ML20196G149
| ML20196G149 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/31/1987 |
| From: | Tiernan J BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8803070049 | |
| Download: ML20196G149 (26) | |
Text
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t SEMI-ANNUAL EFFLUENT BRLFASE REPORT CALVERT CLIFFS NUCLEAR POWER PIANT SECOND HALF - 1987 TABLE OF CONTENTS
- 1. REGULATORY LIMITS . . . . . . . . . . . . . . ....................................... 1 A. Fission and Activation Gases........................................ 1 B. Iodines and Particulates with Half Lives Greater than Eight Days.... 1 C. Liquid Effluents.................................................... 2 II. MAXIMUM PERMISSABLE CONCE.NTRATIONS...................................... 2 A. Fission and Activation Gases........................................ 2 B. Iodines and Particulates with Half Lives Greater than Eight Days.... 3 C. Liquid Effluents.................................................... 3 III. TECHNICAL S PECIFICATION REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . 3 IV. AVERAGE ENERGY.......................................................... 4 V. MEASUREMENTS AND APPP.OXIMATIONS OF TOTAL RADI0 ACTIVITY. . . . . . . . . . . . . . . . . . 4 A. Fission and Activation Gases............... ........................ 4
- 1. Batch Releases........... ...................................... 4
- 2. Continuous Releases............................................. 5 B. Iodine and Particulates,............................................ 5 l
- 1. Batch Releases.................................................. 5 !
- 2. Continuous Releases........ .................................... 5 C. Liquid Effluents.................................................... 5
- 1. Batch Releases.................................................. 5
- 2. Continuous Releases............................................. 6 D. Es t ima t i on o f To tal Er ro r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
- 1. Liquid.......................................................... 6
- 2. Gases........................................................... 6 VI. BATCH RELEASES.......................................................... 7 i A. Liquid.............................................................. 7 B. Gaseous............................................................. 7 VII. ABNORMAL RELEASES....................................................... 8 A. Liquid.............................................................. 8 B. Gaseous............................................................. 8 TA6LES 1A - Gaseous Ef fluents - Summation of Rel eases , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 1C - Gaseous Effluents - Ground Level Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 2A - Liquid Effluents - Summation of All Releases.......................... 13 2 B - L i qu i d E f f lu e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 3A - Solid Waste and Irradiated Fuel Shipments............................. 18 8803070049 871231 F PDR ADOCK 05000317 . <
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. CALVERT CLIFFS NUCLEAR POWER PL ANT EFFLUENT AND WASTE DISPOSAL SEMI- ANNUAL REPORT <
SUPPLEMENTAL INFORM ATION Facility - Calvert Cliffs Nuclear Power Plant I
Licensee - Baltimore Gas & Electric Company I. REGULATORY LIMITS l A. Fission and Aetivation Gases
- 1. The instantaneous release rate of noble gases in- gaseous ~ efflutats l l 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. !
- 2. Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce gaseous emissions when the : calculated l gamma dose due to gaseous . effluents exceeds 1.20 mrad or. the calculated I, beta dose due to gaseous effluents exceeds 2.40 mrad at the site bound-ary in a 92 day period.
- 3. The air dose at the site boundary due to noble gases released 'in gas-eous effluents shall not exceed:
10 mrad gamma radiation / quarter 20 mrad beta radiation / quarter !
20 mrad gamma radiation / year !
40 mrad beta radiation / year
- 4. All of the above parameters are calculated according to the methodology specified in the Offsite Dose Calculation Manual (ODCM). i i B. Iodines and Particulates with Half Lives Greater than Einht Davs i
- 1. The instantaneous release rate of lodines and particulates in' gaseous '
effluents shall not result in a site boundary dose in ' excess of' 1500 mrem / year to any organ.
- 2. The Gaseous Radwaste Treatment System and the Ventilation Exhaust l l Treatment System shall be used to reduce radioactive materials in gas-- ,
eous effluents when calculated doses exceed 1.8 mrem to any organ in n !
92 day period at the site boundary. !
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- 3. The dose to a' member of the public at the site boundary from lodine 131 and particulates with half lives greater than eight days in gaseous
- effluents shall not exceed:
15 mrem to any organ per quarter 30 mrem to any organ per year less than .1% of the above limits as a -result 'of burning contaminated -
oil
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- 4. All of the above parameters are calculated according to the tmethodology specified in the ODCM.
C. Liould Effluents
- 1. The . concentrations of radioactive isotopes in liquid effluents from the plant shall not exceed the values specified in 10 CFR, ~ Part 20, Appen-dix B, for unrestricted areas.
- 2. The liquid radwaste treatment system shall be used to reduce the radio-active isotopes 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.
- 3. The dose to a member of the public in unrestricted areas shall not ex-ceed:
3 mrem whole body dose per quarter 10 mrem dose. to any organ per quarter 6 mrem whole body dose per year -
20 mrem dose to any organ per year 1
- 4. All of the liquid dose parameters are calculated according to the meth-odology specified in the ODCM. ;
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- 11. 51 AXIhlUNI PERhllSS ABLE CONCENTR ATIONS A. Fission and Activation Gases Prior to the batch release of gaseous effluents, the gas gamma activities are summed. If the total does not exceed t!.e dose rate limitations for the most limiting isotope, then the batch is released. If the r1ost limiting ,
isotope criteria is not met, then a detailed dose rate calculation is per- )
formed as described in the ODCM. l 1
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B. Iodines and Particulates with Half Lives Greater than Eicht Days Compliance to the dose rate limitations from Iodines and particulates is demonstrated ' by calculating the maximum quantity _- that could be _ seen on a weekly sample. -This is reduced by a factor of 0.5 for conservatism. As long as the I-131 (most limiting isotope) releases in a seven day period do not exceed 12.5 Ci,- then no further analyses are needed to verify compliance without exceeding the limits of 1.B.3.
C. Liould Effluents The MPCs used for radioactive materials released in liquid effluents are in accordance with Technical Specifications and/or are derived from the -use of notes to Appendix B, 10 CFR, Part 20. In all cases, the - most restrictive (lowest) MPC found for each isotope is used regardless of solubility.
The following limits were used to calculate the percent of applicable limit in Table 2A:
1.
Fission and Activation Products - Limit used 1 x 10~7 uCi/ml. This lim-it was used as given in the notes to Appendix B. Table II, Column 2 of 10 CFR 20.
- 2. Tritium - Limit used 3 x 10-3 uCi/ml.
III. TECilNICAL SPECIFICATION REPORTING REOUIREh!ENTS (Section 6.9.1.8)
A. Previous Calendar Year (1987) Dose Assessment Summary During 1987 liquid releases from Calvert Cliffs resulted in a maximum organ dose of 0.80 mrem and a maximum whole body dose of 0.085 mrem. This was less than 5% of the allowable yearly Technical Specification organ dose lim-it and less than 2% of the allowable yearly Technical Specification whole body dose limit. This dose was calculated using ODCM methodology (Adult Fish and Shellfish Pathways). The Gastro-intestinal Tract was the maximum organ dose pathway.
Gaseous Noble Gas Releases resulted in a maximum of 0.13 mrad samma and 0.35 mrad beta exposure. Particulate releases from Calvert Cliffs resulted in a maximum organ exposure of 0.44 mrem via the Thyroid Pathway. These doses were calculated using ODCM methodology. All gaseous release pathways were below 2% of their allowable Technical Specification limits for 1987.
D. 40 CFR 190 Total Dose Comoliance Using the maximum doses listed in Section 3A and ODCM calculations the maxi-mum exposed individual would receive less than 4% of any of the allowable doses defined by 40 CFR 190.
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9 C. Solid Waste Reoort Reauirements In 1987 there were four types of radioactive solid wastes shipped from Calvert Cliffs. These were:
- 1. Dry compacted waste.
- 2. Radioactive resin dewatered and shipped in high integrity containers.
- 3. Oil absorbed in commercial granular fired clay product or using petroset brand oil solidification agent.
- 4. CVCS and Spent Fuel Pool filters solidified using cement.
D. ODCM and PCP Channes During the second half of 1987 a revision was made to the ODCM to incorpo-rate offsite environmental sampling sites, and site boundary changes.
The changes to the offsite environmental sampling sites were necessary due to new highway construction which forced relocation of some sites. The map changes reflected the new sampling sites, and expanded the site boundary to include new property acquisitions.
This revision did not change any dose or setpoint calculations. A copy of the change is attached.
IV. AVERAGE ENERGY Not Applicable V. ME ASUREMENTS AND APPROXIMATIONS AND TOTAL R ADIOACTIVITY A. Fission and Activation Gases
- 1. Batch Releases Prior to each batch release of gas from a pressurized gas decay tank, a sample is collected and analyzed for each significant gaseous isotope using a Ge detector. The total activity released is based on the pres-sure/ volume relationship (gas laws) of the tank.
Prior to and after the release of gas as a result of purging contain-ment, samples are collected and analyzed for each significant gaseous isotope using a Ge detector. The total activity released is based on containment volume and purge rate. Activity buildup while purging is also considered.
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- 2. Continuous Releases - 1 During the release .of, gas from 'the main vents; samples are collected !
and . analyzed at least weekly for ' each significant - gaseous ' isoto'pe - using a Ge detector. The total' activity released for - the week is' based . on the total sample activity decay corrected to .the : midpoint of. the sample - '
period and multiplied by' theimainl Vent flow for the week. '
B.. todine and Particulates .
- 1. Batch Releases ,
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- The total activity released from- a pressurized gas . decay - tank . contain- y
! - ment purges and containment vents ' as lodines - and particulates is ac- 3
- . counted for by the main- vent Iodine and' particulate continuous - samples.- :
l l 2. Continuous Releases i
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L During the release of gas from the main vents; samples. of -lodines and .-
particulates are collected; using a : charcoal ~ and particulate filter, re- '
= spectively. The filters are removed - weekly and are analyzed f for : each l significant gamma isotope using a Ge - detector. The f total - activity ' re- !
! leased for the week is based on the total. sample activity . found on the !
filters decay corrected to the midpoint of the sample period and multi- '!
plied by the main vent flow for the week. These weekly - particulate filters are then composited to form monthly and quarterly composites at which time gross alpha and strontium 89 and 90 are analyzed. -!
C. Llauid Effluents f
- 1. Batch Releases i i
Prior to the release of liquid from a waste tank, a sample is collected ~ ;
and analyzed for the concentration ' of each significant gamma energy- '
radionuclide to demonstrate compliance with Section I.C.! 'above using l the water flow rate in each discharge conduit -into which the effluent !
is discharged at the time of discharge. The total activity ' released in~
each batch is determined by multiplying the volume released times the concentration of each ' isotope. The actual volume released is ~ based ~on the difference in tank levels prior - to and after the release. A pro- j portional composite sample is also withdrawn for. each release: and this . 1 is used in turn to prepare monthly and quarterly composites' for Juse in analyses of gross alpha, strontium 89 and 90, and tritium.
When steam generator blowdown- is discharged to the circulating' water con-duits, 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. compos-ite. is analyzed for each' significant isotope using a Ge detector and 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- use' in analyses of tritium, gross alpha, and strontium 89 and 90.
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' 2.. Continuous Releases None D. Estimation of Total Error Total error on all releases was estimated ' using as a minimum - the' random l
counting error associated with typical releases. In addition to the random error, the detector , to sample geometry systematic error during gamma count-ing was determined. This included an estimate 'of sample volume error - and-sample pipetting error. More specifically - the following other systematic -
errors were also examined:
- 1. Liquid a) Error in volume of liquid released prior to dilution during batch '
l releases.
b)- Error in volume of liquid released via steam generator blowdown, c) Error in amount of dilution water used during the reporting peri-od.
- 2. Gases a) Error in main vent release flow, b) Error in sample flow rate.
c) Error .in containment purge release flow.
l d) Error in gas decay tank pressure.
Where errors could be estimated they are usually considered additive.
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' VI. BATCH RELEASES J
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3RD 4TH-OUARTER !
QUARTER A. Liquid
- 1. Number of batch releases 5. 70E+ 01 80E+01- , -
- 2. Total time period for batch _
releases (min). - 1 83E+04 1.23E+04
- 3. . Maximum time period for a-batch release (min) ' 1.58E+03 6.47E+02
- 4. ' Average time period for batch .
j releases (min) 3.21E+02 2.57E+02
- 5. Minimum time period for.a I batch release (min) 2.10E+01~ 1.60E+01-
- 6. Average stream flow during periods of effluent into a flowing-stream ,
(liters / min of dilution water). 4.39E+06 4.54E+06-B. Gaseous
- 1. Number of batch releases 2.70E+01 5.00E+00 ;
- 2. Total time period for batch' releases (min) 1.59E+04 1.53E+03
- 3. Maximum time period for a batch ,
release (min) 4.24E+03 5.85E+02
- 4. Average time period for batch release (min) 5.90E+02 3.06E+02
- 5. Minimum time period for a batch release (min) 1.40E+02 1.45E+02 t i
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..VII. ARHOEMAL RELEASES i
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1 3RD- 4TH l OUARTER OUARTER I
A.. Liquid
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-1. Number of releases . 0- i
- 2. -Total activity released'(Curies) 0- l l
B. Gaseous
- 1. Number of releases ~ ' -
- 2. Total activity releases (Curies) .0- -0. -;
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TABLE LA - REC GUIDE 1.21
' CALVERT CLIFFS NUCLEAR POWER PIANT EFFLUENT AND WASTE DISPOSAL SD(I-ANNUAL REPORT SECOND HALF - 1987 CASEOUS EFFLUENTS - SUMMATION OF ALL RET. RASES 3RD 4Til EST. TOTAL A. FISSION AND ACTIVATION GASES UNITS OUARTER OUARTER ERROR.%
- 1. Total Release Ci 9.70E+02 9.99E+02 2.15E+01
- 2. Averace release rate for oeriod uCi/see 1.23E+02 1.27E+02
- 3. Percent of tech.soec.11mit(1) % 1.96E-02 2.01E-02
- 4. Percent of tech.soec.11mit(2) % 7.75E-03 8.04E-03
- 5. Percent of tech.soec.11mit(3) % 2.85E-01 2.94E-01
- 6. Percent of tech.soec.11mit(4) % 1.43E-01 1.47E-01
- 7. Percent of tech.soec. limit (5) % 3.81E-01 3.94E 01
- 8. Percent of tech.sp' 11mit(6) % 1.90E-01 1.97E-01 B. 10 DINES
- 1. Total Iodine - 131 Ci 2.85E-02 2.74E-02 1.84E+01
- 2. Averare release rate for oeriod uCi/see 3.62E-03 3.49E-03 1, Percent of tech.soec. limit (7) % 8.60E-03 8.29E-03
- 4. Percent of tech.soec.11mit(8) % 9.17E-01 8.82E-01 J
- 5. Percent of tech.soec.11mit(9) % 4.59E-01 4.41E-01 C. PARTICULATES l
- 1. Particulates with half lives !
creater than 8 days Ci 2.89E-05 2.49E-05 1.84E+01 l I
- 2. Average release rate for veriod uCi/see 3.68E 06 3.17E-06 j
- 3. Percent of tech.soec.11mit(7) % 8.74E-06 7.52E 06 i
- 4. Percent of tech.soec.11mit(8) % 9.30E-04 8.02E-04 !
- 5. Percent of tech.soec.11mit(9) % 4.65E 04 4.01E-04
- 6. Cross aloha radionetivity Ci <7.80E-06 <1.20E-07 9
TABLE 1A - REC CUIDE 1.21 (Cont.)
CALVERT CLIFFS NUCLEAR POWER PIANT EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT SECOND HALF - 1987 CASEOUS EFFLUENTS - SUMMATION OF AT T. RELEASES 3RD 4TH EST. TOTAL D. TRITIUM UNITS OUARTER OUARTER ERROR.%
- 1. Total Release Ci 4.73E-01 8.28E-02 2.18E+01
- 2. Averare release rate for veriod uCi/see 6.02E-02 1.05E-02 NOTES TO TABLE LA (1) Percent of I.A.1 whole body dose rate limit (500 mrem / year)
(2) Percent of I.A.1 skin dose rate limit (3000 mrem / year)
(3) Percent of I. 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 of I. A.3 beta yearly dose limit (40 mrad) ,
1 (7) Percent of 1.B.1 organ dose limit (1500 mrem / year) l (8) Percent of I.B.3 quarterly dose limit (15 mrem) l (9) Percent of I.B.3 yearly dose limit (30 mrem) l I
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TABLE IC - REG CUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PIANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1987 GASEOUS EFFLUENTS - CROUND IIVEL RELEASES CONTINUOUS MODE BATCil MODE 3RD 4TH 3RD 4Til-
- 1. FISSION AND ACTIVATION GASES UNITS OUARTER OUARTER OUARTER OUARTER Arron -41 C1 - -
2.41E-02 3.78E-03 Krvoton -85 Ci - - 5.70E+00 5.02E+00 Krvoton -85m C1 4.09E+00 2.11E+00 1.78E-02 7.97E 03 Krvoton -87 Ci 5.38E-01 - 1.51E 04 -
Krvton -88 Ci - - 3.10E-03 4.05E-03 Xenon 131m Ci 1.27E+01 1.86E+01 1.53E+00 1.83E+00 i Xenon -133 Ci 7.30E+02 8.37E+02 1.71E+02 7.28E+01 Xenon -133m Ci 2.12E+00 1.44E+01 8.78E-01 9.10E 01 Xenon -135 Ci 4.05E+01 4.61E+01 6.87E 01 2.43E 01 Xenon -135m Ci - - 2.60E-04 -
Total for Period Ci 7.90E+02 9.18E+02 1.80E+02 8.08E+01
- 2. HALOGENS l
Iodine -131 Ci 2.85E-02 2.74E-02 (1) (1) l Iodine -133 Ci 4.86E-02 2.33E-02 (1) (1) l Total For Period Ci 7.71E-02 5.07E-02 (1) (1) f (1) Iodines in batch releases are accounted for with the continuous main vent samplers when the release is made through the plant main vent, t
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TABI2 ]C -REC CUIDE 1.21 (Cont.)
CALVERT CLIFFS NUCI2AR POWER PIANT'
' EFFIEENT AND YASTE DISPOSAL SENI-ANNUAL REPORT SECOND HALF - 1987 CASEOUS EFFLIPQfTS - CROUND LEVEL RELEASES CONTINUOUS MODE BATCll MODE 3RD 4TH 3RD 4Til
- 3. PARTICULATES UNITS OUARTER OUARTER OUARTER OUARTFR Cobalt -58 C1 1.87E-05 7.64E 06 (1) (1)
Cobalt -60 Ci - 9.78E-07 (1) (1)
Strontium -89 Ci <MDA (2) (3) (1) (1) strontium -90 Ci <MDA (2) (3) (1) (1)
Cesium -134 Ci - 2.93E 06 (1) (1)
Cesium -137 Ci 8.92E-06 1.28E-05 (1) (1)
Cerium -141 Ci 4.76E-07 5.27E-07 (1) (1)
Total For Period Ci 2.81E-05 2.49E-05 (1) (1)
(1) Particulates in batch releases are accounted for with the main vent continuous particulate samplers when the release is made through the plant main vent.
(3) Less than minimum detectable activity which meets the LLD requirements of Technical Specification 3.11.2.1.
(3) Does not include Strontium values for the 4th quarter.
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- s TABLE 2A - REC CUIDE 1.21 l
CALVERT CLIFFS NUC12AR POliER FIMIT EFFIIIENT AND WASTE DISPOSAL SIMI-ANNUAL REPORT SECOND HALF - 1987 LIOUID EFF111ENTS - SUMMA 7. ION OF AT1. RELFASES 3RD 4TH EST. TOTAL A. FISSION AND ACTIVATION CASES UNITS OUARTER OUIRTER ERROR.I
- 1. Total Release (not including tritium. rases. aloha) C1 1.61E+00 4.57E-01 2.16E+01
- 2. Average diluted concentration durine oeriod uC1/ml 2.80E-09 7.68E-10
- 3. Percent of tech.soce.11mit(1) % 2.80E+00 7.68E 01
- 4. Percent of tech.soec. limit (2) % 2.71E+00 1.02E+00
- 5. Percent of tech.soec.11mit(3) % 1.36E+00 5.10E-01
- 6. Percent of tech.soec.11mit(4) % 1.30E+00 1.09E-01
- 7. Percent of tech.soec.11mit(5) % 6.51E-01 5.45E 02 B. TRITIUM
- 1. Total Release C1 1.58E+02 3.09E+02 1.81E+01
- 2. Average diluted concentration durine veriod uCi/ml 2.75E 07 5.19E-07
- 3. Percent of aoolicable limit % 9.17E-03 1. 7_3 F, ,,0 2 C. DISSOLVED AND ENTRAINED CASES . . , ,
L._ Total Release C1 3.73E-01 2.13E-01 2.00E+01
- 2. Average diluted concentration i durine ceriod uCi/ml 6.48E-10 3.58E-10 l
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l TARM 2A - REC CUIDE 1.21 (Cont. )
CALVERT CLIFFS NUCLEAR POWER PIANT
. EFFIEENT AND WASTE DISPOSAL SENI-ANNUAL REPORT SECOND HALF'- 1987 l LIOUID EFFIEENTS - SUMMATION OF ALL REMASES i
3RD 4TH EST. TOTAL i D. CROSS ALPHA RADIGACTIVITY UNITS OUARTER OUARTER ERROR.I l
I 1. Total Release ci <1.00E-03 <2.57L 04 3.00E+00 E. VOIEME OF WASTE RELEASES forlor to dilution) liters 6.47E+06 5.15E+06 3.00E+00 F. VOIEME OF DIIETION WATER USED DURINC PERIOD liters 5.75E+11 5.95E+11 1.40E+01 1
NOTES TO TABLE 2A (1) Percent of I.C.1 10 CFR 20 Limit (IE 07 uCi/cc)
(2) Percent of I.C.3 Quarterly Organ Dose Limit (10 mrem)
(3) Percent of I.C 3 Yearly Organ Dose Limit (20 arem)
(4) Percent of I.C.3 Quarterly Whole Body Dose Limit (3 mrem)
(5) Percent of I.C.3 Yearly Whole Body Dose Limit (6 mrem) l l l
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TABLE 2B - REC CUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTK DISPOSAL SENI-ANNUAL REPORT SECOND HALF - 1987 LIOUID EFFIEENTS CONTINIXXIS MODE (1) BATCil MODE 3RD 4TH 3RD 4111 NUCLIDES BU RASED UNITS OUARTER OUARTER OUARTER OUARTER Sodium -24 Ci 0 0 7.74E-04 8.40E 03 Chromium -51 Ci 0 0 1.50E-02 3.22E 03 Manzanese -54 Ci 0 O 6.08E 03 1.27E 03 Cobalt -57 ci 0 0 1.14E-04 3.97E 05 Cobalt -58 Ci 0 0 1.65E-01 2.63E-02 Cobalt -60 Ci 0 0 5.42E-02 5.92E-03 Iron 59 Ci 0 0 2.08E-04 3.77E 05 Strontium -89 Ci 0 0 2.20E-04 (2)
Strontium -90 Ci 0 0 2.01E-04 (2)
Strontium -91 Ci 0 0 1.89E-04 -
Zirconium -95 Ci 0 0 1.50E-02 9.37E 04 Niobium -95 Ci 0 0 3.37E-02 2.95E 03 Niobium -97 Ci 0 0 -
7.46E 05 ,
Molybdenum -99 Ci 0 0 9.41E-04 1.12E 03 Technicium -99m Ci 0 0 1.70E 03 2.17E 03 Ruthenium -103 Ci 0 0 1.01E-03 6.73E 05 Ruthenium -106 Ci 0 0 3.81E 04 -
Cadmium -109 Ci 0 0 -
7.92E 04 Silver -110m Ci 0 0 3.07E-02 2.70E 03 Tin -113 Ci 0 0 1.99E-03 1.35E 04 Antimony -122 Ci 0 0 3.53E-04 -
Antimony -125 Ci 0 0 5.36E-02 1.54E-02 15
TABLE 2B - REC CUIDE 1.21 (Cont.)
. CALVERT CLIFFS NGC12AR POWER PIANT
. EFFIEENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1987 LIOUID EFFIEENTS CONTINUOUS MODC (1) BATCil MODE 3RD 4TH 3RD 4Til NUCLIDES MfRASED UNITS OUARTER OUARTER OUARTER OUARTER Tellurium -132 Ci 0 0 - 2.20E 05 Iodine -131 Ci 0 0 1.22E-01 2.62E 01 Iodine -132 Ci 0 0 2.68E-03 1.97E 04 Iodine' -133 Ci 0 0 8.51E-02 3.68E 02 Iodine -134 Ci 0 0 - 9.63E 06 Iodine -135 Ci 0 0 2.01E 02 5.89E-03 Cesium 134 Ci 0 0 4.10E-01 2.72E 02 Cesium -136 Ci 0 0 2.96E-04 1.46E 03 Ce s ittm -137 Ci 0 0 5.91E-01 5.15E 02 Lanthanum -140 Ci 0 0 - 7.34E 05 Lanthanum -142 Ci 0 0 -
2.91E 04 Cerium -141 Ci 0 0 - 7.96E 05 Cerium -144 Ci 0 0 7.16E-06 -
Tunesten -187 Ci 0 0 1.20E-04 2.85E 05 Total For Period Ci 0 0 1.61E+00 4.57E-01 l
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TABIE 2B o REC GUIDE 1.21 (Cont.1 CALVERT CLIFFS NUCIEAR POWER PIANT
. EFFIlJENT AND WASTE DISPOSAL SENI-ANNUAL REPORT SECOND HALF - 1987 i
LIOUID EFFIEENTS CONTINUOUS MODE (1) BATCil MODE 3RD 4TH 3RD 4Til NUCLIDES REllASED UNITS OUARTER OUARTER OUARTER OUARTER Krvoton -85m Ci 0 0 2.01E-05 9.22E-05 Xenon -131m Ci 0 0 - 9.80E-04 Xenon -133 Ci 0 0 3.24E-01 2.03E-01 Xenon -133m Ci 0 0 2.51E-04 1.65E 03 Xenon -135 Ci 0 0 1.38E-02 5.60E-03 Xenon -135m Ci 0 0 3.45E-02 1.57E-03 Total For Period Ci 0 0 3.73E-01 2.13E 01 (1) There were no continuous liquid releases during the 3rd and 4th quarters.
(2) Does not include Strontium values for the 4th quarter.
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TAB 12 3A CALVERT CLIFFS NUCLEAR POWER PIANT EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT SECOND HALF - 1987 SOLID WASTE AND IRRADIATED } VEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE M)R BURIAL OR DISPOSAL (NOTE IRRADIATED FTEL)
~
l 6-MONTH EST. TOTAL l 1. Tvoe of Vaste UNITS __ PERIOD ERRORI 3
- a. Devatored spent resin m 7.86E+00 Ci 3.55E+02 2.00E+01
- b. Dry Compressible Waste, m3 1.44E+02 Contaminated Equipment, etc. Ci 4.93E+00 5.00E+01 l
3 l c. Irradiated Components, m -----
Control Rods, etc. Ci -----
5.00E+01
- d. Other (CVCS Filters) m3 3.55E+00 Ci 1.50E+01 2.00E+01
- 2. Estimate of Major Nuclides (By Type of Waste)*
- a. Cobalt 58 5.60E+00 %
Cobalt 60 1.70E+00 %
Nickel 63 5.30E+00 %
Iodine 131 1.10E+00 %
Cesium 134 1.70E+01 %
Cesium -137 5.69E+01 %
Others 1.24E+01 %
- b. Iron -55 4.30E+01 %
Cobalt -60 1.50E+01 %
Nickel 63 9.00E+00 %
Cesium -134 1.10E+01 %
l Cesium -137 2.20E+01 % i l
- d. Iron -55 4.90E+01 %
l Cobalt -58 2.40E+00 %
l Cobalt -60 1.40E+01 %
Nickel 63 2.70E+01 %
Antimony -125 4.50E+00 %
Others 3.10E+00 % i l
- Only nuclides greater than 1% were reported l l
- 3. Solid Waste Disposition l Number of Shipments Mode of Transportation Destination i
i 7 Motor Surface Transit Barnwell, S.C.
1 Motor Surface Transit Richland, WASH 18
(.,.[.
t-CHEMISTRY PROCEDURE PROCEDURE NUMBER: CP 607 PROCEDURE TITLE: OFFSITE DOSE CALCULATION MANUAL 1
b / -/b'9 i GENERAL SGPERpSOR - CHEMISTRY DATE ,
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,/ M'ANAGER - NUCLEAR OPERATIONS
/94!W DATE 8)*9 2 - / 9-/6 81 POSRC MEETING # DATE i
i REVISION NUMBER: Revision O CHEMISTRY REVISION FORM NUMBER: CRF 87-38
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(j , ATTACHMENT (9) Page 1 of 2 LOCATIONS OF THE ENVIRONMENTAL SAMPLING SITES FOR THE CALVERT CLIFFS NUCLEAR POWER PLANT SITE SAMPLE SECTOR DISTANCE
- DESCRIPTION KM MI 1 DR1 NW 0.6 0.4 Onsite, Along Clifis 2 DR2 WNW 2.7 1.7 Route 4, Auto Dump 3 DR3 W 2.3 1.4 Route 4, Glovanni's Tavern (Knotty P!ne) 4 DR4 WSW 2.0 1.2 Route 4, Across from White Sands 5 DR5 SW 2.4 1.5 Route 4, at Johns Creek 6 DR6,A4 SSW 2.9 1.8 Route 4, at Lusby 7 A l, S 0.3 0.5 Onsite, Near Guard House, off Camp Conoy Road ,
8 DR7, Ib4 S 0.7 0.5 Onsite, Before Entrance to Camp C 165, Ib6 Conoy 9 DRS, A2 SSE 2.5 1.5 Camp Conoy Road, at the Emergency Siren 10 DR9, A3 SE 2.6 1.6 Bay Breeze Road 11 DR10 NW 6.4 4.0 Calvert Beach Rd. & Decatur St.
12 DRll WNW 6.6 4.1 Dirt Road,off Mackall & Parran Roads 13 DR12 W 6.7 4.2 Bowen & Mackall Roads 14 DR13 WSW 6.1 3.5 Mackall Road, near Wallville 15 DR14 SW 6.4 4.0 Rodney Point 16 DR15 SSW 6.2 3.9 Mill Bridge & Turner Roads 17 DR16 5 6.5 4.1 Across from Appeal School 18 DR17 SSE 5.9 3.7 Cove Point & Little Cove Point Roads ,
17 DR18 SE 7.1 4.5 Cove Point ,
Rev. O
ATTACHMENT (9) Page 2 of 2 LOCATIONS OF THE ENVIRONMENTAL SAMPLING SITES FOR THE CALVERT CLIFFS NUCLEAR POWER PLANT SITE SAMPLE SECTOR DISTANCE
- DESCRIPTION KM MI 20 DR19 NW 4.4 2.3 Long Beach 21 DR20 NNW 0.4 0.3 Onsite, near shore 22 DR21, A5, Ib7, WNW 19.3 12.1 At the Emergency Offsite IbS, Ib9 Facility, off Route 231 23 DR22 S 12.3 7.8 Solomons Island 24 DR23 ENE 12.6 7.9 Taylors Island 25 Wal, Ial, NNE&NE 0.2 0.1 Intake area
- la2 26 Wa2 N 0.3 0.2 Discharge area 27 Wbl ESE 0.6 0.4 Shoreline at Camp Conoy 23 Ib t , Ib2, Ib3 SSE 2.6 1.6 Garden plot off Bay Breeze Road 29 la4,la5 N/A N/A N/A Patuxent River 30 la3 E 0.9 0.6 Camp Conoy 31 la6 NNW 10.7 6.7 Kenwood Beach
- from the Central Point between the two containment buildings.
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s-B ALTIMORE GAS AND ELECTRIC CHARLES CENTER P. O. BOX 1475
- BALTIMORE, MARYLAND 21203 JOSEPH A.TIERNAN vice enssicawr NoctcAn Entmov pgggg37y gg,gggg U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos ! & 2; Docket Nos. 50-317 & $0-318 Semi-Annual Effluent Release Report Gentlemen:
Enclosed please find the Semi- Annual Effluent Release Report in compliance with paragraph 6.9.1.8 of the Unit I and Unit 2 Technical Specifications. This report does not include the analytical results for strontium for the fourth quarter. These salues will be provided in an updated report as soon as these results are available. As required, the meteorological data is on file.
Very truly yours, VW JAT/WBC/gla Enclosure ,
l cc: D. A. Brune, Esquire l J. E. Silberg, Esquire I R. A.Capra, NRC )
S. A.McNeil, NRC l W. T. Russell, NRC l D. C. Trimble NRC l T. Magette. DNR j i
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Document Control Desk February 26, 1988 Page 2 I
bec: P. E. Katz/R. C. L. Olson C.11. Cruse /R. F. Ash R. E. Denton/J. A. hiihalcik R. h!, Douglass/J. T. Carroll T. N. Pritchett/E. 1. Dauereis J. R. Lemons /R. P. Ileibel I W. J. Lippold/A, R. Thornton F. J. 61unno/ht. Gavrilas )
R. B. Pond, Jr./R. E. Cantrell L. B. Russell /R. L. Wenderlich C. C. Lawrence, Ill/hi. J. hiiernicki R. E. Lapp
)
R. C. DeYoung I C. 51. Rice R. G. Staker i L. F. Donatell I hl. E. Bowman /L. E. Satyards D. L. Shaw, Jr.
S. R. Cowne 1 P. E. hicGrane I l
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