ML20210Q097

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Radioactive Effluent Release Rept,Effluent & Waste Disposal Suppl Info,Second Half of 1996
ML20210Q097
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 12/31/1996
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20210P373 List:
References
NUDOCS 9708280106
Download: ML20210Q097 (20)
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Text

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ATTACIIMENT (1)

I CALVERT CLIFFS NUCLEAR POWER PLANT

RADIOACTIVE EFFLUENT RELEASE REPORT

, EFFLUENT AND WASTE DISPOSAL-SUPPL.EMENTAL INFORMATION 4

D K 05 0317 R PDR Calvert Cliffs Nuclear Power Plant - Units 1 & 2 Independent Spent Fuel Storage Installation August 20,1997

ATTACilMENT m CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION-Fa:ility - Calvert Cliffs Nuclear Power Plant Licensee - Baltimore Gas & Electric Company

1. REGULATORY LIMITS A. Fission and Activation Gases
1. He instantaneous release rate of noble gases in gaseous emuents 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 s:.in (Offsite Dose Calculation Manual (ODCM) 3/4.11.2.1).
2. Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce gaseous emissions when the calculated gamma-air dose due to gaseous emuents exceeds 1.20 mrad or the calculated beta-air dose due to gaseous emuents exceeds 2.40 mrad at the site boundary in a 92 day period (ODCM 3/4.11.2.4).
3. The air dose at the site boundary due to noble gases released in gaseous emuents shall not exceed (ODCM 3/4.11.2.2):

10 mrad /qtr, gamma-air 20 mrad /qtr, beta-air 20 mradlycar, gamma-air 40 mrad / year, beta air

4. All of the above parameters are calculated according to the methodology specified in the ODCM.

B. lodines and Particulates with IIalf Lives Greater than Eicht Days

1. The instantaneous release rate of iodines and particulates in gaseous emuents shall not result in a site boundary dose in excess of 1500 mrem / year to any organ (ODCM 3/4.11.2.1).
2. The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous emuents when calculated doses exceed 1.8 mrem to any organ in a 92 day period at or beyond the site boundary (ODCM 3/4.11.2.4).
3. The dose to a meinber of the public at or beyond the site boundary from iodine-131 and narticulates with half lives greater than eight days in gaseous emuents shall not exceed (ODCM 3/4.11.2.3):

15 mrem /qtr, any organ 30 mrem / year, any organ less than 0.1% of the above limits as a result of burning conta.ninated oil.

4. All of the above parameters are calculated according to the methodology specified in the ODCM.

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ATTACIIMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION C. Liquid Emuents

1. The concentrations of radionuclides in liquid effluents from the plant shall not exceed the values specined in 10 CFR Part 20, Appendix B, for unrestricted areas l (ODCM 3/4.11.1,1).
2. The liquid radwaste treatment system shall be used to reduce the concentration of radionuclides in liquid effluents from the plant when the calculated dose to unrestricted areas exceeds 0.36 mrem to the whole body, or '.20 mrem to any organ in a 92 day i period (ODCM 3/4.11.1.3).
3. The dose to a member of the public in unrestricted areas shall not exceed (ODCM 3/4.11.1.2):

3 mrem /qtr, total body 10 mrem /qtr, any organ 6 mrem / year, total body 20 mrem / year, any organ

4. All of the liquid dose parameters are calculated according to the methodology specined in the ODCM.
11. MAXIMUM PERMISSillLE CONCENTRATIONS A. Fission and Activation Gases Prior to the batch release of gasecas effluents, a sample of the source is collected and analyzed by gamma spectroscopy for the principal gamma emitting radionuclides. The identified radionuclide concentrations are evaluated and an acceptable release rate is determined to ensure that the dose rate limits of ODCM 3/4.11.2.1 are not exceeded,
11. lodines and Paniculates with llatf Lives Greater than Eight 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 quanti 0 cation of any release of radiciodines. 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 specined in the ODCM.

C. Liquid Emuents The Maximum Permissible Concentrations (MPCs) used for radioactive materials released in liquid effluents are in accordance with ODCM 3/4.11.1.1 and the values from 10 CFR Part 20, Appendix B, including applicable table notes. In all cases, the more restrictive (lower) MPC found for each radionuclide is used regardless of solubility.

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ATTACllMENT (1)

-CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION III. IECllNICAL SPECIFICATION REPORTING REOUIREMENTS A. Calvert Cliffs Nuclear Power Plant (CCNPPt Technical Snecification 6.6.3

1. Second llalf 1996 Dose Assessment Summary During the second half of 1996, liquid releases from Calvert Cliffs resulted in a calculated maximum organ dose of 0.085 mrem and a maximian whole body dose of 0.0025 mrem, These doses are less than 0.43% of the ODCM yearly organ dose limit and less than 0.05% of the ODChi yearly dose limit for the whole body. The controlling pathway was the fish and shell0sh pathway with adult as the controlling age group, and the gastrointestinal tract representing the organ with the highest calculated dose during the second half of 1996, Gaseous Releases of noble gases resulted in a maximum, quarterly, gamma air dose of 0.001 mrad and a maximum, quarterly, beta air dose of 0.002 mrad. lodines and particulates in gaseous efuuents from Calvert Cliffs resulted in a maximum organ dose of 0.007 mrem for the second half of the year via the child thyroid pathway. These doses were calculated using ODChi methodology. For the second half of 1996, calculated off site doses via the gaseous release pathways were below 1% of their allowable ODChi limits.
2. 40 CFR 190 Total Dose Compliance Based upon the second half releases of 1996 and the ODChi calculations, the maximum exposed individual would receive less than 1% of the allowable dose. During the second half of calendar year 1996, there were no on-site sources of direct radiation that would have contributed to a signincant or 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 the off site radiation doses attributable to on-site sources. Therefore, no increase in the calculated offsite dose is attributed to the direct exposure from on site sources. A more detailed evaluation will be reported in the Annual Radiological Environmental Operating Report.
3. Solid Waste Report Reqt.irements During the second half of 1996, the types of radioactive solid waste shipped from Calvert Cliffs were dry compressible waste, mechanical cartridge filters, and dewatered resins which were shipped in High Integrity Containers (HICs) within NRC approved casks, Scaland containers, and steel boxes. Appendix (A) provides a detailed breakdown of the waste shipments for the second half of 1996 per the categories specified in Technical SpeciGcation 6.6.3. At CCNPP, methods of waste and materials segregation are used to reduce the volume of solid waste shipped offsite for processing, volume reduction and burial.

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ATTACHMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION

4. Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP) Changes in October 1996, the ODCM was revised to incorporate the efnuent controls of the Technical Specifications. This revision was performed in conjunction with License Amend nents 217 and 194 for Units 1 and 2, respectively, which relocated the efnuent controls from the Technical Specifications to the ODCM, in accordance with Generic Letter 89 ol. Several minor changes to the ODCM were also included in this revision.

A summary of those changes is fourd in the document. A copy of the revised ODCM is attached as Appendix (B) in accordance with Technical Specification 6.5.1.c.

Changes were made to the interdepartmental procedure RP-2-101 that contains discussion c' the PCP. The procedure was revised to reucct aamiaistrative changes i resulting from implementation of License Amendments 217 and 194 and to clarify limitations on storage of waste in the Materials Processing Facility. A summary of the changes is found in the document, a copy of which is included as Appendix (C).

B. Radioactive Gaseous Efuuent Monitoring Instrumentation None of the ODCM ef0uent monitors were out of service for greater than 30 days during the second half of 1996.

C. Independent Soent Fuel Storage Installation (ISFSIL Technical Soccincation 6.3 Five casks of spent fuel were transferred to the ISFSI during the second half of 1996. The

- casks were scaled within the confines of the Calvert Cliffs Auxiliary Building prior to transfer to the ISFSI facility No quantity of radionuclides were released to the environment during the ISFSI operation in the second half of 1996. Additional information regarding the ISFSI radiation monitoring program is included in the Annual Radiological Environmental Operation Report.

IV. AVERAGE ENERGY Not Applicable.

V, MEASUREMENTS AND APPROXIMATIONS AND TOTAL RADIOACTIVITY A. Fission and Activation Gases

1. Batch Releases Prior to each batch release of gas from a pressurized waste gas decay tank or containment, a sample is collected and analyzed by gamma spectroscopy using a Germanium (Ge) detector for the principal gamma emitting noble gas radionuclides.

The total activity released is based on the pressure / volume relationship (gas laws) of the tank.

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ATTACIIMENT m CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION

2. Continuous Releases A gas sample is collected at least weekly from the main vents and analyzed by gamma spectroscopy using a Ge detector- for the principal gamma emitting noble gas radionuclides. The total activity released for the week is based on the total sample activity decay corrected tu the sample time multiplied by the main vent Dow for the week.

l Prior to and after each containment purge, a gas sample is collected and analyzed by '

- gamma spectroscopy using a Ge detector for the principal gamma emitting noble gas radionuclides. The total activity released is based on containment volume and purge rate. Activity boildup while purging is also considered.

A monthly composite sample is collected from the main vems and analyzed by liquid scintillation for tritium. The total tritium release for the month is based a this sample analysis and the vent flow.

13. Jodine and Particulates l 1. Batch Releases The total activities of radiciodines and particulates released from pressurized waste gas decay tanks, containment purges, and containment vents are accounted for by the l continuous samplers on the main vent.

l

2. Continuous Releases During the release of gas from the main vents, samples of iodines and 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 activity released for the week is based on the l

total sample activity decay corrected to the midpoint of the sample period multiplied by

[ the main vent flow for the week. These weekly particulate filters are then composited to i form monthly and quarterly composites for the gross alpha and strontium 89 and 90 I

analyses.

C. Liquid Effluents

1. Batch Releases Prior to the release of liquid from a waste tank, a sample is collected and analyzed by gamma spectroscopy for the principal gamma emitting radionuclides. To demonstrate compliance with the requirements addressed 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.

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 difTerence 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 5

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i ATTACIIMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION quarterly composites for the gross alpha, iron 55, strontium 89 and 90, and tritium analyses.

2. Continuous Releases To account for activity from 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 condr? and an allowchte release rate is verified.

When steam generator blowdown is discharged to the circulating water conduits, it is sampled at a minimum of three times per week and these samples are used in turn to prepare a 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 composites for tritium analysis.

During periods of primary to-secondary leakage, the secondary system becomes contaminated, and subsequently contaminates the turbine building sumps. The low level activity water (predominantly tritium) contained in the turbine building sumps is released directly to the Chesapeake Bay. This water is sampled at least three times per week and composited. The composite sample is analyzed at least monthly for tritium and principal gamma emitting radionuclides. The results are multiplied by the actual quantity ofliquid released to determine the total activity released.

D, Estimation of Total Error 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
a. Error in volume ofliquid released prior to dilution during batch releases.
b. Error in volume ofliquid released via steam generator blowdown.
c. Error in amount of dilution water used during the reporting 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 erro s could be estimated they are usually considered additive.

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ATTACHMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT l RADIOACTIVE EFFLUENT RELEASE REPORT EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION VI, IIATCII RFI F ASES 1926 3RD 4Til QUARTER QUARTER A. Liquid l

1. Number of batch releases 2.40E+01 2.60E+01
2. Total time period for batch releases (min) 7.15E+03 7.82E+03 3 hiaximum time period for a batch release (min) 5.85 E+02 5.95E+02
4. Average time period for batch releases (min) 2.98E+02 3.01E402
5. hiinimum time period for a batch release (min) 2.50E+0) 2.50E+01
6. Average stream flow during periods of efiluent into a flowing stream (liters / min of dilution water) 7.67E+06 8.91 E+06 B. Gassnus
1. Number of batch releases 6.00E+00 2.00E+00
2. Total time period for batch releases (min) 2.30E+03 3.18E+04
3. hiaximum time period for a batch release (min) 1.47E+03 3.17E+04
4. Average time period for batch release (min) 3.84E+02 1.59E+04
5. hiinimum time period for a batch release (min) 7.00E+01 1.35E+02 7

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ATTACllMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT EFFLUENT AND WASTE I)lSPOSAL - SUPPLEMENTAL INFORMATION VII.' ABNORMAL REI r ASES 122fi 3RD 4TII l QUARTER QUARTER l A. Liquid

1. Number of releases 0- l
2. Total activity released (Curies) 0- D. Gascus 1, Number of releases  ! 2. Total activity releases (Curies) 1.07E+00 3 Approximately 36 m was inadvertently discharged from the Gaseous Radwaste Treatment System during September and October 1996. This abnormal release was detected when the in service decay tank pressure did not trend upward, as is expected when a decay tank is in service. Investigation revealed that the relief valve on the No.12 waste gas compressor was leaking. Subsequent to the repair of this relief valve, the waste gas surge tank relief valve was found to be leaking. Following extensive planning on how to meet the challenges ofisolating this valve from the system, the valve was successfully replaced in March 1997. The time interval fbr the abnormal release was determined to have begun when in service decay tank pressure leveled oft in September and ended in October when the release pathway was identified. From October through December, the releases via the waste gas surge tank relief valve were accounted for as a normal release.

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ATTACilMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION TABLE lA - REGULATORY GUIDE 1.21 SECOND IIALF - 1996 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES i 3RD 4Til EST. TOTAL j A. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER ERROR.}g  ;

1. Total Release i Ci I 4.50E+00 1 1.51E+01 1 1.20E+0i -
2. Average release rate for period i uCi/sec j 5.66E-01 l 1.90E+00 l
3. Percent of Technical Specification limit (1) j  % 1 1.44 E-04 I 6.06E-04 i
4. Percent of Technical Specification limit (2) l  % i 1.28E 04 1 4.86E-04 I
5. Percent of Technical Specification limit (3) I  % i 2.00E-03 i 8.38E-03 I
6. Percent of Technical Specification limit (4) I  % i 9.99E-04 i 4.19E 03 I
7. Percent of Technical Specification limit (5) l  % l 2.49E-03 1 7.95E 03 l
8. Percent of Technical Specification limit (6) i  % l 1.24 E-03 1 3.98E-03 j H. IODINES I i I i

~

1. Totallodine 131 l Ci 1 1.18E-04 1 1.17E-04 1 16.50E+00
2. Average release rate for period I uCi/sec 1 1.48E 05 i 1.47E-05 1
3. Percent of Technical Specification limit (7) i  % l 3.53E 05 i 3.50E 05 1
4. Percent of Technical Specification limit (8) l  % 1 8.89E-04 I 8.81 E-04 1
5. Percent of Technical Specification limit (9) l  % l 4.44E 04 I 4.41 E-04 i C. PARTICULATES i I j l
1. Particulates with halflives greater than 8 days Ci (10) 1.33 E-06 i2.80E+01 2, Average release rate for period i uCi/sec j (10) I 1.67E-07 1
3. Percent of Technical Specification limit (7) I  %  ! (10) i 2.25E-08 i
4. Percent of Technical Specification lirait(8) I  % i (10) I 1.46E-05 i
5. Percent of Technical Specification limit (9) l  % i (10) l 7.30E-06 i
6. Gross alpha radioactivity l Ci I (10) I (10) i N/A D. TRITIUM i l i i
1. Total Release i Ci l 1.03 E+00 l 4.60E-01 l 1.32E+01
2. Average release rate for period i uCi/sec I l .30E-01 1 5.79E 02  !

NOTES TO TABLE 1 A (1) Percent ofI.A.1 whole body dose rate limit (500 mrem / year)

(2) Percent ofI.A.I skin dose r::te limit (3000 mrem / year)

(3) Percent ofI.A.3 gamma quarterly dose limit (10 mrad)

(4) Percent of1.A.3 gamma yearly dose limit (20 mrad)

(5) Percent ofI.A 3 beta quarterly dose limit (20 mrad)

(6) Percent ofI.A.3 beta yearly dose limit (40 mrad)

(7) Percent of1.B.1 organ dose rate limit (1500 mrem / year)

(8) Percent ofi B.3 quarterly organ dose limit (15 mrem)

(9) Percent of1.D.3 yearly organ dose limit (30 mrem)

(10)_ Less than minimum detectable activity which meets the LLD requirements of ODCM Surveillance Requirement 4.11.2.1.2.

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ATTACIIMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT EFFLUENT AND WASTE DISPOSAL - SUPPLE 31 ENTAL INFORMATION TABLE IC - REGULATORY GUIDE 1.21 SECOND IIALF - 1996 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES i CONTINUOUS MODE l HATCil- MODE 3RD 4Til 3RD 4Til

1. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER QUARTER QUARTER Argon -41 Ci I (2) i (2) I (2) i (2)

Krypton -85 I Ci i (2) l (2) I 1.05E+00 1 7.86E 01 Krypton -85m l Ci I (2) I (2) I (2) I (2)

Krypton -87 I Ci j (2) l (2) i (2) I (2)

Krypton 88 i Ci I (2) I (2) i (2) I (2)

_ Xenon -131m i Ci I (2) l (2) l (2) 1 5.92E 03 Xenon -133 i Ci l 2.13 E+00 l 9.38E+00 i 2.76E-01 1 4.72E-01 Xenon -133m  ! Ci I (2)  ! (2) i 1.43 E-03 l 6.86E-03 Xenon -135 i Ci i 1.04 E+00 1 4.43 E+00 l 3.28E-04 1 6.39E-03 Xenon -138 I Ci I (2)  ; (2) I (2) I (2)

Total for Period I Ci I 3.17E+00 1 1.38 E+01 l  ! .33 E+00 l 1.28E+00

3. IIALOGENS I I I l l lodine 131 l Ci l 1.18E 04 1 1.17E 04 l (1) I (1) lodinc -133 I Ci l 1.63 E-03  ! 1.21 E-03 I (1) l (1)

Total For Period Ci l Ci l 1.75E-03 1 1.33E 03 i (1) 1 (1)

3. PARTICULATES i l i I I Manganese -54 i Ci j (2) l (2) i (1)  ! (1)

Iron -59 l Ci I (2) I (2)  ! (1) I (1)

Cobalt 58 I Ci I (2) I (2) I (1) I (1)

Cobalt 60 I Ci I (2) I (2) 1 (1) I (1)

Zinc -65 i Ci I (2) l (2) I (1) I (1)

Strontium 89 I Ci i (2) i (2) l (1) i (1)

Strontium -90 i Ci I (2) I (2) i (1)  ! (1)

Molybdenum 99 i Ci  ! (2) I (2) I (1) I (1)

Cesium 134  ! Ci  ! (2) I (2) I (1) I (1)

Cesium 137 I Ci I (2) I 1.33 E-06  ! (1) l (1) 4 Cerium -141 1 Ci I (2)  ! (2) I (1)  ! (1)

Cerium -144 i Ci I (2) I (2)  ! (1) I (1)

Gross Alpha Radioactivity i Ci I (2)  ! (2)  ! (1) 1 (1)

Total For Period Ci i Ci I (2) I l .33 E-06 I (1) l (1)

NOTES TO TABLE IC (1) lodines and pa:ticuhtes 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 ODCM Surveillance Requirement 4.11.2.1.2.

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ATTACHMENT (1)

CALVERT CLIFFS NUCLEAR FOWER PLANT-RADIOACTIVE EFFLUENT RELEASE REPORT EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION I TABLE 2A - REGULATORY GUIDE 1.21 Mf, ATIO OF ALL RELEASES j LIQUID EFFLUENTS l

3RD 4Til EST. TOTAL ,

A. FISSION AND ACTIVATION PRODUCTS UNITS QUARTER QUARTER ERROR,% )

1. Total Release (not including i tritium, gases, alpha) Ci 6.90E-02 2.88E-02 1.03 E+01
2. Average diluted concentration during period uCi/ml 6.77E-11 2.44 E-l 1
3. Percent of Technical Specification limit (1) l  % l 6.42E-01 1 2.10E-01 t
4. Percent of Technical Specification limit (2) 1 -  % i 3.21 E-Oi i 1.05E-01 1
5. Percent of Technical Specification limit (3) l  % I 5.97E-02  ! 2.49E-02 I
6. Percent of Technical Specification limit (4) i  %  ! 2.99E-02 i 1.25E-02 i H. TRITIUM i l i 1
1. Total Release j Ci I 8.35E+01 1 3.08E+02 I *l.04 E+01
2. Average diluted concentration during period _

uCi/ml 8.19E 08 2.61 E-07

, 3. Percent of applicable limit (5) I  % l 2.73E 03 I 8.70E 03 I C. DISSOLVED AND ENTRAINED GASES I I l l

1. Total Release i Ci l 9.20E-04 i 8.56E-03 l
  • l .20 E+01
2. Average diluted concentration during period uCi/mi 9.02E-13 7.26E-12 GROSS ALPilA RADIOACTIVITY D. I I I l

1, Total Release l Ci  ! (6) I (6) l E. VOLUME OF WASTE RELEASED (prior to dilution) liters 5.37E+07 9.47E+07 1.30E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 1.02E+12 1.18E+12 1.64 E+01 NOTES TO TABLE 2A (1) Percent ofI C.3 Quarterly Organ Dose Limit (10 mrem) to maximum exposed organ (2) Percent ofI.C.3 Yearly Organ Dose Limit (20 mrem) to maximum exposed organ (3) Percent ofI.C.3 Quarterly Whole Body Dose Limit (3 mrem)

(4) Percent ofI.C 3 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 ODCM Surveillance Requirement 4.11.1.1.1.

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A'ITACilh1ENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION TAllLG 2B - REGULATORY GUIDE 1.21 SECOND IIALF - 1996 LIQUID EFFLUENTS i CONTINUOUS MODE I IIATCII MODE 3RD 4Til 3RD 4TII NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Sodium 24 i Ci j (1) I (1) I (1) l (1)

Chromium -51 l Ci I (1) l (1) l 4.37E 03 1 6.06E-04 Manganese -54 I Ci I (1) I (1) i 1.04 E-03 1 5.09E-04 Iron 55 i Ci I (2) l (2) I 2.36E-02 1 1.llE-02 Cobalt 57 I Ci I (1) I (1) l (1) i 1.64E-05 Cobalt 58 i Ci j (1) I (1) I 9.94 E-03 l 3.07E-03 fron 59  ! Ci I (1) 1 (1) i 2.89E-03  ; 6.17E-05 Cobalt -60 l Ci I (1) l (1) i 3.12E 03  ! 2.42E-03 Zine -65 I Ci j (1) i (1) I (1) I (1)

Strontium 89 I Ci j (1) I (1) I 2.14E 05 I (1)

Strontium -90 i Ci j (1) l (1) i 1.04 E-05 i (1)

Strontium -92 I C! I (1) i (1) I 5.02E-05 I (1)

Niobium -95 t Ci I (1) l (1) I 8.35 E-03 l 2.66E-03 Zirconium -95 i Ci j (1) j (1) 1 4.72E-03 l 1.67E-03 Niobium -97 I Ci I (1) l (1) I (1)  ! (1)

Zirconium -97 i Ci  ! (1) l (1) I (1) i (1)

Molybdenum -99 I Ci I (1) l (1) I (1) i (1)

Technetium 99m l Ci j (1) l (1) 1 4.51 E-06 i (1)

Ruthenium -103 i Ci I (1) I (1)  ! 4.24E 04 I (1)

Ruthenium -106 i Ci I (1) 1 (1)  ! (1) 1 (1)

Silver -110m  ! Ci I (1) I (1) l 3.89E-03 1 2.17E-03 Tin -113 I Ci j (1) i (1)  ! 1.61 E-03 j 2,87E-04 12

ATTACIIMENT (1)

CALVERT Ct.IFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION TABLE 2B - REGULATORY GUIDE L21 (Continued)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT SECOND HALF- 1996 LlQUID EFFLUENTS I CONTINUOUS MODE I BATCil MODE 3RD 4Til l 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER l QUARTER QUARTER Tin -I l 7m l Ci I (1) I (1) i 1.77E 04 1 1.67E-05 Antimony -122 i Ci I (1) } (1) l (1) 1 (1)

Antimony -124 I Ci I (1) I (1) i (1) I (1)

Antimony -125 i Ci l (1) i (1) l 3.73 E-03 1 3.09E-03 Tellurium 127 I Ci  ! (1) _

l (i) I (1) l (1)

Tellurium -129 i Ci  ! (1) I (1) I (1) l (1) '

lodine -131  ! Ci I (1) l (1) I 6.84E-05 i 5.61 E-04 lodine -133 i Ci I (1) I (1) 1 8.62E 05 l 8.61 E-05 lodine -135 I Ci I (1) I (1) I (1) I 1.93E-05 Cesium 134 l Ci I (1) I (1) I 1.84E-04  ! 1.12E 04 Cesium 136 I Ci I (1) l (1) l 4.55E-06 l (1)

Cesium -137 i Ci j (1) l (1) I 6.01 E-04 i 3.49E-04 Barium 139 i Ci I (1) I (1) i (11 i (1)

Barium -140 i Ci I (1) l (1) I (1) I (1)

Cerium 139 i Ci I (1) 1 (1) 1 (1) I (1) lanthanum -140 i Ci I (!) i (1)  ! (1) I (1)

Cerium -141 l Ci  ! (1) I (1) I (1) I 2.07E 05 Cerium -144 i Ci I (1) i (1) i 1.37E 04  ! (1)

Europium 154 I Ci I (1) I (1) l (1)  ! (1)

Europium -155 l Ci I (1)  ! (1) l (1) 1 (1)

Tungsten 187 i Ci I (1) I (1) I (1) 1 (1)

Total For Period i Ci I (1)  ; (I) i 6.90E-02  ! 2.88E-02 Krypton -85  ! Ci  ! (1) i (1) I (i) (1)

Xenon -131m i Ci I (1) t (1) i (1)  ! (1)

Xenon -133 i Ci I (1) I (1)  ! 9.13 E-04 i 8.52E-03 Xenon -133m l Ci I (1) i (1) l (1) i (1)

Xenon -135 i Ci I (1) I (1) i 7.09E-06 i 4.09E-05 Xenon -135m l Ci i (1) I (1) 1 (1) I (1)

Total For Period I Ci I (1) I (1) I 9.20E-04 I 8.56E-03 NOTES TO TABLE 2B (1) Less than minimum detectable activity which meets the LLD requirements of ODCM Surveillance Requirement 4.11.1.1.1.

(2) Continuous mode c01uents are not analyzed for Fe-55.

13

ATTACllMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT

, RADIOACTIVE EFFLUENT RELEASE REPORT EFFLUENT AND WASTE DISPOSAL iSUPPLEMENTAL INFORMATION TABLE 3A CALVERT CLIFFS NUCLEAR POWER PLANT SOLID WASTE AND IRRADIATED FUEL SIIIPMENTS A. SOLID WASTE SillPPED OFFSITE 70R BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-MONTil EST. TOTAL 1 Type of Waste UNITS PERIOD ERROR %

a. Dewatered spent resin m3 1.70E +01 Cl 2.11 E+02 2.00E+01
b. Dry Compressible Waste (Shipped) m3 3.46E+02 Contaminated Equipment, etc. Ci 4.828-01 5.00E+01 b.* Dry Compressible Waste (Buried) m3 1.37E+01 Contaminated Equipment, etc. Ci 4.62E-01 5.00E+0I
c. Irradiated Components, m 3 0.00E+00 Control Rods, etc. Ci 0.00E+00 N/A
d. Other(Cartridge Filters) m3 6.80E+00 Ci 2.17E+01 5.00E+01 (b.) Volume shipped represents waste generated prior to offsite volume reduction.

(b.*) Represents waste buried after volume reduction at offsite processor.

2. Estimate of Major Nuclides (By Type of Waste - Only nuclides >l% are reported) i
a. Fe-55 1.27E+01%

l Co 58 6.16E+00%

Co-60 1.35E+01%

Ni-63 3.85E+01%

Cs-134 8.10E+00%

Cs-137 1.76E+01%

b. 11 3 1.84E+00%

C-14 1.52E+00%

Cr 51 8.75E+00%

Fe-55 2.27E+01%

Co-58 1.40E401%

Co-60 2.29E+00%

Ni-63 1.58E+00%

Nb-95 1.7IE+00%

Zr 95 1.33E+00%

Cs-134 1.32E+01%

Cs-137 2.96E+01%

Ce-144 1,16E+00%

c. N/A 14-

i ATTACitMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION

d. 113 9.90E-02%

C-14 9.95E+00%

Cr 51 3.56E+00%

17 e 55 3.95E+01%

Co-58 1.73E+01%

Co-60 2.29E+00%

Ni 63 6.96E+00%

Nb 95 5.91 E+00%

Zr-95 3.13E+00%

Cs134 9.41E 02%

Cs 137 1.78E-01%

Cc-144 9.64E-Ol%

Sn113 1.18E+00%

Ru 106 1.12E+00%

, Soll6 Waste I)isposition Number erShinments Mode of Transoortation Destination 3 Motor Surface Transit Chem Nuclear Systems, Inc.

Ilarnwell, SC 6 Motor Surface Transit Scientific Ecology Group Oak Ridge, TN 3 Motor Surface Transit Manufacturing Sciences Corp.

Oak Ridge, TN 3 Motor Surface Transit US Ecology, Inc.

Oak Ridge, TN l

15

I i I

1' APPENDIX (A) s i

l l

l WASTE SIIIPMENTS FOR TIIE SECOND IIALF OF 1996 4

Calvert Cliffs Nucicar Power Plant - Units 1 & 2 Independent Spent Fuel Storage Installation August 20,1997

I I

I Al'PENDIX A CALVERT CLIFF 3 NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT WASTE SillPMENTS FOR SECOND llALF OF 1996 TYPE WASTE: DAW 10 CFR PART 61 WASTE CLASS: A SOURCE OF WASTE: - Radiologically Controlled Areas SillPPING CON'l AINER 20' Sealand Containers, D 25 Metal Doxes, and 55 Gallon Drums TOTAL CURIE QUANTITY: 0.482 Ci ilOW DETERMINED: Dose to curie content, conversion by volume based on generic distribution and scaling factors TOTAL SillPPED WASTE VOLUME: 12,260 A' 8

TOTAL HURIAL WASTE VOLUME: 485.5 A IlOW DETERMINED: Container volume and number of containers shipped. Durial volume is determined from information provided by volume reduction processor.

SOLIDIFICATION AGENT OR AHSORHENT: None A-1

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PIANT RADIOACTIVE EFFLUENT RELEASE REPORT WASTE SIIIPMENTS FOR SECOND IIALF OF 1996 TYPE WASTE: Dewatered Resin 10 CFR PART 61 WASTE CIASS: A(S), and D -

SOURCE OF WASTE: Liquid Waste Processing Systems SillPPING CONTAINER: liigh Integrity L-8 120 Liner (120.3)

TOTAL CURIE QUANTITY: 211.9 Ci liOW DETERMINED: Gamma scan analysis using resin sample, conversion by weight based on radionuclide distribution and scaling factors TOTAL SillPPED WASTE VOLUME: 601.5 ff TOTAL llURIAL WASTE VOLUME: 601.5 ft' ilOW DETERMINED: Container vclume and number of containers shipped SOLIDIFICATION AGENT OR AllSORilENT: None 4

A-2

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE LFFLUENT RELEASE REPORT i WASTE SillPMENTS FOR SECOND IIALF OF 1996 TYPE WASTE Mechanical Cartridge Filters ,

10 CFR PART 61 WASTE CLASS: C SOURCE OF WASTE . Liquid Waste Processing Systems SillPPING CONTAINER: liigh Integrity L-8 120 Liner (120.3)

TOTAL CURIE QUANTITY: 21.7 IlOW DETERMINED: Dose to curie content, conversion by weight based on generic distribution and scaling factors TOTAL SillPPED WASTE VOLUME: 240.6 ft' TOTAL llURIAL WASTE VOLUME: 240.6 ft' ilOW DETERMINED: Container volume and number of containers shipped SOLIDIFICATION AGENT OR AllSORHENT: None A-3

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