ML20034F533
| ML20034F533 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/31/1992 |
| From: | Cruse C BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20034F534 | List: |
| References | |
| NUDOCS 9303030362 | |
| Download: ML20034F533 (22) | |
Text
_ - _ _ _ _ _ _ _ _ _ _ - _ _ _ - - _ _ _ _ _ _.
CALVERT CLIFFS NUCL. EAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SUPPLEMENTAL INFORMATION Facility - Calvert Cliffs Nuclear Power Plant Licensee - Baltimore Gas & Electric Company L
REGULATORY LIMITS A.
Fission and Activation Gases 1.
The instar taneous release rate of noble gases in gaseous effluents shall not result in a site bounuary dose rate in excess of 500 mrenttear to the whole body or 3000 mrem / year to the skin (Technical Specification 3/4.11.2.1).
2.
Gascous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce gaseous emissions when the calculated gamma dose due to gaseous effluents exceeds 1.20 mrad or the calculated beta dose due to gas:ous effluents exceeds 2.40 mrad at the site boundary in a 92 day period (Technical Specification 3/4.11.2.4).
3.
The air dose at the site boundary due to noble gases released in gaseous effluents shall not exceed (Technical Specification 3/4.11.2.2):
10 mrad /qtr, gamma air 20 mrad /qtr, beta air 20 mrad & ear, gamma air 40 mradlycar, beta air 4.
All of the above parameters are calculated according to the methodology specified in the Offsite Dose Calculation Manual (ODCM).
B.
gnes and Particulates with Half Lives Greater than Eight Days 1.
The instantaneous release rate of iodines and particulates in gaseous effluents shall not result in a site boundary dose rate in excess of 1500 mrentycar to any organ (Technical Specification 3/4.11.2.1).
l 2.
The Gaseous Radwaste Treatment System and the Ventilation Exhsust Treatment System shall be used to reduce radioactive materials in gaseous effluents when calculated doses exceed L8 mrem to any organ in a 92 day period at or beyond the site boundary (Technical Specification 3/4.11.2.4).
3.
'Ihe dose to a member of the public at or beyond the site boundary from iodine-131 and particulates with halflives greater than eight days in gaseous effluents shall not exceed (Technical Specification 3/4.11.23):
15 mrem!qtr, any organ 30 mrem / year, any organ 9303030362 930226 PDR ADDCK 05000317 j
R PDR
less than 0.1% of the above limits as a result of burning contaminated oil.
4.
All of the above parameters are calculated according to the methodology specified in the ODCM.
C.
Liouid Ef0uents 1.
The concentrations of radionuclides in liquid effluents from the plant shall not exceed the values specified in 10 CFR Part 20, Appendix B, for unrestricted areas (Technical Specification 3/4.11.1.1).
2.
He liquid radwaste treatment system shall be used to reduce the concentration of radionuclides in liquid ef0uents 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 (Technical Specification 3/4.11.1.3).
3.
The dose to a member of the public in unrestricted areas shall not exceed (Technical Specification 3/4.11.1.2):
3 mrem /qtr, total body 10 mrem /qtr, any organ 6 mrem & ear, total body 20 mrem & ear, any organ 4.
All of the liquid dose parameters are calculated according to the methodology specified in the ODCM.
II.
MAXIMUM PERMISSIHIE CONCENTRATIONS A.
Fission and Activation Gases Prior to the batch release of gaseous effluents, a sample of the source is collected and analyzed by gamma spectroscopy for the principal gamma emitting radionuclides.
The iaentified radionuclide concentrations are evaluated and an acceptable release rate is determined to ensure that the dose rate limits of Technical Specification 3/4.1L2.1 are not exceeded.
B.
Todines and Part' ulates with Half Lives Greater than Eicht Days Compliance with the dose rate limitations for iodines and particulates is demonstrated by analysis of the charcoal and particulate samples of the station main vents. The charcoal samples are analyzed by gamma spectroscopy for quantification of any release of radioiodines. The particulate samples are analyzed by gamma spectroscopy for quantification of particulate radioactive material. All of the above parameters are calculated according to the methodology specified in the Offsite Dose Calculation Manual (ODCM).
I l
2
4 i
C.
Liouid Efnuents The MPCs used for radioactive materials released in liquid ef0uents are in j
accordance with Technical Specification 3/4.11.1.1 and the values from 10 CFR 20,
)
Appendix B, including applicabic table notes. In all cases, the more restrictive -
l (lower) MPC found for each radionuclide is used regardless of solubility.
l I
i III.
TECIINICAL SPECIFICATION REPORTING REOUIREMENTS (Section 6.9.1.8) f i
A.
Previous Calendar Year (1992) Dose Assessment Summarv l
During 1992, liquid releases from Calvert Cliffs resulted in a calculated maximum j
annual organ dose of 0.40 mrem and a maximum whole body dose of 0.08 mrem.
[
These doses are less than 2.1% of the Technical SpeciGeation yearly organ dose limit and less than 1.3% of the Technical Specification yearly dose limit for the whole body. Rese doses were calculated using the methodology and parameters outlined in the ODCM. The controlling pathway was the fish and shellfish pathway with adult as the controlling age group, and the gastrointestinal tract representing the organ with the highest calculated dose.
j Gaseous releases of noble gases resulted in a maximum, quarterly, gamma-air dose of 0.04 mrad and a maximum, quarterly, beta-air dose of 0.11 mrad. lodines and j
particulates in gaseous effluents from Calvert Cliffs resulted in a maximum organ
{
dose of 0.48 mrem for the year via the child-infant-thyroid pathway. These doses were calculated using ODCM methodology. For 1992, calculated off-site doses via the gaseous' release pathways were bek)w 1.6% of their allowable Technical Specification limits.
B.
40 CFR 190 Total Dose Compliance 1
Based upon all releases for 1992 and the ODCM calculations, the maximum exposed l
individual would receive less than 2% of the allowable dose. During 1932, there were i
no on-site sources of direct radiation that would have contributed to a significant or i
measurable off-site dose. The direct radiation contribution is measured by both on-site and off-site thermoluminescent dosimeters (TLDs). The results of these measurements did not indicate any statistical increase in off-site radiation doses attributable to on-site sources. Therefore, no increase in the off-site calculated dose is attributable to the direct exposure from on-site sources. A more detailed l
evaluation will be reported in the Annual Radiological Emironmental Operating l
Report.
C.
Solid Waste Report Reauirements During the second half of 1992. the types of radioactive solid waste shipped from Calvert Cliffs were radioactive resin, which was dewatered and shipped in high integrity containers, low level radioactive resin which was dewatered and shipped in i
strong, tight containers, dry compressible waste, which was shipped as LSA waste in strong, tight containers, and irradiated waste which was shipped in a high-integrity l
steel container. Appendix A provides a detailed breakdown of the waste shipments for the second half of 1992 per the categories specified in Technical Specification 6.9.1.8.
j i
3 i
t I
i D.
ODCM and Process Control Procram (PCP) Chances One change was made to the ODCM during the second half of 1992. The change was reviewed by POSRC and approved by the Plant General Manager, Cahrrt Cliffs Nuclear Power Plant, prior to implementation. The scope and basis for this change is discussed in Appendix B.
In keeping with the requirement of the Technical 1
Specification 6.17, a copy of the approved change to the CCNPP ODCM is enclosed l
in Attachment 1.
l No changes were made in the PCP in the second half of 1992.
E.
Radioactive Gaseous Effluent Monitorine Instrumentation
-l None of the Technical Specification effluent monitors were out of service for greater l
3 than 30 days.
i l
IV.
AVERAGE ENERGY Not Applicable.
i V.
MEASUREMENTS AND APPROXIMATIONS AND TOTAL RADIOACTI\\TIY j
A.
Fission and Activation Gases 1
1.
Batch Releases Prior to each batch release of gas from a pressurized gas decay tank, a sample is collected and analyzed by gamma spectroscopy using a Germanium (Ge) i detector for the principal gamma emitting noble gas radionuclides. The total i
activity released is based on the pressure / volume relationship (gas laws) of the tank.
i f
Prior to and after each centainment purge, a gas sample is collected and j
analyzed by gamma spectroscopy using a Ge detector for the principal gamma cmitting noble gas radionuclides. The total activity released is based on j
containment volume and purge rate. Activity buildup while purging is also j
j considered.
i 2.
Continuous Releases I
i i
A gas sample is collected at least weekly from the main vents and analyzed by l
]
gamma spectroscopy using a Ge detector for the principal gamma emitting j
noble gas radionuclides. De total activity released for the week is based on -
1 the total sample activity decay corrected to the sample time, multiplied by the main vent flow for the week.
f a
l 2
e 6
5
l I
A monthly composite sample is collected from the main vents and analyzed by liquid scintillation for tritium. The total tritium release for the month is based i
on this sample analysis and the vent flow.3 B.
Iodine and Particulates 1.
Batch Releases i
l The total actisities of radioiodines and particulates released from pressutized i
waste gas decay tanks, containment purges, and containment vents are accounted for by the continuous samplers on the main vent.
l 2.
Continuous Releases During the release of gas from the main vents, samples of iodines and l
particulates are collected using a charcoal and particulate filter, respectively.
The filters are removed weekly and are analyzed by gamma spectroscopy
{
using a Ge detector for significant gamma emitting radionuclides. The total j
activity released for the week is based on the total sample activity decay -
corrected to the midpoint of the sample period multiplied by the main vent -
l flow for the week. These weekly particulate filters are then composited to form monthly and quarterly composites for the gross alpha and strontium 89 and 90 analyses.
I C.
Liauid Effluents 1.
Batch Releases
~
Prict to the release of liquid from a waste tank, a sample is collected and j
analyzed by gamma spectroscopy for the principal gamma emitting
)
radionuclides. To demonstrate compliance with the requirements addressed j
in Section I.C.1 above, the measured radionuclide concentrations are compared with the allowable MPCs; dilution in the discharge conduit is considered, and an allowable release rate is verified.
b 1
Analysis results from the tritium sample for October 1992 erroneously indicated main vent tritium concentrations several orders of magnitude larger (i.e.,1E7 uCi/cc) than the concentrations normally experienced (i.e., IE10 uCi/cc).
This erroncous analysis result was thought to te hnked to a plant evolution where a pressure relief valve on the steam generator blowdown tank discharged secondary side steam to the plant vent stack. 'lhis steam saturated the tritsum sampler's sihca gel. It is postulated that at some point in time - cither before sample collection or after sample collecuoi:- the sample was contaminated.11 is hypothesir.ed that this contamination was the source of the erroneous analysis rea ult. 'Ihe plant data which supports this hypothesis is as follows. (1) The primary to secondary leak rate did not change significantly during the September / October timeframe, (2) the tritium concentration in the liquid radmaste i
processing s estem did not change significantly during the September / October timeframe, and (3) there were no indications < f commensurate increases in the concentrations of any other radionuchdes in the plant vent during the September /3ctober timeframe. In heu of reporting the erroneous analysis results,it was determined that the tntium concentratons from the previous or fo!!owing months (i.e., Septemter or November)- whichever was greater -- would i
be used to acmunt for the tritium actrvity released from the Unit 1 plant vent stack during October 1992. Since the September, Unit 1, plant vent stack tritium concentration (i.e.,6.41E-10 uCi/cc) was greater than the November, Unit 1 plant vent stack tritium concentration (3.32E-11 uCi/cc), the September value was chosen as the best estimate for the October, Unit 1 plant vent stack tritium concentration.
l J
l 5
,__,m_
=
The total activity released in each batch is determined by multiplying the volume released by the concentration of each radionuclide. The actual volume released 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 the gross alpha, strontium 89 and 90, and tritium analyses.
2.
Continuous Releases i
I Paior to discharge of any continuous releases, a sample is collected and analyzed by gamma spectroscopy for the principal gamma emitting radionuclides. The measured radionuclide concentrations are compared with the allowable MPC concentrations in the discharge conduit, and an allowable release rate is verified.
i When steam generator blowdown is discharged to the circulating water i
conduits, it is sampled daily and these samples are used in turn to prepare a i
weekly blowdown composite sample based on each day's blowdown. The weekly composite sample is analyzed by gamma spectroscopy for the principal gamma emitting radionuclides. 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 quarterly composites for tritium, gross alpha, and strontium 89 and 90 analyses.
During primary to secondary leakage, the secondary system becomes contaminated and subsequently, contaminates the turbine plant sumps. This low-level activity water (predominately tritium) is released directly to the Chesapeake Bay. This water is sampled at least weekly and composited.
These samples are added to a composite based on the amount released during that week. The composite sample is analyzed monthly for tritium and principal gamma emitting radionuclides. The results are multiplied by the actual quantity ofliquid released to determine the total activity released. This composite is used to prepare quarterly samples for strontium 89 and 90 i
analyses.
D.
Estimation of Total Error i
Total error for all releases was estimated using, as a minimum, the random counting error associated with typical releases. In addition to this random error, the following systematic errors were also examined:
1.
Liquid Error in volume of liquid released prior to dilution during batch a.
releases.
l b.
Error in volume ofliquid released via steam generator blowdown.
Error in amount of dilution water used during the reporting period.
c.
i 6
2.
Gases a.
Errorin main vent release flow.
b.
Error in sample flow rate.
f I
c.
Error in containment purge release flow.
i d.
Error in gas decay tank pressure.
i I
Where errors could be estimated they are usually considered additive.
i i
f i
i 9
9 i
l
.i i
5 i
n 8
i t
l l
1
)
I 1
l i
)
I h
i I
I l
t 9
7 i
r I
VI.
IIATCII RELEASES r
1992 3RD 4TII OUARTER OUARTER A.
Liould 1.
Number of batch releases 1.25E+02 1.24E+02 2.
Total time period for batch
[
releases (min) 1.33E+ 04 2.04E+04 3
Maximum time period for a batch release (min) 6J52E+02 1.30E+03 4.
Average time period for batch releases (min) 1.06E+ 02 1.65E+ 02 5.
Minimum time period for a batch release (min) 2.00E+00 2.00E+00 6.
Average stream Dow during periods of effluent into a flowing stream (liters / min of dilution water) 4.47E+06 4.48E+06 l
11.
Gaseous 1.
Number of batch releases 2.50E+01 1.10E+01 2.
Total time period for batch releases (min) 4.14E+04 5.00E+03 P
3.
Maximum time period for a batch l
release (min) 7.60E+ 03 2.54E+03 j
4.
Average time period for batch release (min) 1.65E +03 4.54E +02 5.
Minimum time period for a batch i
release (min) 3.50E+01 1.50E+01 l
I f
I h
l r
I 8
I
-1
?
VII.
ABNORMAL RELEASES i
1992 3RD 4TII i
OUARTER OUARTER
[
r A.
Liould i
1.
Number of releases -0--
l 2.
Total activity released (Curies),
11.
Gaseous j
1.
Number of releases,
f 2.
Total activity releases (Curies) :
I i
t I
l l
i r
i t
I I
9
e TAllLE I A - REG GUIDE 1.21 f
CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEh11-ANNUAL REPORT SECOND IIALF-1992 G ASEOUS EFFLUENTS - SUNINIATION OF ALL RELEASES t
l 3RD 4TII EST. TOTAL A. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER ERROR, %
i 1.
Total Release Ci 2.8SE+01 9.57E+01 5.40E+00 2.
Average release rate for period uCi/sec 3.62E+00 1.20E+01 3.
Percent of Tech. Spec. limit (1) 6.17E-04 3.04E-03 l
4.
Percent of Tech. Spec. limit (2) 8.19E-04 3.11E-03 5.
Percent of Tech. Spec. limit (3)
G 8.84E-03 4.29E-02 6.
Percent of Tech. Spec. limit (4)
G 4.42E-03 2.14E-02 7.
Percent of Tech. Spec. limit (5) 2.71E-02 8.82E-02 8.
Percent of Tech. Spec. limit (6) 1.36E-02 4.41E-02
- 11. IODINES 1.
Totallodine - 131 Ci 6.67E-04 7.55E-04 16.50E+00 2.
Average release rate for period uCi/sec 8.39E-05 9.50E-05 3.
Percent of Tech. Spec. limit (7) 1.99E-04 2.26E-04 4.
Percent of Tech. Spec. limit (8) 5.02E-03 5.69E-03 5.
Percent of Tech. Spec. limit (9) 2.51E-03 2.84E-03 C. PARTICUlATES 1.
Particulates with halflives greater than 8 days Ci 3.21E-05 6.20E-06 i2.80E+01 2.
Average release rate for period uCi/sec 4.04E4 7.80E-07 i
3.
Percent of Tech. Spec. limit ('7) 5.26E-07 1.04E-07 4.
Percent of Tech. Spec. limit (8) 3.56E-04 6.81E-05 5.
Percent of Tech. Spec. limit (9) 1.78E-04 3.40E-05 6.
Gross alpha radioactivity Ci 4.60E-10 (10) 5.36E+01
)
10
i TAllLE 1 A - REG GUIDE 1.21 (Continued) i CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND IIALF-1992 l
GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES l
t 3RD 4TII EST. TOTAL D. TRITIUM UNITS QUARTER QUARTER ERROR,%
4 1.
Total Release Ci 6.66E+00 2.28E-01 1.32E+01 2.
Average release rate for period uCi'sec 8.38E-01 2.87E-02 i
l NOTES TO TAllLE 1 A (1)
Percent of LA.1 whole body dose rate limit (509 mrem / year)
(2)
Percent ofIA1 skin dose rate limit (3000 mrem / year)
?
(3)
Percent of LA.3 gamma quarterly dose limit (10 mrad)
(4)
Percent ofI.A.3 gamma yearly dose limit (20 mrad)
(5)
Percent of I.A 3 beta quarterly dose li. nit (20 mrad)
(6)
Percent ofI.A.3 beta yearly dose limit (40 mrad)
(7)
Percent ofI.B.1 organ dose rate limit (1500 mrem / year)
(8)
Percent ofI.B.3 quarterly organ dose limit (15 mrem)
(9)
Percent of I.B.3 yearly organ dose limit (30 mrem) l (10)
Less than minimum detectable activity which meets the LLD requirements of i
Technical Specification Surveillance Requirement 4.11.2.1.2.
i i
i l
1 11 1
l TAllLE IC - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PIANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND llALF-1992 G ASEOUS EFFLUENTS - GROUND LEVEL RELEASES i
CONTINUOUS MODE IIATCII MODE 3RD 4Til 3RD 4Til
- 1. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER QUARTER QUARTER Argon
-41 Ci (2)
(2) 3.56E-03 (2)
-85 Ci (2)
(2) 5.30E+00 8.24E-01 Krypton
-85m Ci (2) 5.92E-01 1.19E-04 (2)
-87 Ci (2)
(2)
(2)
(2)
I Kryton
-88 Ci (2)
(2)
(2)
_(2) l Xenon
-131m Ci (2)
(2) 2.44E4)1 2.40E-03 Xenon
-133 Ci 1.06E+ 01 7.65E+ 01 9.81 E+00 2.57E4)1 Xenon
-133m Ci (2)
(2) 7.71E-02 2.10E-03 Xenon
-135 Ci 2.71E+00 1.75E+ 01 4 RIE-02 3.55E-03 Xenon
-138 Ci (2)
(2)
(2)
(2)
Total for Period Ci 1.33E+ 01 9.46E + 01 1.55E+ 01 1.09E+ 00 1
- 2. IIALOGENS Iodine
-131 Ci 6.66E-04 7.55E-04 7.43E-07 (1)
{
-133 Ci 1.33E-03 2.94E-03 (1)
(1) i Total For Period Ci 2RIE-03 3.70E-03 7.43E-07 (1)
't J
12
i TAllLE IC - REG GUIDE 1.21 (Continued)
CALVERT CLIFFS NUCLFAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND IIALF-1992 G ASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE IIATCII MODE I
l 3RD 4TII 3RD 4TII
- 3. PARTICULATES UNITS QUARTER QUARTER QUARTER QUARTER j
-54 Ci (2)
(2)
(1)
(1)
-59 Ci (2)
(2)
(1)
(1)
-58 Ci (2)
(2)
(1)
(1)
-60 Ci (2)
(2)
(1)
(1)
Zine
-65 Ci (2)
(2)
(1)
(1) i Strontium
-89 Ci (2)
(2)
(1)
(1)
-90 Ci (2)
(2)
(1)
(1)
-99 Ci (2)
(2)
(1)
(1)
-134 Ci (2)
(2) 2.35E-06 (1)
-137 Ci 2.65 E-05 6.20E-06 3.26E-06 (1)
Ccrium
-141 Ci (2)
(2)
(1)
(1)
-144 Ci (2)
(2)
(1)
(1)
Gross Alpha Radioactivity Ci 4.60E-10 (2)
(1)
(1) i Total For Period Ci 2.65E-05 6.20E4)6 5.61 E-06 (1)
NOTES TO TAllLE 1C (1)
Iodines and particulates 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.
t l
13
TAllLE 2A ~ REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PIANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND 11ALF-1992 LIOUID EFFLUENTS-SUMMATION OF ALL RELEASES 3RD 4Til EST. TOTAL A. FISSION AND ACTIVATION PRODUCTS UNITS QUARTER QUARTER ERROR, %
l.
Total Release (not including i
tritium, gases. alpha)
Ci 6.16E-01 4.66E-01 13.30E+00 2.
Average diluted concentration during period uCi/mi 4.43E-09 2.48E-09 3.
Percent of Tech. Spec. limit (1)
Fo 2.88E+ 00 7.20E.01
}
4.
Pert.;nt of Tech. Spec. limit (2)
Fc 1.44E+00 3.60E-01 5.
Percent of Tech. Spec. limit (3)
Fo 5.12E-01 7.80E-01 6.
Percent of Tech. Spec. limit (4)
Fc 2.56E-01 3.90E-01
- 11. TRITIUM r
1.
Total Release Ci 1.14E+ 02 1.89E+02 19.80E+00 2.
Average diluted concentration L
during period uCi/ml 8.20E-07 1.00E-06
[
3.
Percent of applicable limit (5)
'l 2.73E 3.35E-02 I
a C. DISSOLVED AND ENTRAINED GASES 1.
Total Release Ci 8.58E-02 1.% E-01 14.60E+00 l
2.
Average diluted concentration during period uCi/ml 6.17E.10 1.04E-09 i
e l
i 6
5 s
14
TAllLE 2A - REG GUIDE 1.21 (Continued)
CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND llALF.1992 i
LIOUID EFFLUENTS - SUMM ATION OF ALL RELEASES t
I 3RD 4TII EST. TOTAL D. GROSS ALPIIA RADIOACTIVITY UNITS QUARTER QUARTER ERROR, %
l 1.
Total Release Ci 1.02E-04 (6) l 1
E. VOLUME OF WASTE REI EASED I
(prior to dilution) liters
- 6. CME +07 7.05E+07 11.30E+00 F. VOLUME OF DILUTION WATER USED
?
DURING PERIOD liters 1.39E+ 11 1.88E+11 11.64E+01 i
?
NOTES TO TAllLE 2A I
(1)
Percent ofI.C.3 Quarterly Organ Dose Limit (10 mrem) to maximum exposed organ a
(2)
Percent of LC.3 Yearly Organ Dose Limit (20 mrem) to maximum exposed organ (3)
Percent of LC3 Quarterly Whole Body Dose Limit (3 mrem)
(4)
Percent of LC3 Yearly Whole Body Dose Limit (6 mrem)
(5)
Limit used is 3 x 10-3 uCi/ml (6)
Less than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillance Requirement 4.11.1.1.1.
L I.
r 1
f i
?
P 15 P
_ _ ~
i TAllLE 2H - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND ILALF-1992 i
LIOUID EFFLUENTS f
CONTINUOUS MODE IIATCII MODE 3RD 4Til 3RD 4Til NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Sodium
-24 Ci (1)
(1) 1.77E-04 6.18E4M Chromium
-51 Ci (1)
(1) 3.12E-02 1.14E-02 Manganese
-54 Ci (1)
(1) 736E-03 335E-03 i
Cobalt 57 Ci (1)
(1) 7.61E-05 (1) l Cobalt
-58 Ci (1)
(1) 1.24E-01 436E-02 l
i Iron
-59 Ci (1)
(1) 3.81E-04
-(1)
-60 Ci (1)
(1) 3.89E-02 1.73E-02 j
Zine
-65 Ci (1)
(1) 5.58E-05 (1) 3 Strontium
-89 Ci 6.17E-08 (1) 3.61E-04 (1)
-90 Ci 6.62E-OS (1) 3.87E-04 3.85E-08 Strontium
-92 Ci (1)
(1) 7.56E-05 3.50E-06 Niobium
-95 Ci (1)
(1) 4.40E-02 8.50E-03 4
-95 Ci (1)
-97 Ci (1)
(1) 7.10E-04 1.47E-03 Zirconium
-97 Ci (1)
(1)
(1) 3.55E-04 Molybdenum
-99 Ci (1)
(1)
(1)
(1)
-99m Ci (1)
(1) 2.26E-04 6.50E-04 Rutheniem
-103 Ci (1)
(1) 3.16E-03 3.87E.04 Ruthenium
-106 Ci (1)
(1) 7.4SE-03 1.89E-03 Sihcr
-110m Ci (1)
(1) 930E-03 5.99E-03 J
'lin
-113 Ci (1)
(1) 5.75E-03 4.85E-04 Antimony
-122 Ci (1)
(1) 6.50E-05 8.11E-04
)
i 16
]
I
'fI4LE 2Il-REG GUIDE 1.21 (Continued)
CALVERT CLIFFS NUCLEAR."OWER PIANT EFFLUENT AND WASTE DISPOSAL SEMI. ANNUAL REPORT SECOND IIALF-1992 LIOUID EFFLUENTS i
CONTINUOUS MODE BATCII MODE 3RD 4TII 3RD 4Til NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Antimony
-124 Ci (1)
(1) 3.17E-04 (1)
-125 Ci (1)
(1) 1.06E-02 7.43E-05 Tellurium
-127 Ci (1)
(1) 2.10E-03 (1) i i
-129 Ci (1)
(1) 4.73E4)4 (1) lodine
-131 Ci (1)
(1) 1.51 E-O'
-133 Ci (1)
(1) 6.44E-03 1.22E-02 l
-135 Ci (1)
(1) 6.20E-04 (1) i Cesium
-134 Ci 8.32E-07 4.31 E-07 1.02E-01 1.40E-01 Cesium
-136 Ci (1)
(1) 1.02E4)3 7.00E-04 Cesium
-137 Ci 8.59E-07 4.51 E-05 1.68E-01 1.83E-01
[
-139 Ci (1)
(1) 1.27E-04 1.77E-04 Barium
-140 Ci (1)
(1)
(1) 9.68E-04
[
-139 Ci (1)
(1) 8.27E-06 1.15E415 Lanthanum
-140 Ci (1)
(1) 4.0SE-04 1.97E-03 Cerium
-141 Ci (1)
(1) 1.59E4)4 (1)
-144 Ci (1)
(1) 1.15E-02 4.79E-03 l
-187 Ci (1)
(1)
(1)
(1)
Total For Period Ci L82E-06 4.55E-05 6.16E-01 4.66E-01 4
-131m Ci (1)
(1) 2.16E-05 2.01E-04 l
-133 Ci (1)
(1) 8.41E-02 1.91E-01 Xenon
-133m Ci (1)
(1)
(1) 1.33E-03 17 f
i
i i
TAllLE 211 - REG GUIDE 1.21 (Continued)
CALVERT CLIFFS NUCLEAR POWER PLANT I
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND llALF-1992 L10UID EFFLUENTS CONTINUOUS MODE BATCll MODE 3RD 4Til 3RD 4TII NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Xenon
-135 Ci (1)
(1) 3.60E-04 3.37E-03 l
-135m Ci (1)
(1) 1.28E-03 (1) t Total For Period Ci (1)
(1) 8.58E-02 1.96E-01 l
[
t t
i NOTES TO TAllLE 2Il (1) less than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillance Requirement 4.11.1.1.1.
i s
b i
j l
9 t
h 18
1 TAllLE 3A i
i CALVERT CLIFFS NUCLEAR POWER P1 ANT EFFLUENT AND WASTE DISPOSAL SE5fl-ANNUAL REPORT l
SECOND llALF-1992 I
SOLID WASTE AND IRRADIATED FUEL SIIIPS1ENTS A. SOLID WASTE SillPPED OFFSITE FOR llDRIAL OR DISPOSAL (NOTIRRADI ATED FUEL) 6-510NTil EST. TOTAL
- 1. Type of 0 vte UNITS PERIOD ERROR %
3 a.
Dewatered spent resin m
1.36E+01 Ci 4.12E+02
+2.00E +01 i
3 b.
Dry Compressible Waste (Shipped) m 7.14E+02 l
Contaminated Equipment, etc.
Ci 1.83E-00 5.00E+01 i
3 c.
Irradiated Components, m
1.04E+00 l
Control Rods, etc.
Ci 5.75E+ 03 15.00E+01 3
d.
Other (Cartridge Filters) m 1.02E+01 Ci 2.01E+00 2.00E+01 l
2.
Estimate of 51ajor Nuclides (By Type of Waste - Only nuclides >1 % are reported) l a.
l Fe-55 1.25E+ 00re Co-58 5.48E+00%
Co-60 1.15E+ 00Fc Ni-63 8.82E +00Tc Cs-134 3.26E+017c 4
Cs-137 4.91E+ 017c j
i b.
C-14 1.99E+ 007c Cr-51 9.36E+00rc 1
Fe-55 3.45E+ 019e Co-58 1.4SE+ 00%
l Co-60 9.82E + 00%
l Ni-63 1.27E+ 017c Nb-95 1.01E+ 00Fo l
Ru-106 2.45E+00To Ag-110m 1.37E+00rc Sb-125 4.62E+ 0Fc Cs-134 2.63E+00rc Cs-137 1.04E+ 019c Cc-144 1.97E + 00%
i i
19
?
I TAllLE 3A CALVERT CL IFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND ILALF-1992 i
SOLID WASTE AND 1RRADIATED FUEL SillPMENTS (C<mtinued) j A. SOLID WASTE SillPPED OFFSITE FOR IlURIAL OR DISPOSAL (NOTIRRADIATED FUEL) i 2.
Estimate of Major Nuclides (By Type of Waste - Only nuclides > 1 % are reported) (Continued) f c.
Mn-54 4.39E+007c j
Fe-55 5.83E +0! cc Co-58 1.4SE + 007c j
Co-60 3.27E + 017c Ni-63 1.63E + 007c l
f d.
C-14 8.80E+ 007c Fe-55 4.63E+ 017c j
Co-60 9.30E + 007c Ni-63 1.05E +01%
Ru-106 2.20E+007c Sb-125 2.20E+ 007c Cs-137 1.80E +007c l
Cc-144 1.21E+017c Pu-241 3.30E+ 007c i
3.
Solid Waste Disposition j
l Number of Shir>ments Mode of Transportation Destination
)
10 Motor Surface Transit Chem Nuclear Systems,Inc.
Barnwell, SC l
3 Motor Surface Transit Scientific Ecology Group i
Oak Ridge, TN
]
I t
20
1 APPENDIX A SOLID RADWASTE SillPMENT DATA FOR SEMI-ANNUAL EFFLUENT RELEASE REPORTING SECOND IIALF-1992 l
1TPE WASTE: DAW 10 CFR 61 WASTE CLASS: A SOURCE OF WASTE: Radiologically Controlled Areas l
SillPPING CONTAINER: 40' Sealand Containers TOTAL CURIE QUANTI 1Y: 1.83 Ci IIOW DETERMINED: Dose to curie content, conversion by volume based on generic distribution and scaling factors 3
TOTAL SillPPED WASTE VOLUME: 25230 ft IIOW DETERMINED: Container volume and number of containers shipped SOLIDIFICATION AGENT OR AllSORIIENT: None I
i I
L TYPE WASTE: Dewatered Resin 10 CFR 61 WASTE CLASS: C SOURCE OF WASTE: Miscellaneous Liquid Radwaste Processing /CVCS Processing l
3 SilIPPING CONTAINER: High Integrity L-8-120 liner (120.3 ft )
TOTAL CURIE QUANTIIT: 398 Ci IIOW DETERMINED: Gamma scan using sample of resin. Conversion by weight based on radionuclide distribution and scaling factors.
3 TOTAL SIIIPPED WASTE VOLUME: 360 9 ft 1
IIOW DETERMINED: Container volume and number of containers shipped l
SOLIDIFICATION AGENTOR AllSORIIENT: None A-1 1
APPENDIX A SOLID RADWASTE SIIIPMENT DATA FOR SEMI ANNUAL EFFLUENT RELEASE REPORTING SECOND llALF-1992
'IYPE WASTE: Dewatered Resin 10 CFR 61 WASTE CIASS: B SOURCE OF WASTE: Miscellaneous Liquid Radwaste Processing /CVCS Processing 3
SillPPING CONTAINER: Iligh Integrity L-8-120 liner (120.3 ft )
TOTAL CURIE QUAN'ITIT: 13.8 Ci IIOW DETERMINED: Gamma scan using sample from resin. Conversion by weight based on radionuclide distribution and scaling factors.
3 TOTAL SIIIPPED WASTE VOLUME: 120.3 ft IlOW DETERMINED: Volume of container and number of containers shipped SOLIDIFICATION AGENT OR AllSORilENT: None TYPE WASTE: Irradiated liardware 10 CFR 61 WASTE CLASS: C l
SOURCE OF WASTE: In-core instrumentation SilIPPING CONTAINER: Ifigh Integrity Steel Container i
TOTAL CURIE QUAN'ITIY: 5.75E+03 Ci llOW DETERMINED: Calculation based on material's composition and neutron activation
{
3 l
TOTAL SillPPED WASTE VOLUME: 3.66E+01 ft IIOW DETERMINED: Volume of container and number of containers shipped SOLIDIFICATION AGENT OR AllSORI! ANT: None l
t I
4 A.2 i
i
APPENDIX A SOLID RADWASTE SilIPMENT DATA FOR SEMI-ANNUAL, EFFLUENT RELEASE REPORTING SECOND IIALF-1992 TYPE WASTD Cartridge Filters 10 CFR 61 WASTE CLASS: C l
SOURCE OF WASTD Liquid waste processing filters 3
SIIIPPING CONTAINER: High Integrity L-8-120 Liner (120 ft )
f TOTAL CURIE QUANTITY: 2.01 Ci IIOW DLTERMINED: Dose to curie content, conversion by weight based on generic distribution and scaling factors 3
TOTAL SillPPED WASTE VOLUME: 360.9 ft
)
IlOW DEFERMINED: Container volume and number of containers shipped SOLIDIFICATION AGENT OR AllSORIlANT: None I
h l
i l
i t
f A-3 l
l APPENDIX 11
SUMMARY
OF ClLANGES TO Tile CCNPP ODCM SECOND llALF 199'
?
l l
CilANGES TO TIIE CCNPP ODCM IN SECOND llALF 1992 j
SUMMARY
AND !! ASIS A major revision of the ODCM was approved on July 27,1992. The revision was controlled by the normal procedure change process. The change was reviewed by the Plant Operations and Safety
[
Resiew Committee (POSRC) and was approved by the Plant General Manager, Calvert Cliffs Nuclear Power Plant, prior to implementation. This process meets the requirements of CCNPP Technical Specification 6.17.
This revision of the ODCM represents a significant change in format; however, the methodologies outlined in the previous ODCM remain unchanged. The new formatting greatly improves the clarity j
and organization of the document. A copy of the revised ODCM is attached to this report.
This revision of the ODCM was resiewed in some detail during NRC Safety Inspection INSR 93-01.
The interested reader is referred to INSR 93-01 for additional information.
i i
i I
i 7
t I
4 I
r P
l l
i 4
e H
i
1
)
)
I l
I i
1 ATTACllMENT (1) i ODCM (CI'-607) TEXT WITII l
CIIANGES t
f I
s t
b
.i I
.i t
i
?
v h
j 1
s I
I 1
h t
I k
?
I a
I a
i I
d
(
1' b
i I
t
{
i
..-