ML20237A642

Radioactive Effluent Release Rept

ML20237A642
Person / Time
Site:	Calvert Cliffs
Issue date:	12/31/1997
From:	Earls C BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9808140243
Download: ML20237A642 (26)

Text

CAtttur Cttrrs NocLEAn POWER PLANT Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby. Maryland 20657 August 11,1998 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Independent Spent Fuel Storage Installation Docket No. 72-8 Radioactive Effluent Release Reoort

REFERENCES:

(a) Calvert Cliffs Unit Nos. I and 2 Technical Specification 6.6.3 (b) Independent Spent Fuel Storage Installation Technical Specification 6.3 As required by References (a) and (b), Attachment (1) is provided. Meteorological data is being kept in our onsite file and will be available upon request.

Should you have questions regarding this matter, we will be pleased to discuss them with you.

Very tiuly yours,

/

C. E. Earls General Supervisor- Chemistry CEE/RCG/bjd

Attachment:

(1) Radioactive Effluent Release Report Appendix: (A) Waste Shipments for 1997 \

cc: R. I. Mt Lean, DNR I

.. w ei G L) )

9808140243 971231 PDR ADOCK 05000317 R PDR

. I Document Control Desk Augbst 11,1998 Page 2 (Without Attachment)

R. S. Fleishman, Esquite I1. J. Miller, NRC J. E. Silberg, Esquire Resident Inspector, NRC A. W. Dromerick, NRC J. H. Walter, PSC Director, Project Directorate I-1, NRC K. N. Larson, ANI C. J. Paperiello, NRC l

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. , l ATTACHMENT (1) l l

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CALVERT CLIFFS NUCLEAR POWER PLANT .

RADIOACTIVE EFFLUENT RELEASE REPORT l

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Calvert Cliffs Nuclear Power Plant - Units 1 & 2 Independent Spent Fuel Storage Installation August 11,1998

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• ATTACHMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT Facility - Calvert Cliffs Nuclear Power Plant Licensee - Baltimore Gas & Electric Company I. REGULATORY LIMITS j A. Fission and Activation Gases i

1. The instantaneous release rate of noble gases in gaseous effluents shall not result in a site I boundary dose rate greater than 500 mrem / year to the whole body or greater than l 3000 mrem / year to the skin [Offsite Dose Calculation Manual (ODCM) 3.11.2.1].

2. Gaseous Radweste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce gaseous emissions when the calculated gamma-air dose due to ,

gaseous emuents exceeds 1.20 mrad or the calculated beta-air dose due to gaseous '

emuents exceeds 2.40 n: rad at the site boundary in a 92 day period (ODCM 3.11.2.4).

3. The air dose at the site bouadary due to noble gases released in gaseous emuents shall not exceed (ODCM 3.11.2.2):

10 mrad /qtr, gamma-air 20 mrad /qtr, beta-air 20 mrad / year, gamma-air 40 mrad / year, beta-air

4. All of the above parameters are calculated /xcording to the methodology specified in the ODCM. -

B. Iodines and Particulate with HalfI ives Greater Than Eight Days

1. The instantaneous release rate of Iodine 131 and radionuclides in particulate form with halflives greater than eight days in gaseous effluents shall not result in a site boundary dose in excess of 1500 mrem / year to any organ (ODCM 3,11.2.1). ,

2. He Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous emuents prior to their discharge when calculated doses exceed 1.8 mrem to any organ in a 92 day period at or beyond the site boundary (ODCM 3.11.2.4).

3. He dose to a member of the public at or beyond the site boundary from Iodine-131 and paniculates with halflives greater than eight days in gaseous emuents shall not exceed (ODCM 3.I1.2.3):

15 mrem /qtr, any organ 30 mrem / year, any organ less than 0.1% of the above limits as a resuli 6f b=.i::g contaminated oil.

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

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ATTACHMENT (1) l i

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT J

C. Liauid Effluents

1. The concentration of radionuclides, other that dissolved or entrained noble gases, released in liquid effluents from the plant to unrestricted areas shall not exceed the values specified in 10 CFR Part 20, Appendix B, Table II, Column 2 (ODCM 3.11.1.1).

2. The liquid radwaste treatment system shall be used to reduce the concentration of radionuclides in liquid effluents prior to their discharge from the plant when the i calculated dose to unrestricted areas exceeds 0.36 mrem to the whole body, or 1.20 mrem to any organ in a 92 day period (ODCM 3.11.1.3).

3. The dose to a member of the public in unrestricted areas shall not exceed )

(ODCM 3.11.1.2):

3 mrem /qtr, total body 10 mrem /qtr, any organ 3

6 mrem / year, total body 20 mrem / year, any organ

4. All of the liquid dose parameters are calculated according to the methodology specified i in the ODCM.

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 i analyzed by gamma spectroscopy for the principal gamma emitting radionuclides. The identified radionuclides concentrations are evaluated and an acceptable release rate is determined to ensure that the dose rate limits of ODC,M 3.11.2.1 are not exceeded.

B. Iodines and Particulate with Half Lives Greater than Eight Days Compliance with the dose rate limitations for iodines and particulate is demonstrated by analysis of the charcoal and particulate samples of the station main vents. The charcoal samples are analyzed by gamma spectroscopy to quantify release of radioiodines. The particulate samples are analyzed by gamma spectroscopy to quantify release of particulate radioactive material. All of the above parameters are calculated according to the methodology specified in the ODCM.

l C. Liauld Effluents The Maximum Permissible Concentrations (MPCs) used for radioactive materials released in

)

liquid effluents are in accordance with ODCM 3.11.1.1 and the values from 10 CFR Part 20, Appendix B, Table II, Column 2 including applicable table notes. In all cases, the more restrictive (lower) MPC found for each radionuclides is used regardless of solubility.

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ATTACHMENT (I)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT III. TECHNICAL SPECIFICATION REPORTING REQUIREMENTS A. Calvert Cliffs Nuclear Power Plant (CCNPPt Technical Specification 6.63

1. 1997 Dose Assessment Summary During 1997, liquid releases from Calvert Cliffs resulted in a calculated maximum annual organ dose of 0.239 mrem and a maximum whole body dose of 0.0068 mrem.

These doses are less than 1.20 % of the ODCM yearly organ dose limit and less than 0.12 % of the ODCM yearly dose limit for the whole body. The controlling pathway was the fish and shellfish pathway with adult as the controlling age group, and the gastrointestinal tract representing the organ with the highest calculated dose during 1997.

Gaseous releases of noble gases resulted in a maximum, quarterly, gamma air dose of 0.003 mrad and a maximum, quarterly, beta air dose of 0.013 mrad. Iodines and particulate in gaseous efiluents from Calvert Cliffs resulted in a maximum organ dose of 0.029 mrem for the year via the child-infant-thyroid pathway. These doses were calculated using ODCM methodology. For 1997, calculated offsite doses via the gaseous release pathways were below 1% of their allowable ODCM limits.

2. 40 CFR 190 Total Dose Compliance Based upon the releases of 1997 and the ODCM calculations, the maximum exposed individual would receive less than 1% of the allowable dose. During 1997, 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 offsite thermoluminescent dosimeters (TLDs). The results of these measurements did not indicate any statistical increase in the offsite radiation doses attributable to on-site sources. Therefore, no increase in the calculated offsite dose is attributed to the direct exposure from on-site sources. A more detailed evaluation will be reported in the Annual Radiological Environmental Operating Report.

3. Solid Waste Report Requirements During 1997, the types of radioactive solid waste shipped from Calvert Cliffs were dry compressible and non-compressible waste, cartridge filters, and dewatered resins which were shipped in High Integrity Containers (HICs) within NRC approved casks, Sealand containers, and steel boxes. Appendix A provides a detailed breakdown of the waste shipments for 1997 per the categories specified in Technical Specification 6.6.3. At CCNPP, methods of waste and materials segregation are used to reduce the volume of solid waste shipped offsite for processing, volume reduction and burial.

4. Offsite Dose Calculation Manual and Process Control Program (PCP) Changes There were no changes to the ODCM in 1997. A plant modification was initiated in 1997 to remove containment purge valves and replace them with blind flanges for containment integrity. This modification is scheduled to be completed in 1998 and changes to the ODCM and plant procedures will be implemented subsequent to the completion of the modification. This modification removes the capability to perform a modified (reduced flow rate) purge by throttling purge valves.

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ATTACIIMENT (I)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT There were no changes to the PCP in 1997.

B. Radioactive Gaseous Effluent Monitoring Instrumentation None of the ODCM effluent monitors were out of service for greater than 30 days during 1997.

C. Independent Soent Fuel Storage Installation (ISFSD. Technical Soccification 6.3 No casks of spent fuel were transferred to the ISFSI during 1997. No quantity of radionuclides were released to the environment during the ISFSI operation in 1997.

Additional information regarding the ISFSI radiation monitoring program is included in the Annual Radiological Environmental Operation Report.

IV. AVERAGE ENERGY Not Applicable.

V. MEASUREMENTS AND APPROXIMATIONS AND TOTAL RADIOACTIVITY A. Fission and Activation Gases

1. Batch Releases Prior to each batch release of gas from a pressurized waste gas decay tank or containment, a sample is collected and analyzed by gamma spectroscopy using a Germanium (Ge) detector for the principal gamma emitting noble gas radionuclides.

De total activity released is based on the pressure / volume relationship (gas laws) of the tank.

2. Continuous Releases l

A gas sample is collected at least weekly from the main vents and analyzed by gamma

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spectroscopy using a Ge detector for the principal gamma emitting noble gas j radionuclides. The total activity released for the week is based on the total sample activity decay corrected to the sample time multiplied by the main vent flow for the week.

1 Prior to and after each containment purge, a gas sample is collected and analyzed by I gamma spectroscopy using a Ge detector for the principal gamma emitting noble gas radionuclides. The total activity released is based on containment volume and purge rate.

A monthly composite sample is collected from the main vents and analyzed by liquid I scintillation for tritium. The total tritium release for the month is based on the sample analysis and the main vent flow.

B. Indine and Particulate

1. Batch Releases

l l o ATTACHMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT I

RADIOACTIVE EFFLUENT RELEASE REPORT The total activities of radioiodines and particulate released from pressurized waste gas j decay tanks, containment purges, and containment vents are accounted for by the continuous samplers on the main vent.

2. Continuous Releases During the release of gas from the main vents, samples of iodines and particulate 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 composites for the gross alpha and strontium 89 and 90 analyses.

C. Liauid Efnuents

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 I.C.1 above, the measured radionuclides concentrations are compared with the allowable MPCs; dilution in the discharge conduit is considered, and an allowable release rate is verified.

The total activity released in each batch is determined by multiplying the volume released by the concentration of each radionuclides. The actual volume released is based on the difference in tank levels prior to and after the release. A proportional composite sample is also withdrawn for each release and this is used in turn to prepare mon'hly and quarterly composites for the gross alpha, iron 55, strontium 89 and 90, and tritium analyses.

2. Continuous Releases To account for activity from continuous releases, a sample is collected and analyzed by gamma spectroscopy for the principal gamnia emitting radionuclides. The measured radionuclides concentrations are compared with the allowable MPC concentrations in the discharge conduit, and an allowable release rate is verified.

When steam generator blowdown is discharged to the circulating water conduits, it is sampled at a minimum of three times per week and these samples are used in turn to prepare a weekly blowdown composite sample based on each day's blowdown. The weekly composite sample is analyzed by gamma spectroscopy for the principal gamma emitting radionuclides. These results are multiplied by the actual quantity of blowdown to determine the total activity released. The weekly composite is also used to prepare monthly composites for tritium analysis.

During periods of primary-to-secondary leakage, the secondary system becomes  !

contaminated and subsequently, contaminates the turbine building sumps. The low-level ,

activity water (predominantly tritium) contained in the turbine building sumps is 1 1

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ATTACIIMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT released directly to the Chesapeake Bay. This water is sampled at least three times per week and composited. The composite sample is analyzed at least monthly for tritium and principal gamma emitting radionuclides. The results are multiplied by the actual quantity ofliquid released to determine the total activity released.

D. Estimation of Total Error Total error for 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 ofliquid 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 flow.

d. Error in gas decay tank pressure.

Where errors could be estimated they are usually considered additive.

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a ATTACHMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT VL BATCH RELEASES 1922 IST 2ND 3RD 4TH OUARTER QUARTER OUARTER OUARTER A. Liquid

1. Number of batch releases 2.70E+01 3.70E+01 2.30E+01 2.20E+01

2. Total time period for batch releases (min) 8.63 E+03 7.27E+03 7.27E+03 6.34E+03 3 Maximum time period for a batch release (min) 7.20E+02 5.93 E+02 6.50E+02 6.05E+02

4. Average time period for batch releases (min) 3.20E+02 1.97E+02 3.16E+02 2.88E+02

5. Minimum time period for a batch release (min) 4.1 SE+00 2.00E+01 2.70E+01 2.26E+01

6. Average stream flow during periods of effluent into a flowing stream (liters / min of dilution water) 8.18E+06 6.58E+06 8.76E+06 9.00E+06 B. Gatenna

1. Number of batch releases 6.00E+00 7.00E+00 1.00E+01 4.00E+00

2. Total time period for batch releases (min) 1.02E+03 1.25E+03 1.38E+04 2.40E+01

3. Maximum time period for a batch release (min) 5.40E+02 4.25E+02 1.23 E+04 1.50E+01

4. Average time period for batch release (min) 1.71E+02 1.79E+02 1.38E+03 5.99E+00

5. Minimum time period for a batch release (min) 2.90E+01 1.90E+01 8.69E+00 3.00E+00 I

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ATTACMMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT VIL ABNORMALRELEASES 1991 IST 2ND 3RD 4TII QUARTER QUARTER OUARTER OUARTER A. Liquid

1. Number of releases 2. Total activity released (Curies) B. Gaseous

1. Number of releases 2. Total activity releases (Curies)  !

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, ATTACHMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1 A - REGULATORY GUIDE 1.21 1997 l GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES l

l IST 2ND EST. TOTAL l A. FISSION ANI) ACTIVATION GASES i UNITS QUARTER QUARTER ERROR,%

1. Total Release I Ci i 3.79E+01 1 1.99E+01 1 5.00E+00 l

2. Average ielease rate for period I pCi/sec I 4.88E+00 1 2.54 E+00 1

3. Percent of Technical Specification limit (1) I  % 1 6.16E-04 I 2.85E-04 1

4. Percent of Technical Specification limit (2) I  % 1 3.24 E-04 1 1.66E-04 I

5. Percent of Technical Specification limit (3) I  % i 9.06E-03 1 4.33 E-03 1

6. Percent of Technical Specification limit (4) I  % i 4.53 E-03 1 2.17E-03 I

7. Percent of Technical Specification limit (5) i  % I 1.62E-02 I 8.56E-03 I

8. Percent of Technical Specification limit (6)  !  % i 8.12E-03 1 4.28 E-03 i

?. IODINES I i l i

1. Total lodine - 131 1 Ci i 1.88E-04 1 2.34E-04 1 7.00E+00 l

2. Average release rate for period I pCi/see i 2.42E-05 1 2.98 E-05 1

3. Percent of Technical Specification limit (7) I  % 1 5.75E-05 I 7.08 E-05 1

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4. Percent of Technical Specification limit (8) I  % I 3.60E-02 I 4.49E-02 i

5. Percent of Technical Specification limit ()) I  % i 1.80E-02 1 2.24E-02 i C. PARTICULATE I I i

1. Particulate with halflives l l greater than 8 days Ci I (10) l 5.71 E-06 i2.30E+01

2. Average release rate for period I pCi/sec I (10) I 7.27E-07 l l 3. Percent of Technical Specification limit (7) I  % I (10) I 1.43 E-07 i

4. Percent of Technical Specification limit (8) I  % i (10) I 1.15 E-07 I

5. Percent of Technical Specification limit (9) I  % (10) 1 5.73 E-08 I

6. Gross alpha radioactivity 1 Ci I (10) I (10) i N/A l

l 3RD 4TH l EST. TOTAL A. FISSION AND ACTIVATION GASES UNITS I QUARTER QUARTER I ERROR, %

1.

2.

Total Release Average release rate for period I Ci pCi/sec i 1.45E+02 1 1.24E+0 ! I R E+00 I I 1.83 E+01 1 1.56E+00 1

3. Percent of Technical Sxcification limit (s ) I  % i 2.02 E-03 1 5.07E-04 4

4. Percent of Technical Specification limit (2) I  % 1 1.23 E-03 1 1.66E-04 1

5. Percent of Technical Specification limit (3) I  % i 2.99E-02 1 6.98E-03 i j

6. Percent of Technical Specification limit (4) I  % i 1.49E-02 1 3.49E-03 i

, 7. Percent of Technical Specification limit (5) 1  % 1 6.58E-02 1 5.42E-03 I

8. Percent of Technical Specification limit (6) I  % i 3.29E-02 1 2.71 E-03 i B. IODINES I I I i

1. Total Iodine - 131 i Ci I 5.61 E-04 1 2.71 E-05 1 7.00E+00 l 2. Average release rate for period i pCi/sec I '7 MF-M i 3.4IE 06 1

3. Percent of Technical Specification limit (7) I  % I 1.68E-04 I 8.09E-06 1

4. Percent of Technical Specification limit (8) I  % i 1.07E-01 1 5.19 E-03 I

5. Percent of Technical Specification limit (9) I  % I 5.37E-02 1 2.59E-03 l

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l C. PARTICULATE I i i I j 1. Particulate with halflives I greater than 8 days Ci (10) I (10) 12.30E+01

2. Average release rate for period i pCi/sec I (10) l (10) i

3. Percent of Technical Specification limit (7) I  % i (10) I (10) l

4. Percent of Technical Specification limit (8) I  % i (10) I (10) 1

5. Percent of Technical Specification limit (9) I  % i (10) i (10) I l 6. Gross alpha radioactivity i Ci I (10) 1 (10) l N/A l 9 i

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, A'ITACHMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1 A - REGULATORY GUIDE 1.21 (Continued) 1997 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES I' IST 2ND D. TRITIUM l l l EST. TOTAL UNITS I QUARTER I QUARTER I ERROR,%

l. Total Release I Ci I 7.30E-01 1 1.67E+00 I .l.30E401

2. Average release rate for period I pCi/sec I 9.38 E-02 1 2.13 E-01 l l 3RD 4TH l EST. TOTAL D. TRITIUM UNITS I QUARTER QUARTER I ERROR,%

1. Total Release i Ci i 2.61 E+00 i 7.48E-01 1 1.30+01

2. Average release rate for period i pCi/sec I 3.28E-01 i 9.41 E-02 i NOTES TO TABLE 1A (1) Percent ofI.A.1 whole body dose rate limit (500 mrem / year)

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

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

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

(5) Percent ofI.A.3 beta quarterly dose limit (20 mrad)

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

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

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

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

(10) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of ODCM Surveillance Requirement 4.11.2.1.2.

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, ATTACHMENT (1) l CALVERT CLIFFS NUCLEAR POWER PLANT j RADIOACTIVE EFFLUENT RELEASE REPORT TABLE IC - REGULATORY GUIDE 1.21 1997 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES I CONTINUOUS MODE I BATCH MODE IST 2ND IST 2ND

1. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER QUARTER il QUARTER Argon - 41 i Ci I (2) I (2) I 1.29E-03 I (2)

Krypton - 85 I Ci i 1.55 E+00 1 (2) I 2.85E+00 I 2.25E+00 Krypton - 85m i Ci I (2) I (2) I (2) I (2)

Krypton - 87 i Ci I (2) 1 (2) I (2) I (2)

Krypton - 88 i Ci I (2) I (2) I (2) I (2) l Xenon - 13 Im l Ci I 7.6 I E+00 1 6.97E+00 1 1.07E-02 I (2)

Xenon - 133 i Ci I 2.40E+01 l 9.62E+00 1 2.52E-01 1 2.45E-01 Xenon - 133m i Ci 1 2.97E-02 I (2) I 8.86E-04 l 2.57E-03 Xenon - 135 I Ci i 1.65E+00 1 8.26E-01 l 1.97E-04 1 9.67E-03 Xenon - 135m i Ci I (2[ l (2) I (2) I (2)

Xenon - 138 i Ci I (2) 1 (2) I (2) 1 (2)

Total for Period l Ci I 3.48E+01 1 1.74 E+01 1 3.l l E+00 1 2.51 E+00

2. HALOGENS I I I I I lodine - 131 l Ci i 1.88E-04 1 2.34 E-04 I (1) I (1) lodine - 133 i Ci i 1.06E-03 I 4.47E-04 I (1) I (1)

Total For Period l Ci i 1.24 E-03 1 6.82E-04 I (1) 1 (1) i CONTINUOUS MODE i BATCH MODE 3RD l 4TH 3RD l 4Th I. FISSION AND ACTIVATION GASES I UNITS Q!!ARTER I QUARTER QUARTER I QUARTER Argon - 41 l Ci I (2) I (2) I (2) i 1.14 E-01 Krypton - 85 I Ci l 1.85 E+01 I (2) I 1.72E+01 1 2.19E-01 Krypton - 85m i Ci I 7.67E-03 I (2) I 2.45 E-04  ! 5.35E-02 Krypton - 87 I Ci I (2) I (2) I (2) i 2.65E-02 Krypton - 88 i Ci I (2) 1 (2) I (2)  ! 7.67E-02 Xenon - 131m i Ci I 6.86E-01 I (2) 1 5.13 E-01 I (2)

Xenon - 133 i Ci  ! 8.13 E+01 i 8.07E+00 1 2.39E+01 1 2.04 E+00 Xenon - 133m i Ci 1 5.86E-01 i (2) i 1.62E-01 1 4.64 E-02 Xenon - 135 i Ci i 2.34 E+00 1 4.75 E-01 1 5.91 E-02 1 7.83E-01 Xenon - 135m i Ci i (2) 1 4.18E-01 I (2) l 4.24 E-02 l Xenon - 138 i Ci I (2) I (2) I (2) i 2.93 E-05 Total for Period l Ci i 1.03 E+02 I 8.97E+00 1 4.19E H)1 1 3.41 E+00

2. HALOGENS I I I I l lodine - 131 1 Ci 1 5.6! E-04 l 2.71 E-05 i (1) I (1)

Iodine - 133 i Ci 1 3.39E-04 I 5.53E-05 I (1) 1 (1)

Total For Period I Ci I 9.00E-04 I 8.24E-05 I (1) i (1)

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ATTACIIMENT (1) l CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT TABLE IC - REGULATORY GUIDE 1.21 (Continued) 1997 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES )

I CONTINUOUS MODE I BATCil MODE I I IST I 2ND i IST I 2ND

3. PARTICULATE I UNITS I QUARTER I QUARTER I QUARTER I QUARTER Manganese - 54 i Ci I (2)  ! (2) 1 (1) I (1)

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

Cobalt - 58  ! Ci I (2) i 5.71 E-06 L (1) i- - (1) 'i Cobalt - 60 i Ci I (2) 1 (21 1 (1) I (1)

Zinc - 65 _

. Ci. .f2) , .i , f 2) I (1)  ! (1)

Strontium - 89 I Ci I (2) i (2) I (1) I (1) j Strontium - 90 I Ci I (2) I (2) I (1) I (1) j Molybdenum - 99 I Ci I (2) I (2) I (1) I (1) l Cesium - 134 I Ci I (2) I (2) I (1) (1)

I f

Cesium - 137 i Ci I (2) I (2) I (1) I (1) l Cerium - 141 I Ci I (2) I (2) I (1) i (1) l Cerium - 144 I Ci I (2) I (2) I (1) I (1)

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

Total For Period I Ci I (2) I 5.71 E-06 I (1) ,

(I) ,

l I CONTINUOUS MODE I BATCH MODE I I 3RD I 4TH I 3RD 1 4Til

3. PARTICULATE i UNITS I QUARTER I QUARTER I QUARTER I QUARTER Manganese - 54 I Ci I (2) I (2) I (1) I (1)

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

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

Cobalt - 60 ,

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

Zine - 65 i Ci I (2) I (2) I (1) i (1)

S*rontium - 89 i Ci I (2) I (2) I (1) I (1)

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

Molybdenum - 99 i Ci I (2) I (2) 1 (1) I (1)

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

Cesium - 137 I Ci I (2) I (2) I (1) l (1)

Cerium - 141 l Ci I (2) I (2) I (1) I (1) l Cerium - 144 i Ci I (2) I (2) I (1) I (1)

Gross Alpha Radioactivity l Ci I (2) i (2) I (1) I (1)

Total For Period I Ci I (2) I (2) I (1) I (1)

NOTES TO TABLE 1C (1) Iodines and particulate 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 ODCM Surveillance Requirement 4.11.2.1.2.

12 1

, ATTACHMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2A - REGULATORY GUIDE 1.21 1997 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES IST 2ND l EST. TOTAL A. FISSION AND ACTIVATION PRODUCTS UNITS QUARTER QUARTER I ERROR,%

1. Total Release (not including tritium, gases, alpha) Ci 3.83E-02 1.30E-01 4.00E+01

2. Average diluted concentration during period pCi/ml 3.61E-11 1.51E-10

3. Percent of Technical Specification limit (l) i  % i 1.04 E-01 1 4.55E-01 1

4. Percent of Technical Speducation limit (2) I  % I 5.18E-02 1 2.28 E-01 I

5. Percent of Technical Specification limit (3) I  % i 2.57E-02 1 4.88E-02 i

6. Percent of Technical Specification limit (4)  !  % i 1.29E-02 1 2.44 E-02 i B. TRITIUM I I i i

1. Total Release Ci I 2.90E+02 1 1.52E+02 l 1.00E+01

2. Average diluted concentration l l during period pCi/mi 2.73E-07 l 1.76E-07 1

3. Percent of applicable limit (5) I  % i 9.11E-03 1 5.87E-03 i C. DISSOLVED AND ENTRAINED GASES I I I i

1. Total Release I Ci 1 2.17E-02 1 1.57E-02 1 5.00E+00

2. Average diluted concentration l l during neriod I pCi/ml 2.0(E 11 l , ,1.82E-1l l 3RD l 4Tli EST. TOTAL A. FISSION AND ACTIVATION PRODUCTS UNITS I QUARTER I QUARTER ERROR,% j

1. Total Release (not including l tritium, gases, alpha) Ci 1.10E-01 2.03E-01 1 4.00E+01

2. Average diluted concentration l during period I uCi/mi 9.51E-11 1.70E-10

3. Percent of Technical Specification limit (l) I  % 1 3.39E-01 1 1.49E+00 1

4. Percent of Technical Specification limit (2) i  % i 1.69E-01 1 7.43 E-01 1

5. Percent of Technical Specification limit (3) i  % 1 5.29E-02 1 1.00E-01 1

6. Percent of Technical Specification limit (4) I  % i 2.65E-02 1 5.01 E-02 i B. TRITIUM l I I i

1. Total Release I Ci I 3.14 E+02 1 1.53 E+02 l 1.00E+01

2. Average diluted concentration l l l during period I pCi/mi 2.70E-07 l 1.28E-07 I

3. Percent of applicable limit (5) I  % i 9.01 E-03 1 4.28E-03 I C. DISSOLVED AND ENTRAINED GASES I I I i

1. Total Release I Ci i 2.73E 02  ! 4.57E-02 1 5.00E+00

2. Average diluted concentration during period Ci/ml 2.35E-11 3.84E-11 l

13

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A'ITACHMENT (I)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT l

l TABLE 2A - REGULATORY GUIDE 1.21 (Continued) 1997 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES l IST 2ND l D. GROSS ALPHA RADIOACTIVITY UNITS i QUARTER QUARTER I ERROR,%

1. Total Release i Ci I (6) l (6) i N/A E. VOLUME OF WASTE RELEASED l l (prior to dilution) liters i 1.15E+08 5.07E+07 l 1.30E+00 F. VOLUME OF DILUTION WATER USED l DURING PERIOD liters 1.06E+12 8.63E+11 1 1.64E+01 3RD 4Til D. GROSS ALPHA RADIOACTIVITY UNITS QUARTER QUARTER ERROR,%

1. Total Release i Ci (6) l 4.00E-05 1 4.50E+01 E. VOLUME OF WASTE RELEASED l l l (prior to dilution) I liters 5.02E+07 I 3.59E+07 1 1.00E+00 F. VOLUME OF DILUTION WATER USED l l DURING PERIOD liters 1.16E+12 l 1.19E+12 1 1.60E+01 NOTES TO TABLE 2A (1) Percent ofI.C.3 Quarterly Organ Dose Limit (10 mrem) to maximum exposed organ (2) Percent ofI.C.3 Yearly Organ Dose Limit (20 mrem) to maximum exposet organ (3) Percent ofI.C.3 Quarterly Whole Body Dose Limit (3 mrem)

(4) Percent ofI.C.3 Yearly Whole Body Dose Limit (6 mrem)

(5) Limit used is 3 x 10'3 pCi/ml (6) Less than minimum detectable activity which meets the LLD requirements of ODCM Surveillance Requirement 4.11.1.1.1.

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ATTACHMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2B - REGULATORY GUIDE I.21 FIRST HALF 1997 LIQUID EFFLUENTS l CONTINUOUS MODE BATCH MODE

[ IST 2ND IST 2ND -

NUCLIDES RELEASED Units QUARTER QUARTER QUARTER QUARTER l Beryllium - 7 Ci (1) (1) (1) (1)

Sodium - 22 Ci (1) (1) (1) (1)

Sodium - 24 Ci (1) (1) (1) 2.08E-05 Chromium - 51 Ci (1) (1) 2.35E-03 1.96E-02 Manganese - 5 d,_ Ci (1) (1) 2.61 E-04 5.31 E-04 Iron - $5 Ci (2) (2) 6.33E-03 1.55E-02 l Cobalt - 57 Ci (1) (1) 3.94 E-06 5.62E-05 j Cobalt - 58 Ci (1) (1) 1.91 E-02 4.71 E-02 Iron - 59 Ci (1) (1) 3.65E-04 1.20E-03 Cobalt - 60 Ci (1) (1) 1.27E-03 2.54E-03 Zinc - 65 Ci (1) (1) (1) 8.21 E-05 Strontium - 89 Ci (1) (1) 2.74E-05 (1)

Strontium - 90 Ci (1) (1) (1) 7.19E-06 l Strontium - 92 Ci (1) (1) (1) (1) l Niobium - 95 Ci (1) (1) 1.08E-03 7.27E-03 Zirconium - 95 Ci (1) (1) 8.84E-04 4.74 E-03 Niobium - 97 Ci (1) (1) (1) (1)

Molybdenum - 99 Ci (1) (1) (1) (1) i Ruthenium - 103 Ci (1) (1) (1) 1.06E-04 l Rhodium - 105 Ci (1) (1) (1) (1) )

Silver - 110m Ci (1) (1) 7.57E-04 8.80E-04 Tin - 113 Ci (1) (1) 2.12E-04 5.98E-04 Tin - 117m Ci (1) (1) 1.06E-04 2.46E-04 Antimony - 122 Ci (1) (1) (1) 3.76E-06 Antimony - 124 Ci (1) (1) (1) 4.39E-03 Antimony - 125 Ci (1) (1) 2.87E-03 2.33 E-02 lodine 131 Ci (1) (1) 5.93 E-04 1.08E-04 lodine - 133 Ci (1) (i) 3.25E-05 5.06E-05 lodine - 135 Ci (1) (1) (1) (1)

C<sium - 134 Ci (1) (1) 6.59E-04 5.77E-04 Cesium - 136 Ci (1) (1) (1) 4.82E-06 Cesium - 137 Ci (1) (1) 1.28E-03 8.07E-04 Barium - 140 Ci (1) (1) (1) (1)

Lanthanum - 140 Ci (1) (1) 1.33 E-04 5.16E-06 Cerium - 144 Ci (1) (1) (1) (1)

Europium - 154 Ci (1) (1) (1) (1)

Europium - 155 Ci (1) (1) (1) (1)

Total For Period Ci (1) (1) 3.83 E-02 1.30E-01 15

ATTACHMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2B - REGULATORY GUIDE 1.21 (Continued)

SECOND HALF 1997 LIQUID EFFLUENTS CONTINUOUS MODE BATCII MODE 3RD 4TH 3RD 4Til NUCLIDES RELEASED Units QUARTER QUARTER QUARTER QUARTER Beryllium - 7 Ci (1) (1) 3.58E-04 (1)

Sodium - 22 Ci (1) (1) {l) 1.51 E-04 Sodium - 24 Ci (1) (1) 3.21 E-06 (1)

Chromium - 51 Ci (1) (1) 6.26E-03 2.70E-02 Manganese - 54 Ci (1) (1) 4.08E-01 1.19E-03 fron - 55 Ci (2) (2) 3.3!E-02 7.12E-02 Cobalt - 57 Ci (1) (1) (1) 3.25E-04 Cobalt - 58 Ci (1) (1) 1.50E-02 4.26E-02 fron - 59 Ci (1) (I) 9.33E-05 7.74E-04 Cobalt - 60 Ci (1) (1) 2.28E-03 6.37E-03 Zinc - 65 Ci (1) (1) (1) (1)

Strontium - 89 Ci (1) (1) 1.53E-05 6.40E-05 Strontium - 90 Ci (1) (1) (1) 2.42E-05 Strontium - 92 Ci (1) (1) (1) (1)

Niobium - 95 Ci (1) (1) 5.09E-03 2.21 E-02 Zirconium - 95 Ci (1) (1) 3.92E-03 1.43 E-02 Niobium - 97 Ci (1) (1) (1) 2.10E-06 Molybdenum - 99 Ci (1) (1) 1.14E-05 (1)

Ruthenium - 103 Ci (1) (1) 1.59E-04 5.94 E-04 Rhodium - 105 Ci (1) (1) 2.37E-04 8.67E-04 Silver - 110m Ci (1) (1) 7.77E-04 8.00E-03 <

Tin - 113 Ci (1) (1) (1) 7.88E-04 Tin - 117m Ci (1) (1) (1) (1)

Antimony - 122 Ci (1) (1) __(1) 2.96E-06 Antimony - 124 Ci (1) (1) 3.00E-03 (1)

Antimony - 125 Ci (I) (1) 3.62E-02 1.34 E-03 lodine - 131 Ci (1) (1) 5.38E-04 9.17E-05 lodine - 133 Ci (1) (1) 1.28E-04 3.09E-05 lodine - 135 Ci (1) (1) 2.26E-05 (1) j Cesium - 134 Ci (I) (1) 2.39E-04 4.30E-04 Cesium - 136 Ci (1) (1) 1.05E-05 (1)

Cesium - 137 Ci (1) (1) 3.01 E-04 1.08 E-03 Barium - 140 Ci (1) (1) 1.61 E-05 (1) j Lanthanum - 140 Ci (1) (1) 3.91 E-06 (1) ,

l Cerium - 144 Ci (1) (1) (1) 1.61 E-03 I I Europium - 154 Ci (1) (1) (1) 1.61 E-03 Europium - 155 Ci (1) (1) (1) 4.95E-04 Total For Period Ci (1) (1) 1.10E-01 2.03 E-01 I

16

ATTACHMENT (1) '

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2B - REGULATORY GUIDE 1.21 (Continued) 1997 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE IST 2ND IST 2ND NUCLIDES RELEASED Units QUARTER QUARTER QUARTER QUARTER Xenon - 133 Ci (1) (1) 2.17E-02 1.57E-02 Xenon - 133m Ci (1) (1) 6.04E-05 (1)

Xenon - 135 Ci (1) (1) 1.68E-06 2.83E-06 Total For Period Ci (1) (1) 2.17E-02 1.57E-02 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED Units QUARTER QUARTER QUARTER QUARTER Xenon - 133 Ci (1) (1) 2.72E-02 4.55 E-02 Xenon - 133m Ci (1) (1) (1) 2.72E-04 Xenon - 135 Ci (1) (1) 1.37E-05 5.01 E-06 Total For Period Ci (1) (1) 2.73E-02 4.57E-02 NOTES TO TABLE 2B (1) Less than minimum detectable activity which meets the LLD requirements of ODCM Surveillance Requirement 4.11.1.1.1.

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

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ATTACIIMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT

. TABLE 3A- REGULATORY GUIDE 1.21 1997 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOI ID WASTE SHIPPED OFF SITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 12-MONTH EST. TOTAL

1. Type of Waste UNITS PERIOD ERROR %

a. Dewatered spent resin m3 1.70E+01 Ci 1.16E402 12.00E+01

b. Dry Compressible Waste (Shipped) m3 1.93 E+02 Contaminated Equipment, etc. Ci 4.60E-01 i5.00E+01 b.* Dry Compressible Waste (Buried) m3 3.40E+01 Contaminated Equipment, etc. Ci 2.76E-01 i5.00E+01

c. Irradiated Components, m3 0.00E+00 Control Rods, etc. Ci 0.00E+00 N/A

d. Other (Cartridge Filters) m3 3.40E+00 Ci 1.86E+01 15.00E+01 (b.) Volume shipped represents waste generated prior to offsite volume reduction.

(b.') Represents waste buried after volume reduction at offsite processor.

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

a. Mn-54 1.80E+01%

Fe-55 1.00E+00%

Co-58 1.83E+01%

Co-60 6.10E+00%

Ni-63 8.20E+00%

Sr-90 1.23E+00%

Cs-134 2.03E+01%

Cs-137 3.82E+01%

b. H-3 1.84E+00%

C-14 1.52E+00%

Cr-51 8.75E+00%

Fe-55 2.27E+01%

Co-58 1.40E+01%

Co-60 2.29E+00%

Ni-63 1.58E+00% <

Nb-95 1.71E+00%

Zr-95 1.33E+00% I Cs-134 1.32E+01% I Cs-137 2.96E+01%

Ce-144 1.16E+00% j

c. N/A 18 L________________-____-__ _ _ - . --. i

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ATTACHMENT (1)

CALVERT CLIFFS NUCLEAR POWER PLANT RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 3A - REGULATORY GUIDE 1.21 (Continued) 1997 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

d. C-14 4.50E+00%

Fe-55 7.19E+01%

Co-58 1.50E+00%

Co-60 4.80E+00%

Ni-63 7.84E+00%

Nb-95 6.70E+00%

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

Barnwell, SC 3 Motor Surface Transit Scientific Ecology Group Oak Ridge, TN 6 Motor Surface Transit Manufacturing Sciences Corp.

Oak Ridge, TN 3 Motor Surface Transit Frank W. Hake Associates,Inc.

l Memphis, TN 4 Motor Surface Transit US Ecology, Inc.

Oak Ridge, TN

! 2 Motor Surface Transit DSSI, Inc.

l Kingston, TN 19

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APPENDIX (A) i i

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WASTE SHIPMENTS FOR 1997 l l

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Calvert Cliffs Nuclear Power Plant - Units 1 & 2 Independent Spent Fuel Storage Installation August 11,1998

APPENDIX (A)

CALVERT CLIFFS NUCLEAR POWER PLANT WASTE SHIPMENTS FOR 1997 TYPE WASTE: DAW 10 CFR PART 61 WASTE CLASS: A SOURCE OF WASTE: Radiologically Controlled Areas SHIPPING CONTAINER: 20' Sealand Containers, B-25 Metal Boxes, and 55 Gallon Drums TOTAL CURIE QUANTITY: 0.276 Ci IIOW DETERMINED: Dose to curie content, conversion by volume based on generic distribution and scaling factors TOTAL SIIIPPED WASTE VOLUME: 6,824.5 ft' TOTAL BURIAL WASTE VOLUME: 1,202.7 ft' IIOW DETERMINED: Container volume and number of containers shipped, Burial volume is determined from information provided by volume reduction processor.

SOLIDIFICATION AGENT OR ABSORBENT: None i

i A1

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, APPENDIX (A)

CALVERT CLIFFS NUCLEAR POWER PLANT WASTE SHIPMENTS FOR 1997 TYPE WASTE: Dewatered Resin 10 CFR PART 61 WASTE CLASS: A(S), and B SOURCE OF WASTE: Liquid Waste Processing Systems SHIPPING CONTAINER: High Integrity L-8-120 Liner (120.3)

TOTAL CURIE QUANTITY: 115.9 Ci HOW DETERMINED: Gamma scan analysis using resin sample, conversion by weight based on radionuclides distribution and scaling factors TOTAL SIIIPPED WASTE VOLUME: 601.5 fl 3 TOTAL B'JRIAL WASTE VOLUME: 601.5 fl' HOW DETERMINED: Container volume and number of containers shipped SOLIDIFICATION AGENT OR ABSORBENT: None A-2

I

, APPENDIX (A)

CALVERT CLIFFS NUCLEAR POWER PLANT l WASTE SHIPMENTS FOR 1997 '

TYPE WASTE: Cartridge Filters 10 CFR PART 61 WASTE CLASS: C SOURCE OF WASTE: Liquid Waste Processing Systems SHIPPING CONTAINER: High Integrity L-8-120 Liner (120.3) l TOTAL CURIE QUANTITY: 18.6 IIOW DETERMINED: Dose to curie content, conversion by weight based on generic distribution and scaling factors TOTAL SHIPPED WASTE VOLUME: 120.3 ft' I

TOTAL BURIAL WASTE VOLUME: 120.3 ft' HOW DETERMINED: Container volume and number of containers shipped I 1

SOLID.!FICATION AGENT OR ABSORBENT: None i

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