ML20114B780

From kanterella
Jump to navigation Jump to search
Semiannual Radioactive Effluent Release Rept,Jan-June 1992
ML20114B780
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 06/30/1992
From: Feigenbaum T
NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-92117, NUDOCS 9208310228
Download: ML20114B780 (23)
v • d • e


Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Odii Eea'o%x".Yno2874 f

Telephone (603) 474 9521 a

_cs.. %g j jh

[

Facsimile (603)474 2987 Energy Sorvico Corporation Ted c. I eigenbaum Senior Vice President and Chief Nuclear Officer NYN-92117 August 28, 1992 United States Nuclear llet;ulatory Commission V'ashington, DC 20555 Attention:

Document Control Desk iteferences:

(a)

Facility Operating License No. NPF-86, Docket No. 50 443 (b)

Seabrook Station Technical Specification 6.8.1.4, *Semiennual Radioactive Effluent Release Report"

Subject:

Seabrook Station Semiannual Radioactive Elfluent Release Report Gentlemen:

in accordance with the requirements of Technical Specification 6.8.1.4 [ Reference (b)l, the Seabrook Station Semiannual Radioactive !!ffluent Release Report is provided as.

This report is submitted for the reporting period beginning January 1,1992, and ending June 30, 1992.

The effluent and waste disposal information contained in this report is submitted in the format specified by Appendix B to Regulatory Guide 1.21, Revision 1 (June 1974). The additional information required by Reference (b) is provided as Appendices A through 11 to the report.

Should you have any questions regarding this report, please contact b*-

James M.

Peschel, Regulatory Compliance Manager, at (603) 474-9521, extension 3772.

Very truly yours, W

./

W Ted C. Fe' enbaum Enclosures TCF:ALL/act 9 7 (I n n -

9208310228 920630 a member of the Northeast Utilities system e-PDR ADOCR 05000443 C~.

g PDR If/

Unite'd States Nuclear Regulatory Commission August 28, 1992 I

. Attention: Document Control Desk Page two

. cc:

Mr. Thomas T. Martin -

Regional Administrator United States Nuclear Regulatory Commission Region !

475 Allendale Road King of Prussia, PA 19406 Mr. Gordon E. Edison, St. Project Manager Project Directorate 13 Division of Reactor Projects L

- U.S. Nuclear Regulatory Commission 6:

Washington, DC 20555

- Mr. Noel Dudley

.NRC Senior Resident inspector -

P,0, Ilox 1149 Scabrook, NH :03874 u

bifu 4

h

W u.

North Atlantic

'T Augus'. 28,1992

- ENCL,OSURE 1 TO NYN-92.

h

{ -.

.i E-f

t 4

4

Page 1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information 1992 First and Second Quarters Facility: Seabrook Station Unit 1 Licensee: North Atlantic Ene r gy Service Corporation 1.

Reculatory 1.imit s A.

Gaseous Effluents a.

Fission and activation gases: 5.0 mrad per quarter gamma air dose,10.0 mrad per quarter beta air dose.

b.

Iodines: 7.5 mrem per quarter to any organ, c.

Particulates, half-lives > 8 days: Particula.es and iodines are included in step b.

d.

Tritium: 7.5 mrem per quarter to any organ.

e.

Liquid Effluents:

1.5 mrem per quarter total body and 5 mrem per quarter to any organ, 2.

Maximum Permissible Concentrations The MPC's used in determining allowable releases rates or concentrations are as follows:

Fission and activation gases: 1 MPC a.

b.

lodines: 1 MPC

~

c.

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

Liquid effluents: 1 MPC 3.

Averace Enetcy Not applicable.

4 Measurements and Annroximations of Total Radioactivity The methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition are as follows:

a.

Fission and activation gases-Determined by gamma spectroscopy. Total error is based ou stack flow error, analytical error and calculated sampling error.

b.

Iodines:

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

I Page 2 c.

Particulates: Determined by collection on fixed filter with subsequent gamma spectroscopy analysis. Strontium is determined by con:posite analysis of fiD ars by liquid scintillation, gross alpha by proportional counter, and iror 55 by liquid scintillation. Total error is based on stack flo., 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.

Ilatch Releases The information relating to batch releases of radioactive materials in liquid and gaseous effluents are as follows:

Liquid a.

1.

Number of batch releeses: 59 2.

Total time for batch releases: 11761 minutes 3.

hiaximum time period for batch rcleases: 765 minutes 4 Average time period for batch release: 199 minutes 5.

Niinimum time period for a batch release: 78 n.inutes 6.

Average stream flow during periods of release of effluent into a flowing stream: 1.53 E06 liters per minute.

b.

G aseous 1.

Number of batch releases: 18 2.

Total time period for batch releases: 15948 minutes 3.

hiaxii aum time period for a batch release: 5225 minutes 4.

Average time period for batch releases: 886 minutes 5.

hiinimum time period for a batch releases: 0.5 minutes 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 1A EITLUENT AND WASTE DtSPOSAL SEMANNUAL f1EPCNIT 1992

- GASEOUS EFTlUENTS SUMMATION OF ALL T1ELEASES Unit Quarter Quarter Est. Total SEABROOK STATION 1

1 2

Error %

A. Iission & activation gases 1.

Total release C1 4.60 E-01 2.29 E-01 1.70 E+01 2.

Average release rate for period Cl/sec 5.85 E-02 2.91 E 02 3.

Percent of technical specification limit 1.75 E-03(U 6.T E-04(O B. Iodines 1.

Total lodine-131 Cl ND ND 1.50 E401 2.

Average release rate for period.

pct /sec NA NA 3.

Percent of technical specification limit NA NJ.

C. Particulates 1.

Particulates with half-lives >8 days Cl ND ND 1.80 E+01 2.

Average release rate for period Ct/sec NA NA

3.. Fercent of technical specification Ilmit NA NA 4.

Gross alpha radioactivity Ci ND ND D. Tritium 1.

Total release C1 7.12 E-02 4.11 E-02 1.60 E+01 2.

Average release rate for period gCl/sec 9.06 E-03 5.22 E-03

3. _ Percent t f technical specification limit l

2.60 E-04 1.96 E-04 ND = none detected

- (1) Based on the.gamm air dose.

TABW 1B EFTLUfNT AND WASTE DtSPOSAL SEM1 ANNUAL REPOIIT 1992 GASEOUS EITLUENTS ELEVATED REE/GES

}

CONTINUOUS MDDE BAlCH MDDE Unit Quarter Quarter Quarter Quarter Nuclides Released 1

1 2

1 2

1. Iisston gases krypton-85 Ci ND ND ND ND krypton-85m Cl ND ND 2.01 E-03 ND krypton-87 Cl ND ND 4.46 E-03 ND 6rypton-88 Ci ND ND hD ND xenon 133 Ci ND ND 1.45 E-01 1.05 E -01 xenon-135 Ci ND FD 1.18 E-02 4.24 E-03 xenon-135m Cl NC ND I

1.09 E-02 ND xenon-138 Ci ND ND ND ND Others(specify)

Cl Cl unidentified Ci ND ND ND ND Total for period Ci ND ND 1.74 E-01 1.09 E-01 H. lodites todine-131 Ci ND ND ND ND iodine-133 C1 ND ND NU ND iodine-135 Ci ND ND ND ND Total for period Ci ND ND ND ND C. Particulates strontium-89 Cl ND ND NP ND stront wm-90 Ci ND ND ND ND ceslum-134 Ci ND ND ND ND cesium-137

1 hD ND ND ND barium-lanthanum-140 Ci ND ND ND ND niobium-95 Ci ND ND ND ND cobalt-58 Ci ND ND ND ND cobalt-60 Ci ND ND ND ND chromium-51 Ci ND ND ND ND iron-59 Cl ND ND ND ND mn9anese-54 Ci NP ND ND ND zircontum-95 Ci ND ND ND ND l

ND ND ND ND beryiItum-7 0i ND - none detected

TABLE 1C EFTLUENT AND WASTE DISPOSAL SEM1 ANNUAL TEPOfiT 1992 GASEOUS EFT 1UENTSGnOUND LEW'L FELEASES CON 11N000$ MODE B41CH MODE Unit Quarter Quarter Quarter Quarter Nuclides Released 1

1 2

1 2

-1. Ilssion Oases krypton-85 Cl ND ND ND ND krypton-85m Cl ND ND ND ND krypton-87 Cl ND ND ND ND

. krypton-88 C1 ND ND ND ND xenon-133 Ci ND ND ND ND menon-135 Cl ND ND ND ND menon-1304 Ci ND ND ND ND

~

xenon-138 Cl ND ND ND ND Others(specify)

C1 Cl Cl unidentified Cl ND ND ND ND Total for period Cl ND ND ND ND

- D. lodines iodine-131 Cl ND ND ND ND lodine-133 Cl ND ND ND ND todine-135 C1 ND ND ND ND Total for period C1 ND ND ND ND C. Particulates strontium-89 Ci ND ND ND ND

~

strontium-90 Ci ND ND ND ND

-cesium-134 Cl ND ND ND ND cesium-137 C1 ND ND ND ND barium-lanthanum-140 C1 ND ND ND ND Others(specify)_

C i -.

Ci C1 Ci

\\

unidentified Ci ND ND j

ND ND ND = none detected a

TABLE 2A 4

ETF1ULNT AND W?.STE DISPOSAL SEMLANNUAL HDORT 1t02 LK)UlO E~.fTLUENTS. SUMMATION OC A'.L RE1DSES Unit Quarter Quarter

[ s t, 10 t a l 1

1 2

Error, t

.J l-A. I ission arvi activation products 1.

Total release (not including tritium, gases alpha)

Cl 4.14 E-02 3.60 E-02 6.00 f 00 2.

Average diluted concentration during period vCi/ml 2.07 E-10 1.79 E-10 6.06 E-02(8) l 5.20 E-02(3) 3.

Percent of applicable lim

  • B. Irlttum m _.

1.

Total release Ci 4.15 E+01 9.44 E+01 8.00 E 00 2.

Average diluted concentration durirv;; period pCl/ml 2.08 E -07 4.70 E-07 3.

Percent of applicable limit 6.06 E-02ll) 5.20 E-02N]

C. Dissolved and entrained gases 1.

Total release l

Ci ND ND l

1.90 E+01 2.

Average diluted concentration during period pCi/ml NA NA 3.

Percent of applicable limit NA NA D. Gross alpha radioactivity 1.

Total release Ci hD ND 1.00 E +01 E.

Volum of waste released (prioi to dilution) liters 4.81 E+07 4.26 E +07 1.30 E 00 f.

Volum of dilution water used during period liters 2.00 E+11 I

2.01 E+11 9.00 f 00 l

}

ND none detected (1)

Based on the naximuni organ dose.

. -. =

TABLE 2B EFTLUENT AND W/STE DISPOSAL SEM1ANNt9L REPORT 1992 UOulD DTtUENTS CONilN000$ MODE BATCH MODE Unit Quarter Quarter Quarter l

Nuclide$ Released 1

I 2

1 Quarter 2

strontlum-89 C1 ND ND ND ND strontlum C1 ND ND ND ND ces*vm-134 Ci ND ND ND ND -

cesium-137-Ci ND ND ND ND

. lodine-131 Ci ND ND 6.35 E 2.84 E-04

cobalt-58 C1 4.12 E-03 2.16 E-03 1.19 E-03 8.52 E-04 cobalt-60 Cl 6.66 E-04 ND 2.38 E-04 6.36 E-04 iron-59 Cl ND ND 5.77 E-95 N3 2inc-65 Ci ND ND ND ND nunganese 'i4 Cl 1.48 E-04 ND 3.13 E-04 2.11 E-04 chromium-51 Ci ND ND ND ND -
zirconium-niobium-95 I

Ci ND -

ND ND 1.37 E-05

beryllium-7 Ci ND ND 3.94 E-07 3.97 E-05 tc:hnetium-99m Cl ND ND 2.80 E-06 1.10 E-04 antimony-124 Cl ND ND 8.12 E-05 ND --

ant inony-125 :

Ci ND ND 1.98 E-03 1.73 E-03 Other(specify)

-l sodium-24 Cl ND ND 1.08 E-04 ND

. cesium-137 C1

-5.59 E-05 ND ND ND lodine-133 Cl ND ND 1.37 E-05 1.91 E-04

' iron-55 C1 2.97 E-02 1.74 E-02 2.62 E-03 1.24 E-02 Unidentifled Ci ND ND ND ND Totalforperiod(above).

Ci 3.47 E-02 1.95 E-02 6.67 E-03 1.65 E-02 xenon-133 -

Cl ND ND ND ND xenon-135 Cl ND ND NU ND :

ND - none detected-I

TMRES ETT1UENT AND WASTE DISPOSAt. SEMLANNUAL REPORT 1772 S(X.lD WASTE AND IRRAD1ATED FUEL SHliWEFUS

~ A SOUD WASTE SHIPPED OFFSITE f~OR HUFBAL OR (MSPOSAL (Not inadiated fuel)'

Unit first Est. Total 6-nonth Error, 4

.l.

Type of wasto. NONE Period 3

a Spent resins, filfar sludges, evaporator m

NONE bottoms etc -

C1 3

b Dry compressible waste, contaminated m

NONE equip, etc C1 3

c Irradiated components, control rods etc m

NONl C1 3

d Other(described) m NONE Ci i

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

N/A b.

c.

d.

3. Solid Waste Disposition Nunter of Shipments Mode of Iransportation Destination
10NE H. IRRADIATED FUEL SHIPMENTS (Dispostbon)

Nunher of Shipnents Mode of Transportation Destination NONE

c-L\\PPENDIX A Off-Site Dose Calculation Manual j.

Reouirement:

Technical Sp cification 6.13.2.b requires that licensee initiated changes to the Off-Site Dose Calculation Manual (ODCM) be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the _ change (s) was made effective. Changes made to the Radiological Environmental Monitoring Program (REMP) in accordance.vith Technical Specification 3.12.1 and 3.12.2 are to be included.

Response

The following changes were made to the REMP during the reporting period (Januaiy 1,1992 through June 30,1992). A copy of ODCM Revision 11, affecting Part 13, Section 4.0 (REMP) is enclosed.

- Air sample station AP/CF-02, which was located at the llampton Marina on Harbor-Road in Hampton, N il, has been relocated to the Normandeau Associates, Inc. field office (next door) on Harbor Road.

l This change does not affect any calculational methods.

' Control location TL-39, was relocated from Epping, NH (N.W. of.

Seabrook Station) to Fremont, Nil (W.N.W. of Seabrock Station).

No changes were made to the ODCM Part A -(Radiological Efflu e n t -

Monitoring) during the reporting period (January 1,1992 through June 30, 1992).

(

F vm e

+

-e-

...m

.. _. ~. _ _ _

p-i..

APPENDIX 11 Process Control Procram Reauirement:

Technichi Specification 6.12.2.a requires-that licensee initiated changes -to ti:e Process Control Program be submitted to the Commission in the Semiannual Radioactive Effluent Release Rcport for the period in which the change (s) were made.

Resnonse:

N6 changes were made to the Process Control Program during the reporting period (January 1,1992 through June 30,'1992),

?

,,-7

APPENDIX C Radioactive Liould Effluent Monitorinn Instrumentation Reauirement:

Radioactive Liquid Effluent Monitoring Instrumentation channels are required to be operable in accordance with Technical Specification 3.3.3.9.b.

With less than the minimum number of channels operable for 30 days, Technical Specification 3.3.3.9.b requires that an explanation for the delay in cerrecting the inoperability be provided the next Semiannual Effluent Release Report in accordance with Technical Specification 6.8.1.4.

Resoonse:

A review of the Action Statement Status trackir.g system archive during the reporting period (January 1,

1992 through June 30, 1992) indicated Technical Specification 3.3.3.9 was entered for more than 30 consecutive days during the period of April 15,1992 to May 16,1992. This was due to flow transmitter WL-FT-1458, being unable to monitor flow during Steam e

Generator Blowdown System rinser. WL-FT-1458 is a magnetic type flow measuring device, and relies on icas in the flowstream to determine flow.

Since the water had been through the Steam Generator Blowdown System demineralizer just prior to passing by the flo v monitor, the conductivity of the fluid was too low for the flow-transmitter to work correctly. Waste (j

Test Tank discharges have sufficient conductivity' to allow WL-FT-1458 to y

measure flow correctly. A Request for Engineering Services was submittc<l to add a flow transmitter for this particulat Steam Generator Blowdown System flowpath.

f E

4 d

,6PPEND1X D itadioactive Gaseous Effluent Monitorint Instrumentation It c o uir e m e n t :

It u dioactive Gascous Effluent Monitoring Inst r u me n t ation channels are required to be operable in accordance with Technical Specification 3.3.3.10.b.

With less thon the minimum number of channels operable for 30 days, Technical Specification 3.3.3.10.b requires that an explanation for the delay in correct:,.g the inoperability be provided '.9 the next Semiannual Effluent Itelease Iteport in accordance with Technical Specification 6.8.1 A.

It e s po n s e :

A review of the Action Statement Status tracking system archive indicated Technical Specification 3.3.3.10 was never entered for more than 30 consecutive days during the reporting period (January 1,1992 through June 30, 1992),

e W

1 l

. - -.....~.-

.. -. ~... - -... -.

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

APPENDIX E 1iould floidun Tanks

~

Reauirement:

Technical Specification 3.11.1.4 limits the quantity of radioactive mateiial contained in any temporary unprotected cutdoor tank. With the quantity of radioactivt materialin any temporary unprotected outdoor tank exceeding the limits of Technical Specification 3.111.4, a description of the events leading in this condition is required in the next Semiannual Effluent Release Report puisuant to Technical Specification 6.8.1.4.

Response

No temporary.inprotected cuidoor tanks exceeded the limits of Technical Specification 3.11.1.4 during the reporting period (January 1,1992 th ough J u ne - 30, 1992).

4 i

l l'

i-

F APPENDIX F R adwaste Treatment Systems Reauirement:

Technical Speelfication 6.14.1.a requires that licensee initiated changes to the Radwaste Treatment Systems (liquid, gaseous, and solid) be submitted to the Comm4sion in the Semisnnual Radioactive Effluent Release Report for ti.e period in which the change was made.

R espon se:

Major licensee initiated changes to the Radwaste Treatment Systems will be reported to the NRC in the annual PEAR update, as permitted by Section 6.14 of the Technical Specifications.

h b

m m

9 a

I 1

..... _ _ _ _ _ _.. _ _ _.. _ ~.

I APPENDIX G Unnlanned Releases Reauirement:

Technical Specification 6.8.1.4 requires a '-

and description of unplanned releases of radioactive materials in gaseous ead liquid effluents made during

' the reporting peri 6d from the site to UNRESTRICTED AREAS.

~ R e s po n.sge_:

No unplanned releases exceeded the limits of Technic'i Specification 6.8.1.4 during the reporting period-(January 1,1992 through June 30, 1992).

+

4 r.

i.

I ll c

A e

s+v-.

nau'm-m,

-,we-

-e v+-

,--~

i p,

~

T' e

'4'.

a 1.

'; 1.

.sL,..

h W.__

APPENDIX 11 4..

I J

4 4 1 f

k i

I 4

y y

e y

-r w -- r nr e e

+

w.

m w

RXDCONTROLCOPYdbhOk

            • +****************

1.

Does this manual / manual revision:

a.

Make changes in the facility as described in the n

Y LJ es No FSAR7 b.

Make changes in procedures as described in the Y'8 FSAR7

[Jo c.

Involve tests or experin:ents not described in L N

'8 the FSAR7 d.

Involve changes to the existing Operating License n

Y LJ

'8 I

or require additional license requirements?

2.

If any of the above questions are answered yes, a safety evaluation per NHY Procedure 11210 is required.

[h!h PREPARED BY:

J. T. LINVILLE, CHEMISTKY DEPARTMENT SUPERVISOR Y

n l

SUBMITTED BY:

W.'B.

LELAND, CHEMISTRY AND HEALTH PHYSICS MANAGER DATE l

SORC REVIEW COMPLETED DURING MEETING NUMBER:

~N DATE: b ~.

b.

APPROVED BY:

A d>/ b l Ad/f/

D'.'?!

  1. J0D, STATION MANAGER

'DITE APPROVED BY:

MeM C

B.i. DRAWBRIDGE - J2sECUTIVE DIRECTOR -

/,8 ATE N g RCDUCTION REVISION 11 -- EFFECTIVE:

02/08/92 DATE OF LAST PERIODIC REVIEW:

2/5/91 DATE NEXT 'FERIODIC REVIEW DUE:

2/5/93 f., 7

[

yDb Y

l l

t 1

l

. - ~, _

TABLE B.4-1 g h, yye FADIOLOGICAL ENVIRONMENTAL MONITORINO STATIONS (*)

Distance From Exposure Pathway Sample Location Unit 1 Direction From and/or Sample and Designated Code Containment (km) the Plant 1.

AIRBORNE (Particulate and Radiciodine)

AP/CF-01 PSNH Barge 2.7 ESE Landing Area l

AP/CF-02 Harbor Road 2.7 E

AP/CF-03 SW Boundary 0.8 SV AP/CF-04 W. Boundary 1.0 W

r;-

AP/CF-05 Winnacunnet H.S.03 4.0 NNE AP/CF-06 Georgetown 24.0 SSW Subrtation (Control) 2.

WATERBORNE

'a.

Surface WS-01 Ecmpton-Discharge Area 5.3 E

WS-51 Ipswich Bay (Control)-

16.9 SSE O) 5.3 E

b.

Sediment SE-02 Hampton-Discharge Area D) 3.1 E

SE-G7 Hampton Beach ff+h SE-08 Seabrook Beach 3.2 ESE SE-52 Ipswich Bay (Ccitrol)D3 16.9 SSE

~

SE-57 Plum Island Beach 15.9 SSE (Control)D) 3.

INGESTION a.

Milk TM-04 Salisbury, MA 5.2 SW

~

'iM-09 Hampton, NH 5.5 NNW T) '-10 Hampton Falls, NH 4.8 WNW O) 7.0 NW TF. - 15 Hampton Falls, NH T!.- 2 0 Rowley, MA (Control) 13.3 S

b.

Fish and Invertebrates (*)

FH-03 Hampton - Discharge 4.5 ESE Area FH-53 Ipswich Bay (Control) 16.4 SSE HA-04 Hampton - Discharge 5.5 E

Area HA-54 Ipswich Bay (Control) 17.2 SSE MU-06 Hampton - Discharge 5.2 E

Area MU-56 Ipswich Bay (Control) 17.4 SSE

.. p B.4-2 CDCM Rev. 11

TABLE B.4 1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING STATIONS (*3 dih Distance From Y

Exposure Pathway Sample Location Unit 1 Direction From and/or Sample and Desinnsted Code Containment (km) the Plant TL-27 Highland St.,

7.6 W

S. Hampton TL-28 Route 150. Kensington 7.9 41N TL-29 Frying Pan Lane, 7.4 IN Hampton Falls TL-30 Route 101C, Hampton 7.9 NNV TL-31 Alumni D-ive, Hampton 4.0 NNE TL-32 Seabrook Elementary

.9 S

School TL-33 Dock Area, Nevouryport 9.7 S

TL-34 Bow St., Exeter 12.1 NW TL-35 Lincoln Acksrman 2.4 NIN School-TL-36 Route 97, Georgetown 22 SSW (Control) l-TL-37 Plaistow, NH (Control) 26 WSW l

TL-38 Hraapstead. NH (Control) 29 W

i

-l TL-39 Fremont, NH (Control) ~

27 WNW TL-40 Newmarket. NH (Control) 24 N!N TL-41 Portsmouth, NH 21 NNE (Control)N TL-42 Ipswich, MA (Control) N 27 SSE

'a)

Sc.mple locations are shown on Figures B.4-1 to B.4-6.

~

(

--(b)

This sample location is not required by monitoring program defined in Part A of ODCM; program requirements specified in Part A do not apply to samples taken at this location.

(c). Samples wi,. be collected pursuant to ODCM Table A.5-1.

Samples are not L

required -f rom all-stations li:ted during any sampling interval (FH = Fish;

'HA = Lobsters;.-MU f Muscles). Table A.5-1 specifies that "one sample of-three commercially and recreationally important species' be_ collected in the vicinity of the plant' discharge area, with similar species being collected at a control

= location.

(This_ wording is consistent with the NRC Final Environmental u

Statement for Seabrook. Station.) _Since the discharge area is off-shore, there is a great-number of fish-species _that could be considered commercially or recreationally,important.

Some are migratory (such as striped bass), making L

_them less desirable as an indicator,of plant-related radioactivity.

Some pelagic species (such as herring and mackerel) tend to school and wander

-throughout a large area,_sometimes making _ catches of significant size-difficult to _ 'obt ain.

Since the collection of all species would be difficult or

-impossible, and would provide unnecessary redundancy in terms of monitoring important pathways to man, three-fish and invertebrate species have been specified>as a_ minimum requirement. -Samples may inelude_ marine fauna such as lobsters, clams, mussels, and bottom-dwelling fish, such a s flounder or hake.

Several similar species.may be-grouped:together into one sample if sufficient sample mass for a single species is not available af ter a reasonable effort has h

U been made~(e.g., yellowtail flounder and winter flounder).

B.4-4 ODCM Rev. 11

i FIGURE B.4 * * -

DIRECT PJpIATION MONITORING LOCATIONS OUTSIDE 12 KILOKETERS OF SEA 3R00K STATION

.S%

i

^

NNW N \\, f yyg

(

0 f

10-15 j

yy-KILCMETin9 e

YORX G). A

%s %,

HE, CURHAM e Riyf4>

TL-40 t.

/

/

s k

HE'4 MARKET e PORTSHOUTH e

/

RAYMOND TL 41 EPP 10 Miles /

\\

WNW

_1

?)?

gyg TL-39O--

FREMON g

l e

e D ETER i

N I

SEE ENLARGEMENT IN FIGURE 8.4-5 i

HAMPTONl'

.l 8

SEABROOK STATION

- W-

.KINGSTCHeI N*g 4

i Wh-E g

SEAsRooK e. E e

i T

I g

s.

/4.

DISCMARGE $1TE TL A s,.

SALI53URY fi 4AMESBURY e-

/

PLAIST0'J e.

t

/-

1 TL-37 A

-g. N /-

I ESE I

. - ~is}

N HEWBURYPORT 1

g ATLANTIC OCEAN j

W5W' NAVERHILLe

.[

i

_, PLUM ISLAND

.s, N

, L.,..

  • LAWRENCE ~

IPSVICH BAY SE-IPSWICH-_e gTL.42 5W e GLOUCESTER SS,E

\\ -

c3 SSW S

' *[,D gp B.4-10 ODCM Rev. 11 t

.

Retrieved from "https://kanterella.com/w/index.php?title=ML20114B780&oldid=4290464"