ML20246L087
| ML20246L087 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/30/1989 |
| From: | Whittier G Maine Yankee |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| GDW-89-284, MN-89-111, NUDOCS 8909060221 | |
| Download: ML20246L087 (14) | |
Text
L. , g. ., .. _. .
.. a
~
M WJ ,p,
'MaineYankee atuxea tacinornon uame suce im j+-
, l1r ,4 a .c ED! SON DRIVE . AUGUSTA, MAINE 04330. (207) 622-4868 i
i.
9 :gx " -
~
+ '
2
' df.7. .i l '.
6i +i August 29, 1989 MN-89-111 GDH-89-284 Region I UNITED STATES NUCLEAR REGULATORY COMMISSION
' 475 Allendale Road .
King of Prussia, Pennsylvania 19406 -
Attention: Mr. William T. Russell, Regional Administrator ,
e
References:
(a) License No. DPR-36 (Docket No. 50-309) h-Gentlemen: ~.
Subject:
Semiannual Effluent Release Report
~
Enclosed is the Maine Yankee Semiannual Effluent Release Report for the period January 1,1989 to June 30, 1989. There were no changes to the ~
Off-Site Dose Calculation Manual. These reports are submitted in accordance with Technical Specifications 5.9.1.6, 4.13, 3.28, 3.16 and 3.17.
Very truly yours, MAINE YANKEE
/
kh&
G. D. Whittier, Manager Nuclear Engineering and Licensing GDH:HSD _
- Enclosure -
c: Mr. Richard H. Hessman Mr. Eric J. Leeds Mr. Cornelius F. Holden
, Document Control. Desk 1
Mr. Donald Hoxie - DHE Mr. Allan Prysunka - DEP - Oil & Hazardous Haste .
! American Nuclear Insurers
[6N
'i
' 05021-DSS
! s909060221 s90630 _
! F;DR ADOCK 0500 ..
s
.i. . Jr R$L-_;
. ,6 ' sd t* M * .. p::- % ' c ,
Y. Yii;k a * , t;~' . :s. ,
.m
-cts,al;Jj
.m enpG*p:c"J",.
1onp png . .y , .
ll5 3d&W -
, bjf7N?
' MAINE YANKEE ATOMIC POWER COMPANY n ,
, 9 $@l:f-Q Gln p c.y. W " u j l ln*f ;i U,,a%W eQ -9 3..
^ .<
16 4' T,. ,
SEMIANNUAL EFFLUENT RELEASE REPORT
$Rfth:@N l, ' '
w; . - -
.;. January - June, 1989 7
i
'l .
1.0 INTRODUCTION
l Tables 1 through 4 list the recorded radioactive liquid and gaseous -
effluents and solid waste for the first six months of the year, with data -
i summarized on a quarterly basis, i
Appendices A through 0 indicate the status of reportable items per the requirements of Technical Specifications 3.16.C, 3.17.0, 3.28. A. 3.28.8, 4.8.A, 4.13 and 5.9.1.6. -
i f
e 05051-DS
, 'T % pg_g .yad E.~. _l
- ~
[* a -v- Maine YankA Art;Ti- P~o wer Station AL.
Effluent and Waste Discosal Semiannual Reoort '
' ', 7ITT' First and Second Ouarters. 1989 j;, l _. ' ' ,, Gaseous Effluents - Summation of All Releases ~
- lh"f?i ??qs, ' ' ' ~
~
YMVy ,
Est. Total
' " illfft"c
. , avi.x Unit Quarter 1st Quarter 2nd Error. %
av 3;qf P-j iA. Fission add Activation Gases
- 1. Total release Ci 4.29 E-01 2.18 E-01 2.50 E+01
- 2. Averace release rate for oeriod UCi/ set 5.45 E-02 2.78 E-02. -
- 3. Percent of reculatory limit % 1.64 E-04 9.04 E-05 B. Iodines .
- 1. Total Iodine-131 Ci 9.38 E-06 5.39 E-06 2.50 E+01 -
- 2. Averaae release rate for oeriod UCi/sec 1.19 E-06 6.84 E-07
- 3. Percent of reculatory limit % 1.05 E-05 6.00 E-06_
C. Particulate _ . .
- 1. Particulate with T-1/224 8 davs Ci 1.46 E-06 1.57 E-07 2.50 E+01
- 2. Averaae release rate for oeriod UCi/sec 1.85 E-07 1.99 E-08
- 3. Percent of reculatory limit % 4.57 E-07 5.81 E-08 ,
- 4. Gross aloha radioactivity C1 1.84 E-07 8.18 E-08 l
D. Tritium
- 1. Total release C1 1.20 E+00 2.12 E+00 2.50 E+01 l 2. Averace release rate for oeriod UCi/sec 1.53 E-01 2.70 E-01
- 3. Percent of reaulatory limit % 6.69 E-04 1.18 E-03 1
i i
i f
i 05051-DS
~
' 7G): r . , .Leau :1 l '" $o? chief ? v,6lQ Ma1rre Yankee Atomic Power Stat 12a NNkar p H Effluent and Waste Discosal Semiannual Reoort L * ;ig[Jff ' 9 First and Second Ouarters.1989 Gaseous Effluents - Elevated Release
' , ,+4dij$.;7$
e r$' " '
r .
Continuous Mode Batch Mode 01#3.d7.'""
f :;MGQ Nuclides Released Unit Quarter Quarter Quarter Quarter Q Z ' ,. >
1st 2nd 1st 2nd _,_
a
- .,y
[ 7 T 1. Fission Gases Krvoton-85 Ci N/D* N/D* N/D* N/D* __
y
, Krvoton-85m Ci N/D* N/D* N/D* 3.59 E-04__
N/D* N/D*
L Krvaton-07 Ci N/D* N/D* --
~
L Krvoton-88 Ci N/D* N/D* N/D* N/D*
Xenon-133 Ci N/D* N/D* 4.26 E-01 2.09 E-01 Xenon-135 Ci N/D* N/D* 1.45 E-04 8.72 F,,Q3._
Xenon-135m Ci N/D* N/D* N/D* N/D*
Xenon-138 Ci N/D* N/D* N/D* N/D* .
Xenon-133m Ci N/D* N/D* 2.38 E-03 7.13 E-06.
Xenon-131m Ci N/D* N/D* N/D* N/D*
Arcon-41 Ci N/D* N/D* N/D* N/D* ;
Unidentified Ci N/D* N/D* N/D* N/D* l Total for oeriod Ci N/D* N/D* 4.29 E-01 2.18 E-01l* i 1
- 2. Iodines Iodine-131 Ci 9.34 E-06 3.85 E-06 3.93 E-08 1.54 E Iodine-133 C1 1.04 E-05 1.47 E-05 5.21 E-08 3.39 E-06 Iodine-135 Ci N/D* N/D* 2.02 E-08 1.60 E-06 Total for neriod C1 1.97 E-05 1.86 E-05 1.12 E-07 6.53 E-06 l
- 3. Particulate Strontium-89 Ci N/D* N/D* N/D* N/D* l Strontium-90 Ci N/D* N/D* N/D* N/D*
Cesium-134 Ci N/D* N/D* N/D* N/D*
Cesium-137 Ci 5.73 E-07 N/D* N/D* 1.32 E Barium-Lanthanum-140 Ci N/D* N/D* N/D* N/D' Zinc-65 Ci N/D* N/D* N/D* N/D* !
Cobalt-58 Ci N/D* N/D* N/D* N/D*
Cobalt-60 Ci 8.83 E-07 1.55 E-07 N/D* 8.80 E-10 Others Ci N/D* N/D* N/D* N/D*
- N/D - Not Detected .
O i
i i j 05051-0S .
__ _ __.______.___________.______J
- 4. 43Li._;. JABLE 1C
..'4 .
~
. -Maine Yankee Atomic Power Station
- Effluent and Waste Disnosal Semiannual Renort '
First and Second Ouarters 1989 Gaseous Effluents - Ground Level Releases
[ ,
V, .. .
m.
f li There were.no routine measured' ground level continuous or batch mode gaseous releases' during the first and second quarters of 1989. .
l l
4 .
l e,.
1 l-.
l 05051-DS
t XloWA ?_Q l'*'
. (I" . '
Maine Yankee Atomic Pombt Station Effluent and Haste Disogsal Semiannual Reoort
- 4 Er "
- rt,. eg frf . ,
First and Second Ouarters. 1989
' ' ' ~
7 Liouid Effluents - Summation of All Releases
%]lP.,1 7,; A - :
- Ch % ",q' ~
- g. m p f-
' ,.4 . p ' Unit Quarter Quarter Est. Total 1st 2nd Error. %
r _
,,; iA.' Fission and Activation Products
~1. Total release (not including tritium. aases. aloha) Ci 1.01 E-01 1.49 E-02 1.50 E+01
- 2. Average diluted concentration ,
durina ceriod uti/ml 5.05 E-10 7.16 E-11
- 3. Percent of aoolicable limit % 7.65 E-03 1.61 E-03 B. Tritium -
- 1. Total release Ci 3.52 E+01 9.59 E+01 1.50 E+01
- 2. Average diluted concentration durina ceriod UCi/mi 1.76 E-07 4.61 E-07
- 3. Percent of acolicable limit % 5.87 E-03 1.54 E-02 C'
C. Dissolved and Entrained Gases _.
- 1. Total release Ci 6.74 E-03 8.38 E-02 1.50 E+01
- 2. Average diluted concentration durina Deriod UCi/ml 3.37 E-11 a.03 E-10 ,
- 3. Percent of anolicable limit % 1.69 E-05 2.01 E-04 D. Gross Alpha Radioactivity
- 1. Total release Ci 2.89 E-05 N/D* 1.50 E+01
- 2. Average diluted concentration durina ceriod UCi/ml 1.45 E-13 N/D*
E. Volume of waste released (prior to dilution) _
liters 1.54 E+07 7.76 E+06 1.00 E+01 F. Volume of dilution water used durina ceriod liters 2.00 E+11 2.08 E+11 1.00 E+01 h
05051-DS
.o
- ) J' Haine Yankee Atomic Power Station
'j' _- Effluent and Haste DisDosal Semiannual ReDort
- , first and Second Ouarters. 1989 y
[n's',.;, ,
Licuid Effluentt I' ~i Continuous Mode Batch Mode.
, -'.' Nuclides Released Unit Quarter Quarter Quarter Quarter
[ " ' Cdyg ,
1st 2nd 1st 2nd t
ll;'
Strontium-89 Ci N/D* N/D* 2.50 E-04 N/D*
Strontium-90 Ci N/D* N/D* N/D* N/D*
Cesium-134 Ci N/D* N/D* 2.65 E-03 9.01 E-05 Cesium-137 Ci 1.23 E-05 4.81 E-05 8.52 E-03 5.78 E-04 .'
Icdine-131 Ci N/D* N/D* 3.37 E-03 8.94 E-04_
Cobalt-58 Ci N/D* N/D* ].42 E-02 2.04 E-03 -
Cobalt-60 Ci 1.40 E-04 1.51 E-04 1.52 E-02 4.20 E-03 Iron-59 Ci N/D* N/D* N/D* N/D*
Zi nc-65 Ci N/D* 9.39 E-08 N/D* N/D*
Mancanese-54 Ci N/D* 1.23 E-08 1.22 E-03 3.79 E-04 Chromium-51 Ci N/D* N/D* 4.27 E-04 N/D* L' Zi rconium-Niobium-9S Ci N/D* 5.08 E-07 1.05 E-05 .N/D* _
Holybdenum-99 Ci N/D* N/D* 1.57 E-04 1.15 E-05 Technetium-99m Ci N/D* N/D* 3.73 E-04 9.35 E-06 l Barium-tanthanum-140 Ci N/D* 9.31 E-07 1.30 E-04 1.21 E-04 Ceri um-141 Ci N/D* N/D* N/D* N/D*
Others Iron-55 Ci N/D* N/D* 6.85 E-03 2.55 E-03 Silver-110m Ci N/D* N/D* 1.94 E-03 1.22 E-04 Iodine-133 Ci N/D* 4.74 E-07 9.62 E-04 N/D*
Antimonv-124 Ci N/D* N/D* 2.79 E-02 1.85 E-03 Antimony-125 Ci N/D* 1.36 E-05 1.67 E-02 1.82 E-03 Ruthenium-103 Ci N/D* 2.28 E-08 N/D* N/D*
Cobalt-57 Ci N/D* N/3* 4.51 E-06 N/D*
Tin-113 Ci N/D* 3.85 E-07 2.63 E-05 2.49 E-05
_MDj denti fi ed Ci H/D* N/D* N/D* N/D*
Total for Deriod (above)(1)Ci 1.52 E-04 2.15 E-04 1.01 E-01 1.47 E-02 Xenon-133 C1 1.05 E-04 1.96 E-05 6.53 E-03 8.24 E-02 Xenon-135 Ci N/D* 2.30 E-06 1.02 E-04 3.36 E-04 Xenon-131m Ci N/D* N/D* N/D* 2.76 E-04 Xenon-133m Ci N/D* N/D* N/D* 7.49 E-04 Krvoton-85m -
Ci N/D* 2.11 E-06 N/D* N/D*
KrvDton-88 C1 N/D* 1.33 E-06 N/D* N/D*
( N/D* - Not Detected (1) - Total for period does not include unidentified in this summation but is included in Table 2A, Item A1.
05051-DS
TABLE 3
~
Maine Yankee Atomic Power Station fl D uent and Haste D1900111 Semiannual Reoort First and Second Ouarters.19fd Solid Maste and Irradiated Fuel Shioments
.A. Solid Haste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)*
Unit 6-Month Est. Total
___fsri od Error. %
- 1. Type of Haste
- a. Spent resins, filter sludges, evaporator m3 3.4 i 10 bottoms. etc. - LSA container **.+ w Ci 55.72-
- b. Dry. compressible waste, contaminated m3 84.1 i 10 eauioment. etc. - LSA container +.++ C1 1.5
- c. Irradiated components, control rods, .a3 0 etc. Ci 0
- d. m3 Ci
- e. m3 C1
- 2. Estimate of Major Nuclide Composition (By Type of Haste)***
- a. Fe-55 35% elus' or minus 10% __
Ni-63. 31% olus or minus 10%
Co-60 22% olus or minus 10%
Cs-137 2% olus or minus 10%
l Ba-137M 2% olus or minus 10%
Sb-125 1% olts or minus 10%
- b. Cs-137 10% olus or minus 10%
Co-60 22% olus or minus 10%
Co-58 11% olus or minus 10%
Cs-134 3% olus or minus 10%
Ni-63 14% olus or minus 10%
Fe-55 26% olus or minus 10%
Zr-95 5% olus or minus 10%
Sb-125 2% olus or minus 10%
- 3. Solid Haste Disposition ,
Number of Shioments Mode of Transportation Destination From Maine Yankee 5 Trucking over Highway Chem-Nuclear, Barnwell, S.C.
From SEG # 31 Trucking over Highway Chem-Nuclear, Barnwell, S.C.
B. Irradiated Fuel Shipments (Disposition)
+ Contain?r volume equal to 55 gal ons (drums).
++ Contalair volume equal to 110 f t (boxes).
m Contal' ar volume equal to 170 ft (liners) (HIC)
- Solid waste is Class A, as defined in 10CFR61.55. 84.1 m3, 1.5 Ci
- Solid waste is Class B, as defined in 10CFR61.55 0.8 m3, 6.76 Ci
- Solid waste is Class C, as defined in 10CFR61.55 2.6 m3, 48.96 Ci
- Solidification agent is cement.
- Excluding nuclides with half-lives less than 12.8 days.
- SEG performs super compacting of DAH.
05051-DS
T[ . .
mott 4
@(p <
l Sucolemental Information G'
i 1. . Reaulatory Limits .
Maximum Permissible Concentration ]
- a. Fission and activation gases: 10CFR20; Appendix B. Table 2, Column 1
. b. Iodines: 10CFR20; Appendix B. Table 2, Column 1 .
- c. Particulate, (with half. . .., .
lives greater than 8 days) 10CFR20; Appendix B. Table 2, Column 1
- d. Liquid effluents: 10CFR20; Appendix B, Table 2 Column 1
- e. Total noble gas concentration 2E-04 uC1/mi ,
~
- 2. Averace Eneray - Not Aeolit.able
- 3. Measurements and Anoroximations of Radioactivity
- a. Fission and Activation Cases [-
Continuous Discharge - Vent stack samples are analyzed monthly. Activity l
1evels determined are assumed constant for the surveillance interval. The continuous vent stack monitor reading is used as a basis for increasing periodic sample frequency. 0~ l L ~
Batch Discharges - Direct measurements of the waste gas hold-up drums are taken prior to discharge. Containment vents and purges are analyzed by direct measurement of the containment atmosphere at periodic intervals during discharge. .
- b. Icdines .
l Primary vent stack iodine totals are taken from a minimum of weekly measurements of an in-line charcoal filter.
- c. Particulate Primary vent stack particulate totals are taken from a minimum of weekly measurements of an in-line particulate filter.
- d. Licuid Effluents Samples of secondary systems' liquid effluents are analyzed weekly for gross beta-gamma, alpha, tritium, dissolved gases, and gamma emitting isotopes.
Each batch release fs analyzed for gross beta-gamma, alpha, tritium, di_ssolved gases, and gamma emitting isotopes prior to discharge.
Composite samples are made of secondary and primary system liquid effluents for a quarterly analysis of Strontium-90 and Strontium-89.
Primary system liquid effluents are also analyzed quarterly for Iron-55.
l -
05051-DS -
@N . TABLE 4 .a -
(( , ~. (Continued) j$' - 4. Batch Releases e
- a. Liouio's .,
- 1. Number of batch releases: 57
- 2. Total time period for batch releases: 187 hours0.00216 days <br />0.0519 hours <br />3.091931e-4 weeks <br />7.11535e-5 months <br />, 50 mirastes
- 3. Maximum time period for a batch release: 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br />. 5 minutes
- 4. Average time period for batch releases: 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, 18 minutes
- 5. Minimum time period for a batch release: 15 minutes
- 6. Average stream flow during periods of release of effluents into a flowing stream: N/A
- 7. Maximum gross release concentration (uCi/ml): 1.71 2-07 ~.
l
- b. Gaseous .
- 1. Number of batch releases: 12
- 2. Total time period for batch releases: 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />, 53 minutes '
- 3. Maximum time period for a batch release: 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />, 22 minutes
- 4. Average time period for b&tch releases: 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, 44 minutes
, 5. Minimum time period for a batch release: 15 minutes
- 6. Maximum gross release rate (uC1/sec): 1.13 E+03 ..
- 5. Abnormal Releases --
- a. Licuid .
There were no abnormal liquid releases during the reporting period. .
- b. Gaseous There were no abnormal gaseous releases during the reporting period.
- 6. On-line Containment Purae On-line containment purge was not employed during the reporting period.
l l
l 05051-PS
c37, ,
L .
, ('
APPENDIX A 3 Radioactive Effluent Henitorina Instrumentation Recoirement: Radioactive effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specificat'ons 3.28.A &
B. With less than the minimum number of channels operable and reasonable efforts to return the instrument (s) to operable status within 30 days being unsuccessful. Technical Specifications 3.28.A &
B requires an explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Report.
Resoonse: The requirements of Technical Specifications 3.28.A and 3.28.B. -
governing operability of radioactive effluent monitoring instrumentation, were met for this reporting period, and no report is required.
~
d M
O i
l i
I l 05051-0S i
g 'y , t., .,
id < APPENDIX B p". .- ..-
pf 'f- Linuid Radwaste Treatment System- '
F- .,
+
R'eauirement: With radioactive liquid waste being discharged without treatment with i~
estimated doses in excess of the limits in Technical Specification i
3.17.C.1, a report must be submitted to--the Commission in the
- Semiannual Effluent Release Report for the period. - -
a; Resoonse:- The requirements of Technical Specification 3.17.C.1 were met during
- this period and, therefore, no report is required. ,
i I
=
e e
L. .
A e4 o
C g .
5' i
.I '.
l 105051-0S H
b - - - _ - - - - - - - - - - _ - _ - - _ _
%1 b ..
APPENDIX C Gaseous Radwaste Treatment System Requirement: Mith radioactive gaseous waste being discharged without treatment with doses in excess of the limits in Technical Specifications 3.18.D.1, a report must be submitted to the Commission in the Semiannual Effluent Release Report for the period.
Resnonse: The requirements of Technical Specification 3.18.D.1 were met during this period and, therefore, no report is required.
~.
1 l
- h. .
m e O
e S
e 05051-DS
j!,. ...--
<* , ~.
APPENDIX D
^
ii- Lower Limit of Detection for Radiological Analyses Requirement:' Technical Specification 4.13 requires that when unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Semiannual Radiaattive Effluent Release Report.
Resoonse: Analyses were performed in such a manner that the stated LLD's were achievable under routine conditions. On occasion, with liquid samples, however, the presence of detected higher energy isotopes l caused a compton background elevation. This interference was sufficient to make some of the specified LLD's in those liquid samples unattainable. This occurred in four (4) of the samples for I Zinc-65, and one (1) for Iron-59. All other isotope LLD's were met.
On all occassions, the specified LLD's were attained on the gaseous samples.
e O
O e
- 05051-0S
- -__ _____________ _____