ML20064F187

From kanterella
Revision as of 17:09, 22 March 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Effluent & Waste Disposal Semiannual Rept for Second Half 1993, Suppl Info
ML20064F187
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 12/31/1993
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20064F188 List:
References
NUDOCS 9403150205
Download: ML20064F187 (24)
v • d • e


Text

, ,._ - .- - ,. .. ._- . . . .

'?

I a

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  ;

L 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 (Technical Specification 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 effluents exceeds 1.20 mrad or the calculated beta-air dose due to gaseous 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 I 20 mrad / year, gamma-air 40 mrad / year, beta-air

4. All of the above parameters are calculated according to the methodology specified in the Offsite Dose Calculation Manual (ODCM).

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

1. The instantaneous release rate of iodines and particulates in gaseous effluents shall not result in a site boundary dose in excess of 1500 mrem / year  ;

to any organ (Technical Specification 3/4.11.2.1).

2. The Gascous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous . l cffluents when calculated doses exceed 1.8 mrem to any organ in a 92 day -l period at or beyond the site boundary (Technical Specification 3/4.11.2,4).
3. The dose to a member of the public at or beyond the site boundary from~ 'l iodine-131 and particulates with half lives greater than eight days in gaseous l

effluents shal: not exceed (Technical Specification 3/4.11.2.3): ,

15 mrem /qtr, any organ

-9403150205 931231 I FOR ADDCK 05000317

.R PDR.' x

r.

f 30 mrem / year, any organ less than 0.1% of the above limits as a result of burning contaminated l oil.

4. All of the above parameters are calculated according to the methodology ,

specified in the ODCM.

C. 1.iauid Effluents

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 effluents from the plant when the calculated dose to unrestricted areas exceeds 036 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 / year, total body 20 mrem / year, any organ

4. All of the liquid dose parameters are calculated according to the methodology ,

specified in the ODCM. '

II. M AXIMUM PERMISSillLE CONCEN 1 n.iTIONS A. Fission and Activation Gases 1

Prior to the batch release of gaseous effluents, a sample of the source is collected and .l analyzed by gamma spectroscopy for the principal gamma emitting radionuclides. l The identified radionuclide concentrations are evaluated and an acceptable release  !

rate is determined to ensure that the dose rate limits of Technical ll' Specification 3/4.11:2.1 are not exceeded.

B. Iodines and Particulates with Half 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 quantification of any release of radiciodiries. Thevarticulate samples are analyzed by gamma spectroscopy for quantit cation of particulate radioactive material. All of the above parameters are calculated according to the methodology specified in the Offsite Dose Calculation Manual (ODCM).

2

k C. Liauid Effluents The MPCs used for radioactive materials released in liquid effluents are in ,

accordance with Technical Specification 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.  ;

III. TECllNICAL SPECIFICATION ItEPOllTING ItEOUlltEMENTS A. Calvert Cliffs Nuclear Power Plant (CCNPPL Technical Specification 6.9.1.8

1. Previous Calendar Year (1993) Dose Assessment Summary

^

During 1993, liquid releases from Calvert Cliffs resulted in a calculated maximum annual organ dose of 0.48 mrem and a maximum whole body dose of 0.20 mrem. These doses are less than 2.4% of the Technical Specification yearly organ dose limit and less than 3.3% of the Technical Specification yearly dose limit for the whole body. 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  !

during the second half of 1993 and the liver representing the organ with the -

  • highest calculated dose during the first half of 1993.

Gaseous Releases of noble gases resulted in a maximum, quarterly, gamma air dose of 0.004 mrad and a maximum, quarterly, beta air dose of 0.01 mrad.

Iodines and particulates in gaseous effluents from Calvert Cliffs resulted in a maximum organ dose of 0.40 mrem for the year via the child-infant-thyroid -

pathway. These doses were calculated using ODCM methodology. For 1993, calculated off-site doses via the gaseous release pathways were below 1.3% of l their allowable Technical Specification limits.

2. 40 CFR 190 Total Dose Compliance Based upon all releases for 1993 and the ODCM calculations, the maximum exposed individual would receive less than 2% of the allowable dose. During 1993, there were no on-site sources of direct radiation that would have contributed to a significant or measurable off-site dose. The direct radiation contribution is measured by both on-site and off-site thermoluminescent j 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 off-site 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 Requirements During the second half of 1993, the types of radioactive solid waste shipped from Calvert Cliffs were radioactive resin, which was dewatered and shipped ,

in high integrity containers; dry compressible waste, which was shipped as LSA waste in Sealand containers; Irradiated Components, which were shipped in a high-integrity steel container; and fuel pool processing filters, which were shipped in a high integrity container. Appendix A provides a 3

detailed breakdown of the waste shipments for the second half of 1993 per l the categories specified in Technical Specification 6.9.1.8.

4. ODCM and Process Control Program (PCP) Changes One revision was made to the ODCM during the second half of 1993. The  ;

revision was reviewed by the POSRC and approved by the Plant General l' Manager, Calvert 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 Specification'6.17, a copy of the approved  :

change to the CCNPP ODCM is enclosed in Attachment (1).

One change was made to the PCP during the second half of 1993. The change was reviewed by the POSRC and approved by the Plant General Manager, Calvert 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 Specification 6.17, a copy of the approved change to the CCNPP PCP is enclosed in Attachment (2).

5. Radioactive Gaseous Effluent Monitoring Instrumentation None of the Technical Specification effluent monitors were out of service for greater than 30 days.

B. Independent Spent Fuel Storace Installation (ISFSI). Technical Soccification 63 Two casks of spent fuel were transferred to the ISFSI during the fourth quarter of 1993. These casks are sealed 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 1993. Additional information regarding the ISFSI radiation monitoring program will be included in the Annual Radiological Environmental Operation Report.

IV. AVERAGE ENERGY Not Applicable.

1 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, 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.

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 -

r 4

h containment volume and purge rate. Activity buildup while purging is also considered.

2. Continuous Releases l

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 . ]

noble gas radionuclides. The total 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 flow for the week.

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 "

on this sample analysis and the vent flow.

B. Iodine and Particulates

1. Batch Releases The total activities of radiciodines and particulates relcased from pressurized waste gas decay tanks, containment purges, and containment vents are accounted for by the coniinuous samplers on the maia vent.
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 Oc detector for significant gamma emitting radionuclides. The total activity released for the week is based on the total sample activity decay corrected to the midpoint of the sampic period multiplied by the main vent ,

flow for the week. These weekly partiMate filters are then composited to .

form monthly and quarterly composites fo the gross alpha and strontium 89 and 90 analyses.

C. Liouid Effluents

1. Batch Releases Prior to the release of liquid from a waste tank, a sample is collected and analyzed by gamma spectroscoff for il e principal gamma emitting radionuclides. To demonstrate compliancu 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 differen:e in tank levels prior to and after the .,

release. A proportional composite sample is also withdrawn for each release t and this is used in turn to prepare monthly and quarterly composites for the gross alpha, strontium 89 and 90, and tritium analyses.

5 :l

l

2. Continuaus Releases Prior to aischarge of any continuous releases, a sample is collected and analyzed by gamma spectroscopy - for the principal gamma emitting radionuclides. The measured radionuelide concentrations are compared with the allowable MPC concentrations in the discharge conduit, and an allowable j release rate is verified. l When steam generator blowdown is discharged to the ritculating water conduits, it is sampled daily and these samples are used it, turn to prepare a ,

weekly blowdown composite sample based on each dayN 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 and gross alpha analyses.

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 weekly and composited. These samples are added to a composite based on the amount released during that week. The composite sample is analyzed at least monthly for tritium and principal gamma emitting radionuclides The results are multiplied by the actual quantity of liquid released to octermine the total activity released. ,

D. - Estimation n?Te al Error Total error for all releases was estimated using, as a minimum, the random counting error a.sociated with typical releases. In addition to this random error, the following systematic errors were also examined:

1. Liquid
a. Errer in volume of liquid released prior to dilution during batch relea5Cs.
b. Error in volume of liquid 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 errors could be estimated they are usually considered additive. ,

f 6

i I

VI. BATCllHELEASES 1993 3RD 4TII l OUARTER OUARTER A. Uguld

1. Number of batch releases 4.20E4 01 2.60E+01
2. Total time period for batch releases (min) 8.12E+03 1.31E +04 3 Maximum time period for a batch release (min) 5.95E+ 02 2.33E+03
4. Average time period for batch releases (min) 1.93E+02 5.55E +02
5. Minimum time period for a "

batch release (min) 2.50E + 01 2.29E+01

6. Average stream flow during periods of ef0uent into a flowing stream (liters / min of dilution water) 4.59E+06 4.66E+06 H. Gaseous
1. Number of batch releases 3.00E +00 7.00E+00
2. Total time period for batch releases (min) 2.20E+03 3.77E+03
3. Maximum time period for a batch ,

release (min) 1.37E+03 1.10E+03

4. Average time period for batch release (min) 7.32E+02 5.39E+02
5. Minimum time period for a batch release (min) 2 00E+00 1.50E+ 01 7

VII. AllNORMAL RELEASES 1993 3RD 4Til OUARTER OUARTER A. Llauld

1. Number of releases 2. Total activity released (Curies) II. Gaseous
1. Number of releases 2. Total activity releases (Curies) l 8

i TAllLE 1 A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT i SECOND llALF - 1993 l l

G ASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES j

3RD 4Til EST. TOTAL i A. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER ERROR, %

1. Total Release Ci 6.77E+00 4.51E +01 it.20E+01
2. Average release rate for period uCi/sec 8.62E-01 5.74E+00
3. Percent of Tech. Spec. limit (1)  % 5.29E-04 1.93E-03
4. Percent of Tech. Spec. limit (2)  % 2 42E-04 1.49E-03
5. Percent of Tech. Spec. limit (3)  % 7.04E-03 2.63E-02
6. Percent of Tech. Spec. limit (4)  % 3.52E-03 1.32E-02
7. Percent of Tech. Spec. limit (5)  % 4.89E-03 2.39E-02
8. Percent of Tech. Spec. limit (6)  % 2.45E-03 1.20E-02 II. IODINES
1. TotalIodine - 131 Ci 8.00E-04 9.95E-04 11.10E+00
2. Average release rate for period uCi/sec 1.02E-04 1.27E-04
3. Percent of Tech. Spec. limit (7)  % _ 2.42E-04 3.01 E-04
4. Percent of Tech. Spec. limit (8)  % 1.53E-01 1.91 E-01
5. Percent of Tech. Spec. limit (9)  % 7.66E-02 9.53E-02 C. PARTICULATES
1. Particulates with halflives greater than 8 days Ci (10) 4.70E-05 i2.80E+01
2. Average release rate for period uCi/sec (10) 5.98E-06
3. Percent of Tech. Spec. limit (7)  % (10) 9.37E-07
4. Percent of Tech. Spec. limii(8)  % (10) 5.41E-04
5. Percent of Tech. Spec. limit (9)  % (10) 2.71E-04
6. Gross alpha radioactivity Ci (10) (10) 1536E+01 1

9 i 1

l TAllLE l A - REG GUIDE I.21 (Continued)

CALVERT CLIFFS NUCLEAR POWER PLANT .I EFFLUENT ANI) WASTE DISPOSAL SEA 11-ANNUAL REPORT I SECOND IIALF - 1993 -

G ASEOUS EFFLUENTS - SUhth1ATION OF ALL RELCAEE3 3RD 4Til EST. TOTAL D. TRITIUA1 UNITS QUARTER QUARTER ERROR, %  !

. 1. Total Release Ci 9.25E+00 6.67E +00 il.32E+01

2. Average release rate for period uCi/sce 1.18E +00 8.4SE-01 l

NOTES TO TAllLE 1 A (1) Percent of LA.1 whole body dose rate limit (500 mrem / year)

(2) Percem ofI.A.1 skin dose rate limit (3000 mrem / year)

(3) Percent of1.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 ofI.A3 beta yearly dose limit (40 mrad)

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

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

(9) Percent of I.B.3 yearly organ dose limit (30 mrem)

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

I 1

10

l TAllLE IC - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AN D WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND llALF - 1993 G ASEOUS EFFLUENTS . GROUND LEVEL RELEASES CONTINUOUS MODE IIATCll MODE I 3RD 4Til 3RD 4Til

1. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER QUARTER QUARTER Argon -41 Ci (2) (2) 3.47E-03 4.38E-03 !

I Krypton -85 Ci (2) (2) (2) 1.25E+00 l Krypton -85m Ci (2) 3.57E-01 (2) 5.39E-04 i Krypton -87 Ci (2) (2) (2) (2)

Krypton -88 Ci i (2) (2) -(2) (2)

Xenon -131m Ci (2) (2) (2) (2) l Xenon -133 Ci 1.87E+00 2.92E+01 3.59E-03 3.58E-01 1 Xenon -133rn Ci (2) (2) (2) 6.04E-03 Xenon -135 Ci 4.90E+00 1.40$+01 1.11 E-04 1.50E-02 I Xenon -138 Ci (2) (2) (2) (2)

Total for Period Ci 6.77E+00 4.35E +01 7.17E-03 1.63E+00

2. IIALOGENS Iodine -131 Ci 8.00E-04 9.95E-04 2.39E-08 (1)

Iodine -133 Ci 9.59E-03 1.00E-02 4.41E-08 .(1)

Total For Period Ci 1.04E-02 1.10E-02 6.80E-08 (1) 11

.- = - . . . . - - . .- -

TAllLE IC - REG GUIDE 1.21 (Continued)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI. ANNUAL REPORT SECOND llALF- 1993 GASEOUS EFFLUENTS - GROUND LINEL RELEASES CONTINUOUS MODE IIATCil MODE 3RD 4Til 3RD 4Til

3. PARTICULATES UNITS QUARTER QUARTER QUARTER QUARTER Manganese -54 Ci (2) (2) (1) (1)

Iron -59 Ci (2) (2) (1) (1)

Cobalt -58 Ci (2) (2) (1) (1)

Cobalt -60 Ci (2) (2) (1) (1)

Zinc -65 Ci (2) (2) (1) (1)

Strontium -89 Ci (2) (2) (1) (1)

Strontium -90 Ci (2) (2) (1) (1)

Molybdenum -99 Ci (2) (2) (1) (1) u Cesium -134 Ci (2) 1.77E-05 (1) (1)

Cesium -137 Ci (2) 2.93E-05 (1) (1)

Cerium -141 Ci (2) (2) (l') (1)

Cerium -144 Ci (2) (2) (1) (1)

Gross Alpha Radioactivity Ci (2) (2) (1) (1)

Total For Period Ci (2) 4.70E-05 (1) (1)

NOTES TO TAllLE 1C (1) Indines 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.

12

TAllLE 2A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND 11ALF - 1993 LIOUID EFFLUENTS - SUMMATION OF ALL RELEASES 311D 4TII EST.TOTAI A FISSION AND ACTIVATION PRODUCTS UNITS QUARTER QUARTER ERROR, %

1. Total Release (not including tritium, gases, alpha) Ci 8.70E-02 2.23E-01 11.03E+01
2. Average diluted concentration during period uCi/mi 7.25E-11 3.07E-10
3. Percent of Tech. Spec limit (1)  % 1.05E-01 2.01E+00
4. Percent of Tech. Spec. limit (2)  % 5.25E-02 1.00E-00
5. Percent of Tech. Spec. limit (3)  % 5.60E-02 3.08E-02
6. Pereent of Tech. Spec. limit (4)  % 2.80E-02 1.54E-02
11. TRITIUM
1. Total Release Ci 1.32E+02 1.65E +02 1.04E+01
2. Average diluted concentration during period uCi/ml 1.10E-07 2.29E-06
3. Percent of applicable limit (5)  % 3.66E-03 7.62E-03 C. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci 1.71 E-02 9.55E-03 1.20E+01
2. Average diluted concentration during period uCi/mi 1.42E-11 1.32E-11 13

TAllLE 2A - REG GUIDE 1.21 (Continued)

CALVERT CLIFFS NUCLEAR POWER PIANT )

EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPOR: 1 SECOND I1ALF - 1993 LIOUID EFFLUENTS - SUMMATION OF ALL REl. EASES l 3RD 4TIl EST. TOTAL D. GROSS ALPIIA RADIOACTIVITY UNITS ERROR,% ]

QUARTER QUARTER y

1. Total Release Ci (6) (6) 1 E. VOLUME OF WASTE RELEASED '

(prior to dilution) liters 1.07E +08 1.89E+08 it.30E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 1.20E+ 12 7.24E+ 11 it.64E+01 {

l i

NOTES TO TAllLE 2A (1) Percent of 1.C.3 Quarterly Organ Dose Limit (10 mrem) to maximum exposed organ l

(2) Percent of I.C.3 Yearly Organ Dose Limit (20 mrem) to maximum exposed organ (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 uCi/ml (6) Less than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillance Requirement 4.11.1.1.1.

14

TAllLE 211 - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR l'OWER PLANT EFFLUENT AND WAS'IT DISI'OSAL SEMI ANNUAL REPORT SECONI) IIALF - 1993 LIOUID EFFLUENTS CONTINUOUS MODE IIATCil MODE 3RI) 4Til 3RD 4Tll NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Sodium -24 Ci (1) (1) 1.31E-04 (1)

Chromium -51 Ci (1) (1) 2.35E-01 (1)

Manganese -54 Ci (1) (1) 2.34E-04 1.54E-05 Iron -55 Ci (2) (2) 6.29E-03 1.05E-01 Cobalt -57 Ci (1) (1) 5.63E-06 (1)

Cobalt -58 Ci (1) (1) 1.69E-02 1.92E-03 Iron -59 Ci (1) (1) (1) 9.54E-03 Cobalt -60 Ci (1) (1) 9.80E-04 3.21E-03 1

Zine -65 Ci (1) (1) (1) (1) i Strontium -89 Ci (1) (1) 7.92E-05 2.62E-05 Strontium -90 Ci (1) (1) 2.48E-05 5.71E-05 Strontium -92 Ci (1) (1) (1) (1)

Niobium - -95 Ci (1) (1) 6.26E-04 (1)

Zirconium -95 Ci (1) (1) 2.11E-04 (1)

Niobium -97 Ci (1) (1) (1) (1)

Zirconium -97 Ci (1) (1) (1) (1)

Molybdenum -99 Ci (1) (1) (1) (1)

Technetium -99m Ci (1) (1) (1) (1)

Ruthenium -103 Ci (1) (1) 1.77E-04 (1)

Ruthenium -106 Ci (1) (1) (1) (1) l Silver -110m Ci (1) (1) 2f>8E-03 9.56E-02 Tin -113 Ci (1) (1) 1.50E-05 7.80E-05 15

TAllLE 211 - REG GUIDE 1.21 (Continued)

CALVERT CLIFFS NUCLEAR POWEit PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND IIALF - 1993 -

LIOUID EFFLUENTS CONTINUOUS MODE 11ATCil MODE 3RD 4Til 3RD 4TII NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Antimon/ -122 Ci (1) (1) (1) (1)

Antimon:r -124 Ci (1) (1) 1.65E-03 (1)

Antimony -125 Ci (1) (1) 2.34E-02 1.83E-03 Tellurium -127 Ci (1) (1) (1) (1)

Tellurium -129 Ci (1) (1) (1) (1)

Iodine -131 Ci (1) (1) 1.25E-03 1.09E-03 Iodine -133 Ci (1) (1) 1.63E-03 1.03E-03 Iodine -135 Ci (1) (1) (1) (1)

Cesium -134 Ci (1) (1) 1.03E-02 1.45E-03 Cesium -136 Ci (1) (1) (1) (1).

Cesium -137 Ci (1) (1) 1.81E-02 4.21E-03 Barium -139 Ci (1) (1) (1) (1)

Barium -140 Ci (1) (1) (1) (1)

Cerium -139 Ci (1) (1) (1) '(1)

Lanthanum -140 Ci (1) (1) (1) (1)

Cerium -141 Ci (1) (1) (1) (1)

Cerium -144 Ci (1) (1) (1) (1)

Tungsten -187 Ci (1) (1) (1) (1)

Total For Period Ci (1) (1) 8.70E-02 2.23E-01 16

TAllLE 211 - REG GUIDE 1.21 (Continued)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT SECOND IIALF - 1993 LIOUID EFFLUENTS CONTINUOUS MODE IIATCII MODE 3RD 4Til 3RD 4Til NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QU/RTER Xenon -131m Ci (1) (1) 9.50E-05 1.78E-04 Xenon -133 Ci (1) (1) 1.59E-02 8.55E-03 Xenon -133m Ci (1) (1) (1) (1)

Xenon -135 Ci (1) (1) 1.11 E-03 8.26E-04 Xenon -135m Ci (1) (1) (1) (1)

Total For Period Ci (1) (1) 1.71 E-02 9.55E-02 i

NOTES TO TAllLE 211 (1) Less than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillance Requirement 4.11.1.1.1.

(2) Continuous mode ef0uents are not analyzed for Fe-55.

17

l l

TAllLE 3A CALVERT CLIFFS NUCLEAR POWER 14 ANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT i SECOND llALF - 1993 )

l SOLID WASTE AND 1RRADIATED FUEL SillPMENTS A. SOLID WASTE SillPPED OFFSITE FOR IlURIAL OR DISPOSAL (NOTIRRADIATED FUEL) 6-MONTil EST. TOTAL

1. Type of Waste UNITS PERIOD ERROR %

3

a. Dewatered spent resin m 1.36E +01 Ci 3.25E + 02 2.00E+01 3
b. Dry Compressible Waste (Shipped) m 1.77E+02 Contaminated Equipment, etc. Ci 6.06E-01 15.00E+01
c. Irradiated Components, m3 1.63E+00 Control Rods, etc. Ci 4.61 E+ 03 5.00E+01
d. Other (Cartridge Filters) m3 3.41 E+ 00 ,

Ci 1.11 E+01 2.00E+01

2. Estimate of Major Nuclides (By Type of Waste - Only nuclides >1 % are reported) a.

Fe-55 2.34E+00%

Co-58 1.20E+01 %

Co-60 2.49E+ 00%

Ni-63 7.12E+00%

Cs-134 3.33E+01%

Cs-137 4.12E +01 %

b.  ;

H-3 1.61E+00%

C-14 1.56E+00%

Cr-51 7.90E+ 00% l Fe-55 2.32E+01% l Co-58 1.37E+01% 1 Co-60 2.34E+00%

Ni-63 1.61E+01 %

Nb-95 1.59E+00%

Zr-95 1.29E+00%

Cs-134 1.34E +01%

Cs-137 3.04E+01 % l Cc-144 1.17E+00%

c.

Mn-54 5.55E+00%

Fe-55 5.77E+01%  !

Co-58 1.88E+00% l Co-60 3.17E+ 01% j Ni-63 2.75E+00%

18

TAllLE 3A (Continued)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND flALF - 1993 .1 SOLID WASTE AND litRADIATED FUEL, SillPMENTS A. SOLID WASTE SillPPED OFFSITE FOlt IlURIAL OR DISPOSAL (NOT IRRADIATED FUEL,)

d.

C-14 2.46E + 00%

Cr-51 7.05E+00%

Fe-55 2.37E+01 %

Co-58 1.14E+01%

Co-60 1.07E+01 % >

Ni-63 8.30E+00%

Nb-95 1.16E+01 %

Zr-95 7.13E+(X)%

Ru-106 2.49E+ 00%

Ag-110m 2.49E+00%

Sn-113 1.50E+00%

Sb-125 2.15E+00% -

Cc-144 2.33E+ 00%

3. Solid Waste Disposition Number of Shioments Mode of Transportation Destination 6 Motor Surface Transit Chem Nuclear Systems, Inc.

Barnwell, SC 3 Motor Surface Transit Scientific Ecology Group Oak Ridge, TN l

1 19 l

APPENDIX A

. SOLID RADWASTE SIIIPMENT DATA FOR SEMI-ANNUAL EFFLUENT RELEASE REPORTING SECOND IIALF- 1993

'IYPE WASTE: DAW 10 LFR PART 61 WASTE CLASS: A SGURCE OF WASTE: Radiologically Controlled Areas SillPPING CONTAINER: 40' Sealand Containers TOTAL CURIE QUANTrlY: 0.61 Ci IlOW DETERMINED: Dose to curie content, conversion by volume based on generic distribution and scaling factors TOTAL SIIIPPED WASTE VOLUME: 6240 ft 3 IIOW DETERMINED: Container volume and number of containers shipped SOLIDIFICATION AGENT OR AllSORilENT: None l

I TYPE WASTE: Dewatered Resin -

10 CFR PART 61 WASTE CLASS: C )

SOURCE OF WASTE: Miscellaneous Liquid Radwaste Processing and CVCS System SIIIPPING CONTAINER: Iligh Integrity L-8-120 liner (120.3 ft3)

TOTAL CURIE QUANTrlY: 308 Ci IIOW DETERMINED: Gamma scan using sample of resin. Conversion by weight based on  !

radionuclide distribution and scaling factors.

TOTAL SIIIPPED WASTE VOLUME: 120.3 ft 3 IIOW DETERMINED: Container volume and number of containers shipped SOLIDIFICATION AGENT OR AllSORIIENT: None A-1

l APPENDIX A l

-)

SOLlh RADWASTE SillPMENT DATA FOR SEMI ANNUAL EFFLUENT RELEASE REPORTING l SECOND IIALF - 1993 i l

l TYPE WASTE: Dewatered Resin 10 CFR PART 61 WASTE CLASS: B J SOURCE OF WASTE: Miscellaneous Liquid Radwaste Processing i SIIIPPING CONTAINER: High Integrity L-8-120 liner (120.3 ft3)

TOTAL CURIE QUANTITY: 14.7 Ci llOW DETERMINED: Gamma scan m:ng sample of resin. Conversion by weight based on radionuclide distribution and scaling factors.

TOTAL SIIIPPED WASTE VOLUME: 240.6 ft 3 IlOW DEYERMINED: Container vohune and number of containers shipped SOLIDIFICATION AGENT OR AllSORilENT: None TYPE WASTE: Dewatered Resin 10 CFR PART 61 WASTE CLASS: A SOURCE OF WASTE: Miscellaneous Liquid Radwaste Processing SIIIPPING CONTAINER: IIigh Integrity L-8-120 Liner (120.3 ft3)

TOTAL CURIE QUAN*lTIT: 2.75 Ci llOW DETERMINED: Dose to curie content, conversion by weight based on generic distribution and scaling factors j TOTAL SillPPED WASTE VOLUME: 120.3 ft 3 ,

I!OW DETERMINED: Container volume and number of containers shipped SOLIDIFICATION AGENT OR AllSORilANT: None A-2

APPENDIX A SOLID RADWASTE SIIIPMENT DATA FOR SEMI ANNUAL EFFLUENT RELEASE REPORTING SECOND llALF- 1993 1YPE WASTE: Irradiated Hardware 10 CFR PART 61 WASTE CIASS: C SOURCE OF WASTE: Incore Hardware SIIIPPING CONTAINER: High Integrity Carbon Steel Liner (57.4 ft3 )

TOTAL CURIE QUANTrlY: 4610 Ci IIOW DETERMINED: Calculation based on material's composition and neutron activation ,

TOTAL SillPPED WASTE VOLUME: 57.4 ft 3 .

IIOW DETERMINED: Container volume and number of containers shipped SOLIDIFICATION AGENT OR AllSORIlENT: None 1YPE WASTE: Cartridge Filters 10 CFR PART 61 WASTE CLASS: C SOURCE OF WASTE: Fuel Pool filters Sl!IPPING CONTAINER: High Integrity L-8-120 liner (120.3 ft3 )

TOTAL CURIE QUANT 11Y: 11.1 Ci IIOW DETERMINED: Dose to curie content, conversion by volume based on generic distribution and scaling factors TOTAL SillPPED WASTE VOLUME: 1203 ft3 HOW DETERMINED: Container volume and number of containers shipped SOLIDIFICATION AGENT OR AHSORIIENT: None i

A-3 1

APPENDIX 11 1

SUMMARY

OF CIIANGES TO TIIE CCNPP ODCM SECOND IIALF 1993 CIIANGES TO Tile CCNPP ODCM IN SECOND IIALF 1993

SUMMARY

AND llASIS A revision of the ODCM was approved on August 26,1993. The revision was controlled by the normal procedure change process. The change was reviewed by the Plant Operations and Safety Review 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.

An executive summary of the changes made to the ODCM are described on pages 164 and 165 of the ODCM, Revision 1, Change 0. 7 A change to the PCP was approved on August 27,1993. The change was controlled by the normal procedure change process. The change was reviewed by the Plant Operations and Safety Review 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.

P The change to the PCP was the addition of the statement that all changes to the PCP must be POSRC reviewed and submitted to the NRC in the Semi-Annual Radioactive Effluent Release Report for the period in which the change was made.

h I.

r B-1

.,

Retrieved from "https://kanterella.com/w/index.php?title=ML20064F187&oldid=2659474"