium - 134 Ci 8.621 E-10 Msium-137 Ci 5.316 E-6*
Iarium-lanthanum - 140 Ci fobalt-58 Ci 4.596 E-6 4.325 E-2 balt - 60 Ci 1.505 E-5 4.087 E-2
[teshm -138_ '
l.706 E-6 3.196 E-4
( m - 54 2.023 E-3 m - 31
( .
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- 95 4.883 E-3 8.010 E-5
-1 15 78 184 :NE E $
m - 88 2.137 E-2
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. A-4
EFFLUENT Af4D WASTE DISPOSAL SEMIANilUAL REPORT - 1978 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS -
A. Solid waste shipped offsite for burial or disposal .
, 1. Type of waste Unit 6-month Est. Total period Error, %
, a. Spent resins, filter sludges, m3 6.113 E 2 1 evaporator bottoms, etc. Ci 1.398 E 2 4
- b. Dry compressible waste, contaminated m3 2.031 E 2 1 equipment, etc. Ci 2.026 E 1 200
- c. Irradiated components, control rods, m3 etc. Ci _.
- d. Other m3 ,
4 Ci __
- 2. Estimate of major nuclide composition
., a. CS-137 % 55.5 a CS-134 % 40.4
+
CO-58 & 60 % 4.0
) b. 00-60 % 85.0
) 00-58 % 15.0 __
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- 3. Solid Waste Disposition
~
Number of Shioments Mode of Transoortation Destination 1
' M Sheffield, Ill M Bannell, S. C.
A-5 i578 183 ;
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= .
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1978 MDA GASEOUS EFFLUENTS - ELEVATED RELEASE 4
CONTINUOUS MODE 8ATCH MODE
~
Nuclides Released Unit ist Quarter 2nd Quarter 1st Guarter i 2nd Quarte,r ,_
FISSION GASES Krypton - 85 Ci <8.119 E3 <9.064 E3 <5.975 E1 <2.870 E O Krypton - 85m Ci <2.553 E1 <2.850 E1 <l.519 E-1 <7.297 E-3 Krypton - 87 Ci <3.771 E1 <4.210 E1 <2.775 E-1 <l.333 E-2 Krypton - 88 Ci <5.429 E1 <6.061 E1 <3.994 E-1 <l.919 E-2 Xenon - 133 Ci <6.407 E1 <7.153 E1 <4.714 E-1 <2.265 E-2 Xenon - 135 Ci <l.629 E2 <l.819 E2 <l.198 EO <5.758 E-2 Xenon - 135m Ci <6.114 E2 <6.826 E2 <4.498 EO <2.161 E-1 Xenon - 138 Ci <3.169 E2 <3.538 E2 <2.332 EO <l.120 E-1 -
Xenon - 133m Ci <l.340 E2 <1.496 E2 <9.861 E-1 <4.737 E-2
_ Total for ceriod Ci <9.526 E3 <l.064 E4 <7.006 E1 <3.366 E O
,,,10 DINES
. Iodine - 131 Ci <4.174 E-6 <4.660 E-6 <l.807 E-4 <9.429 E-6 Iodine - 133 Ci <6.153 E-6 <6.869 E-6 <2.663 E-4 <1.390 E-5 ,
ladine - 135 Ci <l.141 E-5 <l.274 E-5 <4.915 E-4 <2.565 E-5 lotal for oeriod Ci <2.174 E-5 <2.427 E-5 <9.385 E-4 <4.898 E-5 l
E.$TICULATES s
}Stratium - 89 Ci <3.084 E-6 <3.443 E-6
}Stratium - 90 Ci <l.066 E-6 <l.190 E-6
- Cesium - l$a Ci <6.231 E-6 <6.956 E-6 <2.697 E-4 <l.408 E-5 *
' Cesium - 137 Ci <6.060 E-6 <6.765 E-6 <2.623 E-4 <l.369 E-5 Barium-lanthanum - 140 Ci <2.762 E-5 <3.084 E-5 <l.195 E-3 <6.238 E-5
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RADIOACTIVE EFFLUENT RELEASE REPORT INDIANA & MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT UNIT NOS.1 & 2 '
BRIDGMAN, MICHIGAN July 1, 1978 through December 31, 1978 i\
y 4x d
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'k, 1573 190 -
, Docket Nos. 50-315 & 50-316 License Nos. OPR-58 & DPR-74
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