ML20138H551

Effluent & Waste Disposal Annual Rept Suppl Info 1996

ML20138H551
Person / Time
Site:	Seabrook
Issue date:	12/31/1996
From:	NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:
Shared Package
ML20138H542	List: ML20138H538 ML20138H551 ML20138J335 ML20138J362
References
NUDOCS 9705070219
Download: ML20138H551 (13)

Text

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Supplemental Information 1996 Facility: Seabrook Station Unit 1 Licensee: North Atlantic Energy Service Corporation

1. Regulatory Limits A. Gaseous Efiluents

a. 5.0 mrad per quarter gamma air dose.

b. 10.0 mrad per quarter beta air dose.

c. 7.5 mrem per quarter to any organ.

B. Liquid Efiluents

a. 1.5 mrem per quaner total body.

b. 5 mrem per quaner to any organ.

c. 2.OE-04 uCi/ml dissolved or entrained gas.

2. Maximum Permissible Concentrations i

Provide the MPC's used in determining allowable releases rates or concentrations.

a. Fission and activation gases: 1 MPC

b. Iodines: 1 MPC

c. Particulates, half-lives > 8 days: 1 MPC l

d. Liquid effluents: 1 MPC j

3. Averege Energy Not applicable.

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4. Measurements and Approximations of Total Radioactivity Provide the methods used to measure or approximate the total radioactivity in ef0uents and the methods used to determine radionuclide composition.

a. Fission and activation gases: Determined by gamma spectroscopy. Total error is based on stack flow error, analytical error and calculated sampling error.

b. lodines: Determined by collection on charcoal with subsequent gamma spectroscopy analysis. Total error is based on stack flow error, analytical error and calculated sampling error,

c. Particulates: Determined by collection on fixed filter with subsequent gamma spectroscopy analysis. Strontium is determined by composite analysis of filters by liquid scintillation, gross alpha by proportional counter, and iron 55 by liquid scintillation. Total error is based on stack flow error, analytical error and calculated sampling error.

d. Liquid Effluents: Determined by gamma spectroscopy. A composite sample is analyzed for strontium by liquid scintillation, tritium by liquid scintillation, alpha by proportional counter, and iron 55 by liquid scintillation. Total error is based on the volume discharge error and analytical error.

5. Batch Releases Provide the following information relating to batch releases of radioactive materials in liquid and gaseous effluents.

a. Liquid r

1. Number of batch releace::: 126

2. Total time for latch releases: 28112 minutes

3. Maximum time period for batch release: 575 minutes

4. Average time period for batch release: 223 minutes

5. Minimum time period for batch release: 23 minutes

6. Average stream flow during per'ods of release of effluent into a flowing l stream: 1.65E06 liters per minute

b. Gaseous

1. Number of batch releases: 46

2. Total time for batch releases: 11900 minutes

3. Maximum time period for batch release: 3340 minutes

4. Average time period for batch release: 259 minutes

5. Minimum time period for batch release: 0.3 minutes

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

d

6. Abnormal Releases

a. Liquid

1. Numberofreleases: 0

2. Total activity releases: N/A

., b. Gaseous d

1. Numberofreleases: 0 Total activity releases: N/A i

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TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Quarter Quarter Est.

1 2 3 4 Total Error, %

A. Fission and activation gases

1. Total releases Ci 9.19E-03 9.73E-03 1.10E-01 1.22E+01 1.70E+01l

2. Average release rate uct/s.c 1.18E-03 1.24E-03 1.39E-02 1.54E+00 for period

3. Percent of applicable t 2.80E-04 3.28E-04 2.16E-03 1.46E 02 Technical Specification limit B. Iodines

1. Total release C1 ND l ND ND 5.67E-08 1. 5 0 E+ 01 l

2. Average release rate "Ci>**c ND ND ND 7.14E-09 for period

3. Percent of applicable t N/A N/A N/A 1.45E-01 Technical Specification limit C. Particulates

1. Total release Ci 5.25E-05 ND ND ND 1.80E+01l

2. Average release rate uC1'**c 6.75E-06 ND ND ND for period

3. Percent of applicable t 3.39E-02 N/A N/A N/A Technical Specification limit

4. Total alpha radioactivity C1 ND ND ND ND D. Tritium

1. Total release Ci 7.29E-02 3.36E+00 9.37E+00 1.07E+01 1. 6 0 E+ 01 l

2. Average release rate ua "*c 9.37E-03 4.28E-01 1.18E+00 1.35E+00 for period

3. Percent of applicable  % 3.39E .. 39E-02 1.36E-01 1.45E-01 Technical Specification limit ND = NONE DETECTAllLE Footnote: Sr-90 was positively identified in the 1st quarter sample of the steam packing exhauster.

Further investigation indicated that the positive indication may have been sample contamination caused by the reuse of glassware used in this type of low level analysis.

Laboratory methods were changed to use new glassware for this analysis. Monthly samples taken immediately after for three months indicated no detectable SR-90. The quarterly

. samples analyzed subsequent to that sample have not indicated any detectable radioactivity l

(this includes those samples analyzed following an identified primary to secondary leak and fuel defects).

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.I TABLE IB EFFLUENT AND NASTE DISPOSAL ANNUAL REPORT (1996)

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES '

CONTINUOUS Nuclides Released Unit Quarter Quarter Quarter Quarter 1 2 3 4 l i

1. Fission and activation gases argon-41 Ci ND ND ND ND krypton-85 Ci ND ND ND ND '

krypton-85m Ci ND ND ND ND krypton-87 Ci ND ND ND ND '

krypton-88 Ci ND ND ND ND xenon-133 Ci ND ND ND ND xenon-135 C1 ND ND ND ND  !

xenon-135m Ci ND ND ND ND xenon-138 Ci ND ND ND ND  ;

Ci

{

Ci j unidentified Ci ND ND ND ND I Total for period Ci ND ND ND ND

2. Iodines l

iodine-131 Ci ND ND ND 5.49E-08 l iodine-133 Ci ND ND ND ND iodine-135 Ci ND ND ND ND Total for perio'd Ci ND ND ND 5.49E-08

3. Particulates I strontium-89 Ci ND ND ND ND strontium-90 Ci ND ND ND ND cesium-134 Ci ND ND ND ND I cesium-137 C1 ND ND ND ND I barium-lanthanum-140 Ci ND ND ND ND cobalt-58 Ci ND ND ND ND )

Ci  !

unidentified Ci ND ND ND ND Total for period Ci ND ND ND ND ND = NONE EXPECTED l

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TABLE IB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1996)

!!ASIOUS EFFLUENTS-GROUND LEVEL RELEASES a

RATCH i i

Nuclides Released Unit Quarter Quarter Quarter Quarter  ;

i 1 2 3 4 i

1. Fission and activation gases

argon-41 Ci ND ND ND ND j krypton-85 Ci ND ND ND ND l krypton-85m Ci ND ND ND ND ;

krypton-87 Ci ND ND ND ND l krypton-88 Ci ND ND ND ND l xenon-133 01 ND ND ND ND '

i xenon-135 Ci ND ND ND ND i i

xenon-135m Ci ND ND ND ND i

a xenon-138 Ci ND ND ND ND l Ci [

Ci ,

unidentified Ci ND ND ND ND !

t Total for period Ci ND ND ND ND

)

2. Iodines iodine-131 Ci ND ND ND ND f

< iodine-133 Ci ND ND ND ND

! iodine-135 C1 ND ND ND ND i {

Total for period Ci ND ND ND ND j i

j 3. Particulates j strontium-89 Ci ND ND ND ND f strontium-90 Ci ND ND ND ND l cesium-134 Ci ND ND ND ND cesium-137 Ci ND ND ND ND j barium-lanthanum-140 CL ND ND ND ND j cobalt-60 Ci ND ND ND ND

) Ci unidentified Ci ND ND ND ND Total for period Ci ND ND ND ND

]' ND = NONE DETECTED 1

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

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TABLE IB EFFLUENT AND WASTW DISPOSAL ANNUAL REPORT (1996)

. GASEOUD EFFLUENTS-ELEVATED RELEASES CONTINUOUS Nuclides Released Unit Quarter Quarter Quarter Quarter 1 2 3 4 1

1. Fission and activation gases argon-41 Ci ND ND ND l ND krypton-85 Ci ND ND ND ND krypton-85m Ci ND ND ND 4.65E-04

krypton-87 Ci ND ND ND ND

{

krypton-88 Ci ND ND ND ND

=

xenon-133 Ci ND ND ND 1.02E+01 ,

?

j xenon-135 Ci ND ND ND 1.98E+00

! xenon-135m Ci ND ND ND ND xenon-138 Ci ND ND ND ND Ci

Ci unidentified Ci ND ND ND ND

{

l Tote' for period Ci l ND ND ND 1.22E+01

2. Iodines iodine-131 Ci ND ND ND 1.64E-10 iodine-133 Ci ND ND ND 1.68E-09 iodine-135 Ci ND ND ND ND Total for period Ci ND ND ND 1.84E-09

3. Particulates strontium-89 Ci ND ND ND ND strontium-90 Ci ND ND ND ND cesium-134 Ci ND ND ND ND cesium-137 Ci ND ND ND ND barium-lanthanum-140 Ci ND ND ND ND

~ cobalt-58 Ci 4.69E-05 ND ND ND cobalt-60 Ci 5.61E-06 ND ND ND chromium-51 Ci ND ND ND ND manganese-54 Ci ND ND ND ND niobium-95 Ci ND ND ND ND j iron-59 Ci ND ND ND 10 I unidentified Ci ND ND ND ND Total for period Ci 5.25E-05 ND ND ND l ND = NONE DETECTABLE i

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

TABLE IB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1996)

GASEQUS EFFLUENTS-ELEVATED RELEASES BATCH Nuclides Released Unit Quarter Quarter Quarter Quarter 1 2 3 4

1. Fission and activation gases argon-41 Ci 6.31E-03 8.66E-03 9.46E-02 2.00E-02 krypton-85 Ci ND ND ND ND krypton-85m Ci ND ND ND ND krypton-87 Ci ND ND ND ND krypton-88 Ci ND ND ND ND xenon-133 Ci 2.70E-03 1.07E-03 1.55E-02 5.35E-03 xenon-135 Ci 1.81E-04 ND ND 2.66E-05 xenon-135m Ci ND ND ND ND xenon-138 Ci ND ND ND ND Ci Ci l

unidentified Ci ND ND ND ND Total for period Ci 9.19E-03 9.73E-03 1.10E-01 2.54E-02

2. Iodines iodine-131 Ci ND ND ND ND iodine-133 Ci ND ND ND ND iodine-135 Ci ND Nd ND ND Total for period Ci ND ND ND ND

3. Particulates strontium-89 Ci ND ND ND ND strontium-90 Ci ND ND ND ND ,

cesium-134 Ci ND ND ND ND cesium-137 Ci ND ND ND ND l

barium-lanthanum-140 Ci ND ND ND ND l Ci unidentified Ci ND ND ND ND Total for period Ci ND ND ND l 10 ND = HONE DETECTABLE .

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TABLE 2A EFFLUENT AND WAATE DISPOSAL ANNUAL REPORT 1996

)

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES l

Unit Quartes a guarter 2 Quester 3 Quarter 4 het, Total Error, t A. Fission and activation products

1. Total releases CA 1.10s 02 6.61s-02 1.41s-c3 s.4tt43 e.ous.oo 2, Average diluted concentration uCA /ud 6.798-11 2.66E-10 6.9)s-11 3.798 11 during period

3. Fercent of applicable limit t e.63s-0) 1.14E-02 1.47s.02 1.29E-02 B. Tritium

1. Total release CA 1.10h.02 1 41b.02 2.661 02 1.665 02 8.00E.00

2. Average daluted concentration ucarma 5.6as-07 6.60s-07 2.cas-06 6.34a-07 during period l

)

3. Percent of applicable limit t 8.636-01 1.14E-02 1.47s.02 1.29s 02 C. Dissolved and entrained gases

1. 'Jotal release CA ND NL NL 6.925-05 1.90k.01 1

2. Average diluted concentration uCiimi ND ND HD 2.661-13 l during period

3. Percent of applicable limit t N/A N/A N/A 1.335-01 D. Gross alpha radioactivity

1. Total release Ci No NL No Nn 3,90g.c3 E. Volume of waste liters 2.296 07 1.726 07 1.76s.07 1.468 07 1.306 00 released (prior to dilution)

F. Volume of dilution 11ters 1.e96 11 2.17E.11 2.368+11 2.23E.11 9.00E+bo water used during period ND = NONE DETECTABLE

. - ~ ~ - _ _ . - . . . . . . . - - . . - . _ . - - - ~ . . _ - - . - . . . - . . - ._-. _. . . ~ . = . . .

)

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I TABLE 2B J

z EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 i

} LIQUID EFFLUENTS l CONTINUOUS MODE l I d

4 Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 e

strontium-89 Ci ND ND ND ND i strontium 30 Ci ND

, ND ND ND cesium-134 Ci ND ND ND ND cesium-137 Ci ND ND ND ND iodine-131 Ci ND ND ND 2.51E-05 4

2 iodine-132 Ci ND ND ND 5.70E-05 iodine-133 Ci ND ND ND 9.15E-05 1

iodine-134 Ci ND ND ND 1.85E-05 l iodine-135 Ci ND ND ND 8.37E-05 l cobalt-58 Ci ND ND ND 2.37E-05 cobalt-60 Ci ND ND ND ND t

j iron-59 Ci ND ND ND ND

] zinc-65 Ci ND ND ND ND

{ manganese-54 Ci ND ND ND ND f chromium-51 Ci ND ND ND ND 1

1 zirconium-niobium-95 C1 ND ND ND ND

[ molybdenum-99 Ci ND ND ND ND

} technetium-99m Ci ND ND ND ND l barium-lanthanum-140- Ci ND ND ND ND j cerium-141 Ci ND ND ND ND t

i unidentified Ci ND ND ND ND l Total for period (above)l Ci l ND l ND l ND l 3.00E-04 l

}

l xenon-133 Ci ND ND ND ND

! ;renon-135 Ci ND ND ND ND l ND - NONE DETECTABLE l

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t TABLE 2B l, EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996

! LIQUID EFFLUENTS i BATCH MODE J

! Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 l strontium-89 C1 ND ND ND ND ,

4 i strontium-90 Ci ND 1

ND ND ND i i cesium-134 Ci ND ND ND ND l

cesium-137 Ci ND ND ND ND ,

j iodine-131 Ci ND ND 7.90E-06 8.60E-05 {

I iodine-133 Ci ND ND 6.71E-06 I J

2.94E-05 j cobalt-57 Ci ND ND 3.95E-05 2.27E-05

!- cobalt-58 Ci 3.09E-03 2.19E-03 3.69E-03 1.6BE-03 cobalt-60 Ci 3.24E-04 8.89E-04 1.36E-03 1.45E-03 chromium-51 C1 3.53E-04 ND ND ND iron-55 C1 1.40E-03 5.92E-04 4.31E-03 4.46E-03 iron-59 Ci ND ND ND ND zinc-65 Ci ND ND ND ND manganese-54 Ci 5.92E-05 9.47E-05 8,13E-05 8.61E-05 i zirconium-niobium-95 Ci ND ND ND ND  :

molybdenum-99 Ci ND ND ND ND I technetium-99m Ci ND .ND 2.29E-05 1.85E-05 barium-lanthanum-140 Ci ND ND ND ND cerium-141 Ci ND ND ND ND antimony-124 Ci 7.06E-04 5.33E-04 1.01E-04 4.01E-06 i antimony-125 Ci 5.02E-03 5.18E-02 4.49E-03 3.07E-04 bromine-82 Ci ND ND 1.34E-05 1.05E-05 Ci unidentified Ci ND ND ND ND Totalforperiod(above)lCi l1.10E-92 l5.61E-02 l1.41E-02 l8.15E-03 l i xenon-133 Ci ND ND ND 5.52E-05 xenon-135 Ci ND ND ND 4.04E-06 ND = NONE DETECTABLE

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TABLE 3 1

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 1

, SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.

SOLID WASTE SillPPED OFFSITE FOR BURIAL OR DISPOSAL (Not !rradiated fuel)  ;

, 1.4 Type of wasts (no shipment made)- ' Unit Est. Total Error %

a. Spent resins, filter sludges, evaporator bottoms, etc. O m' E 1

0 ci j b. Dry compressible waste, contaminated equipment 0 m' E O ci

}

c. Irradiated components, control rods, etc. O m' E 2

0 ci i d. Other(describe) 0m 3 E O ci j

)

j 2. Estimate of major nuclide composition (by type of waste) a.

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3. Solid Waste Disposition Number of Shinments Mode of Transnortation Destination j None

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l APPENDIX A l Off-Site Does Calculation Manual Requirement: Technical SpeciGcation 6.13.2.b requires that licensee initiated changes to the Off-Site Dose Calculation Manual (ODCM) be submitted to the Commission in i the Annual Radioactive Ef0uent Release Report for the period in which the i change (s) was made effective. Changes made to the Radiologica I Environmental Monitoring Program (REMP) in accordance with Technical SpeciDeation 3.12.1 and 3.12.2 are to be included.

Resnonse: In 1996, Revision 16 was made to the ODCM. As part of this revision a number of minor changes were made to the REMP. These changes were made to clear up several inconsistencies within Chapter 4 of the ODCM.

These changes in Table B.4-1 are: l

• Air sample AP/CF-2-Name change to sampler location

• Sediment Sample Point (SE-07) was defined as not being required for the REMP as defined in Part-A of the ODCM. l 1

= Milk sample location (TM-08) was redefined as (TM-09). I e

The location for TLD (monitor) TL-30 was redefined.

Also, due to the reduction of the U.S. EPA's involvement in the Intercomparison Program, an independent vendor (Analytics) has been included in the cross-check program. The Analytics samples are for air, milk and water matrices.

. Revised the nomenclature for various position titles.

• Revised the quarterly composite analysis requirements in Part A, per previous NRC approval.

• Added Appendix B, Concentrations in Air and Water Above Natural Background.

. Added Appendix C documentation for an alternate computerized option, Method 1 A, for dose calculations.

• Added references to Method 1 A throughout the manual.

. Added sections to the manual describing the Waste Gas System end the Main Condenser Air Evacuation Radiation Monitors, along with the basis for their setpoint.