ML20090A794

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Effluent & Waste Disposal Semiannual Rept,Jul-Dec 1991
ML20090A794
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 12/31/1991
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20090A781 List:
References
NUDOCS 9203030101
Download: ML20090A794 (22)
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Text

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e e CAIXERT CLIFFS NUCLEAR POWER PIANl' EFFLUENT ANI) WASTE DISPOSAL SEMI. ANNUAL REPORT SUPPL.EMENTAL INFORMATION Facility . Calvert Cliffs Nuclear Power Plant Licensee . Ilattimore Gas & Electric Company

1. REGULATORY LIMITS A. Fiuion and Activation Gases
1. The instantaneous release rate of noble gases in gaseous efnuents shall not result in a site boundary dose rate greater than 500 mrem / year to the whole body or greater than _ 30(X) 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 dose due to gaseous ef0uents exceeds 1.20 mrad or the calculated beta dose due to gaseous efuuents exceeds 2.40 mrad at the site boundary in a 92 day period (Technical Specification 3/4.11.2.<l).
3. The air dom at the site boundary due to noble gases released in gaseous efnuents si.e4 - it exceed (Technical Specification 3/4.11.2.2):

10 mrad /qtr, gamma air 20 mrad /qtt, beta air 20 mrad / year, gamma air 40 mrad 4 ear, beta air

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

B. Iodines and Particulates with 11alf Lives Greater than Eicht Days

1. The instantaneous release rate of iodines and particulates in gaseous ef0uents shall not result in a site boundary dose in excess of 1500 mrem & car to any organ (Technical Speci0 cation 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 ef0uents when calculated doses exceed 1.8 mrem to any organ in a 92 day 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 lodine 131 and particulates with half lives greater than eight days in gaseous efnuents shall not exceed (Technical Specification 3/4.11.2.3):

15 mrem /qtr, any organ h O & O1 R CK 920224 05o00337 PDR l

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30 mrentycar, any organ less than 0.1% of the above limits as a result of burning contaminated oil. ,

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

C. Liould Ef0uents

1. The concentrations of radionuclides in liquid effluents from the plant shall not exceed the values specified in 10 CFR Part 20, Appendix B, for unrestricted areas (Technical Specification 3/4.11.1.!).
2. The liquid. radwaste treatment system shall be used to reduce the concentration of radionuclides in liquid ef0uents from the plant when the ,

calculated doses to unrestricted areas exceed 0.36 mrem to the whole body, or l.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 S};ccification 3/4.11.1.2): ,

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

20 mrentycar, any organ

4. All of the liquid dose parameters are calculated according to the methodology specified in the ODCM.
11. MAXIMUM PEltMISSilit.E CONCENTitATIONS A. Fission and Activation Gases i

Prior to the batch release of gaseous ef0 cents, 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 Technical Specification 3/4.11.2.1 are not exceeded.

l B. Jodines and Particulates with llalf Lives Greater than Eicht Days Compliance with the dose rate limitations for iodines and particulates is demonstrated by analysis of the charcoal and particulate samples of the station main vents. The charcoal samples are analyzed by gamma spectroscopy for quantification of any release of radiciodines. The particulate samples are analyzed by gamma spectroscopy for quantification of particulate radioactive material. Based on .

guidance provided in the ODCM, compliance with dose rate limits for the '

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E,._._.-...____ __,_ -_ __ _ _ . _ . . . . - _ _ _ _ _ _ _ _ _ .

radiolodines rend particulates may be based on a comparison of the actual measured release quantity over a sample period with a pre. established upper bound.

C. Liould Efnuents

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The MPCs used for radioactive materials released in ikuld efnuents are in i accordance with Technical Specification 3/4.11.1.1 and the va ucs from 10 CFR 20,  ;

Appendix 13, including ap?heable table notes. In all cases, the more restrictive (lower) MPC found for eac 1 radionuclide is used regardless of solubility.

Ill. TECilNICAI, SPIOltlCATI()E.lWPol(TlNG l(EOUIR131ENTS (Section 6.9.1.8) ,

A. Previous Calendar Ygg (199m Dose Auessment Summary During 1991 liquid releases from Calvert Cliffs resulted in a calculated maximum organ dose of 1.90E.01 mrem and a maximum whole body dose of 5.08E.02 mrem. +

These doses are less than 2% of the Technical Speci0 cation yearly organ dose limit and less than 2% 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 control!!ng age group, and the Gastro. intestinal Tract representing the organ with the highest calculated Cose.

Gascous releases of noble gases resulted in a maximum air dose of 8.55E.02 mrad, gamma and 1.79E-01 mrad, beta. lodine and particulate releases from Calvert Cliffs ,

resulted in a maximum organ dose of 9.62E-02 mrem for the year via the milk. infant.

  • thyroid pathway. 'Ihese doses were calculated using ODCM methodology. For 1991, miculated offsite doses via the gaseous release pathways were below 3% of their

. allowable annual _ allowable Specification limits.

11. 40 CFR 190 Total Dose Compliancs  :

Ilased upon all releases for 1991 and the ODCM calculations, the maximurn exposed individual would receive less than 1% of the allowable dose. During 1991, there were no on. site sources of direct radiation that would have contributed to a significant or 3 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 incicase in the off. site calculated doses is attributable to the direct ex insure from on. site sources. A more detailed evaluation will be reported in the Annua : Radiological Environmental Monitoring Report.

C. Solid Waste Report Requirements During the second half of 1991 the types of radioactive solid waste ship?cd from Calvert Cliffs were radioactive resin, which was dewatered and shipped in high integrity containers, irradiated hardware which was shipped in high integrity steel containers, and dry compressible waste, wh.a was shipped as ISA waste in strong, tight containers. Also, Appendix A provides a detailed breakdown of the waste shipments for the second half of 1991 per the categories as specified in Technical Speci0 cation 6.9.1.8.

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

D. ODCM and PCP Change Two changes were made to the ODChi during the second half of 1991. The changes were reviewed by POSitC and approved by the Plant General h'anager, Calvert Cliffs Nuclear Power Plant, prior to implementation. 'the scope and basis for tha change is discussed in Appendix It in keeping with the requirement of the Technical SpeciGeation 6.17, a copy of the change to the CCNPP ODCh1 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 1991.

II. Jhdioactive Gaseous lilquent hionitoring instrumentation The Unit 2 hiain Vent Ileader Noble Gas effluent monitor (2111-$415) was out of service for greater than 30 days during the second half of 1991. This notice is required by Technical Specification 3.3.3.9. This monitor was declared inoperable on August 9, 1991 because of frequent Ilhts pump failures. The source of the failures was a _

blocked discharge line fitting but the source of the problem was not immediately identified despite extensive troubleshooting efforts. The Rhts effluent monitor was restored to service on September 12,1991.

lY. AYlil(AGE ENEl{G1 Not Applicable.

V. A_1EASU,lilB1ENTS ANI) Appl {ONIMATIONS ANI)TOTAIMl)JOACll\Tly A. Eission and Activation Gases 1._ llatch 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 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 radionucliJes. The total activity released is based on containment vohime and purge rate. Activity buildup while purging is also considered.

2. Continuous lleleases 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 radionuchdes. 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 now for the week.

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A monthly composite sample is collected from the main vents and analyzed by liquid scintillation for tritium. *lhe total trh;um release for the month in based on this sample analysis and the vent flow.

B. lodine and Particulates

1. 11atch Releases
  • lhe total activities of radiolodines and particulates released from a pressurized gas decay tank, containment pur;es and containment vents are accounted for by the continuous samplers on tle rnain vent.

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2. Continuous lleleases Dering the release of gas from the main vents, samples of lodines and particulates are collected usin a a charcoal and particulate filter, respectively. l The filters are removed wee dy and are analyted by gamma spectroscopy using a Oc detector for signliicant gamma emitting radionuclides. 'the total ,

activity released for the week is based on the total sample activity decay  ;

currected to the midioint of the sample period multiplied by the main vent i flow for the week. T hese weekly particulate filters are then composited to form monthly and quarterly composites for the gross alpha and strontium 89 and 90 analyses.

C. Liquid Efiluents

1. thitch Releases Prior to the release of liquid from a waste tank, a sample is collected and analyzed by gamma spectroscopy for the principal gamma etnitting radionuclides. To demonstrate compliance with the requirements addressed in Section 1.C.1 above, the measured radionuclide concentrations are  ;

compared with the allowable MPCst dilution in the discharge conduit is considered, and an allowable release rate is verified.

The total activity re! cased in each batch is determined by multiplying the volume t :Icased by the concentration of each radionuclide. The actual volume released is based on the difference in tank levels prior to and after the release. A proportional composite sartple is also withdrawn for each release and this is used in turn to prepare monthly and quarterly composites for the gross alpha, strontlem 89 and 90, and tritium analyses. ,

2. Continuous lleleases ,

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 allowaHe release rate is 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 S.

, m ._._. __ . - _ . _ . . _ . _ . _ , . _ , - . _ _ . . - _ . . _ _ _ . . _ . ~ _ _ _ _ _ - _

I emitting radionuclides. These results are multiplied by the actual quantity of ,

blowdown to determine the total activity released.1he weekly composite is also used to prepare anonthly 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 plrnt sumps. This ,

low level activity (mostly tritium) water is released directly to the Chesapeake llay. This water is sampled at least weekly and cornposited. These samples are added to a composite basco <>n the amount released during that week.

The composite sample is analyzed monthly for tritium and for the principal gamma emitting radionuclides. The results are multiplied by the actual quantity of liquid released to determine the total activity released. This  ;

composite is used to prepare quarterly sampics for strontlurn 89 and 90 ,

analyses.

- D. Estimation of Total Error Tual 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 syste:natic errors were also examined:

1. Liquid a) Error in volume of liquid 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 ilow.

d) Error in gas decay tank pressure.

Where errers could be estimated they are usually considered additive.

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VI. Illif'! Hl:1,EAS12i 12?l l

3RI) 4Til OtfARTEll OtfAltTl:R  !

A. Ih!!M

1. Number of batch releases 3.10E4 01 3.70E401
2. Total time period for batch releases (min) 1.40E +04 3.32E+04 i 3 hiuximum time period for a batch release (min) 1.63E+03 1.32E +04 4 Average ti.ne period for batch releases (min) 4.51E +02 8.97E4 02  !
5. hiinimum tinie period for a batch release (min) 6.00E+ 00 1.00E + 00
6. Average r,tream flow during periods of effluent into a flowirig stream (liters / min of dilution water) 4.46E+06 4.47E + 06 II. Gnseous

-1. Number of batch releases 1.50E+01 2.00E+ 01

2. Total time period for batch releases (min) 8.55E+04 3.06E+ 04
3. hinximum time period for a batch

. release (min) 6.74 E + 04 9.33E +03

4. Average time period for batch release (min) 5.70E+03 1.53E+03
5. - hiinimum time period for a batch release (min) 1.00E+00 1.00E+00 7

VI1. A11NO14h1 AL.ltl'I.lMSES

.tlu 31tD 4Til O1!AllTElt QL%Iti1,11 A. 1,hi!!d

1. Number of releases 0- 0-
2. Total activity released (Curles) 0 .O.
11. - Gnwous
1. Number of releases 0 0
2. Total activity releases (Curies) O. 0 i

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plli.lj i A ItEG GUIDE I.2I i CAINEllT CLilTS NUCLIMR POWEll PLANT EITLUENT ANI) WASTE 1)lSPOSAL SEMI. ANNUAL llEPOllT SECONI) IIAl.F .1991 GASEOUS EFFl.UENTS SUMMATION OF AILIEI.1%SliS 3111) 4Til EST. TOTAL A. FISSION AND ACI'lVATION G LSES UNITS QUAlt!'Elt QUAltTER EltitOlt, %

1. Total Release ci 5.05E+ 02 6.75E+ 02 15.40E+ 00
2. Average release rate for period uCi/sce 2.12E+ 01 3.81 E+ 0!
3. Percent of Tech. Spec. limit (1)  % 3.42E 03 4.62E 03
4. Percent of Tech. Snee. limit (2)  % 1.30E-03 1.79E-03
5. Percent of Tech. Spec. limit (3)  % 1.93E-01 2.61 E-01 6- Pereent of Tech.Spee limit (4)  % 9.65E 02 1.30E 01 ,

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7. Percent of Tech. Spec, limit (5)  % 2.17E-01 3.95 E-01 l
8. Percent of Tech. Spec. limit (6)  % 1.08E 01 1.488-01 I
11. IODINES
1. TotaI hidine - 131 Ci 1.23E-02 1.74 E-02 16.50E + 00
2. Average release rate for period uCi/sce 5,16E-04 9.84 E-04 1
3. Percent of Tech. Spec. limit (7)  % 1.23E-03 2.34E-03  ;
4. Percent of Tech. Spec, limit (8)  % 2.85E+ 00 4.03 E+00
5. Percent of Tech. Spec. limit (9  % 1.42 E+ 00 2.02 E+00 C. PAltTICULATES

-1. Particulates with halflives greater than 8 days Ci 7.91 E-05 4.62E-08 12.80E F01

2. Average release rate for period uCi/sce 3.33E.06 2.61 E-09
3. Percent of Tech. Spec. limit (7) -% 7.91 E-07 6.20E-09
4. Percent ofTech Spec, limit (8) G 1.83E 1.07E-05 i

5, Percent of Tech. Spec. limit (9)  % 9.16E 03 5.35 E-06

6. Gross alpha radioactivity Ci 3 06E+00 2.52E + 00 15.36E +01 l

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'.lAllLlLIAd[EG GUlDE I,2I (ConQ CALVERT CLilTS NUCLEAR POWER PI ANT EITLUENT AND WASTE DISPOSAL SEhll. ANNUAL REPORT SECOND llALF.1991 j fiASji{ JUS EITLUl:NTS SUNINI ATION OF Al.I, RiiLEASES '

P 3RD 4Til EST. TOTAL i

D. TRITIUAl UNITS QUARTER QUARTER ERitOR, %

1. Total Release Ci 4.69E + 00 6.39E-01 f l.32E+01
2. Average relcase rate for period uCi/sec 2.98E-01 4.06E.02 NOTES TO TAllLE l A l (1) Percent of 1.A.1 whole body dose rate litnit (500 mrem / year)

(2) Percent of I.A.! 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 I.A.3 beta quarterly dose limit (20 mrad) >

(6) Percent of1.A.3 beta yearly dose limit (40 mrad)

(7) Percent of LB.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 mrem)

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

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311}LlilC + IU'O.lil311lIldl CAISEl(T Cl.IITS NUCl.EAlt l'OWEtt PLANT EIT1.UENT AND WASTE lilSPOSAl, SEMI. ANNUAL,1(EPol(T SI:COND llAI.F .1991 G ASEOUS IIFI,0 ENTS . GBOUNI) 1.EYEt, f(l;Llinl2i CONTINUOUS Mul)E IINICilMOllE 31(D 4Til 31(13 4Til

1. I'lSSION AND ACTIVATION GASES UNITS QUAL (TElt QUAL (TElt QUAL (TElt QUAL (TElt Argon 41 Ci (2) -(2) 3.44E 65 1.58E 03 Krypton 85 Ci (2) (2) 1.58E + 00 5.70E +(X)

Krypton -85tn Ci 4.49E HK) 5.73 E + 00 2.37E-05 (2)

Krypton 87 Ci (2) 1.07 E + 00 (2) (2)

Kryton 88 Ci (2) (2) (2) (2)

Xenon -131rn Ci (2) (2) 8.51 E-02 6.16E 01 Xcnon 133 Ci 4.35E +02 5.51 E + 02 8.12E-01 3.19E + 01 Xenon 133m Ci (2) (2) 4.64 E-04 5.66E-01 Xenon 135 Ci 6.18E + 01 7.76E + 01 4.07E-04 3.04E-01 Xenon. 138 Ci (2) (2) (2) (2)

Total for Perkx! Ci 5.02 + 02 6.36E4 02 2.48E + 00 3.84E + 01

2. liALOGENS lodine 131 Ci 1.42E-03 7.12E-03 (1) (1) lodinc 133 Ci 1.08E-02 1.03E-02 (1) (1)

Total For Period Ci 1.22E-02 1.74F 02 (1). (1)

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CAINEl(T CLitTS NUCLEAlt l'OWEll l'! ANT EITLUENT ANI) WASTE 1)lSI'OSAL SES11. ANNUAL 1(EPOl(T SECONI)IIALF 1991 GASEOUS EITI.tlENTS Gl(OUNI)113'EL1(El EASliS CONTINUOUS MOI)E IIATCil MOI)E 31(D 4Til 31(1) 4Til

3. pal (TICUIATES UNITS QUAL (TElt QUAL (TElt QUAL (TElt QUAL (TElt 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)

Zine 65 Ci (2) (2) (1) (1)

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

Strontium 90 - C1 (2) (3) (1) (1)

Molybdenum 99 Ci (2) (2) (1) (1) l Cesium 134 Ci (2) (2) (1) (1) l Cesium 137 Ci (2) (2) (1) (1)

Cerium 141 Ci (2) (2) (1) (1)

Cerium -144 Ci (2) (2) (1) _ (1) i Total For Period Ci - -

(1) (1)

NOTES TO TAllLE IC

'_ (1) Iodines and particulates in batch releases are accounted for with the main vent continuous samplers when the release is made through the plant main vent.

(2) Ixss than minimum detectable activity wh!;h meets the LLD requirements of Technical Specification Surveillance Requirement 4.11.2.1.2.

(3) The fourth quarter strontium results will be available in a supplemental repot, as soon as the activity values are available.

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TAlll 10 24 - l(liG Gilli)E I.21 CAIXEl(T Cl.IITS NUCLEAR POWEl( PLANT 1:lTLUENT AND WASTE DISPOSAL SEhll ANNUAL 1(EPOllT SECOND llAl.F.1991 I

1.10111D EFFl.UENTS . SUMM ATION OF AI.1,itEl. EASES 31(D 4Til EST. TOTAL A. FISSION ANI) ACTIVATION PROI)UCIS UNITS QUARTER QUARTER ERl(OR,'7r -

1. Total Release (not including i tritium, gases, alpha) Ci 5.87E.01 1.62E 01 13.30E+ 00
2. Average diluted concentration i during period uCi/ml 1.18E-08 8.28E.10
3. Percent of Tech. Spec. limit (1)  % 8.45 E-02 1.75E44
4. Pcrcent of Tech. Spec. limit (2)  % 4.25E 02 8.75E-02
5. Pcrcent of Tech. Spec. limit (3)  % 5.59E 01 2.50E 02
6. Percent of Tech. Sp~;. limit (4)  % 2.79E-01 1.25 E-02
11. TRITIUht
1. Total Release Ci 4.33E +02 4.52E+02 i9.80E+ 00
2. Average diluted concentration during period uCi/ml 8.66E 06 2.28E4)6
3. Percent of applicable limit (5)  % 2.89E-01 7.60E-02 C.1)lSSOINED AND ENTRAINED GASES
1. Total Release Ci 2.95E-02 1.76E-01 14.60E+00
2. Average diluted concentration

. during period uCi/mi 5.95E.10 9.00E.10 i

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lill.Lli1A:.RLG GU1111: ' LLLCetu l CAINEltT Ct.IITS NUCl.I'All POWElt PLANT l'ITLUENT ANI) WASTE lilSPOS Al, SEMI. ANNUAL lli:POllT SECONI) ll All' .1991 LlOUll) EITI.111TI S StIMM ATION OEAhldUil EASES 31tl) 4Til P.ST. 'l O'I'A L 1). UltOSS ALPilA ItAI)lO ACTI\TlY UNITS QUAltTElt QUAltTElt EltitOlt,'"c

1. Total Release Ci 2.23E 05 8.35E-05 15.36E+ 01 E. VOLUME OF WASTE RlilliASliS (prior to dilution) liters 9.73 E + 06 2.14 E + 07 1.30E + 00 F. VOLUME OF DILUTION WATER USliD DUlHNG PEltlOD liters 5.00E + 11 1.98E + 11 1.64 E + 0!

NOTIES 'l O TAILLE 2A (1) Percent of 1.C.3 Quarterly Organ Dose Limit (10 miem)

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

(3) Percent of 1.C.3 Ouarterly Whole 13ody Dose Limit (3 mrem)

(4) Pescent of 1.C.3 Yearly Whole llody 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 Sun eillance Requirement 4.11.1.1.1.

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Billi: 311 ItEG Gull.llLLal CAISEltT CLilTS NUCl.lMit l'OWEl( l'l ANT LITLUENT AND WASTE DISI'OSAl, SEMl. ANNUAL,itEl'Ol(T SECOND llALP.1991 LLQUID El'l'l,UENTS '

CON l'INUOUS MODE IIATCil MODE 311D 4Til 31tD 4Til NUCl.lDES itELEASED UNITS QUAltTEll QUAltTElt QUAltTElt QUAltTEll Sodium 24 Ci (1) (1) 8.74E-05 (1)

Chromium -51 Ci (1) (1) (1) 1.24E-04 Manganese 54 Ci (1) (1) 1.02E 03 1.92E 04 Cobalt 57 Ci (1) (1) (1) (1)

Cobalt 58 Ci (1) (1) 1.50E-02 7.35E-02 Iron 59 Ci (1) (1) (1) (1)

Cobalt 60 Ci (1) (1) 8.47E 03 4.82E 03 Zine 65 Ci (1) (1) (1) (1)

Strontium 89 Ci (1) (1) 3.28E-03 (2)

Strontium 90 Ci (1) (1) 2.93 E-04 (2)

Strontium 92 Ci (1) (1) (1) (1)

Niobium 95 Ci (1) (1) 2.85E-04 1,78E-03 Niobium -97 Ci (1) (1) 1.41 E-04 1.10E-03 Zirconium 95 Ci (1) (1) (1) 8.95E 04 Molybdenum -99 CI (1) (1) (1) (1)

Technetium 99m Ci (1) (1) 5.72E-04 3.05E-04 Ruthenium 106 Ci (1) (1) (1) . (1)

Silver -110m Ci (1) (1) 5.82E-03 1.92E-03 Tin 113 Ci (1) (1) (1) (1) ,

Antimony 122 Ci .(1) (1) 3.71E-05 6.04 E-06 Antimony' -125 Ci (1) (1) 1.39E-02 1.63E-05

!- Technetium -132 Ci (1) (1) (1) (1) 15

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CAINEl(T Cl.IITS NUCLi'All l'OWElt l'! ANT EITLUENT ANI) WASTE lilSPOSAL SEMI. ANNUAL 1(El'OltT SECONI) II ALF .1991 j.10U1D ElTillib'IS l CONTINUOUS MOI)E IIATCll MODE .

31(D 4TII 311D 4TII NUCL1 DES itELEASED UNITS QUAllTElt QUAL (TElt QUAlf.rElt QUAltTElt lodinc 131 Ci (1) (1) 1.85E-02 1.71 E-02 Imline 132 Ci (.1) (1) (1) 8.29E-06 lodine 133 Ci (1) (1) 1.82E-02 1.93E.03 Jodine 135 C1 (1) (1) 1.86E-04 (1)

Cesium 134 Ci (1) (1) 9.42E-02 1.89E-02 Cesium 136 Ci (1) (1) (1) 1.12E 05 Cesium 137 Ci (1) (1) 4.06E.01 3.82E.02 Barium 140 Ci (1) (1) 1.33E-03 (1)

Lanthanum 140 C1 (1) (1) 1.67E 03 5.25E-04 Cerium 144 Ci (1) (1) 1.87E-04 (1)

Tungsten 187 Ci (1) (1) 2.21E 04 (1)

Total For Period Ci (1) (1) 5.50E 01 1.43E-01 Xenon -131 m . Ci (1) (1) (1) (1)

Xenon 133 Ci (1) (1) 2.85E 02 1.18E-01 Xenon 133m Ci (1) (1) (1) 1.50E-03 Xenon 135 Ci (1) (1) 9.46E-04 - 7.37E-04 Xenon 135m Ci (1) (1) (1) (1)  ;

Total For Period Ci (1) (1) 2.95E-02 1.76E-01 16

TAlti.E 3 A j CAINEllT CLilTS NUCLEAll POWElt PLANT l EITLUENT AND WASTE DISPOSAL SEMI. ANNUAL llEPOllT t

' SECOND llALF - 1991

$ Sol,II) WASTE AND 1RitADI ATEll l'UEL SillPMENTS k A SOI,lD WWIE Silli' PED OEl' SITE 1111t ilUltl Al, Olt DISPOSAL,(NOT lititAI)l ATED l'UEl,)

6-hil I'li EST. TOTAL Q ,y '

"aste UNITS PEltlOD EllitOlt %

w, v .

m, tb { , .atered spent resin Ci 6.81 E +00 6.31 E +01 2fK)E+01 3

Compressible Waste (Burial) m 7.bl E + 01

.ataminated Equipment. etc. C 1.32 E + 01 tSJK)E +01 (1 ior to Compaction) nr( 5.40E + 02 c

c. Irradiated Components, m3 6.20E 01 Control Rods, etc. Ci 4.32E + 03 5.00E +01
d. Other (CVCS Filters) m3 -

Ci -

2AK)E+01

2. Estimate of Major Nucl8a 3 (by Type of Waste - Only nuclides >l G are reported)
a. Iron -55 4.55 E + 00 %

Cobalt -58 1.55E+00 ??

Cobalt -60 2.95E+00 'b Nickel -63 1.06E+01 %

Anhmony -125 1.10E +00 %

Cesium -134 1.96E +01 %

Cesium 137 5.56E+01 %

b. Carbon -14 2.05E+00 G Chromium -51 9.62 E + 00 %

Iron -55 3.55E+01 G 1 Cobalt -58 1.52E+00 %

Cobalt -60 1.01E +01 %

Nickel -63 1.31E+01 G Ruthenium -106 2.52E+00 G Silver -110 1.41 E +00 %

Antimony -125 4.75E+00 %

Cesium -134 2.70E+00 G Cesium -137 1.07E+01 %

c. Manganese -54 1.20E +00 %

1ron -55 5.ME+01 %

Cobalt -60 3.80E+01 %

Nickel -63 4.00E+00 %

18

t

, L\lli.E 3A CAINEltT Cl.lFFS NUCLEAlt l'OWEll l'I ANT EFFLUENT AND WASTE 1)lSI'OSAL SEMI. ANNUAL llEl'OllT SECONI) IIALF .1991 fiOl,II) WASTE AND lilllAl)l ATED FUEL, SillPMENIji(Cont.)

A. SOi,lD WASTE Sil!1'I'EI) OFFSITE FOlt ItUltl AL Olt DISPOSAI,(NOT 11111ADI ATEI) I'UEl,)

3. Solid Waste Disposition Number of Shjpments Mode of Transportation Destination 4 Motor Surface Transit Chem Nuclear System,Inc.

Barnwell, SC 1 Motor Surface Transit Scientific Ecology Group Oak Ridge, TN 19

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

4 APPENDIX A l

SOLID RADWASTE SillPMENT DATA l FOR  !

SEMI. ANNUAL EFFLUENT RELEASE REPOltTING  !

- SECOND IIALF 1991 l l

l

'IYPE WASTE: DAW 10 CFR 61 WASTE CLASS: A SOURCE OF WASTE: Radiologically Controlled Areas 3

SillPPING CONTAINEll: Scaled Container (2080 ft )

TOTA L CURIE QUANTI'IT: 13.2 Ci llOW DETEllMINED: Dose to curie content, conversion by volume based on generic distribution and scaling factors TOTAL llURIED WASTE VOLUME: 2474 ft3 IIOW DETERMINED: Container volume and number of containers shipped SOLIDIFICATION AGENT OR AllSOltL*'NT: None

'lTPE WASTE: Dewak.ed Resin 10 CFR 61 WASTE CIASS: A SOURCE OF WASTE: Miscellaneous Liquid Radwaste Processing /CVCS Processing SIIIPPING CONTAINER: High Integrity L-S-120 liner (120.3 ft3 )

TOTAL CURIE QUAN'ITlY: 13.2 Ci IIOW DETERMINED: Gamma scan using sample of resin

' 3 TOTAL WASTE VOLUME: 120.3 ft buried / Resin volume 87.2 ft3 IIOW DETERMINED: Weighed liner and calculated volume of resin SOLIDIFICATION AGENT OR AllSOltilENT: None A-1

TAlijS 211 - ItEG Gull)E 1.21 (CenM _

CALVEltT CLilTS NUCI EAlt l' OWED l'LANT l EITLUENT ANI' WASTE 1)lSI'OSAL SEMI ANNUAL llEl'OltT SECONI) llALF - 1991 1.10U11) EFI'I.UENTS NOTES TO TAltl.E 211 (1) Less than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillance llequirement 4.11.1.1.1.

(2) The fourth quarter strontium results will be submitted in a supplemental report as soon as the concentration values are available.

neu 17

APPENDIX A SOLID ltADWASTE SillPh1ENT DATA l'Olt SEh11. ANNUAL EFFLUENT RELEASE ItEPOltTING SECONI)IIALF 1991

'IYl'E WASTE: - Dewatered Resin 10 CFR 61 WASTE CIASS: B SOURCE OF WASTE: hiiscellaneous Liquid Radwaste Processing /CVCS Processing S!!!PPING CONTAINElt: High Integrity 1 8120 liner (120.3 ft3 )

TOTAL CURIE QUANTrlY: 61.0 Ci IIOW DETERh11NED: Gamma scan using sample from resin 3

TOTAL WASTE VOLUhlE: 120.3 ft buried / Resin volume 83.2 ft3 IlOW DLTERh11NED: Weighed liner and calculated volume of resin SOLIDIFICATION AGENT OR AllSORilENT: None

'IYPE WASTE: Irradiated Hardware 10 CFR 61 WASTE CIASS: C' SOURCE OF WASTE: In-Core Instrumentation Wire SillPPING CuNTAINER: High Integrity Steel Container TOTAL CURIE QUANTrlY: 4320 Ci IlOW DETERh11NEI): . Calculation based on materials composition and neutron activation TOTAL WASTE VOLUh1E: 22 ft IIOW DETERh11NEDr Container Volume SOLIDIFICATION AGENT OR AllSOltilANT: None A-2

~

1

-4; APPENDIX 11 1

SUMMAl(Y OF Cl!ANGES TO Tile CCNPP ODCM '

SECOND IIAl.F 1991 l

l CilANGES TO TIIE CCNPP ODCM IN SECOND llAl.F 1991

SUMMARY

AND llASIS The Calvert Cliffs Offsite Dose Calculation Manual (ODCM) 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.

Two changes were made to the ODCM duric; the second half of the year 1991. The changes were reviewed by the Plant Operations and Safety Review Committee (POSI(C) and approved by the Plant General Manager, Calvert Cliffs Nuclear Power Plant, prior to implementation. Change bars are previded in the right margin of the ODCM text to identify the changes made.

The first change was resiewed and approved on September 16,1991, and designated as change 91 155. This change was made to describe an environ.nental sampling location in better detail.

The second change was resiewed and approved on December 3,1991 and de !gnated as change 91211. The purpose of this- change was to correct site boundary direction dc ignation. The atmospheric dispersion factor listed was correct.

B-1

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

.=

l NITACIth!ENT (1) -

OI) Chi (CI' 607) TEXT MTIII

ClIANGES i

j.

1 l

E f

l-t I,

1 . .__ _.. ......_.__.__..;.______.___.__._..._

CP-607

, Page 2 of 2 ATTACBM[KT 9 (CON'T)

LQCATION U f_ T5IE ENVIRONMENTAL SAMPLIE SITES FOR Tile CALVERT CLIFFS NUCLEAR POWER PLANT SITE SAMPLE SECTOR DISTANCE

  • DESCRIPTION KM MI 16 DR16 S 6.5 4.1 Across from Appeal School 17 DR17 SSE 5.9 3.7 Cove Point & Little Cove Point Roads 18 DR18 SE 7.1 4.5 Cove Point 19 DR19 NW 4.4 2.8 Long Beach 20 DR20 NNW 0.4 0.3 Onsite, near shore 21 DR21,AS, WNW 19.3 12.1 At the Emergency Ib7, Ib8, Offsite Facility, Ib9 off Route 231 22 DR22 S 12.5 7.8 Solomons Island 23 DR23 ENE 12.6 7,9 Taylors Island 24 Wa'i , I al , NNE&NE 0.2 0.1 Discharge Vicinity la2 25 Wa2 N 0.3 0.2 Discharge Area 26 Wbl CSE 0.6 0.4 Shoreline at Camp Conoy 27 lbl,1b2, SSE 2.6 1.6 Garden Plot off Bay Ib3 Breeze Road PCR 28 la4,la5 N/A** N/A**N/A** Patuxent River 91-[B511]

155 l 29 la3 E 0.9 0.6 Camp Conoy 30 la6 NNW 10.7 6.7 Kenwood Beach

  • From the Central Point Between the Two Containment Buildings.
    • Sector and distance information is not given because these are control PCR samples of free-swimming fish species required by T.S. 4.12.1 to be 91-collected only "in areas not influenced by plant discharge". Exact 155 sample location may therefore vary. [B511]

Rev. I

Paga 13 of U I

2 3.2.5_ 'All iodines and particulate gamma emitters discharged from the

-b plant shall be accounted for with the continuous main sent header samples since all gaseous effluents are discharged via this path.

3.2.6 A gaseous waste discharge permit shall be prepared for batch re', eases to document release conditions and approva.'s, sample analysis results and compliance with Technical Specifications.

3.2.7 Credit shall be taken for main vent dilution from the reactor unit through which a release is conducted.

Unit 1 - Main Vent Flow - 63.7 m3/sec Unit 2 - Main Vent Flow - 57.5 m3/sec 3.3 Gaseous Effluent Dose Rate 3.3.1 Site Boundary Dose Rate (Total Body, Skin)

-- Technical Specificatien 3.11.2.la limits the dose rate at the I site boundary due to noble gas releases to s 500 mrem /yr, total body s 3000 mrem /yr, skin. If any of these are exceeded, lPMF review 40CFR302 to determine if a Reportable Quantity limit l90-102 has been exceeded. (3755) Radiation monitor alarm setp'ints l are established to assure that these release limits are not l exceeded. In the event any gaseous releases from the station results in the alarm setpoints' being exceeded, an evaluation of the unrestricted area dose. rate'resulting from the release may be performed using the following equations:

bt3 = X/Q X (2 KjXhj) bs = X/Q x (I Lj+1.1M)xhj g Where:

'btb = total body dose rate (mrem /yr)

X/Q = atmospheric dispersion 3

to the SE site boundary PMF PCR 2.2E-06 (sec/m ) 90 , 102 211

- \,

Rev. 1

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