ML20235L682
| ML20235L682 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/31/1988 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20235L683 | List: |
| References | |
| NUDOCS 8902270627 | |
| Download: ML20235L682 (19) | |
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SEMI-ANNUAL EFFLUENT RELEASE REPORT l
CALVERT CLIFFS NUCLEAR POWER PLANT L
SECOND HALF - 1988 TABLE OF CONTENTS I.
REGULATORY LIMITS..............................................
........ 1 A.
Fission and Activation Gases........................................
1 B.
Iodines and Particulate with Half Lives Greater than Eight Days....1 C.
L i q u i d E f fl u e n t s.................................................... 2 II. MAXIMUM PERMISSABLE CONCENTRATIONS......................................
2 A.
Fission and Activation Gases........................................
2 B.
Iodines and Particulate with Half Lives Greater than Eight Days.... 3 C.
L i q u i d E f fl u e n t s.................................................... 3 III. TECHNICAL SPECIFICATION REQUIREMENTS....................................
3 IV. AVERAGE ENERGY.......................................................... 4 V.
MEASUREMENTS AND APPR0XIMATIONS OF TOTAL RADIOACTIVITY.................. 4 A.
Fission and Activation Gases........................................
4 1.
Batch Releases..................................................
4 2.
C o n t i n u o u s Rel e a s e s............................................. 4 B.
Iod i ne and Parti cul ates............................................. 4 1.
BatchReleases..................................................4 2.
Co nt i nu o u s Rel e a s e s............................................. 5 C.
L i q u i d E f fl u e n t s.................................................... 5 1.
B a t c h Rel e a s e s.................................................. 5 2.
Co n t i n u o u s Rel e a s e s............................................. 5 D.
Es ti mat i on o f Tot al Error........................................... 6 1.
Liquid.......................................................... 6 2.
Gases........................................................... 6 VI.
BATCH RELEASES..........................................................
7 A.
Liquid..............................................................
7 B.
Gaseous.............................................................
7 VII. ABNORMAL RELEASES....................................................... 8 A.
Liquid.............................................................. 8 B.
G a s e o u s.............................................................. 8 TABLES i
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1 A - Gaseous Effluents - Summation of Rel eases.............................. 9 1C - Gaseous Ef fl uents - Ground Level Rel eases............................. 11 2A - Liquid Effluents - Summation of All Releases.......................... 13
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2 8 - L i q u i d E f fl u e n t s...................................................... 15 l
3A - Sol id Waste and Irradiated fuel Shipments............................. 18 l
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CALVERT CLIFFS NUCLEAR POWER' PLANT-EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SUPPLEMENTAL INFORMATION Facility - Calvert' Cliffs Nuclear Power Plant Licensee - Baltimore Gas & Electric Company i
I.
REGULATORY LIMITS A.
Fission and Activation Gases 1.
The instantaneous release rate of noble gases in gaseous effluents shall not result in a site boundary dose rate greater than 500 mrem / year to the whole body or greater than 3000 mrem / year to the skin.
2.
Gaseous Radwaste Treatment System and the Ventilation Ex-haust Treatment System shall be used to reduce gaseous emis-sions when the calculated gamma dose due to gaseous effluents exceeds 1.20 mrad or the calculated beta dose'due to gaseous effluents exceeds 2.40 mrad at the site boundary in a 92 day period.
3.
- The air dose at the site boundary due to noble gases re-leased in gaseous effluents shall not exceed:
t 10 mrad gamma radiation / quarter 20 mrad beta radiation / quarter 20 mrad gamma radiation / year 1
40 mrad beta radiation / year 4.
All of the above parameters are calculated according to the methodology specified in the Offsite Dose Calculation Manual (0DCM).
B.
Iodines and Particulate with Half Lives Greater than Eiaht Days 1.
The instantaneous release rate of Iodines and particulate in gaseous effluents shall not result in a site boundary dose in excess of 1500 mrem / year to any organ.
j 2.
The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous effluents when calculated doses exceed 1.8 mrem to any organ in a 92 day period at the site bounda-Ty<
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3.
The. dose to a member of the _ public at the, site boundary from Iodine 131 and particulate with half lives greater than eight days in gaseous effluents shall not exceed:
15 mrem to any organ per quarter 30 mrem to any organ per year less than.1% of the above' limits as a result of burning i-contaminated oil 1
4.
All of the above parameters are calculated according to the methodology specified in the ODCM.
C.
Liauid Effluents
.1.
The concentrations of radioactive isotopes in ' liquid effluents from the plant shall not exceed the values speci-fied in 10 CFR, Part 20, Appendix B, for unrestricted areas.
2.
The liquid radwaste treatment system shall be used to reduce the radioactive isotopes in liquid effluents from the plant when the calculated doses to unrestricted areas exceed 0.36 mrem to the whole body, or 1.20 mrem to any organ in a 92 day period.
3.
.The dose to a member of the public in unrestricted areas shall not exceed:
3 mrem whole body dose per quarter l
10 mrem dose to any organ per quarter 6 mrem whole body dose per year 20 mrem dose to any organ per year 4.
All of the liquid dose parameters are calculated according to the methodology specified in the ODCM.
II.
MAXIMUM PERMISSABLE CONCENTRATIONS A.
Fission and Activation Gases Prior to the batch release of gaseous effluents, the gas gamma activities are summed.
If the total does not exceed the dose rate limitations for the most-limiting isotope, then the batch is released. _ :If the most-limiting isotope criteria is not met, then a detailed dose rate calculation is performed as described in the CDCM.
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Iodines and Particulate with Half Lives Greater than Eiaht Days Compliance to the dose rate limitations from Iodines and particu-lates is demonstrated by calculating the maximum quantity that-1 could be seen on a weekly sample. This is reduced by a factor of 0.5 for conservatism.
As long as the I-131 (most limiting iso-tope) releases in a seven day period do not exceed 12.5 Ci, then f
no further analyses are needed to verify compliance without ex-I ceeding the limits of 1.B.3.
1 C.
Liauid Effluents The MPCs used for radioactive materials released in liquid effluents are in accordance with Technical Specifications and/or are derived from the use of notes to Appendix B, 10 CFR, Part 20.
In all cases, the most restrictive (lowest) MPC found for each isotope is used regardless of solubility.
III. TECHNICAL SPECIFICATION REPORTING RE0VIREMENTS (Section 6.9.1.8)
A.
Previous Calendar Year (1988) Dose Assessment Summary During 1988 liquid releases from Calvert Cliffs resulted in a maximum organ dose of 3.67E-01 mrem and a maximum whole body dose of 5.36E-02 mrem.
This was less than 2% of the allowable yearly Technical Specification organ dose limit and less than 1% of the allowable yearly Technical Specification whole body dose limit.
This dose was calculated using ODCM methodology (Adult Fish and Shellfish Pathways). The Gastro-Intestinal Tract was the maximum organ dose pathway.
Gaseous Noble Gas Releases resulted in a maximum of 1.84E-01 mrad gamma and 4.84E-01 mrad beta exposure.
Iodine and particulate releases from Calvert Cliffs resulted in a maximum organ exposure of 5.37E-01 via the Thyroid Pathway. These doses were calculated using ODCM methodology.
All gaseous release pathways were below 2% of their allowable Technical Specification limits for 1988.
B.
40 CFR 190 Total Dose Compliance Based upon the releases for the first half of 1988 and the ODCM calculations, the maximum exposed individual would receive less than 1% of the allowable dose.
This does not include the direct radiation contribution which did not show a
statistical difference greater than the normal background.
A more detailed evaluation will be reported in the Annual Radiological Environmental Monitoring Report.
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p' C.:
Solid Waste Report Requirements During the first half of 1988, the types of radioactive solid waste shipped from Calvert Cliffs were radioactive resin, which '
was dewatered and shipped in high integrity containers, and dry compressible waste, which was-shipped in Type H containers.
D.
00CM and PCP Chances No changes were made in the second half of 1988.
IV.
AVERAGE ENERGY Not Applicable V.
MEASUREMENTS AND APPROXIMATIONS AND TOTAL RADI0 ACTIVITY l
A.
Fission and Activation Gases 1.
Batch Releases l
Prior to each batch release of gas from a pressurized gas decay tank, a sample is collected and analyzed for each sig-nificant gaseous isotope using a Ge detector. The total ac-tivity released is based on the pressure / volume relationship (gas. laws) of the tank.
I Prior to and after the release of gas as a result of purging containment, samples are collected and analyzed for each significant gaseous isotope using a Ge detector.
The total activity released is based on containment volume and purge rate. Activity buildup while purging is also considered.
2.
Continuous Releases During the release of gas from the main vents, samples are collected and analyzed at least weekly for each significant gaseous isotope using a Ge detector.
The total activity re-leased for the week is based on the total sample activity decay corrected to the midpoint of the sample period and niultiplied by the main vent flow for the week.
B.
Iodine and Particulate 1.
Batch Releases The total activity released from a pressurized gas decay tank, containment purges and containment vents as Iodines and particulate is accounted for by the main vent Iodine and particulate continuous samples.
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2.
? Continuous' Releases During the release of gas from the main vents,; samples. of Iodines and particulate.areicollected using a charcoa1L and particulate. filter, respectively.. The ~ filters' are removed weekly and.are analyzed for each. significant gamma isotope-using a Ge' detector.
The total activity released. for the week is based on the total sample activity found on the fil-ters decay corrected..to the_ midpoint of the sample period i
and' multiplied by the main vent flow for the week.
These
. weekly particulate filters are then composited to form monthly and quarterly composites at which time gross. alpha and strontium 89 and 90 are analyzed.
C.
Liauid Effluents 1..
Batch Releases Prior to the release of liquid from a waste tank, ' a sample is collected;and analyzed for the concentration of each sig-nificant gamma energy radionuclides to demonstrate compliance-with Section I.C.1 above using the water flow rate in each discharge ~ conduit' into which the effluent is discharged at the. time'of. discharge.. The total activity. released in each batch;is determined by multiplying the volume released times theiconcentration of each isotope.. The actual. volume re-
-leased is. based on-the difference in tank levels prior to '
-and after.the release.
A proportional composite sample is also withdrawn for each release and this is'used in turn.to prepare monthly and quarterly. composites for use in analyses of gross alpha, strontium 89 and 90, and tritium.
When steam generator blowdown is discharged to the circulat-ing water conduits,- it is sampled daily and these samples are used in turn.to prepare. a weekly blowdown composite based on each day's blowdown. The weekly composite is ana-lyzed for each significant isotope using a Ge detector and these results are -multiplied by the actual quantity of blowdown to determine the total activity released.
The
. weekly composite is also used to prepare monthly and quar-terly composites for use in analyses 'of tritium, gross
~ lpha,.and strontium 89 and 90.
a 2.
Continuous Releases None l
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g-D.
Estimation of Total Error Total 1 error on all releases was estimated using as a minimum.the random counting error associated with typical releases.
In addi-tion to the random error, the detector to sample geometry system-atic error during gamma counting was determined.
This included an estimate of sample volume error and sample pipetting error.
More specifically the following other systematic errors were also examined:
1.
Liquid a)
Error in volume of-liquid released prior to dilution during batch releases.
b)
Error in volume of liquid released via steam generator blowdown.
c)
Error in amount of dilution water used during the re-
-porting period.
2.
-Gases a)
Error in main vent release flow.
b)
Error in sample flow rate.
c)
Error in containment purge release flow, d)
Error in gas decay tank pressure.
Where errors could be estimated they are usually considered additive.
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'VI.' BATCH RELEASES' 12H 3RD 4TH-0VARTER OVARTER A.
Liauid 1.
Number of-batch releases 4.00E+01
-8.40E+01 2.
Total time period for batch
-releases (min).
1.02E+04-1.17E+04 3.
Maximum. time period for a
. batch release (min):
~6.22E+02 6.15E+02 4.
Average-time period for batch-releases; (min)l 2.55E+02 1.39E+02
- 5. -Minimum time period for.a batch release..(min) 1.70E+01 1.70E+01 6.
Average stream flow during periods of effluent into a flowing stream (liters / min.of dilution water).
4.54E+06 4.54E+06 B.
Gaseous 1.
Number of batch releases 2.40E+01 1.70E+01 2.
Total time period for batch L
" releases (min) 6.81E+03 9.93E+03 3-Maximum time period for a batch release.(min) 3.70E+02 2.84E+03
-4.
Average time period for batch release (min).
2.84E+02 5.84E+02 5.- Minimum time period for a batch release (min) 6.00E+01 1.60E+01 7
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VII. ABNORMAL RELEASES l.i 1916 3RD 4TH OVARTER OVARTER A.
Liauid 1.
Number of releases 2.
Total activity.' released (Curies) B.
Gaseous-1.
Number of. releases 0- 2. - Total activity releases (Curies)- \\
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TABLE 1A - REG GUIDE 1 21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1988 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 3RD 4TH EST. TOTAL A.
FISSION AND ACTIVATION GASES UNITS OVARTER 00ARTER ERROR.%
1.
Total Release Ci 6.51E+02 7.87E+02 2.15E+01 2.
Averaae release rate for oeriod uCi/sec 8.28E+01 1.00E+02 3.
Percent of tech.soec. limit (1) 2.02E-02 2.33E-02 4.
Percent of tech.soec. limit (2) 7.60E-03 9.00E-03 5.
Percent of tech.soec. limit (3) 2.83E-01 3.27E-01 l
6.
Percent of tech.soec. limit (4) 1.41E-01 1.63E-01 1
Percent of tech.soec. limit (5) 2.92E-01 3.54E-01 8.
Percent of tech.soec. limit (6) 1.46E-01 1.77E-01 8.
10 DINES 1.
Total Iodine - 131 Ci 1.20E-02 9.34E-03 1.84E+01 2.
Averaae release rate for period uCi/sec 1.53E-03 1.19E-03 3.
Percent of tech.soec. limit (7) 1.65E-04 1.29E-04 4.
Percent of tech.soec. limit (8) 1.21E-01 9.40E-02 5.
Percent of tech.soec. limit (9) 6.05E-02 4.70E-02 C.
PARTICULATE 1.
Particulate with half lives areater than 8 days Ci 3.68E-05 1.88E-05 1.84E+01 2.
Averaae release rate for oeriod uCi/sec 4.68E-06 2.39E-06 3.
Percent of tech.soec. limit (7) 5.05E-07 2.58E-07 4.
Percent of tech.soec. limit (8) 3.70E-04 1.89E-04 i
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Percent of tech.soec. limit (9) 1.85E-04 9.45E-05 6.
Gross alpha radioactivity Ci
<7.36E-06
<5.19E-05
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TABLE 1A - REG GUIDE 1.21 (Cont.)
CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1988 GASE0US EFFLUENTS - SUMMATION OF ALL RELEASES 3RD 4TH EST. TOTAL D.
TRITIUM UNITS OVARTER OUARTER ERROR.%
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- j. Total Release Ci 1.27E+00 8.31E+00 2.18E+01 l
2.
Averaae release rate for oeriod uCi/sec 1.62E-01 1.06E+00 NOTES TO TABLE 1A (1)
Percent of I.A.1 whole body dose rate limit (500 mrem / year)
(2)
Percent of I.A.1 skin dose rate limit (3000 mrem / year)
(3)
Percent of I. A.3 gamma quarterly dose limit (10 mrad)
(4)
Percent of I.A.3 gamma yearly dose limit (20 mrad)
(5)
Percent of I.A.3 beta quarterly dose limit (20 mrad)
(6)
Percent of I.A.3 beta yearly d:ve limit (40 mrad)
(7)
Percent of I.B.1 organ dose limit (1500 mrem / year)
(8)
Percent of I.B.3 quarterly dose limit (15 mrem)
(9)
Percent of I.B.3 yearly dose limit (30 mrem) 10
18BLE IC - REG GUIDE 1.21 l-CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1988 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 1
CONTINUOUS MODE BATCH MODE i
3RD
-4TH 3RD 4TH J.
FISSION AND ACTIVATf9N GASES UNITS OUARTER 00ARTER OUARTER OUARTER Aroon
-41 Ci (2)
(2) 2.35E-02 1.18E-02 Krvoton
-85 C1 (2)
(2) 4.72E+00 1.62E+01 Krvoton
-85m Ci 1.02E+01 9.83E+00 7.25E-03 3.13E-03 Krvoton
-87 Ci 2.36E+00 5.18E+00 (2)
'(2)
Krvton
-88 Ci 2.12E+00 2.18E+00 (2) 1.50E-03 Xenon
-131m Ci (2)
(2) 2.58E-01 2.55E+00 Xenon
-133 Ci 5.31E+02 6J5E+02 1.49E+01 5.37E+01 1
-133m Ci 6.64E+00 lm94E+00 1.llE-01 3.19E-01_
-135 Ci 7.84E+01 8.01E+01 1.18E-01 7.96E-02 Xenon
-138 Ci (2)
(2)
(2)
(2)
Total for Period Ci 6.31E+02 7.14E+02 2.01E+01 7.29E+01 2.
HALOGENS Iodine
-131 Ci 1.20E-02 9.34E-03 (1)
(1)
-133 Ci 3.14E-02 2.32E-02 (1)
(1)
-135 Ci (2) 8.97E-05 (1)
(1)
Total For Period Ci 4.34E-02 3.26E-02 (1)
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TABLE IC -REG GUIDE 1.21 (Cont.)
CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT SECOND HALF - 1988 i
GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE-3RD 4TH 3RD-4TH 3.
PARTICUtATES UNITS OUARTER OUARTER 00ARTER OUARTER Manaanese
-54 Ci (2)
(2)
-(l)
-(l) tobalt
-58 C1 (2)
(2)
(1)
(1)
-59 Ci (2)
(2)
(1)
(1)
-60 Ci 2.80E-06 (2)
(1)
(1)
Zine
-65 Ci (2)
(2)
(1)
(1)
-89 Ci (2)
(3)
(1)
(1)
-90 Ci (2)
(3)
(1)
(1)
Mol ybdenum C1 (2)
(2)
(1)
(1)
-134 Ci (2)
(2)
(1)
(1)
-137 Ci 3.40E-05 1.88E-05 (1)
(1)
-141 C1 (2)
(2)
(1)
(1)
-144 C1 (2)
(2)
(1)
(1)
Total For Period Ci 3.68E-05 1.88E-05 (1)
(1)
(1). Iodines and particulate in batch releases are accounted for with the main vent continuous samplers when the release is made through the plant main vent.
(2) Less than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillance Requirement 4.11.2.1.2.
(3) Analysis for the 4th quarter not completed.
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TABLE 2A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1988
+
I LIOUID EFFLUENTS - SUMMATION OF ALL RELEASES 3RD 4TH EST. TOTAL A.
FISSION AND ACTIVATION PRODUCTS UNITS OVARTER OUARTER ERROR.%
1.
Total Release (not including tritium.aases. alpha)
Ci 8.62E-01 8.89E-02 2.16E+01 2.
Average diluted concentration durina period uCi/ml 1.45E-09 1.49E-10 3.
Percent of tech. spec. limit (1) 6.24E-01 2.27E-01 4.
Percent of tech.soec. limit (2) 3.12E-01 1.13E-01 5
Percent of tech.soec. limit (3) 8.13E-01 8.68E-02 6.
Percent of tech.soec limit (4) 4.06E-01 4.34E-02 l
B.
TRITIUM 1.
Total Release Ci 5.46E+01 8.34E+01 1.81E+01 2.
Average diluted concentration durina period uCi/ml 9.18E-08 1.40E-07 3.
Percent of aoolicable limit (5) 3.06E-03 4.67E-03 C.
DISSOLVED AND ENTRAINED GASES
?
1.
Total Release Ci 7.20E-02 5.92E-02 2.00E+01 2.
Average diluted concentration durina period uCi/ml 1.21E-10 9.95F-11 i
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TABLE 2A - REG GUIDE 1.21 (Cont.)
i CALVERT CLIFFS NUCLEAR POWER PLANT I
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT I
SECOND HALF - 1988 f
f LIQUID EFFLUENTS - SUPMATION OF ALL RELEASES 3RD 4TH EST. TOTAL D.
GROSS ALPHA RADI0 ACTIVITY UNITS OUARTER OUARTER ERROR.%
(
1.
Total Release Ci
<8.18E-05
<3.25E-04 3.00E+00 l
l
.E.
VOLUME OF WASTE RELEASES forior-to dilution) liters 4.38E+06 6.66E+06 3.00E+00 1
F.
VOLUME OF DILUTION WATER USED DURING PERIOD liters 5.95E+11 5.95E+11 1.40E+01-NOTES TO TABLE 2A (1). Percent of I.C.3 Quarterly Organ Dose Limit (10 mrem)
(2)
Percent of I.C.3 Yearly Organ Dose Limit (20 mrem)
(3) Percent of I.C.3 Quarterly Whole Body Dose Limit (3 mrem)
(4) Percent of I.C.3 Yearly Whole Body Dose Limit (6 mrem)
(5) Limit used is 3 x 10-3 uti/ml 14
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TABLE 2B - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT-
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SECOND HALF - 1988 LIOUID EFFLUENTS CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS OVARTER OVARTER QUARTER QUARTER Sodium Ci (1)
(1) 1.69E-04 1.02E-05 Chromium
-51 Ci (1)
(1) 4.36E-03 (2)
Manaanese'
-54 Ci (1)
(1) 1.23E-03 5.25E-04 Cobalt
-58 Ci (1)
(1) 4.57E-02 7.18E-03 Iron
-59 Ci (1)
(1)
(2)
(2)
-60 Ci (1)
(1) 7.85E-03 3.07E-03 Zint
-65 Ci (1)
(1)
(2)
(2)
-89 Ci (1)
(1) 1.80E-03 (3)
-90 Ci (1)
(1)
<l.31E-04.,
(3)
-95 Ci (1)
(1) 1.71E-03 2.55E-03 Niobium
-95 Ci (1)
(1) 5.02E-03 2.66E-03 Niobium
-97 Ci (1)
(1) 1.15E-02 1.23E-04 Tgghnicium
-99m Ci (1)
(1) 1.02E-03 4.22E-05 Ruthenium
-103 Ci (1)
(1)
(2) 1.50E-04 Cadmium
-109 C1 (1)
(1)
(2) 1.97E-04 Silver
-110m Ci (1)
(1) 1.36E-02 1.74E-03 Tin
-113 Ci (1)
(1) 9.00E-04 7.78E-04 Antimony
-124 Ci (1)
(1) 1.35E-03 2.92E-03 Antimony
-125 Ci (1)
(1) 2.73E-02 1.53E-02 Iodine
-131 Ci (1)
(1) 3.78E-02 9.00E-03 l
-132 Ci (1)
(1) 7.74E-06 (2)
]
i 15 l
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TABLE 28 - REG GUIDE 1.21 (Cont.)
CALVERT CLIFFS NUCLEAR POWER PLANT I'
EFFLUENT'AND WASTE DISPOSAL SEMI-ANNUAL REPORT' L
SECOND HALF - 1988
-LIOUID EFFLUENTS CONTINUOUS MODE BATCH MODE l
3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS OUARTER 00ARTER OUARTER DUARTER Iodine
-133 Ci (1)
(1) 1.06E-02 1.68E-03 j.
-135 C1 (1)
(1) 2.67E-04 (2)
-134' C1 (1)
(1) 1.97E-01 9.27E-03 Cesium
-136 Ci (1)
(1) 5.58E-04 (2)
-137 C1 (1)
(1) 4.92E-01 2.78E-02 Barium
-140 Ci (1)
(1)
(2) 1.72E-05 Cerium
-141 Ci (1)
(1)
(2)
(2)
-144 C1 (1)
(1) 2.74E-05, P.118E-03 Lanthanum
-142 C1 (1)
(1)
(2) 1.66E-03 Mercury
-203 Ci (1)
(1)
(2) 5.28E-05 Total For Period C1 (1)
(1) 8.62E-01 8.89E-02 I
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r TABLE 28 - REG GUIDE 1.21 (Cont.)
CALVERT CLIFFS NUCLEAR POWER PLANT i
EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT SECOND HALF - 1988 LIOUID EFFLUENTS CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS OVARTER QUARTER DUARTER QUARTER Krvoton
-85m Ci (1)
(1)
(2) 1.47E-05 Krvoton
-88 Ci (1)
(1) 6.70E-04 (2)
-131m Ci (1)
(1)
(2) 5.39E-04 Xenon
-133 Ci (1)
(1) 7.00E-02 5.80E-02 Xenon
-133m C1 (1)
(1) 6.87E-05 2.89E-04 Xenon
-135 Ci (1)
(1) 1.31E-03 3.50E-04 Total For Period Ci (1)
(1) 7.20E-02 5.92E-02 (1) There were no continuous liquid releases during the 3rd and 4th quarters.
(2) Less than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillance Requirement 4.11.1.1.1.
(3) Analysis for the 4th quarter not completed.
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c TABLE 3A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1988 SOLID WASTE AND IRRADIATED FUEL SHIPNENTS A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOTE IRRADIATED FUEL) 6-MONTH EST. TOTAL 1.
Tvoe of Waste UNITS PERIOD ERROR %
3 a.
Dewatered spent resin m
1.30E+01 Ci 7.02E+02 2.00E+01 3
b.
Dry Compressible Waste, m
2.22E+02 Contaminated Equipment, etc.
Ci 6.76E+00 3
c.
Irradiated Components, m
Control Rods, etc.
Ci 3
d.
Other (CVCS Filters) m Ci 2.
Estimate of Major Nuclides (By Type of Waste)*
a.
-58 3.05E+01 %
-60 1.70E+00 %
-63 5.10E+00 %
-134 1.87E+01 %
-137 4.00E+01 %
b.
-55 4.20E+01 %
-60 1.50E+01 %
-63 9.00E+00 %
-134 1.10E+01 %
-137 2.20E+01 %
- Only nuclides greater than 1% are reported 3.
Solid Waste Disposition Number of Shioments Mode of Transportation Destination 11 Motor Surface Transit Barnwell, S.C.
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