ML20082L775

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Revised Effluent & Waste Disposal Semiannual Rept 1990, Reflecting Liquid effluents-summation of All Releases for Third & Fourth Quarter
ML20082L775
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 12/31/1990
From:
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:
Shared Package
ML20082L764 List:
References
NUDOCS 9109040344
Download: ML20082L775 (14)
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Text

TABLE 2A 17FLUfNr AND WASTE DISI'OSAL SIM1 ANNUAL REPORT 1990 LIQUID EFFIDENTS-StH4AT10N OF ALL RELEASES Unit Quarter Quarter Est. Total 1 3 4 Error, 2 A. F1ssion arx1 activation products

1. Total release (not including tritium, C1 1.78 E-05 2.16 E-03 6.00 E00 gases, alpha)
2. Average diluted concentration during period C1/ml 8.81 E-14 1.01 E-11
3. Percent of applicable limit  ! 7.60 E-04 1.65 E-03 (1)

B. Trititan

1. Total release C1 4.59 E 01 6.74 " 01 8.00 E00
2. Average diluted concentration during period Ci/ml 2.27 E-07 3.16 E-07
3. Percent of applicable limit 2 7 60 E-04 1.65 E-03 (1)

C. Dissolved ami entrained gases

1. Total release Ci ND. E ND. E 1.90 E01
3. Average diluted concentration during period C1/ml ND. E NP. E
3. Percent of applicable limit I NA. E NA. E D. Cross alpha radioactivity fl.TotalRelease Ci ND. E ND. E 1.00 E01 L-E. Volume of waste released (prior to dilution) liters 3.14 E07 2.77 E07 1.30 E00 F. Volume of dilution water used during period liters -2.02 Ell 2.13 Ell 9.00 E00 ND - none detected (1) Based on the maximum organ dose.

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9109040344 910829 1 PDR ADOCK 05000443 '

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TABl.E 2B EFFill?NT AND WASTE DISPOSAI SIMIA10RfA1, REPORT 1990 1.IQUID EIT11JENTS CONTINUOUS MODE BATCilM0pE Unit Quarter Quarter Quarter Quarter 4

Nuclides Released 1 3 4 3 strontium-69 C1 ND. E ND. E ND, E ND. E strontium-90 Ci ND. E ND, E ND. E _ND. E cesium-134 Ci ND. E ND. E ND. E ND. E cesium-137 Ci ND. E ND. E ND. ._E ND. E iodine-131 Ci ND. E ND. E lND, E ~ND. E colelt-58 Ci ND. E ND. E 1.78 E-05 1.13 E-03 cobalt-60 Ci ND. E ND. E ND. E ND. E iron-59 Ci ND. E ND. E ND, E 1.43 E-05 zinc-65 Ci ND. E ND. E ND. E ND. E manganese-54 Ci ND. E ND. E ND. E ND. E chrontium-51 Ci ND. E ND. E ND. E 2.32 E-04 zirconium-niobium-95 Ci ND. E ND. E ND. E ND. E molybdenum-99 Ci ND. E ND. E ND. E ND, E technetium-99m Ci ND. E ND. E _ _ND.

E _ND. E barium-lanthanum-140 Ci ND. E ND, E ND. E ND. E cerium-141 Ci ND. E ND. E ND. E ND. E Other (specify) Ci ND. E ND, E ND, E ND. E Antimony - 124 Ci . E . E . E 8.02 E-04 Ci . E . E E . E C1 . E . . .

unidentified Ci ND. E ND. E ND. E ND. E l Total for period (above) j Ci _lND, E lND. E l1.78 E-05l2.16E-03]

xenon-133 Ci ND, E ND. E ND. E ND. E xenon-135 Ci ND. E ND. E ND. E ND. E ND = none detected 4

l New ilampshire Yankee August 29, 1991 ENCL,OSURE 3 TO NYN 91133

TABLE _4._ REVISION _1 SeabrooltStation Effluent and_ Waste _ Disposal Semiannual Report 1990 tlaximurd" DIL-Site _Doaes_.and_1Mae_Comi.tments _toJ1 ember.a_oLthelsblic (b)

________._ Dose _(mrcm)_ _._____ __

1st 2nd 3rd 4th (c)

__liource Quarter Quarler Quarter Quarler Year ____

Liquid Effluents:

Total Body Dose 1.5E-09 6.0E-08 1.2E-05 2. 2E- 05 3.4E-05 Organ Dose 1.5E-09 2.2E-07 1.4E-05 3.2E-05 4.6E-05 (1) (1) (1) (1) (1)

Airborne Effluents:

Iodines, Tritium and --

4.1E-06 2.0E-06 7.8E-05 8.4E-05 Particulates (2) (3) (4)

Noble Cases Beta Air --

2.0E-07 1.6E-05 1.5E-02 1.5E-02 (mrad) (5) (6) (7)

Gamma Air -

7.1E-07 3.5E-05 1.3E-02 1.3E-02 (mrad) (5) (6) (7)

Doses (mrem) at Receptor Locations Inside Site Boundary (d):

Education Center (SW, 335 m)

Beta Air Dose (mrad) --

3.0E-10 --

5.9E-10 8.9E-10 Gamma Air Dose (mrad) -

5.7E-10 --

9.0E-10 1.5E-09 Organ Dose (mrem) --

2.3E-09 --

3.4E-11 2.3E-09 (8) (8)

The " Rocks" (ENE 318 m)

Beta Air Dose (mrad) -- - 2.8E-06 7.9E-04 7.9E-04 Gamma Air Dose (mrad) -- -

3.4E-06 2.9E-04 2.9E-04 Organ Dose (mrem) --

1.2E-07 7.3E-08 3.1E-07 5.0E-07 (8) (8) (8)

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

IAELE_b_BELIS1011 (Continued)

SnaktDDh_Slutlan Ef. fluent _and_.h'asidispD asl_.S nmiannua LRe para 1220 (b)

Dase.Larsm) 1st 2nd 3rd 4th (c)

_ Source Guartar Quatter. Quarler _Quarler Year Direct Dose From Plant Operation (e) 0 (a) "Maxir.um" means the largest fraction of corresponding 10CFR50, Appendix I, dose design objective.

(b) The numbered footnotes indicate the age group, organ, and location of the dose receptor, where appropriate.

(1) Adult /GI-LLI.

(2) Child /whole body, ESE-2414 meters.

(3) Child /whole body, ENE-2414 meters.

(4) Child /whole body, SE-2414 meters.

(5) W-914 meters.

(6) ENE-2276 meters.

(7) SSE-914 meters.

(8) Teen /whole body.

(c) " Maximum" dose for the year is the sum of the maximwn doses f or each quarter. This results in a conservative yearly dose estimate, but still well within the limits of 10CFR50.

(d) For each special receptor location, the doses calculated for the duration of the airborne ef fluent releases were adjusted by the occupancy f actor provided in Seabrook's ODCM (i.e., 0.0014 for the Education Center and 0.0076 for the " Rocks").

(e) Only station sources are considered since there are no other facilities within five miles of Seabrook Station. The annual dose at the closest receptor location in each sector (as listed in Table B.4-1 of Seabrook's ODCM) was determined f rom 1990 environment TLD data and compared with the annual dose determined from pre-operational environment TLD data. No statistical difference which could be attributed to station sources was identified.

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Seabrook Station Supplemental Effluent Release Report Radiological Impact Assessment For 1990-Revision 1 I. Introduction

, Doses resulting from liquid and gaseous effluents from Seabrook Station during 1990 were calculated in accordince with Method II as defined in the Seabrook Offsite Dose Calculation Manual (ODCM). The calculational methods used follow the models in Regulatory Guide 1.109. The calculations included maximum total body doses and organ doses from all liquid releases, maximum offsite organ doses

.resulting from airborne iodines, tritium and particulate radionuclides, and maximum offsite beta air and gamma air doses frem airborne noble gases. In addition, the doses associated with gaceous effluents were also calculated for i

the special receptor locations inside the site bout.Jary: the Education Center and

the " Rocks". The airborne effluent doses presented in Table 4 are the summation of elevated and ground releases.

The calculated maximum annual total body dose and the maximum organ dose from liquid effluents represent, respectively, 0.001% and 0.0005% of the dose limits l established by Technical Specification 3.11.1.2. The calculated annual maximum dose from airborne iodine, tritium and particulate radionuclides for offsite

! receptor locations represent 0,0006% of the dose limit established by Technical Specification 3.11.2.3, whereas the caiculated maximum annual beta air and gamma air doses from airborne noble gases for offsite receptor locations represent, respectively, 0.08% and 0.13% of the dose limits established by Technical Specification 3.11.2.2. The calculated annual beta air and gamma air doses from airborne noble gases for the Education Center were, respectively, 4.5e-9% and 1.5e-8% of the limits in Technical Specification 3.11.2.2, whereas, for the

" Rocks" the annual doses were, respectively, 0.004% and 0.003% of the Technical Specification limits. The calculated annual doses from airborne iodines, tritium and particulate ' radionuclides at the Education Center and the " Rocks" were, respectively, 1.5e-8% and 3.3e-6% of the limits in Technical Specification 3.11.2.3.

The sum of the maximum whole body doses from all exposure pathways for the liquid and gaseous effluents, plus the direct whole body dose from station operation, was 8.7e-03 mrem to a hypothetical individual. This total whole body dose l

conservatively represents 0.03% of the whole body dose limit for a member of the l public as set forth in 40CFR190, and demonstrates compliance with that code.

II. tiethod for Calculating the Total Body and Maximum Organ Doses Resultinc from l Liould Releases The computer code IDLE, which is consistent with the models in Regulatory Guide 1.109 (Reference 1), was used to calculate the total body and organ doses resulting from liquid effluents from Seabrook Station. The general equations A- ,

3, A-4, A-5, A-6 and A-7 from Regulatory Guide 1.109 are applied in IDLE. The total body doses and the organ doses are evaluated for each of the four age groups (i.e. , infant, child, teen and adult) to determine the maximum total body dose and maximum organ dose via all existing exposure pathways (i.e., fish and aquatic invertebrate ingestion, and shoreline exposure) to an age-dependent individual. The values for the various factors considered in equations A-3 l

through A-7 have been taken from Regulatory Guide 1.109 and the Seabrook Station Offsite Dose Calculation Manual (ODCM) (Reference 2). The specific values used for the usage factor (U,p), mixing ratio (M p), bioaccumulation factor (Bip), dose factors (D.ip3), transit time (t,), transfer constant from water to sediment (K ),

exposure time for sediment or soil (t ),3 and shore width factor (W) are provided by the reference sources as summarized in Table A. The flow rate of the liquid effluent (F) and .the release rates for radionuclides (Qt) are measured specifically. _ prior to each liquid release. The values for half lives for radionuclides (Tt ) and their radioactive decay constants (h) have been taken l

from Kocher (Reference 3).

The exposure pathways considered in the calculations of total tody and maximum organ doses resulting from liquid discharges from Seabrook Station have been limited to ingestion of aquatic foods and exposure to shoreline deposits. The dose calculations do not include the ingestion of potable water and irrigated vegetation as potential exposure pathways because the liquid effluents from the plant are discharged into salt water.

Table 4 lists the calculated liquid pathway doses for each calendar quarter and also the total for the year.

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4 Table A

. Factor _ Source U., Table B.7-1, Seabrook ODCM

] M, .Section B.7.1, Seabrook ODCM (value-0.1 was used)

B ip Table A-1, Reg. Guide 1.109 D,gp3 Tables E 11 through E-14, R.G. 1.109 tp Section B.7.1, Seabrook ODCM

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K. Re6. Guide 1.109

, tb Reg. Guide 1.109 V Table A 2, Reg. Guide 1.109 (value-0.5) 4 III. Method _for Calculatine the Camma and Beta Air Doses from Noble Cases The computer codes AIRAD and AEOLUS 2 (Mod 02) were used for the calculation of both the gamma and beta air doses resulting from noble gases present in gaseous

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effluents released from Seabrook Station. The features and use of AEOLUS 2 (Mod

02) for the calculation of atmospheric dispersion factors (i.e. , Chi /Q factors) from recorded meteorological data (i.e. , meteorological data measurements taken
during the time of the release) are described in section B.7.3.2 of Seabrook's ODCM. Meteorological dispersion factors concurrent with periods of batch gas releases are calculated along with the values for quarterly average dispersion factors. The atmospheric dispersion factors calculated using AEOLUS 2 (Mod 02) were, in turn, used in the- gamma and beta air dose calculations by AIRAD. AIRAD is consistent with the models presented in Regulatory Guide 1.109, general I

equations B-4 and B 5. The values for the dose factors, DF i and DF , have been j i l:

taken from Table B-1 -in Regulatory Guide 1.109.

Table 4 list the calculated air doses for each calendar quarter, and the total for the year.

IV. Method for Calculatine the Critical Orcan Dose Resultine from Iodines.

Tritium and Particulates with T in Creater than 8 Days in Caseous Releases The computer codes AEOLUS 2 (Mod 02) and ATMODOS were used for the calculation of the organ doses resulting from iodines, tritium and particulates with half-l

4 lives greater than 8 days present in gaseous effluents released from Seabrook Station. The features and use of AEOLUS 2 (Mod 02) for the calculation of atmospheric dispersion factors (i.e. , Chi /Q factors) from recorded meteorological data (i.e., meteorological data measurements taken during the time of the release) are described in section B.7.3.2 of Seabrook's ODCM. Meteorological dispersion factors concurrent with periods of batch gas releases were calculated along with the values for quarterly average dispersion factors. The atmospieric dispersion factors calculated using AEOLUS 2 (Mod 02/ were, in turn, used in the dose calculations by ATMODOS. ATMODOS calculates the organ doses ( i.e., dose to bone, liver, kidney, lung, lower large intestine, total body, and skin) due to the presence of radionuclides other than noble gases in gaseous effluents, and is consistent with the models presented in Appendix C of Regulatory Guide 1.109.

The pathways considered in the dose calculations are the ground plane, inhalation, and ingestion of stored vegetables, fresh garden vegetables, milk and meat. The critical organ dose is determined for the offsite location (e.g. , site ,

boundary, nearest resident or farm) of recepter pathways as identified in the most recent annual land use census. The total body dose contributions via the ground plane and inhalation pathways as calculated by ATMODOS have also been included in the total body dose estimates for the special receptor locations inside the site boundary. Equations C-1 through C 13 are applied in the ATMODOS calculation of the critical organ doses. The input data and assumptions are those provided in Appendix C of Regulatory Cuide 1.109, except where site-specific data and assumptions have been identified in Tables B.7-2 and B 7-3 of l'

l Seabrook's ODCM. These two ODCM tables provide the options for special conditions, depending on the type of receptor being evaluated at a specific l location, that are to be applied in Method II calculations. The receptor type l

controls the exposure pathways for calculational purposes. The receptor types used in the dose calciations were e resident receptor (which considered the L ground plane, inhalation and vegetable ingestion exposure pathways), a milk i-receptor (which considered the ground plane, inhalation, vegetable and milk ingesticn exposure pathways) and a boundary and radius receptor (both of which considered the ground plane and inhala' tion exposure pathways). The resident and milk receptor locations for the various sector were based on the 1990 land use census data for Seabrook Station (see Table B for the latest land use census).

The radius receptor locations were applied at seve al distances in each sector to insure that the location of the maximum doses were not overlooked.

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Depletion of the plume during transport is-considered by AEOLUS 2 (Mod 2) in the calculations of atmospheric dispersion factors - (e.g. ,- calculation of [X/Q)D) .

A shielding factor (Sr) of 0.7 is applied for residential structures. The source for the values of the various factors used in equations C 1 through C-13 are summarized below.

Factor Source tb Reg. Guide 1.109 h3 Kocher (Reference 3)

DFC ij Table E-6, Reg. Guide 1.109 (X/Q]D Calculated by AEOLUS 2 (Mod 2)

R. Table B.7-3, Seabrook ODCM DFA),i Tables E-7 through E 10, R.G 1.109 di Reg. Guide 1,109 P , t. , tw-and Y, Tabic B.7-2, Seabrook ODCH r Table E-15, Reg. Guide 1.109 B,3 Table E-1, Reg. Guide 1.109 p Reg. Guide 1.109 H Table B.7-2, Seabrook ODCM F. Tables E-1 and E 2, R.C. 1.109 Q, Table E-3, Reg. Guide 1.109

-tr Reg. Guide 1.109 fp Table B.7 2, Seabrook ODCM f, Table B.7 2, Seabrook ODCM Fr Table E-1, Reg. Guide 1.109 t, Table E-15, Reg. Guide 1.109 DFI ip Tables E-11 through E-14, R.G.1.109 U{,U" Table B.7-3, Seabrook ODCM I

U[,UA Table B.7-3, Seabrook ODCM l

.- . .. . =-

t. .

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. 4 f.as.t.2r Souree f, , ft Reg Cuide 1.109

- (fg Calculated by AEOLUS 2 (Mod 2) r

3. Table E-15, Reg. Cuide 1.109 Qr Table E-3, Reg. Cuide 1.109

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l l r V. References l i

1. Calculation of Annual Doses to Man from Routine Releases of [

Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR Part-50, Appendix.I, Reg. Guide 1.109, Rev 1, Oct. 1977. i

2. Seabrook Station Offsite Dose Calculation Manual.
3. Kocher, D.C., Dose-Rate Conversion Factors for Exposure to ,

Photons and Electrons, Health Physics, Vol. 45, No. 3, Sept. 1983. ,

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TABLE B Receptor Locations for Seabrook Station Nearest Receptor Nearest Nearest Nearest Location (*) Resident <b) Cardentb) Milk Animal (b)

Sector mile (km) mile (km) mile (hn) mile (km)

NNW 0.6(0.9) 0.7(1.1) 0.7(1.1) 3.4(5.5)

N 0.6(0.9) 0.6(1.0) 2.5(4.0) -

NNE 1.8(2.9) 2.0(3.2) 2.0(3.2) 3.7(5.9)

NE 1.4(2.3) 1.5(2.4) 2.0(3.2) -

ENE 1.4(2.3) 1.5(2.4) - -

E 1.S(2.4) 1.6(2.6) - -

ESE 1.4(2.3) 1.5(2.4) - -

SE 1.4(2.3) 1.5(2.4) 2.2(3.5) -

SSE 0.6(0,9) 0.6(1.0) 0.7(1.1) -

S 0.6(0.9) 0.6(1.0) 0.8(1.3) 4.3(6.9)

SSW 0.6(0.9) 0.6(1.0) 0.8(1.3) -

SV 0.6(0.9) 0.6(1.0) 1.0(1.6) 3.2(5.2)

WSW 0.6(0.9) 0.7(1,1) 1.2(1.9) 4.0(6.4)

V 0.6(0.9) 0.6(1.0) 0.7(1.1) -

VNW 0 6(0.9) 0.6(1.0) 1.0(1.6) 3.0(4.8)

NW 0.6(0.9) 0.6(1.0) 0.7(1.1) 4.4(7.1)

(a) The nearest receptor location is taken to be the site b2oundary for all sectors except the NNE through SE sectors. The actual site boundary for each of these six sectors is located over marsh (e.g. ,

water). Consequently, the nearest receptor locations in these sectors represents the closest dry land beyond the site boundary.

(b) The location given is based on data from the Seabrook Station 1990 Land Use Census.

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