ML20237K802

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Effluent & Waste Disposal Semiannual Rept for First & Second Quarters 1987
ML20237K802
Person / Time
Site: Yankee Rowe
Issue date: 06/30/1987
From: Papanic G
YANKEE ATOMIC ELECTRIC CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
FYR-87-92, NUDOCS 8709080029
Download: ML20237K802 (21)
v • d • e


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EFFLUENT AND WASTE DISPOSAL SJMIANNUAL REPORT FOR FIRST AND SECOND QUARTERS, 1987 s

l Yankee Atomic Electric Company v

Rowe, Massachusetts 4824R/20.124 h

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8709080029 970630 PDR ADOCK 05000029 R

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TABLE 1 A q

Yankee Atomic Electric Company, Rowe, Massachusetts y

I Effluent and Waste Disposal Semiannual Report First and Second Quarters, 1987 Gaseous Effluents - Summation of All Releases i.

Unit Quarter Quarter Est. Total-i 1-2 Error, %

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A. Fission and Activation Gases I

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1. Total releare Ci 1.09E+02 1.26E+02 25.50E+01
2. Average release rate for period uCi/see 1.39E+01 1.60E+01
3. Percent of Tech. Spec. limit (1)(4) 1.22E+00 9.50E-01 B. Iodines
1. Total Iodine-131 Ci 3.65E-08 2.86E-06 22.50E+01
2. Average release rate for period uCi/sec 4.64E-09 3.64E-07
3. Percent of Tech. Spec. limit (2)(4) 9.87E-02 6.53E-02 C. Particulate
1. Particulate with T-1/2 > 8 days Ci 4.22E-06 3.24E-06 e3.00E+01
2. Average release rate for period uCi/sec 5.37E-07 4.12E-07
3. Percent of Tech. Spec. limit (3)

(3)

4. Cross alpha radioactivity Ci

<1.60E-08

<1.20E-07 D. Tritium

1. Total release Ci 1.26E+00 __8.10E+01 23.00E+01
2. Average release rate for period uCi/sec 1.60E-01 1.03E-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 approximately the same.

(2) Technical Specification 3.11.2.3.a for dose from 1-131, Tritium, and radionuclides in particulate form.

(3) Per Technical Specification 3.11.2.3, dose contributions from Tritium and particulate are included with 1-131 above in Part B.

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

4824R/20.124 I

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TABLE 1B Yankee Atomic' Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report First and Second Quarters, 1987 Gaseous Effluents - Elevated Release Continuous Mode Batch Mode Nuclides Released Unit _

Quarter Quarter Quarter (1) Quarter 1

2 1

2

1. Fission Gases-Krypton-85 Ci 4.80E-02 3.15E+00 4.49E+00 Krypton-85m Ci 1._67E+00 6.98E-01 1.37E-01 Krypton-87 Ci

_1.66E+00 7.68E-01

<2.06E-02 Krypton-88 Ci 3.47E+00 1.48E+00 1.09E-01 Xenon-133 Ci 5.56E+01 4.74E+01 4.20E+01 Xenon-135 Ci 2.04E+01 1.07E+01 2.40E+00 Xenon-135m Ci 2.16E+01 6.89E-0C

<1.01E-02 Xenon-138 Ci 1.00E+0%

4.56E-01

<3.83E-02 Xenon-133m Ci 1.30E+00 9.66E-01 6.60E-01 Argon-37 C1 1.72E-02 3.11E-01 4.32E-01 Argon-41 Ci 3.76E-01 1.61E-01

<1.70E-02 Carbon-14 Ci 9.06E-03 5.43E-01 7.60E-01 Xenon-131m Ci 1.40E+00 1.09E+00 8.27E-01 Unidentified Ci Total for period Ci 1.09E+02 7.46E+01 5.19E+01

2. Iodines Iodine-131 C1 3.65E-08 1.52E-06 1.34E-06 Iodine-133 Ci

<4.97E-06

<1.42E-06

< 1. '2 6 E-0 6 Iodine-135 Ci (3.00E-07

<1.71E-07 (1.52E-07 Total for period Ci 3.65E-08 1.52E-06 1.34E-06

3. Particulate

' Strontium-89 Ci (8.67E US

<5.73E-08 (6.47E-08 Strontium-90 Ci (1.73E-08

<l.27E-08 (1.44E-08 Cesium-134 Ci 4.10E-07 1.78E-07 1.58E-07 Cesium-137 Ci 8.75E-07 2.02E-07 1.79E-07 Barium-Lanthanum-140 Ci

<2.57E-06

<1.19E-06

<1.06E-06 Zine-65 Ci (1.95E-06 (8.85E-07

<7.85E-07 Cobalt-58 Ci

<8.21E-07 (4.07E-07

<3.61E-07 Cobalt-60 Ci 2.83E-06 1.29E-06 1.14E-06 Iron-59 Ci

<1.71E-06

<8.11E-07 (6.58E-07 Chromium-51 Ci

<5.38E-06

<2.61E-06

<2.31E-06 Zirconium-Niobium 95 Ci (1.37E-06

<7.15E-07

<5.80E-07 Cerium-141 Ci (6.96E-07 2.20E-08 1.95E-08__

Cerium-144 Ci

<3.08E-06

<1.45E-06

<1.28E-06__

Antimony-124 Ci (8.22E-07

<3.87E-07

<3.43E-07 Manganese-54 Ci 1.01E-07 3.05E-08 2.70E-08 Silver-110M Ci

<8.03E 07

<3.65E-07

<3.24E-07 Molybdenum-99 Ci

<5.88E-06

<2.72E-06

<2.41E-06 Ruthenium-103 Ci

<7.3_2E-07 __.<3.47E-07

<3.08E-07 Total for period Ci 4.22E-06 1.72E-06 1.52E-06 (1) There were no batch gaseous releases f or the first quarter.

4S24R/20.124 1

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TABLE IC Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report First and Second Quarters 1987 Gaseous Effluents - Ground Level Releases There were no routine measured ground level continuous or batch mode gaseous releases during the first or second quarters of 1987.

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TABLE 2A Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report First and Second Quarters, 1987 Liquid Effluents - Summation cf All Releases Unit Quarter Quarter Est. Total 1

2 Error, %

A. Fission and Activation Products

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

Ci s.88E-03 4.14E-03 z2.00E+01

2. Average diluted concentration during period uCi/ml 9.48E-11 1.75E-10
3. Percent of applicable limit (1) 3.81E-03 5.30E-03 B. Tritium
1. Total release Ci 9.90E+01 3.38E+01 21.00E+01
2. Average diluted concentration during period uCi/ml 1.60E-06 1.43E-06
3. Percent of applicable limit (1) 5.33E-02 4.77E-02 C. Dissolved and Entrained Gasus
1. Total release Ci 1.30E-00 7.15E-02 e2.00E+01
2. Average diluted concentration during period uC1/ml 2.10E-08 3.03E-09
3. Percent of applicable limit (2) 1.05E-02 1.51E-03 D. Gross Alpha Radioactivity
1. Total release Ci

<1.87E-06

<1.46E-06 23.50E+01 E. Volume of liquid effluent released (prior to dilution) liters 5.78E+06 3.88E+06 m3.00E+01 F. Volume of dilution water used during period liters 6.20E+10 2.36E+10 25.00E+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 2E-04 microcuries/ml (Technical Specification 3.11.1).

The percent of applic'able 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

l TABLE 2B.

Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report j

I First and Second Quarters, 1987 Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 1

2 1

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Strontium-89 Ci (2.62E-04

<1.36E-04 4.72E-06 3.04E-05 Stronti.um-90 Ci

<5.24E-05

<1.63E-05 1.19E-06

<6.96E-06 Cesium-134 Ci 1.39E-05 9.96E 1.12E-03 9.15E-04 Cesium-137 Ci 3.55E-05 1.78E-05 1.20E-03 1.04E-03 Iodine-131 Ci 4.21E-05

<1.28E-05 6.05E-04 3.23E-04 Cobalt-58 C1 2.29E-07

<1.39E-05 (9.79E-06 5.52E-07 Cobalt-60 Ci 1.88E-05 1.18E-05 6.50E-05 9.36E-05 Iron-59 Ci

<6.65E-05

<2.71E-05

<1.57E-05

<2.74E-05 Zinc-65 Ci

<7.53E-05

<2.96E-05

<1.89E-05

<3.30E-05 Manganese-54 Ci

<3.41E-05

<1.38E-05 1.82E-05 1.02E-05 Chromium-51 Ci (2.49E-04

<1.02E-04

<1.60E-04

<1.82E-04 Zirconium-Niobium-95 Ci

<5.48E-05

<2.28E-05

<1.93E-05

<3.04E-05 Molybdenum-99 Ci (2.41E-04 (9.92E-05

<8.21E-05

<1.20E-04 Technetium-99m C1 1.11E-05 9.53E-06

<2.35E-05 2.30E-07 Barium-Lanthanum-140 Ci

<1.05E-04

<4.51E-05

<6.89E-05 2.81E-06 Cerium-141 Ci (4.40E-05

<1.80E-05

<3.76E-05

<3.17E-05 Ruthenium-103 Ci

<3.09E-05

<1.25E-05

<1.91E-05

<2.32E-05 Cerium-144 C.i

<l.98E-04

<8.15E-05

<1.72E-04

<1.44E-04 Iodine-133 Ci

<3.22E-05

<1.28E-05 1.39E-05 3.98E-07 Scienium-75 Ci

<3.57E-05

<1.43E-05

<2.41E-05

<2.57E-05 Silver-110m Ci

<3.24E-05 (1.37E-05

<1.27E-05

<1.94E-05 Antimony-124 Ci

< 3.15E-05

<1.30E-05 (2.73E-05

<2.95E-05 Carbon-14 Ci 2.33E-03 1.28E-03 Iron-55 Ci

<5.24E-03

<2.73E-03 4.14E-04 3.90E-04 Cesium-136 Ci

<3.19E-05

<1.31E-05

<1.05E-05

<1.54E-05 Tellurium-132 Ci (2.62E-05

<1.04E-05 (1.79E-05 5.32E-07 Total for period (above) Ci 1.22E-04 4.91E-05 5.76E-03 4.09E-03_

Xenon-133 Ci 1.04E-04 9.15E-06 1.21E+00 6.61E-02 Xenon-135 Ci 5. 20 E_-0 5

<l.01E-05 3.48E-04 5.42E-05 Xenon-131m Ci

<l.12E-03

<4.51E-04 2.47E-02 1.62E-03 Xenon-133m Ci

<2.29E-04 (8.93E-05 4.95E-03 2.86E-04 Krypton-85 Ci (1.02E-02 (4.22E-03 5.71E-02 3.48E-03 4824R/20.124

IAplE 3 Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report First and Second Quarters, 1987 Soli _d_ Waste and Irrsdiated 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 3

1.70E+01

a. Spent resins, filter sludges, evaporator m

bottoms, etc. - LSA container **,+

Ci 4.00E+00 23.00E+01 3

b. Dry compressible waste, contaminated m

equipment, etc. - LSA container ++

Ci 3

c.

Irradiated components, control rodt, m

etc.

Ci 3

d.

m Ci 3

m c.

Ci

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

a.

Iron-55

% 4.01E+01 Hydrogen-3

% 3.41E+01 Cesium-137

% 7.30E+00 l

l Cobalt-60

% 6.80E+00 Cesium-134

% 5.30E+00 Manganese-54

%__2.20E+00 Niobium-95

% 1.10E+00 k

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

Truck Barnwell, SC B. Irradiated Fuel Shipments (Disposition): None Container volume equal to 55 gallons (drums).

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

Solid waste is Class A, as defined in 10CFR61.55.

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

4824R/20.124

APPENDIX A 1

Radioactive Liquid Effluent Monitoring Instrumentation J

Requirement: Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with Technical l

Specification 3.3.3.6.

With less than the minimum number of channels operable and reasonable efforts to return the instruc..ent(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.

Response

The flow rate measuring device for the steam generator blowdown tank effluent (Table 3.3-8) was installed during this reporting period, but has not yet been calibrated. ACTION Statement 17 of Table 3.3-8 is still in effect until the flow rate measuring device for the steam generator blowdown tank effluent is calibrated, which is expected during the next reporting period.

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A-1 4824R/20.124

APPENDIX B Radioactive Gaseous Effluent Monitoring Instrumentation Requirement: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with Technical j

Specification 3.3.3.7.

With less than the minbaum number of channels operable 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.

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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APPENDIX C Liquid Holdup Tanks l

Requirement: Technical Specification 3.11.1.4 limits the quantity of radioactive material contained in any outside temporary tank.

i 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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1 APPENDIX D Radiological Environmental Monitoring Program Requirement: The radiological environmental monitoring program is conducted in accordan'ce 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 requires the identification of the new location (s) for obtaining replacement sample (s) in the next Semiannual Effluent 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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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.

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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 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 the identification of the new location (s) in the next Semiannual Effluent Release Report.

The annual Land Use Census was not completed during this

Response

reporting period.

E-1 4824R/20.124

APPENDIX F

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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 Semiannual Radioactive Effluent Release Report-1

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

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Response

There was one licensee initiated amendment to the Process Control Program during this reporting period.

The following April 23, 1987 changes were made to the YNPS Process Control Program:

Provided the option of drilling of cement solidified in a.

55-gallon drums to allow for inspection of selected drums for dryness, and b.

Add to and modify Appendix B. " Station Procedures Which Implement the PCP."

The above changes did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.

The changes have been reviewed and accepted by PORC, and are noted in the revised PCP.

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j APPENDIX G Off-Site Dose Calculation Manual l

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

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

Response

There were no changes made to the ODCM during this reporting period.

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APPENDIX H Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems Requirement: 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 Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee.

Response

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 Supplemental Information First and Second Quarters, 1987 1.

Technical Specification Limits - Dose and Dose Rate Technical Specification 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 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 l

Greater than 8 days 1

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 I-1 4824R/20.124

2.

Technical Specification Limits - Concentration Technical Specification and Category Limit a.

Noble Gases No MPC limits b.

Iodine-131. Tritium and Radionuclides No MPC limits in Particulate Form With Half-Lives Greater than 8 days c.

Liquids 3.11.1 ~.1 Total sum of the fraction of MPC (10CFR20, Appendix B, Tables II, Column 2), excluding noble gases less than:

1.0 3.11.1.1 Total noble gas concentration 2E-04 uCi/cc 3.

Measurements and Approximations of Total Radioactivity a.

Noble Gases

" 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 +55 percent.

b.

Iodines Iodines are continuously monitored by drawing a sample from the primary vent stack through a particulate filter and charcoal cartridge. The filter and charcoal cartridge are removed and I-2 4824R/20.124

analyzed weekly. The errors associated with these measurements are estimated to be 25 percent.

c.

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

The errors associated with the determination of particulate effluents

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are estimated to be 230 percent.

d.

Liquid Effluents Liquid effluents are determined by direct measurement.

In line composite samples are analyzed for strontium - 89, strontium - 90, 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 thece measurements are as follows:

fission and activation products, 320 percent; tritium, i10 percent; dissolved fission gases, 20 percent; alpha activity, 135 percent.

4.

Batch Releases a.

Liquids First Quarter Number of batch releases:

20 Total time period for batch releases:

7850 minutes Maximum time period for a batch release:

1800 minutes Average time period for batch releases:

392 minutss Minimum time period for a batch release:

235 minutes Average stream flow during period (Sherman Dam):

763 cfs Average discharge rate:

18.0 gpm I-3 4824R/20.124

Second Quarter Number of batch releases: 48

' Total time period for batch releases:

15193 minutes Maximum time period for a batch-release:

1715 minutes Average time period for batch releases:

316 minutes Minimum time period for a batch release:

15 mint.tes Average stream flow during period (Sherman Dam):

382 cfs Average discharge rate:

20.0 gpm b.

Gases First Quarter There were no batch releases during the first quarter.

-Second Quarter Number of batch releases:

7 Total time period for batch releases:

2725 minutes Maximum time period for a batch release:

650 minutes Average time period for batch releases:

389 minutes Minimum time period for a batch release:

105 minutes i

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Abnormal Releases a.

Liquid I

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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~4824R/20.124

Telephone (017) 872-8100 TWX 710-380-7619 YANKEE ATORflC ELECTRIC CdhfPANY y,

1671 Worcester Road, Framingham, Massachusetts 01701 i

August 28, 1987 FYR 87-92 United States Nuclear Regulatory Commission Document Control Desh l

Washington, DC 20555

References:

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

Subject:

Semiannual Effluent Release Report

Dear Sir:

l Enclosed are the tables summarizing the quantities of radioactive liquid and gaseous cffluents, and solid waste released from Yankee Nuclear Power Station at Rowe, Massachusetts for the first and second quarters of 1987. This information is submitted in accordance with Technical Specification 6.9.5.b.

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

Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY i

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George '[Fapanic, /Jr.

Senior Project Engineer - Licensing GP/25.114 cc: USNRC Region I USNRC Resident Inspector, YNPS I

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