ML20080L929

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NMPNS-Unit 1 Semi-Annual Radioactive Effluent Release Rept, July-Dec 1994
ML20080L929
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 12/31/1994
From:
NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML20080L917 List:
References
NUDOCS 9503030061
Download: ML20080L929 (31)
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NINE MILE POINT NUCLEAR STATION - UNIT 1 l

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT t JULY - DECEMBER 1994  !

f N/AGARA MOHA WK POWER CORPORATION i

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9503030061 950227  :

PDR ADOCK 05000220 '

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NINE MILE POINT NUCLEAR STATION - UNIT 1 i

SEMI-ANNUAL RADIOACTIVE EFFLUENT RFLEASE REPORT JULY - DECEMBER 1994 l

I SUPPLEMENTAL INFORMATION Facility: Nine Mile Point Unit #1 Licensee: Niagara Mohawk Power Corporation -  ;

1. TECHNICAL SPECIFICATION LIMITS i

A) FISSION AND ACTIVATION GASES

1. The dose rate limit of noble gases from the site to areas at and beyond the site boundary shall be less l than or equal to 500 mrems/ year to the total body and less than or equal to 3000 mrems/ year to the  !

skin.

2. The air dose due to noble gases released in gaseous effluents from the Nine Mile Point 1 Station to ,

areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal i to 5 milliroentgen for gamma radiation and less than or equal to 10 mrads for beta radiation, and during any calendar year to less than or equal to 10 milliroentgen for gamma radiation and less than or equal to

, 20 mrads for beta radiation.  ;

B&C) TRITIUM, IODINES AND PARTICULATES, HALF LIVES > 8 DAYS l i

1. The dose rate limit of Iodine-131, lodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days, released to the environs as part of the gaseous wastes from the site,  ;

shall be less than or equal to 1500 mrems/ year to any organ.

2. The dose to a member of the public from Iodine-131, lodine-133, Tritium and all radionuclides in j particulate form with half lives greater than eight days as part of gaseous effluents released from the .l Nine Mile Point i Station to areas at and beyond the site boundary shall be limited during any calendar  ;

quarter to less than or equal to 7.5 mrems to any organ and, during any calendar year to less than or  ;

equal to 15 mrems to any organ. '

i D) LIQUID EFFLUENTS l

1. The concentration of radioactive material released in liquid effluents to unrestricted areas shall be j limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gas, the  ;

concentration shall be limited to 2E-04 microcuries/ml total activity.

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2. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents j released from Nine Mile Point Unit I to unrestricted areas shall be limited during any calendar quarter 1 to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, l and during any calendar year to less than or equal to 3 mrems to the total body and to less than or equal l to 10 mrems to any organ.

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2. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents.

A) FISSION AND ACTIVATION GASES Noble gas effluent activity is determined by on-line gamma spectroscopic monitoring (intrinsic germanium crystal) or gross activity monitoring (calibrated against gamma isotopic analysis of a 4.0L Marinelli grab sample) of an isokinetic stack sample stream.

B) IODINES lodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled from an isokinetic stack sample stream.

C) PARTICULATES Activity released from the main stack is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from an isokinetic sample stream.

For emergency condenser vent releases, effluent curie quantities are estimated based on the isotopic distribution in the Condensate Storage Tank water and the Emergency Condenser shell water. Actual isotopic concentrations are found via gamma spectroscopy. Initial release rates of Sr-89, Sr-90 and Fe-55 are estimated by applying scaling factors to release rates of gamma emitters. For emergency condenser vent releases, the activity of Tritium released during normal operation or during batch releases is conservatively estimated by multiplying recent condensate storage tank H-3 activity by assumed steaming rates out the vents.

D) TRITIUM Tritium effluent activity is estimated by liquid scintillation or gas proportional counting of monthly samples taken with an air sparging/ water trap apparatus.

E) LIQUID EFFLUENTS isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters.

F) SOLID EFFLUENTS isotopic contents of waste shipments are determined by gamma spectroscopy, gross alpha and water content i analyses of a representative sample of each batch. Scaling factors established from primary composite sample analyses conducted off-site are applied, where appropriate, to find estimated concentration of non-gamma emitters. For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.

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,. . ATTACHMENT I Page 1 of 2

, Summary Data Unit 1 JL Unit 2_ Reporting Period July - December 1994 Liquid Effluents:

10CFR20, Appendix B, Table 11, Column 2 Average MPC uCi/ml(Qtr.2) = N@,,

Average MPC - uCi/ml (Qtr. 4) = M/A_

Average Energy (Fission and Activation gases - Mev):

Otr. 2 Er = 5.02E-02 E, = 1.40E - 01 Otr. 4 . Er = 6.93E-02 E, = 1.57 E - 01 Liquid: There were no liquid releases during the reporting period.

Number of batch releases .

1 Total time period for batch releases (hrs)

  • N/A Maximum time period for a batch release (hrs) N/A Average time period for a batch release (hrs) . N/A Minimum time period for a batch release (hrs) N/A Total volume of water used to dilute the liquid effluent during release period P.: N/A Total volume of water available to dilute the liquid effluent during reporting period (L) 2.58E + 11 UNIT 1 (ONL Y)

Gaseous (Emergency Condenser Vent): There were no releases from the operation of the emergency condenser vent.

Number of batch releases 1 Total time period for batch releases (hrs) . N/A Maximum time period for a batch release (hrs)

  • N/A Average time period for a batch release (hrs)
  • N/A Minimum time period for a batch release (hrs) N/A Gaseous (Primary Containment Purge): i Number of batch releases
  • 1 Total time period for batch releases (hrs) 6.90E + 00 Maximum time period for a batch release (hrs) 6.90E + 00  !

I Average time period for a batch release (hrs) 6.90E + 00  !

Minimum time period for a batch release (hrs) 6.90E + 00

ATTACHMENT 1 Page 2 cf 2 -

, , Summary Data Unit 1 X Unit 2 Reporting Period Julv - C _ _ ._ _- 19M Abnormal Releases: There were no abnormal releases during the reportmg period.

A. Liquide:

Number of releases 1 Total activity released N/A Ci S. Geseous:

Number of releases 1 Total activity released N/A Ci i

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.* ATTACilMENT 2 l Unit 1 JL. Unrt2 _ Reporting Period July - Decembgr_19,24 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL f f,,, ES1. TOTAL f OUARTER OUAR T*6 ERROR.%

A. Fission & Activation Gases' f

1. Total release Ci 1.44E + 02 5.71 E + 01 5.00E + 01 l
2. Average release rate pCi/sec 1.81 E + 01 7.18E + 00

. t B. lodines

1. Total iodine-.131 Ci 3.56E - 05 2.03E- 04 3.00E + 01
2. Average release rate for period pCi/sec 4.53E - 06 2.55E - 05 i C. Particulates 8 .

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1. Particulates with half-lives > 8 days Ci 2.16E-04 1.08E- 03 3.00E + 01
2. Average release rate for period pCi/sec 2.75E - 05 1.3GE - 04
3. Gross alpha radioactivity Cl 6.54E - 05 4.70E - 05 2.50E + 01 8

D. Tritium

1. Total release Ci 7.49E + 00 2.74E + 01 5.00E + 01
2. Average release rate for period pCi/sec 9.52E - 01 3.45E + 00 E. Percent of Tech Spee Limits Fession and Activation Gases Percent of Quarterly Gamma Air Dose Limit (5 mrem)  % 1.16E - 01 6.66E- 02
  • Percent of Quarterly Beta Air Dose Limit (10 mrem)  % 1.19E - 01 5.27E - 02 Percent of Annual Gamma Air Dose Limit to Date (10 mrem) % 5.99E-02 9.32E - 02 Percent of Annual Beta Air Dose Limit to Date (20 mrem)  % 6.10E-02 8.75E - 0] ,

Percent of Whole Body Dose Rate Limit (500 mrem /yr)  % 2.77E - 03 1.65E - 03 '

Percent of Skin Dose Rate Limit (3000 mrem /yr)  % 1.11 E - 03 6.25E - 04 -

Tritium, lodines. and Particulates8 j fwith half-lives nrester than 8 days)

Percent of Quarterly Dose Limit (7.5 mrem)  % 1.14E - 01 2.26E - 01 Percent of Annual Dose Limit (185 mrem)  % 1.16E - 01 2.12E - 01 Percent of Organ Dose Rato Limit (1500 mremlyr)  % 2.29E - 03 4.49E - 03 i

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' Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. .

A lower hmit of detection of 1.00E-04 pCi/mi for required noble ganes,1.00E ~11 Ci/mi for required particulates, 1.00E - 12 pCi/mi for required lodines, and 1.00E-06 pCi/ml for Tritium, as required by Technical Specifications, has been venfied.

2 Tritium, iron-SS, and Strontium resuits were not received from the off-site vendor at the time of this report. These numbers include estimates, and actual numbers will be provided in the next Semi-Annual Report.

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ATTACHMENT 3 1

, Unrt 1 J,,, Unit 2 Reporting Period July - C= _..__- 1994

, GASEOUS EFFLUENTS ELEVATED RELEASE ]

CONTINUOUS MODE' i

' Nuclides Released QUARTER QUARTER

1. Fission Gases' Argon-41 Ci " "

Kryptom85 Ci " "

t Krypton 85m Ci 8.11 E + 00 *'  !

Krypton 87 Ci **

Krypton-88 Ci " "

Xenon-127 Ci ,

Xenon 133 Cl 1.38E + 02 5.03E + 01  !

Xenon-133m Ci " "

Xenon-135 Ci " 6.75E + 00 Xenon-135m Ci " '*

Xenon-137 Ci ** "

Xenon-138 Ci

2. todines' lodine-131 Ci 3.56E - 05 2.03E - 04 i lodine-133 Ci 2.97E - 03 3.75E- 03 lodine-135 Ci " " ,
3. Particulates

Strontium-89 Ci 3.15E-05 5.95E- 04 ,

Strontium-90 Ci

7.37E-05 Cesium-134 Ci " "

Cesium-137 Ci 1.95E-05 " i Cobalt-60 Cl 1.28E - 04 9.95E-05 -

Cobalt-58 Ci " " '

Manganese-54 Ci " "

Barium-Lanthanum-140 Ci "

Antimony 120 Ci ",

Niobium-95 Ci " ",

Cerium-141 Ci " " k Cerium-144 Ci " "

Iron-59 Ci " " t Cesium-136 Ci " "

Chromium-51 Ci " "

Zinc-65 Ci " " j Iron-55 Ci 3.50E - 05 3.07E-04 i Molybdenum-99 Ci " "

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4. Trrtium8 Ci 1.52E + 00 2.20E + 01 e

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' Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A tower limit of detection of 1.00E-04 pCi/mi for required noble gases,1.00E-11 pCi/ml for required particulates,1.00E-12 pCi/mi for required lodines, and 1.00E-06 pCi/mi for Tntium, as required by Technical Specifications, has been verificd.

8 Tritium, Iron-SS, and Strontium results were not received from the off-site vendor at the time of this report. These numbers include estimates, and actual numbers will be included in the next Semi-Annual Report.

  • No batch mode release occurred during the reporting period.

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ATTACHMENT O Unit 1.X_ Unit 2__, Reporting Period July - Dreember 1994 GASEOUS EFFLUENTS GROUND LEVEL RELEASES There were no releases via the emergency condenser vent operation. Only leakage from the vents results in an assumed release based on the concentrations in the condensate storage tanks and condenser shell.

CONTINUOUS MODE BATCH MODE There were na batch rolesses during the reporting period.

f, 4* 3* 4*

QUARTER QUARTER QUARTER QUARTER Nuclides Released

1. Fission Gases' Argon-41 Ci ** "

Krypton-85 Ci " "

Krypton-85m Ci " "

Krypton-87 Cl ** "

Krypton-88 Ci ' "

Xenon-133 Ci 4.29E - 03 5.30E - 03 Xenon-133m Cl Xenon-135 Ci Xenon-135m Ci " "

Xenon-137 Ci Xenon-138 Ci " "

Xenon-127 Ci **

2. lodines' lodine-131 Ci " "

todine-133 Ci "

lodine-135 Ci _"

3. Particulates

Strontium-89 Ci 2.07E - 07 5.48E-07 Strontium-90 Ci 2.88E - 08 6.85E - 08 Cesium-134 Ci " "

Cesium-137 Ci 6.82E-08 2.24 E - 08 Cobalt-60 Ci 1.60E - 05 1.35E - 06 Cobalt-59 Ci " "

Manganese-54 Ci 5.77E - 08 2.58E - 08 Barium-Lanthanum-140 Ci " "

Antimony-125 Ci " "

Niobium-95 Ci " "

Cerium-141 Ci " "

Cerium-144 Ci " "

fron 59 Ci " '

Cesium-136 Ci " '

Chromium 51 Ci " "

Zine-65 Ci " "

fron-S S Ci 6 09E-07 8.45E - 07 Molybdenum-99 Ci n "

4. Tntium Ci 5.97E + 00 5.39E + 00

' Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A tower limit of detection of 1.00E-04 pCi/mi for required noble gases.1.00E ~11 Ci/mi for required particulates.

1.00E - 12 uCi/ml for required lodines, and 1.00E -06 pCi/mi for Tritium, as required by Technical Specifications, has been verified.

' tron 55 and Strontium results were not received from the off-site vendor at the time of this report. These numbers include estimates, and actual numbers will be included in the next Semi-Annual Report.

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ATTACHMENT 5 Page 1 of 2 Unit 1.2L Unit 2 ,,,,,,, Reporting Period July - December 1934

. LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES f 4* EST. TOTAL QUARTER QUARTER ERROR. %

A. Fission & Activation Products i

1. Total release (not including Trhium, gases, alpha) Ci No Releases No Releases 5.00E + 01  ;
2. Average diluted concentration during reporting period pCi/mi No Releases No Releases B. Tritium 1, Total relea*e Ci No Releases No Releases 5.00E + 01
2. Average diluted concentration during reporting period pCi/ml No Releases No Releases C. Dissolved and Entrained Gases l
1. Total release Ci No P.aleeses No Releases 5.00E + 01
2. Average diluted concentration during reporting period pCi/ml No Releases No Releases l-i
0. Gross Alpha Radioactivity
1. Total release Ci No Releases No Releases 5.00E + 01 r

E. Volumes  ;

1. Prior to dilution Liters No Releases No Releases 5.00E + 01
2. Volume of dilution water used during release period Liters No Releases No Releases 5.00E + 01
3. Volume of dilution water available during reporting period Liters 1.25E + 11 1.33E + 11 5.00E + 01 F. Percent of Technical Specification limits Percent of Quarterly Whole Body Dose Limit (1.5 rnrem)  % No Releases No Releases Percent of Quarterly Organ Dose Limit (5 mrem)  % No Releases No Releases Percent of Annual Whole Body Dose Limit to Date (3 mrem)  % No Releases No Releases Percent of Annual Organ Oose Limit to Date (10 mrom)  % No Reloeses No Releases Percent of 10CFR20 Concentration Limit  % No Releases No Releases Percent of Dissolved or Entrained Noble Gas Limit (2.00E-04  % No Releases No Releases  !

Ci/ml)

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, .'* ATTACHMENT 5 Page 2 of 2 Unit 1,)L, Unit 2_ Reporting Period July - December 1994 F.

. LIQUID EFFLUENTS RELEASED ,

BATCH MODE f

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Nucl6 des Released ' QUARTER QUARTER j Strontium-89 Ci No Releases No Releases Strontium-90 Ci No Releases No Releases Cesium-134 Ci No Reloeses No Relooses Cesium-137 Ci No Releases No Releases lodine-131 Ci No Releases No Releases '

Cobalt Ci No Releases No Releases "

Cobalt-60 Ci No Releases No Releases i Iron-59 Ci No Releases No Releases Zinc-65 Ci No Relooses No Releases  !

Manganese-54 Ci No Releases No Releases Chromium-51 Ci '

No Releases No Releases '

Zirconium-Niobium-95 Ci No Releases No Releasee Molybdenum 99 Ci No Releases No Releases {

Technetium-99m Ci No Releases No Releases -

Barium-Lanthanum 140 Ci No Releases No Releases Cerium-141 Ci No Releases No Releases Tungsten-187 Ci No Releases No Releases '

Arsenic-76 Ci No Releases No Releases lodine 133 Ci No Releases No Releases iron-55 Ci No Releases No Relooses 7 Neptunium-239 Ci No Releases No Releases Praseodymium-144 Ci No Releases No Releases lodine-135 Ci No Releases No Releases i

Dissolved or Entrained Gases Cl No Releases No Releases Tritium Ci No Releases No Releasee 5

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., , ATTACHMENT 6 Page 1 of a l

j Unit 1 JL, Unrt 2_ Reporting Period July - December 1994

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SOLID WASTE AND IRRADIATED FUEL SHIPMENTS: There were no shipments sent for burial.

A.1 TYPE Volume Activity' I im') (Co l l

Class Class 1

A B C A B C I Spent Resin' E E E E E E

1. a l

Filter Sludge g g g g g g l

Concentrated Waste g g g g g g i Evaporator Bottoms l Total g g g g g g

2. Dry Compressible Weste, Dry Q g g g g g Non Compressible Waste (Contaminated Equipment) ,

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3. Irradiated Components E E E E E E

' The estimated total error is 5.00E + 01 %.

' One Unit 1 steel cncased high integrity container of waste Class A bead resin was placed in interim storage at Nine Mile Point during the reporting period. The total activity was 5.73E + 00 curies and the volume was 5.69E + 00m'.

ATTACHMENT 6 Page 2 of 6 )

Unit 1 X Unit 2 Reporting Period July - December 1994 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.1 TYPE Solidification Container Packnae Anent

1. Spent Resin N/A N/A N/A Filter Sludge N/A N/A N/A Concentrated Waste N/A N/A N/A i
2. Dry Compressible Waste, N/A N/A N/A Dry Non-Compressible Waste (Contaminated Equipment)
3. Irradiated Components N/A N/A N/A I

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ATTACHMENT 6 Page 3 of 6 j l

Unit 11 Unit 2_ Reporting Period July P-- --1994 ]

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. SOLID WASTE AND IRRADIATED FUEL SHIPMENTS l A.2 ESTIMATE OF MAJOR NUCLlDE COMPOSITION (BY TYPE OF WASTE) 1

e. Spent Resins, Filter Studges, Concentrated Weste: There were no shipments Nuclide Percent
b. Dry Compressible Weste, Dry Non-Compressible Weste (Contaminated Equipment): There were no shipments.

Nuclide Percent a

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c. Irradiated Components: There were no shipments.

Nuclide ~ Percent

d. Other: There were no shipments, i Nuclide Percent 3

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Uni 1 X Unit 2 Reporting Period July - December 1994 SOLID WASTE AND 1RRADIATED FUEL SHIPMENTS A.3. SOLID WASTE DISPOSITION There were no shipments Number of Shipments Mode of Transportation Destination O N/A N/A B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)

There were no shipments.

Number of Shioments Mode of Transportation Destination O N/A N/A

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ATTACHMENT 6 Page 5 cf 6 Unit 1,2L, Unit 2_ Reporting Period July - December 1994 SOLID WASTE AND 1RRADIATED FUEL SHIPMENTS C. SOLtD WASTE SHIPPED OFF-SITE TO VENDORS FOR PROCESSING AND SUBSEQUENT BURIAL There were no shipments sent for burial.

Below is a summary of Dry Active Waste that was shipped off e5 for processing and burial by vendor faciltties (i.e.,

ALARON, AMERICAN ECOLOGY RECYCLE CENTER, INC., and/or SCIENTIFIC ECOLOGY GROUP) during July -

December 1994. These totals were reported separately from "10CFR61 Solid Waste Shipped for Burial" since (a) waste classification and burial was performed by the vendors, and (b) Technical Specification 6.9.1 requires reporting of "information for each class of solid waste (as defined by 10CFR61) shipped off-site during the reporting period" The inforrnation provided in this section, therefore, is in addition to that required by the Technical Specifications. The following data represents the actual shipments made from the off-site vendors of our non-compacted commingled trash that was processed prior to burial.

C.1. TYPE OF WASTE - noncompacted commingled trash shipped to Oak i Hidge, TN for processing prior to burial at Barnwell, SC Burial Volume Activity Est. Total (m 8) (Ci) Error % ,

9 0 5.00 + 01 C.2. ESTIMATE OF MAJOR NUCIIDE COMPOSITION:

There were no shipments.

Nuclide Percent C.3. SOLID WASTE DISPOSITION: There were no shipments.

Number of Shipments Mode of Transportation pestination 0 N/A N/A 1

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, . . ATTACHMENT 6 Page 6 of 6 -

Unit 1_ X Unit 2_ Reporting Period Julv - December 1994 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS D. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURit.L

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There were no shipments of sewage sludge with detecteMe quant &s of plant <eleted nucNdes from NMP to the treatment facility during the reporting period, d

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. ATTACHMENT 7

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' Unit 1 l_ Unit 2_ Reporting Period July - December 1994

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL'

.There were no changes to the Unit 1 Off-Site Dose Calculation Manual during the reporting period.

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. ATTACHMENT 8 Unit 1 X_ Unit 2 _ Reporting Period July - December 1994

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM The Unit 1 PCP Revision 02 was implemented in November 1994. Copies of Revisions 01 and 02 are attached. The following changes were approved by the Station Operations Review Committee (SORC)in October 1994 and do not affect or impact the safety of redweste operations. These changes were done to improve and/or reflect current redwaste operations.

Old Page # New Page # Section # Change Reason for Change 1 1 1.0 Changed the statement of Updated to reflect the purpose to include storing need for interim storage of low-level radioactive of radioactive wastes.

waste.

1 1 3.1.1 Added step a for the Updated to reflect the transferring between units transfer of wastes of wastes to be placed in between units for the interim storage. purpose of interim storage as determined necessary and as provided for by facilities allocations.

2 2 3.2 Added step 3.2.7 to Updated to reflect the identify procedural control need for interim storage for waste placed in of radioactive wastes.

interim storage.

3 3 3.4.1 Added step d to identify Updated to reflect the procedural control for need for interim storage waste placed in interim of radioactive wastes.

storage.

5 5 5.1 Added three references as References the Safety sters 5.1.5, 5.1.6 & Evaluation and UFSAR 5.1.7 sections for wastes and interim storage.

6 6 5.4 Added four supplemental Updated to reflect references as steps 5.4.4, current references.

5.4.5, 5.4.6 & 5.4.7 7 7 Attachment 1 Added the procedure for Updated to include the Interim Storage (S-WHP- current procedure for

1) to the Waste Handling !nterim Storage.

Procedures (WHPs) hst, i

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. ATTACHMENT 9

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Unit 1 X - Unit 2 Reporting Period July - C+: __.__.- 1994 l

SUMMARY

OF WOPERABLE MONITORS There were no inoperande monitors for a period poster then 30 days during the reporting period.

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ATTACHMENT 10 Page 1 cf 3

. ' SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1994)

. NINE MILE POINT NUCLEAR STATION UNIT 1 .

DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES lNSIDE THE SITE BOUNDARY  ;

JANUARY - DECEMBER 1994 Doses to members of the public (as defined by the Technical Specifications) from the operation of ,

the NMP1 facility as a result of activity inside the site boundary are based on activities at the  !

Energy Center. This facility is open to the public and offers educations information, summer picnicking activities and fishing. Any possible doses received by a member of the public by utilizing the private road that transverses the east and west site boundaries are not considered here since it ,

takes a matter of minutes to travel the distance.

The activity at the Energy Center that is useo for the dose analysis is fishing because it is the most time consuming. Although there is no specific survey information available, many of the same individuals have been observed to return again and again because of the access to salmonid and take trout populations. Dose pathways considered for this activity include direct radiation, inhalation and external ground (shoreline sediment or soil) doses. Other pathways, such as ingestion pathways, are not considered because they are either not applicable, insignificant, or are considered as part of the evaluation of the total dose to a member of the public located off-site.

Releases from the NMP1 stack and emergency condenser vents were evaluated for the inhalation pathway.

The direct radiation pathway is evaluated in accordance with the methodology found in the Offsite Dose Calculation Manual (ODCM). This pathway considers three components: direct radiation from the generating facilities, direct radiation from any possible overhead plume and direct radiation from plume submersion. The direct radiation pathway is evaluated by the use of high sensitivity environmental TLD's. Since any significant fishing activity near the Energy Center occurs between April through December, environmental TLD data for the approximate period April 1 - December 31, 1994 were considered. Data from two environmental TLD's from the approximate area where the fishing occurs were compared to control environmental TLD locations for the same time period.

The average fishing area TLD dose rate was 6.7E-03 mrem per hour for the period. The average control TLD dose rate was 5.9E-03 mrem per hour for the period (approximate cecond, third and fourth calendar quarters of the year). The average increase in dose as a result of fishing in this area at a conservative frequency of eight hours per week for thirty-nine weeks is 2.5E-01 mrem from direct radiation for the period in question. The majority of the dose from this pathway is from the NMP1 facility because of it's proximity to the fishing area. A small portion may be due to the NMP2 facility.

The inhalation dose pathway is evaluated by utilizing the inhalation equations in the ODCM, as adapted from the Regulatory Guide 1.109. The equation basically gives a total inhalation dose in mrem for the time period in question (April- December). The total dose equals the sum, for all applicable radionuclides, of the NMP1 stack and emergency condenser vent release concentration, times the average NMP1 stack and emergency condenser vent flowrate, times the applicable five.

year average calculated X/O, times the inhalation dose factors from Regulatory Guide 1.109, Table E-7, times the Regulatory Guide 1.109 annual air intake, times the fractional portion of the year in question, in order to be slightly conservative, no radiological decay is assumed.

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- ATTACHMENT 10 Pag) 2 cf 3

, SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1994)

NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY - DECEMBER 1994 1

The 1994 calculation utilized the following information ,

NMP1 Stack:

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- Unit 1 average stack flowrote = 1.11E+02 m'/sec

- X/Q value = 8.9 E-06 (annual NWN sector, historical average)

Inhalation dose factor = Table E-7 of Regulatory Guide 1.109

- Annual air intake = 8000 m* per year (adult) I

- Fractional portion of the year = 0.0356 (312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />)

- Co-60 = 1.10E-01 pCi/m 8 ,

- Fe-55 = 1.52E-01 pCi/m 8  !

- Sr 89 = 2.49E-01 pCi/m 8

- St-90 = 2.73E-02 pCi/m*

H-3 = 1.58E +04 pCi/m 8

- 1-131 = 1.03E-01 pCi/m 8 1 133 = 2.89E + 00 pCl/m 8

- Cs-137 = 7.43E-03 pCi/m 3 Emergency Condenser Vent:

Average Vent Flowrate = 4.42E-04 m 8/sec X/O value = 6.63E-06 (conservative ground level value)

Inhalation dose factor = Table E-7 of Regulatory Guide 1.109 Annual air intake = 8000 m 8per year (adult)

Fractional portion of the year = 0.0356 (312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />)

Sr-89 = 1.41E +02 pCi/m 8 Sr-90 = 1.74E + 01 pCi/m*

Cs- i'J 7 = 2.58E +01 pCi/m 8 Co-60 = 5.31E +02 pCi/m 8 '

Mn-54 = 3.21 E + 01 pCi/m*

Fe-55 = 2.33E+ 02 pCi/m 8 H3 = 1.54E + 09 pCi/m3- see note below The inhalation dose to a member of the public from NMP-1 as a result of activities inside the site I boundary is 1.16E-03 mrem to the thyroid (maximum organ dose) and 9.05E-04 mrem to the whole body.

The dose from standing on the shoreline while fishing is based on the methodology in the ODCM, as adapted from Regulatory Guide 1.109. During 1994, it was noted that fishing was performed from the shoreline on many occasions although waders were also utilized in order to be conservative, it is assumed that the maximum exposed individual fished from the shoreline at all times. The use of waders, of course, would result in a dose of zero from this pathway. The shoreline sediment doses are not taken into consideration by environmental TLD data. i l

The ODCM equation basically gives the total dose to the whole body and skin from the sum of all l plant-related radionuclides detected in shoreline sediment samples. The plant related radionuclide concentration is adjusted for background sample results, as applicable. The equation, therefore, l yields the whole body and skin dose by multiplying the radionuclide concentration adjusted for any '

background data (as applicable), times a usage factor, times the sediment or soil density in grams per square meter (to a depth of one centimeter), times the applicable shore width factor, times the regulatory guide dose factor, times the fractional portion of the year over which the dose is applicablo. in order to be conservative and to simplify the equation, no radiological decay is assumed since the applicable radionuclides are usually long lived.

Note: Assumed release based on the concentrations in the condensate storage tanks and condenser shell.

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ATTACHMENT 10

, Page 3 of 3 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1994)

NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY - DECEMBER 1994

- The calculation utilized the following information:

- Usage factor = 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> Density in grams per square meter = 40,000 -

Shore width factor = 0.3

- Whole body and skin dose factor for each radionuclide = Regulatory Guide 1.109, Table E-6

- Fractional portion of the year = 1 (used average radionuclide concentration over total time period)

Average Cs-137 concentration = 0.208 pCi/g Average Co-60 concentration = 0.017 pCi/g The total whole body and skin dose from standing on the shoreline to fish is 4.4E-03 mrem whole body and 5.1E-03 mrem skin dose for the period.

Doses to members of the public relative to activities inside the site boundary from aquatic pathways other than ground dose from shoreline sediment / soil are not applicable.

In summary, the total dose to a member of the public as a result of activities inside the site boundary from the direct radiation, inhalation and shoreline dose pathways is 2.6E-01 mrem to the whole body and 1.2E-03 mrem to the maximum exposed internal organ (thyroid). The dose to the skin of an adult is 5.1E-03 mrem. These doses are generally a result of the operation of NMP1. However, a portion of these doses for the direct radiation pathway may be attributable to the NMP2 facility.

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ATTACHMENT 11 Pag) 1 cf 3

. - SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1994)

NINE MILE POINT NUCLEAR STATION UNIT 1 RADIATION DOSES TO THE LIKELY MOST EXPOSED MEMBER OF THE PUBLIC  ;

OUTSIDE THE SITE BOUNDARY t

JANUARY - DECEMBER 1994 Radiation doses to the likely most exposed member of the public outside of the site boundary are  ;

evaluated relative to 40CFR190 requirements. The dose limits of 40CFR190 are 25 mrem (whole i body or organ) per calendar year and 75 mrem (thyroid) per calendar year. The intent of i 40CFR190 also requires that the effluents of NMP1 as well as other neerby uranium fuel cycle I facilities be considered. In this case, the effluents of NMP1, NMP2 and the James A. FitzPatrick (JAF) facilities must be considered. .

Doses to the likely most exposed member of the public as a result of effluents from the site can be evaluated by using calculated dose modeling based on the accepted methodologies of the facilities'

' Off-site Dose Calculation Manuals (ODCM's) or may, in some cases, be calculated from the analysis results of actual environmental samples. Acceptable methods for calculating doses from i environmental samples are also found in the facilities' ODCM's. These methods are based on Regulatory Guide 1.109 methodology.

Dose calculations from actual environmental samples are, at times, difficult to perform for some pathways. Some pathway doses should be estimated using calculational dose modeling. These pathways include noble gas air dose, inhalation dose, etc. Other pathway doses may be calculated directly from environmental sample concentrations using Regulatory Guide 1.109 methodology.

Since the effluents from the generating facilities are low, the resultant gaseous and liquid effluent i doses are anticipated to be low. In view of this, doses can be based on calculated data. Doses are not based on actual environmental data for 1994 with the exception of doses from direct radiation, ,

fish consumption and shoreline sediment. In addition, in order to be conservative and for the sake  ;

of simplicity, it is assumed in the dose calculations that the likely most exposed member of the  ;

public is positioned in the maximum receptor location for each pathway at the same time. This i approach is utilized because the doses are very low and the computations are greatly simplified.

The following pathways are considered: l

1. The inhalation dose is calculated at the critical residence because of the high occupancy factor. I In order to be conservative, the maximum whole body and organ dose assumes no correction for residing inside a residence.
2. The milk ingestion dose is calculated utilizing the maximum milk cow location. As noted previously, in order to be conservative and for the sake of simplicity, the likely most exposed member of the public is assumed to be at all critical receptors at one time. In this case, the member of the public at the critical residence is assumed to consume milk from the critical milk [

location, j

3. The maximum dose from the milk ingestion pathway as a result of consuming goat's milk is  !

based on the same criteria established for item *2", above (ingestion of cow's milk).

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, ATTACHMENT 11 - Page 2 cf 3  !

. SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1994)

NINE MILE POINT NUCLEAR STATION UNIT 1 RADIATION DOSES TO THE LIKELY MOST EXPOSED MEMBER OF THE PUBLIC OUTSIDE THE SITE BOUNDARY JANUARY DECEMBER 1994

4. The maximum dose associated from consuming meat is based on the critical meat animal. The likely most exposed member at the critical residence is assumed to consume meat from the  :

critical meat animal location.

5. The maximum site dose associated with the consumption of vegetables is calculated from the critical vegetable garden location. An noted previously, the likely most exposed member of the public is assumed to be located at the critical residence and is assumed to consume vegetables from the critical garden location.
6. The dose, as a result of direct gamma radiation from the site, encompasses doses from direct

" shine" from the generating facilities, direct radiation from any overhead gaseous plumes, ,

plume submersion and from ground deposition. This total dose is measured by environmental l TLD. The critical location is based on the closest year-round residence from the generating facilities 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 the local meteorology. During 1994, the closest residence and the critical downwind residence are at the same location The measured average dose of 1994 at the critical residence was 50.2 mrem. The average control dose was 48.8 mrem. The average dose at the critical residence is slightly greater than i the average controllocation dose. The net increase in dose is due to the differences between doses from naturally occurring radionuclides in the soil and rock at the different locations and due to the standard deviation in TLD measurements. This difference is dose rate can be demonstrated by observing the 1994 average dose for an environmental TLD located near the ,

critical residence TLD, but approximately 700 feet closer to the generating facilities. The '

annual average dose for this TLD location was 48.0 mrem. The dose for this location is lower than the critical residence location even though they are close to one another and even though the TLD location with the lowest dose is closer to the generating facilities.

7. The dose, as a result of fish consumption, is considered as part of the aquatic pathway. The dose for 1994 is calculated from actual results of the analysis of environmental fish samples.

For the sake of being conservative, the average plant-related radionuclide concentrations were utilized from fish samples taken near the site discharge points. Only Cs-137 was detected during 1994. Adjusting the average concentration of Cs-137 in indicator samples by subtracting the average concentration of Cs-137 in control samples resulted in a net negative concentration. Therefore, no dose was calculated and assumed to be zero for this pathway.

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ATTACHMENT 11 Page 3 of 3 SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1994 NINE MILE POINT NUCLEAR STATION UNIT 1 RADIATION DOSES TO THE LIKELY MOST EXPOSED MEMBER OF THE PUBLIC OUTSIDE THE SITE BOUNDARY JANUARY - DECEMBER 1994

8. The shoreline sediment pathway is considered relative to recreational activities. The dose due to recreational activities from shoreline sediment is based on the methodology in the ODCM as ,

adapted from Regulatory Guide 1.109. The ODCM gives the total dose to the whole body and skin from the sum of plant-related radionuclides detected in actual shoreline sediment samples.

The plant-related radionuclide concentration is adjusted for background sample results, as applicable. The total whole body and skin dose from shoreline recreational activities is 7.7E-04 mrem whole body and 9.OE-04 mrem skin dose for the period. '

9. In summary, the maximum dose to the most likely exposed member of the public is 6.14E-02 mrem to the thyroid (maximum organ dose) and 2.55E-02 mrem to the whole body. It should be noted that the maximum organ dose and maximum whole body doses are based on the sum of the maximum doses observed for all three facilities regardless of age group. This results in some conservatism. The maximum organ and whole body doses were a result of gaseous effluents. Doses as a result of liquid effluents were secondary. The total whole body and skin dose from shoreline recreational activities are 7.7E-04 mrem whole body and 9.OE-04 mrem skin dose for the period. The direct radiation dose to the critical residence from the generating f acilities was insignificant or zero. The dose to an individual as a result of fish consumption was also zero. These maximum total doses are a result of operations at the ,

Nine Mile Point Unit 1, Nine Mile Point Unit 2 and the James A. Fitzpatrick facilities. The maximum organ dose and whole body dose are below the 40CFR190 criteria of 25 mrem per calendar year to the maximum exposed organ or the whole body, and below 75 mrem per calendar year to the thyroid.

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9 9 9 UPDATE TO THE PREVIOUS REPORTS i

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, , Unit 1 J,_ Unit 2_ Reporting Period Julv F - -1994  !

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, UPDATE or nELEAsE AND DOSE DATA POR GASEOUS (ELEVATED AND ORoUND LEVELI AND UQUID EFFLUENTS I

Updata of osta using actual results from the off-site vendors for Strontium, Tritium, and trorF55 for the second quarter of-- '

1994.

GASEOUS LIQUID -  !

2" QUARTER .2dQUARTER Nuclide' Activity (Ci) Activity (Ci)  !

l Sr-89 4.26E - 05 No Releases l l

Sr-90 8 96E-08 No Releases H3 6.60E + 00 No Releases ,

1 Fe 55 6.28E- 06 No Releases f Particulates GASEOUS LIQUID ,

f

1. Particulates with Ci 1.69E - 04 NL4 l half-lives >8 days *.
2. Average release rate pCi/sec 2.15E- 05 g[A, I for period Tritium [

c

1. Total release Ci 6.50E + 00 NL4
2. Average release rate pCi/sec 8.27E - 01 NLA, for period .

Tritium, lodines, and GASEOUS LIQUID ,

Particulates (with half- ,

lives arester than 8 9.aysl

1. Percent of Quarterly  % 658E-02 NLA Dose Limit' (Quarterly) (Quarterly)
2. Percent of Annual  % 5.85E - 02 N/A Dose Limit to Date8 (Annual) (Annual)
3. Percent of Organ  % 1.32E - 03 g!_4

- Dose Rate Limit (Quarterly) (Quarterly)

(Gaseous)(Quarterly) NL4 gi4  :

- Dose Limit (Liquid) (Annual) (Annual) 'i (Annual & Quarterly)

4. Percent of 10CFR20  % N!A NLA, f Concentration Limit t (Liquid) T
5. Percent of Di6 solved  % N/A N/A or Entrained Noble Gas (Liquid) b i

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5 Cercentrations less than the lower limit of detection, as required by Technical Specifications are indicated with a double asterisk.

The dose is to the maximally exposed organ for gaseous effluents.

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, ATTACHMENT 6' ' Page 5 cf 6  ;

Unit 1.E_ Unit 2 ,,,,,,, Reporting Period Januarv - June 1994

, SOLID WASTE ANI,.hRADIATED FUEL SHIPMENTS C. S' O LID WASTE SHIPPED OFF-SITE TO VENDORS FOR PROCESSING AND SUBSEQUENT BURIAL

, Below is a summary of Dry Active Waste that was shipped off-site for processing and burial by vendor facilities (i.e.,

l.

ALARON, AMERICAN ECOLOGY RECYCLE CENTER, INC., and/or SCIENTIFIC ECOLOGY GROUP) during January -

^

,!yne 191e4 These totals were reported separately from *10CFR61 Solid Waste Shipped for Burial" since (a) waste classification and burial was performed by the vendors, and (b) Technical Specification 6.9.1 requires reporting of

  • information for each class of solid waste (as defined by 10CFR61) shipped off-site during the reporting period" The j information provided in this section, therefore, is in addition to that required by the Technical Specifications. The i following data represents the actual shipments made from the off site vendors of our non-compacted commingled trash that was processed prior to bt. rial. The number of shipments reported here represents the total number that was shipped from the off-site vendor for burial. This does not represent the number of shipments Niagara Mohawk sent to be processed, nor does it represent the operating history during January . June 1994. The number of shipments i buried represent what was actually buried by the vendor during January June, but does not necessarily reflect the  !

waste or D.A.W. that was generated during January - June 1994. The vendor will await shipment until a full cask is j ready which means that NMPC waste can be commingled with other licensees

  • waste. However, the vendor performs 5 an analysis for each shipment to determine the volume and activity buried under each utilities' license, and prepares a  ;

separate report for each licensee. t I

C.1. TYPE OF WASTE - noncompacted commingled trash and i contaminated fuel pool equipment shipped to Oak Ridge, TN for Burial Volume Activity Est. Total I processing prior to burial at Barnwell, SC (m') (Cil Error. % l 2.83E + 01 4.44E - 01 5.00 + 01 l 1

C.2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION  !

i Nuclide Percent f

(1) Co-60 5.75E + 01 ,

'(2) Cs-137 3.07E + 01 '

(3) Mn-54 5.39E + 00  :

(4) CO-58 2.30E + 00  !

(5) Cr-51 <

1.52E + 00 l (6) Fe-59 i.23E + 00 (7) Other 1.36E + 00 j C.3. SOLID WASTE DISPOSITION l

1 Number nf Shipments Mode of Transportation Destination

,41 Truck Barnwell SC l

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l This Attachment 6 supersedes the information provided in the January - June 1994 Semi-Annual Radioactive Effluent Release Report with an update of burial volume, activity, nuclide composition, and number of shipments for Nine Mile Point Nuclear Station Unit 1.

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ATTACHMENT 10 - Pag) 1 cf 3

. SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1993)

NINE MILE POINT NUCLEAR STATION UNIT 1

  • DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY - DECEMBER 1993 Doses to members of the public (as defined by the Technical Specifications) from the operation of the NMP1 facility as a result of activity inside the site boundary are based on activities at the Energy Center. This f acility is open to the public and offers educational information, summer picnicking activities and fishing. Any possible doses received by a member of the public by utilizing the private road that transverses the east and west site boundaries are not considered here since it takes a matter of minutes to travel the distance. {

l-The activity at the Energy Center that is used for the dose analysis is fishing because it is the most time consuming. Although there is no specific survey information available, many of the same individuals have been observed to return again and again because of the access to salmonid and lake trout populations. Dose pathways considered for this activity include direct radiation, inhalation and external ground (shoreline sediment or soil) doses. Other pathways, such as ingestion pathways, are not considered because they are either not applicable, insignificant, or are considered as part of the evaluation of the total dose to a member of the public located off-site. In addition, only releases from the NMP1 stack were evaluated for the inhalation pathway. The emergency condensers were not operated during 1993.

The direct radiation pathway is evaluated in accordance with the methodology found in the Off-Site Dose Calculation Manual (ODCM). This pathway considers three components: direct radiation from the generating facilities, direct radiation from any possible overhead plume and direct radiation from plume submersion. The direct radiation pathway is evaluated by the use of high sensitivity i environmental TLD's. Since any significant fishing activity near the Energy Center occurs between -

April through December, environmental TLD data for the approximate period of April 1 - December 31,1993 were considered. Data from two environmental TLD's from the approximate area where the fishing occurs were compared to control environmental TLD locations for the same time penod. ,

The average fishing area TLD dose rate was 7.0E-03 mrem per hour for the period. The average '

control TLD dose rate was 5.7E-03 mrem per hour for the period (approximate second, third and fourth calendar quarters of the year). The average increase in dose as a result of fishing in this area at a conservative frequency of eight hours per week for thirty-nine weeks is 4.1E-01 mrem from direct radiation for the period in question. The majority of the dose from this pathway is from ,

the NMP1 facility because of it's proximity to the fishing area. A small portion may be due to the NMP2 facility. t The inhalation dose pathway is evaluated by utilizing the inhalation equation in the ODCM, as i adapted from the Regulatory Guide 1.109. The equation basically gives a total inhalation dose in '

mrem for the time period in question (April- December). The total dose equals the sum, for all applicable radionuclides, of the NMP1 stack release concentration, times the average NMP1 stack flowrate, times the applicable five-year average calculated X/Q, times the inhalation dose factors from Regulatory Guide 1.109, Table E-7, times the Regulatory Guide 1.109 annual air intake, times the fractional portion of the year in question. In order to be slightly conservative, no radiological .

decay is assumed.

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. ATTACHMENT 10 Page 2 of 3 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1993) ,

NINE MILE POINT NUCLEAR STATION UNIT 1

  • DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY - DECEMBER 1993 The 1993 calculation utilized the following information:

NMP1 Stack:

Unit 1 average stack flowrate = 1.04E+02 m 8/sec

- X/O value = 8.9 E-06 (annual NWN sector, historical average)

Inhalation dose factor = Table E-7 of Regulatory Guide 1.109 Annual air intake = 8000 m 8per year (adult) ,

- Fractional portion of the year = 0.0356 (312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />)

Co-60 = 1.05E-01 pCi/m 8 Fe-55 = 6.68E-02 pCi/m 8

- Sr-89 = 1.24E -01 pCi/m Sr-90 = 1.13E-02 pCi/m*

H-3 = 5.81 E + 03 pCi/m 8 1-131 = 2.63E-02 pCi/m*

1-133 = 7.73E-02 pCi/m 8

- 1-135 = 1.42E-02 pCi/m*

The inhalation dose to a member of the public from NMP1 as a result of activities inside the site boundary is 2.72E-04 mrem to the lung (maximum organ dose) and 2.44E-04 mrem to the whole body.

The dose from standing on the shoreline while fishing is based on the methodology in the ODCM, as adapted from Regulatory Guide 1.109. During 1993, it was noted that fishing was performed ,

from the shoreline on many occasions although waders were also utilized. In order to be i conservative, it is assumed that the maximum exposed individual fished from the shoreline at all times. The use of waders, of course, would result in a dose of zero from this pathway. The shoreline sediment doses are not taken into consideration by environmental TLD data.

The ODCM equation basically gives the total dose to the whole body and skin from the sum of all plant-related radionuclides detected in shoreline sediment samples. The plant-related radionuclide concentration is adjusted for background sample results, as applicable. The equation, therefore, yields the whole body and skin dose by multiplying the radionuclide concentration adjusted for any I background data (as applicable), times a usage factor, times the sediment or soil density in grams '

per square meter (to a depth of one centimeter), times the applicable shore width factor, times the regulatory guide dose factor, times the fractional portion of the year over which the dose is  ;

applicable. In order to be conservative and to simplify the equation, no radiological decay is '

assumed since the applicable radionuclides are usually long lived.

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, e ATTACHMENT 10 Page 3 of 3 l L -

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1993)

NINE MILE POINT NUCLEAR STATION UNIT 1* i DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES J INSIDE THE SITE BOUNDARY  !

l JANUARY - DECEMBER 1993 '

The calculation utilized the following information:

- Usage factor = 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> Density in grams per square meter = 40,000 Shore width factor = 0.3 Whole body and skin dose factor for each radionuclide = Regulatory Guide 1.109, Table E-6 i

l- -

Fractional portion of the year = 1 (used average radionuclide concentration over total time period)

Average Cs-137 concentration = 0.295 pCi/g Average Co-60 concentration = 0.031 pCi/g The total whole body and skin dose from standing on the shoreline to fish is 6.61E-03 mrem whole body and 7.73E-03 mrem skin dose for the period.

Doses to members of the public relative to activities inside the site boundary from aquatic pathways other than ground dose from shoreline sediment / soil are not applicable. ,

in summary, the total dose to a member of the public as a result of activities inside the site boundary from the direct radiation, inhalation and shoreline dose pathways is 4.2E-01 mRern to the whole body and 2.72E-04 mrem to the maximum exposed internal organ (lung). The dose to the skin of an adult is 7.73E-03 mrem. These doses are generally a result of the operation of NMP1. However, a portion of these doses for the direct radiation pathway may be attributable to the NMP2 facility. '

' This Attachment 10 superriedes the previous Attachment 10 submitted in the " July-December 1993 Semi-Annual Radioactive Effluent Release Report," and represents an update of various radionuclide actwities and subsequent internal organ dose and whole body dose. The update is due to the receipt of offsite vendor analyses and an error in the calculation of the pCi/m'.

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