ML20059D117

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Effluent & Waste Disposal Semiannual Rept for First & Second Quarters 1990
ML20059D117
Person / Time
Site: Yankee Rowe
Issue date: 06/30/1990
From: Papanic G
YANKEE ATOMIC ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYR-90-119, NUDOCS 9009060099
Download: ML20059D117 (23)
v • d • e


Text

l

.s YANKEEATOMIC ELECTRIC COMPANY

"'Cl*l'.g*g%'*;*l"

.p.

580 Main Street, Bolton, Massachusetts 01740-1398

w. -

l August 29, 1990 BYR 90-119 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

References:

(a) License No. DPR-3 (Docket No. 50-29)

Subject:

Semiannual Effluent Release Report

Dear Sir:

. Enclosed are the tables summarizing the quantities of' radioactive liquid and gaseous effluents, and solid waste released from Yankee Nuclear Power Station at Rowe, Massachusetts for the first and second quarters of'1990.

This information is submitted in accordance with Technical Specification 6.9.6.b.

We trust that this information is satisfactory; however, should you have any questions, please contact us.

Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY Georg.Papanic, J.

Senior Project Engineer - Licensing GP/tlp/WPP72/96 Enclosures cc: USNRC Region I USNRC Resident Inspector, YNPS 9009060099 900630 PDR ADOCK 05000029 R

PDC

.EE lfy m

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e EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FOR' i

FIRST AND SECOND QUARTERS 1990 i

P Yankee Atomic Electric Company Rowe, Massachusetts WPP12/32

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LIST OF TABTIR AND APPENDICES Title East 1A Gaseous Effluents - Summation Of All Releases 1

1B Gaseous Effluents - Elevated Releases.

2 10 Gaseous Effluents - Routine Ground Level Releases 3-2A Liquid Effluents - Summation Of All Releases 4

2B Liquid Effluents - Routine Releases 5

3 Solid Waste and Irradiated Fuel Shipments 6

i APPENDIX A Radioactive Liquid Effluent Monitoring Instrumentation A-1 APPENDIX B Radioactive Gaseous Effluent Monitoring Instrumentation B-1 APPENDIX C Liquid Holdup Tanks C-1 APPENDIX D Radiological Environmental Monitoring Program D-1 APPENDIX E Land Use Census E-1 APPENDIX F Process Control Program F-1 APPENDIX G Off-Site Dose Calculation Manual G-1 APPENDIX H Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems H-1 APPENDIX I Supplemental Information I-1 APPENDIX J Sewage Sludge Disposal J-1 l

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t TABLE 1A Yankee Atomic Electric Company. Rowe. Massachusetts Effluent and Waste Dis _osal Semiannumi Report n

First.and Second Ouarters 191Q-Gaseous Effluents - So=== tion of All Releasg1 l

l Unit Quarter Quarter.

Est. Total 1

2 Error. 1 l

A. Fission and Activation Gases

1. Total release C1 4.35E+01 5.37E+01 15.50E+01
2. Average release rate for oeriod uC1/sec 5.53E+00 6.83E+00
3. Percent of Tech. Soec. limit (1) 2.60E-01 1.14E+00 B. Iodines
1. Total Iodine-131 Ci

<4.70E-07 2.40E-05 12.50E+01

2. Averare release rate for oeriod uCi/see

<5.98E-08 3.05E-06 l

3. Percent of Tech. Soec. limit (2) 5.18E-01 5.86E-01 C. Particulates
1. Particulates with T-1/2 > 8 days 01 1.59E-06 2.02E-06 13.00E+01
2. Averare release rate for oeriod uci/see 2.02E-07 2.57E-07
3. Percent of Tech. Spec. limit 1

(3)

(3)

4. Gross alpha radioactivity Ci

.<5.08E-08

<5.44E-08 D. Tritium

1. Total release Ci 1.16E+00 8.27E-01 13.00E+01
2. Averare release rate for oeriod uC1/see 1.48E-01 1.05E-01
3. Percent of Tech. Spec. limit (3)

-(3},__

(1) Technical Specification 3.11.2.2.a for ganma air dose. Percent values for Technical Specification 3.11.2.2.b for beta air dose are approximately the same.

(2) Technical Specification 3.11.2.3.a for dose from I-131, tritium, and radionuclides in particulate form.

(3) Per Technical Specification 3.11.2.3, dose contribution from tritium and particulates are included with I-131 above in Part B. WPP12/32

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TABLE IB Yankee Atsmic Electric Company. Rowe. Massachusetts Effluent and Waste Discosal Semlannual Report First and Second Ouarters 1990 GARAQue Effluents - Elevated Relente Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 1

2 1*

2 4

1. Fission Gases Krvoton-85 C1 1.26E-02 1.31E-02 2.09E+00 Krypton-85m 01 4.02E-01 4.62E-01 1.76E-02 Krypton-87 Ci 4.76E-01 5.82E-01 1.08E-04 Krypton-88 01 8.46E-01
9. 91 E -01 8.88E-03 Xenon-133 C1 1.42E+01 1.08E+01 9.88E+00 Xenon-135 Ci 9.75E+00 9.75E+00 5.58E-01 Xenon-135m Ci 1.70E+01 1.61E+01

<2.75E-01 Xenon-138 C1 4.90E-01 7.86E-01 (6.23E-02 Xenon-133m C1 1.14E-02 2.27E-01 1.48E-01 Argon-37

.Ci 2.45E-02 2.28E-02 4.32E-03 Argon-41' Ci

'2.21E-01 2.31E-01 6.72E-03 Carbon-14 Ci 2.52E-03~

2.63E-03 6.56E-01 Xenon-131m Ci 4.47E-02 3.40E-02 1.79E-01 Unidentified Ci

__ Total for oeriod Ci 4.35E+01 4.01E+01 1.36E+01

2. Iodines Iodine-131 Ci

<4.70E-07 1.77E-07 2.38E-05 i

Iodine-133 Ci (5.43E-07 8.55E-08 1.13E-05 Iodine-135 Ci

<1.19E-07

<1.71E-08 7.79E-02_

Total for oeriod Ci

<1.13E-06 2.63E-07 3.59E-05

3. Particulates Strontium-89 C1

<1.06E-06

<3.07E-07

<4.70E-08 Strontium-90 C1

<3.18E-07

<9.79E-08

<1.51E-08 Cesium-134 C1

<2.31E-07

<3.53E-07

<5.50E-08 Cesium-137 __

C1 2.16E-07 1.15E-07

,1.80E-0E Barium-Lanthanum-140 Ci (7.22E-07 (9.53E-07

<1.47E-07 l

Zine-65 Ci

<5.60E-07 (9.18E-07

<1.42E-07 Cobalt-58 Ci

<2.36E-07

<6.90E-07

<1.07E-07 Cobalt-60 C1 1.37E-06 1.44E-06 2.20E-07 Iron-59 Ci

<5.13E-07

<9.61E-07

<1.49E-07 Chromium-51 Ci

<1.50E-06

<2.02E-06

<3.10E-07 Zirconium-Niobium-95 Ci

<3.96E-07 (5.36E-07

<8.30E-08 Cerium-141 Ci

<1.97E-07

<2.62E-07

<4.00E-08 Cerium-144 C1

<8.68E-07

<1.15E-06

<1.80E-07 Antimony-124 Ci (2.18E-07

<2.80E-07

<4.30E-08 Manganese-54 Ci (2.47E-07 1.97E-07 3.00E-08 Silver-110m Ci

<2.27E-07 (4.56E-07

<7.10E-08_

_ 1.68E-06

<1.44E-06

<2.20E-07 Molybdenum-99 Ci Ruthenium-103 C1

<1.98E-07

<2.52E-07

<3.90E-08 Total for oeriod C1 1.59E-06 1.75E-06 2.70E-07

  • There were no batch mode releases during this reporting period.

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TABLE IC l

Yankee Atomic Electric Company. Rowe. Massachusetts Effluent and Waste Disposal Samiannumi Report First_and Second Ouarters 1990 Caseous Effluents - Ground Level Relemmes There were no routine measured ground level continuous or batch mode gaseous releases during the first or second quarters of 1990.

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TABLE 2A t

j Iankee Atomic Eltgtric Company. Rowe. Massachutt111 Effluent and Waste Disposal Semi &nnual Report First and Second Ouarters 1990 l

Lipuid Effluents - Summation of All Releases

,_ Unit Quarter Quarter Est. Total 1

2 Error. %

A. Fission and Activation Products

1. Total release (not including tritium, gases, alpha)

Ci 2.56E-02 1.90E-02 12.00E+01

2. Average diluted concentration during perind uC1/mi 3.91E-10 3.03E-10

___3. Pettent of applicable limit (1) 1 1.13E-04 7.14E-05 B. Tritium

1. Total release ci 1.03E+02 5.41E+01 11.00E+01
2. Average diluted concentration durine period uC1/mi 1.57E-06 8.63E-07
3. Percent of applicable limit (1) 5.24E-02 2.88E-02 C. Dissolved and Entrained Gases
1. Total release ci 1.04E-01 4.05E-02 12.00E+01
2. Average diluted concentration datinEJAeriod uCi/mi 1.59E-09 6.46E-10
3. Percent of applienble limit (2) 7.95E-04 3.23E-04 D. Gross Alpha Radioactivity
1. Total. release C1 1.60E-07

<2.81E-06 13.50E+01 E. Volume of waste released (prior to dilution) liters 6.06E+06 6.35E+06 13.00E+01 F. Volume of dilution water used during period liters 6.55E+10 6.27E+10 17.00E+00 (1) Concentration limits specified in 10CFR20, Appendix B, Table II, Column 2 (Technical Specification 3.11.1.1).

The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit.

l (2) Concentration limits for dissolved and entrained noble gases is 2.00E-04 uCi/ml l

(Technical Specification 3.11.1).

The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did l

any release exceed the concentration limit.

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TABLE 2B lankee Atomic Electric Company. Rowe. Massachusetts Ef fluent _ and Waste Disposal Semiannual Report Eirst and Second Ouarters 191Q Licuid Effluent 1 Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 1

2 1

2

_ Strontium-89 Ci (2.37E-04 (1.62E-04

<1.87E-05

<1.38E-05

_ Strontium-90 Ci (6.52E-05

<6.83E-05

<6.00E-06

<1.00E-06

_ Cesium-134 Ci fl.88E-05 2.3BE-05 6.97E-05 5.03E-05

_C111un-117 Ci

<2.00E-05 7.83E-06 8.01E-07

[Cnhnit-58 Ci

<1.99E-05

<2.09E-05 (7.72E-06 (5.17E-06

_Cohnit-60 Ci 8.75E-07 2.07E-06 3.58E-05 1.96E-05 Iron-59 Ci

<4 11E-05

<4.21E-05

<1.51E-05

<1.07E-05 2

Zine-65 Ci (4.36E-05 (4.51E-05

<1.71E-05

<1.28E-05

_Mangangse-54 Ci

<1.93E-05

<2.13E-05

<B.43E-06

<5.65E-06 Chromium-51 Ci

<1.4BE-04

<1.5BE-04

<7.26E-05 (5.28E-05

~

_ Zirconium-Nio'bium-95 Ci

<3.44E-05

<3.60E-05

<1.27E-05

<9.17E-06

_Molyhdenum-99 Ci (1.44E-04

<1.52E-04

<$.40E-05

<4.04E-05

_Itthngtium-99m Ci

<1.67E-05

<1.77E-05

<1.11E-05

<6.23E-06

_ Barium-Lanthanum-140 Ci (6.54E-05 (7.04E-05 (3.10E-05

<2.27E-05 Cerium-141 Ci

<2.64E-05 (2.80E-05 (1.76E-05

<1.06E-05

.. Rut henium-103 Ci

<1.84E-05 (2.04E-05 (9.08E-06

<6.43E _ Cerium-144 Ci (1.19E-04

<1.26E-04 (8.26E-05 1.63E-06 Indine-133 Ci (1.89E-05 (2.06E-05

<9.31E-06 (6.69E-0&_

E111Dium-75 Ci

<2.11E-05

<2.2BE-05

<1.10E-05

<7.95E-06 Silvgr-110m Ci

<1.95E-05

<2.11E-05

<9.10E-06

<6.72E-06 Antimonv-124 Ci

<1.79E-05

<2.00E-05 1.52E-06

<9.33E-06

_ Carbon-14 Ci 2.40E-02 1.87E-02 Iron-55 Ci

<2.02E-03

<1.66E-03 1.38E-03

<1.57E-04

_ Cesium-136 Ci

<1.93E-05

<2.08E-05

<7.86E-06

<5.46E-06 Antimony-125 Ci

<5.26E-05

<5.80E-05

<2.78E-05

<2.12E-05,

_ Unidentified C1

_Iotal.for period (above) C1 8.98E-06 1.02E-04 2.56E-02 1.89E-02

_Kenon-133 Ci 9.34E-05

<7.12E-05 8.97E-02 3.32E-02

_Kinon-135 Ci

<1.63E-05

<1.59E-05 5.03E-04 5.60E-05

_ Xenon-131m Ci

<6.67E-04 (7.09E-04 1.02E-03 5.36E-04 Xenon-133m Ci

<1.26E-04

<1,17E-04 7.14E-04 2.17E-04 Krypton-85 01 (6.51E-03

<6.84E-03 1.23E-02 6.53E-03 I WPP12/32 I

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TABLI 3 lanhte Atomic Electric Company. Rewe. Massachusetts Efflugnt and Wagig_Digposal Semiannual Report First and Second Ouatlers 1990 Sqlid_ Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)

Unit 6-Month Est. Total Period Error. 1

1. Type of Waste 3

a.

Evaporator bottoms *, Class A waste, m

LSA containers. 55-malion dritma 01 b.

Dry compressible waste, contaminated m#

Ci equipmgnt, etc., Class A waste, LSA, 105-ft boxes I

c.

Irradiated components, control rods, m

6.80E+00 3

C1

1. 6 '.E+0 2 5.00E+01 dewateredspentregin,ClassCwaste, polx_Hla._120.3 ft
2. Estimate of Major Nuclide Composition (By Type of Waste)**

1 c.

Cc.gium-137 6.27E+01%_

CREium-134 1.42E+011 Iron-55 9.22E+001_

Nickel-63 5.48E400%

Cobnit-60 5.40E+001_

Strontiun-10 1.59E+00%

Plutonium-241 1.99E-01%_

Carbon-14 1.72E-011

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 2

Truck Barnwell, SO B. Irradiated Fuel Shipments (Disposition): None

  • Solidification agent is cement.
    • Excluding radionuclides with half-lives less than 12.8 days. WPP12/32

APPENDIX A Radioactive Liquid Effluent Monitorina Instrumentation E quirement: Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification 3.3.3.6.

With less than the minimum number of channels operable and reasonable ef forts to return the instrument (s) to operable status within 30 days being unsuccessful Technical Specification 3.3.3.6.b requires an explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Report.

Resp.onant Since the requirements of Technical Specification 3.3.3.6 governing the operability of radioactive liquid ef fluent monitoring instrumentation were met for this reporting period, no response is required.

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APPENDIX _B Radioactive Caneous l'.f fluent Monitorine Instrumentation Requirement:

Radioactive gaseros effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specificatiot 3.3.3.7.

With less than the minimum number of channels :p; table and reasonable efforts to return the instrument (s) to operable status within 30 days being unsuccessful, Technical Specification 3.3.3.7.b requires an explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Report.

Resnonte Since the requirements of Technical Specification 3.3.3.7 governing the operability of radioactive gaseous ef fluent monitoring instrumentation were met for this reporting period, no response is required.

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APPENplX C i

Liould Holdno Tanka Erguirement Technical Specification 3.11.1.4 limits the quantity of radioactive material contained in any outside temporary tank.

With the quantity of radioactive material in any outside 1

temporary tank exceeding the limits of Technical Specification s 3.11.1.4, a description of the events leading to this condition is required in the next Semiannual Effluent Release Report.

Ensponse The limits of Technical Specification 3.11.1.4 were not exceeded during this reporting period.-

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APPENDIX D J

Radiological Environmental Monitorinn Program

]

l Es.guiremenk t The radiological environmental monitoring program is conducted in accordance with Technical Specification 3.4.12.1.

With milk or fresh leafy vegetation samples no longer available from one

[

t or more of the required sample locations, Technical

{

Specification 3.4.12.1.c requires the identification of the new.

location (s) for obtaining replacement sample (s) ir. the next Semiannus'. Effluent Release Report and inclusion of revised Off-Site Dose Calculation Manual figure (s) and table (s) reflecting the new location (s).

Respongs:

No milk or fresh leafy vegetation samples were found to be unavailable during this reporting period.

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APPtyDig_g Land Utt_Ctatua Requirrmen11 A land use census is conducted in accordance with Technical l

Specification 3.12.2.

With a land use census identifying a location (s) which yields at least a 20 percent greater dose or dose commitment than the values currently being calculated in Technical Specification 4.11.2.3 Technical Specification 3.12.2.a requires the identification of the new location (s) in the next Semiannual Effluent Release Report.

Reap.Qngs:

The Innd use census was not completed during this reporting period.

Requirmment: With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) at least 20 percent greater than at a location from which samples are currently being obtained in accordance with Technical Specification 3.12.1. Technical Specification 3.12.2.b requires that the location (s) be added to the program if permission f0om the owner to collect samples can be obtained and if sufficient sample volume is available. The identificatien of the new location (s) is required in the next Semiannual Ef fluent Release Report.

Reap.nnas The land use census was not completed during this reporting period.

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APPENDIX.T l

i Procean control Pronram I

t he.guirement: Technical Specification 6.14.1 requires that licensee initiated j

changes to the Process Control Program be submitted to the Connission in the Sealannual Effluent Release Report for the period in which the change (s) was made.

}

Resp 9nant There was no licensee initiated change (s) to the Process Control i

Program during this reporting period.

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APPENDIX C Off-Site Dose Calculation Manual j

Rtquirammat Technical Specification 6.15.2 requires that licensee initiated changes to the Off-Site Dose Calculation Manual (ODCM) be i

submitted to the Commission in the Semiannual Effluent Release Report for the period in which the change (s) was made effective.

t Res p.nnan t Appendix A, which contains the commitments for the disposal of septage as provided by the Application for Approval to Routinely Dispose of Septage under 100FR20.302 and the NRC acceptance it.ter of May 17, 1990, was added to the ODCM.

The addition of

l Appendix A is required to be permanently incorporated into the ODCM and does not reduce the accuracy or reliability of dose calculations or setpoint determinations.

The change was j

reviewed and found acceptable by the Plant Operation Review Committee (PORC) on May 21, 1990 (PORC Meeting 90-44).

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APPENDIX H 4

e Radioactive Liould. Gaseous. and Solid Waste Treatment Systems Requirenteat t Technical Specification 6.16.1 requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the Semiannual

)

Effluent Release Report for the period in which the evaluation i

was reviewed by the Plant Operation Review Committee.

Raanoma.c There were no licensee initiated major changes:to the radioactive waste systems (liquid, gaseous, and solid) during I

this reporting period.

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WPP12/32

I AEPENDIX 1 Suo_olemental Information First and Second Ouarters 1990 i

1.

Technical Speelfication Limits - Dome and Dose Rate Technical Sptsjfication and Catenory Limit a.

Hpble Cases 3.11.2.1 Total body dose rate 500 mrem /yr 3.11.2.1 Skin dose rate 3000 mrem /yr 3.11.2.2 Gamma air dose 5 mrad in a quarter 3.11.2.2 Gamma air dose 10 mrad in a year 3.11.2.2 Beta air dose 10 mrad in a quarter 3.11.2.2 Beta air dose 20 mrad in a year b.

Iodine-131. Tritium. and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days 3.11.2.1 Organ dose rate 1500 mrem /yr 3.11.2.3 Organ dose 7.5 mrem in a quarter i

3.11.2.3 Organ dose 15 mrem in a year

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Liquids 3.11.1.2 Total body dose 1.5 mrem in a quarter 3.11.1.2 Total body dose 3 mrom in a year 3.11.1.2 Organ dose 5 mrem in a quarter 3.11.1.2 Organ dose 10 mrem in a year 1

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_ Technical Specification Limits - Concentration Technical Soecification and Category Limil i

l a.

Noble Catgg No MPC limits b.

ladine-131. Tritium. and Radionuclides No MPC limits in Particulate Form With Half-Lives Greater Than__8 Day.a i

c.

Liquida 3.11.1.1 Total sum of the fraction of MFC (10CFR20,, Appendix B, Table II, Column 2), excluding noble gases less thant 1.0 3.11.1.1 Total noble gas concentration 2.00E-Oh uC1/cc 3.

diaturements and Approximations of Total Radfoactivity a.

NakLt_GAtta Continuous discharges are determined by indirect measurement.

Primary gas samples are taken periodically and analyzed.

It is assumed that in primary to secondary leakage all gases are ejected through the air ejector.

In primary coolant charging pump leakage all gases are ejected to the primary vent stack either during flashing or liquid waste processing. Batch discharges are determined by direct measurement.

Errors associated with these measurements are estimated to be 155 percent.

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1 Do 12db1LE Iodines are continuously monitored by drawing a sample from the j

primary vent stack through a particulate filter and charcoal cartridge.

The filter and charcoal cartridge are removed and analyzed weekly. The errors associated with these measurements are estimated to be 125 percent.

c.

Particulatta The particulate filter described in (b) above is analyzed weekly.

The errors associated with the determination of particulate effluents are estimated to be 130 percent.

d.

Liquid Efflutata Liquid effluents are determined by direct measurement.

In line composite samples are analyzed for strontium-89, strontium-90, iron-55, gross alpha activity, and carbon-14. There is no compositing of samples for tritium or dissolved fission gas analysis.

For continuous discharges composite samples are used for gamma isotopic analysis. A gamma isotopic analysis is performed on a representative sample for each batch release using the Marinelli Beaker geometry.

The errors associated with these meas;eements are as follows:

fission and activation products, 120 percent; t c4. tium,

A10 percent; dissolvec fission gases, 120 percent; alpha acoivi$y, 235 percent.

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e 4.

hatch Releasta a.

Liquids l-The batch release data is presented in two categories in order to ptovide accurate average discharge rate values.

Outdoor Routine Tank Batches Monts Firct Oggrigt Number of batch releases:

19 4

Total time period for batch releases (minutes):

5480 6260 Maximum time period for a batch release (minutes):

340 1770 Average time period for batch releases (minutes):

288 1565 Minimum time period for a batch release (minutes):

235 1210 i

Average stream flow (Sherman Dam) during period (cts):

832 832 Average discharge rate (gpm):

24.3 6.1 Outdoor Routine Tank Second Ouarter Batches Monts Number of batch releases:

15 2

Total time period for batch releases (minutes):

3977 5882 Maximum time period for a batch relecse (minutes):

310 3942 Average time period for batr8 releases (minutes):

265 2941 Minimum time period for a batch release (minutes):

240 1940 Average stream flow (Sherman Dam) during period (cfs):

689 689 Average discharge rate (gpm):

26.6 3,4 b.

Ganga First Dunrter There were no batch gaseous releases during this reporting period.

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$gggnd Guarter Number of batch releases: 5 i

Total time period for batch releases (minutes):

987 Maximwn time period for a batch release (minutes):

375 Average time period for batch releases (minutes):

197 Minimum time period for a batch release (minutes):

45 5.

Abnormal RelRREta Technical Specification 6.9.5.b requires the reporting of any unplanned releases from the site to the site boundary of radioactive material in gaseous and liquid effluents made during the reporting period.

a.

Liquid There were no nonroutine liquid releases during the reporting period, b.

Gases There were no nonroutine gaseous releases during the reporting period.

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WPP12/32

l APPENDIX J Sewame Sludre Dispugl Erguirementt For periods in which disposal of septage occurs, the licensee shall report in the Semiannual Effluent Release Report, the volume, liquid, and solid mass fractions, radionuclide concentrations in the liquid and solid fractions, and the total activity disposed.

Response

The following information is provided for the disposal of sewage sludge during the reporting periodt Volume Discharged (gallons):

7000 Liquid Fraction of Waste 9.24E-01 Solid Fraction of Wastet 7.58E-02 Nuclide Content in Liquid Fraction (uci/g):

ND*

Nuclide Content in Solid Fraction (uci/g): Cesium-137, 1.28E-07 Cobalt-60, 6.33E-07 Total Activity Discharged (uci):

Cesium-137, 2.57E-01 Cobalt-60, 1.27E+00 TOTAL 1.53E+00 i

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  • ND = Not Detectable J-1 WPP12/32

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