ML20024C106

Semiannual Effluent Release Rept for Calvert Cliffs Nuclear Power Plant,Second Half - 1982

ML20024C106
Person / Time
Site:	Calvert Cliffs
Issue date:	03/01/1983
From:	Lundvall A BALTIMORE GAS & ELECTRIC CO.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8307120264
Download: ML20024C106 (19)

Text

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SEMI-ANNUAL EFFLUENT RELEASE REPORT FOR CALVERT CLIFFS NUCLEAR POWER PLANT SECOND HALF - 1982 LIST OF ENCLOSURES TITLE PAGE Regulatory Limits 1

Maximum Permissible Concentration 2

Measurements and Approximation of Total Radioactivity 3

Batch Releases 7

Abnormal Releases 8

Gaseous Effluents - Summation of Releases 9

Gaseous Effluents - Isotopic Breakdown 10 Liquid Effluents - Summation of Releases 12 Liquid Effluents - Isotope Breakdown 13 Solid Waste Shipments 16 8307120264 830301 PDR ADOCK 05000317 R

PDR

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1/

SUPPLEMENTAL INFORMATION Facility - Calvert Cliffs Nuclear Power Plant Licensee - Baltimore Gas & Electric Company L

REGULATORY LIMITS A.

Fission and Activation Gases:

1.

The instantaneous release rate of gross activity, except for I-131 and particulates with half-lives longer than eight days shall not exceed Qi 4

5

~

(3.85 x 10 )(MPC)i where Qi is the release rate in Ci/sec for isotope i and MPCi is the maximum permissible concentration of isotope i as defined in Appendix B, l

Table II, Column i,10 CFR 20.

l 2.

The release rates of gross gaseous activity shall not exceed 16 percent of the values specified in I.A.I. above when averaged over any calendar quarter. See Table IA, A3.

3.

The release rates of gross gaseous activity shall not exceed 8 percent of the values specified in I.A.I. above when averaged over 12 consecutive months. See Table IA, Ate.

l 1]( Submitted in accordance with Section 5.6.1.b of Appendix B of the Environmental Technical Specifications t

r-

- B.

Iodines and Particulates, Half-Lives > 3 Days:

1.

The release rate from the main vents of I-131 and particulates with half-lives greater than eight days released to the environment as part of

' airborne effluents shall not exceed 2.0 uCi/sec.

2.

The release rates of I-131 and particulates shall not exceed 8 percent of the value specified in I.B.I. above when averaged over any calendar quarter. See Table IA, B3.

3.

It should be noted that " iodines" as used here includes only iodine-131 since the Technical Specifications only refer to it specifically. Such other iodines, i.e., iodine-133, lodine-135, etc., are treated as gross activity and are included in I.A.I. and I.A.2.

4.

The release rates of I-131 and particulates shall not exceed 4 percent of the values specified in I.B.I. above when averaged over any 12 consecutive months. See Table IA, B4, C.

Liquid Effluents:

1.

The release rate of radioactive liquid effluents, excluding tritium and i

noble gases, shall not exceed 10 curies per unit during any calendar quarter.

2.

The radioactivity release concentrations in liquid effluents from the plant shall not exceed the values specified in 10 CFR, Part 20, Appendix B, for unrestricted areas.

l II.. MAXIMUM PERMISSIBLE CONCENTRATIONS 1

The MPC's used for radioactive materials released in liquid and gaseous 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.

i.

l

-_3_

The following limits were used to calculate the percent of applicable limit in

' Table 2A:

A.

Fission and Activation Products _ Limit used 1 x 10-7 uCi/ml. This limit was used as given in the notes to Appendix B, Table II, Column 2 of 10 CFR 20.

B.

Tritium - Limit used 3 x 10~3 uC1/ml.

This limit was used as given in Appendix B, Table II, Column 2 of 10 CFR 20.

C.

Dissolved and Entrained Gases - Limit used 3 x 10-6 uCi/ml.

This limit was used as given in Appendix B, Table II, Column 2 of 10 CFR 20.

III.

AVERAGE ENERGY - not applicable IV.

MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 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 isotope using a Ge(Li) detector. The total activity released is based on the pressure / volume relationship (gas laws) of the tank prior to and af ter the release.

Prior to and after the release of gas as a result of purging containment, samples are collected and analyzed for each significant isotope using a Ge(LI) detector. The total activity released is based on containment volume and purge rate with activity buildup while purging is being considered.

o.

2.

Continuous releases During the release of gas from the main vents, samples are collected and analyzed at least weekly for each significant isotope using a Ge(Li)

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detector. The total activity released for the week is based on the weekly result multiplied by the main vent flow for the week.

B.. Iodine and Particulates:

1.

Batch releases Total activity released from a pressurized gas decay tank as iodines and particulates is measured by the same methods as fission and activation gases.

4 Prior to and after the release of gas as a result of purging containment, iodines are sampled using a charcoal filter and particulates are sampled using a particulate filter. These filters are analyzed for each significant i

isotope using a Ge(Li) detector. The total activity released is based on containment volume and purge rate with activity buildup while purging is being considered.

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 for each significant isotope using a Ge(LI) detector. The total activity released g

for the week is based on the activity found on the filters multiplied by the main vent flow for the week. The activity on the filters is corrected for decay and buildup during the sample period. These weekly particulate filters are then composited to form monthly and quarterly composites at which time gross alpha e.nd strontium 89 and 90 are analyzed.

..,..e

-5 C.

Liquid Effluents:

1.

Batch releases Prior to the release of liquid from a monitor tank, a sample is collected and analyzed for the concentration of each significant gamma energy peak to demonstrate compliance with Section I.C.1 above using 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 af ter the release. A proportional composite sample is also withdrawn for each week's releases, and this is used in turri to prepare monthly and quarterly composites for use in analyses of gross alpha and strontium 89 and 90.

l 2.

Continuous releases Steam generator blowdown 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 for each significant isotope 1

l using a Ge(Li) detector and these results are multiplied by the actual t

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 -

1 and 90.

1 I

D.

Estimation of Total Error Total error on all releases was estimated using as a minimum the random counting error associated with typical releases. In addition to the random error, the detector to sample geometry systematic error during gamma counting 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 releases.

b.

Error in volume of liquid released via steam generator blowdown.

c.

Error in amount of dilution water used during the reporting period.

2.

Gases a.

Error in main vent release flow.

b.

Error in sample flow rate.

c.

Error in containment purge release flow.

d.

Error in gas decay tank pressure.

Where errors could be estimated they were usually considered additive.

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. V.

BATCH RELEASES 3rd 4th Quarter Quarter A.

Liquid:

1.

Number of batch releases 9.30E+01 7.70E+01 2.

Total time period for batch relene (hours) 5.20E+02 3.57E+02 3.

- Maximum time period for a batch release (min) 1.38E+03 1.64E+03 4.

Average time period for batch releases (min) 3.36E+02 2.78E+02 5.

Minimum time period for a batch release (min) 1.30E+01 1.90E+01

6. - Average stream flow during periods of effluent into a flowing stream (liters / min of dilution water) 4.64E+06 4.64E+06 B.

Gaseous:

1.

Number of batch releases 4.90E+01 1.50E+01 2.

Total time period for batch releases (min) 1.85E+04 7.18E+04 3.

Maximum time period for a batch release (min) 4.62E+03 3.72E+04 Average time i d for batch 4.

. release (min) per o 3.80E+02 4.79E+03 5.

Minimu:n time period for a batch release (min) 6.00E+00 1.20E+02 s

. yL ABNORMAL RELEASES 3rd 4th Quarter Quarter A.

Liquid:

1.

Number of releases 2.

Total activity released (Curies)U B.

Gaseous:

1.

Number of releases 2.

Total activity releases (Curies) i 2] Excluding tritium and dissolved gases s

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

' TABLE 1A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1982 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 3rd 4th Est. Total A.

Fission and activation gases Units Quarter Quarter Error, %

1.

Total Release Ci 4.01E+03 3.00E+02 2.15E+01 2.

Average release rate for period uCi/sec 5.10E+02 3.82E+01 3.

Percent of tech. spec. limit (1) 2.88E+00 2.31E-01 4.

Percent of tech. spec. limit (2) 2.90E+00 1.73E+00 B.

Iodines 1.

Total iodine - 131 Ci 7.00E-03 2.01E-03 1.84E+01 2.

Average release rate for period uCi/sec 8.90E-04 2.56E-04 3.

Percent of tech. spec. limit (3) 5.56E-01 1.60E-01 4.

Percent of tech. spec. limit (4) 6.51E+00 1.55E+00 C.

Particulates 1.

Particulates with half lives greater than 8 days Ci 2.14E-04 1.00E-03 1.84+01 2.

Average release rate for period uCi/sec 2.72E-05 1.27E-04 3.

Percent of tech. spec. limit (3) 1.70E-02 7.94E-02 4.

Percent of tech. spec. limit (4) 6.13E+00 5.86E+00 5.

Gross alpha radioactivity Ci

< 5.40E-07

< 9.07E-07 D.

Tritium 1.

Total Release Ci 4.10E-01 2.01E-01 2.18E+01 2.

Avemge release rate for period uCi/sec 5.21E-02 2.55E-02 3.

Percent of tech. spec, limit (1) 4.22E-04 2.07E-04 (1) Percent of I.A.2 for each quarter (2) Percent of I.A.3 for previous 12 months (3) Percent of I.B.2 for each quarter (4) Percent of I.B.3 for previous 12 months J

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. TABLE IC REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT SECOND HALF - 1982 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch stode 3rd 4th 3rd 4th 1.

Fission and activation gases Units Quarter Quarter Quarter Quarter krypton

- 85m Ci 4.50E+01 5.10E-01 krypton

- 88 Ci 2.60E-01 1.20E-03 xenon

- 131m C1 3.40E+01 1.10E+00 xenon

- 133 C1 4.00E+02 1.80E+02 3.50E+03 1.00E+02 xenon

- 133m Cl 1.10E+01 1.20E+00 xenon

- 135 Ci 6.00E+00 1.12E+01 2.40E+01 1.80E+00 argon

- 41 Ci 1.00E-01 1.50E-02 krypton

- 87 Ci 8.10E-03 Total For Period Ci 4.06E+02 1.91E+02 3.60E+03 1.10E+02 2.

Halogens Iodine

- 131 Cl 5.00E-03 1.98E-03 2.00E-03 2.80E-05 lodine

- 132 C1 2.20E-07 6.80E-09 lodine

- 133 Ci 1.81E-03 1.80E-03 5.95E-04 6.26E-06 iodine

- 135 Ci 9.00E-03 8.10E-03 8.90E-07 4.10E-08 bromine

- 82 Ci 8.90E-06 4.60E-06 Total For Period Cl 1.58E-02 1.20E-02 2.61E-03 3.90E-05

. TABLE IC REG GUIDE 1.21 (CONT'D)

CALVERT CLIFFS NUCLEAR POWER PLANT SECOND HALF - 1982 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode 3rd 4th 3rd 4th 3.

Particulates Units Quarter Quarter Quarter Quarter strontium

- 89 Cl 1.llE-04 9.25E-07

. strontium

- 90 Ci

< 2.32E-05

< l.05E-06 rubidium

- 88*

Ci 9.10E-02 2.40E-03 cobalt

- 58 Ci 1.90E-08 1.00E-03 cesium

- 138*

-C1 2.60E-04 1.50E-05 cesium

- 134 Ci 2.90E-06 cesium

-137 Cl 7.10E-06 7.40E-08 Total For Period Ci 1.34E 1.97E-06 9.12E-02 3.41E-03 o Particulates with half lives less than eight days.

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- TABLE 2B REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1982 LIQUID EFFLUENTS Continuous Mode (1)

Batch Mode 3rd 4th 3rd 4th Nuclides Released Units Quarter Quarter Quarter Quarter str:ntium

- 89 Cl 1.76E-05 8.65E-03 1.71E-02 strrntium

- 90 Cl 1.76E-05 1.27E-02 4.10E-02 c1sium

- 134 Ci 1.72E-01 1.87E-01 casium

- 137 Ci 3.00E-01 3.31E-01 lodine

- 131 C1

< 5.54E-05 3.90E-01 7.75E-02 cobalt

- 58 Ci 3.24E-01 4.76E-01 cobalt

- 60 Ci 5.57E-02 4.95E-02 lodine

- 132 Ci 8.25E-05 manganese

- 54 Cl 1.85E-02 8.60E-03 chromium

- 51 Ci 8.75E-02 1.03E-01 zirconium

- 95 Ci 2.79E-02 1.73E-02 nl:blum

- 95 Ci 5.15E-02 2.81E-02 molybdenum

- 99 Cl 1.50E-02 1.llE-03 barium

- 140 Ci 5.81E-03 entimony

- 124 Ci 1.43E-02 1.83E-02 lodine

- 133 Ci 1.32E-01 7.79E-03 cntimony

- 125 Ci 1.23E-01 5.40E-02 cobalt

- 57 Ci 7.01E-05 1.07E-03 silver

- 110m Ci 1.78E-01 3.31E-02 linthanum

- 140 Ci 1.24E-02 tin

- 113 C1 2.35E-03 1.75E-05 sodium

- 24 Ci 7.50E-04 8.12E-04 ruthenium

- 103 Ci 2.72E-03 2.89E-03

. TABLE 2A REG GUIDE.1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1982 LIQUID EFFLUENTS - SUMM ATION OF ALL RELEASES 3rd 4th Est. Total A.

Fission and activation products Units Quarter Quarter Error, %

1.

Total release (not including tritium, gases, alpha)

Ci 2.09E+00 1.43E+00 2.16E+01 2.

Average diluted concentration during period uCi/mi 3.74E-09 2.31E-09 3.

Percent of applicable limit 3.74E+00 2.31 E+00 B.

Tritium 1.

Total release Ci 1.29E+02 9.73E+01 1.81E+01 2.

Average diluted concentration during period uCi/ml 2.33E-07 1.59E-07 3.

Percent of applicable limit 7.77E-03 5.30E-03 C.

Dissolved and entrained gases 1.

Total release Ci 9.62E-03 6.llE-03 2.00E+01 2.

Average diluted concentration during period uCi/ml 3.94E-09 1.34E-09 3.

Percent of applicable limit 1.31E-01 4.47E-02 D.

Gross alpha radioactivity 1.

Total release Ci 4 9.62E-03

< 6.llE-03 3.00E+00 E.

Volume of Waste Releases (prior to dilution) liters 1.24E+07 9.74 E+06 3.00E+00 F.

Volume of dilution water used during period liters 5.54E+11 6.13E+ 11 1.40E+01 m

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, TABLE 2B REG GUIDE 1.21 (CONT'D)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1982 LIQUID EFFLUENTS Continuous Mode (1)

Batch Mode 3rd 4th 3rd 4th Nuclides Released Units Quarter Quarter Quarter Quarter neptunium

- 239 Ci 1.12E-03 cntimony

- 122 C1 4.05E-02 2.24E-02 ruthenium

- 106 Cl 8.87E-04 1.36E-03 unidentified Ci

< l.37E-05 4.73E-03 4.87E-03 Tetal For Period Ci

< l.04E-04 1.98E+00 1.48E+00

' TABLE 2B REG GUIDE 1.?! (CONT'D)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1982 LIQUID EFFLUENTS Continuous Mode (1)

Batch Mode 3rd 4th 3rd 4th Nuclides Released Units Quarter Quarter Quarter Quarter Xenon

- 133 Ci (1.34E-05 2.17E+00 7.07E-01 X non

- 135 C1 2.75E-03 1.35E-03 Xenon

- 133m C1 3.77E-03 9.47E-04 Xenon

- 131m C1 4.78E-03 (1) Continuous mode releases, i.e., nuclides released, are less than " unidentified" unless otherwise noted.

I

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. TABLE 3A EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1982 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-Month Est. Total 1.

Type of Waste Units Period Error %

a.

Spent resin, filter sludge m3 1.74E+01 evaporator bottoms, etc.

Cl 1.19E+02 2.00E+01 b.

Dry compressible waste, m3 5.88E+01 contaminated equipment, etc.

Ci 1.18 E+01 5.00E+01 c.

Irradiated components, m3 control rods, etc.

Ci

.d.

Other (describe) m3 Ci 2.

Estimate of major nuclides (by type of waste) a.

Cobalt

- 58 4.43E+01 Cesium

- 137 2.93E+01 Cesium

- 134 1.76E+01 Manganese - 54 1.80E+00 Cobalt

- 60 2.50E+00 Antimony

- 122 2.60E+00 Strontium

- 90 1.22E+00 b.

Cobalt

- 60 2.77E+01 Cobalt -

- 58 4.76E+01 Cesium

- 137 5.09E+00 Cesium

- 134 3.27E+00 Manganese - 54 2.40E+00 Niobium

- 95 4.70E+00 Chromium - 51 5.45E+00 Zirconium - 95 2.40E+00 c.

3.

Solid Waste Disposition Number of Shipments Mode of Transportation Destination 11 Motor surface transit Barnwell, S. C.

1 l

PART 50 e DOMESTIC LICENSING OF PRODUCTION AND (5) Administrative controls. Admin-

~

istrative controls are the provisions re-(2) The submission of a report to the

~

lating to organization and manage-appropriate NRC Regional Office The guides set out in Appendix this chapter within sixty (60)shown in Appendix D of Par r

ment, procedures, recordkeeping, O

review and audit, and reporting neces-days g

after January 1 and July 1 of each *Swater-cooled nuclear power reactors to-sary to assure operation of the facility kyear specifying the quantity of each of gmatmeet t in a safe manner.

the principal radionuclides released to erials in effluents released to un-be :; unrestricted areas in liquid and in gas-Icrestricted are (dx1) This section shall not deemed to modify the technical speci-eeous effluents during the previous six [ rea fications included in any Ucense issued '(6) months of operation and such prior to January 16,1969.

technical specifications have

' by the Commission to estimate maxiA IIcense in ~cther inform

. which

• not been designated shall be deemed to include the entire safety analysis mum potential annual radiation doses-

{ 50.37 Agreement limiting access to Re-

report as technical specifications.

to the public resulting from effluent (2) An appUcant for a license autho-releases. Copies of such report shall be stricted Data.

6

lization facilitrizing operation of a production or uti-sent to the Director of Inspection and' As part of his appIIcation and in any y to whom a construc-Enforcement, U.SJ Nuclear Regulatory event prior to the receipt of Restricted t

tion permit has been issued prior to -Commission.s Washington.'D.C. 20555.

Data or the issuance of a license or construction permit, the applicant January 16, 1969, may submit techni-cal specifications in accordance with shall agree in writing that he will not permit any individual to have access to this section, or in accordance with the T, Restricted Data until the Civil Service requirements of this part in effect If quantitles of radioactive materials 'E Commission shall have made an inves-tigation and report to the Commission

3) At t e in tia Ive of'the Commis.

e i nif ant y e

s ec

1. "M "

be amended to include technical spect. Acifically. On the basis of such repor f"lty of such indhidual and the

• 1. D a

fications of the scope and content Sand any additional information the om-mission shall have determined that which would be required if a new 11. eCommission may obtain from the 11 permitting such person to have access cense were being issued.

to Restricted Data will not endanger Icensee or others, the Commission me,y afrom time to time require the licensee the common defense and security. The

~

lto take such action as the Commission agreement of the applicant in this deems appropriate.

regard shall be deemed part of the li-cense or construction permit, whether 3 50.36a : Technical specifications on ef-so stated therein or not.

' fluents from nuclear poner reactors.

(a)In order to keep releases of radio-i 50.38 active materials to unrestricted areas Incligibility of certain applicants.

Any person who is a citizen, nation-during normal reactor operations, in-cluding expected operational occur.

(b)In establishing and implementing 7 any corporati. al, or agent of a foreign rences, as low as is reasonably achiev-N neratine Drocedures described in

• the Commi on, or other entity which paragraph (a) of this section, the 11-E to believe is ownedssion knows or ha able, each license authorizing oper.

censee shall be guided by the follow-a dominated by an allen a ation of a nuclear power reactor will controDed, or ing considerations: Experience with E include technical specifications that, the design, construction and operation }.shall be ineligible to r-

. In addition to requiring compliance of nuclear

" with applicable provisions of ( 20.106 power reactors indicates of this chapter, require:

that compliance with the technical obtain a license.

apply for and (1) That operating procedures devel-specifications described in this section oped pursuant to i 50.34a(c) for the will keep average annual releases of "I 50.39 Public inspection of applications control of effluents be established and radioactive material in effluents at Applications and documents submit-followed and that equipment installed small percentages of the limits spect, te,d to the Commission in connection in the radioactive waste system, pursu.- the operatingfled in i 20.106 of this chapter and in with applications may be made avalla, license. At the same ble for public inspection in accordance ant to i 50.34(a) be maintained and 3 me, the licensee is permitted the ti used.

with the provisions of the regulations Iflexibility of operation, compatible contained in Part 2 of this chapter.

6

[ with considerations of health and

. safety, to assure that the public is pro-STANDARDS rOR IaICENSEs AND vided a dependable source of power CONsTRDCT1oM PERMITS t

even under unusual operating condi-j tions which may temporarily result in f 50.40 Common standards.

releases higher than such small per.

In determining that a license will be centages, but still uithin the limits Issued to an applicant, the Commis-specified in and the opera { ting license. It is expect

• considerations:20.106 of this c sion will be guided by the following bility under unusual operating condi 'and equip

(

res the facility tions, the bcensee will exert his best e.,and oth e use of the facility, efforts to keep lesels of radioactive er technical specifications, or material m, cfnuents aslow as a reasonaNy the proposals. In regard to any of the achievable.

foregoing collectively provide reason-able assurance that the applicant will comply with the regulations in this chapter, including the regulations in Part 20, and that the health and safety of the public wiU not be endan-gered.

6 September 1,1982 50-17

58.

D

~ Unl wful divtrsion of soure-2 rnateria!

5 40.64(c)

Promptly P,T

.RO

-None 59.

D-Unlawful div:rsion of source rniterial 5 40.64(e) 15 days W

~ RO(1) lli(1) 60.

D Effluent Monitoring Report

$ 40.65 Semiannually W

RO(1) 1E (1)

. 61.

D Ceasing operations due to emission controls

540, 10 days subsequent to restart W

RO(1)

DCD (1)

App. A.1, Crit. 8 62.

D Failure of retention system

540, immediately.

P.T RO or IE None C

. App. A.1, Crit. 8 A 63 D

Annual site inspection

540, 60 days W

NMSS -

None App. A.IV 64

.A Effluent releases report -

5 50.36at a)(2), Semiannually W

RO (1)

. DcD (1 ).

Tech Specs 65 A,B Changes in security plan made without prior 5 50.54(p)

Two months af ter change W

NRR or MPA (1 )

approval NMSS (2) 66.

A,B Changes in emergency plan made without prior 5 50.54(q) 30 days after change or proposed to NRC W'

RO (1)

DCD (1) approval 67.

A,B Construction deficiency report 5 50.55(e)(2) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> P,T RO None 68.

A,B Construction deficiency report 5 50.55(e)(3) 30 days W

RO(!)

DCD (1 )

69.

A,B Facility changes, tests, and experiments.

5 50.59(b)

Annually or as otherwise specified in W

RO(1)

. DCD (1) conducted without prior approval license 70.

A,B Financial report 5 50.71(b) '

Annually W

NRR (10)

None w %.w,

-~,., -

- +~mwn-, _,.

Y h

bihOD' ETN-s APPENDlX A (Continued)

Types of Primary Secondary No.

Licensee Report Required By Timing Method Recipient Recipient e

71.

A,B FSAR updating 5 50.71(c)(1). Annually W

NRR (12)

None 72.

A,B Significant events

$ 50.72(a)

Prompt (I hour)

P OP CFR None 73.

A,B Financial report Part 50, Annually W

N R R (10)

None App.C,-

hsftRB t

A BALTIM ORE GAS AND ELECTRIC CHARLES CENTER P.O. BOX 1475 BALTIMORE, MARYLAND 21203 ARTHUR E. LUNDVALL. Jn.

Vict PRESIDENT Supply March 1,1983 Mr. Ronald C. Haynes, Director Office of Inspection & Enforcement c

U. 5. Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, PA 19t 06 4

SUBJECT:

Calvert Cliffs Nuclear Power Plant Docket Nos. 50-317 and 50-318 Semi-Annual Effluent Release Report

Dear Mr. Haynes:

The purpose of this letter is to forward to you the attached Semi-Annual Effluent Release Report for the second half of 1982 in compliance with Paragraph 5.6.1.b of the Unit I and Unit 2 Environmental Technical Specifications. This report does not include the meteorological summary which will be forwarded at a later date.

Very truly your,,/

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cc:

Director, Office of Management Information j

and Program Control l

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