Text

Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters,1987,Including Annual Radiological Impact on Man
	ML20148M723
Person / Time
Site:	Yankee Rowe
Issue date:	12/31/1987
From:	Papanic G; YANKEE ATOMIC ELECTRIC CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	FYR-88-41, NUDOCS 8804060101
	Download: ML20148M723 (41)
	v • d • e

,

t Tchiphon2 (617) 872 8100 4

TWX 110-3&%7619 YANKEE ATOMIC ELECTRIC COMPANY 1671 Worcester Road, Framingham, Massachusetts 01701

^

March 29, 1988 FYR 88-41 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

References:

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

(b) Letter, YAEC to USNRC, dated February 26, 1988

Subject:

Semiannual Effluent Release Report

Dear Sir:

Enclosed please find the supplemental report which includes the summary of estimates of off-site radiation doses resulting from plant effluents during

{

1987. This information is submitted in accordance with Technical Specification 6.9.5.b.

For convenience, the above supplemental report is submitted with the inclusion of the 1987 third and fourth quarters radioactive liquid and gaseous releases, and solid waste disposal table summaries, which were previously submitted in Reference (b).

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

Very truly yours.

YANKEE ATOMIC ELECTRIC COMPANY l

l 4

c Jr. y)30n b Q

/

G. Pap Senior Project Engineer #

Licensing f

CP/25.517 i

Enclosures f

cc: USNRC Region I l

USNRC Resident Inspector. YNPS

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i i

i l

8804060101 371231 PDR ADOCK 05000029 1

R DCD

LJ l

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FOR THIRD AND FOURTH QUARTERS. 1987 I

INCLUDING ANNUAL RADIOLOGICAL IMPACT ON MAN FOR 1987 l

1 Yankee Atomic Electric Company Rowe, Massachusetts 2819R/4.242

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i, ERRATA

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In the Yankee Effluent and Waste Disposal Sesiannual Report covering the first cnd second quarters of 1987, the following corrections should be madet Supplemental Information None 1

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2819R/4.242

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TABLE OF CONTENTS j

Page l

11 ERRATA...........................................................

1

1.0 INTRODUCTION

2 2.0 METEOROLOGICAL DATA..............................................

3 3.0 DOSE ASSESSMENT..................................................

3.1 Doses From Liquid Effluents................................

3 4

3.2 Doses From Noble Gases.....................................

3.3 Doses from Iodine-131. Tritium and Radionuclides in Particulate Form With Half-Lives Greater 5

Than 8 Days................................................

8 REFERENCES.......................................................

9 TA3LES...........................................................

APPENDIX A Radioactive Liquid Effluent Monitoring Instrumentation......................................

A-1 APPENDIX B Radioactive Gaseous Effluent Monitoring Instrumentation......................................

B-1 APPENDIX C Liquid Holdup Tanks..................................

C-1 APPENDIX D Radiological Environmental Monitoring Program........

D-1 APPENDIX E Land Use Census......................................

E-1 APPENDIX F Process Control Program..............................

F-1 APPENDIX G Off-Site Dose Calculation Manua1.....................

G-1 1

APPENDIX H Radioactive Liquid, Gaseous and Solid Waste Treatment Systems....................................

H-1 APPENDIX I Supplemental Information.............................

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LIST OF TABLES f

Number Title P_ age 1A.

Gaseous Effluents - Summation Lf All Relesses 9

1B Gaseous Ef fluents - Elevated Releases 10 1C Gaseous Effluents - Routine Ground Level Releases 11 1A Liquid Effluents - Summation Of All Releases 12 85 Liquid Effluents - Routine Releases 13 3

Solid Waste and Irradiated Fuel Shipments 14 4

Maximum Off-Site Doses and Dose Cossaitments to Members of the Public 15-16 5A to 5H Annual Summary of Upper Level Joint Frequency Distribution 17-24

-iv-2819R/4.242

i YANKEE ATOMIC ELECTRIC COMPANY SEMIANNUAL EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 1

1.0 INTRODUCTION

Tables 1 through 3 list the recorded radioactive liquid and gaseous effluents and solid waste for the second six months of the year, with data summarised on a quarterly basis. Table 4 sununarises the estimated radiological dose comunitments f rom all radioactive liquid and gaseous cffluents released during the year 1987. Tables 5A through 5H report the cumulative joint frequency distributions of wind speed, wind direction, and cteospheric stability for the 12-month period, January to December 1987.

Radioactive effluents reported in the Semiannual Effluent Report covering the first six months of the year were used to determine the off-site doses for the first half of 1987.

As required by Technical Specification 6.9.5.b dose commitments resulting from the release of radioactive materials in liquids and gases were estimated in accordance with the "Yankee Nuclear Power Station Off-Site Dose Calculation Manual" (ODCM). These dose estimates were made using a "Method II" analysis as described in the ODCM. A "Method II" analysis incorporates the methodology of Regulatory Guide 1.109 (Reference 1) and e

actual measured meteorological data recorded during the reporting period.

For batch gaseous releases, the meteorological conditions concurrent with the time of release of radioactive materials (as determined by sampling frequency and measurement) were used for determining the gaseous pathway doses. As required by Technical Specification 6.9.5.b.(2), this report shall also include an assessment of the radiation doses from radioactive effluents to member (s) of the public due to allowed recreational activities inside the site boundary during the year. However, for this reporting period, no recreational activities inside the site boundary w?re permitted, and therefore are not addressed. The limited use of the Information Center on-site is associated with educational activities as they pertain to the production of electricity and as such are not included under Specification 6.9.5.b.(2).

Assessment of 2819R/4.242

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I radiation doses (including direct radiation) to the likely most exposed real member (s) of the public for the calendar year for the purposes of demonstrating conformance with 40 CFR 190. Environmental Radiation Protection Standards for Nuclear Power Operations, are also required to be included in this report, if the conditions indicated in Technical Specification 3.11.4 "Total Dose" have been exceeded during the year.

Since the conditions indicated in the action statement under Technical Specification 3.11.4.a were not entered into during the year, no additional radiation dose assessments are required.

All calculated dose estimates for this reporting period are well below the dose criteria of 10 CFR Part 50, Appendix I.

Appendices A through H indicate the status of reportable items per the requirements of Technical Specifications 3.3.3.6, 3.3.3.7. 3.11.1.4, 3.4.12.1, 3.12.2, 6.14.1, 6.15.2, and 6.16.1. 2819R/4.242

2.0 METEOROLOGICAL DATA Meteorological data was collected during the reporting period from the site's 200 foot meteorological tower located approximately 180 meters north of the vapor container. The tower instrumentation is designed to meet the requirements of Regulatory Guide 1.23 (Reference 2) for meteorolcgical monitoring.

The main release point for gases discharged from the plant is via the 150 foot primary vent stack, located between the vapor container and the primary auxiliary building. The primary vent stack is treated as a mixed mode elevated release point dependent upon windspeed as described in Regulatory Guide 1.111 (Reference 3).

X/Q and D/Q values were derived for all receptor points from the site meteorological record using a straight line airflow model. All dispersion and deposition f actors have been calculated errploying appropriate source configuration considerations and removal mechanism (e.g., dry deposition) described in Regulatory Guide 1.111 (Reference 3).

Terrain elevatiotis, including downwind valley flow corrections for the surrounding area were factored into the calculation of X/Q and D/Q values at each receptor location.

1 2819R/4.242

3.0 DOSE ASSESSMEhi 3.1 Doses from Liould Effluents Technical Specification 3.11.1.2 limits total body (1.5 arem per quarter, and 3 aree per year) and organ doses (5 arem per quarter, and 10 mrem per year) from liquid ef fluents to a member of the public to those specified in 10 CFR Part 50 Appendix I.

By implementing the requirements of 10 CFR Part 50. Appendix I, Technical Specification 3.11.1.2 assures that the release of radioactive material in liquid effluents will be kept "as low as is reasonably achievable."

Exposure pathways that could exiat as a result of liquid effluente are fish, dirtet exposure from river shoreline sedimentation, milk and meat via cnimal ingestion of the Deerfield River water, and meat, milk and vegetable pathways via crop irrigation with water withdrawn from the Deerfield River.

The drinking water and aquatic invertebrate pathways de not exist downriver of the Yankee Plant at Rowe.

j The dose analysis for the liquid pathways, given above, assumes a dilution based on the monthly average flow at the Sherman Dam. This results in conservative dose estimates f rom the liquid ef fluents.

The resultant whole body and organ doses from liquid effluents were determined by summing the contributions from all pathways at each location.

The whole body and organ doses to a member of the public from liquid effluents cre given in Table 4.

The estimated quarterly and annual doses due to liquid effluents are well below the 10 CFR Part 50, Appendix ! dose criteria of Technical Specification 3.11.1.2. 2819R/4.242

3.2 Doses From Noble Cases Technical Specification 3.11.2.2 limits the gamna air dose (5 mrad per quarter, and 10 mrad per year) and beta air (10 mrad per quarter, and 20 mrad per year) dose from noble gases released in gaseous effluents from the site to creas at and beyond the site boun?try to those specified in 10 CFR Part 50 Appendix I.

By implementing the requirements of 10 CFR Part 50, Appendix I, Technical Specification 3.11.2.2 assures that the releases of radioactive noble gases in gaseous effluents will be kept "as low as is reasonably ochievable."

Dose estimater due to the release of noble gases to the atmosphere were calculated at the site boundary, nearest resident, nearJst vegetable garden end nearest milk animal in each of the sixteen principle compass directions, cs well as the point of highest off-site ground level air concentration of radioactive materic'.s. Gama and beta air doses, as well as whole body and skin doses, were calculated at each of the above locations.

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To determine the beta contribution to the skin dose, a semi-infinite cloud andel was utilized. The whole body gama dose was calculated using a finite cloud sector average model with a Caussian distribution of activity in the vertical plane. The sama radiatien received f rom the cloud at a point of interest was determined by integrating the contribution from a differential volume over the entire cloud, taking into account the geometry of the cloud, variation in concentration, attenuation by the interaction of photons with matter in the path between the source and receptor point, and scattering of radiation from material outside the direct path to the point of interest-For skin and whole body doses an attenuation factor of 0.7 was applied to th+, dose calculations to secount for the dose reduction due to shielding which would be provided by a residential structure. No additional credit was taken for decay of radionuclides in transit to the receptor point.

The estimated quarterly and annual gama and beta air doses at the point of highest off-site exposure are listed in Table 4.

The estimated gama and beta air doses due to noble gases released in gaseous effluents are well below the 10 CFR Part 50, Appendix ! dose criteria of Technical Specification 3.11.2.2. 2819R/4.242

3.3 Dores From Iodine-131. Tritium _and Radionuclides in Particulate Form With j.

Half-Lives Greater Than 8 Days Technical Specification 3.11.2.3 limits the organ dose to a member of the public from iodine-131, tritium and radionuclides in particulate form with half-lives greater than 8 days (hereafter called iodines and particulates) in gaseous effluents released from the site to areas at and beyond the site boundary to those specified in 10 CFR Part 50, Appendix I (7.5 rrem per f

quarter, and 15 mrem per year).

By implementing the requirements of 10 CFR Part 50, Appendix I, Technical Specification 3.11.2.3 assures that the releases of iodines and particulates in gaseous effluents will be kept "as low cs is reasonably achievable."

Exposure pathways that could exist as a result of the release of iodines and particulates to the atmsphere it.clude external headiation from cetivity deposited onto the ground surface, inhalation and ingestion of vegetables, meat and milk. Dose estimates ware made at the site boundary, g

nearest resident, nearest vegetable garden and nearest milk animal in each of i

the sixteen principle compass directions. The nearest resident, nearest vegetable garden and nearest milk animal in each sector were identified by the most recent Annual 1,s.nd Use Census as required by Technical Specification 3.12.2.

Doses were also calculated at the point of maximum ground level air concentration of radioactive materials in gaseous effluents. Doses were calculated for pathways which were determined by the field survey to actually exist. Conservatively, a vegetabic garden was assumed to exist at each milk cnimal location. Furthertaore, the meat pathway was assumed to exist at each milk animal location. Meat animals were assumed to receive their entire intake from pasture during the second and third quarters. Milk animals were t

casumed to receive 50 percent of their intake from pasture during this period. This assumption is realistic since most dairy operations utilize 1

supplemental feeding of animals when on pasture or actually restrict animals to full time silage feeding throughout the entire year. 2819R/4.242 i

l The resultant orgsn doses were deternit.ed after adding the contributions from all pathways at each locat!.on.

Doses were calculated for the whole body, GI-tract, bone, liver, kidney, thyroid, lung and skin for cdults, teenagers, children and infants. Thu maximum estimated quarterly and cnnual organ doses due to iodines and particulates at any of the off-site receptor locations are reported in Table 4 The doses to all other organs at all other locations for all other age groups are less than the doses reported in Table 4.

The estimated organ doses from iodines and particulates in gaseous effluents are well below the 10 CFR Part 50, Appendix I dose criteria of Technical Specification 3.11.2.3.

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l-REFERENCES-1.

Regulatory Guide 1.109. "Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance With 10 CFR Part 50. Appendix 1." U.S. Nuclear Regulatory Coaunission.

Of.' ice of Standards Development. Revision 1. October 1977.

2.

Regulatory Guide 1.23. "On-Site Meteorological Pacgrams (Safety Guide 23)." U.S. Nuclear Regulatory Comission. Of fice of Standards Development. February 1972.

3.

Regulatory Guide 1.111. "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases f rom Light - Water -

Cooled Reactors." U.S. Nue'.,sar Regulatory Comission. Of fice of Standards Development. Revision 1. October 1977.

1 i

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1 TABLE 1A Yankee Atomic Electric Company. Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters.1987 Caseous Effluents - Summation of All Releases Unit Quarter Quarter Est. Total 3

4 Error. %

f A. Fission and Activation Cases

1. Total release Ci 7.74E+01 7.17E+01 e5.50E+01

2. Average release rate for period uCi/sec 9.85E+00 9.12E+00

3. Percent of Tech. Spec. limit (1)(4) %

7.42E-01 6.58E-01 B. Iodines

1. Total Iodine-131 C1 2.10E-05 4.25E-06 22.50E+01

2. Average release rate for period uCi/see 2.67E-06 5.41E-07

3. Percent of Tech. Spec. limit (2)(4) %

6.40E-02 4.93E-02 i

C. Particulatts

1. Particulates with T-1/2 > 8 days Ci 2.69E-06 2.71E-06 23.00E+01

2. Average release rate for period uCi/see 3.4 2 E-0 7 3.45E-07

3. Percent of Tech. Spec. limit 1

___ 3)

(3 )

(

)

4. Cross alpha radioactivity C1 2.80E-08 1.42E-08 D. Tritium

1. Total release Ci 9.42E-01 1.47E+00 23.00E+01 __

2. Average release rate for period uCi/see 1.20E-01 1.87E-01

3. Percent of Tech. Spec. limit 1

(3)

N (1) Technical Specification 3.11.2.2.a f or 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 T itium and particulates are included with I-131 above in Part B.

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TABLE IB l

Yankee Atomic Electric 03mpany. Rowe Massachusetts Ef fluent and Waste Disposal Semiannual Report Third and Fourth Quarters.1987 f

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

Nuclides Released Unit _

Quarter Quarter Quarter Quarter 3

h 3

4

1. Fission Cases Krypton-85 Ci 2.09E-02 1.36E-02 Krypton-85m Ci 8.68E-01 8.02E-01 Krypton-87 Ci 7.51E-01 8.09E-01 Krypton-88 Ci 1.54E+00 1.58E+00 Xenon-133 Ci 4.06E+01 3.48E+01 Xenon-135 Ci 1.52E+01 1.36E+01 Xenon-135m Ci 1.61E+01 1.85E+01 Xenon-138 Ci 4.83E-01 5.26E-01 Xenon-133m Ci 8.68E-01 4.63E-01

)

Arnon-37 Ci 3.38E-02

2. 55 E-02 J

Arnon-41 Ci 4.62E-01 3.35E-01 Carbon-14 Ci 3.60E-03 2.34E-03 Xenon-131m Ci 5.21E-01 2.78E-01 f

Unidentified Ci total for period Ci 7.74E+01 7.17E+01

8. Iodines Iodine-131 Ci 2.10E-05 4.25E-06 Iodine-133 Ci 1.63E-05 (1.67E-06 1

Iodine-135 Ci (1.90E-06

< 1. 9 2 E-0 7 Total for period Ci 3.73E-05

4. 25 E-06 8

3. Particulates Strontium-89 Ci

< 7. 7 2E-0 8 (3.79E-08 Strontium-90 Ci (8.69E-09

<$.42E-09 Cesium-134 Ci 9.75E-08 1.04E-07 Cesium-137 Ci 4.05E-07 5.75E-07 Barium-Lanthanum-140 Ci

<1.19E-06 (9.54E-07 Zine-65 Ci

<9.30E-07 (7.19E-07 Cobalt-58 Ci

<3.97E-07 (2.98E-07 Cobalt-60 Ci 2.06E-06 2.03E-06 Iron-59 Ci (8.27E-07 (6.44E-07 Chromium-51 Ci 8.14E-08

<2.04E-06

)

Zirconium-Niobium-95 Ci

1. 99E-08 (5.05E-07 Cerium-141 Ci

< 3. 41 E-0 7

( 2. 6 5 E-0 7 Cerium-144 Ci

< !.4 7E-06 (1.14E-06 Antimony-124 Ci (3.71E-07 (2.96E-07 Manaanese-54 Ci 2.40E-08

<3.13E-07 Silver-110m Ci (3.71E-07 (2.78E-07

)

Molybdenum-99 Ci

< 2. 80E-06 (2.13E-06 Ruthenium-103 Ci.

<3.41E-07

<2.66E-07 Total for period Ci 2.69E-06 2.71E-06 (1) There were no batch m;de releases during this reporting period. 2819R/4.242

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Tall.E 1C l

l Yankee Atomic _ Electric Company. Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1987 f

Gaseous Effluents - Ground Level Releases i

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There were no routine measured ground level continuous or batch mode gaseous releases during the third or fourth quarters of 1987.

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_ 2419R/4.242 b

TM1.E 2A Yan,kee Atomic Electric Company. Rowe. Manachusetts

,7,f fluent and k'aste Disposal, Semiannual Mcpprj Th'rd and Tourth Quarte,,es. 1987 Liquid Ef fluents - Sumation of All Rele 'es

/

Unit Quarto ~ ~ E rter Est. 5tal 3

4 Error. %

I A. Finion and Activation l'roducts 1.1 Total release (not including tritium, rasesy alpha)

Ci 4 M -03 1.29E-03 22.00E+01

._ 2. Average diluted concentration during period uCi/ml

6. 76E-11.,_ 2.00E-11

3. Percent of soplicable limit (1) 7.18E-03

_ 1.41E-03 B. Tritium

1. Total release Ci 3.12E+01

5. 4SE +('1 el.00E+01

2. Avsrage diluted concentration during period uci/ml 4.91E-07 840_E-07

_ 3. Percent of applicable limit (1) 1.64E-02 2.83E-02 C. Dissolved and Entrained Cases

1. Total release Ci 1.97E-02 7.57E-02 22.00E+01

2. Average diluted concentration during period uCi/mi 3.10E-10 1.17E-09

'). Pg_r.cynt of applicable limit (2) 1 1.55E-04 S.85E-04 D. Gross Alpha Radioactivity

1. Total release Ci

<2.66E-06 43,41E-06 23.50E+01 E. Volume of waste teleased (prict to dilution) liters 7.28E+06 ' 6.44E+06 23.00E+01 F. Volume of dilution water used durin,t period liters 6 '3E+10

_6.45E+10 25.00E+00 (1) Concentration limits.pecifled in 10CFR, Part 20. Appendix., Table II, Coluen 2 (Technical Sp.,cification 3.11.1.1).

The percent of applicable limit reported is based on the sverage diluted concentration during the period. At no tir.< old any release exceed the concent;ation limit.

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

The perce t of applicable limit reported is based on the average diluted (.c.entration during the period. At no time did any release exceed the concentration limit. 1819R/4.242

f s

k TABLE 2B sq Yankee Atomic _ E*ectric Companyx Rowe, Massachusetts Effluent _and Wast? Disposal Semiannual Report Ibi.rd and Fourth Juarters 1987 Liquid Effluents Continuous ' foot BatchMode\\.

) 'i Nuclides Released Unit Quarter Quarte.r Quarter Quarter 3

4 3

4 4

I l

Strontium-89 Ci (1.08E<04

<2.39E-04 "

2.58E-05

<1.37E-06

[

Strontium-90 Ci 2.02T-07

<2.99E-05 "

6.36E-06 1.40E-06 Cesium-134 Ci, 2.49E-05 6.2]E_-O h 5.L C-04 L 16E-05 Cesium-137 Ci

1. 02E-04 1.53E-v5 6.71E-04 9.07E-05;,_

Iodine-131 Ci 2.19E-05 1.85E-05 g,_1, 25E-03 1.

-04 Cobalt-58 Ci

<3.41E.05 (4.12E-05 3.55E-06

<6.c5E-f%

1 l

Cobalt-60 Ci

_3.37E-05 8.55E-06 1.38E t?4

4. 26Eg _

Iron-59 Ci (7.10E-05

<9.25E-05 2.22E-06

<1. 31r. 0 Zine-65 Ci

<8.452-05

<9.91E-05

<2.32E-05

<1.52E-05

(

Manganese-54 Ci G.J31-05

<4.43E-05 3.17E-05 5.52Ed7].

f Chromium-51 Ci

<2.75E-04

<3.28E-04

<1.40E-04

<7.lsE05 Zirconium-Niobium-95 Ci 25.98E-05 (7.23E-05 7,51E-37 2.11E-07

\\

_ 3.13E-04 d.JSE-05

<4.67E-05 Molybdenum-99 Ci (2.71E-Oh l

Technetium-99m Ci 1.27E-05

).33E-Of

<1.67E-05

<1.02E-05

)

Barium-Lanthanum-140 C!

(1.15E-04

<1.61E-05

<5.00E-05 (2.63E-05

' 2. 67E-M el. 66E -05 Cerium-141 Ci _, <4.76E-05

< 5. 5g-05 Ruthenium-103 Ci (3.31E-05 (4.18E-05

<1.45E-05 (7.76E-06 Cerium-144 C5 (2.184 64

<2.50E-04

<1.24E-04 3.57E-06 Iodine-133 Ci

<3.57E-05

<4.09E-05 1.82E-04 2.37E-05 Selenium-75 Ci

<3.88E-05

<a.59E-05

<2.08E-05

<1.09E-05 Silver-110m Ci

<3.56E-05 (4.10F-05

<1.22E-05

<7.53E-06 Antimony-124 Ci

<3.52E-05 (4.12 U 5

< 1.66' C05.

2. 86 R--06 g

'8.09E-Of P.21E-04 Carbon-14 Ci Iron-55 Ci

<6.71E-03

<5.98E-03 4.25E-04

<4.56E-04 Cesium-136 Ci

<3.46E-05

<4.34E-05

<1.00E-05 (6. 7 7 E-06 j

Unidentified Ci Total for period (above) C1 1.95E.04 5.09E-05 4.C?E-6 1.29E-03 Xenon-133 Ci 79.63E-05

<1.19E-0 1.09E-02 6.32E-02

__ Xenon-135 Ci

<4.72E-05

<3.7 h 05

1. 18E-04 7.56E-05

<1.'02-03 d.44E-03 6.95E-05 1.93E-03 Xenon-131m Ci

/

Xenon-133m Ci

<2.4?E-04

<2.94E-04 1.10E-04 2.63T.-04

~

Krypton-85 Ci (1,12E-02

<1.37E-02 8.49E-03 1.0's 02 _

2819R/4.242

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TABLE 3 J

Yankee Atomic Electric Compann, Rowe, Massachusitts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters, 1987 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Euria1 or Disposal (Not Irradiated Fuel)*

Unit 6-Month Est. Total g

f M

Period Error, %

)

1. Type of Waste a.Spentresins,filtersludges,eva"jorator 3

8.10E+00 m

bottoms, etc. - LSA container **,+

C1 7.93E-01 23.00E+01 J

1.61E+02

b. Dry compressible waste, contaminated m

equipment, etc. - LSA container ++

Ci 4.04E+00 21.00E+02 J

c. Irradiated components, control ro.ir,

m Ci etc.

m$

d.

Ci 3

m e.

Ci

{

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

a.

Hydrogen-3

% 3.51E+01 b.

Cesium-137

% 3.24E+01 Cesium-137

% 2.26E+01 Cesium-134

% 2.97E+01 Cesium-134

% 1.92E+01 Iron-55

% 2.65E+01

{)

Iron-55

% 1.74E+01 Ccbalt-60

% 3.94E+00 Cobalt-60

% 2.67E+00 Niobium-95

% 2.66E+00 Nickel-63

% 1.44E+00 Nickel-63

% 2.06E+00 f

Iron-59

% 1.57E+00 Manganese-54 % 1.10E+00 4

3. Solid Waate Disposition

(

Number cf Shipments Mode of Transportation Destination

)

6 Truck Barnwell, SC B.'Irradicted Fuel Shipments (Disposition): None.

/

+ Container volume equal to 55 gallons (drums).

++ Container volume equal to 105 f t3 (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/4.242

h.

TABLE 4 Yankee Atomic Electric Company. Rowe Massachusetts E'. fluent and Waste Disposal Semiannual Report Third and Fourth Quarters. 1987 Maximum

O'f-Site Doses and Dose Commitments to Members of the Public Dose (mrem)***

1st 2nd 3rd 4th Source Quarter Quarter Quarter Quarter Year **

Lf. quid Effluents 1

Whole Body (1) 3.67E-02 4.29E-02 2.07E-02 1.47E-02 1.15E-01 Critical Organ (2) 5.87E-02 7.03E-02 3.24E-02 1.60E-02 1.77E-01 Airborne Effluents Iodines and Particulates 1.40E-02 1.94E+00 4.80E-03 3.70E-03 1.96E+00 (3)

(3)

(4)

{

Noble Gases Beta Air 1.5SE-01 1.15E-01 8.99E-02 7.26E-02 4.36E-01 (5)

(mrad)

Gamma Air 5.96E-02 2.87E-02 3.71E-02 3.29E-02 1.58E-01 (mrad)

"Maximum" means the largest fraction of corresponding 10CFR50, Appendix I, dose design objective.

i

- "Maximum" dose for the year is the sum of the maximum doses for each quarter.

This results in a conservative yearly dose estimate, but still well within the limits of 10CFR50.

O**The numbered footnotes indicate the location of the dose receptor, age group, and organ, where appropriate.

(1) Adult, second quarter; child, first, third, and fourth quarters (2) Liver of child

)

(3) Bone of child SW, and WSW-1300 meters (4) Thyroid of child, SW, and WSW-1300 meters (5) S and SSE-800 meters v 2819R/4.242 1

1

f TABLE 4 (Continued)

THIS PAGE INTENTIONALLY LEFT BLANK l

/

1 s

, 2819R/4.242

}

i TABLE 5A i

Yt& EE R0WE JM37-EE087 METECELCGICAL DATA JOINT FRETAEN^Y DISTPIB'JTICN 196.0 FT WIND [4TA STAHLITY CLA59 A class FREQ'.EY.Y (PEE:CEhT) =

.63 WIND DIRECTION FRCri SFEED09H)

N N*iE NE ENE E ESE SE Scie 5

S%'

SW G W RW NW NY' VFR TOTAL CAiM 0

0 J

G 0

0 0

(!;

.00

.03

.00

.00 00

.00

.05

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.O

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.00

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. 0'.,

.00

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0 0

0 i-0 0

0 0

0

(-s 0

t'

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.00 9)

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. r*'

,y

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,en

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4-7 n

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u.c

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.M X

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.% 8.!'

4.03 3?.7? 8.16 2.04

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(1) 2.(4

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. f:

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( 1 ) ; {f/ T' ? T Q Qf([ ( @ ~ T;* 'C T

1," ff4 T @ Cl*I (2)*E5r:EK Oc M Cor f?!9 d!0*G Fy THIS PU10:.

C= CAL" (WIND $ PEED LEss ThM % E2.c. 70

.M C 1

TABLE 5B

(

METEOR 0LO.lCA'. IAM J0 INT FF.EQUENCY DISTRIEJ'IM i

YATEE FM JAT7-CEC 87 19..( FT WIND DATA STAE!LITY CLM. : E CLAS3 FRE0'.OCY (PEK!NT) = 1.27 WIND DIFICTION FR0".

SPEEDi"Jta N

'NE NE E*.I E EM SE $$E S S?#

SM L9 W WW Kd WW W2 TOTr_

CU 0

a 0

0 0

0 (1)

.0)

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ALL SFfEf5 5

1 1

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(')**EEEC O' A' L G'72 C!!ED'.'A'!(*3 F.T TWI! 8ME

'2)*EPCEN' C ALL GX0 OETEWAT10'd F(G THIS F910D

(= CALM (WIND SSEED LESS T4N 04 ECM TO. 60 Fe i

)

TABLE SC l

YtME R0WE AN3MCC?? METEOROLOGICAL DATA J0: tit FRE0"Ev:Y DISTRIB'JTICN 196.0 FT WIND DATA 5T 5 11TY CLA55 0 CLAs? FRIP.'E'/.Y (FER2NT) = 2.37 WIND DIFfCTION FP71 SPEED W H1 N V;E PF.

ENT E N

?! 55E S SSW SW W12 W

Wi.!

W N% Vk T0it CA' N 0

0 0

0

^

(1)

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a 0. 0,

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2 4-7 4

2 6

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' 43 5.91 1,6? 1.0;

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1.63

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(= Cte (WPO SFIED LE55 Tm4'i OR ECG_ 70, 60 *': a -

{

TABLE 5D YReEE RtWE #N?7-EEC87 l'ETEOROLOGICR [4TA &lNT FREC(EN:Y DISTRIBUTICN 196.0 FT WIND [e.TA STABILlTY C % ? D CIA 33 FFf0'.ENCY (PEF.fNT) = 49.35 WIND DIFECTICt1 FF.M 55EED(MPH)

N h'.I NE ENE E ESE SE SSE S SSW SW W"41 W W N'.;

NW VPL TC%

CC 0

0 0

0 (1)

.00

.06

.00

.0)

.00

.M

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.00

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.00

.(n

.00

.G C-?

71 103

E

't 26 12 17 10 14 M

47

?2 21 15 2

0 4:

54

2:

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.T C

.9 1 ':

C' 1"

J.6 45

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=

y 1:-

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.73

.73 12." !,!! 2.10 3.70 5.13 3.8.5 2.45 1.0? 2.2: c.$i 0

ai ' '

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. 34

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45

.57 1.09 1.83 2.53 1.92 1.21

.95 1.09

1. 3'.:

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I 8-12

? '. 3 :57 15 2

1 6

5 c

31 72 143 Iti 54 27 47 59 0

12:

V

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1. E ?.73 4.38 1.42

.70 1.22 2 '. '

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7.43 fD 4.03 :. 0

.23

.01 61

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.06

.12

.t?

.c 1,54 2.16

.72

.35

. e. 0 !.:7

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2L (1) 2.74 2,3*

. 0s

60

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Au cw:M 755 77; 154 54 ri 61 60 6'-

!?2 2'4 409 ?91 174 117 153 2N 0

^ ?9 !.9

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' a 4.01 1 41 1.4? 1.Si 1.56 1.64 3.44 6.62 10.63 10.1+ 4.51 3,05 (ti 14.67 20.3:

1 (2) 9.71 10.02 1.M

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e (1 )*. {E [h ' T (L $2 I".kU'$ f($

T.

fl'{

b (2actVD.i (.: a.'. rm Opipv,il( c: :(r Tut: p?c tr':

C= Ctt.M (WIN 2 ? SEED LEtt TW4N Cc E0.E TO. 60 F #- -

)\\.

TABLE SE r

1 i

Yt#:EE F%E JA437-DECS7 PETEOROLOGICAL DATA JOIN 1 FRE0'.E'CY DISTRIPJTION M6.0 FT 'It!. [ATA STA?!!.ITY Ctc35 E CLASS FREC8.ENCY (FERCENT) = 35.22 WIND DIRECTION FRCft (f?ED(PFH)

N NNE NE ENE E E!2 5E Ssi S SSJ 9 WW W

E' NW W VFK TOTK Cl,?

0 O

O 0

0 0

(1)

.00 00

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(-3 264 Sti lEs 75 52 57

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43 77 73 61 30 31 3:

0 16 (1) 9.?? '?.42

!.56 2.':

1. r *. 1.9 1.24 1,5:

1. " 2.74 2 'O 2,17 1.07 1.10 ' 2.2?

f-

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'<, r 6.0 - 's 67 43 45

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.o' ALL SPEEM 456 540 273 90 61 48 53 75 81 172 208 113 54 46 48 94 0

25 ".

(1) !!.20 33 ?i 9.70 7.20 4.':

1 ~; 1.F 2.77 2.66 6.11 7.3i 4.01 1.02 1.0 1.7

?.34

.0:

(2) 5.?7 12.69

51 1.16

.73

.62

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.60

.!? !.21

.F i

( j )d[W'.* [S (' (.7[ 0*-94T[(f.'i Eff. TH}'- E A'i (21:PEMENT Cf R'. CE OMEWION! FOR 14t$ FIR 10' C= CliM (WIP!: SFIED LESS TMN C6 EC$A. TO.60 P ' -

)

TABLE 5F l

f YWIE R0WE #G7-EECS7 METEOROLOGICAL LATA JOINT FREQUEN:Y DISTFIBJTION 196.0 FT WIC DATA STAEILITY at.5. F RASS FF93.ENCY (PEMENT) = 7.??

WIND DIFECTION FRG1 SFEED(.94)

N NNE NE ENE E EcE SE SSE S $$W SV 6'

W WW NW N VFR.

TOTC CALM 0

0 0

(1)

.00

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24 27 19 15 17 17 23 7

15

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oi 4.ce 10.s

7. cr2 5.3 e.c;

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2, p 2,e^

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4 '-

27 34 26

??

26 33 48 23 18 9

13 22 0

W ti; 7.10 20,f? 14.85

7. 5; 4.4 5.el

4. 3 3.E0 4.25 5,4! 7.92 3.S0 2.97 1.4) 2,15 : ':

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(2)

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(j ):C[E^T'.* 7 RL ( *: 7 l3 }EE','47!0'i3 C(f I,"' T;";"'

(2MEKE!.T 0; ALL 000:' OMEUTIO'n F00 THi! PERI'.I C= CALN (WIND STEED LES: T @.' 0; E M L TO.60 W )

l l

TABLE SG 1

l i

I l

t

[

YAN?IE R0WE JAtG7-[EC87 METEPIC_0GICAL DATA 0lNT FREO.IN:Y CISTRIBJTION 196.0 FT WIND DATA STASILIT+ C'E 0 CUGSS FFEO.EN0Y (FERCENT) = 2.34 WIND DIRECTION F701 SFTED(MMO N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NW WL T0itL CALM 0

0 0

0 (1)

.00

. 0':

.0)

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.00

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11 7

11 6

6

?

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6 5

a

^

3 0

c'

(:)

2.7" A.0 3 ?*

!. 04 3,'

3.t'

4. 0 3.5'

', i's ?.30 2.7! 2.20 1.10 1.10 1.10 1.!'

.00 E '.. N

(:1 N

14

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- - - - - - - ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

APPENDIX A

. Radioactive Liquid Effluent Monitoring Instrumentation I

Requirement: Radioactive liquid effluent monitoring instrumentation channels required to be operable in accordance with Technical ars Specit! cation 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 3

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) which was installed during the last reporting period was calibrated and declared operational on November 19, 1987. ACTION Statement 17 of Table 3.3-8 was still in effect, until the flow rate measuring device for the steam generator blowdown tank effluent was calibrated.

1 A-1 2819R/4.242

I l

[

I APPENDIX B Radioactive Gaseous Effluent Monitoring Instrumentation l

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 ef fluent monitoring instrumentation were met for this reporting period, 4

no response is required.

B-1 2819R/4.242

___-__--_____a

1 l

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.

I C-1 2819R/4.242

1 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 Of f-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/4.242 l

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

Response

No changes were made in the Radiological Environmental Monitoring Program as a result of the 1987 land use census.

E-1 2819R/4.242

I l

APPENDIX F Process Control Program Reguirement: Technical Specification 6.14.'. requires that licensee initiated changes to the Process Control Program be submitted to the Comission in the Semiannual Radioactive Ef fluent Release Report for the period in which the change (s) was made.

Response

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

f r-1 2819R/4.242

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 Comission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective.

Response

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

G-1 2819R/4.242

l i

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/4.242

APPENDIX I Supplemental Irformation Third and Fourth Quarters, 1987 s

1.

Techn, leal Specification Limits - Dose and Dose Rate Technical Specification r.nd Category Limit a.

Noble Gases 3.11.2.1 Total body dose rate 500 mrem /yr 7,

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 j

l 3.11.2.1 Organ dose rate 1500 mrem /yr l

l 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/4.242 r

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 MFC (10CFR20, Appendix B. Tables II, Column 2), excluding noble gaser less than:

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

Measurements and Approximations of Total Radioactivity a.

Noble Cases l

"Continuous discharges" are determlaed by indirect measurement.

l l

Primary gas samples are taken periodically and analyzed.

It is assumed that in prf. mary to seconde.ry leakage all gases are ejected tnrough 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 1 5 percent.

5 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/4.242

analyzed weekly. The errors associated with these measurements are estimated to be 125 percert.

c.

Particulates l

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

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

d.

Liquid Effluents 1

Liquid effluents are determined by direct measurement.

In line b

composite samples are analyzed for strontium-89, strontium-90. gross alpha activity and carbon-14. There is no compositing of samples for i

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 l

)

associated with these measurements are as follows:

fission and f

activation products, 20 percent; tritium, 110 percent; dissolved fission Lases, tt0 pera nt; alpha activity, 135 percent.

4.

Bptch Reisases, a.

Liquido i

Third Quarter l

Number of batch releases:

22 Total time period for batch releases: 9,119 minutes s

Maximum time period for a batch release:

1,975 minutes i

l Average time period for batch releases:

415 minutes j

Minimum time period for a batch release:

240 minutes Average stream flow during period (Sherman Dam): 437 cfs Average discharge rate:

16.7 gpm I-3 2819R/4.242

[

l' Fourth Quarter Number of batch releases:

18 Total time period for batch releases: 6,371 minutes Maximum time period for a batch release:

1,275 minutes Average time period for batch releases:

354 minutes l

Minimum time period for a batch release:

240 minutes Average stream flow during period (Sherman Dam): 836 cfs

(

Average discharge rate:

18.9 gpm b.

Gases There were no batch gaseous releases during the third and fourth quarters of 1987.

5.

Abnormal Releases a.

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

b.

Gases There vere n, nonrout ine gaseous releases during the reporting period.

5 ve I-4 2819R/4.242 a

- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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