ML20207G078

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Semi-Annual Radioactive Effluent Release Rept for 980701-981231 for NMP-1
ML20207G078
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 12/31/1998
From:
NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML20207G071 List:
References
NUDOCS 9903110411
Download: ML20207G078 (28)
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Text

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NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1998 NIAGARA MOHAWK POWER CORPORATION

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Page 1 of 2 NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY- DECEMBER 1998 SUPPLEMENTAL INFORMATION Facility: Nine Mile Point Unit #1 Licensee: Niagara Mohawk Power Corporation

1. TECHNICAL SPECIFICATION LIMITS A) FISSION AND ACTIVATION GASES
1. The dose rate limit of noble gases released in gaseous efHuents from the site to areas at and beyond the site boundary shall be less than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year to the skin.

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2. The air dose due to noble gases released in gaseous effluents from Nine Mile Point Unit I to I areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 milliroentgen for gamma radiation and less than or equal to 10 mrad for ,

I 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 mrad for beta radiation. l l

l B&C) TRITIUM,10 DINES AND PARTICULATES, HALF LIVES > 8 DAYS l l

1. The dose rate limit of lodine-131, lodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days, released in gaseous effluents from the site to areas at and beyond the site boundary shall be less than or equal to 1500 mrem / year to any organ.
2. The dose to a member of the public from lodine-131, lodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from Nine Mile Point Unit I to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrem to any organ and, during any calendar year to less than or equal to 15 mrem to any organ.

D) LIQUID EFFLUENTS

1. The concentration of radioactive material released in liquid effluents to unrestricted areas j shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table 11, '

Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 microcuries/ml total activity.

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

A) FISSION AND ACTIVATION GASES Noble gas effluent activity is determined by on-line gamma spectroscopic monitormg (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 and composite analysis of the filters for non-gamma emitters.

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

E) EMERGENCY CONDENSER VENT EFFLUENTS The 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 and actual release rates are determined from post offsite analysis results. The activity of fission and activation gases released due to tube leaks is based on reactor steam leak rates using offgas isotopic analyses.

F) LlQUID EFFLUENTS Isotopic contents of liquid effluents are determined by isotopic analysis of a representative sample of each batch and composite analysis of non-ganuna emitters.

G) SOLID EFFLUENTS isotopic contents of waste shipments are determined by gamma spectroscopy analysis of a representative sample of each batch. Scaling factors established from primary composite sample f 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.

i ATTACHMENT 1 Summary D:t3 P:gt 1 Of 2 1 Unit 1 X Urut 2 Reporting Period July December 1998 Uguid Effluente; f

, . 10CFR20, Appendix B, Table 11, Column 2 Average MPC uCl/ml(Otr. 3) = N/A Average MPC uCi/rni (Qtr. 4) = NIA Average Energy (Fieelon and Activation gases Movi:

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l Otr. L  : By = 2.47E - 01 P, = 3.17E 01 Qtr. L  ? By = 2.47E - 01 Pe = 3.17E 01 Uquid:

Number of batch releases . O Total time period for batch releases (hrs)  : N/A i

Maximum time period for a batch release (hrs)  : N/A i i

Average timo 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 I the hquid effluent dunng release period (L) NLA Total volume of dilution water available during the reporting period (L)  : 2.77E + 11 Gaseous (Emergency Condeneer Vent):

Number of batch releases '

O Total time period for batch releases (hrs)  : N/_A Maximum time period for a batch release (hrs)  : NA Average time period for a batch release (hrs)  : NM Mmimum time period for a batch release (hrs)  : N_I_A Geseous (Primary Containment Purgel:

Number of batch teleases 0 Total time period for batch releases (hrs)  : N/A Maximum time period for a batch release (hrs)  : NLA Average time period for a batch release (hrs)

  • NJA Minimum time period for a batch release (hrs) ,

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ATTACHMENT 1 Summ*ry Dito Pros 2 of 2 Urvt1 X Unit 2 Reportmg Penod July - December 1998 Abnormal Releases:

A.. Uguide; Number of releases 0 Total activity released N]_A Ci B. Gaseous:

Number of releasee 0 Total activity released NLA Ci l

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I ATTACHMENT 2 Urdt 1 X Unit 2 Reportmg Period July - December 1998 l

l GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES. ELEVATED AND GROUND LEVEL l l 3 4* EST. TOTAL QUARTER OUARTER ERROR,%

i A. tiesion & Activation cases l

1. Total release Ci 5.84E - 04 1.55E - 03 5.00E + 01 1
2. Average release rate uCi/sec 7.35E - OS 1.95E - 04 l l

B. lodines J

1. Total lodine-131 Ci 1.66E 04 1.89E - 04 3.00E + 01
2. Average release rate for period uCi/sec 2.00E OS 2.40E - 05 C. Particulates' ,

1 Particulates with half-lives >8 days Ci 1.81E 04 8 63E - 04 3.00E + 01 j

2. Average release rate for period uCi/sec 2.19E - 05 1.10E - 04 1
3. Gross alpha radioactivity Ci 5.50E - OS 3.86E - 05 2.50E + 01 l l

D. Tritium' ,

1. Total release Cl 1.73E + 01 4.79E + 01 5.00E + 01
2. Average release rate for period uCi/sec 2.18E + 00 6.09E + 00 l i E. Percent of Tech. Spec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose  % 4.72E - 06 1.25E - 05 Limit (5 mR)

Percent of Quarterly Beta Air Dose Limit  % 3.03E 06 8.01E - 06 (10 mrad)

Percent of Annual Gamma Air Dose Limit  % 6.31E 05 6.94E - 05 to Date (10 mR)

Percent of Annual Beta Air Dose Limit to  % 2.78E 05 3.18E - 05 Date (20 mrad)

Percent of Whole Body Dose Rate Limit  % 1.23E - 07 3.27E - 07 (500 mrem /yr)

Percent of Skin Dose Rate Limit  % 5.44E - 08 1.44E 07 (3000 mrem /yr)

F. Tritium, lodines, and Particulates' (with half lives areater than 8 days)

Percent of Quarterly Dose Limit  % 1.93E - 01 3.15E - 01 (7.5 mrom)

Percent of Annual Dose Limit  % 2.23E - 01 4.47E - 01 (15 mrem)

Percent of Organ Dose Rate Limit  % 3.E7E - 03 6.33E - 03 (1500 mrem /yr)

I Tritium, iron-55, and Strontium results for the fourth quarter were not received from the off site vendor at the time of this report. These numbers include estimates. Actual numbers will be provided in the next Semi-Annual Report.

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ATTACHMENT 3

,l i t11 Wt2 - Reporting Penod July December 1998 l GASEOUS EFFLUENTS ELEVATED RELEASE l

CONTINUOUS MODE' 3* 4*

Nuclides Rolenoed OUARTER QUETER .

1. Fission Gesee' i i

Argon-41 Ci ++ **  !

Krypton-85 Ci " ++ ,

Krypton-85m Ci G U  !

Krypton-87 Ci G U 1

    • ++

Krypton-88 Ci - _

i Ci ** ++

Xenon-127 i Xenon-133 Ci U U l Xenon 133m Ci U U f Ci ++ ++

Xenon-135 Ci ++ ++

Xenon-135m .

Xenon-137 Ci G U  !

Ci ++ ++

Xenon-138 - _

2. lodines' lodine.131 Ci 1.66E - 04 1.89E - 04 lodine 133 Ci 1.24E - 03 1.43E 03 Ci " "

lodine-135

3. Particulates 1.a Stu ntium-89 Cl 1.64E - 05 3.24E - 04 S trontium-90 Ci 3.92E - 05 Ci " ++

Cesium-134 Ci " 2.06E - 05  !

Cesium 137 Cobalt-60 Ci 1.62E 04 2.39E 04 Cobalt-58 Ci 1.28E 05 Ci " "

Manganese-54 Ci " "

Barium-Lanthanum 140 Antimony 125 Ci Ci " ++

Niobium 95 Cerium-141 Ci 1.05E - 05 Ci " "

Cerium 144 Ci " ++

Iron-59 Ci " "

Cesium- 136 Ci " 3.80E - 05 Chromium-51 Ci " "

Zinc 65 tron-55 Ci ', 1.77E - 04 Ci " " l Molybdenum-99 Neodymium-147 Ci 3 {

4. Tritium' Ci 3.99E + 00 2.52E + 01 Concentrations less than the lower limit of detection of the counting system used are indicated with a double i asterisk. A lower limit of detection of 1.00E-04 uCi/ml for required noble gases,1.00E-11 uCi/mi for required  !

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

8 Tritium, Iron-55, and Strontium results for the fourth quarter were not received from the off-site vendor at the time of this report. These numbers include estimetes. Actual numbers will be included in the next Semi Annual j Report.

a Contributions from any purges are included.

+ ATTACHMENT 4 Unit 1 X- Unit 2 - Reporting Period July - December 1998 GASEOUS EFFLUENTS - OROUND LEVEL RELEASES Ground level roleseos are determined in accordance with the Off Site Dose Calculation Manuel and Chemistry procedures.

CONTINUOUS MODE BATCH MODE There were no batch releases during the reporting period 35 4* 3d g OUARTER QUARTER QUARTER QUARTER

1. Fission Gases' Ci *+ ++

Argon-41 ~ ~~

Ci *+ ++

Krypton-85 Ci " ++

Krypton-85m Ci ' +*

Kryptorv87 Ci " ++

Krypton-88 Ci " "

Xenon-133 Xenon-133m Ci Xenon-135 Ci 5.84E 04 1.55E - 03 Ci " ++

Xenon-135m Ci " ++

Xenon-137 Xenon-138 Ci Ci ** ++

Xenon-127

2. lodines' lodine-131 Ci Ci " ++

lodine-133 Ci " ++

lodine-135

3. Particulates' 8 Strontium-89 Ci 2.28E - 07 Strontium-90 Ci 2.84E - 08 Ci ", "

Cesium 134 Cesium-137 Ci 5.46E 09 ",

Cobalt-60 Ci M5E **

06 8.59E 07 Cobalt 58 Ci Mangar ese-54 Ci 1.49E - 07 3.41E - 08 Ci a "

Barium-Lanthanum 140 Ci ", ++ l Antimony 125  !

Ci ", ++

Niobium-95 Ci ", "

Cerium-141 Ci " ++

Cerium-144 Ci " ++

fron-59 Cesium-136 Ci ",

Ci " "

Chromium-51 Ci ++ ++

Zinc 85 Iron-55 Ci 1.13E - 06 5.19E - 07 Ci " "

Molybdenum-99

4. Tntium' Ci 1.34E + 01 2.27E + 01 I

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

a j Iron-55 and Strontium results for the fourth quarter were not received from the off-site vendor at the time of this report, These numbers include estimates. Actual numbers will be included in the next Semi-Annual Report.

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ATTACHMENT 5 '

Page 1 of 2 Unit 1. X Unit 2 Reporting Period July - December 1998 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 3d 4* EST.

QUARTER QUARTER TOTAL ERROR, %

A. Fission & Activation Products  !

1. Total release (not including Tritium, gases, alpha) Ci No Releases No Releases 5.00E + 01
2. Average diluted concentration during reporting period uCi/mi No Releaser No Releases '

B. Tritium

1. Total release Ci No Releases No Releases 5.00E + 01
2. Average diluted concentration during reporting period uCi/mi No Releases No Releases f

C. Dissolved and Entrained Garg

1. Total release Ci No Rolemees No Releases 5.00E + 01
2. Average diluted concentration during reporting period uCi/mi No Releases No Releases L D. Gross Alphe Radioactivity
1. Total release Ci No Releases No Releases 5.00E + 01 E. Volumes
1. Prior to dilution Liters No Releases No blesses 5.00E + 01
2. Volume of dilution water available during release period Liters No Releases No Releases 5.00E + 01
3. Volume of normal service water available during the Liters 1.41E + 11 1.36E + 11 5.00E + 01 reporting period.  ;

F. Percent of Technical Specification Limits Percent of Quarterly Whole Body Dose Linst (1.5 mrem)  % No Releases No Releases j Percent of Quarterly Organ Dose Limit (5 mrem)  % No blesses No Rekaseo Percent of Annual Whole Body Dose Limit to Date (3 mrem)  % No blesses No Releases Percent of Annual Organ Dose Limit to Date (10 mrem)  % No Releases No Releases l Percent of 10CFR20 Concentration Limit  % No Releases No Releases l Percent of Dissolved or Entrainoa Noble Gas Limit  % No Releases No Releases l (2.00E-04 uCi/ml)

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et ATTACHMENT 5 Page 2 of 2 Unit 1 X 15 nit 2 Reporting Period July - December 1998 LIQUID EFFLUEN7"., RELEASED BATCH MODE' Nuclides Released QUA TER QUA TER Strontium-89 Ci No Releases No Releases Strontium-90 Ci No Releases No Roleases l Cesium-134 Ci No Releases No Releases l Cesium-137 Ci No Releases No Roleseos lodine 131 Ci No Releases No Releases Cobalt-58 Ci No Releases No Releases Cobalt-60 Cl No Releases No Releases l tron 59 Ci No Releases No Releases Zinc-65 Ci No Rolesses No Releases Manganese-54 Ci No Releases No Releases Chromium-51 Cl No Releases No Releases  ;

i Zirconium-Niobium-95 Ci No Releases No Releases l Molybdenum-99 Ci No Reieases 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 Cl No Releases No Releases l Neptunium-239 Ci No Releases No Releases l Praseodymium-144 Ci No Releases No Releases l lodine-135 Ci No Releases No Releases I

l Dissolved or Entrained Gases Ci No Releases No Releases i Tritium Ci No Releases No Releases

' No continuous mode release occurred during the report period.

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ATTACHMENT 6 Page 1 of 6

. Unit 1 ' X ' Unit 2 Reporting Penod July December 1998 8000 WASTE AND mRADIATED FUEL SHIPMENTS:

A.1 TYPE Volume Activity' a

(m ) (C0 Class Class A B C A B C to Spent Rosin SM g g +02 9 9 (Dewatered)

Filter Sludge p p p 9 9 9 Concentrated Waste .0 0 0 0 0 0 Evaporator Bottoms Total 9 9 9 9 9 9

2. Dry Compressible Waste 9 9 9 9 9 9 3, Irradiated Components 9 9 9 9 9 2
4. Other:

1 l A. Evaporator Bottoms to 1.66E + 01 4.40E + 01 Q 1.90E + 01 8.91 E + 01 0 Vendor for Processing l

B. Dry Compressible 3.33E + 01 p p 3.942 - 02 0 9

! Waste to Vendor for i Processing C. Dewatered Bead 2.81E + 01 p p 2.06E + 01_ p 9 l Resin to Vendor for Procassing l

The estimated total error is 5.00E + 01 %.

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ATTACHMENT 6 Page 2 of 6 i

. Unit l' X Unit 2 Reporting Period July December 1998 SOLID WASTE AND 1RRADIATED FUEL SHIPMENTS i A.1 TYPE Solidification Container Packana Agent i

1. Spent Posin Poly Hic Type A None  ;

. (De'vatored) i Filter Sludge N/A N/A N/A j Concentrated Warte N/A N/A N/A

2. Dry Compressible Weste (non-compacted) '

N/A N/A N/A

3. Irradiated Components N/A N/A N/A l
4. Other l A. Evaporator B0ttoms P,olyjalc Type A None i B. Dry Compressible Weste Metal Box Type A None l C. Dewatered Bead Rosin Poly HIC Type __A None I

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ATTACHMENT 6 Page 3 of 6 l

l Unit 1 X Unit 2 Reporting Period July December 1998 SOLIO WASTE AND NIRADIATED FUEL SHIPMENTS h A,2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)

e. Spent Rosine l
Nuclide Percent  !

l (1) Co-60 8.82E + 01 (2) Mn-54 8.21 E + 00 (3) Ni 63 2.21 E + 00 i (4) Other 1.38E + 00

b. Dry Compressible Weste: There were no shipmente.
c. Irradiated Componente: There were no shipraente.

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1. Other: Eveporetor Bottoms l Nuclide Percent (1) Cs-137 5.15E + 01 i (2) Co-60 4.03E + 01 .

l (3) Mn-54 4.49E + 00 l l (4) Fe-55 1.24E + 00 ,

f (5) Co-144 1.17E + 00 +

(6) Other 1.30E + 00 r

2. Other: Dry Cornpressible Weste Nuchde Percent (1) Cs-1'37 7.16E + 01 (2) Co-60 2.46E + 01 (3) Ni-63 1.74E + 00 1 (4) Co-144 1.19E + 00 l (5) Other 8.70E - 01 1
3. Other: Dewetered Spent Resin

.. I Nuclide Percent (1) Co-60 6.73 E + 01 (2) Co-137 2.02E + 01 (3) Fe-55 4.36E + 00 (4) C-14 2.52 E + 00 (5) Mn-54 1.89E + 00 (6) Cs-134 1.24E + 00 (7) Other 2.49E + 00 1-l

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1 ATTACHMENT 6 Page 4 of 6

- Unit la X Unit 2 Reporting Period July . December 1998 SOLID WASTE AND 1RRADIATED FUEL SHIPMENTS A.3. SOLIO WASTE DISPOSITION:

1 Number of Shipmente Mode of Trenoportation Destination l

2 Truck Sernwell, SC -

11, Truck Chem-Nuclear Sernwell, SC 1 Truck GTS - Duratek Oak Ridge, TN 5 Truck Molten Metal Oak Ridge, TN B. IRRADIATED FUEL SHIPMENTS (DISPOSITION): There were no shipments.

Number of Shipmente Mode of Trenoportation Destination 0 N/A N/A i

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i ATTACHMENT 6 Page 5 Of 6  ;

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- Unit 1'_X_,_ Unit 2_ Reporting Period July December 1998 SOLID WASTE AND 1RRADIATED FUEL SHIPMENTS -

C. SOLID WASTE SHIPPED OFF-SITE TO VENDORS FOR PROCESSING AND SUBSEQUENT BURIAL Below is a summary of NMP-1 radweste buried by vendor facilities during July - December 1998. These totals were reported separately from *10CFR61 Solid Weste Shipped for Burial" since (a) waste classification and burialis 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 following data represents the actual shipments made from the off sire vendors of our radweste that was processed and commingled prior to burial.

C.1. TYPE OF WASTE Noncompacted trash, dry nord compressible waste and spent resins Burial Volume Activity Est. Total processed by vendor facilities prior to burial at Barnwell, SC. 8 (m ) (Ci) Error, %

2.02E + 01 9.99E + 01 5.00 + 01 l

C.2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent (1) Co-60 5.07E + 01 i

(2) Cs-137 3.77E + 01 l (3) Mn-54 7.36E + 00 1

(4) Fe-55 1.77E + 00 (5) Other 2.47E + 00 C.3. SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 1,7_ Truck Barnwell. SC 1

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ATTACHMENT 6 Page 6 of 6 Unit 1 X Unit 2_ Reporting Period July - December 1998 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS D. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIAL There were no shipments of sewage sludge with detectable quantities of plant related nuclides from NMP to the treatment facility during the reporting period, 1

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ATTACHMENT 7

. Unit 1 X Unit 2 Reporting Period July - December 1998 I

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 l' X Unit 2 Reporting Period July - December 1998

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM There were no changes to the Unit 1 Process Control Program during the reporting period.

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ATTACHMENT 9 Unit 1' X Unit 2 Reporting Period July December 1998

SUMMARY

OF INOPERABLE MONITORS There were no inoperable monitors for a period greater than 30 days during the reporting period.

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ATTACIIMENT 10 Page 1 of 4 1

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1998)

NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF TIIE PUBLIC DUE TO TIIEIR ACTIVITIES INSIDE TIIE SITE BOUNDARY JANUARY - DECEMBER 1998 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 located approximately one quarter mile west of NMPl. This facility 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.

The activity at the Energy Center that is used for the dose analysis is fishing near the shoreline adjacent to the NMP site. 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 and vent were evaluated for the inhalation pathway.

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 environmental Thermoluminescent Dosimeters (TLDs). 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, '

1998 were considered. Data from environmental TLDs 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 7.0E-03 mrem pe- hour for the period.

The average control TLD dose rate was 6.lE-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 2.8E-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 its proximity to the fishing area.

l A small portion may be due to the NMP2 facility. ,

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ATTACIIMENT 10 Page 2 of 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1998)

NINE MILE POINT NUCLEAR STATION UNIT 1 l DOSES TO MEMBERS OF TIIE PUBLIC DUE TO TIIEIR ACTIVITIES l INSIDE TIIE SITE BOUNDARY JANUARY - DECEMBER 1998 )

l The inhalation dose pathway is evaluated by utilizing the inhalation equation in the ODCM, as l adapted from Regulatory Guide 1.109. The equation basically gives a total inhalation dose l in mrem for the time period in question (April - December). The total dose equals the sum, j l for all applicable radionuclides, of the NMP1 stack and Emergency Condenser Vent release I concentrations, times the average NMP1 stack and Emergency Condenser Vent 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 j the fractional portion of the year in question. In order to be slightly conservative, no l radiological decay is assumed. l

? l The 1998 calculation utilized the following information:

l NMP1 Stack:

  • Unit 1 average stack flowrate = 1.11E+02 m'/sec
  • X/Q value = 8.9E-06 (annual NWN sector, historical average)

/,7nnal air intake = 8000 m' per year (adult)

  • ( Zonal psion 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 = 1.82E-01 pCi/m' Fe-55 = 6.68E-02 pCi/m'  !

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  • Sr-89 = 1.31E-01 pCi/m'  !

Sr-90 = 1.48E-02 pCi/m' i

  • H-3 = 1.16E+04 pCi/m'
  • I-131 = 1.42E-01 pCi/m' l  ;

I-133 = 1.17E+00 pCi/m'  ;

  • Cr-51 = 1.43E-02 pCi/m'
  • Co-58 = 4.83E-03 pCi/m'
  • Ce-141 = 3.96E-03 pCi/m' l

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l ATTACIIMENT 10 Page 3 of 4 l

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1998)

NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF TIIE PUBLIC DUE TO TIIEIR ACTIVITIES INSIDE TIIE SITE BOUNDARY JANUARY - DECEMBER 1998 Emergency Condenser Vent:

  • Average vent flowrate = 4.42E-04 m'/sec X/Q value = 6.63E-06 (conservative ground level value)

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 = 2.28E+01 pCi/m'

. Sr-90 = 2.70E+00 pCi/m'

  • - Co-60 = 3.43E+02 pCi/m'

=

Mn-54 = 4.24E+01 pCi/m'

. Fe-55 = 1.57E+02 pCi/m'

= H-3 = 4.67E+09 pCi/m' The inhalation dose to a member of the public from NMP1 as a result of activities inside the site boundary is 1.3E-03 mrem to the thyroid (maximum organ dose) and 1.lE-03 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 1998, 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 ODCM equation basically gives the total dose to the whole body and skin from the sum of i 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 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 l

ATTACIIMENT 10 Page 4 of 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1998)

NINE MILE POINT NUCi. EAR STATION UNIT 1 DOSES TO MEMPERS OF TIIE PUBLIC DUE TO TIIEIR ACTIVITIES INSIDE TIIE SITE BOUNDARY JANUARY - DECEMBER 1998 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.

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 l

=

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

=

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

  • Average Cs-137 concentration = 0.273 pCi/g The total whole body and skin dose from standing on the shoreline to fish is 4.3E-03 mrem whole body and 5.0E-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 l boundary from the direct radiation, inhalation and shoreline dose pathways is 2.8E-01 mrem j to the whole body and 1.3E-03 mrem to the maximum exposed internal organ (thyroid). The dose to the skin of an adult is 5.0E-03 mrem. These doses are generally a result of the operation of NMPl. However, a portion of these doses for the direct radiation pathway may be attributable to the NMP2 facility.

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ATTAClIMENT 11 Page 1 of 3 i SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1998)

NINE MILE POINT NUCLEAR STATION UNIT I DOSES TO MEMBERS OF TIIE PUBLIC DUE TO TIIEIR ACTIVITIES OUTSIDE TIIE SITE BOUNDARY JANUARY - DECEMBER 1998 Radiation doses to the likely most exposed member of the public outside of the site boundary are evaluated relative to 40CFR190 requirements. T'ie dose limits of 40CFR190 are 25 mrem (whole body or organ) per calendar year and 75 dem (thyroid) per calendar year. The intent of 40CFR190 also requires that the effluents of NMP1, as well as other nearby uranium fuel cycle facilities, be considered. In this case, ine 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 19 using calculated dose modeling based on the accepted methodologies of the facilities' Off-Site Dose Calculation Manuals (ODCMs) or may, in some cases, be calculated from the analysis results of actual environmental samples. Acceptable methods of calculating doset from environmental samples are also found in the facilities' ODCMs. 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 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 1998 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. Thi.< approach is utilized because the doses are very low and the computations are greatly simplified.

The following pathways are considered:

1. The inhalation dose is calculated at the critical residence because of the high occupancy factor. In order to be conservative, the maximum whole body and organ dose assumes no correction for residing inside a residence.

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ATTACIIMENT 11 Page 2 of 3 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1998)

NINE MILE POINT NUCLEAR STATION UNIT 1 i DOSES TO MEMBERS OF TIIE PUBLIC DUE TO TIIEIR ACTIVITIES l OUTSIDE TIIE SITE BOUNDARY JANUARY - DECEMBER 1998

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.
3. The maximum dose from the milk ingestion pathway as a result of consuming goat's milk is based on the same criteria es;ablished for item "2", above (ingestion of cow's milk).
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 I

from the critical vegetable garden location. As noted previously, the likely most l exposed member of the public is assumed to be located at the critical residence and is I 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 l plumes, plume submersion and from ground deposition. This total dose is measured by environmental TLDs. 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 1998, the closest '

residence and the critical downwind residence are at the same location.

The measured average dose for 1998 at the critical residence was 53.8 mrem. The average control dose was 54.3 mrem. The dose at the critical residence can be considered representative of the background dose since the control location dose was higher. Therefore, no dose was calculated and was assumed to be zero for this pathway.

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ATTACIIMENT 11 Page 3 of 3 l

l SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1998) l NINE MILE POINT NUCLEAR STATION UNIT 1 '

DOSES TO MEMBERS OF TIIE PUBLIC DUE TO TIIEIR ACTIVITIES OUTSIDE TIIE SITE BOUNDARY j .J ANUARY - DECEMBER 1998  ;

7. The dose, as a result of fish consumption, is considered as part of the aquatic pathway.

The dose for 1998 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.

The only plant-related radionuclide detected in fish umples was Cs-137. This nuclide l

was detected in one sample from a control locatian only and not detected in any fish 1 sampled from the site discharge location. Therefore, no dose was calculated and was assumed to be zero for this pathway.

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 l 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 are 2.2E-04 mrem whole body and 2.6E-04 mrem skin dose for the period.

In summary, the maximum dose to the likely most exposed member of the public is 9.2E-02 mrem to the thyroid (maximum organ dose) and 8.7E-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 2.2E-04 mrem whole body and 2.6E-04 mrem skin dose for the period. The direct radiation dose to the critical residence from the generating facilities 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 NMP1, NMP2 and  !

the JAF facilities. The maximum organ dose and whole body dose are below the 40CFR190 l l criteria of 25 mrem per calendar year to the maximum exposed organ or the whole body, and l below 75 mrem per calendar year to the thy  ;

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l ATTACHMENT 12 Update of Actual Data for the Second Quarter 1998 l

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I Page 1 of 1 Unit 1 X Unit 2 Reporting Period January - June 1998 UPDATE OF RELEASE AND DOSE DATA FOR GASEOUS (ELEVATED AND GROUND LEVEL) AND LIQUID EFFLUENTS Update of data using actual results from the off4ite vendors for Strontium, Tritium, and Iron-55 for the second quarter 1998.

GASEOUS LIQUID i 2d QUARTER 1998 2" QUARTER 1998 )

Nuclide' Activity (Cl) Activity (Ci)

I S r-89 6.22E - 06 No Releases i

Sr-90 " No Releases H-3 1.45E + 01 No Releases

. Fe-55 " l No Releases  ;

GASEOUS LIQUID l Particulates J 1, Particulates with half-lives Ci 9.02E - 05 No Releases l

>8 days j

2. Average release rate pCi/sec (gaseous) 1.21E - 05 No Releases (gaseous) or diluted pCi/mi (liquid) concentration (liquid) for reporting period Tritium 1. Total release Ci 1.45E + 01 No Releases
2. Average release rate for Ci/sec (gaseous) 1.85E + 00 No Releases i period (gaseous) or diluted Ci/ml (liquid) l concentration (liquids) for the reporting period Tritium, lodines, and Particulates GASEOUS LIQUID

{with half lives arenter than 8 days)'

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1. Percent of Quarterly Dose Limit 8  % 1.02E - 01 No Releases (Quarterly) (Quarterly
2. Percent of Annual Dose Limit to Date'  % 1.27E 01 No Releases (Annual) (Annual) l
3. Percent of Organ 1

-Gaseous Dose Rate Limit (Quarterly)  % 2.16E - 03 No Releases Liquid Dose Limit (Quarterly) (Quarterly)

(Quarterly & Annual) N_ /A No Releases (Annual) (Annual)

4. Percent of 10CFR20 Concentration Limit 8 (Liquid)  % NJJA No Roleases
5. Percent of Dissolved or Entrained Noble Gas (Liquid)  % NA No Heleases

'- Concentrations less than the lower limit of detection, as require 1 by Technical Specifications are indicated with a double asterisk.

8 The dose is to the whole body for liquid effluents and to the maximally exposed organ for gaseous effluents.

8- The percent of the 10CFR20 concentration limit is based on the average concentration during the quarter.

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