ML20153E470

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Effluent & Waste Disposal Semiannual Rept for First & Second Quarters 1988
ML20153E470
Person / Time
Site: Yankee Rowe
Issue date: 06/30/1988
From:
YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML20153E477 List:
References
NUDOCS 8809060329
Download: ML20153E470 (17)
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Text

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EFFLUENT Aht WASTE DISPOSAL SENIANhTAL REPORT FOR FIRST AND SECOND QUARTERS. 1988 Yankee Atomic Electric Company Rowe Massachusetts 4824R/20.124 4I I,

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y TABLE 1A Yankee Atomic Electric Company. Rowe Massachusetts Ef fluent and Waste Disposal Semiannual Report First and Second Quarters, 1988 Gaseous Effluents - Summation of All Releases l'ai t Quarter Quarter Est. Total 1

2 Error. 1 A. Fission and Activation Gases

1. Total release Ci 5.58E+0) 5.79E+01 25.50E+01
2. Averate release rate for period uCi/see 7.10E+00, 7.37E+00
3. Percent of Tech. Spee. limit (1)(4) 5.40E-01 5.94E-01 B. lod.nes
1. Total Iodine-131 Ci 1.12E-06 3.28E-06 22.50E+01
2. Average release ra*.e for period uCi/see 1.42E-07 4.17E-07
3. Percent of Tech. Spec. limit (2)(4) 1 4.01E-01 5.67E-0'.

C. Particulates

1. Particulates with T-1/2 > 8 days Ci 1.56E-06 1.93E-06 e3.00E+01
2. Average release rate for period uCi/see 1.98E-07 2.46E-07
3. Percent of Tech. Spec. limit (3)

(3)

4. Gross alpha radioact!vity

_Ci

<5.40E-08 2.48E-08 D. Tritium

1. Total release Ci 1.37E+00 1.1BE+00 23.00E+01
2. Average release rate for period uCi/see 1.74E-01 1.50E-01
3. Percent of Tech. Spec. 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 approximstely the same.

(2) Technical Specification 3.11.2.3.a for dose f rom I-131. Tritium, and radionuclides in particulate form.

(3) Per Tachnical Specification 3.11.2.3 dose contributions from Tritium and particulates are incluoed with I-131 above in Part B.

(4) The first and second quarter percent of Technical Specification limits are based on coliservative plant quarterly dose determinations.

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TABLE IB Yankee Atomic Electric Comrany. Rowe Massachusetts Effluent and Waste Disposal Semiannual Report First and Second Quarters, 1988 Gaseous Effluents - Elevated Release Continuous Mode Batch Mode (1)

Nuclides-Released Unit Quarter Quarter Quarter Quarter 1

2

1. Fission Gases Krypton-85 Ci 2.96E-02 3.74E-02 Krypton-85m Ci 5.59E-01 6.61E-01 K ypton-87 Ci 5.15E-01 5.58E-01 Krypton-88 Ci 1.02E+00 1.22E+00 Xenon-133 Ci 2.47E+01 2.36E+01 Xenon-135 Ci 1.16E+01 1.30E+01 Xenon-135m Ci 1.61E+01 1.68E+01 Xenon-138 Ci 1.48E-01 3.75E-01 Xenon-123m Ci 4.89E-01 7.25E-01 Argon-37 Ci 4.92E-02 6.01E-02 Argon-41 Ci 2.02E-01 2.68E-01 Carbon-14 Ci 6.10E-03 7.71E-03 Xenon-131m Ci 3.91E-01 5.80E-01 Ci Unidentified Total for period Ci 5.58E+01 5.79E+01
2. Iodines Iodine-131 Ci 1.12E-06 3.28E-06 Iodine-133 Ci 6.30E-07 2.58E-06 Iodine-135 Ci (1.40E-07

<5.70E-07 Total for period Ci 1.75E-06 5.86E-06

3. Particulates Strontium-89 Ci

<7.77E-08

<2.31E-07 Strontium-90 Ci

<1.01E-07

<1.85E-07 Cesium-134 Ci 2.61E-08 (4.32E-07 Cesium-137 Ci 4.13E-07 3.13E-07 Barium-Lanthanum-140 Ci (9.23E-07 (1.29E-06 Zine-65 Ci (7.18E-07

<1.01E-06 Cobalt-58 Ci

<3.02E-07 (4.42E-07 Cobalt-60 Ci 1.09E-06 1.62E-06 Iron-59 Ci (6.76E-07

<9.22E-07 Chromium-51 Ci (1.98E-06

<2.54E-06 Zirconium-Niobium 95 Ci (4.99E-07

<7.33E-07 Cerium-141 Ci (2.60E-07

<3.56E-07 Cerium-144 Ci

<1.14E-06

<1.5CE-06 Antimony-124 Ci

<2.84E-07

< 3. 90E,-0 7 Manganese-54 Ci (3.24E-07 (4.53t-07 Silver-110M Ci (2.84E-07

<3.79E-07 Molybdenum-99 Ci

<2.12E-06 (2.98E_06 Ruthenium-103 Ci (2.58E-07

<3.48E-G.

Total for period Ci 1.53E-06 1.93E-06 (1) There were no batch mode releases during this reporting period.

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' TABLE 1C X

de Atomic Electric Company. Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report First and Second Quarters. 1988 Caseous Effluents - Ground Level Releases

  • 4 There were no rou';ine measured ground level continuous or batch mode gaseous releaves during the first or second quarters of 1988.

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4824R/20.124 k ----...

TABLE 2A Yankee Atomic Electric Company. Rowe. Massachusetts Ef fluent and Waste Disposal Semiannual Report First and Second Quarters. 1988 Liquid 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 5.96E-03 2.59E-02 22.00E+01

2. Average diluted concentration during period uCi/ml 9.67E-11 4.20E-10
3. Percent of applicable limit (1) 2.89E-04 1.57E-03 B. Tritium
1. Total release Ci 4.45E+01 6.69E+01 21.00E+01
2. Average diluted concentration during period uCi/mi 7.22E-07 1.08E-06 3._ Percent of applicable limit (1) 2.41E-02 3.61E-02 C. Dissolved and Entrained Gases
1. Total release Ci 1.40E-02 3.09E-01 22.00E+01
2. Average diluted concentration during period uCi/mi 2.27E-10 5.01E-09
3. Percent of applicable limit (2) 1.14E-04 2.50E-03 D. Gross Alpha Radioactivity
1. Total release Ci

<2.04E-06

<3.97E-06 m3.50E+01 E. Volume of liquid effluent released (prior to dilution) liters 5.26E+06 7.14E+06 m3.00E+01 F. Volume of dilution water used during period liters 6.16E+10 6.17E+10 25.00E+00 (1) Concentration limits specified in 10CFR, Part 20, Appendix B. Table 11 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 2E-04 microcuries/ml (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 any release exceed the concentration limit.

4824R/20.124

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-TABLE 2B Yankee Atomic Electric Company. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Report First and Second Quarters. 1988 i

Liquid Effluents Continuous Mode Batch Mode N ;11 des Released Unit Quarter Quarter Quarter Quarter 1

2 1

2 Strontium-89 Ci (1.35E-04

<2.39E-04

<5.59E-06

<1.88E-05 Strontium-90 Ci (1.55E-04

<1.13E-04

<8.02E-06 (9.14E-06 Cesium-134 Ci 3.55E-06 1.47E-05 1.24E-04 1.08E-03 Cesium-137 Ci 6.66E-06

'.21E-05 1.72E-04 1.22E-03 Iodine-131 Ci 4.05E-06 9.10E-05 3.95E-05 1.25E-02 Cobalt-58 Ci (2.74E-05 (2.38E-05 (3.84E-06

<7.74E-06 Cobalt-60 Ci 6.14E-06 5.02E-06 1.76E-05 3.15E-05 Iron-59 Ci

<5.91E-05 (4.98E-05 (7.43E-06

<1.32E-05 Zine-65 Ci (6.14E-05 (5.20E-05 (8.59E-06

<1.51E-05 Manganese-54 Ci (2.75E-05

<2.38E-05 (4.12E-06 2.68E-07 Chjnium-51 Ci

<2.01E-04 (1.81E-04

<4.60E-05

<1.22E-04 Zirconium-Niobium-95 Ci (4.71E-05 (4.01E-05

<6.94E-06 (1.51E-05 Molybdenum-99 Ci

<1.94E-04

<1.76E-04

<3.00E-05

<6.62E-05 Technetium-99m Ci 4.78E-06 1.32E-06 4.67E-07

<1.65E-05 Barium-Lanthanum-140 Ci (8.97E-05 (7.91E-05 (2.04E-05 (5.18E-05 Cerium-141 Ci (3.44E-05

<3.13E-05

<7.76E-06

<2.65E-05 Ruthenium-103 Ci

<2.63E-05

<2.25E-05

<5.63E-06

<1.52E-05 Cerium-144 Ci

<1.54E-04

<1.39E-04

<3.55E-05

<1.21E-04 Iodine-133 Ci

<2.57E-05 3.12E-05 1.61E-06 2.19E-06 Selenium-75 Ci (2.77E-05

<2.47E-05 (6.33E-06 (1.72E-05 Silver-110m Ci (2.57E-05 (2.23E-05

<5.38E-06

<9.66E-06

_Antime.1y-124 Ci (2.48E-05

<2.28E-05 (7.86E-06

<2.05E-05 5.59E-03 2.26E-02

_ Carbon-14 Ci Ci

<7.01E-04 (5.78E-04 (2.92E-05 6.10E-04 Iron-55 Cesium-136 Ci (2.67E-05

<2.36E-05

<3.97E-06 3.18E-06 Antimony-125 Ci

<7.10E-05 (6.26F-05

<1.87E-05

<4.77E-05 Unidentified Ci Total for period (above) Ci 2.52E-05 1.85E-04 5.94E-03 2.57E-02 Xenon-133 Ci 5.49E-05 2.19E-06 1.26E-02 2.91E-01 Xenon-135 Ci

<2.18E-05

<1.84E-05 4.64E-05 1.45E-04 Xenon-131m Ci

<8.65E-04 (7.95E-04 2.06E-04 5.21E-03 Xenon-133m Ci

<1.74E-04 (1.54E-04 7.87E-05 1.48E-03 Krypton-85 Ci (8.87E-03 (7.91E-03 1.00E-03 1.17E-02

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TABLE 3 Yankee Atomic Electric Company. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Report First and Second Quarters. 1988 Solid Waste'and Irradjated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)*

Unit Six-Month Est. Total Period Error. %

1. Type of Waste
a. Spent resins, filter sludges, evaporator m3 bottoms, etc. - LSA container **.+

Ci

b. Dry compressible waste, contaminated mJ 3.27E+01 eoulpment, etc. - LSA container ++

Cit 2.34E-01 21'. 00 E+0 2

c. Irradiated components, control rods, mJ etc.

Ci d.

m3 ci m3 e.

Ci

2. Estimate of Major Nuclide Composition (By Type of Waste)***
b. Cesium-137

% 3.23E+01 Cesium-134

% 2.97E+01 Iron-55 k 2.65E+01 Cobalt-60

% 3.93E+00 Niobium-95

% 2.69E+00 Nickel-63

% 2.06E+00 Iron-59

% 1.58E+00 Manganeso-54

% 1.10E+00 Carbon-14

% 4.70E-02

3. Solid Wast 3 Disposition Number of Shipments Mode of Transportation Destination 1

Truck Barnwell, SC B. Irradiated Fuel Shipments (Disposition)

None

+ Container volume equal to 55 gallons (drums).

++ Container volume equal to 105 ft3 (boxes).

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

t Estimated.

4824R/20.124

s APPENDIX A Radioactive Liquid Effluent Monitoring Instrumentation Requirement: 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 efforts to return the instrument (s) to operable status within 30 days being unsuccessful. Technical Specification 3.3.6.b requires an explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Report.

R,esponse:

Since the requirements of Technical Specifi.ation 3.3.3.6 governing the operability of radioactive liquid effluent monitoring instrumentation were met _ for this reporting period, no response is required.

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APPENDIX B Radioactive Gaseous Effluent Monitoring Instrumentation.

Requirement: Radioactive gaseous effluent monitoring instrumentation channels

]

are required to be operable in accordance with Technical Specification 3.3.3.7.

With less than the minimum number of channels operable and reasonable efforts to return the instrument (s) to operable status within 30 days being l

unsuccessful, TecL11 cal Specification 3.3.3.7.b requires an explanation for the delay in correcting the inoperability in the a

next Semiannual Ef fluent Release Report.

Response

Since the requirements of Technical Specification 3.3.3.7 governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period.

no response is required.

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.a APPENDIX C Liquid Holdup Tanks Requirement : Technical Specification 3.11.1.4 limits the quantity of radioactive matcrial contained in any outside temporary tank.

With the quantity.of radioactive material in any outside 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.

Response

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

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8 APPENDIX D Radiological Environmental Monitoring Program

' Requirement:

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 or more of the required sample locations. Technical Specification 3.12.1.c re, quires the identification of the new location (s) for obtaining replacement sample (s) in the next Semiannual Ef fluent Release Report and inclusion of revised Off-Site Dose Calculation Manual Figure (s) and Table (s')

reflecting the new location (s).

Response

No new sampling locations were needed to be identified in accordance with the above requirement.

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D-1 4824R/20.124

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s-o APPENDIX E Land Use Census Requirement: 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 annual Land Use Census was not completed during this reporting. period.

Requirement: With a land use census identifying a location (s) which yields a cal:ulated 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 the identification of the new location (s) in the next Semiannual Effluent Release Report.

Response

The annual Land Use Census was not completed during this reporting period.

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4824R/20.124 s

APPENDIX F 9

Process Control Program Requirement: Technical Specification 6.14.1 requires that licensee initiated changes to the Process Control Program be submitted to the Commission in the Semiennual Radioactive Effluent Release Report for the period in which the change (s) was made.

Response

There were no licensee initiated changes to the Process Control Program during this reporting period.

F-1 4824R/20.124

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APPENDIX G Off-Site Dose Calculation Manual Requirement: 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.

Response

There was one licensee initiated revision to the Off-Site Dose Calculation Manual during this reporting period which consisted of the following:

1.

Section 4.0 of the ODCM was revised in Revision 6 to reflect the following changes:

Food product sampling location TF-12 was deleted from a.

Table 4.1 since samples from there were no longer required after October 31, 1986.

b.

The fenceline location and several building names and locations were updated in Figure 4-4 2.

The ODCM was also revised in Revision 6 to reflect additional changes in the liquid dose and gaseous dose and dose rate calculations. These changes are identified as follows:

a.

The liquid dose factors in Section 3.0 were revised to reflect the additional dose pathways of irrigated food crops to man, and irrigated food crops to cow to man.

These additional pathways were included as a result of a survey which indicated that water from the Deerfield River was used to irrigate foed crops.

G-1 4824R/20.124

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APPENDIX G

'(Continued) b.

The liquid dose equations in Section 3.0 were revised to incorporate a Deerfield River flow rate correction factor to account for variation in the river flow rate during the year. The minimum monthly ten-year average (August 1974 to September 1984) Deerfield River flow rate below Sherman Dam was used in the correction factor as a default value if actual river flow data during release periods is unavailable.

c.

In the example calculations in Section 5.0, the steam

~

generator flow rate, f, was changed to 100 gpm to 2

reflect the' maximum flow rate during actual discharge, and generate the most restrictive liquid monitor setpoint.

d.

The text in Section 6.0 was revised to reflect a flow' rate meter placed on the steam generator blowdown tank discharge line to estimate the discharge rate during periods of release. The flow rate meter was installed during the previous reporting period in response to Technical Specification Amendment Change 92 wh'ich required a flow rate measuring device for the steam generator blowdown tank effluent (Table 3.3-8).

e.

Ths noble gas dose equations, dose conversion factors for individual iodine, tritium, and particulate radionuclides, description of bases for equations in i

Section 3.0, and effluent monitor setpoint equations in Section 5.0, were revised for a more recent 5-year (1981 through 198S) period than the original ODCM.

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e-APPENDIX G (Continued) f.

The iodine, tritium, and particulate dose and dose rate-factors in Section 3.0 were-expanded to include nuclides not considered previously in the dose and dose rate calculations.

g.

The noble gas dose rate equations and dose rete factors for iodine and particulate radionuclides in Section 3.0 were revised to change the shielding factor from 0.7 to 1.0 to account for the fact that the dose rate applies at all times at, or beyond, the site boundary.

h.

Section 3.0 of the ODCM was also expanded to includ'e a methodology for calculating the gamma air and beta air doses in the case of an unexpected ground level noble gas release, since other listed gaseous dose equations relate to the plant stack only.

i. The following changes relate to the calculational development of the dose factors in Section 3.0:

(1) The agricultural productivity for pasture grass was

-2

-2 changed from 0.75 kg m to 0.7 kg m to keep consistent with USNRC Regulatory Guide 1.109 Revision 1, October 1977.

(2) The crop exposure time to the plume for stored feed was changed from 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> to 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br />, since the stored feed that cattle consume at and around Rowe is corn silage.

(3) The fraction of leafy vegetables grown in the garden of interest was changed from 0.5 to 1.0 to keep consistent with Regulatory Guide 1.109.

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4 APPENDIX G (Continued)

(4) The fraction of iodine assumed to be in elemental form was corrected from 1.0 to 0.5 to keep

~

consistent with Regulatory Guide 1.109.

(5) The absolute humidity value was changed from 8.0 g m-3 to 5.6 3 m-3,gne, gg g,,,,,,

representative average value for the region. The

~

value of 5.6 g m was taken from Health Physics Journal, Volume 39. Number 2. August 1980 Pergannon Press,~ Ltd.

(6) The ground deposition factors (D/Q values) which are factor'ed into the critical organ dose and dose rate factors were revised to reflect the relative deposition rate curves from USNRC Regulatory Guide 1.111. Revision 1. July 1977.

j. Miscellaneous typographical errors were also corrected throughout the ODCM which had no impact on the methodology or parameter values used.

None of the above changes will reduce the accuracy or reliability of dose calculations or setpoint determinations.

l The calculated methodology is the same as in the original version of the ODCM and remains consistent with Regulatory Guide 1.109 changes.

Changes in the dose calculations relate to parameter values which have been updated to reflect Regulatory Guide 1.109 values or more conservative site-related values.

The above changes have been reviewed and approved by PORC.

The revised ODCM pages reflecting the above changes are included as part of this Appendix.

G-4 4824R/20.124

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