ML20012A200

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Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters 1989
ML20012A200
Person / Time
Site: Yankee Rowe
Issue date: 12/31/1989
From: Papanic G
YANKEE ATOMIC ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYR-90-021, BYR-90-21, NUDOCS 9003080494
Download: ML20012A200 (21)
v • d • e


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YANKEEATOMICELECTRIC COMPANY

"'6"?0,?lg'@,"l" i.'

Yd'ume 580 Main Street, Bolton, Massachusetts 01.'10-1398 t

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f February 28, 1990 BYR 90-021 i

United States Nuclear Regulatory Commission Document Control Desk L

Washington, DC 20555

Reference:

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

Subject:

Semiannual Effluent Release Report

Dear Sir:

I Enclosed please find the tables summarizing the quantities of radioactive liquid and gaseous effluents and solid waste released from the Yankee plant at

.Rowe, Massachusetts for the third and fourth quarters of 1989 submitted in 7

accordance with Technical Specification 6.9.5.b.1.

The summary of the estimates of off-site radiation doses resulting from plant effluents during 1989.will be provided in a supplemental report in accordance with Technical Specification 6.9.5.b 2.

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. We trust that this information is satisfactory; however, should you have l

any questions, please contact us.

Very truly yours, 1

l YANKEE ATOMIC ELECTRIC COMPANY l

Ge rge apanic, J

('

Senior Project Engineer Licensing GP/b11/WPP77/12 Enclosures cc: USNRC Region I USNRC Resident Inspector, YNPS l

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FOR THIRD AND FOURTH QUARTERS 1989 Yankee Atomic Electric Company Rowe, Massachusetts 8334R'

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s' TABLE 1A a

IAnkt.R At.omic Electric Company. Rowe. Massachusetts Effluent and Warte Disposal Semiannual Report Third and Fourth Ouarters 1989 Caseous Effluents - So---tion of All Releasts

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1 Unit Quarter Quarter Est. Total 3

4 Error. %

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A. Fission and Activation Gases i

1. Total release C1 4.31E+01 4.79E+01 5.50E+01
2. Average release rate for period _

uC1/sec 5.48E+00 6.09E+00-

3. Percent of Tech. Spec. limit (1) 3.76E-01 5. 5 2E-01_ _

B. Iodines

1. Total Iodine-131 Ci 8.56E-05 1.29E-06 2.50E+01
2. Average release rate for period uCi/see 1.09E-05 1.64E-07

___ 3. Percent of Tech. Soec. limit (2) 1 1.01E+00 2.53E-01 C. Particulates

1. Particulates with T-1/2 > 8 dava C1 5.93E-06 4.62E-05 23.00E+01
2. Average release rate for period uCi/sec 7.54E-07 5.8&E-Q4_
3. Percent of Tech. Spec. limit 1

(3)

(3)

4. Gross alpha radioactivity Ci 3.26E-08 (6.51E-08 3

D. Tritium

1. Total release ci 1.78E+00 1.13E+00 r3.00E+01
2. Average release rate for period uC1/see 2.26E-01 1.44E-01
1. Percent of Tech. Spee. limit (3)

(3)

(1) Technical Specification 3.11.2.2.a for gamma 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 i

radionuclides in particulste form.

I (3) Per Technical Specification 3.11.2.3, dose contribution from tritium and g

particulates are included with I-131 above in Part B.

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ei TABLE IB Yankee Atomic Electric Comoany. Rows. Massachusetts Effluent and Waste Disposal Samiannuni Report Third and Fourth Ounrters 1989 Gaseous Effluents - Elevated Release Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter

  • 3 4

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1. Fistion Gases Krypton-85 Ci 5.82E-03 7.58E-03 1.03E+00 Krvoton-85m C1 3.65E-01 4.98E-01 7.73E-03 i

Krvoton-87 Ci 3.76E-01 5.58E-01 (4.34E-02 Krvoton-88 01 7.13E-01 7.17E-01 5.21E-03

___ Xenon-133 C1 1.09E+01 1.54E+01 1.08E+01

___ Xenon-135 Ci 6.88E+00 1.09E+01 6.64E-01 Xenon-135m Ci 1.00E+01 1.87E+01

<5.12E-01 Xenon-138 Ci 1.71E-01 3.36E-01 (2.22E-01 Xenon-133m C1 1.99E-01 4.04E-01

_2.46E-01

_.... Argon-3 7 Ci 1.34E-02 6.99E-03 1.21E-01 Arron-41 Ci 2.67E-01 2.76E-01 6.63E-03 Carbon-14 C1 1.16E-03 1.52E-03 2.03E-01 Xenon-131m Ci 3.43E-02 4.85E-02 9.00E-02 Unidentified C1 Total for period C1 2.99E+01 4.79E+01 1.32E+01

2. Iodines Iodine-131 C1 4.2BE-05 1.29E-06 4.28E-05 Iodine-133 C1 4.1QE-06

<6.30E-07 4.10E-06 Iodine-135 C1 3.15E-07 (5.03E-07 3.15E-07 Total for oeriod Ci 4.72E-05 1.29E-06 4.72E-05 32_tatticulates Strontium-89 C1 (5.05E-07

<3.54E-07 (5.05E-07 Strontium-90 Ci (1.14E-07 (1.37E-07 cl.14E-07 Cesium-134 Ci

<3.03E-07 (2.96E-07

<3.03E-07 Cesium-137 Ci 7.50E-07 2.86E-07 7.50E-07

_._ Barium-Lanthanum-140 C1 4.81E-07

<9.00E-07 4.81E-07 Zinc-65 C1

<6.80E-07 (6.81E-07 (6.80E-07 Cobalt-58 Ci 9.01E-07

<3.08E-07 9.00E-07 Cobalt-60 Ci

3. 4 7 E-06 4.26E-06 3.47E-06 Iron-59 C1

<6.30E-07

<6.12E-07

<6.30E-07 Chromium-51 Ci 9.50E-06 3.01E-07 9.50E-06 Zirconium-Niobium-95 C1 1.11E-06 2.14E-07 1.11E-06 Cerium-141 Ci 1.99E-07 4.93E-08 1.99E-07 Cerium-144 01

<1.05E-06

<1.13E-06

<1.05E-06 Antimony-124 Ci 3.35E-06 2.53E-07 3.35E-06 Mannanese-54 C1 2.13E-06 5.64E-07 2.13E-06 Silver-110m 01 1.25E-07

<2.67E-07 1.26E-07 Molybdenum-99 Ci

<1.92E-06 (2.06E-06

<1.92E-06 Ruthenium-103 Ci 1.11E-06

<2.42E-07 1.10E-06 Total for period C1 2.31E-05 5.93E-06 2.31E-05

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

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e TABLE IC l

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Yankee Atomic Electric Company. Rowe. Massachusetts Efflumnt and Waste Disposal Semiannual Report i

Third and Fourth Ouarters 1989

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Caseous Ef fluents - Ground Level Releases I

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There were no routine measured ground level continuous or batch mode gaseous L

releases during the third or fourth quarters of 1989.

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e table 2A Yankee Atomic Elsi'.c c ContPany. Rohli&Esachusitis Effluent _and E $t.,_DiaggA&1 Semiannual Reparl Third and Fourth Ouarters 1989 L1 Auld Effluents - S - ation of All Releases Unit Quarter Quarter Est. Total 3

4 Error. 1 A. Fission and Activation Products

1. Total release (not including tritium emnes aloha)

C1 1.96E-03 7.23E-03 12.00E+01

2. Average diluted concentration durine period ucl/mi 3.22E-11 1.07E-10
3. Percent of applicable ilmit (1) 3.01E-04 7.04E-05 B. Tritium
1. Total release Ci 5.97E+01 4.27E+01
  • 1.00E+01
2. Average diluted concentration durine ceriod uCi/mi 9.82E-07 6.34E-07
3. Percent of applicable limit (1) 3.27E-02 2.11E-02 C. Dissolved and Entrained Gases
1. Total release ci 2.33E-02 1.47E-02 r2.00E+01
2. Average diluted concentration aurine period uti/mi 3.83E-10 2.18E-10
3. Percent of applicable limit (2) 1.92E-04 1.09E-04 D. Gross Alpha Radioactivity
1. Total release ci

<2.44E-06 (2.69E-06 23.50E+01 E. Volume of waste released (prior to dilution) liters 6.30E+06 5.61E+06 3.00E+01 F. Volume of dilution water used during_ period liters 6.0BE+10 6.74E+10

  • 7.00E+00

'(1) Concentration limits specified in 10CFR, Part 20, 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.

(2) Concentration limits for dissolved and entrained noble gases is 2.00E-04 microcuries/ml (Technical Specification 3.11.1).

Thc 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.

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IABLE 2B.

Yankee. Atomic Electr.'c_. Company.. Rowe, MattachustitA Effluen,t and Waste Disposal Semiannuni Report Third and Fourth Ouarters 1989 Liguid Effluents Continuous Made Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3

4 3

4

<1.07E-05 Strontium-89 C1

<2.25E-04

<1.51E-04 (2.64E-05

_ Strontium-90 Ci

<5.13E-05 (8.08E-05

<9.16E-06 (5.49E-06

_ Cesium-134 C1 1.40E-05

<1.65E-05 5.07E-05 6.30E-05

_ Cesium-137 Ci 4.98F-05 2.64E-06 8.04E-05 1.20E-04

_Loding-131 C1 2.40E:Q5

<1.58E-05 2.55E-05 7.27E-06

[hobalt-58 Ci (2.06E-05

<1.77E-05

<5.97E-06 (4.91E-06

_Cohalt:60 C1 2.85E-06 2.27E-06 2.28E-05 1.46E:QE_

_;(Inn-59 Ci (4.13E-05

<3.61E-05

<1.19E-05

<9.12E-06

_liinc-65 C1 (4.47E-05

<3.72E-05

<1.31E-05

<1.02E-05__

_!1anganese-54 Ci

<2.11E-05

<1.77E-05 1.58E-06 3.10E-06

_ Chromium-51 Ci (1.56E-04

<1.28E-04 (5.57E-05

<4.92E-05

_Xirconium-Niobium-95 Ci

<3.59E-05

<2.95E-05

<1.03E-05 (8.15E-06

_hlol ybdenum-99.

Ci (1.49E-04

<1.22E-04

<4.24E-05

<3.47E-05

_Ierhnetium-99m C1 2.79E-06 1.26E-06 1.84E-07

<5.28E-06_

.Jarium tan thanum-140 Ci

<6.86E-05

<5.75E-05

<2.35E-05

-<2.03E-05

_ Cerium-141 Ci (2.70E-05

<2.32E-05

<9.97E-06

<8.45E-06

~Euthenium-103

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<1.88E-05

<1.58E-05

<6.71E-06

<6.05E-0E_

_ Cerium-144 Ci (1.23E-04

<1.07E-04 (4.61E-05

<3.96E-05

_ lodine-133 Ci

<1.94E-05

<1.64E-05 1.45E-06 5.26E-07

_ Selenium-75 Ci

<2.15E-05

<1.85E-05

<8.04E-06

<7.06E-06.

_S.ilver-110m Ci (1 95E-05

<1.63E-05 (6.66E-06

<5.74E-06 2

Antimonv-124 Ci (1.89E-05

<1.60E-05 9.35E-07 2.76E-06.,

1.69E-03 6.89E-03

_Carbott:14 01 Iron-55 Ci (1.38E-03

<1.62E-03 (1.40E-04 1.23E-04

_Cngfum-136 Ci

<2.07E-05

<1.68E-05

<5.97E-06

<4.85E-06

_Aptimonv-125 Ci

<5.45E-05

<4.65E-05

<2.05E-05

<1.87E-05

_ Unidentified C1

_ Intal for period (above) Ci 9.34E-05 6.17E-06 1.87E-03 7.22E-03 Xenon-133 Ci 2.88E-06 (6.45E-05 1.64E-02 6.46E-03

_Xgnon-135 Ci

<1.57E-05

<1.30E-05 3.22E-05 3.67E-05

_ Xenon-131m 01

<6.78E-04

<5.85E-04 4.29E-04 3.03E _ Xenon-133m Ci

<1.32E-04

<1.10E-04 5.72E-05 1.69E-05 Kryoton-85 Ci (6.69E-03

<5.52E-03 6.39E-03 7.92E-03 8334R

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TABLE 3 g1

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Yankee Atomic Electric Comnanv. Rowe. Massachusetts Effluent _and_Wasig_Disphgal_ Semiannual _ Report Third and Fourth Ouarters 1989 Solid Waste and Igradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)

Unit 6-Month Est. Total Period Error. %

1. Type of Naste a.

Evaporator bottoms *, Claos A waste, m3 3.14E+01 LSA containers. 55-ra11on drums 01 1.34E+00

  • 3.00E+01_

b.

Dry compressible waste, contaminated m3 4.86E+01 equipment, etc., Class A waste, LSA, Ci 6.99E-01 al.00E+02 105-ft3 boxes

2. Estimate of Major Nuclide Composition (By Type of Waste)**

n'. Tritlum 2.97E+01%

~ Nickel-63 1 65EiOO%....

Cesium-137 2.75E+01%

Carbon-14 1.13E-01%

Cesium-134 2.39E+01%

Iron-55 1.53E+011-Cobalt-60 2.06E+00%

Nickel-63 1.23E+00%

Carbon-14 8.40E-02%

b.

Cesium-137 3.74E+01%

Cesium ;].34 '

3,42E+01%

Iron-55 2.17E+01%

Cobalt-60 E.84E+00%

Niobium-95 2.01E+00%

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

5 Truck Barnwell, SC B. Irradiated Fuel Shipments (Disposition): None 1.

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  • Solidification agent is cement.
    • Excluding nuclides with half-lives less than 12.8 days.

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  • p' APPENDIX A

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Radioactive Liquid Effluent MonitorinR_Infinnentation

'Reauirement Radioactive liquid effluent monitoring instrumentation channels ll are required to be operable in accordance with Technical Specification 3.3.3.6.

With less then the minimum number of i

r channels operable and reasonable efforts 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.

Response

Since the. requirements of Technical Specification 3.3.3.6.

governing the operability of radioactive liquid effluent monitoring instrumentation were met for this reporting period,.

4 no response is required.

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'f APPENDIX B

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Radioactive _ Casio.us_FJfluent Monitoring Instrumerttation b

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Requirement
Radioactive gaseous affluent monitoring instrumentation' channels are required to be operable in accordance with Technical Specification 3.3.3.7.

With less than the minimum number of ch'annels operable and reasonable efforts to return the I

-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.

Resp.onant

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

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Aff.ENDIX C Liquid Holdup Tanks i

Requirements Techt ical 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 a;

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

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.Reasonse:

The limits of Technical Specification 3.11.1.4 were not exceeded

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' APPENDIX D p:

Radiological Environmental Monitorine ProgIAE Requirement: The radiological environmental monitoring program is conducted I

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in accordance with Technical Specification 3.4.12.1.

With milk k

or fresh leafy vegetation samples no longer available from one.

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) in the next Sendannual Effluent Release Report and inclusion of! revised Off-Site Dose Calculation Manual figure (s) and table (s) reflecting the new location (s).

Response

All required milk and fresh leafy vegetation samples were available during this reporting period.

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E ', s APPENDIX E Tand Use Cengua Reaufrement: A land use census is conducted in accordance with Technical 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.

Response

The land use census for this reporting period did not identify-

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any locations yielding at least a 20 percent greater dose or dose commitment than the values currently being calculated in Technical Specification 4.11.2.3.

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Requirement: 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 I

which samples are currently being obtained in accordance with

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Technical Specification 3.12.1. Technical Specification 3.12.2.b L

requires that the location (s) be added to the program if p

permission from the owner to collect samples can be obtained and if sufficient sample volume is available. The identification of the new location (s) is required in the next Semiannual Effluent Release Report.

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Response

No changes were made in the Radiological Environmental i

Monitoring Program as a result of the 1989 land use census.

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APPENDIX F Process Control Program Enguirement: Technical Specification 6.14.1 requires that licensee initiated-4 changes to the Process Control Program be' submitted to the Conscission in the Semiannual Radioactive Ef fluent Release Report.

for. the period in which.the change (s) was made.

Response

There was no licensee initiated change (s) to the Process Control Program during this reporting period, s

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APPENDIX G 4

j Off-Site Dose Calculation Manuni Reauirement: Technical Specification 6.15.2 requires that licensee initiated changes to the Off-Site Dose Calculation Manual be submitted to the Commission in the Semiannual Radioactive Effluent Release-Report for the period in which the change (s) was made effective.

Responne:

There were no licensee initiated changes to the Off-Site Dose Calculation Manual during this reporting period.

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APPENDIX H Radioactive Liquid. Caseous. and Solid Waste Treatment Systems

' Requirement Technical Specification 6.16.1 requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, i

and solid) be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the i

evaluation was reviewed by the Plant. Operation Review Committee.'

I Responan:

There were no licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) during this reporting period.

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APPENDIX..I

.,5,

Supplemental Information J

Third and Fourth Ouarters 1989 1.

Technical Specification Limits - Dose and Dose Rate i

Technical Soecification and Category Limit a.

Noble Gases 3.11.2.1 Total body dose rate 500 mrem /yr 3.11.2.1 Skin dose rate 3000 mrem /yr

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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 Part!culate Form With Half-Lives Greater Than 8 Davq t

3.11.2.1 Organ dose rate 1500 mrem /yr 3.11.2.3 Organ dose 7.5 mrem in a quarter 3.11.2.3 Organ dose 15 mrem in a year c.

Liquids 3.11.1.2 Total body dose 1.5 mrem in a quarter

-3.11.1.2 Total. body dose 3 mrem 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 l

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Technical Specification Limits - Concentration i

Technical Specification and Category Limit i

.a.

Noble Cases No MFC limits b.

Iodine-131. Tritium. and Radionuclides No MPC limits in Particulate Form With Half-Lives Greater Than 8 Days I

c.

Liquida i

3.11.1.1 Total sum of the fraction of MPC j

(100FR20, Appendix B, Tables II, l

Column 2), excluding noble gases L

e less than:

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3.11.1.1 Total noble gas concentration 2.00E-04 uCi/cc l

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Measurements and Approximations of Total Radioactivity 1

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Noble Cases i

" Continuous discharges" are determined by indirect measurement.

'i Primary gas samples are taken periodically and analyr.ed.

It is.

l assumed that in primary to secondary leakage all gases are ejected I

through the air ejector.

In primary coolant charging pump leakage all gases are ejected to the primary vent stack either during j

flashing or liquid waste processing.

" Batch discharges" are l

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. determined by direct measurement. Errors associated with these measurements are estimated to be 155 percent.

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b.

Iod'ines Iodines are continuously monitored by drawing a sample f rom the primary vent' stack through a' particulate filter and charcoal

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r cartridge.

The filter and charcoal cartridge are removed and shalyzed weekly.

The errors associated with these measurements are 4

estimated to be A25 percent.

.c.

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

.The errors associated'with the determination of particulate effluents are estimated to be 230 percent.

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Liquid Effluents g

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 Marine 111' i

Beaker geometry.

The errors associated with:these measurements are as follows:

fission and activation products, f20 percent; tritium, 210 percent; dissolved fission gases,'i20 percent; alpha activity, 135 percent.

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' Batch Releaggs-a.

Liquids Third Ouarter Number of batch releases:

23 Total time period for batch releases: 8,007 minutes t

o Maximum time period for a batch release:- 1,195 minutes Average time period for batch releasess. 348 minutes i

r Minimum time period for a batch release: 56 minutes

-Average stream flow during period (Sherman Dam):

523 cfs Average-discharge rate:

19.6 gpm

. Fourth Ounrter Number of. batch releases:

11 Total time period for batch releases:

7,960 minutes Maximum time period for a batch release:

2,970 minutes Average time period for batch releases:

724 minutes Minimum time period for a batch release:

217. minutes Average stream flow during period (Sherman Dam):

765 cfs

. Average discharge rate:

10.5 gpm b.

Gases l

Third Ounrter l

Number of batch releases: 5 Total time period for batch releases:

782 minutes Maximum time period for a batch release:

300 minutes Average time period for batch releases:

156 minutes Minimum time period for a batch release:

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Fourth Ouarter There were no batch gaseous releases during this reporting period.

5.

Abnormal Releases

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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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