ML20141J037

Addendum to Effluent & Waste Disposal Semiannual Rept, Jul-Dec 1985

ML20141J037
Person / Time
Site:	FitzPatrick
Issue date:	12/31/1985
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20141J033	List: JAFP-86-0270, Forwards Addendum to Effluent & Waste Disposal Semiannual Rept for Jul-Dec 1985. Rept Includes Assessment of Radiation Doses to Public,Changes to Environ Sample Locations & Deviations from Required Environ Sampling ML20141J037
References
NUDOCS 8604250275
Download: ML20141J037 (16)

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADDENDUM TO THE EFFLUENT AND WA3TE DISPOSAL SEMIANNUAL REPORT JULY 1985 - DECEMBER 1985 DOCKET NO.: 50-333 LICENSE NO.: DPR-59 8604250275 860331 PDR ADOCK 05000333 R PDR k

TABLE 6 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JULY 1985 - DECEMBER 1985 ASSESSMENT OF RADIATION DOSES TO THE GENERAL PUBLIC INTRODUCTION The James A. FitzPatrick Nuclear Power Plant Technical Specifications require that the radiation doses to the likely most exposed member of the public from reactor releases be assessed. The doses to the public are assessed by using dose model calculations. The dose models are based on acceptable methodologies found in the Offsite Dose Calculation Manual (ODCM). The ODCM also provides for the calculation of offsite doses based on the results of environmental field sampling. Both calculation methods are based on the methodology presented in Regulatory Guide 1.109. The doses to the likely most exposed member of the public are calculated for the calendar period of July 1, 1985 through December 31, 1985. These dates cover the period of time for the 1985 calendar year during which the Radiological Effluent Technical Specification were in effect. For the first half of 1985 the requirement to perform dose calculations did not exist and doses to the public during that period are not included in this report.

MODEL CONSIDERATIONS Calculated doses are not based on actual environmental sample data for 1985, with the exception of doses from direct radiation. To provide for possible physical variations in actual parameters from those used in the dose model (i.e. residence time inhalation rates, consumption rates etc.) and for simplification, it is assumed in dose calculations that the likely most exposed member of the public is positioned in the maximum receptor location for each pathway during the assessment period.

1. Inhalation Dose - The inhalation dose is calculated at the critical residence due to the high occupancy factor.

2. Cow Milk Ingestion - The cow milk ingestion dose is calculcted using the critical milk cow location based on atmospheric dispersion factors. The likely most exposed member of the public is assumed to obtain milk from the critical milk location.

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TABLE 6 (Con't)

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l EFFLUENT AND WASTE DISPOSAL i SEMIANNUAL REPORT / JULY 1985 - DECEMBER 1985

ASSESSMENT OF RADIATION DOSES TO THE GENERAL PUBLIC l

3. Goat Milk Ingestion - The goat milk ingestion pathway is calculated based on the critical goat location.

1 Again, the likely most exposed member of the public is assumed to obtain goat's milk from the critical goat milk location. i

4. Meat Consumption - The maximum dose resulting from meat i consumption is based a the critical meat location which

is considered to be at the critical milk cow location.

The likely most exposed member of the public is assumed i to obtain meat from the critical meat animal location.

5. Fruit and Vegetable Consumption -

The maximum dose i associated with the consumption of fruits and vegetables is calculated using the critical garden location. The likely most exposed member of the ,

assumed to obtain vegetables from the public is critical garden location.

6. Direct Radiation - The dose as a result of direct radiation from the site includes contribution from direct shine from the two generating facilities located at the site, direct radiation from the overhead gaseous plume and plume submersion and from ground plane deposition. This total dose is measured by environmental TLD. The critical location is based on the closest year round

residence from the generating facilit',3 as well as the closest residence in the critical downwind sector in order to evaluate both direct radiation from the generating facilities and gaseous plumes as determined by local meteorology. During 1985 l (3rd & 4th quarters), the closest resident and the

critical downwind resident. are at the same location.

7. Liquid Pathways - Doses to the likely most exposed member of the public as a result of liquid releases were calculated using the potable water, fish l

consumption, shoreline deposition and boating pathways.

i The critical resident was assumed to participate in the l aquatic activities, consume potable water and fresh j water fish.

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TABLE 6 (Con't)

. NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPGRT/ JULY 1985 - DECEMBER 1985 ASSESSMENT OF RADIATION DOSES TO THE GENERAL PUBLIC

8. Activities Inside The Site Boundary - Doses to members of the public as a result of activities inside the site boundary are limited to actirities at the Energy Information Center. This site is open to the public and offers educational information and summer picnicking sites. The dose pathways considered for activities at the Energy Information Center include direct radiation and inhalation. The direct radiation evaluation includes contributions from four possible components: direct radiation from the generating facilities, direct radiation from a possible overhead plume, direct radiation from plume submersion and direct radiation from ground plane deposition. The direct radiation pathway is evaluated using high sensitivity environmental TLD's. The inhalation pathway is evaluated using the source term for tritium, iodine and particulates with halflives greater than 8 days.

TABLE 6 (Con't)

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JULY 1985 - DECEMBER 1985 ASSESSMENT OF RADIATION DOSES TO THE GENERAL PUBLIC CALCULATION FACTORS

1. Meteorology - actual meteorological data and sector wind frequency distribution for the time period of July 1, 1985 through December 31, 1985 was used to determine average dispersion factors (X/Q, D/Q) used in the dose calculations. Meteorological data for the period was submitted in the Semiannual Report for the period of July 1, 1985 through December 31, 1985 Table 4 See Table 6-1 for specific X/Q and D/Q Values.

2. Specific Activities -

The specific release activities used in the dose assessment are listed in the Semiannual Radioactive Effluent Release Report (1.21 Report) for the period of July 1, 1985 through December 31, 1985.

a. Noble gases - Table 1B elevated

- Table 1C ground level

b. Iodine and particulates - Table 1B elevated Table IC ground level

, c. Liquid effluen~ts - Table 2B

3. Residence Time

a. Energy Information Center - 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> / year

b. Critical resident - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day J

4. Receptor locations

a. See Table 6-1

TABLE 6 (Con't)

. NEW YORK POWER AUTHORITY JAFES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JULY 1985 - DECEMBER 1985 ASSESSMENT OF RADIATION DOSES TO THE GENERAL PUBLIC

5. Direct Radiation:

a. Energy Information Center:

Data from two environmental TLD's located immediately to the east and west of the Energy Information Center are compared to the average of the .three TLD control locations.

The average Energy Information Center TLD dose was 7.0 mrem per standard month (based on TLD data for the entire year). The average control TLD dose was 7.0 mrem per standard month. The net dose is 0.0 mrem per standard month or 0.0 mrem for the period covered by this assessment.

b. Critical resident:

The measured direct radiation dose for the second half of 1985 to the critical resident is based on TLD data which measured the annual dose to be 66 mrem or 5.5 mrem per standard month. The average annual control dose, based on the average of three control locations, was recorded to be 67.5 mrem or 5.6 mrem per standard month. The net critical residence dose is less than the control dose which results from naturally occurring radionuclides in the soil and rock in the environment. The direct radiation dose to the critical resident as a result of activities at the generating facilities is assumed to be 0.0 bases on TLD data.

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TABLE 6 (Con't)

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JULY 1985 - DECEMBER 1985 ASSESSMENT OF RADIATION DOSES TO THE GENERAL PUBLIC

4. CALCULATION RESULTS The results of calculated doses are contained in Table 6-2. The total dose of each organ was calculated based on the assumption that the likely most exposed member of the public received the dose that would be accumulated as a result of participation in aquatic recreation and consuming food products from each of the critical receptor locations.

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TABLE 6 (Con't)

NEW YORK POWER AUTHORITY  !

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JULY 1985 - DECEMBER 1985 ASSESSMENT OF RADIAITON DOSES TO THE GENERAL PUBLIC I

TABLE 6-1 CRITICAL RECEPTOR DATA RECEPTOR GEOGRAPHIC LOCATION ATMOSPHERIC DISPERSION FACTORS A. IODINES & PARTICULATES DISTANCE / DIRECTION

• RELEASE X/Q D/Q POINT (sec/m8 ) (1/m )

1. Critical Garden 0.8 mi @ 107* (ESE) ST -

1.2E-9 1.2 mi @ 82* (E) TB -

6.3E-9 0.8 mi @ 107" (ESE) RW' _

4.2E-9 1.2 mi @ 82* (E) RX/RF _

2.9E-9

2. Critical Cow / Meat 2.2 mi @ 138* (SE) ST _

4.5E-10 6.4E-10 TB -

RW -

7.5E-10 RX/RF 6.5E-10

3. Critical Goat 7.5 mi @ "89* (E) ST _

1.0E-10 TB -

1.1E-10 RW -

1.3E-10 RX/RF 1.2E-10

4. Critical Resident

a. Inhalacion 0.9 mi @ 82*(E) ST 2.4E-8 -

TB 1.3E-7 -

RW 3.1E-7 -

RX/RF 1.3E-7

b. Deposition 0.7 Mi @ 118* (ESE) ST _

1.3E-9 TB ~

3.0E-9 RW -

5.2E-9 RX/RF 3.3E-9 B. NOBLE GASES

1. Energy Information Center 0.9" mi @ 266* (W) ST 9.9E-10 _

TB 2.1E-8 -

RW 1.9E-7 -

RX/RF 1.8E-3 1

2. Critical Resident 1.5 mi @ 202*(SSW) ST 7.6E-8 -

(Site Boundry) 0.6" mi @ "90* (E) TB 1.6E-7 -

RW 4.9E-7 ~

RX/RF 1.9E-7 _

• ST = Main Stack, TB = Turbine Building Vent, RW = Radwaste Building Vent RX/RF = Reactor Building / Refuel Floor Vent

TABLE 6 (Con't)

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE D'.SPOSAL SEMIANNUAL REPORT / JULY 1985 - DECEMBER 1985 ASSESSMENT OF RADIAITON DOSES TO THE GENERAL PUBLIC Table 6-1 (Con't)

CRITICAL RECEPT 0R DATA C. DIRECT RADIATION GEOGRAPHIC LOCATION MEASURED DOSE TLD LOCATIONS DISTANCE / DIRECTION MREM / STANDARD MONTH *

1. Critical Residence 0.7 mi @ 118* 5.5

2. Control Location #1 16.4 mi @ 42* 6.2

3. Control Location #2 12.6 mi @ 226* 5.6

4. Control Location #3 19.8 mi @ 170* 5.2

5. Energy Information 0.88 mi @ 266*(W) 5.9 Center

• BASED ON ANNUAL MEASURE DOSE

• e -mrT-a- -

t----r w+ -vn== --==--r-m m y ---r1- 'rp=-- 1 F- -"*12- fr +Me -'*y q T- - '

TABLE 6 (Con't) - -

NEW YORK POWER AUT110RITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ~

EFFLUENT-AND WASTE DISPOSAL SEMIANNUAL REPORT / JULY 1985 - DECEMBER 1985 ASSESSMENT OF RADIATION DOSES TO Tile GENERAL PUBLIC TABLE 6-2 HAXIMUM INDIVIDUAL ORGAN DOSES IN mrem Source Total Body Skin Liver Thyroid ICidney Lung GI-LLI Bone A. Gaseaus Pathway

1. Noble Cases 8.7E-3 1.7E-2 _

2. Radiciodines 9.7E-4 1.0E-3 8.2E-2 8.lE-4 1.lE-3 7.65-4 1.lE-3 2.6E-3 Particulates CHILD

• CHILD

• INFANT

• INFANT

• CHILD

• TEEN

• TEEN

• CHILD

• CPD** GFD** GPD** COWSM** CPD** CPD** GFD** STV**

I f B. Liquid Pathway 5.3E-6 6.5E-7 5.4E-6 4.8E-6 4.8E-6 4.8E-6 8.4E-6 3.8E-6 TEEN

• TEEN

• TEEN

• TEEN

• TFEN* TEEN

• TCEN* TEEN

• LSD** LSD** LSD** LSD** LSD** LSD** FWF** LSD**

C. Direct Radiation 0.D _ _ _ _ _ _ _

l D. Activites Inside 4.2E-4 1.iE-3 3. 4 E-6 Site Boundry NC** NC** CHILD *

(All Sources) INHAL**

ACE CROUP OF MAXIMUM ORCAN DOSE PRIMARY PATHWAY FOR DOSE CONTRIBUTION TO EACH ORGAN .

Where: GPD = Ground Plant Deposition COWSM = Lovs Milk SFV = Stored Fruits /Vegtables NC = Noble Cases INHAL

• Inhalation LSD = Lake Shore Deposits FWF = Fresh Water Fish

TABLE 6 (Con't)

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JULY '985 - DECEMBER 1985 ASSESSMENT OF RADIATION DOSES TO THE GENERAL PUBLIC

5. 40 CFR 190 Assessment ,

The James A. FitzPatrick Nuclear Power Plant Technical Specifications require that radiation doses to the likely most exposed member of the public are assessed relative to 40 CFR 190 regiiirements. The dose limits of 40 CFR 190 are 25 mrem (whole body or organ) per calendar year and 75 mrem (thyroid) per calendar year. The requirement of 40 CFR 190 states that the effluents of the James A. FitzPatrick Nuclear Power Plant and other nearby uranium fuel cycle facilities be considered. In this case, the effluents of the James A. FitzPatrick Nuclear Power Plant and the Nine Mile Point-1 Power Plant must be considered. The maximum total dose to the thyroid is I calculated to be 1.1 mrem and the maximum organ dose is 0.03 mrem to the bone. The calculated doses are based on reactor effluents from the Nine Mile -1 facility for the entire year of 1985. The dose contribution from the James A.

FitzPatrick Nuclear Power Plant are based on reactor releases for only the third and fourth quarter of 1985. The calculated doses are well below the requirements of 40 CFR 190 and demonstrate compliance.

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TABLE 7 NEW YORK POWER AUTHORITY JAFES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JULY 1985 - DECEMBER 1985 ENVIRONMENTAL SAMPLE LOCATION CHANGES The location (direction and distance) for the critical dairy cow, milk goat and garden have changed. In each case the replacement location is in a less critical location with respect to atmos-phere dispersion factors.

1. The critical dairy cow, was part of a small dairy operation which is no longer in existence because of a death in the family. There are no plans to restart a dairy operation. The new critical dairy cow location is located in the southeast sector 2.2 miles from the site.

2. The critical goat location changed because the owners of the previous location have discontinued goat raising. The owners of the new critical goat location indicated at the time of the census that they do not consume goats milk. It is assumed, however, that the owners do consume goats milk for conservative dose estimates. The new critical location is located in the east sector, 7.5 miles from the site.

3 ,. The critical garden location was changed as a result of the owners selling their residence and land to move.

The residence will be destroyed or moved and the land sold to Oswego County for park land development. The new cri tical garden is located in the east sector 0.9 miles from the site.

4. TLD map #22 was changed to Hickory Grove Road (4.5 miles at 97 E) from Demster Beach Road (4.8 miles at 97' E) because of continual theft of the TLD. The new location is still within the Technical Specification requirements for environmental TLDs.

This section is included in accordance with the requirements of j RETS 6.2, Land Census Program.

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TABLE 8 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JULY 1985 - DECEMBER 1985 DEVIATIONS FROM THE REQUIRED ENVIRONMENTAL SAMPLING SCHEDULE EXCEPTION TO THE PROGRAM

1. The air sampling pump at the R2 offsite environmental sampling station was inoperable from October 3, 1985 (0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />) to October 4, 1985 (0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />).

Ineperability was the result of de-energizing the pump for electrical repair, circuit box upgrade, and wiring change.

2. The air sampling pump at the R3, off site environmental sampling station was inoperable from October 16, 1985 (0821 hours0.0095 days <br />0.228 hours <br />0.00136 weeks <br />3.123905e-4 months <br />) to October 16, 1985 (1503 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.718915e-4 months <br />). Inoper-ability was the result of de-energizing the pump for circuit box upgrade and wiring change.

3. The air sampling pump at the R4 offsite environmental sampling station was inoperable from October 17, 1985 (0812 hours0.0094 days <br />0.226 hours <br />0.00134 weeks <br />3.08966e-4 months <br />) to October 17, 1985 (1442 hours0.0167 days <br />0.401 hours <br />0.00238 weeks <br />5.48681e-4 months <br />). Inoper-ability was the result of de-energizing the pump for circuit box upgrade and wiring change.

4. The air sampling pump at the R1 offsite environmental sampling station was inoperable from October 18, 1985 (0750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br />) to October 18, 1985 (1437 hours0.0166 days <br />0.399 hours <br />0.00238 weeks <br />5.467785e-4 months <br />). Inoper-ability was the result of de-energizing the pump for circuit box upgrade and wiring change.

5. The air sampling pump at the R5 offsite environmental sampling station was inoperable from October 29, 1985 (0914 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.47777e-4 months <br />) to October 30, 1985 (1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br />). Inoper-ability was the result of de-energizing the pump for circuit box upgrade and wiring change.

6. The air sampling pump at the R2 offsite environmental sampling station was inoperable form November 17, 1985 (1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br />) to November 19, 1985 (1243 hours0.0144 days <br />0.345 hours <br />0.00206 weeks <br />4.729615e-4 months <br />).

, Inoperability was caused by an electrical malfunction.

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TABLE 8 i

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JULY 1985 - DECEMBER 1985 DEVIATIONS FROM THE REQUIRED ENVIRONMENTAL SAMPLING SCHEDULE 7.- The air sampling pump at the R2. offsite environmental

, sampling station was inoperable from December 17, 1985

(0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br />) to Dccember 17, 1985 (1255 hours0.0145 days <br />0.349 hours <br />0.00208 weeks <br />4.775275e-4 months <br />).

1 Inoperability was cause by an electrical malfunction.

! 8. The spring collection of GAMMARUS did not contain sufficient quantities for Sr-89 and Sr-90 analysis as required by Table 4.3.1, Appendix B of the James A.

FitzPatrick Nuclear Power Plant Environmental Technical

! Specifications, which were in effect at the time of the

sample collection. As required by plant procedures, three attempts were made to obtain sufficient quantitier of GAMMARUS for analysis. The unavail-2 ability of GAMMARUS is most likely due to the unseason-ably cold temperature of Lake Ontario and the delay of the spring lake turnover. Few GAMMARUS were inhabiting 4 the shoreline shallows during the- spring sampling

, season. The collection of GAMMARUS in sufficient I quantities has historically (1982 and 1984) been a j difficult sample medium to obtain due to seasonal L unavailability.

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f NOTE: ATTACHED IS A REVISION TO TABLE 5 0F THE JAMES A.

FITPATRICK NUCLEAR POWER PLANT SEMIANNUAL RADIOLOGICAL EFFLUENT RET. EASE REPORT, FOR THE PERIOD OF JULY 1, 1985 THROUGH DECEMBER 31, 1985, DATED FEBRUARY 28, 1986.

TABLE 5 FROM THE ORIGINAL SUBMITTAL SHOULD BE REPLACED BY THE ATTACHED CORRECTED PAGE.

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TABLE 5

! NEW YORK l'0WER AUTHORITY JnMES A. FITZPATPICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT / JULY 1985 - DECEMBER 1985

SUMMARY

OF CHANGES TO OFFSITE DOSE CALCULATION MANUAL In accordance with Section 7.3.C.3 of Amendment 93 to the James A. fitzPatrick Nuclear Power Plant Technical Specifications, changes made to the Process Surveillance Procedures (PSP) and Offsite Dose Calculation Manual (ODCM) during the reporting period are to be included in the Semiannual Radiological Effluent Release Report.. Pursuant to this requirement, the following information is provided:

1 No changes or revisions were made to the Process Control Program or the ODCM during the reporting period of July 1, 1985 through 1*

December 31, 1985.

! Although the ODCM was not changed or revised during the above i

referenced reporting period, it has undergone two revisions during the period of time between the original submittal for review by the Commission (October 26, 1983) and the beginning of this reporting period. The referenced revisions are dated; June 15, 1983 (Rev. 0), June 25, 1985 (Rev. 1) and June 28, 1985 (Rev.

2). Appendix I to this document provides a copy of the latest revision to the ODCM (Rev. 2) which will serve as a reference for future changes to the ODCM.

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• Revision No. 1 to Semiannual Radioactive Effluent Release Report Dated February 28, 1986.

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Revision 1, Dated March 31, 1986 i

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