ML20029A766

Semiannual Effluent Release Rept for Second Half 1990.

ML20029A766
Person / Time
Site:	Calvert Cliffs
Issue date:	12/31/1990
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20029A765	List: ML20029A764 ML20029A766 ML20029A767
References
NUDOCS 9103040226
Download: ML20029A766 (19)

Text

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SEMI-ANNUAL EFFLUENT RELEASE REPORT CALVERT CLIFFS NUCLEAR POWER PLANT SECOND HALF - 1990 TABLE OF CONTENTS

1. REGULATORY LIMIY3....................................................... 1

.A. Fission and Activation Gases........................................ 1 B. Iodines and Particulates with Half Lives Greater than Eight Days....1 C. L i q u i d E f fl u e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 II. MAX I MUM P ERMI S S I B L E CONC ENT RAT I ON S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 A. Fission and Activation Gases........................................ 2 B. Iodines and Particulates with Half Lives Greater than Eight Days.... 3 C. L i q u i d E f fl uen t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 III. TECHNICAL SPECIFICATION REQUIREMENTS.................................... 3 IV. AVERAGE ENERGY.......................................................... 4 V. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY.................. 5

.A, Fission-and Activation Gases........................................ 5

1. Batch Releases.................................................. 5

2. Continuous Releases,............................................ 5 B. I od i ne and Pa rti cul a te s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

1. BatchReleases.......................................,..........5

2. Con t i nuou s Rel e a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 C. L i q u i d E f fl u e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6

1. B a t c h Re l e a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6

2. C o n t i nu ou s Rel e a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 D'. E s t i ma t i on o f To t al Error . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ,7

1. Liquid.......................................................... 7

2. Gases........................................................... 7 VI. BATCH RELEASES.......................................................... 8 A. Liquid.............................................................. 8 B. Gaseous............................................................. 8 V I I . ABNORMAL RELEA S E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 A. Liquid.............................................................. 9

'B.- Gaseous......~....................................................... 9 TABLES

'l A - Gaseous Ef fluents -- Summation of Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 1C - Gaseous Effluents - Ground Level Releases. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 2A - Liquid Effluents - Summation of All Releases. . . . . . . . . . . . . . . . . . . . . . . . . . 14 2 B - L i q u i d E f fl u e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 3A - Solid Waste and Irradiated Fuel Shipments............................. 18

, APPENDIX-A.................................................................A-1 APPENDIX B,................................................................B-1 ATTACHMENT 1 9103040226 910226 PDR ADOCK 05000317 R 'PDR

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CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SUPPLEMENTAL INFORMATIM Facility - Calvert Cliffs Nuclear Power Plant Licensee - Baltimore Gas & Electric Company 1.- REGULATORY LIMITS ,

A. : Fission and Activation Gases

l. 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 Syste::. 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 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 n 20 mrad /qtr,. beta air 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-E (0DCM).

B. Todines and Particulates with Half Lives Greater than Eiaht Days

1. The- instantaneous release rate of iodines and particulates- in 1

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).

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+ 2. The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous effluents when calculated doses exceed 1.8 mrem to any

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organ in a 92 day _ period at or beyond the site boundary (Technical-Specification 3/4.11.2.4).

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.3. The dose to a member of the public at or beyond the site boundary

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from. iodine 131 and particulates with half lives greater than eight days in gaseous effluents shall not exceed (Technical

-Specification 3/4.11.2.3):

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

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

C. Liouid Effluents

1. .The . concentrations of radionuclides in liquid efflaents 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. The liquid radwaste treatmeat system shall be used to reduce the concentration of radionuclides in liquid effluents from the plant when :the calculated doses to unrestricted -areas exceed 0.36 mrem to -the whole body, or 1.20 mrem to any organ in a 92 day period (Technical Spect f.ication 3/4.11.1,3).

'3. The dose .to a member of the public in unrestricted areas shall not exceed (Technical'Specifcation 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 ODCH.

II. MAXIMUM PERMISSIBLE CONCENTRATIONS

.A. Fission and Activation Gases Prior to the batch release of gaseous effluents, a sample of the-

, source is collected and analyzed by gammat 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 Technical

. Specification 3/4.11.2.1 are not exceeded.

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B. lodines and Particulates with Half Lives Greater than Eiaht 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 radiciodines. The particulate samples are analyzed by gamma spectroscopy for quantification of particulate radioactive material. Based on guidance provided in the ODCH, compliance with dose rate limits for the radiciodines and particulates may be based on a comparison of the actual measured release quantity over a sample period with a pre-established upper bound.

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 20, Appendix B, including applicable table notes, in all cases, the more restrictive (lower) MPC found for each radionuclide is used regardless of solubility.

!!!. TECHNICAL SPECIFICATION __ REPORTING RE0VIREMENTS (Section 6.9.1.8)

A. previous Calendar Year (19901 Dose Assessment Summary During 1990 liquid releases from Calvert Cliffs resulted in a calculated maximum organ dose of 3.02E-01 mrem and a maximum whole body dose of 2.19E-02 mrem. These doses are less than 4% of the Technical Specification yearly organ dose limit and less than 1% of the Technical Specification yearly dose limit for the whole body.

These doses were calculated using ODCM methodology. The controlling pathway was the fish and shellfish pathway with adult as the controlling age group, and the Gastro-intestinal Tract representing the organ with the highest calculated dose.

Gaseous releases of noble gases resulted in : maximum air dose of 1.78E-02 mrad, gamma and 5.08E-02 mrad, beta. Iodine and particulate releases frctm Calvert Cliffs resulted in a maximum organ dose of 2.38E-03 mrem for the year via the milk-infant-thyroid pathway. These doses were calculated using ODCM methodology. For 1990, calculated offsite doses via the gaseous release pathways were below 3% of their allowable Technical Specification limits.

B, 40 CFR 190 Total Dose Compliance Based upon all releases for 1990 and the ODCM calculations, the maximum exposed individual would receive less than 1% of the allowable dose. During 1990, there were no on-site sources of direct radiation that would have contributed to a significant or measurable offsite dose. The direct radiation contribution is measured by both on-site and off-site thermoluminescent dosimeters (TLD), 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 o f f-s i te calculated doses is attributable to the 3

direct exposure from on site sources. A more detailed evaluation will be reported in the Annual Radiological Environmental Monitoring Report.

C. Solid Waste Report Reauirements During the second half of 1990, the types of radioactive solid waste shipped from Calvert Cliffs were radioactic resin, which was dewatered and shipped in high integrity containers, dry compressible waste, which was shipped as LSA waste in strong, tight containers, and irradiated hardware, which was shipped in a strong steel container.

Table 3A summarizes the waste shipment data. Also, Appendix A provides a detailed breakdown of the waste shipments for 1990 per the categories as specified in Technical Specification 6.9.1.8.

D. ODCM and PCP Chana u One change was made to the ODCM during the calendar year 1990 This change was reviewed by 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 change to the CCNPP ODCM is enclosed in Attachment 1.

Vertical lines in the right margin of the text denote the above referenced change with accompanying change number.

No changes were made in the PCP in the second half of 1990.

E. hdioactive Gaseous Ef fluent Msnitorina Instrumentation The Unit 2 Steam Generator Blowdown RMS effluent monitor (2-RE-4014),

the liquid Waste Discharge Header RMS effluent monitor (0-RE 2201),

i.nd the Waste Gas Discharge Header RMS effluent monitor (0-RE-2191) were out of service for greater than thirty days. These notifications are required by Technical Specification 3.3.3.0 :nd 3.3.3.10. These monitor: were all declared inoperable because of failed source check criteria, as based on Operations Instruction 01-35. (The Operations instruction 01-35 has been modified, and new source check criteria has been establised.)

The Unit 2 Steam Generator Blowdown ef fluent monitor (2-RE-4014) was declared inoperable on August 28, 1989 and restored to service on December 19, 1990. The Liquid Waste Discharge Header effluent monitor (0 RE 2201) was declared inoperable on March 12, 1989 and restored to eervice on November 2, 1990. The Waste Gas Discharge Header RMS effluent monitor (0-RE 2191) was declared inoperable on March 12, 1989 and restored to .;ervice on November 21, 1990.

IV. AVERAGE ENER01 Not Applicable 4

V. MEASUREMENTS AND APPROXIMATIONS AND TOTAL RAQ10 ACTIVITY A. fissior, and Activation Gasn

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 Ge detector for the princ9al gamma emitting noble gas radionuclides. The total actiyily 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 cuntainment volume and purge rate. Activity buildup while purging is also considered.

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 fn* 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 sanple is collected f rom the main vents and analyzed by liquid scintillation for tritiur. The total tritium release for the month is based on this sample analysis and the vent flow.

B. lodine and Particulates

1. Batch Releases The total activities of radioiodines and particulates released from a pressurized gas decay tank, containment purges and containment vents are accounted for by the contir.uus samplers on the main 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 Ge 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 sample period multiplied by the main vent flow for the week. These weekly particulate filters are then composited to form monthly and quarterly composes for the gross alpha and strontium 89 and 90 analyses.

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C. Liouid 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 1.C.1 above, the measured radionuclide concentrations are compared with the allowable HPCs; 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 difference in tank levels prior to and af ter 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, sitxtium 89 and 90, and tritium analyses.

2. Continuous Releases Prior 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 12 verified.

When steam generator blowdown is discharged to the circulating water conduits, it is sampled daily and these samples are used in .

turn to prepare a weekly blowdown composite based on each day's blowdown. The weekly composite is analyzed by gamma spectroscopy for the principal gamma emitting radionucliw s. 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 (mostly tritium) water is released directly to the Chesapeake Bay. This water is sampled at least weekly and analyzeo, by gamma spectroscopy, for the principal gamma emitting radionuclides, and added to a composite based on -

the amount released during that week. This monthly composite is analyzed, by gamma spectroscopy, for the principal gamma emitting radionuclides. These results are multiplied by the actual quantity o f- liquid released to determine the total activity released. This monthly composite is aise used to prepare monthly and quarterly composites for tritium, gross alpha, and strontium 89 and 90 analyses, i

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D. [ilimation of Total Errat Total error on 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 of liquid released prior to dilution during batch releases.

b) Error in volume of liquid released via steam generator blowdown, c) Error in amount of dilution water used during the reporting period.

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2. Gases a) Error in main vent release flow, b) Error in sample flow rate.

c) Error in containment purge release flow, d) Error in gas decay tank pressure.

Where errors could be estimated they are usually considered additive.

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VI. BATCH RELEA$El D10 3RD 4TH QUARIER QUARIIB A. LLquid

1. Number of batch releases 3.30E401 4.10E+01

2. Total tirne period for batch releases (min) 1.34E404 1.37E+04 3 Maximum time period for a batch release (min) 2.E/E403 1.10E403

4. Average time period for batch releases (min) 4.05E+02 3.35E402

5. Minimum time period for a batch release (min) 2.10E+01 9.00E400

6. Average stream flow during periods of effluent into a flowing stream (liters / min of dilution water) 2.64E406 3.94E+06 B. Gaseous

1. Number of batch releases 1.80E401 2.80E401

2. Total time period for batch releases (min) 8.57E+04 1.05E405

3. Maximum time period for a batch release (min) 1.02E+04 1.29E404

4. Average time period for batch release (min) 4.76E+03 3.75E+03

5. Minimum time period for a batch release (min) 6.00E401 2.00E+00 8

Vll. ABNORMAL RELEASES 1HQ 3RD 4TH QUARILB DVABIf3 A. Liould

1. Number of releases 0- 0-

2. Total activity released (Curies) 0-B. Gaseous

1. Number of releases 0- 0-

2. Total activity releases !. Curies) J 9

! IAtti_1A REG GU10E 1.21

, CALVERT CLIFFS NUCLEAR POWER PLANT L I EFFLUENT AND WA5TE DISPOSAL SEMI. ANNUAL REPORT

$ECOND HALF 1990 RAliQU$ EFFLU[NTS - $UMMATION OF ALL RELEASES 1

I 3RD 4TH EST. TOTAL i A. F15SION_AND AQTIVATION GASES UNITS QUARTER OVARTER ERRERi%

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1. Total Release Ci 4.01E-01 6.40E+02 6.20E400 __ l

2. Averaae release rate for period uti/sec 5.10E-02 8.14E401 1

3. Percent of tech.soec.11mit(1)  % 3.61E 07 1.12E 02 e 4. Fercent of tech.soec. limit (2)  % 5.08E-06 4.48E 03

5. Percent of tech.soce.11mit(3)  % 4.81E-06 1.67E-01 1

6. Percent of tech.soec.11mit(4)  % 2.40E 06 8.33E-02

7. Percent of tech.soec. limit (5)  % 2.73E-04 2.40E-01.

8. Percent of tech.socc. limit (6)  % 1.36E-04 1.20E 01 B.- 10 DINES

1. Total lodine - 131 Ci (10) 1.12E 03 16.50E+q0

2. Averaae release rate for period uti/sec -

1.42E 04

3. Percent of tech.soec.11mit(7) 9' - 3.37E-04

4. Percent of tech. spec. limit (8)  % -

'. 2.59E-01

5. Percent of tech.soec.11mit(9)  % -

1.30E-01 C. PARTICULATES ,,_ _

l. Particulat0s with half lives areater than 8 days Ci 7.59E-06 (10) 2.80E+01

2. Averaae release rate for period uti/sec 9.65E-07 -

3. Percent of tech.soec.11mit(7)  % 2.29E-06 -

4. Percent of tech.soec.11mit(8)  % 1.76E-03 -

E Percent of tech.soec.11mit(9)  % 8.80E-04 -

6. Gross alpha radioactivity Ci (10) (10) f6.54E+01 l

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

IMLLIA REGEIDLLZLIContd CALVERT Cliff 5 NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SENI. ANNUAL REPORT SECOND HALF 1990 M51011.$_LfLLVENTS SUMMAIJQN OF ALLALL(A$li 3RD 4TH EST. TOTAL D. TRITillM _LNITS QQMIER QU,ARTER LRRQL%

1. Total Release CJ 5.68E 02 4.001:02 1.32E+91

2. Averaae release rate for period uti/sec L22E 03 5.09E 03 _

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

(2) Percent of 1.A.1 skin dose rate limit (3000 mrem / year)

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

(4) Percent of 1. A 3 gamma yearly dose limit (20 mrad)

(5) Percent of 1. A.3 beta quarterly doso limit (20 mrad)

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

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

(8) Percent of 1.B.3 quarterly dose limit (15 mrem)

(9) Percent of 1.B.3 yearly dose limit (30 mrom)

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

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__ .m . _ . . _ _ - . _ . _ . _ _ .-___..____,.._.___,__..~.__,___.._.._.._.a.

IAMLLC - RELGU10Lhti CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1990 GMLOULLEfLVENTS - GROUND LEVEL RELL&$[$

CONTINUOU5 MODE 3RD BATCH N0DE 41H 3RD

1. .. T15510N AND ACTIVAJ10N GASESUtilTS OVARIER 4TH OVARTER OVARTER Argan QUARIIR_

41 Ci (2) (2) (2)

Kryplon 3. 35E - OL 85

_Ci (2). ( 2)- 4.01E 01 Krypton -85m 5.05LOL Ci (2) 3J9E 01 (2)

_ Kryp19ty 87 411[ .QL Ci (2) (2) (11-Kryton 3.55E 04 B.8 Ci (2) J2) . _121 3.52E OL Xenon 131m ti (2) 1.22E401 (2)_ 4.661120 Xcton 133 Ci (2) 9. qZ1101--

(2)

Xenon 5.10E 4_0L

_ _l} 3m Ci (2) (2) (2)

Xenon 2. 72 E40L

-135 Ci (2) 9 E f+00 [2) 9.22[ qL Xenon- llB Ci (2) J2) (2)__ _ (2)

Total.Jor Period Ci -

1.21E402 4.01E 01 5.19Et 0L L _lthLEGIES Iodine 131 Ci (2) 1.12E 03 (1) lodine (11

-133 Ci (2) 9.78E-04 (1) (1)

_ J 0l Jor Period Ci -

2.10E-03 (lL (11 12

TABLE IC -REG GQLQE 1.21 (Cont.d CALVERT CLIFF 5 NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SENI ANNUAL REPORT SECOND HALF 1990 M5E0VS EFFLUENTS - GROUND LE.YILERIA511 CONTINUOUS N0DE BATCH N0DE 3RD 4TH 3RD 4TH

3. PARTICULATES UNITS OUARTER 00ARTER 00ARTER 00ARTER Mana g e -54 Ci (2) (2) (1) (1) fron Ci (2) (2) (1) (1)

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

Cobalt 60 C1 (2) (2) (1) (1)

Zine -65 Ci (2) ( 2,) (1) (1)

Strontium -89 Ci (2) (3) (1) (1)

Strontium -90 Ci (2) (3) (1) (1)

Molybdenum 99 Ci (2) (2) (1) (1)

Cesium -134 Ci (2) (2) (1) (1)

Cesium -137 Ci 7.59E 06 (2) (1) (1) l Cerium -141 Ci (2) (2) (1) (1)

Cerium -144 ,

Ci (2) (2) (1) (1)

Total For Period- Ci -7.59E-06 - (1)- (1)

(1) lodines'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.

(3) Analysis not completed for 4th Quarter.

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1 IABLE_2A - REG GUIDE _1.21 ,

CALVERT CLIFFS HUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT "

j SECOND HALF - 1990 LIQUID EFFLUENTS - SUMMATION OF ALL RELLAi[$

b i 3RD 4TH EST. TOTAL A. FISSION AND ACTIVATION PRODUCTS UNITS OUARTER OUARTER ERROR.%

j .

1. Total Release (not including tritium.aalgj.alobal Ci 7.25E-01 4.53E-01 11.03E401

2. Average diluted concentration durina period uti/mi 2.10E 09 8.78E 10

3. Percent of tech. spec.11mitfll  % 1.07E400 6.36E 01 4

4. Percent of tech. spec. limit (2)  % 5.34E-01 3.18E 01

5. Percent of tech.snee.11mitf31  % 3.75E-01 2.49E 01

6. Percent of tech. spec.11mit(41  % 1.88E 01 1.25E-01 B. TRITIUM l 1. Total Release Ci 3.12E400 5.41E+01 1.04E+01

2. Average diluted concentration-durina neriod uti/ml 9.03E 09 1.05E 07

.3. Percent 'of anolicable limit (51  % 3.01E-0( 3.50E-03 C. DISSOLVED AND ENTRAINED GASES

1. Total Release Ci (6) 1.09E-01 - 4.80E400

2. Average diluted concentration durina period uti/ml - 2.llE-10 14

-,-,a..-,-. - ....----.-.:--._.,.-,,, . _ _ - - ,..... - -_.-

TABLE 2A - REUiUJDE 1.21 (Csntd CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SENI ANNUAL REPORT

-SECOND HALF - 1990 LLQUJD EFFLUENTS - $UMMATION OF ALL RELEAELS 3RD 4TH EST. TOTAL D. GROSS ALPHA RA010 ACTIVITY Udll$ QUARTER QUARTER ERROR J.

1. Total Release ci 6.15E-05 (6) 13.34E401 E. VOLUME OF WASTE RELEASES (prior to ailution) liters 2.15D06 4.38D06 d l . 30D 00 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 3.46E+11 5.lsbil 1. 64 D01 l

l NOTES TO TABLE 2A l (1) Percent of I.C.3 Quarterly Organ Dose Limit (10 mrem)

(2) Percent of I.C.3 Yearly Organ Dose Limit (20 mrem)

(3) Percent of I.C 3 Quarterly Whole Body Dose Limit (3 mrem) 1 (4) Percent of 1.C.3 Yearly Whole Bouy Dose limit (6 mrem) ,

(5) Limit used is 3 x 10*3 uti/ml _

(6)- Less than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillaace Requirement 4.11.1.1.1.

1 15

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

IAS1E.1B - REG..AulDE.1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT SECOND HALF - 1990 L1QQ10 EFFLUENTj CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UN,((E_ 00ARTER OVARTER - 0VARTER OVARTER Sodium - 24 Ci (1) (2) (2) 1.28E 04 Chromium -51 Ci (1) (2) (2) 3.34E 03 Manaanese - 54 C1 (1) (2) 2.72E-02 2.6)E-03 Cobalt - 57 Ci (1) (2) 6.59E 03 7.41E 06

- [gbalt - 58 C1 (1) (2) 5 Q2E 02 8.12E 03

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

Cobalt - -

60 Ci (1) (2) 4.38E-01 2.64E 02

_Zine - 65 Ci (1) (2) (2) (2) f Strontium - 89 Ci (1) (2) (2) (3)

Strontium 90 Ci (1) (2) 7.46E 04 (3)

Strontium' 92 C1 (1) (2) (2) 1.09E-05

- Niobium -95 C1 (1) (2) (2) 5.00E-04 t

Niobium -97 Ci (1) (2) (2) 6.67E-05 Zirconium- -95 Ci (1) (2) (2) 2.78E 04 Molybdenum -- 99 Ci (1) (2) (2) 1.94E 04

' Technetium 99m Ci- __( 1) (2) (2) 1.15E-03 Ruthenium -106 Ci (1) (2) (2) 7.42E-03 Silver' -110m Ci (1) (2) 2.20E-02 2.35E 02 Tin 113- Ci (1) (2) 4.38E 06 (2)- .

Antimonv' 122 Ci ___ (1) (2) 2.59E 06 3.77E-05 Antimony -125 . Ci (1) (2) 3.23E 02 1.21E-01

- Technetium -132 Ci (1) (2) (2) 4.82E 06 l

l l.

16 9 .g-wr.*,- y- pen- m-~-ery.y.,evg--+'+t =-*br- v *

'*-**vw we' '- ets,**w- = e-'e- - e ew----+s-+-+e-m-+++-w*'e-- "*--**e*-*

. _.._._ ~

l- 1&B.LLIB .RER GUIDLL.2.LICDBM CALVERT CLIFF 5 NUCLEAR POWER PLANT EFFLUENT AND WA5TE DISPOSAL SEMI ANNUAL REPORT SECDND HALF 1990

Ligul0 Errlutgis CONTIN 00VS MODF BATCH MODE 3RD 4TH 3RD 4TH L NUCLIDES RELEASED UNITS OVARTER OVARTER QQ&RTER OVARTER

, Iodine - 131 Ci (1) 6.78E 06 (2) 2.62E 02 lodine - 133 C1 (1) (2) (2) 7.82E 03 lodine - 135 .

Ci (1) (2) (2) 1.63E 04 i Cesium - 134- Ci (1) 8.30E 07 2.43E 02 3.61E 02

. Cesium- - 136 Ci (1) (2) (2) 6.79E 05

, ~ Cesium -

12] C1 (1) 2.77E-06 1.16E 01 1.78E 01 ,

. Barium - 140- Ci (1) (2) (2) 3.09E 05 i

tanthanum' - 140 Ci (1) (2) (2) 2.23E-04 4- Cerium - 141 Ci. (1) (2) (2) (2)

Lgrium - 144 Ci (1) (2) 0.05E 03 9.07E 03 Tunasten - 187 Ci (1) (2) (2) 4.63E 04

' Total For Period Ci (1) 1.04E-05 7.25E 01 4.53E-01 Xenon - 131m Ci (1) (2) (2) 3.52E 04 5

Xenon - 133 Ci (1) (2) (2) 1.06E 01 Xenon - 133m Ci (1) (2) (2) 2.01E 03 i Xenon -

135 Ci (1) (2) (2) 2.28E 04 -

Xenon - 135m- __

Ci (1) (2) (2) 5.71E 04

-Total For Period Ci (1) (2) - 1.09E-01 <

(1)- There were no continuous liquid releases during the 3rd quarter.

(2) Less than minimum' detectable activity which meets the LLO requirements of Technical Specification. Surveillance Requirement 4.11.1.1.1..

(3) - Analysis- not completed for 4th Quarter.

17 y v -, 7..-M ..v w.g- m.,,v. , %w myw- <..,+,e.-%_ .,..m., ,%,..% .. ,,m , u, 4 w.r , w % , . w.. w., , 7.y ,,,-,e v ,% %.< , mm m ,- . , , , - , , , , , , , , - , -

IMLUh CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT SECOND HALF 1990 1Q11D WA5TE ANLifLRMLATED FUELjlilDilt{1}

fu__10llD WASTE $1[lPPE0_OFFSITE FOR BilA18L OR DISPQ}AL_(t(OT IRRADJAIID_EVEll 6-MONTH EST. TOTAL 14__IYP1_.of Waste UNITS PERIOD ERROR %

a. Dewatered spent resin m3 3.70E400 Ci 6.19E401 2.00E+01

b. Dry Compressible Waste, m3 1.10E+02 Contaminated Equipment, etc. Ci 4.67E400 5.00E+01

c. Irradiated Components, m3 1.24E400 Control Rods, etc. Ci 4.05E403 5.00E401

d. Other (CVCS filters) m3 - --

Ci -- -

2.00E401

2. Estimate of Major Nuclides (By Type of Waste)*

a. Manganese -54 2.64E400 %

fron 55 8.44E400 %

Cobalt -58 4.91E400 %

Nickel -63 3.85E+01 %

Antimony -125 3.72E400 %

Cesium -134 8.18E400 %

Cesium 137 2.75E401 %

b. Tritium 3 3.14E+00 %

Carbon -14 1.10E400 %

Iron -55 4.47E401 %

Cobalt -58 1.44E400 %

Cobalt 60 1.41E+01 %

Nickel 63 1.73E+01 %

Cesium 134 3.03E400 %

Cesium 137 1.10E+01 %

Antimony -125 1.42E+00 %

c. Iron -55 4.96f+01 %

Cobalt 60 4.53E+01 %

Nickel 63 4.80E+00 %

, o Only nuclides greater than 1% are reported 18

IMLLJA CALVERT CLIFFS NVCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SLHl. ANNUAL REPORT SECOND HALF - 1990 SALID_WASIE ANQ,jRRA01AlfDEIL5HlftfHI$ (Cont.)

eu_.J011 D W A$1L$tilEEf D_0 F F 51 T E FOR BURJ ALOLD15E0 $ALIE0LIRRAD.l AIIDJ.UIU

3. Solid Waste Disposition th!aber of Shit @ fall Rode of Trar11 par 131 tion Destinalica 4 Motor Surface Transit Scientific Ecology Group Oak Ridge, IN 5 Motor Surface Transit Chem Nuclear Systems Inc.

Barnwell, SC 19

APPENDIX A SOLID RADWASTE SHIPNENT DATA FOR SEMI-ANNUAL EFFLUENT RELEASE REPORTING SECOND HALF - 1990 TYPE WASTE: DAW 10 CFR 61 WASTE CLAS$: A SOURCE OF WASTE: Radiologically Controlled Areas SHIPPING CONTAINER: CPC B 25 Box TOTAL CURIE QUANTITY: 4.41 Ci HOW DETERMINED: Dose to curie content, conversion by volume based on generic distribution and scaling factors TOTAL WASTE VOLUME: 3870 ft3 HOW DETERMINED: Container volume and number of containers shipped

-SOLIDIFICATION AGENT OR ABSORBENT: None TYPE WASTE: Dewatered Resin 10 CFR 61 WASTE CLASS: B SOURCE OF WAS1E: Hiscellaneous liquid Radwaste Processing /CVCS Processing

-SHIPPING CONTAINER: High Integrity L 8 120 liner (120.3 ft3)

TOTAL CURIE QUANTITY:_ 32.8 Ci HOW DETERMINED: Gamma scan using sample of resin TOTAL WASTE VOLUME: 120.3 ft3 buried / Resin volume 44.2 ft 3 HOW DETERMINED: Weighed liner and calculated volume of resin SOLIDIFICATION AGENT OR ABSORBENT: None A-1

)

APPENDIX A l SOLID RADL'ASTE SHIPMENT DATA  !

FOR SEMI. ANNUAL EFFLUENT RELEASE REPORTING SECOND HALF 1990 TYPE WASTE: Dewatered Resin l 10 CFR 61 WASTE CLAS$: B  !

SOURCE OF WASTE: Hiscellaneous Liquid Radwaste Processing /CVCS Processing SHIPPING CONTAINER: High Integrity L 8-120 liner (120.3 ft3)

TOTAL-CURIE QUANTITY: 29.1 Ci ,

HOW DETERMINED: Gamma scan using sample from resin TOTAL WASTE VOLUME: 120.3 ft3 buried / Resin volume 86.6 f t 3 HOW DETERMINED: Weighed liner and calculated volume of resin SOLIDIFICATION AGENI OR ABSORBENT: None TYPE WASTE: ICI Wires 10 CFR 61 WASTE CLASS: C SOURCE OF WASTE: Irradiated core components SHIPPING CONTAINER: 3 Carbon Steel 1-13G liner (14.6 ft )

TOTAL CURIE QUANTITY: 4050.0 Ci HOW DETERNINED: Component physical characteristics, material composition, irradiation history, and radiation levels TOTAL WASTE'. VOLUME: 43.8 ft3 HOW DETERMINED: Container volume and number of containers shipped SOLIDIFICATION AGENT OR ABSORBENT: None A2

....7 Al'I'ENDIX 11 SUMh1ARY OF CilANGES TO Tile CCN1'I' ODCh1 _

1990 t

si

l 4

-- APPENDIX B j

CHANGES TO THC CCNPP ODCM IN 1990

$UMMARY AND BA$15 The Calvert Cliffs Offsite Dose Calculation Manual (ODCN) is contained in the Chemistry Procedure CP 607. Changes to this document are controlled through the normal procedure change review and approval process. This process meets the requirements of CCNPP Technical Specification 6.17.

One group of changes was made to the ODCM during the calendar year 1990. The change was reviewed by PO$RC and ap) roved by the Plant General Manager,

-Calvert Cliffs Nuclear Power Plant, prd or to implementation. This change was reviewed and approved on July 27, 1990, and designated as Change 90-102.

Change bars are provided in the right margin of the ODCM text to identify these changes.

A. change:in a . previous year (Change 89191) approved the use of fewer the five circulating water pumps recuired to be operating in order to conduct a liquid radwaste release, in thns change, the minimum number of circulating water pumps . required to be operating during a liquid radwaste release was changec to normally a minimum of three.

This change in the required number of pumps does not reduce the plant's capability for ensuring that releases are maintained within the release rate limits (Technical Specification 3/4.11.1.1.). The allowable release rate is determined prior to each release by a comparison of the radionuclide concentration in the release and the actual dilution water flow at that time (i.e., the numb" of circulating water pumps operating). Radiation monitor setpoints are appropriately changed, or release rate reduced as needed to reflect the change in the dilution water flow. The dose calculations that are performed for demonstrating compliance with limits of Technical Specification 3/4.11.1.2 are also based on the actual circulating water flow at the time-of

-the release. This change in the- ODCM does not reduce the accuracy .or reliability of the dose calculations or setpoint determinations.

The-second change corrects the radiciodine and particulate controlling pathway deposition- value that was: previously. entered incorrectly in the ODCM during the last change. The correct value was used in all dose calculati.ons during 1990.

= Another change incorporates some requirements; of 40CFR302 - Designation, Reportable Quantities and' Notifications. These additions were made to ensure-this regulation is reviewed if we exceed any-technical specification limits.

Finally 'there were several small corrections and additions made- to correct and add measurement units in tables -and calculations, and' provide a better

~ definition of terms in calculations.

None of these changes in the ODCP reauce the accuracy or reliability of the dose calulations or setpoin? determinations B-1 j

l IAhlL3A CALVERT CLIFFS NUCLEAR POWER PLANT

- EFFLVENT AND WASTE DISPOSAL SEMI AhNUAL REPORT FIRST HALF - 1990 SOLID WASTE AND 1RRADIATED FUEL 5HIPMENTS M,_50 LID _ WASTE SHIPPED OFFSITE FOR BURI AL OR DISPOSAL (NOT IRRADI ATED FUELJ >

C 110 NTH EST. TOTAL

1. Tvoc of Waste UNITS PEllQQ_ ERROR %

a. Dewatered spent resin m3 ....

C1 - --

2.00E401

'b. Dry Compressible Waste, m3 2.04E+02 Contaminated Equipment, etc. C1 4.57E+00 5.00E401 3 c. Irradiated Compcnents, m3 ----

Control Rods, etc. Ci --

5.00E+01

d. . Other (CVCS Filters) m3 ....

Ci ----

2.00E401

2. Estimate of Major Nuclides-(Dy Type of Waste)*

b. Tritium - 3 3.14E+00 %

Carbon -

14 1.10E+00 %

1ron- - 55 4.47E+01 %

Cobalt - 58 1.44E400 %

Cobalt -- 60 1.41E+01 %

Nickel - 63 1.73E+01 %

Cesium - 134 3.03E400 %

4- Cesium. -

137 1.10E+01 %

Antimony- - -

125 1.42E400 %

o Only nuclides greater than 1% are reported-

- 3. Solid Waste Disposition Number of Shioments Mode of Transportation Destination 8 Motor Surface Transit Scientific Ecology Group-Oak Ridge, TN 17 t

,---e,b,rev.--w,e_-, e,-e---g=-r+-*+-,%.-e s --ew -v-e, ,, n e

, c c -r ,w.,-e-+w--+--++,-vee- wmw * ,=w-r e e we 4 -e .-we--e-me:r----+===-,-ww-+=+.=www-----w-----,e

ATI'ACllMENT I ODCM (Cl%07) TEXT WITil CilANGES

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