Text

Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters,1986
	ML20207T182
Person / Time
Site:	Yankee Rowe
Issue date:	12/31/1986
From:	Papanic G; YANKEE ATOMIC ELECTRIC CO.
To:	Murley T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
	FYR-87-21, NUDOCS 8703230288
	Download: ML20207T182 (82)
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT:

. FOR THIRD'AND FOURTH' QUARTERS. 1986 1

Rowe, Massachusetts

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TABLE 1A Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters, 1986 Gaseous Effluents - Summation of All Releases Unit Quarter Quarter Est. Total 3

4 Error, %

A. Fission and Activation Gases

1. Total release Ci 1.49E+02 1.13E+02 25.50E+01

2. Average release rate for period uCi/sec 1.90E+01 1.44E+01

3. Percent of Tech. Spec. limit (1)

B. Iodines

1. Total Iodine-131 Ci 1.18E-04 1.88E-06 22.50E+01

2. Average release rate for period uCi/see 1.50E-05 2.39E-07

3. Percent of Tech. Spec. limit (2)

C. Particulates

1. Particulates with T-1/2 > 8 days Ci 1.39E-06 4.56E-06 m3.00E+01

2. Average release rate for period uCi/sec 1.77E-07 5.80E-07 3.-Percent of Tech. Spec. limit (3)

(3)

4. Gross alpha radioactivity Ci 2.50E-08 1.80E-08 D. Tritium

1. Total release Ci 2.88E+00 1.59E+00 z3.00E+01

2. Average release rate for period uCi/see 3.66E-01 2.02E-01

3. Percent of Tech. Spec. limit (3)

(3) l (1) Technical Specification 3.11.2.2.a for gamma air dose. Percent values for l

Technical Specification 3.11.2.2.b for beta air dose are approximately the i

same.

(2) Technical Specification 3.11.2.3.a for dose from I-131 Tritium, and i

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.

l Percent of Technical Specification limits will be provided in the supplemental L

report which will include the annual dose summary.

9_

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TABLE IB

-Yankee Atomic Electric Company, Rowe, P.assachusetts

-Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters, 1986

' Gaseous Effluents - Elevated Release Continuous Mode Batch Mode (1)

Nuclides Released Unit Quarter Quarter.

Quarter Quarter 3

4 3

4

1. Fission Gases Krypton-85 Ci

-3.93E-02 4.66E-02 Krypton-85m Ci 1.71E+00 1.39E+00 Krypton-87 Ci 1.58E+00 1.26E+00 Krypton-88 Ci 1.90E+00 2.63E+00 Xenon-133 Ci 7.38E+01 5.86E+01 Xenon-135 Ci 2.96E+01 2.21E+01 Xenon-135m Ci 3.80E+01 2.37E+01 Xenon-138 Ci 4.48E-01 6.89E-01 Xenon-133m Ci 9.25E-01 1.25E+00 Argon-37 Ci 1.68E-02 1.43E-02 Argon-41 Ci 1.03E-01 1.57E-01 Carbon-14 Ci 5.61E-03 6.66E-03 Xenon-131m Ci 9.06E-01 1.22E+00 Unidentified Ci Total for period Ci 1.49E+02 1.13E+02

2. Iodines Iodine-131 Ci 1.18E-04 1.88E-06 Iodine-133 Ci 2.91E-05 7.21E-06

)

Iodine-135 Ci

<1.44E-06

<3.64E-06 Total for period Ci 1.47E-04 9.09E-06

3. Particulates Strontium-89 Ci

<7.31E-08

<1.89E-07 Strontium-90 Ci

<9.23E-09 (4.35E-08 Cesium-134 Ci

<3.93E-07 1.11E-06 Cesium-137 Ci 4.89E-08 1.18E-06 Barium-Lanthanum-140 Ci

<1.21E-06

<2.02E-06 Zine-65 Ci

<8.97E-07 (1.37E-06 Cobalt-58 Ci 7.03E-08 (6.35E-07 Cobalt-60 Ci 1.16E-06 2.23E-06 Iron-59 Ci

<8.38E-07 (1.25E-06 Chromium-51 Ci

<2.82E-06 (4.77E-06 Zirconium-Niobium-95 Ci

<7.20E-07

<1.10E-06 Cerium-141 Ci

<3.52E-07 7.95E-09

~

Cerium-144 Ci (1.48E-06

<2.63E-06 Antimony-124 Ci

<3.69E-07 (6.89E-07 Manganese-54 Ci 1.07E-07 2.90E-08 Silver-110m Ci

<3.56E-07

<6.22E-07 Molybdenum-99 Ci

<2.77E-06

<4.52E-07 Ruthenium-103 Ci

<3.46E-07 (5.60E-07 Total for period Ci 1.39E-06 4.56E-06 (1) There were no batch mode releases during this reporting period. 2819R

4 e

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TABLE IC Yankee Atomic Electric Company. Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1986 Gaseous Effluents - Ground Level Releases

~ There were no routine measured ground level continuous or batch mode gaseous releases during the third or fourth quarters of 1986.

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TABLE 2A Yankee Atomic Electric Company. Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters, 1986 Liquid Effluents - Summation of All Releases Unit Quarter Quarter Est. Total 3

4 Error, %

A. Fission and Activation Products

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

Ci 3.66E-03 2.36E-03 e2.00E+01

2. Average diluted concentration during period uCi/ml 5.99E-11 3.81E-11

3. Percent of applicable limit (1) 3.57E-03 1.67E-03 B. Tritium

1. Total release Ci 5.78E+01 4.12E+01 el.00E+01

2. Average diluted concentration during period uC1/ml 9.46E-07 6.64E-07

3. Percent of applicable limit (1) 3.15E-02 2.21E-02 C. Dissolved and Entrained Gases

1. Total release Ci 7.55E-02 1.12E-01 e2.00E+01

2. Average diluted concentration during period uCi/mi 1.24E-09 1.81E-09

3. Percent of applicable limit (2) 6.20E-04 9.05E-04 D. Gross Alpha Radioactivity

1. Total release Ci 1.25E-06

<2.65E-06 3.50E+01 E. Volume of waste released (prior to dilution) liters 5.04E+06 5.98E+06 e3.00E+01 F. Vclume of dilution water used during period liters 6.11E+10 6.20E+10 e5.00E+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 applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit. 2819R

6 TABLE 2B Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters, 1986 Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3

4 3

4 Strontium-89 Ci (2.26E-04

<2.26E-04

<1.57E-05

<1.59E-06 Strontium-90 Ci

<3.17E-05

<5.08E-05

<2.61E-06 6.83E-07 Cesium-134 Ci 1.83E-06 2.01E-05 7.28E-04 3.62E-04 Cesium-137 C1 1.21E-05 4.52E-05 7.63E-04 3.73E-04 Iodine-131 Ci 5.97E-06 1.75E-05 5.99E-04 2.64E-04 Cobalt-58 Ci (1.51E-05

<2.15E-05 1.18E-06 5.09E-07 Cobalt-60 Ci 9.99E-06 1.07E-05 7.63E-05 1.16E-04 Iron-59 Ci

<3.00E-05

<3.91E-05

<1.35E-05

<8.46E-06 Zine-65 Ci (3.09E-05 (4.26E-05

<1.65E-05

<1.19E-05 Manganese-54 Ci (1.51E-05

<1.93E-05 3.81E-05 1.12E-05 Chromium-51 Ci

<1.15E-04

<1.66E-04

<1.14E-04 (7.30E-05 Zirconium-Niobium-95 Ci

<2.55E-05

<3.42E-05

<1.54E-05

<1.07E-05 Molybdenum-99 Ci (1.08E-04

<1.47E-04

<6.51E-05

<4.46E-05 Technetium-99m Ci

<2.32E-05

<3.16E-05

<1.40E-05

<1.02E-05 Barium-Lanthanum-140 Ci (4.85E-05 (6.68E-05 (4.54E-05

<2.86E-05 Cerium-141 Ci (2.00E-05

<2.86E-05

<2.19E-05

<1.67E-05 Ruthenium-103 Ci (1.38E-05 (1.95E-05

<1.32E-05 (8.24E-06 Cerium-144 Ci

<9.11E-05

<1.27E-04

<1.00E-04 (7.33E-05 Iodine-133 Ci

<1.39E-05

<1.96E-05 3.89E-05 2.00E-05 Selenium-75 Ci

<1.61E-05 (2.29E-05

<1.64E-05

<1.08E-05 Silver-110m Ci

<1.45E-05

<1.96E-05

<1.03E-05 (6.92E-06 Antimony-124 Ci

<1.32E-05

<1.92E-05

<1.67E-05

<1.26E-05 Carbon-14 Ci 1.15E-03 9.24E-04 Iron-55 Ci (4.25E-03

<5.65E-03 2.23E-04 1.94E-04 Cesium-136 Ci (1.48E-05 (1.93E-05 1.29E-05 9.55E-07 Antimony-125 Ci

<4.04E-05 (5.63E-05 (4.25E-05

<2.70E-05 Unidentified Ci Total for period (above) Ci 2.99E-05 9.35E-05 3.63E-03 2.27E-03 Xenon-133 Ci 5.52E-04 5.34E-05 6.13E-02 1.05E-01 Xenon-135 Ci 2.21E-04

<1.77E-05 1.08E-04 1.85E-04 Xenon-131m Ci

<5.12E-04 (7.32E-04 3.51E-03 1.93E-03 Xenon-133m Ci 2.84E-04

<1.47E-04 2.30E-04 5.32E-04

_ Krypton-85 Ci

<4.70E-03

<6.60E-03 9.55E-03 3.11E-03 2819R

TABLE 3 Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report

- Third and Fourth Quarters,1986 Solid 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. Type of Waste

a. Spent resins, filter sludges, evaporator m

6.20E+00 3

bottoms, etc. - LSA container **,+

Ci 4.00E-01 3.00E+01

b. Dry compressible waste, contaminated m3 1.49E+01 equipment, etc. - LSA container ++

Ci 4.34E-01 el.00E+02

c. Irradiated components, control rods, m3 etc.

Ci

d. Waste oil - LSA container **,+

m3 6.60E+00 C1 1.50E-02 e3.00E+01 e.

m3 Ci

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

a.

Iron-55

% 2.54E+01 b.

Manganese-54 % 6.30E+00 Cesium-137

% 1.71E+01 Iron-55

% 5.70E+00 Cesium-134

% 1.36E+01 Hydrogen-3

% 5.80E+00 Hydrogen-3

% 1.02E+01 Cobalt-60

% 5.00E+00 Manganese-54 % 8.10E+00 Strontium-89 % 4.20E+00 Cobalt-60

% 6.60E+00 c.

Hydrogen-3

% 8.40E+01 Niobium-95

% 6.10E+00 Iron-55

% 5.50E+00 Strontium-89 % 4.00E+00 Chromium-51

% 1.80E+00 b.

Cesium-137

% 1.89E+01 Niobium-95

% 1.70E+00 Cesium-134

% 1.81E+01 Ruthenium-103 % 1.70E+00 Niobium-95 1 1.81E+01 Ruthenium-106 % 1.50E+00

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

Truck Barnwell, SC 1

Truck Richland, WA B. Irradiated Fuel Shipments (Disposition): None.

+ container volume equal to 55 gallons (drums).

++ 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. 2819R

r 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.

Response

Technical Specification Amendment change 92 incorporated a requirement for a flow rate measuring device for the steam generator blowdown tank effluent (Table 3.3-8).

At the time of the change the blowdown tank effluent line did not have a flow measuring device. On June 26, 1986 at 1510 ACTION Statement 17 of Table 3.3-8 was entered with the required flow rate being estimated from curves relating the discharge rate to the vacuum maintained in the discharge line. Operations Department surveillance forms have been amended to include the four-hour surveillance requirement.

An engineering evaluation was conducted to ensure the proper choice of a flow measuring device which would withstand high temperatures and potentially high solids buildup. A plant design change has been initiated for installation of the flow measuring device. Estimations of the time necessary to install and test the device indicate that blowdown would have to be secured (rather than rerouted) in order to preclude an adverse impact on waste disposal processing time. Operable steam generator blowdown monitors are required (T.S. Table 3.3-4) in operating Modes 1 through 4.

Since the completion of the engineering evaluation, the facility has not entered Mode 5 operation.

Entrance into Mode 5 would be required in order to secure blowdown.

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APPENDIX A (Continued)

- The requirements of the ACTION Statement will be maintained until the upcoming refueling outage when the plant design

- change will incorporate the installation of a flow measuring device. An approximate completion date of June 15, 1987 is planned.

J 4

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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 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 Requirement: 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 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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2.

APPENDIX D Radiological Environmental Monitoring Program i

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 3.4.12.1.c requires the identification of the new locat.,n(s) for obtaining replacement sample (s) in the next Semiant2a1 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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' 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 land use census for.this reporting period did not identify-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.

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 s ' 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 land use census for this reporting period identified two milk animal locations which yielded a calculated dose commitment 1

(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.

Specifically, such milk animal locations were found at WNW, 1.9 km and NE, 3.7 km.

Neither location, however, would be able to provide E-1 2819R

r:

APPENDIX E (Continued) 4 samples of sufficient size over an extended period due to the small number of milking cows owned. -Consequently,-the two-existing locations, TM-12 and TM-13, were kept as official sampling locations.

With respect to food crop sampling locations, Station TF-13, Monroe, was added to the program based on the above dosimetric criterion. Station TF-12, Ford Hill Road, was deleted from the program following October 31, 1986, pursuant to Technical.

Specification 3.12.2.b.

E-2 2819R

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

i

' Response:

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

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F-1 2819R 1

APPENDIX G Off-Site Dose Calculation Manual i

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

Revision 5 of the ODCM included land use census-initiated changes in Section 4.0.

Specifically, food crop sampling Location TF-13 was added to Table 4-1, and a footnote to Table 4-1 was added to allow Location TF-12 to be discontinued after October 31, 1986. Figure 4-2 (map) was changed to reflect the addition of Location TF-13.

Several clerical errors in Section 4.0 from Revision 4 were corrected with Change No. 6.

Specifically, they were:

(1) in Table 4-1, food crop sampling Location TF-12 was incorrectly listed as Harriman Station, 3.2 km, N, and was changed to Ford Hill Road, 3.5 km, E; (2) air sampling Location AP/CF-13 was changed from SSE to SE; and (3) food crop and broadleaf vegetation Locations TF-11 and TV-11 were changed from 1.1 km to 1.3 km.

Additionally, the revision date for Revision 1 was changed from March 30, 1983 to March 30, 1984.

The revised pages of the ODCM are given in the six attached pages.

G-1 2819R

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YANKEE NUCLEAR POWER STATION OFF-SITE DOSE CALCULATION MANUAL YANKEE ATOMIC ELECTRIC COMPANY NUCLEAR SERVICES DIVISION 1671 WORCESTER ROAD TRAMINGilAM, MASSACHUSETTS 01701 i

PREPARED BY/DATE REVIEhED BY/DUE APPROVED Andrew D. Hodgdon 12/2/82 PORC,11/29/82 ORIGINAL William D. Billings 12/2/82 6-M[ b= If [2'[Ff N

M/4dNf7 3

REVISION 1 Matth.5 ds 196'l h;3.,f./['

EM M 6 =*j

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$,8CM REVISION 2 r

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985 Ye IN M/hth [ud PORC Meeting 86-16 REVISION 3

, cgb.f February 25, 1986 PORC Meetin co-4 ri.

a E e u / t C ~ 9.r/a /r<

2?u.

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raay 20,19e REVISION 4 FORC Keeti,ng co-by /'

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Sept. 30,1966g,, m y,(. Y REVISION S i

REVISION RECORD L

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~ Revision gate Description 0

12/1/82 Initial printing. Approved by PORC 11/29/82.

Submitted for USNRC approval 12/3/82.

1 3/30/84 Change in environmental monitoring sampling locations based on 1983 land use census.

Errors in Table 4.1 corrected. Maps revised.

2 7/30/85 Addition of Intercomparison Program description to Section 4.0, Reviewed by PORC 7/30/85.

3 3/19/86' Addition of a PVS I-131 inspection limit to demonstrate compliance with Technical Specification 3.11.2.1.b.

4 5/21/86 Change in milk sampling location. Samples no longer available at Station TM-11.

S 9/30/06 Change in food product sampling location based on 1986 land use census.

l l

l Revision 5 - September 30, 1986 Approved By:

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REVISION RECORD l'

LIST OF AFFECTED PAGES Changes, deletions or additions in the most recent revision are indicated by a bar in the margin or by a dot near the page number if the entire page is affected.

PA21 Revision i to iii 5

viii 1

4-1 to 4-10 1

4-1 2

3-24 to 3-26 3

4-3, 4-9 4

4-3, 4-9, 4-10 5

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1

d Revision 5 - September 30, 1986 Approved By:

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3H(L,.J,,g pgLL3 Figure 4-2 Yankee Plant Radiological Environmental Monitoring Locations L*'

Within 12 Miles (Airborne, Waterborne and Ingestion Pathways),

Revision 5 - Septeciber 30, 1986 4-3 Approved By: ///h-.

7.;.3

O-Table 4-1 t

Radiological Environmental Monitoring Stations

k(

Distance From Direction From Exposure Pathway Sample Location I

and/or SamDie and Desionated Code +

the Plant (km) the Plant 1.

AIRBORNE (Radioiodine and Particulate)

AP/CF-11 Observation Stand 0.5 NW f

AP/CF-12 Monroe Bridge 1.1 SW AP/CF-13 Rowe School 4.2 SE AP/CF-14 Harriman Power 3.2 N

Station AP/CF-21 Williamstown 22.2 W

2.

WATERBORNE i

a.

Surface WR-11 Bear Swamp Lower 6.3 Downriver f

Reservoir WR-21 Harriman Reservoir 10.1 Upriver b.

Ground WG-11 Plant Potable On-Site Well WG-12 Sherman Spring 0.2 NW I

c.

Sediment SE-11 Number 4 Station 36.2 Downriver l

From SE-21 Harriman Reservoir 10.1 Upriver i

Shoreline 3.

INGESTION a.

Milk TM-13 Whitingham, VT B.4 ENE TM-12 Readsboro, VT 6.1 N

TM-21 Williamstown, MA 21.0 WSW b.

Fish FH-11 Sherman Pond 1.5 At Discharge Point and Inverter-FH-21 Harriman Reservoir 10.1 Upriver brates c.

Food T F-11 Monroe Bridge 1.3 SW Products TF-13 Monroe 1.9 WNW l

TF-21 Williamstown 21.0 WSW TV-11 Monroe Bridgc**

1.3 SW TF-12 Ford Hill Road ***

3.5 E

I l

l Revision 5 - September 30, 1986 Approved By: A e/-

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4-9 l

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Table 4-1 (continued)

Radiological Environmental Monitoring Stations

Exposure Pathway Sample Location Distance From Direction From and/or Sample and Desianated Code +

the Plant (km) the Plant 4.

DIRECT RADIATION GM-1 Furlan House 0.8 SW GM-2 Observation Stand 0.5 NW GM-3 Rowe School 4.2 SE GM-4 Harriman Station 3.2 N

GM-5 Monroe Bridge 1.1 SW GM-6 Readsboro Road Barrier 1.3 N

GM-7 Whitingham Line 3.5 NE GM-8 Monroe Hill Barrier 1.8 S

GM-9 Dunbar Brook 3.2 SW GM-10 Cross Road 3.5 E

GM-11 Adams High Line 2.1 WNW GM-12 Readsboro, VT 5.5 NNW GM-13 Restricted Area Fence 0.08 WSW GM-14 Restricted Area Fence 0.11 WNW GM-15 Restricted Area Fence 0.08 NNW GM-16 Restricted Area Fence 0.13 NNE GM-17 Restricted Area Fence 0.14 ENE GM-18 Restricted Area Fence 0.14 ESE GM-19 Restricted Area Fence 0.16 SE

(

GM-20 Restricted Area Fence 0.16 SSE GM-21 Restricted Area Fence 0.11 SSW GM-22 Heartwellville 12.6 NNW GM-23 Williamstown Substation 22.2 W

GM-24 Harriman Dam 7.3 N

GM-25 Whitingham 7.7 NNE GM-26 Sadoga Road 7.6 NE GM-27 Number 9 Road 7.6 ENE GM-28 Number 9 Road 6.0 E

GM-29 Route 8A 8.2 ESE GM-30 Route BA 9.4 SE GM-31 Legate Hill Road 7.6 SSE GM-32 Rowe Road 7.9 5

GM-33 Zoar Road 6.9 SSW GM-34 Fife Brook Road 6.4 SW GM-35 Whitcomb Summit 8.6 WSW GM-36 Tilda Road 6.6 W

GM-37 Turner Hill Road 6.7 WNW GM-38 West Hill Road 6.6 NW GM-39 Route 100 6.8 NNW GM-40 Readsboro Road 0.5 W

Sample locations are shown on Figures 4-1 through 4-7.

- TV-11 Station is f or leafy vegetables.

+ Station 1X's are indicator stations and Station 2X's are control stations (excluding the Direct Radiation stations).

I

(*

- - Sampics not required after October 31, 1986.

Revision 5 - September 30, 1986 Approved By: M t-r'm t

n in

m 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, 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.

H-1 2819R

o.

APPENDIX I Supplemental Information Third and Fourth Quarters 1986 1.

Technical Specification Limits - Dose and Dose Rate Technical Specification and Category Limit a.

Noble 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 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 2819R

o 2.

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

Noble Gases No MPC limits b.

Iodine-131. Tritium and Radionuclides Wo MPC limits in Particulate Form With Half-Lives Greater than 8 days c.

Liquids 3.11.1.1 Total sur of the fraction of MPC (10CFR20, Appendix B, Tables II, Column 2), excluding noble gases less than:

1.0

'f 3.11.1.1. Total noble gas concentration 2E-04 uri/ce:

3.

Measurements and Approxier3+1ons of Total Radioactivity a.

Noble Ga'ses t

" Continuous discharges" are determincd by indirect measurement.

Primary gas samples are taken periodic.mily and analyzed.

It is assumed that in primary to. secondary leak-age all gases are v'jected through the air ejector.

In' primary coolant charging pump leakage all gases are ejected to the primary vent stack either dur!ng flashing or liquid waste process!.ng. Batch discharges" i.re determit.ed 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 2819R w- -.

V

, F-J g..

(

-.g, h

{,

analysed weekly. 1The errors associated with these measurements are=

c

. estimated to be 125 percent.

f 3

QU c.

Particulates-1

' j,,

The particulh e filter described in (b) above is analyzed weekly.

The errors nasociated with~the determination of particulate effluents are estimated ~to-be !30 percent.

~-

d.

Liquid Effluents >

g

..[

Li. quid 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 analysir ts performed on a representative sounple. for each batch release using the Marinelli Beaker geometry.

t The errors associated with these measurements are as follows:

s

-fission and activation products, 220 percent; tritium, 10 percent; diss~olved fission gases, !20 percent; alpha activity, 135 percent.

\\

4.

- Batch Releas_e,s, a.

Liquids Third Quarter 3

Number of batch releases:

22 Total time period for batch releases 9,594 minutes

, Maximum time period for a batch release:

1,560 minutes

. kierage time period for batch releases: 436 minutes

' i,

, m nimum time period for a batch release 82 minutes Average stream flow during period (Sherman Dam): 587 cfs s

Average discharge rate:

14 gpm I-3 3'

2819R O'

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4

..., _,, _ _ _. _ _,. _. _ _...,,, _.. -,., _ ~,. _, _ _. -..

o:

Fourth Quarter

(

Number of batch releases:

14

'k Total" time period for batch releases:

10,235 minutes Maximum time period.for a batch release:

2,795 minutes Average time period for batch releases:

731 minutes Minimum time period for a batch release: 235 minutes 3

' Average stream flow during period (Sherman Dam):

753 cfs r Average discharge rate:

8.5 gpm y

b.

Gases

, There were no batc'h gaseous releases during the third and fourth

' quarters of 1986.

5.

Abnormal Releases a.

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

b.

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

I h

I-4 2819R

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a im 4

1 EFFLUENT AND WASTE DISPOSAL

' SEMIANNUAL REPORT FOR THIRD AND FOURTH QUARTERS, 1986 i

4 t

i i

i I

. r.

I-Yankee Atomic Electric Company Rowe, Massachusetts

' i

[.

p

s.

TABLE 1A Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters, 1986 1

Gaseous Effluents - Summation of All Releases Unit Quarter Quarter Est. Total 3

4 Error, %

A. Fission ~and Activation Cases

1. Total release ci 1.49E+02 1.13E+02 25.50E+01

2. Average release rate for period uCi/sec 1.90E+01 1.44E+01

3. Percent of Tech. Spec. limit (1)

B. Iodines

1. Total Iodine-131 Ci 1.18E-04 1.88E-06 22.50E+01 2.-Average release rate for period uCi/see 1.50E-05 2.39E-07

3. Percent of Tech. Spec. limit (2)

.C. Particulates

1. Particulates with T-1/2 > 8 days Ci 1.39E-06 4.56E-06 23.00E+01

2. Average release rate for period uCi/sec 1.77E-07 5.80E-07

3. Percent of Tech. Spec. limit (3)

(3)

4. Gross alpha radioactivity Ci 2.50E-08 1.80E-08 D. Tritium

1. Total release ci 2.88E+00 1.59E+00 m3.00E+01

2. Average release rate for period uCi/sec 3.66E-01 2.02E-01

3. Percent of Tech. Spec. limit 1

(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 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.

Percent of Technical Specification limits will be provided in the supplemental report which will include the annual dose summary. 2819R

e t

TABLE IB Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters, 1986 Gaseous Effluents - Elevated Release Continuous Mode Batch Mode (1)

Nuclides Released Unit Quarter Quarter Quarter Quarter 3

4 3

4

1. Fission Gases Krypton-85 Ci 3.93E-02 4.66E-02 Krypton-85m Ci 1.71E+00 1.39E+00 Krypton-87 Ci 1.58E+00 1.26E+00 Krypton-88 Ci 1.90E+00 2.63E+00 Xenon-133 Ci 7.38E+01 5.86E+01 Xenon-135 Ci 2.96E+01 2.21E+01 Xenon-135m Ci 3.80E+01 2.37E+01 Xenon-138 Ci 4.48E-01 6.89E-01 Xenon-133m Ci 9.25E-01 1.25E+00 Argon-37 Ci 1.68E-02 1.43E-02 Argon-41 Ci 1.03E-01 1.5 7E-01 Carbon-14 Ci 5.61E-03 6.66E-03 Xenon-131m Ci 9.06E-01 1.22E+00 Unidentified Ci Total for period Ci 1.49E+02 1.13E+02

2. Iodines Iodine-131 Ci 1.18E-04 1.88E-06 Iodine-133 Ci 2.91E-05 7.21E-06 Iodine-135 Ci

<1.44E-06

<3.64E-06 Total for period Ci 1.47E-04 9.09E-06

3. Particulates Strontium-89 Ci

<7.31E-08

<1.89E-07 Strontium-90 Ci

<9.23E-09 (4.35E-08 Cesium-134 Ci

<3.93E-07 1.11E-06 Cesium-137 Ci 4.89E-08 1.18E-06 Barium-Lanthanum-140 Ci

<1.21E-06

<2.02E-06 Zine-65 Ci

<8.97E-07

<1.37E-06 Cobalt-58 Ci 7.03E-08

<6.35E-07 Cobalt-60 Ci 1.16E-06 2.23E-06 Iron-59 Ci

<8.38E-07

<1.25E-06 Chromium-51 Ci (2.82E-06

<4.77E-06 Zirconium-Niobium-95 Ci

<7.20E-07

<1.10E-06 Cerium-141 Ci

<3.52E-07 7.95E-09 Cerium-144 Ci

<1.48E-06

<2.63E-06 Antimony-124 Ci

<3.69E-07 (6.89E-07 Manganese-54 Ci 1.07E-07 2.90E-08 Silver-110m Ci

<3.56E-07

<6.22E-07 Molybdenum-99 Ci (2.77E-06

<4.52E-07 Ruthenium-103 Ci

<3.46E-07

<5.60E-07 Total for period Ci 1.39E-06 4.56E-06 (1) There were no batch mode releases during this reporting pericd. 2819R t_

a TABLE IC i

Yankee Atom c-Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1986 Gaseous Effluents - Ground Level Releases There were no routine measured ground level continuous or batch mode gaseous releases during the third or. fourth quarters of 1986.

. 2819R

m-

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l' c.~

'[

, TABLE 2A Yankee Atomic Electric Company. Rowe Massachusetts Effluent and Waste Disposal Semiannual ~ Report m <

' Third and Fourth Quarters. 1986.

2 Liquid Effluents Summation of All Releases

~

L Unit Quarter Quarter >

Est. Total 3

4-Error. %

A. Fission and Activation Products'

1. Total release (not including tritium.' gases, alph'a)

Ci 3.66E-03 2.36E-03 c2.00E+01

12. Average diluted concentration during period uCi/ml 5.99E-11 3.81E-11"

3. Percent of applicable limit (1) 3.57E-03 1.67E-03 B. Tritium

1. Total release Ci 5.78E+01 4.12E+01 el.00E+01

2. Average diluted concentration-6.64E-07 during period

" uCi/m1' 9.46E-07

3. Percent of applicable limit (1)-

3.15E-02 2.21E-02

-C. Dissolved and Entrained Gases 1." Total release Ci 7.55E-02 1.12E-01 e2.00E+01-2.,_ Average; diluted concentration during period-uCi/ml 1.24E-09 1.81E-09

3. Percent of applicable limit (2)'

6.20E-04 9.05E-04 JD. Gross Alpha Radioactivity.

1.. Total release Ci 1.25E-06

<2.65E-06 m3.50E+01 E.-Volume of waste. released (prior to

" dilution) liters 5.04E+06 5.98E+06

' 3.00E+01 F. Volume.of dilution water used

'during period liters 6.11E+10 6.20E+10 e5.00E+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 l

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 4

i microcuries/ml (Technical Specification 3.11.1).

The percent of applicable j

limit reported is based on the average diluted concentration during the period.- At no time did any release exceed the concentration limit. l 2819R

TABLE 2B Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters, 1986 Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3

4 3

4 Strontium-89 Ci

<2.26E <2.26E <1.57E-05

<1.59E-06 Strontium-90 Ci

<3.17E-05

<5.08E-05

<2.61E-06 6.83E-07 Cesium-134 Ci 1.83E-06 2.01E-05 7.28E-04 3.62E-04 Cesium-137 Ci 1.21E 4.52E-05 7.63E-04 3.73E-04 Iodine-131 Ci 5.97E-06 1.75E-05 5.99E 2.64E-04 Cobalt-58

-Ci (1.51E-05

<2.15E-05 1.18E-06 5.09E-07 Cobalt-60 Ci 9.99E-06 1.07E-05 7.63E-05 1.16E-04 Iron-59 Ci

<3.00E-05

<3.91E-05

<1.35E-05

<8.46E-06 Zine-65 Ci

<3.09E-05

<4.26E-05

<1.65E-05

<1.19E-05 Manganese-54 Ci (1.51E-05

<1.93E-05 3.81E-05 1.12E-05 Chromium-51 Ci

<1.15E-04

<1.66E-04

<1.14E-04

<7.30E-05 Zirconium-Niobium-95 Ci

<2.55E-05

<3.42E-05

<1.54E-05

<1.07E-05 "Solybdenum-99 Ci

<1.08E-04

<1.47E-04

<6.51E-05

<4.46E-05 Technetium-99m Ci

<2.32E-05

<3.16E-05

<1.40E-05

<1.02E-05 Barium-Lanthanum-140 Ci (4.85E-05

<6.68E-05

<4.54E-05

<2.86E-05 Cerium-141 Ci

<2.00E-05

<2.86E-05

<2.19E-05

<1.67E-05

-Ruthenium-103 Ci

<1.38E-05

<1.95E-05

<1.32E-05

<8.24E-06 Cerium-144 Ci

<9.11E-05

<1.27E-04

<1.00E-04

<7.33E-05 Iodine-133 Ci

<1.39E-05

<1.96E-05 3.89E-05 2.00E-05 Selenium-75 Ci (1.61E-05

<2.29E-05

<1.64E-05

<1.08E-05 Silver-110m Ci

<1.45E-05

<1.96E-05

<1.03E-05

<6.92E-06 Antimony-124 Ci

<1.32E-05

<1.92E-05

<1.67E-05

<1.26E-05 Carbon-14 Ci 1.15E-03 9.24E-04 Iron-55 Ci

<4.25E-03

<5.65E-03 2.23E-04 1.94E-04 Cesium-136 Ci

<1.48E-05

<1.93E-05 1.29E-05 9.55E-07 Antimony-125 Ci

<4.04E-05

<5.63E-05

<4.25E-05

<2.70E-05 Unidentified Ci Total for period (above) Ci 2.99E-05 9.35E-05 3.63E-03 2.27E-03

_ Xenon-133 Ci 5.52E-04 5.34E-05 6.13E-02 1.05E-01 i-Xenon-135 Ci 2.21E-04

<1.77E-05 1.08E-04 1.85E-04 l

Xenon-131m Ci

<5.12E-04

<7.32E-04 3.51E-03 1.93E-03 Xenon-133m Ci 2.84E-04

<l.47E-04 2.30E-04 5.32E-04 Krypton-85 Ci

<4.70E-03

<6.60E-03 9.55E-03 3.11E-03 '

2819R

TABLE 3 Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters, 1986 Solid 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.ll

1. Type of Waste

a. Spent resins, filter sludges, evaporator m3 6.20E+00 bottoms, etc. - LSA container **,+

Ci 4.00E-01 23.00E+01

b. Dry compressible waste, contaminated m3 1.49E+01 equipment, etc. - LSA container ++

Ci 4.34E-01 21.00E+02

c. Irradiated compocents, control rods, md etc.

Ci 3

d. Waste oil - LSA container **,+

m 6.60E+00 Ci 1.50E-02 23.00E+01' e.

md Ci

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

a.

Iron-55

% 2.54E+01 b.

Manganese-54 % 6.30E+00 Cesium-137

% 1.71E+01 Iron-55

% 5.70E+00 Cesium-134

% 1.36E+01 Hydrogen-3

-% 5.80E+00 Hydrogen-3

% 1.02E+01 Cobalt-60

% 5.00E+00 Manganese-54 % 8.10E+00 Strontium-89 % 4.20E+00 Cobalt-60

% 6.60E+00 c.

Hydrogen-3

% 8.40E+01 Niobium-95

% 6.10E+00 Iron-55

% 5.50E+00 Strontium-89 % 4.00E+00 Chromium-51

% 1.80E+00 b.

Cesium-137

% 1.89E+01 Niobium-95

% 1.70E+00 Cesium-134

% 1.81E+01 Ruthenium-103 % 1.70E+00 Niobium-95

% 1.81E+01 Ruthenium-106 % 1.50E+00

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

Truck Barnwell, SC 1

Truck Richland, WA B. Irradiated Fuel Shipments (Disposition): None.

+ Container volume equal to 55 gallons (drums).

++ 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. 2819R

'Oh

, 9 APPENDIX A~

Radioactive Liquid Ef fl 2ent Monitoring Instrumentation Requirement: Radioactive liquid effluent' monitoring instrumentation channels are required to be opera' ale 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 be'ing 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

Technical Specification Amendment change 92 incorporated a requirement for a flow rate measuring device for the steam generator' blowdown tank effluent (Table 3.3-8).

At-the time of the change the blowdown tank effluent line did not have a flow measuring device. On June 26, 1986 at 1510 ACTION-Statement 17 of Table 3.3-8 was entered with the required flow rate being estimated from curves relating the discharge rate to the vacuum maintained.

in the discharge line. Operations Department surveillance forms have been amended to include the four-hour surveillance requirement.

An engineering evaluation was conducted to ensure the proper choice of a flow measuring device which would withstand high temperatures and potentially high solids buildup. A plant design change has been initiated for installation of the flow measuring device. Estimations of the time necessary to install and test the device indicate that blowdown would l

have to be secured (rather than rerouted) in order to preclude l

an adverse impact on waste disposal processing time.

Operable steam generator blowdown monitors are required (T.S. Table 3.3-4) in operating Modes 1 through 4.

Since the completion j.

of the engineering evaluation, the facility has not entered l

Mode 5 operation. Entrance into Mode 5 would be required in order to secure blowdown.

A-1 22819R.

.m.

.m

__-r.

APPENDIX A (Continued)

(:

The requirements of the. ACTION Statement will-be maintained' j

'.until the upcoming refueling outage when the plant design

..r>

. change will incorporate the installation of a flow measuring-device. An approximats. completion date.of June 15, 1987 is planned.

A-2

m.

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 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.

Re'sponse:

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.

B-1

- 2819R

APPENDIX C Liquid Holdup Tanks'-

Requirement: 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 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.

C-1 2819R t

3 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 orLfresh 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 locatica(s) for obtaining replacement sample (s) in the next Semiannual Effluent Release Report and inclusion of revised 0ff-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.

D-1 2819R

.: 7y.

a APPENDIX E y

Land Use Census t

~ Requirement: A land use census is conducted in accordance with Te'chnical I

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 any locations yielding at least a 20 percent greater. dose or l

dose commitment than the values currently being calculated in Technical Specification 4.11.2.3.

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.

Response

The land use census for this reporting period identified two milk animal locations which yielded a calculsted 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.

Specifically, such milk-animal locations were found at WNW, 1.9 km and NE, 3.7 km.

Neither location, however, would be able to provide E-1 2819R

APPENDIX E (Continued) samples of sufficient size over an extended period due to the small number of milking cows owned. Consequently, the two existing locations, TM-12 and TM-13, were kept as official sampling-locations.

With respect to food crop _ sampling locations, Station TF-13, Monroe, was added to the program based on the above dosimetric criterion. Station TF-12, Ford Hill Road, was deleted from the program following October 31, 1986, pursuant to Technical Specification 3.12.2.b.

E-2 2819R

APPENDIX F 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 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.

t Y-F-1 2819R

- ~,

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

Revision 5 of the ODCM included land use census-initiated changes in Section 4.0.

Specifically, food crop sampling Location TF-13 was added to Table 4-1, and a footnote to Table 4-1 was added to allow Location TF-12 to be discontinued after October 31, 1986. Figure 4-2 (map) was changed to reflect the addition of Location TF-13.

Several clerical errors in Section 4.0 from Revision 4 were corrected with Change No. 6.

Specifically, they were:

(1) in Table 4-1, food crop sampling Location TF-12 was incorrectly listed as Harriman Station, 3.2 km, N, and was changed to Ford Hill Road, 3.5 km, E; (2) air sampling Location AP/CF-13 was changed from SSE to SE; and (3) food crop and broadleaf vegetation Locations TF-11 and TV-11 were changed from 1.1 km to 1.3 km.

Additionally, the revision date for Revision 1 was changed from March 30, 1983 to March 30, 1984.

The revised pages of the ODCM are given in the six attached pages.

G-1 2819R

r.

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(.

l YANKEE NUCLEAR POWER STATION

. OFF-SITE DOSE CALCULATION MANUAL YANKEE ATOMIC ELECTRIC COMPANY NUCLEAR SERVICES DIVISION 1671 WORCESTER ROAD FRAMINGHAM, MASSACHUSETTS 01701.

's PREPARED BY/DATE REVIEED BY/IRTE APPROW.D Andrew D. Hodgdon 12/2/82 PbRC 11/29/82 ORIGINAL William D. Billings 12/2/82 EMI O=- -L 2/u/rr

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,J/gfyf2/f>7 REVISION 1 f

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. REVISION 3

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'!I' REVISION 5

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REVISION RECORD

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-Revision Date Description 0

12/1/82 Initial printing.

Approved by PORC 11/29/82.

Submitted for USNRC approval 12/3/82.

1 3/30/84 Change in environmental monitoring sampling locations based on 1983 land use census.

Errors in Table 4.1 corrected. Maps revised.

2 7/30/85 Addition of Intercomparison Program description to Section 4.0.

Reviewed by PORC 7/30/85.

3 3/19/86 Addition of a PVS I-131 inspection limit to demonstrate compliance with Technical Specification 3.11. 2.1. b.

4 5/21/86 Change in milk sampling location. Samples no lor.jer available at Station TM-11.

5 9/30/86 Change in food product sampling location based on 1986 land use census.

,l'edill/

/!

EEm Revision 5 - September 30, 1986 Approved By:

(.

-ii-

~

~-

-REVISION RECORD LIST OF AFFECTED PAGES l

Changes, deletions or additions in the most recent revision are indicated by a bar_in the margin or by a dot near the page number if the entire page is

affected.

Pace Revision i'to iii 5

viii 1

4-1 to 4-10 1

4-l '

2 3-24 to 3-26 3

4-3, 4-9 4

4-3, 4-9, 4-10 5

(

I.

-iii-

,~

N Y

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_~_

-- :=

=-

__~_

Karruen RutAvon HEARTWELLVILLE

.=:=

--~

~ FH-21

'kiWHITINGHAM TM-12 @ EADSBORO i

R e

@ nt-13 WR-21 @ AP/CF-14 Sherman Pond vEucni I

t TF-13 @l q~ l mas 5ACHUSETTS l

HONROE 8RI E SSg gngtsst, IN FIGURE 4-1 g

PLANT l L__i 5m hp lower Rucrvou

@ AP/0F-13 I

e ROWE l

hi-11

HEATH Ctg.'4 4et CHARLEMONT s

i t

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'SE-11 KILOMETERS I

SHELEURNE FALL $,

l Figure 4-2 Yankee Plant Radiological Environmental Monitoring Locations Within 12 Miles (Airborne, Waterborne and Ingestion Pathways).

Approved By: //fh Lon l

Revision 5 - September 30, 1986 4-3 e.

n

-.-.....-,-v.

v, Table 4-1 Radiological Environmental Monitoring Stations *

(

Exposure Pathway-Sample Location Distance From Direction From and/or Sample and Designated Code +

the Plant (km) the Plant 1.

AIRBORNE (Radioiodine and Particulate)

AP/CF-11 Observation Stand 0.5 NW AP/CF-12 Monroe Bridge 1.1 SW AP/CF-13 Rowe School 4.2 SE AP/CF-14 Harriman Power 3.2 N

Station AP/CF-21 Williamstown 22.2 W

2.

WATERBORNE a.

Surface WR-11 Bear Swamp Lower 6.3 Downriver Reservoir WR-21 Harriman Reservoir 10.1 Upriver b.

Ground WG-11 Plant Potable On-Site Well WG-12 Sherman Spring 0.2 NW c.

Sediment SE-ll Number 4 Station 36.2 Downriver From SE-21 Harriman Reservoir 10.1 Upriver i

Shoreline 3.

INGEhTION a.

Milk TM-13 Whitingham, VT 8.4 ENE TM-12 Readsboro, VT 6.1 N

TM-21 Williamstown, MA 21.0 WSW b.

Fish FH-11 Sherman Pond 1.5 At Discharge Point and Inverter-FH-21 Harriman Reservoir 10.1 Upriver brates c.

Food TF-ll Monroe Bridge 1.3 SW Products TF-13 Monroe 1.9 WNW l

TF-21 Williamstown 21.0 WSW TV-11 Monroe Bridge **

1.3 SW TF-12 Ford Hill Road ***

3.5 E

l

/

~).

Revision 5 - September 30, 1986 Approved By: _fp /-

.//e4m m k.

4-9

,y

.v.

Table 4-1 (continued)

Radiological Environmental. Monitoring Stations

Exposure Pathway Sample Location Distance From Direction From and/or Sample and Desianated Code +

the Plant (km) the Plant

'4.

DIRECT RADIATION GM-1 Furlon House 0.8 SW GM-2 Observation Stand 0.5 NW GM-3 Rowe School 4.2 SE GM-4 Harriman Station 3.2 N

GM-5 Monroe Bridge 1.1 SW GM-6 Readsboro Road Barrier 1.3 N

GM-7 Whitingham Line 3.5 NE GM-8 Monroe Hill Barrier 1.8 S

GM-9 Dunbar Brook 3.2 SW GM-10 Cross Road 3.5 E

GM-ll Adams High Line 2.1 WNW GM-12 Readsboro, VT 5.5 NNW GM-13 Restricted Area Fence 0.08 WSW GM-14 Restricted Area Fence 0.11 WNW GM-15 Restricted Area Fence 0.08 NNW GM-16 Restricted Area Fence 0.13 NNE GM-17 Restricted Area Fence 0.14 ENE

' GM-18 Restricted Area Fence 0.14 ESE GM-19 Restricted Area Fence 0.16 SE k

GM-20 Restricted Area Fence 0.16 SSE GM-21 Restricted Area Fence 0.11 SSW GM-22 Heartwellville 12.6 NNW GM-23 Williamstown Substation 22.2 W

GM-24 Harriman Dam 7.3 N

GM-25 Whitingham 7.7 NNE GM-26 Sadoga Road 7.6 NE GM-27 Number 9 Road 7.6 ENE GM-28 Number 9 Road 6.0 E

GM-29 Route 8A 8.2 ESE GM-30 Route 8A 9.4 SE GM-31 Legate Hill Road 7.6 SSE GM-32 Rowe Road 7.9 S

GM-33 Zoar Road 6.9 SSW GM-34 Fife Brook Road 6.4 SW GM-35 Whitcomb Summit 8.6 WSW GM-36 Tilda Road 6.6 W

GM-37 Turner Hill Road 6.7 WNW GM-38 West Hill Road 6.6 NW GM-39 Route 100 6.8 NNW GM-40 Readsboro Road 0.5 W

Sample locations are shown on Figures 4-1 through 4-7.

- TV-ll Station is f or leaf y vegetables.

+ Station 1X's are indicator stations and Station 2X's are control stations (excluding the Direct Radiation stations).

l

(*

- - Samples not required after October 31, 1986.

s Revision 5 - September 30, 1986 Approved By: M m2 L

,,n

s 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.

H-1 2819R

"7Mf a

1

't APPENDIX I Supplemental Information Third and Fourth Quarters, 1986

'1.

Technical Specification Limits'- Dose and Dose Rate Technical Specification and Category Limit a.

Noble 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 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 2819R l

6 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 2819R

m

~

--a.

lll.

Q :l y;

a w,-

c L

analyzed weekly. The errors associated with'these measurements are estimated;to be 125,. percent.

A.

c.

Particulates-The particularI filter described in (b) ab ve is analyzed weekly.

The errors associated with the determination of particulate' effluents are estimated to.be 30 percent.

l

'd.

Liquid Effluents a) iU Liquid effluents are determined by direct measurement.

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

Fer continuous (discharges composite samples are used for ganvaa isotopic 3

analysis.n AgammaisotopicanaYysisisperformedon'arepresentative sample for each batch release using the.Marinelli Beaker. geometry.

The errors asstciatEd with these measurcents are as foll'ows:

fission and activation products, 20 percent; tritium, 10 percent; dissolved fission gases, 20 percent; alpha actiivity, 135 percent.-

/

4.

Batch Releases a.

Liquids

\\

Third Quarter Number of batch releases:

22 Total time period for batch releases:

9,594 minutes Maximum time period for a batch rel. ease: 1,560 minutes Average time period for batch releases: 436 minutes Minimum time period for a batch release: 82 minutes Average stream flow during period (Sherman Dam): 587 cfs Average discharge rate:

14 gpm I-3 2819R e

m.

+ -. - - - -.

,.,-3 n

..,-g-..

.,-p.

.-,.,y-

-~

g

,a vl i-

-x

~;; r Fourth Quarter-Number of batch rhleases:- 14.

Total time period for batch releases:

10,235 minutes Maximum time period for a batch release:

2,795 minutes Average-' time period for batch releases:

731' minutes s

N.

s

.+-.a Minimum time period for a batch release:

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

753 cfs

. Average discharge rate:

8.5 gpm a

b.

Gases

~\\

hnerewere'nobatchgaseousreleasesduringthethirdandfourth if quarters of 1986.

f-5.

Abnormal-Releases e

a.

Li ould's

-\\

~ There were no nonroutine liquid releases during the reporting period.

v.,

b.

Gases -

4-There were no nonroutine gaseous releases during the. reporting period.

y 4

1 s

I-4 2819R i

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EFFLUENT AND UASTE DISPOSAL-

- SEMIANNUAL REPORT' s

s I

FOR

+.

4 1

- I; THIRD'AND FOURTH' QUARTERS,.1986 i't.

i -

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I O!

Yankee Atomic Electric Company Rowe, Massachusetts c

/

A f:r' A

t-

-.+.rw g# e

-e*

.x v n-r-m.,--.--4 my..y

.--..,.-4.,w.,9.,

y

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y#.r-4

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---+,-,--r

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ev-,

-, = - -. - - -. - - -

v=

o TABLE 1A Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Peport Third and Fourth Quarters, 1986 Gaseous Effluents - Summation of All Releases Unit Quarter Quarter Est. Total 3

4 Error, %

A. Fission and Activation Gases

1. Total release Ci 1.49E+02 1.13E+02 25.50E+01

2. Average release rate for period uCi/see 1.90E+01 1.44E+01

3. Percent of Tech. Spec. limit (1)

B. Iodines

1. Total Iodine-131-Ci 1.18E-04 1.88E-06 e2.50E+01

2. Average release rate for period uCi/see 1.50E-05 2.39E-07

3. Percent of Tech. Spec. ligi_t (2)

C. Particulates

1. Particulates with T-1/2 > 8 days Ci 1.39E-06 4.56E-06 23.00E+01

2. Average release rate for period uCi/see 1.77E-07

-5.80E-07

3. Percent of Tech. Spec. limit (3)

(3)

4. Gross alpha rrdioactivity Ci 2.50E-08 1.80E-08 D. Tritium

1. Total release Ci 2.88E+00 1.59E+00 e3.00E+01

2. Average release rate for period uCi/sec 3.66E-01 2.02E-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 I-131, Tritium, and radioauclides 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.

Percent of Technical Specification limits will be provided in the supplemental report which will include the annual dose summary. 2819R

TABLE IB

-Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters, 1986 Gaseous Effluents - Elevated Release Continuous Mode Batch Mode (1)

Nuclides Released Unit Quarter Quarter Quarter.

Quarter 3

4 3

4

{

1. Fission Gases Krypton-85 Ci 3.93E-02 4.66E-02 Krypton-85m Ci 1.71E+00 1.39E+00 Krypton-87 Ci 1.58E+00 1.26E+00 Krypton-88 Ci 1.90E+00 2.63E+00 Xenon-133 Ci 7.38E+01 5.86E+01 Xenon-135 Ci 2.96E+01 2.21E+01 Xenon-135m Ci 3.80E+01 2.37E+01 Xenon-138 Ci 4.48E-01 6.89E-01 Xenon-133m Ci 9.25E-01 1.25E+00 Argon-37 Ci 1.68E-02 1.43E-02 Argon-41 Ci 1.03E-01 1.57E-01 Carbon-14 Ci 5.61E-03 6.66E-03 Xenon-131m Ci 9.06E-01 1.22E+00 Unidentified Ci Total for period Ci 1.49E+02 1.13E+02

2. Iodines Iodine-131 Ci 1.18E-04 1.88E-06 Iodine-133 Ci 2.91E-05 7.21E-06 Iodine-135 Ci

<1.44E-06

<3.64E-06 Total for period Ci 1.47E-04 9.09E-06

3. Particulates Strontium-89 Ci (7.31E-08

<1.89E-07 Strontium-90 Ci

<9.23E-09

<4.35E-08 Cesium-134 Ci

<3.93E-07 1.11E-06 Cesium-137 Ci 4.89E-08 1.18E-06 Barium-Lanthanum-140 Ci

<1.21E-06

<2.02E-06 Zine-65 Ci

<8.97E-07

<1.37E-06 Cobalt-58 Ci 7.03E-08

<6.35E-07 Cobalt-60 Ci 1.16E-06 2.23E-06 Iron-59 Ci

<8.38E-07

<1.25E-06 Chromium-51 Ci (2.82E-06

<4.77E-06 Zirconium-Niobium-95 Ci

<7.20E-07

<1.10E-06 Cerium-141 Ci

<3.52E-07 7.95E-09 Cerium-144 Ci

<1.48E-06 (2.63E-06 Antimony-124 Ci (3.69E-07 (6.89E-07 Manganese-54 Ci 1.07E-07 2.90E-08 Silver-110m Ci

<3.56E-07

<6.22E-07 Molybdenum-99 Ci

<2.77E-06 (4. 5 2E-07 Ruthenium-103 Ci

<3.46E-07

<5.60E-07 Total for period Ci 1.39E-06 4.56E-06 (1) There were no batch mode releases during this reporting period. 2819R

u;- -

e n,.

s.

s TABLE IC Yankee Atomic Electric Company. Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1986 Gaseous Effluents-- Ground Level Releases There were no routine -measured ground level continuous or batch mode gaseous releases during the third or fourth quarters of 1986.

. 2819R

. -;(

.s:

^

TABLE 2A Yankee Atomic Electric ~ Company. Rowe, Massachusetts Effluent and Waste Disposal-Semiannual Report

. Third and Fourth-Quarters 1986 Liquid Effluents - Summation of All Releases Unit Quarter Quarter Est. Total.

3 4

Error. %

~A. Fission and Activation Products 1.. Total release (not-including tritium,' gases, alpha)

Ci-3.66E-03 2.36E-03 22.00E+01'

2. Average diluted concentration during period uCi/mi

'5.99E-11 3.81E-11 3.-Percent of applicable limit (1) 3.57E-03 1.67E-03 B.~ Tritium

1. Total release Ci 5.78E+01 4.12E+01 21.00E+01-

2. Average diluted concentration during period uCi/ml 9.46 E -07 6.64E-07

^

3. Percent of applicable limit (1) 3.15E-02 2.21E-02

~C. Dissolved and Entrained Cases

1. Total release Ci 7.55E-02 1.12E-01 22.00E+01

2. Average diluted concentration during period uCi/ml 1.24E-09 1.81E-09

3. Percent of applicable limit (2) 6.20E-04 9.05E-04 D. Gross Alpha Radioactivity

1. Total release Ci 1.25E-06

<2.65E-06 23.50E+01 E. Volume of waste. released (prior to dilution) liters 5.04E+06 5.98E+06 m3.00E+01 F. Volume of dilution water used during period liters 6.11E+10 6.20E+10 e5.00E+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 applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit. 2819R

o TABLE 2B Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters, 1986 Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3

4 3

4 Strontium-89 Ci

<2.26E-04

<1.57E-05

<1.59E-06 Strontium-90 Ci

<3.17E-05

<5.08E-05

<2.61E-06 6.83E-07 Cesium-134 Ci 1.83E-06 2.01E-05 7.28E-04 3.62E-04 Cesium-137 Ci 1.21E-05 4.52E-05 7.63E-04 3.73E-04 Iodine-131 Ci 5.97E-06 1.75E-05 5.99E-04 2.64E-04 Cobalt-58 Ci (1.51E-05

<2.15E-05 1.18E-06 5.09E-07 Cobalt-60 Ci 9.99E-06 1.07E-05 7.63E-05 1.16E-04 Iron-59 Ci

<3.00E-05

<3.91E-05

<1.35E-05

<8.46E-06 Zine-65 Ci

<3.09E-05

<4.26E-05

<1.65E-05

<1.19E-05 Manganese-54 Ci

<1.51E-05

<1.93E-05 3.81E-05 1.12E-05 Chromium-51 Ci

<1.15E-04 (1.66E-04

<1.14E-04

<7.30E-05 Zirconium-Niobium-95 Ci (2.55E-05

<3.42E-05

<1.54E-05

<1.07E-05 Molybdenum-99 Ci

<1.08E-04

<1.47E-04

<6.51E-05

<4.46E-05 Technetium-99m Ci

<2.32E-05

<3.16E-05

<1.40E-05

<1.02E-05 Barium-Lanthanum-140 Ci

<4.85E-05

<6.68E-05

<4.54E-05

<2.86E-05 Cerium-141 Ci (2.00E-05

<2.86E-05

<2.19E-05

<1.67E-05 Ruthenium-103 Ci

<1.38E-05

<1.95E-05

<1.32E-05 (8.24E-06 Cerium-144 Ci

<9.11E-05

<1.27E-04

<1.00E-04

<7.33E-05 Iodine-133 Ci

<1.39E-05

<1.96E-05 3.89E-05 2.00E-05 Selenium-75 Ci

<1.61E-05

<2.29E-05

<1.64E-05

<1.08E-05 Silver-110m Ci

<1.45E-05

<1.96E-05

<1.03E-05

<6.92E-06 Antimony-124 Ci

<1.32E-05

<1.92E-05

<1.67E-05

<1.26E-05 Carbon-14 Ci 1.15E-03 9.24E-04 Iron-55 Ci

<4.25E-03

<5.65E-03 2.23E-04 1.94E-04 Cesium-136 Ci

<1.48E-05

<1.93E-05 1.29E-05 9.55E-07 Antimony-125 Ci

<4.04E-05

<5.63E-05

<4.25E-05

<2.70E-05 Unidentified Ci Total for period (above) Ci 2.99E-05 9.35E-05 3.63E-03 2.27E-03 Xenon-133 Ci 5.52E-04 5.34E-05 6.13E-02 1.05E-01 Xenon-135 Ci 2.21E-04

<1.77E-05 1.08E-04 1.85E-04 Xenon-131m Ci

<5.12E-04

<7.32E-04 3.51E-03 1.93E-03 Xenon-133m Ci 2.84E-04

<1.47E-04 2.30E-04 5.32E-04 Krypton-85 Ci

<4.70E-03 (6.60E-03 9.55E-03 3.11E-03 2819R

p f-~ _

TABLE 3 Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters, 1986 Solid 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. Type of Waste

a. Spent resins, filter sludges, evaporator m3 6.20E+00 bottoms, etc. - LSA container **,+

Ci 4.00E-01 m3.00E+01

b. Dry compressible waste, contaminated m4 1.49E+01 equipment, etc. - LSA container ++

Ci 4.34E-01

-e1.00E+02

-c.

Irradiated components, control rods, md n

etc.

Ci

d. Waste oil - LSA container **,+

m3 6.60E+00 Ci 1.50E-02 m3.00E+01 e.

m3 Ci

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

a.

Iron-55

% 2.54E+01 b.

Manganese-54 % 6.30E+00 Cesium-137

% 1.71E+01 Iron-55

% 5.70E+00 Cesium-134

% 1.36E+01 Hydrogen-3

% 5.80E+00 Hydrogen-3

% 1.02E+01 Cobalt-60

% 5.00E+00 Manganese-54 % 8.10E+00 Strontium-89 % 4.20E+00 Cobalt-60

% 6.60E+00 c.

Hydrogen-3

% 8.40E+01 Niobium-95

% 6.10E+00 Iron-55

% 5.50E+00 Strontium-89 % 4.00E+00 Chromium-51

% 1.80E+00 b.

Cesium-137

% 1.89E+01 Niob'Ium-95

% 1.70E100 Cesium-134

% 1.81E+01 Ruthenium-103 % 1.70E+00 Niobium-95

% 1.81E+01 Ruthenium-106 % 1.50E+00

3. Solid Waste Disposition

_ Number of Shipments Mode of Transportation Destination 1

Truck Barnwell, SC 1

Truck Richland, WA B. Irradiated Fuel Shipments (Disposition): None.

+ Cortainer volume equal to 55 gallons (drums).

++ 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. 2819R 1

r-e

w 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.

Response

Technical Specification Amendment change 92 incorporated a requirement for a flow rate measuring device for the steam generator blowdown tank effluent (Table 3.3-8).

At the time of the change the blowdown tank effluent line did not have a flow measuring device. On June 26, 1986 at 1510 ACTION Statement 17 of Table 3.3-8 was entered with the required flow rate being estimated from curves relating the discharge rate to the vacuum maintained in the discharge line. Operations Department surveillance forms have been amended to include the four-hour surveillance requirement.

An engineering evaluation was conducted to ensure the proper choice of a flow measuring device which would withstand high temperatures and potentially high solids buildup. A plant design change has been initiated for installation of the j

flow measuring device. Estimatior.s of the time necessary to install and test the device indicate that blowdown would

[

have to be secured (rather than rerouted) in order to preclude I

an adverse impact on waste disposal processing time.

Operable l

steam generator blowdown monitors are required (T.S. Table 3.3-4) in operating Modes 1 through 4.

Since the completion l

of the engineering evaluation, the facility has not entered Mode 5 operation. Entrance into Mode 5 would be required in order to secure blowdown.

l l

A-1 2819R l

APPENDIX A (Continued)

The requirements of until the upcoming refuelingthe ACTION Statement will b e maintained change will incorporate the i outage when the plant design device.

An approximate nstallation of a flow measuri completion date ng planned.

of June 15,1987 is I

i A-2 8

t.-

APPENDIX A'(Continued) s.

.Th'e requirements of the ACTION Statement will'be maintained until the upcoming' refueling' outage when the plant design-

-change.will incorporate-the installation of a flow measuring device. An approximate completion date of June 15, 1987 is planned.

A-2 l

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e t i.

APPENDIX'B '

-Radioactive Gaseous Effluent Monitor'ing 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 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.

B-1 2819R

>: 2 APPENDIX C Liquid Holdup Tanks Requirement: 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 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.

C-1 2819R

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 3.4.12.1.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

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

D-1 2819R

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 land use census for this reporting period did not identify

[

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.

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.

Response

The land use census for this reporting period identified two milk animal locations which yielded a calculated 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.

Specifically, such milk animal locations were found at WNW, 1.9 km and NE, 3.7 km.

Neither location, however, would be able to provide E-1 2819R 8

APPENDIX E (Continued) samples of sufficient size over an extended period due to the small number of milking cows owned. Consequently, the two existing locations, TM-12 and'TM-13, were kept as official sampling locations.

With respect to food crop sampling locations, Station TF-13, Monroe, was added to the program based on the above dosimetric criterion. Station TF-12, Ford Hill Road, was deleted from the

-program following October 31, 1986, pursuant to Technical Specification 3.12.2.b.

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-APPENDIX F 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-

~

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.

F-1 2819R

'h-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

Revision 5 of the ODCM included land use census-initiated changes in Section 4.0.

Specifically, food crop sampling Location TF-13 was added to Table 4-1, and a footnote to Table 4-1 was added to allow Location TF-12 to be discontinued after October 31, 1986. Figure 4-2 (map) was changed to reflect the addition of Location TF-13.

Several clerical errors in Section 4.0 from Revision 4 were corrected with Change No. 6.

Specifically, they were:

(1) in Table 4-1, food crop sampling Location TF-12 was incorrectly listed as Harriman Station, 3.2 km, N, and was changed to Ford Hill Road, 3.5 km. E; (2) air sampling Location AP/CF-13 was changed from SSE to SE; and (3) food crop and broadleaf vegetation Locations TF-11 and TV-11 were changed from 1.1 km to 1.3 km.

Additionally, the revision date for Revision 1 was changed from March 30, 1983 to March 30, 1984.

The revised pages of the ODCM are given in the six attached pages.

I G-1 2819R

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YANKEE NUCLEAR POWER STATION OFF-SITE DOSE CALCULATION MANUAL YANKEE ATOMIC ELECTRIC COMPANY NUCLEAR SERVICES DIVISION 1671 WORCESTER ROAD FRAMINGHAM, MASSACHUSETTS 01701 j

PREPARED BY/DATE REVIEED BY/Dmi APPROVED l

^"dT'"

H dEd " I//

PORC 11/29/82 ORIGINAL l

William D. Billings 12/2/82

[ & f $ --- f

'hY 3h 0*N sf/Akk7fD REvlS10N 1 March 30s /9f'/

REVISION 2 Lc-M [ 6 rh[s ORC Me g., f 0

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a FORC Ideetin co-c E u a l 4 C -

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May 20, 198..

REVISION 4

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REVISION 5 ScGwdA,,(m,-.w.

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Sept. 30, 19564,n n [, 7 i

REVISION RECORD

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Revision Date Description

~~

0 12/1/82 Initial printing. Approved by PORC 11/29/82.

Submitted for USNRC approval 12/3/82.

1 3/30/84 Change in environmental monitoring sampling locations' based on 1983 land use census.

Errors in Table 4.1 corrected. Maps revised.

2 7/30/85 Addition of Intercomparison Pr no description to Section 4.0.

Reviewed by PORC,a0/85.

3 3/19/86 Addition of a PVS I-131 inspection limit to demonstrate compliance with Technical Specification 3.11. 2.1. b.

4 5/21 /86 Change in milk sampling location. Samples no longer available at Station TM-11.

5 9/30/86 Change in food product sampling location based on 1986 land use census.

Revision 5 - September 30, 1986 Approved By:

. '/ ' < - i u -.s

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=

' 4 REVISION RECORD LIST OF AFFECTED PAGES ii indicated by a Changes, deletions or additions in the most recent rev s on are bar in the margin or by a dot near the page number if the entire page is affected.

Pjule Revision i to iii 5

viii 1

4-1 to 4-10 1 1 2

3-24 to 3-26 3

4-3, 4-9 4

4-3, 4-9, 4-10 5

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Revision 5 - September 30, 1986 Approved By:

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- FH-21

WHITINGHAM TM-12 @READSBORO U

@ Tu-13 WR-21 @ AP/CF-14 Shvunan Pond 3

E VERMONT

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I NONROE BRIDGE '

I SEE E#tARCENEli? JN FIC!lRE 4-1 PLANT I L____1 ScML Sep lower Rucrvoia !

@ AP/CF-13 I

ROWE WR-11

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'5E-11 KILOMETERS l

SHELBURNE FALLS,l r

i Figure 4-2 Yankee Plant Radiological Environmental Monitoring Locations Within 12 Miles (Airborne, Waterborne and Ingestion Pathways),

Approved By: //'fY T. on Revision 5 - September 30, 1986 4-3 l

l

7-J di,'

u; Table 4-1 Radiological Environmental Monitoring Stations *

. t; Exposure Pathway 1

. Sample Location Distance From Direction From and/or Sample and Designated Code +

the Plant (km) the Plant

~

1.

AIRBORNE (Radioiodine and Particulate)-

AP/CF-11 Observation Stand' O.5-NW AP/CF-12. Monroe Bridge 1.1 SW AP/CF-13 Rowe School 4.2 SE AP/CF-14 Harriman Power-3.2 N

Station AP/CF-21 Williamstown 22.2 W

2.

WATERBORNE a.

Surface 'WR-11 Bear Swamp Lower 6.3 Downriver Reservoir WR-21 Harriman Reservoir 10.1 Upriver b.

Ground WG-11 Plant Potable On-Site Well WG-12 Sherman Spring 0.2 NW c.

Sediment SE-11 Number 4 Station 36.2-Downriver From SE-21 Harriman Reservoir 10.1 Upriver Shoreline 3.

INGESTION a.

Milk TM-13 Whitingham, VT B.4 ENE TM-12 Readsboro, VT 6.1 N

TM-21 Williamstown, MA 21.0 WSW b.

Fish FH-11 Sherman Pond 1.5 At Discharge Point and Inverter-FH-21 Harriman Reservoir 10.1 Upriver brates c.

Food TF-11 Monroe Bridge 1.3 SW Products TF-13 Monroe 1.9 WNW l

TF-21 Williamstown 21.0 WSW TV-11 Monroe Bridge **

1.3 SW TF-12 Ford' Hill Road ***

3.5 E

I Revision 5 - September 30, 1986 Approved By: g M t

4-9

7 Table 4-1 (continued)

Radiological Environmental Monitoring Stations

Exposure Pathway Sample Location Distance From Direction From and/or Sample and Desianated Code +

the Plant (km) the Plant 4.

DIRECT RADIATION GM-1 Furlon House 0.8 SW GM-2 Observation Stand 0.5 NW GM-3 Rowe School 4.2 SE GM-4 Harriman Station 3.2 N

GM-5 Monroe Bridge 1.1 SW GM-6 Readsboro Road Barrier 1.3 N

GM-7 Whitingham Line 3.5 NE GM-8 Monroe Hill Barrier 1.8 S

GM-9 Dunbar Brook 3.2 SW GM-10 Cross Road 3.5 E

GM-11 Adams High Line 2.1 WNW GM-12 Readsboro, VT 5.5 NNW GM-13 Restricted Area Fence 0.08 WSW GM-14 Restricted Area Fence 0.11 WNW GM-15 Restricted Area Fence 0.08 NNW GM-16 Restricted Area Fence 0.13 NNE GM-17 Restricted Area Fence 0.14 ENE GM-18 Restricted Area Fence 0.14 ESE GM-19 Restricted Area Fence 0.16 SE k

GM-20 Restricted Area Fence 0.16 SSE GM-21 Restricted Area Fence 0.11 SSW GM-22 Heartwellville 12.6 NNW GM-23 Williamstown Substation 22.2 W

GM-24 Harriman Dam 7.3 N

GM-25 Whitingham 7.7 NNE GM-26 Sadoga Road 7.6 NE GM-27 Number 9 Road 7.6 ENE GM-28 Number 9 Road 6.0 E

GM-29 Route 8A 8.2 ESE GM-30 Route BA 9.4 SE GM-31 Legate Hill Road 7.6 SSE GM-32 Rowe Road 7.9 S

GM-33 Zoar Road 6.9 SSW GM-34 Fife Brook Road 6.4 SW GM-35 Whitcomb Summit 8.6 WSW GM-36 Tilda Road 6.6 W

GM-37 Turner Hill Road 6.7 WNW GM-38 West Hill Road 6.6 NW GM-39 Route 100 6.8 NNW GM-40 Readsboro Road 0.5 W

Sample locations are shown on Figures 4-1 through 4-7.

- TV-11 Station is f or leafy vegetables.

+ Station 1X's are indicator stations and Station 2X's are control stations (excluding the Direct Radiation stations).

I

(*

- - Samples not required after October 31, 1986.

Revision 5 - September 30, 1986 Approved By: ['

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7 t-

o 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, 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.

H-1 2819R

APPENDIX I Supplemental Information Third and Fourth Quarters, 1986 1.

Technical Specification Limits - Dose and Dose Rate Technical Specification and Category Limit a.

Noble 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 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 2819R

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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 2819R

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analysed weekly. The errors < associated with these measurements are estimated to be 12{percen..

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c..Particulates.

- The' particulat$ filter described = in (b) above is analyzed weekly.

The errori associated with the determination of particulate effluents are estimated to be 30 percent.

4 d.

Liquid Effluents

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v Liquid effluents are determined by'direc.t measurement.- In line 1

(<t' y

composite samples are analyzed for strontium-89, strontium-90, iron-55, gross alpha activity and carbon-14 There is no compos!. ting If

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of samples for tritium or dissolved fission gas analysis.

For '

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continuous discharges composite samples are used for gamma isciopici '

1 analysis. Agammaisotopicanalysisisperformedonarepresentapve-

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sample for each batch. release using the Marinelli Beaker geometry.'

The errors associated with these measurementr'are Ls (f ollows:

a fission and activation products,120 perceni;; tritium, 10 percent; dissolved fission gases, 20 percent; alpha activity, ! 5 percent.

3

)

'4.

Batch Releases i

1 a.

Liquids q'

i Third Quarter L

s' Number of batch releases:

22 Total' time period for batch releases:

9,594 minutes

(.

Maximum time period for a batch release:

1,560 minutes Average time period for batch releases: 436 minutes Minimum time period for a batch release: 82 minutes l

~

Average stream flow during period (Sherman Dem): 587 cis Average discharge rater 14 gpm 1

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Number.of tatch releases:

14

' Total time period for batch releases:

10,235 minutes Maximum time period for a batch release:

2,795 minutes Average time period for batch releases:

731 minutes Minimum time period for a batch release: 235 minutes Average etream flow during period (Sherman Dam):

753 cfs c

Average discharge rate:

8.5 gpm

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b.

Gases t g There were no b'atch gaseous releases during the third and fourth quarters of'1985.

^

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Abnormal Releases

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a.

Liquid s

There were no nonroutine liquid releases during the reporting period.

b.

Gases i

There were no nonroutine gaseous releases during the reporting period.

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YANKEE ATOMIC ELECTRlC COMPANY T:pho"' (* ") * ' ** '

TWX 710 380 7619

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1671 Worcester Road, Fram:ngham, Massachusetts 01701 2.C2.01

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February 26, 1987 FYR 87-21 y,,

United States Nuclear Regulatory Commission Region I 3

631 Park Avenue King of Prussia, PA 19406 Attention:

Dr. Thomas E. Murley Regional Administrator

Reference:

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

Subject:

Semiannual Ef fluent Release Report

Dear Sir:

Enclosed please find three copies of 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 1986 submitted in accordance with Technical Specification 6.9.5.b.l.

The summary of the estimates of off-site radiation doses resulting from plant effluents l

during 1986 will be provided in a supplemental report in accordance with l

Technical Specification 6.9.5.b.2.

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

Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY I

l George spanic, Jt'.

Senior Project Engineer - Licensing Yankee Project

'GP/dlb

'gnclosures a

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- _ _ _ _ _ - _ _

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