ML20041F279
| ML20041F279 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 03/08/1982 |
| From: | Maine Yankee |
| To: | |
| Shared Package | |
| ML20041F271 | List: |
| References | |
| NUDOCS 8203160355 | |
| Download: ML20041F279 (9) | |
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i MAINE YANKEE ATOMIC POWER COMPANY i
. EFFLUENT AND WASTE DISPOSAL i
SEMI-ANNUAL REPORT i.
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JULY - DECEMBER, 1981 I
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PDR ADOCK 05000309' PDR N,. -,-...-..R
O EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT OULY - DECEMBER 1981 FACILITY: MAINE YANKEE ATOMIC POWER COMPANY LICENSEE: MAINE YANKEE ATOMIC POWER COMPANY 1.
Regulatory Limits a.
Fission and activation gases:
10 CFR 20; Paragraph 20.106 b.
c.
Particulates, half lives 8 days d.
Liquid effluents:
2.
Maximum Permissible Concentrations a.
Fission and actuation gases:
10 CFR 20; App. B. Table 2 Col.1 b.
c.
Particulates, half lives 8 days d.
Liquid effluents:
3.
Average Energy - Not Applicable 4.
Measurement and Approximations of Radioactivity a.
Fission and activation gases:
Continuous discharge - vent stack samples are analyzed monthly and the levels of activities determined are assumed to hold for the period between samples.
The continuous vent stack monitor reading is used as a basis for increasing periodic sample frequency. Air ejector is sampled monthly and on any increase in continuous air ejector monitor reading.
Batch discharges - direct measurement of waste gas holdup drums are made before discharge. Containment vents and purges are analyzed by direct measurement of the containment atmosphere at periodic intervals during the discharge.
b.
Continuous monitoring of primary vent stack lodines are made by weekly measurements of an in-line charcoal filter.
Batch discharges - direct measurement of waste gas holdup drums before discharge.
c.
Particulates - continuous monitoring of primary vent stack is made by weekly measurement of an in-line particulate filter.
Batch discharges - direct measurement of waste gas holdup drums before discharge.
. d.
Liquid Effluents Weekly sample of secondary systems liquid effluents for gross Beta-gamma, alpha, tritium, dissolved gases and gamma emitting isotopes each batch t
release.
Composite samples are made of secondary and primary systems liquid effluents for a quarterly analysis of strontium 90 and 89.
5.
Batch Release a.
Liquid 1.
Number 7f releases:
96 2.
fetal time for batch releases:
393 hrs 2 min 3.
Maxirca time for batch releases:
11 hrs 36 min 4.
Average time for batch releases:
4 hrs 6 min 5.
Minimum time for batch releases:
55 min 6.
Average stream flow during periods of release of effluent into a flowing stream:
7.
Maximum gross release rate (uci/ml) 4.15E-8 b.
Caseous 1.
Number of batch. releases:
17 2.
Total time period for batch releases:
174 hrs 35 min 3.
Maximum time period for a batch release:
72 hrs O min 4.
Average time period for a batch release:
10 hrs 16 min 5.
Minimum time for a batch release:
20 min 6.
Maximum gross release rate (uci/sec):
1.06E+3 6.
Abnormal Releases f
a.
Liquid There were no abnormal liquiu releases during this reporting period.
b.
Gaseous During an investigation of a change in slope of the containment weight of i
air value on August 14, 1981, it was discovered that the box containing the containment APD particulate paper had weld cracks.
This event resulted in an unplanned radioactive release through the primary auxiliary building vent system particulate and charcoal filters into the primary l
vent stack.
Total specific nuclide activity released was 2.48E-2 C1.
This activity, as well as that of the individual nuclides, is reported in Tables lA and 1B of this report.
c.
The following table is not attached since there was no applicable release
[
during this reporting period.
Table IC - Gaseous Effluents, Ground Level Releases.
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, PELEASE OF WASTE GAS STORAGE DRINS BEFORE 60-DAY HOLDUP PERIOD Technical Specification 3.17B3 requires a special effluent report should the average holdup time of waste gas be less than 60 days.
The following drum had a holdup time of less than 60 days during normal operations in the 2nd half of 1981.
(In days)
Release No.
Decay Drum Date Isolated Date Released Holdup Time Cu.Ft.
586 C
7/7/81 8/26/81 49 928 The average holdup time for the second half of 1981, of all decay drums during-normal operation, was 66 days.
Early release of the decay drum by Permit No. 586 was required by the needed backup storage space.
This drum contained low activity gases resulting from startup following. the refueling shutdown.
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TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 GASEOUS EFFLUENTS-SWMATION OF ALL RELEASES
===__
_ - - - - - - - - - - - - - = = = _ _ _ _ _ _ - - - - - - - - - - - - - -
3RD ATH EST.
UNIT QUARTER QUARTER TOTAL
.BRROR %
. - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ = = _ _ _ _ _ = - - - - - = = = _ _ _.--- _
-===____=--
A.
FISSION & ACTIVATION GASES
_= ---- _
_ _ - - - = _
=====------
1.
Total Release CI 9.47E+01
- 4. 39E-04 1.55E+01 2.
Average Release Rate for Period UCI/SEC 1.20E+01 5.58E-05
=-
3.
% of Tech. Specification Limit 1.04E-01 2.57E-06
___=
Y
==_
_-._,----_---===--- =___= --==--
B.
10 DINES
--===______ _----------,----
- = --------------- --
=_
1.
Total Iodine-131 CI 1.27E-04
- 1. 32E-04 1.57E+01 2.
Average Release. Rate for Period UCI/SEC 1.61E-05 1.67E-05
=-- = --
3.
% of Tech. Specification Limit 4.19E-04
- 4. 34E-04
_ -------=----- --------
- = = = _ _
__-------==- --==------- __ -
-=_
. - = - - _ _ _ _ - - - - - - - - -
C.
PARTIQJLATES
====--
1.
Particulates with T 1/2,) 8 Days CI
- 5. 81E-05
- 1. 71E-05 1.57E+01-l 2.
Average Release Rate for Period UCI/SEC 7.39E-06 2.18E-06 3.
% of Tech. Specification Limit
- 4. 33E-05 3.21E-06 l
4.
Gross Alpha Radioactivity CI 1.09E-06 2.32E-07
+
====_
_-------=
======_
_ - _=__ _ - - - - - - _ ---
J D.
TRITIW
_ _ _ = = = _ _ _ _ - - - - - -
1.
Total Release CI 1.18E +00 1.59E +00 1.09E+00 2.
Average Release Rate for Period UCI/SEC 1.50E-01 2.02E-01 3.
% of Tech. Specification Limit 1.94E-03 2.62E-03
_=_=____---- --=== --------- ____
r TABLE 18 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH MODE FD 4TH FD -
4TH
' NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER -
QUARTER l.
FISSION GASES KR-85~
CI
< 8.0E-05
< 8.00E-05 9.43E+01
< 8.00E-05 KR-85M CI
< 1.0E-07
< 1.00E_07
< 1.0E < 1.00E-07 KR-87 CI.
< 3.0E-07
< 3.0 E -07
<. 3.00E-07
< 3.0E-07 KR-88 CI
< 3.50E-07
< 3.50E-07
< 3.50E-07
< 3.50E-07 XE-133 CI
< 3.50E < 3.50E-07 3.39E-01 2.27E-04 XE-135 CI
< 7.00E-07
< 7.00E-07 2.42E-03
< 7.00E-07 XE-135M CI
< 5.00E-07
< 5.0E < 5.00E-07
< 5.00E-07 XE-138 CI
< 1.70E-07
< 1.70E-07
< l.70E-07
< 1. 70E-07 XE-131M CI
< 1.00E-06
< 1.00E-06 7.88E-03
< l.00E-06' XE-13 F CI
< 5.00E-07
< 5.00E-07
< 5.00E < 5.0E-07 AR-41 CI
< 1.7E -06
< l.70E-06
< l.70E-06
< 1.7E-06 UNIDENTIFIED CI 0.00E-01
.0.00E-01 0.00E-01 2.11E-04 TOTAL FOR PERIOD CI 0.0E-01 0.00E-01 9.47E+01 2.27E-04 2.
10 DINES I_131 CI 1.27E-04 1.32E < 9.60E-15
< 9.60E-15 I-132
.CI
< 5.50E-13
< 5.50E-13
< 5.50E-13
< 5.50E-13 I-133 CI 7.03E-04 4.77E-04
< 4.6E-14
< 4.60E I-134 CI
< l. 6E-12
< l.60E-12
< 1.60E_12
< l.60E-12 i
I-135 CI
- < 4.5E-13
< 4'.50E-13
< 4.50E-13
< 4.50E-13 TOTAL FOR PERIOD CI 8.30E-04 6.09E-04 0.00E-01 0.00E-01 3.
PART10JLATES l
4 L
SR-89 CI
< l.00E-16
< l.00E-16
< 1.00E-16
<l.00E-16 l
SR-90 CI 2.91E-08
< 4.7E-18
< 4.70E-18
< 4.7E-18 i
CS-134 CI
< 9.70E-15
< 9.70E-15
< 9.70E-15
< 9.7E CS-137 CI 1.56E-05 2.60E-06
< 1.10E-14
< 1.10L -14 BA-140 CI
< 3.60E-14
< 3.6E-14
< 3.60E-14
< 3.60E-14 l
OTHERS C0-60 CI 2.98E-05 1.36E-06
< l.40E-14
< 1.40E-14 l
CI 0.00E-01 0.00E-01 0.00E-01 0.0E-01 CI 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CI 0.00E-01 0.00E_01 0.00E-01 0.00E-01 CI 0.00E-01 0.00E-01
- 0. 00E-Ol '~
0.00E-01 CI 0.00E_01 0.00E-01~
0.00E-01 0.00E-01 CI 0.00E-01 0.00E-01 0.00E-01' O.00E-01 CI 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CI 0.00E-01 0.00E-01 0.00E-01 0.00E-01 I
UNIDENTIFIED CI 0.00E_01 0.00E-01 0.00E-01 0.00E-01 P
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-TABLE 2A
~ EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES
_--------_-------___= --------_----------=_____ -
3RD 4TH EST. TOTAL UNIT QUARTER QUARTER
. ERROR %
A.
FISSION AND ACTI\\ATION PRODUCTS
- j 1.
Total Release CI 3.05E-01 4.57E-02 8.39E-01
_----_-----__-_------==
2.
Average Diluted Concentration During Period UCI/ML 1.74E-09 2.07E-10 3.
% Applicable Limit 3.922WD3 1.72E-03
_____-----__-__----______--=
B.
U1ITIUM 1.
Total Release CI 3.54E+01 9.51E+01 3.50E-01
-_---__--_ ---=-
2.
Average Diluted Concentration During Period UCI/ML 2.02E_07 4.30E_07 3.
% Applicable Limit 6.74E-03 1.43E-02 i
C.
DISSOLVED AND ENTRAINED GASES i-g 3
g
=- ----_-
2.
Average Diluted Concentration During Period UCI/ML 4.06E-12 4.00E-12
- =---====---_---_
3.
% Applicable Limit ~
2.03E-06 2.00E-06
- _ - _ _ - - - - - - - _ - - - _ _ _ = _ - = = - - - - - - - - - - - - = = - - _ = = - _ - - - - - _ - - -
I D.
CROSS ALPHA RADI0 ACTIVITY 1.
Total-Release CI 1.57E-04 3.41E-03 6.99E+00
-_. _----- ___.. __---____--- = =-------__---_---_------------_----__-_--__---_-_--
E.
VOLUME OF WASTE LITERS
- 2. 81E +07
- 2. 63E+07 1.00E+01 i
F.
VOLUME OF DILUTION LITERS 1.75E+11 2.21E+11 1.00E+01
=----_-------
-_---_-----__----_-------__--_----_-----_-__----_--_-___----- _=___
- TOTAL RELEASE EXCLUDING TRITItN, GASES, APO ALPHA.
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TABLE 28 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER-3 QUARTER-4 QUARTER-3 QUARTER-4 SR-89 CI
< l.00E-09
< l.00E-09
< l.00E-08 1.96E-04 SR-90 CI
< l.00E-09
< 1.00E-09
< 1.00E-08 3.92E-05 CS-134 CI
< 5.0 T -08
< 5.00E-08
< 5.00E-07 6.14E-05 CS-137 CI
< l.00E-08
< 1.00E-08 6.46E-04 6.14E-04 CO-58 CI
< 5.00E-08
< 5.00E-08 7.41E-02 1.19E-02 CO-60 CI 9.llE -03 6.4 3E-04 6.18E-03 1.44E-02 FE-59 CI
< l.00E-07
< l.00E-07
< 1.00E-06
< l.00E-06 ZN-65 CI
< 9.00E-08
< 9.00E-08
< 9.00E-07
< 9.00E-07 f44-54 CI 7.35E-04
< 5.00E-08
- 2. 67E-03 4.62E-03 CR-51 CI
< 3.00E-07
< 3.00E-07
< 3.00E-06
< 3.00E-06 ZR-95 CI
< 8.00E-08
< 8.00E-08
< 8.00E-07
< 8.00E-07 MO-99 CI
< 4.00E-08
< 4.00E-08
< 4.00E-07 4.43E-05 TC-99M CI
< 4.00E-08
< 4.00E-08
< 4.00E-07
< 4.00E-07 BA-140 CI
< 2.00E-07
< 2.00E-07
< 2.00E-06
< 2.00E-06 CE-141 CI
< 4.00E-07
< 4.00E-07
< 4.00E-07
< 4.00E-07 OTHER HG-203 CI
< 2.00E-08
< 2.00E-08 4.97E-02
< 2.00E-07 SE-75 CI
< 2.00E-08
< 2.00E-08 1.52E-01
< 2.00E-07 C0-57 CI
< l.00E-08
< l.00E-08
- 4. 31E-05
< l.00E-07 F-18 CI
< 4.00E-08
< 4.00E-08 2.99E-03 2.68E-03 SB-124 CI
< l.00E-08
< l.00E-08 5.96E-04
< l.00E-07 I-133 CI
< 4.00E-07
< 4.00E-07
< 4.00E-06 4.18E-04 i
AG-110M CI
< 2.00E-08
< 2.00E-08
< 2.00E-07 8.08E-04 CO-57 CI
< l.00E-08
< l. 00E-08
< l.00E-07 2.48E-04 l
NA-24 CI
< l.00E-08
< 1.00E-08
< l.00E-07 1.62E-03 j
UNIDENTIFIED CI 0.00E-01 0.00E-01 0.00E-01 0.00E-01 i
TOTAL FOR PERIOD CI 1.14E-02 9.83E-04 2.94E-01 4.47E-02 XE-133 CI
< l.00E-07
< 1.00E-07 5.03E-04 5.51E-04 XE-135 CI
< 6.00E-06
< 6.00E-06 2.07E-04 3.33E-04 I
NOTE: ACTIVITIES OF ZR-95 AND BA-140 INCLUDE CONTRIBUTIONS OF DAUGHTERS.
NOTE: LESS THAN (
) VALUES ARE MINIMLN DETECTABLE ACTIVITIES IN UCI/CC.
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TABLE 3
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLIO WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-m nth E st. Tosat
- 1. Type of was:e unii Period Err or. %
- a. Spent resins, filter sim!ges, evaporator n/
4.95 E bot toms, ete.
Ci 152 E 3.0 ti.1
- b. Dry compressible waste, contaminated m'
1.6 E2 equip etc.
Ci 6.9 E 3.0 E 1
- c. Irradiated components, control m'
E rods.cic.
Ci E
F
- d. Other (describe) m' E
Ci E
E
- 2. Estimate of maior nuclide composition (by type of waste)
CS-137 q
5 0E a.
Cc-58 9
2 5 II Cc-50 2 bE b.
Cs-137 9
5 OE Cc-58 2.5E LC-bU g.
- 2. E 7
E c.
E E
d.
E q
E E
3.
Solid Waste Disposition Number of Shipments Mode of TransporIation Destination 9
Truck Chem-Nuclear, Barnwell, S.C.
5 Truck Nuclear Eng. Co., Richland, Wash.
B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation Destination 1 :
v I.21 19
.