ML20065Q753

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Effluent & Waste Disposal Annual Rept 1993, Seabrook Station Unit 1
ML20065Q753
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 12/31/1993
From: Feigenbaum T
NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:
Shared Package
ML20065Q755 List:
References
NYN-94053, NUDOCS 9405060002
Download: ML20065Q753 (13)
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Text

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Page 1 EFFLUENT AND WACTE DISPOSAL ANNUAL REPORT Supplemental Information 1993 Facility: Seabrook Station Unit 1 Licensee: North Atlantic Energy Service Corporation

1. Regulatory Limits A. Gaseous Effluents
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 Effluents

a. 1.5 mrem per quarter total body
b. 5 mrem per quarter to any organ.
2. Maximum Permissible Concentrations Provide the MPC's used in determ!nsng 3COWable releases rates or concentrations.
a. Fission and activation gases: 1 MPC
b. lodines: 1 MPC
c. Particulates, half-lives > 8 days: 1 MPC
d. Liquid effluents: 1 MPC
3. Average Enerav Not applicable.

94o5060002 940429 PDR ADOCK 05000443 R PDR

Page 2

4. Measuremery and ADDroximations of Total Radioactivity Provide th ~ methods used to measure or approximate the total radioactivity in effluents ind the methods used to determine radionuclide composition.
a. Fision and activation gases: Determined by gamma spectroscopy. Total E 'for 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
1. Number of batch releases:165 l
2. Total time for batch releases: 32940 minutes
3. Maximum time period for batch releases: 522 minutes
4. Average time period for batch release: 200 minutes i
5. Minimum time period for a batch release: 75 minutes
6. Average stream flow during periods of release of effluent into a flowing stream: 1.54E06 liters per minute.
b. Gaseous
1. Number of batch releases: 49
2. Total time period for batch releases: 3836 minutes
3. Maximum time period for a batch release:1685 minutes
4. Average time period for batch releases: 78 minutes
5. Minimum time period for a batch releases: 1 minute
6. Abnormal Releases
a. Liquid
1. Number of releases: 0
2. Total activity releases: N/A
b. Gaseous
1. Number of releases: 0
2. Total activity released: N/A

TABLE 1 A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES UNIT OUARTER QUARTER QUARTER QUARTER Est. Total SEABROOK STATION 2 4 1 1 3 Error, %

A. Fission & Activation Gases

1. Total release o 1,96e-02 5.46e-02 1.24e-02 2.29e-02 1.70E + 01
2. Average release rate for period pCI/sec 2.55e-03 6.94e-03 1.56e-03 2.88e-03 3 percent of technical specification hmit  % 2.3E-03 4.32 E-03 3.38E-04 2.08E-03 (1) (1) (1) (1)

B. lodines

1. Total iodine Cl ND ND ND ND 1.50E + 01 i
2. Average release rate for period pCi/sec NA NA NA NA f

l 3 Percent of technical specification limit  % NA NA NA NA l

C. Particulates i

1 Pancuiates witn nait iives >s days a ND ND 2.57E-07 4.03E-07 1.80E + 01

2. Average release rate for penod pCl/sec NA NA 3.23E 08 5.07E-08 3 Percent of technical specification kmrt  % 1.95E-03 3.99E-04 8.04E-04 8.93E-03
4. Cross alpha radioactivity Cl ND ND ND ND D. Tritium
1. Totai reiease Ci 1.62 E-03 3.90E-03 7.41E 03 6.20E-01 1.60E + 01 2 Average reiease rate for period uCi/sec 2.11 E-04 4.96E-04 9.35E-04 7.80E-02 3 Percent of tecnnical specification limit  % 1.95E-03 3.99E-04 8.04E-04 8.93E-03 1

(1) Gamma Air Dose

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 GASEOUS EFFLUENTS-MIXED RELEASES-CONTINUOUS MODE

1. Fission and Activation Cases Nuclides Released Unit ouarter ouarter ouarter ouarter 1 1 2 3 4 krypton-Bs Cl ND ND ND ND krypton-85m Cl ND ND ND ND krypton 87 Ci ND ND ND ND krypton-88 Cl ND ND ND ND xenon-133 Cl ND ND ND ND xenon-135 Cl ND ND ND ND xenon-135m Cl ND ND ND ND xenon 138 Ci ND ND ND ND argon-41 Cl ND ND ND ' ND unidentified Cl ND ND ND ND Total for period Cl ND ND ND NO
2. lodines iodine-131 U ND ND ND ND lodine-133 Ci ND ND ND ND iodine-135 Cl ND ND ND ND Total for period Cl ND ND ND ND
3. Particulates strontium-89 Cl ND ND ND ND strontium-90 Cl ND ND ND ND cesium 134 Cl ND ND ND ND cesium 137 Cl ND NO ND ND barium / lanthanum 14D Cl ND ND ND ND nioblum-95 Cl ND ND ND ND zirconium-95 Cl ND ND ND ND cobalt 58 Cl ND ND ND ND cobalt 60 Cl ND ND ND ND chromium 51 Cl ND NO ND ND Iron-59 Cl ND ND ND ND manganese-54 Cl ND ND ND ND beryllium 7 Cl ND ND ND ND unidentified Cl ND ND ND ND Total for period ND ND ND ND

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE I l

1. Fission and Activation Cases Nuclides Released Unit Quarter Quarter Quarter Quarter 1 1 2 3 4 i

I krypton 85 Cl ND NC ND ND krypton-85m Cl ND ND ND ND krypton-87 Cl ND ND ND ND l krypton 88 Cl ND ND ND ND xenon 133 Cl ND ND ND ND i

I xenon 135 Cl ND ND ND ND j l

xenon 135m Cl ND ND ND ND 1 xenon 138 Cl ND ND ND ND argon 41 Ci ND ND ND ND l

Unidentified Ci ND ND ND ND Total for period Cl ND NO ND ND

2. lodines lodine 131 Ci ND ND ND ND iodine 133 Ci ND ND ND ND lodine-135 Cl ND ND ND ND Total for period Ci ND ND ND ND I i
3. Particulates strontium-89 Cl ND ND ND ND strontium-90 Cl ND ND ND ND cesiurn 134 Ci ND ND ND ND cesium 137 Cl ND ND ND ND barium / lanthanum 140 Cl ND ND ND ND niobium-95 Cl ND ND ND ND zirconium-95 Ci ND ND ND ND cobalt 58 Cl ND ND 1.97E-07 4.03E 07 cobalt 60 Cl ND ND ND ND chromium-51 Ci ND ND ND ND Iron-59 Cl ND ND ND ND manganese-54 Cl ND ND G.03E-08 ND Total for this period Cl ND ND 2.57E-07 4.03E-07

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TABLE 1C

! EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 l GASEOUS EFFLUENTS-MIXED LEVEL RELEASES-BATCH MODE l

1. Fission and Activation Cases

! Nuclides Released Unit Quart 3r Quarter Quarter Quarter 1 1 2 3 4 krypton 85 Ci krypton 85m Cl 3 37E44 1.56E43 ND 3.34E44 krypton-87 Cl 192E43 3.61E43 ND 7.87E44 krypton 88 Cl 9.79E44 4 02E43 ND 7.73E44 xenon 133 Cl 1.41E 03 9.18E43 6.85E43 2.80E43 xenon 135 Cl 2 30E 03 9 65E 03 2.39E45 3 71E45 xenon 135m Cl 9.55E 04 3.84E43 2.80E 03 7.90E 03 l

xenon 138 Cl 4.36E 03 1.20E-02 ND 2.35E 03 argon-41 Ci 7.23E43 1.07E42 1.35E 04 4 28E-03 xenon 133m Cl ND ND 1.83E-04 ND unidentified Cl ND ND ND ND Total for period Cl 1.96E42 s 465 02 1.24E-02 2.29E-02

2. lodines lodine-131 Cl ND ND ND ND lodine 133 Cl ND NO ND ND i

lodine-135 Ci ND ND ND ND l

i Total for period Cl ND ND ND ND

3. Particulates ,

l strontium-89 Cl ND ND ND ND strontium 90 Cl ND ND ND ND 1

Cesium 134 Cl ND ND ND ND cesium-137 Cl ND ND ND ND barium / lanthanum 140 Cl ND ND ND ND 1

niobium-95 Cl ND ND NO ND zirconlum-95 Cl ND ND ND ND cobalt-58 Ci ND ND ND ND cobalt-60 Cl NO NO ND ND chromium-51 Cl ND ND ND ND Iron-59 Cl ND ND ND ND manganese-54 Cl ND ND ND ND beryllium-7 Cl ND ND ND ND unidentified Cl ND ND ND ND Total for period ND ND ND ND

TABLE 1C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES-BATCH MODE

1. Fission and Activation Gases i

Nuclides Released Unit Quarter Quarter Quarter Quarter 1 1 2 3 4 krypton-85 Cl ND ND ND ND krypton-85m Cl ND ND ND ND krypton-87 Cl ND ND ND ND krypton 88 Cl ND ND ND ND xenon-133 Cl ND ND ND ND xenon-135 Cl ND ND ND ND xenon-135m Ci ND ND ND ND xenon-138 Ci ND ND ND NO argon-41 CI ND ND ND ND unidentified Cl ND ND ND NO Total for period Cl ND ND ND ND 2, lodines iodine 131 Cl ND NO ND ND iodine 133 Ci ND ND ND ND lodine 135 Cl ND ND ND ND Total for period Cl ND ND ND ND

3. Particulates strontium-89 Cl ND ND ND ND strontium-90 Ci ND ND ND ND cesium-134 Cl ND ND ND ND ceslum 137 Cl ND ND ND ND banum/ lanthanum 140 Cl ND ND ND ND niobium-95 Ci ND ND ND ND Zirconlum 95 Cl ND ND ND ND cobalt-58 Cl ND ND ND ND cobalt 60 Cl ND ND NO ND chromium 51 Cl ND ND ND ND tron 59 Cl ND ND ND ND manganese-54 Ci ND ND ND ND beryllium-7 Cl ND ND ND ND unidentified Ci ND ND ND ND Total for period Cl ND ND ND ND

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

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TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 j LIQUID EFFLUENTS SUMMATION OF ALL RELEASES UNIT 1 OUARTER QUARTER QUARTER QUARTER Est. Total SEABROOK STATION 4 1 2 3 Error, %

A. Fission & Activation Products 1, rotal release <not including tritium, o 3.99E-02 3.12E-02 1.29E-02 6.03E-03 6.00E + 00 gases. alphal 2 Average diluted concentration during vClimi 2.12E 10 1.48E-10 6.42E-11 3.17E-11 period i

3. Percent of appucacie limit  % 6.66E-02 5.80E 02 1.94E-02 8.4E-03 (2) (2) (2) (1)

B. Tritium

1. Total Release 0 1.27E + 02 1.59E + O2 5.87E + 01 2.18E + O2 8.00E + 00
2. Aymge D'LU1ED CON (ENTRAftON DU41NG MCUML 6.75E-07 7.54E-07 2.92E-07 1.15E 06 PE RiOD
3. PERCENT OF APPitCABLE LtMir  % 6.66E-02 5.80E 02 1.94E-02 8.4 E-03 (2) (2) -(2) (1)

C. DISSOLVED AND ENTRAINED GASES

1. TOT AL RnE ASE Cl ND ND ND 1.17 E-05 1.90E + 01
2. AvtRAGE DRUffD cONUNMATION DUmNG MCat NA NA NA 6.16E 14 PERIOD
3. Pr acENT of ^"Pttc A8t f L'Mi t  % NA NA NA 3.1 E-08 l

1 D. Gross Alpha Radioactivity

1. Toint rninase ci ND ND ND ND 1.00E + 01 E Volunw of mste releasadiver>r to dilutiord liters 4.31 E + 07 4.32E + 07 3.92E + 07 4.26E + 07 1.30E + 00 F. Volume of dilution water used hters 1.88E + 11 2.11 E + 11 2.01 E + 11 1.90E + 11 9.00E + 00 during period

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 LIQUID EFFLUENTS - CONTINUOUS NUCllde5 released units Quarter Quarter Quarter ouarter 1 2 3 4 strontium-89 Ci ND ND ND ND strontium-90 Cl ND ND ND ND cesium-134 Cl ND ND ND ND cesium 137 Cl ND ND ND ND iodine-131 Cl ND ND ND ND lodine-133 Cl ND ND ND ND cobalt-58 Cl ND ND ND ND cobalt-60 Cl ND 1.72E-05 ND ND iron-55 Cl ND ND ND ND iron-55 Cl ND ND ND ND sinc 65 Cl ND ND ND ND manganese-54 Cl ND 1.86E-06 ND ND chromium-51 Cl ND ND ND ND nibium-97 Ci ND ND ND ND xirconium niobium 95 Ci ND ND ND ND berylium 7 Cl ND ND ND ND technetium-99m Ci ND ND ND ND antimony-124 Cl ND ND ND ND l antimony-125 Cl ND ND ND ND bromine-82 Cl ND ND ND ND sodium-24 Cl ND ND ND ND cesium 137 Cl ND ND ND ND molybdenum-99 Cl ND ND ND ND barium-lanthanum-140 Cl ND ND ND ND cenum-141 Cl ND ND ND , ND undidentified Cl ND ND ND ND total for period Cl ND 1.91E 05 ND ND CI Ci xenon 133 Ci ND ND ND ND xenon 135 Cl ND ND ND ND i

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TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 LIQUID EFFLUENTS - BATCH NUCLlDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER 1 2 3 4 STRONTIUM-89 Cl ND ND ND ND strontium-90 Ci ND ND ND ND cesium-134 Cl ND ND ND ND cesium 137 Ci ND ND ND ND lodine-131 Cl 1.36E-04 3.49E-06 ND ND iodine 133 Cl 1.16E-04 ND 1.35E46 1.94E 06 cobalt 58 Cl 3.97E-03 2.82E-03 9.74E-04 2.17E43 cobalt-60 Ci 7.18E-04 5.50E-04 2.04E 04 5.22E 04 fron-59 Ci 5.02E 04 2.17E-04 ND 7.56E-06 Iron-55 Cl 2.97E-02 2.43E-02 1.17E 02 ND manganese-54 Cl 2.55E-04 2.44E-04 4.18E-05 4.88E44 chromium-51 Cl 1.65E-04 ND ND ND niobium-97 Cl 3.32E 06 ND ND 1.90E-05 xirconium-niobium-95 Cl 3.08E 5 6.74E-06 ND ND berylium-7 Ci 1.17E 04 ND ND ND technetium-99m Cl 1.58E 05 1.60E-05 ND 2.59E-06 antimony-124 Cl 8.24E-05 6.32E-04 ND ND antimony 125 Cl 3.98E-03 2.03E 03 ND 2.82E-05 bromine-82 Ci 1.03E-04 7.25E46 ND ND sodium-24 Cl 2.05E 05 ND ND ND cesium 137 Cl ND 3.30E-05 ND ND unidentified Ci ND ND ND ND total for period Ci 3.99E-02 3.12E-02 1.29E-02 6.03E 03 Cl Cl Cl Ci Ci xenon-133 Cl ND ND ND ND xenon 135 Ci ND ND ND 1.17E-05

TABLE 3 l

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

Unit First Est. Total 6-month Error. %

1. Type of waste NOM Period
a. Spent resins. filter sludges, evaporator 0m 3 NONE bottoms, etc 0 Ci
b. Dry compressible waste. contaminated 0 ri 3 NONE equip, etc 0 Ci
c. Irradiated components. control rods etc 0 m' NONE O C1 3
d. Other (described) 0m NONE C C1
2. Estimate of major nuclide composition (by type of waste)
a. N/A l

I b.

l 1

I c.

l d.

i l

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3. Solid Waste Disposition NJmbor of ShiDments Mo@ of Transportation Destination NONE j l

B. IRRADIATED FUEL SHIPMENTS (Disposition)

N;mber of ShfDrints Mode of Transportation Dostination NONE l

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.,a .a - . .. . a -- - - n -,--- ...c. -u. ..-.. . , ... . . - ..-.. . _ . . _ - . - . ,.

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APPENDIX A l

Off-Site Dose Calculation Manual Requirement: Technical Specification 6.13.2.b requires that licensee initiated changes to the Off Site l

! Dose Calculation Manual (ODCM) be submitted to the Commission in the Annual l Radioactive Ellluent Release Report for the period in which the change (s) was made efTective. Changes made to the Radiological Environmental Monitoring Program (REMP) in accordance with Technical Specification 3.12.1 and 3.12.2 are to be included.

I Response: Two revisions to the ODCM were made effective during the reporting period.

Revision 12 The Method 1 gaseous dose calculations were revised so that short term hatch release .

doses would be more accurately determined. Several typographical errors were also corrected.

Revision 13 Periodic review. No changes.

l A complete copy of the ODCM is enclosed for simplicity of review due to the extensive number of pages effected by Revision 12.

l No changes were made to the Radiological Environmental Monitoring Program during this reporting period.

l l

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