ML20217P771

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Forwards Annual Radioactive Effluent Release Rept for 1997. Rept Submitted Per TS 6.8.1.4
ML20217P771
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 04/30/1998
From: Feigenbaum T
NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20217P774 List:
References
NYN-98062, NUDOCS 9805070071
Download: ML20217P771 (2)


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1 North North Atlantic Energy Service Corporation I

l 'fg Atlantic h

P.O. Box 300 seehreot, xi10a874 (603) 474-9521 The Northeast Utilities Sr, tem l April 30,1998 l

Docket No.54-443 NYN-98062 AR#97010035 {

l U.S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555-0001 Seabrook Station Annual Radioactive Effluent Release Renort i

North Atlantic Energy Service Corporation (North Atlantic) has enclosed the Annual Radioactive Effluent Release Report for 1997. This report is submitted pursuant to Technical Specification 6.8.1.4. '

The following information is provided in the enclosures:

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Enclosure 1 Effluent release data as required by Regulatory Guide 1.21 Enclosure 2 Joint frequency distributions of wind speed, wind direction and atmospheric stability l

Enclosure 3 Radiation dose assessment Should you have any questions regarding this letter, please contact Terry L. Ilarpster, Director of Licensing Sen ices, at (603) 773-7765.

Very truly yours, NORTII ATLANTIC ENERGY SERVICE CORP.

/ .4)^ 06.7 /W Tdf C. F6fgenbaum /

Executive Vice Phident and dy bg6 Chief Nuclear Officer 9805070071 998430 P9R ADOCK 05000443 R PDR L

U.S. Nuclear Regulatory Commission NYN-98062 / Page 2 cc:

II. J. Miller, NRC Region 1 Administrator C. W. Smith, NRC Project Manager, Project Directorate 1-3 l R. K. Lorson, NRC Senior Resident Inspector l

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ENCLOSURE I TO NYN-98062 I

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l l l l EFFLUENT AND WASTE DISPOSAL ANNUAL IIEPORT I

Supplemental information 1997 l

l Facility: Sea'orook Station Unit i Licensee: North Atlantic Energy i i Sen' ice Corporation .

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1. Regulatorv Limits  !

I A. Gaseous Efnuents l

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a. 5.0 mrad per quarter gamma air dose. O
b. 10.0 mrad per quarter beta air dose,
c. 7.5 mrem per quarter to any organ.

IL Liquid Ef0uents -

a. 1.5 mrem per quarter total body.
b. 5.0 mrem per quarter any organ.
c. 2.0E-04 pCi/ml dissolved or entrained gas.

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2. Maximum Pennissible concentrations  !

l Provide the MPCs used in detennining allowable release rates or concentrations.

a. Fission and activation gases: 1 MPC
b. lodines: 1 MPC
c. Particulates, half-lives > 8 days: 1 MPC
d. Liquid Efnuents: 1 MPC 1
3. Average Energy Not applicable l l
4. Measurements and Annroximations of Total Radioactivity Provide the methods used to measure or approximated the total radioactivity in efnuents and the methods l used to detennine radionuclide composition.  ;

A. Fission and activ tion gases: Determined by gamma spectroscopy. Total error is based on sta .k Dow error, analydcal error, analytical error and calculated sampling error.

It lodines: Determined by collection on charcoal with subsequent gamma spectroscopy analysis.

Total error is based on stack Dow error, analytical error and calculated sampling error.

l C. Particulates: Detennined by collection on fixed filter with subsequent gamma spectroscopy j analysis. Strontium is determined by composite analysis of ulters by liquid scintillation, gross alpha by proportional counter, and iron 55 by liquid scintillation. Total error is based on stack Dow error, anc.lytical error and calculted sampling error.

D. Liquid Ef0uents: Determined by gamma spectroscopy. A composite sample is analyzed for strontium by liquid scintillation, tritium by liquid scintillation, gross alpha by proportional counter, and iron 55 by liquid scintillation. Total error is based on the volume discharge error and analytical error.

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

A. Liquid  !

a. Number of be:h releases: 132
b. Total time for batch releases: 34938 minutes
c. Maximum time period for ba:ch release. 2000 minutes
d. Average time period for batch rdease: 263 minutes
e. Minimum time period for batch release: 21 minutes
f. Average stream flow during periods of release of effluents into a flowing stream:  !

1.50E+06 liters per minute B. Gaseous

a. Number of batch releases: 75
b. Total time for batch releases: 36700 minutes
c. Maximum time period for batch release: 5520 minutes I
d. Average time period for batch release: 503 minutes I
e. Minimum time period for batch release: 1 minute l
6. Abnormal Releases A .. Liquid
a. Number of releases: 0
b. Total activity released: N/A B. Gaseous
a. Number ofreleases: 0
b. Total activity released: N/A f

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TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997 GASEOUS EFFLUENTS-SUMMATION OF RELEASES Unit Quarter Quarter Quarter Quarter Est. Total 1 2 3 4 Error, %

A. Fission and activation gases l 1. Total releases C1 4.44E+01 5.34E+02 3409E+00 3.96E-01 1.70E+01l

2. Average release rate ucs/sec 5.70E+00 6.79E+01 3.89E-01 4.98E-02 for period
3. Percent of applicable  % 1.41E-02 2.29E-1 2.26E-3 3.94E-04 Technical Specification limit B. Iodines
1. Total release Ci 2.27E-06 9.01E-04 6.39E-05 ND 1.50E+01l
2. Average release rate uctisec 2.92E-07 1.16E-04 8.22E-06 NA for period
3. Percent of applicable  % 1.63E-02 2.04E-Oi 6.55E-02 4,41E-02 Technical Specification I

limit C. Particulates

1. Total release Ci ND 1.13E-04 1.96E-05 1.64E-05 1.80E+01l
2. Average release rate uCaisac NA 1.46E-05 2.52E-06 2.11E-06 for period t 3. Percent of applicable  % 1.63E-02 2.04E-01 6.55E-02 4.41E-02 l l Technical Specification

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4. Total alpha radioactivity Ci ND ND ND ND D. Tritium I
1. Total release Ci 9.33E+C0 2.72E+01 2.71E+01 2.42E+01 1.60E+01l l 2. Average release rate uct/sec 1.20E+00 3.46E+00 3.41E+00 3.04E+00 l for period
3. Percent of applicable  % 1.63E-02 2.04E-01 6.55E-02 4.41E-02 l Technical Specification limit l

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! TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1997)

GASEOUS EFFLUENTS-ELEVATED RELEASES CONTINUOUS Naclides Released Unit Quarter Quarter Quarter Quarter

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1. Fission and activation gases argon-41 Ci ND ND ND ND krypton-85 C1 1.17E+00 4.42E-01 ND ND krypton-85m Ci 7.95E-01 1.67E-01 ND ND krypton-87 C1 1.91E-02 1.53E-01 ND ND krypton-88 Ci 3.25E-02 2.35E-01 ND ND xenon-131m Ci ND ND ND ND xenon-133 Ci 2.97E+01 4.35E+02 1.79E+00 ND xenon-133m Ci 1.86E-03 6.65E-01 ND ND xenon-135 Ci 1.23E+01 1.18E+01 8.56E-01 ND xenon-135m Ci 9.23E-03 6.51E-01 ND ND xenon-138 Ci ND ND ND ND Ci Ci I unidentified Ci ND ND ND ND Total for period Ci 4.40E+01 4.49E+02 2.65E+00 0.00E+00
2. Iodines iodine-131 Ci ND 7.74E-04 6.39E-05 ND iodine-133 Ci ND 3.02E-05 ND ND iodine-135 Ci ND ND ND ND Total for period Ci 0.00E+00 8.04E-04 6.39E-05 0.00E+00
3. Particulates strontium-89 Ci ND ND 1.43E-05 1.64E-05 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 5.61E-05 5.28E-06 cobalt-60 Ci ND ND ND ND chromium-51 Ci ND ND ND ND manganese-54 Ci ND ND ND ND niobium-95 Ci ND ND ND ND iron-59 Ci ND ND ND ND unidentified Ci ND ND ND ND Total for period C1 0.00E+00 5.61E-05 1.96E-05 1.64E-05

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 997)

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

1. Fission and activation gases argon-41 Ci 2.27E-02 5.80E-02 1.23E-01 ND krypton-85 Ci ND 1.59E+00 ND ND krypton-85m Ci ND 5.22E-02 3.18E-04 ND krypton-87 Ci ND ND ND ND krypton-88 Ci ND ND 5.70E-04 ND xenon-131m Ci 2.49E-04 9.59E-01 ND ND xenon-133 Ci 2.93E-01 7.95E+01 3.08E-01 3.81E-01 xenon-133m Ci 7.80E-03 7.61E-01 ND 2.09E-03 xenon-135 Ci 5.63E-03 1.88E+00 1.48E-02 9.37E-03 xenon-135m Ci ND ND ND ND xenon-138 Ci ND ND ND ND Ci unidentified Ci ND ND ND ND Total for period Ci 3.29E-01 8.48E+01 4.47E-01 3.92E-01
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 0.00E+00 0.00E+C0 0.00E+00 0.00E+00
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 C1 ND ND ND ND barium-lanthanum-140 Ci ND ND ND ND Ci unidentified Ci ND ND ND ND Total for period Ci ND ND ND ND

l TABLE 1B l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1997)

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES BATCH Nuclides Released Unit Quarter Quarter Quarter Quarter 1 2 3 4 l

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1. Fission and activation gases argon-41 Ci ND ND ND ND l

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-131m Ci ND 1.21E-04 ND ND xenon-133m Ci ND 3.42E-05 ND ND xenon-133 Ci ND 9.36E-02 ND 3.51E-03 xenon-135 Ci ND ND ND ND xenon-135m Ci ND 1.41E-03 ND ND xenon-138 Ci ND ND ND ND Ci Ci unidentified Ci Total for period Ci ND 9.52E-02 ND 3.51E-03

2. Iodines iodine-131 Ci ND 4.16E-05 ND ND iodine-132 Ci ND 1.27E-05 ND ND iodine-133 Ci ND ND ND ND iodine-135 Ci ND ND ND ND Total for period Ci 0.00E+00 5.43E-05 0.00E+00 0.00E+00
3. Particulates strontium-89 Ci ND ND ND ND strontium-90 Ci ND ND ND ND cesium-134 Ci ND ND ND ND cesium-136 Ci ND ND ND ND cesium-137 Ci ND 1.27E-09 ND ND barium-lanthanum-140 Ci ND ND ND ND cobalt-57 Ci ND 2.15E-08 ND ND cobalt-58 Ci ND 1.81E-05 ND 6.67E-10 cobalt-60 Ci ND 5.47E-07 ND 5.90E-10 manganese-54 Ci ND 3.28E-07 ND ND l iron-59 Ci ND 2.29E-07 ND ND niobium / zirconium-95 Ci ND 1.14E-06 ND ND chromium-51 Ci ND 6.61E-06 ND ND technetium-99m Ci ND 3.08E-08 ND ND bromine-82 Ci ND ND ND 5.08E-09 unidentified Ci ND ND ND ND Total for period Ci ND 2.70E-05 0.00E+00 6.34E-09

1 TABLE IB I EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1997)

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS Nuclides Released Unit Quarter Quarter Quarter Quarter 1 2 3 4

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 l xenon-133 Ci ND ND ND ND I xenon-135 Ci ND ND ND ND xenon-135m Ci ND ND ND ND xenon-138 Ci ND ND ND ND Ci l

l Ci unidentified Ci ND ND ND ND Total for period Ci ND ND ND ND l

2. Iodines iodine-131 Ci 7.32E-07 3.20E-05 ND ND iodine-133 Ci 1.54E-06 1.09E-05 ND ND Ci Total for period Ci 2.27E-06 4.29E-05 ND ND
3. Particulates strontium-89 Ci ND ND ND ND strontium-90 Ci ND ND ND ND cesium-134 Ci ND 6.58E-06 ND ND cesium-136 Ci ND 1.78E-06 ND ND cesium-137 Ci ND 5.26E-06 ND ND barium-lanthanum-140 Ci ND ND ND ND cobalt-58 Ci ND 1.60E-05 ND ND cobalt-60 Ci ND 2.04E-07 ND ND manganese-54 Ci ND 5.16E-07 ND ND unidentified Ci ND ND ND ND Total for period C1 NU 3.03E-05 ND IO i

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997 LIQUID EFFLUENTS-SUMMATION OF RELEASES i

~. ... . 1 -t.., . . . . . . , . .. .. . E. . ~1 arror, 4 A. Fission and activation products

1. Total releases ca 1.66s 02 2.40s-o2 1.61s-02 s a4s-o2 6.oos.oo
2. Average diluted concentration uC2/mi 4.45s-11 1.43E 10 7.255-11 3.69E 11 during period
3. Percent of applicable limit 4 1.2vs-u2 1.54h-o2 1.17E-02 4.13s-c)

B. Tritium

1. Total release C1 4.198 02 2.oss 02 5.79E.02 1.29s 02 a.ocE.oo
2. Average diluted concentration uClimi 2.oss-06 1.59E-u6 2.52E-06 s.24s-07 during period 3- Percent of applicable 11 mat 6 1.2CE-02 1.64s-02 1.)?E-02 4.13s-0)

C. Dissolved and entrained gases I

1. Total release Ci v.44E-04 2.018-02 g g 1,90E+01
2. Average diluted concentration uC1/ ml 4.stE-12 1.51E-10 kA NA during period
3. Percent of applicable limit 6 2.40E-06 7.6hE-oh NA NA D. Gross alpha radioactivity
1. Total release Ca ND ND ND ND 1.06E.01 E, volume of wasta lit.ra 1.66a.o? 2.16s.07 2.uum.07 2.74E.07 1.1eh.00 released (prior to dilution)

F. Volume of dilution lit.rs 1.9?E.11 1.31E.11 2.los.11 2.46E+11 9.ocs.uu water used during period i

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I TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997 l

LIQUID EFFLUENTS

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Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 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 5.21E-04 1.76E-04 2.46E-05 iodine-131 Ci 8.21E-04 6.12E-04 ND ND l iodine-133 C1 1.98E-04 4.60E-05 ND ND 1

cobalt-57 Ci ND 2.84E-05 5.43E-06 ND cobalt-58 Ci 3.96E-04 9.13E-03 6.79E-03 2.85E-03 cobalt-60 Ci 1.70E-03 2.36E-03 4.34E-04 5.44E-04 chromium-51 C1 4.13E-05 8.11E-05 ND ND iron-55 Ci 3.93E-03 4.29E-03 4.01E-03 2.44E-03 l iron-59 Ci ND ND ND ND zinc-65 Ci ND ND ND ND manganese-54 Ci 9.77E-05 1.86E-04 ND 4.74E-05 zirconium-niobium-95 Ci ND 2.07E-05 ND 1.34E-05 molybdenum-99 Ci ND ND ND ND technetium-99m Ci 4.97E-06 ND 1.72E-06 ND barium-lanthanum-140 Ci ND ND ND ND cerium-141 Ci ND ND ND ND antimony-124 Ci 6.85E-06 ND 7.81E-04 1.52E-04 antimony-125 Ci 9.27E-03 4.61E-03 3.88E-03 2.77E-03 niobium-97 Ci ND 1.86E-05 ND ND tin-117m Ci ND 4,07E-05 ND ND sodium-24 Ci ND ND 3.07E-06 ND l unidentified Ci ND ND ND ND l Total for period (above) l Ci l 1.65E-02 l 2.19E-02 l 1.61E-02 l 8.84E-03 l xenon-133 Ci 8.63E-04 1.02E-03 ND ND xenon-135 Ci 8.45E-05 7.75E-05 ND ND i

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I TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997 LIQUID EFFLUENTS CONTINUOUS MODE I

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 strontium-89 Ci ND ND ND ND i strontium-90 Ci ND ND ND ND cesium-134 Ci ND 2.54E-04 ND ND cesium-137 Ci ND 2.63E-04 ND 1.52E-07 iodine-131 Ci 6.50E-05 8.19E-04 ND ND iodine-133 Ci 1.10E-04 7.01E-04 ND ND cobalt-58 Ci ND 3.94E-05 6.00E-04 4.01E-07 cobalt-60 Ci ND 1.98E-06 1.74E-06 ND iron-59 Ci ND ND ND ND zinc-65 Ci ND ND ND ND j manganese-54 Ci ND ND ND ND chromium-51 Ci ND ND ND ND zirconium-niobium-95 Ci ND ND ND ND molybdenum-99 Ci ND ND ND ND technetium-99m Ci ND ND ND ND barium-lanthanum-140 Ci ND ND ND ND cerium-141 Ci ND ND ND ND l unidentified Ci ND ND ND ND

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l Total for period (above)l Ci l 1.75E-04 l 2.08E-03 l 6.02E-04 l 5.53E-07 l xenon-131m Ci ND 2.47E-04 ND ND xenon-133m Ci ND 7.88E-05 ND ND xenon-133 Ci ND 1.85E-02 ND ND xenon-135 Ci ND 1.44E-04 ND ND l

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997 SOLID WASTE AND IRRADIATED FUEL SilIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURI AL OR DISPOSAL (Not Irradiated Fuel)

1. Type of waste (no shipment made) Unit Est. total error %

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a. Spent resins, filter sludges, evaporator - Om E
bottoms, etc. Ci
b. Dry compressible waste, contaminated 3

equip., etc. Om E Ci

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e. Irradiated components, control rods, etc. l; 3

Om E Ci

d. Other (describe)  !

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Om E Ci

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

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3. Solid Waste Disposition i

Number of shinments Mode of transnortation Destination None

I LIST OF APPENDICES Apautdis Iith A Offsite Dose Calculation Manual B Process Control Program C Radioactive Liquid Effluent Monitoring Instrumentation D Radioactive Gaseous Effluent Monitoring instrumentation E Liquid lioidup Tanks F Radwaste Treatment Systems G Unplanned Releases 11 Corrections to Prior Annual Radioactive Effluent Release Reports i

1 Appendix A Offsite Dose Calculation Manual Requirement:

l Technical Specification 6.13.2.b requires that licensee initiated changes to the Off-Site Dose Calculation Manual be submitted to the Commission in the Annual Radioactive Efiluent Release Report for the period in which the changes was/were made effective. Include in this changes to the Radiological Environmental Program in accordance with Technical Specifications 3.12.1 and 3.12.2.

Resoonse:

During 1997, the following changes to the REMP section of the ODCM were made. These changes were made to the ODCM to more fully reDect the actual program and notjust Technical Specification required locations. These changes were reviewed and approved by the Station's SORC (# 97-143) on November l 12,1997. These additions to Table B.4-1 of the ODCM reflect sample locations that were always a part of the program but are not required by Technical Specifications.

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  • Air Sample Locations AP/CF -07 & -08 have been included in Table B. 4-1 of the ODCM as alternate / backup locations.

Milk Location TM-21 has been included in Table B. 4-1 of the ODCM, as a control backup location.

Invertebrate (mussel -mytilus) Location MU-09 has been included in Table B.4-1 of the ODCM, as an indicator backup location. This species is an intertidal species ar;d 4 not part of the sampling program as required by Technical Specifications.

. Invertebrate (mussel - mytilus) Location MU-59 has been included in Table B.4-1 of the ODCM, as I a control backup location.

Milk Location TM-08 was added to the program in March 1997. This is indicated in Table B.4-1 of the ODCM. This location is an indicator station and has the highest ranked (cakulated) critical organ dose.

This location was part of the program until 1994-when the owner sold off her herd and temporarily left the business. This addition is in response to the return of milk production at this location.

Section Clarified the method to calculate RM-6509 setpoir.ts for Waste Test Tank 5.1.1.1 & discharges. Specifically, added beta emitters to the setpoint calculation Section 8.1 methodology. Previously the setpoint was calculated using gamma; beta was included in the ODCM definition but not specifically identified.

Clarified the term MPC, to indicate the most restrictive MPC for an

" unidentified" mixture or a mixture known not to contain certain radionuclides as given in 10CFR20 Appendix B, notes.

r Section Defined the unidentified mix MPC as the most restrictive MPC for an 5.1.2 " unidentified" mixture or a mixture known not to contain certain radionuclides as given in 10CFR20 Appendix B, notes.

Section 6 Modified the Turbine gland seal exhauster release description to reDect current status of being a monitored release path. The noble gas released is periodically monitored via grab samples, and a ratio between the Condenser air evacuation

) and turbine gland exhaust will be determined periodically.

The changes to Section 5.1.1.1 and Section 8.1 were clarifications to ensure that beta emitters where used to determine maximum discharge rates and radiation monitor setpoints.

Section 5.1.2 was changed to give better clari6 cation for the selection of the most restrictive MPC for an "unidentiGed" mixture or a mixture known not to contain certain radionuclides as given in 10CFR20 Appendix B.

Section 6 was changed to add a better description of this efDuent release point.

The changes that were made to the ODCM in 1997 do not reduce the accuracy or reliability of dose calculations or set point determinations.  !

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