ML20138Q680

NMPNS - Unit 1 Semi-Annual Radioactive Effluent Rept for Jul-Dec 1996

ML20138Q680
Person / Time
Site:	Nine Mile Point
Issue date:	12/31/1996
From:	NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML20138Q674	List: ML20138Q671 ML20138Q680
References
NUDOCS 9703070182
Download: ML20138Q680 (27)

Text

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i NINE MILE POINT NUCLEAR STATION - UNIT 1 j SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i

JULY - DECEMBER 1996 l

4 N/AGARA MOHAWK POWER CORPORA TION 4

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9703070182 970229

! PDR ADOCK 05000220

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. NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1996 SUPPLEMENTAL INFORMATION j Facihty: Nine Mile Point Unit #1 Licensee: Niagara Mohawk Power Corporation j

1. TECHNICAL SPECIFICATION LIMITS 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 than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year to the I skin.

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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 to 5 milliroentgen for gamma radiation and less than or equal to 10 mrad 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 mrad for beta radiation.

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

1. The dose rate limit of Iodine-131, Iodine-133, Tritium and all radionuclides in particultte form with half-lives greater than eight days, released to the environs as part of the gaseous effluems from the site, shall be less than or equal to 1500 mrem / year to any organ.

2. The dose to a member of the public from Iodine-131, lodine-133, Tritium and all radionuclides in particulate form with half lives greater than eight days as part of gaseous effluents released 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 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 shall be 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 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 guarter to less than or equal to 1.5 mrem 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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, Page 2 of 2 jL 2. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACnVITY 4

1 Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents, a

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

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l B) IODINES lodine effluent activity is deternuned by ganuna spectroscopic analysis (at least v>Wy) of charcoal l cartridges sampled from an isolanetic stack sample stream.

J i C) PARTICULATES i

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

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For emergency condenser vent releases, effluent curie quantities are estimated based on the isotopic distribution in the Condensate Storage Tank water and the Emergency CA-r shell water. Actual isotopic concentrations are found via gamma spectroscopy. Initial release rates of Sr-89, Sr-90 and Fe-55 are estimanal 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 sema==8 rates out the vents.

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) LIQUID EFFLUENTS Isotopic contents ofliquid effluents are determined by 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 analysis 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 1 Summary Data Page 1 Of 2

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Unit 1 JL Unit 2_ Reporting Period Julv - December 1996  !

Uqidd Effluents:

10CFR20, Appendix B, T able 11, Column 2 Average MPC - uCi/ml (Qtr. 2) = ML4 Average MPC uCi/ml (Qtr. 4_) = MlA Avesese Energy (Fieelon and Activation gasee . Mov):

Otr,g_  : Ey = gl4 E, = g[A Qtr. L  : Ey = 2.47E - 01 E, = 3.17E - 01 US.id: There were no liquid releases during the reporting period, Number of batch releases  : 0 Total time period for batch releases (hrs)  : ML4 Maximum time period for a batch relonse (hrs)  : Mia Average time period for a batch release (hrs)  : M!A Minimum time period for a batch release (hrs)  : HLA, Total volume of water used to dilute the liquid effluent during release period (L)  : NL4 Total volume of water used to diluto j the liquid effluent during reporting  !

period (L)  : 2.72E + 11 1

Geseous (Emergency Condenser Vent): There were no releasea from the operation of the emergency condeneer vent. i Number of botch releases  : O i

Total time period for batch releases (hrs)  : E!A l Maximum time period for a batch release (hrs)  ; EL4 1 l

ELA Average time period for a batch relem.e (hrs)

Minimum time pericd for a batch release (hrs)  : E!A, Geseous (Primary Containment Purge):

Number of batch releases  : 2 Total time period for batch releases (hrs)  : 1.00E + 01 Maximum time period for a batch release (hrs)  : 5.00E + 00 Average time period for a batch release (hra)  : 5.00E + 00 Mmimum time period for a batch release (hrs)  : 5.00E + 00

V l ATTACHMENT 1

{ Summary Data Page 2 of 2 Unit 1_)L Unit 2 ,,,,_ Reporting Period Julv - December 1996 Abnormal Releases: There were no abnormal releases during tM reporting period.

A. Ugulds Number of releases 1 Total activity rolessed N/A Ci l B. Gaseous:

l Nurnber of rolessee 0 Total activity rolessed N/A Cl l

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1 ATTACHMENT 2 Unit 1 '2L Unit 2_ Reporting Period July - D: :-1:r 1996 i GAGEOUS EFFLUENTS SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL M 4_8 EST TOTAL QUARTER QUARTER ERROR. %

A. Fission & Activation asses'

1. Total release Ci **

. 8.74E - 01 5.00E + 01

2. Average release rate pCi/sec **

. 1.10E - 01 B. 10 dine,

1. Total iodine-131 Cl 1.21E - 04 1.34E - 04 3.00E + 01

2. Average release rate for period pCi/see 1.64E 06 199E - 06

C. Particulates '

1. Particulates with half-lives >8 days Ci 4.99E - 06 1.31 E + 03 3.00E + 01

2. Average release rate for period pCi/sec 6.36E - 06 1.66E - 04

3. Gross cipha radioactivity Ci 7.11E - 06 4.60E 06 2.50E + 01 D. 2

Tritium

1. Total release Ci 8 61E + 00 3.28E + 01 5.00E + 01

2. Average release rate for period pCi/sec 1.10E + 00 4.13E + 00 l E. Percent of Tech. Soec. Limits Fission and Activation Geses' Percent of Quarterly Gamma Air Dose  % 4.00E - 03 Limit (5 mR)

Percent of Quarterly Beta Air Dose Limit  % *' 1.63E - 03 (10 mrad)

Percent of Annual Gamma Air Dose Limit  % 4.64E - 04 2ASE-03 to Date (10 mR)

, Percent of Annual Beta Air Dose Limit to  % 1.86E - Qi 1.00E - 03 Date (20 mrad)

Percent of Whole Body Dose Rate Limit  % " 1.06E - 04 I (500 mrem /yr) l

% ** 3. /0E - 06 Percent of Skin Dose Rate Limit (3000 mrem /yr) 1 Tritium. lodines. and Particulates2 1 (with half-lives arester than 8 days)

Percent of Quarterly Dose Limit  % 9.06E - 02 6.97E - 01 (7.5 mrom) 4 Percent of Annual Dose Limit  % 1.61E 01 6.66E - 01

(15 mrom)

Percent of Organ Dose Rate Limit  % 1.82E - 03 1.192 0{

(1500 mrem /yr)

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

asterisk. A lower limit of detection of 1.COE-04 pCi/mi for required noble gaseu.1.00E-11 pCl/mi for required particulates,1.00E-12 pCi/mi for required lodines, and 1.00E-08 pCi/mi for Tritium, as required by Technical j Specifications, has been verified.

2 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, and actual numbers will be provided in the next Semi-Annual

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- Unit f,2L Unit 2 ,,,_ Reporting Period Julv December 1996 GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODE

• f 38 QUARTER Nuclides Rolessed QUARTER

1. <

Fission Geses' l Cl " '

Argon-41 l' Krypton-85 Ci , 1*

Krypton-85m Cl 1*

Krypton-87 Ci Ci " "

Krypton-88 Ci " "

Xenon-127 Ci " "

Xenon-133 Ci " "

Xenon-133m Xenon-135 Ci l' g,lg - 01 Ci " "

Xenon-135m Xenon-137 Ci ", l',

Xenon-138 Ci *1, ,,

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lodines' I lodine-131 Cl 1.21E 04 1.34E 04 '

lodine-133 Cl 5 84E - 04 1.56E 03 Ci a ..

lodine-135 3.

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Particulates1 ,2 Strontium-89 Ci WM" 6 62E - 04 Strontium-90 Ci 8.03E - 06 Ci ** ..

Cesium 134 Cesium-137 Ci 9.12E - 06 1.77E 06 Cobalt-60 Ci 2.96E - OS 1,06E - 04 Ci * ..

Cobalt-58 Manganese-54 Ci U U Barium-Lanthanum-140 Ci U U Antimony-125 Ci U U Niobium-95 Ci U U Cerium-141 Ci U U Cerium-144 Ci U U tron-59 Ci U U Cesium-136 Ci U U Chromium-51 Ci U U Ci U U Zinc-65 iron-55 Ci U 3.81E - 04 Ci " ..

Molybdenum 99 - -

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2 Ci 2.1 PE + 00 2.33E + 01 Tritium I Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.00E-04 pCi/ml for required noble gases,1.00E-11 pCi/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 verified.

2 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 and actual numbers will be included in the next Semi-Annual Report.

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ATTACHMENT 4 Unit 1 l_' Unit 2_ Reporting Period July - December 1996 GASEOUS EFFLUENTS OROUND LEVEL RELEASES There were no releasee via the emergency condeneer vent operation. Only leakage from the vente results in an assumed release based on the concentrations in the condensate storage tenke and condenser shell.

CONTINUOUS MODE BATCH MODE There were no batch releases during the reporting period. ,

b $ $ $

QUARTER QUARTER QUARTER QUARTER

1. F;ssion Geses' Ci " "

Argon-41 Ci " "

Krypton-85 Ci " "

Krypton-85m Krypton-87 Ci Krypton-88 Ci ",

Ci " "

Xenon-133  ;

Ci "

Xenon-133m Xenon-135 Ci ",

5.83E - 06 Ci ** "

Xenon 135m Ci " "

Xenon-137 Ci "

Xenon-138 Xenon-127 Ci " ",

2. lodines' Ci " **

lodine-131 Ci " 2,09E - 06 lodine 133 Ci " "

lodine-135 j

3. ParticuletesI l Ci ** 4.08E - 07 Strontium-89 Strontium-90 Ci ."

5.11E - 08

++

Cesium-134 Cl Cesium-137 Cl 2.88E - 08 2.25E - 08 Cobalt-60 Ci 1.65E - 06 2.86E 06 Ci " 3,99E - 07 Cobalt 58 Ci " 1.17E - 06 Manganese-54 Ci ++ ..

Barium-Lanthanum-140 Ci "~- ..

Antimony-125 Ci " ..

Niobium-95 Ci ** +=

Cerium-141 Ci " 3.84E - 08 Cerium-144 Ci " 8.87E - 07 fron-59 Ci " ..

Cesium-136 Chromium 51 Ci Ci b

5.99E - 07 Zino-65 Iron-55 Ci Ci 5

2.41E - 06 Molybdenum-99

4. Tritium

• Ci 6.42E + 00 9.53E + 00 I Concentrations less than the lower limit of detection of the counting sustem used are indicated with a double asterisk. A lower limit of detection of 1.00E-04 pCi/rni for required noble gases,1.00E-11 pCi/mi for required particulates,1.00E-12 pCi/ml for required lodines, and 1.00E-06 pCi/mi for Tritium, as required by Technical Specifications, has been verified.

• Tritium, Iron-55, and Strontium results for the fourth quarter were not receivu from the off-site vendor et the time of this report. These numbers include estimates, and actual numbers will be included in the next Semi-Annual Report. '

ATTACHMENT 5 Page 1 of 2 Il Unit 1 K_ Unit 2_ Reporting Period Juiv - December 1996 I

LIQUID EFFLUENTS SUMMATION OF ALL RELEASES i 1

f f EST. TOTAL ERROR, %

QUARTER QUARTER q

A. Finoion & Activation Products

1. Total release (not including Tritium, gases, alpha) Ci No Releases No Releasee 5.00E + 01 i

2. Average diluted concentration during reporting period pCl/mi No Releases No Releasee B. Tritium

1. Total release Ci No Releases No Relenees 5.00E + 01 I

2. Average diluted concentration during reporting period pCi/mi No Releasee No Releases C. Dissolved and Entrained Gases

1. Total release Ci No Releases No Releasee 5.00E + 01  ;

2. Average diluted concentration during reporting period pCi/ml No Releases No Releases l D. Gross Aloha Radioactivity

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1. Total release Ci No Releases No Releasee 5.00E + 01

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E. Volumes

1. Prior to dilution Liters No Releases No Releasee 5.00E + 01

2. Volume of dilution water used during release period Liters No Releases No Releases 5.00E + 01 J. Volume of dilution water available during reporting period Liters 1.39E + 11 1.33E + 11 5.00E + 01 F. Percent of Technical Specification Limits Percent of Quarterly Whole Body Dose Limit (1.5 mrom)  % 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 blesses No Releases Percent of Annual Organ Dose Limit to Date (10 mrem)  % No Releases No Releases Percent of 10CFR20 Concentration Limit  % No Releases No Releases l Percent of Dissolved or Entrained Noble Gas Limit  % ho Releases No Releases (2.00E-04 pCl/ml)

' On April 30,1996 the actual drain path for a hard piped steam trap drain, off of the steam supply to the nitrogen );

vaporizing unit, was found to be routed to the station's warm water discharge channel. Station drawings erroneously showed the drain path going to the station floor drain system. The drain path was subsequently changed to match the drawings so that now the system drains to a sump where it can be directed to radwaste. The work was completed on July 30,1996. The nitrogen vaporizing system was not operated subsequent to the April 30,1996 discovery until after the drain line was re-routed to radweste.

However, it is possible that during the operation of the nitrogen vaporizing system in the past, the steam drain trap contained contamination. The source of the possible contamination, mainly tritium,is from the condensate storage tank feedwater supply to the electric boiler which provides the steam to the nitrogen vaporizing unit. A similar configuration existed in 1988 where possible contamination, from the same steam supply to the vaporizing unit, drained to the discharge channel via the nitrogen vaporizing unit overflow line. A conservative analysis was performed in 1988 and the results showed that the activity concentration in the overflow was less than 1 total MPC fraction. Also, due to the limited run time of the nitrogen vaporizing unit, the calculated total activity discharged per drywell inertion was shown to be approximately 1/60th the activity discharged for a radweste discharge tank. Nine Mile Point Unit 1 is designed with a once through cooling system which typically discharges approximately 280,000 gpm of cooling water via the warm water discharge channel. This dilution water would reduce the total MPC fraction in the warm water discharge channel to approximately less than 3E-05 based on discharge rate equal to the boiler steam supply rating. This drain path was previously changed to direct the overflow to the plant processing systems.

The calculation performed in 1988 conservatively used the rated boiler output which bounds the worst case release rate for the April 30,1996 found configuration for the steam trap drain line. Additionally, a review of the recent (February 8,1995 -

September 8,1996) condensate storage tank water isotopic results reveals activity concentrations that are less than 1 total MPC fraction. Furthermore, the results of an envirorsnental monitoring and sampling program on the warm water discharge channel supports the conclusion of the calculation. There has been no anomalous activity detected as a result of this monitoring.

ATTACHMENT 5 Page 2 of 2 Unit 1,E_ Unit 2_ Reporting Period July December 1996 UQUID EFFLUENTS RELEASED BATCH MODE' Nuclideo Reler. sed QUARTER QUARTER Strontium-89 Ci No Releseos No Rolesses Strontium-90 Ci No blesses No Relemees Cesium-134 Ci No Releases NoRolesees Cesium-137 Ci No Releases No Roleseos lodine-131 Ci No Releases No Releases Cobalt-58 Ci No Roleseos No Roleseos Cobalt-60 Cl No Rolesses No Roleseos iron 59 Ci No Reiseses No Roleseos Zinc-65 Ci No Rolesses No Releases Mengenese-54 Ci No Roleseos No Releases Chromium-51 Ci No Roleseos No Roleseos Zirconium-Niobiurn-95 Ci No Releseos No Roleseos Molybdenum-99 Ci No Releases No Releases Technetium-99m Cl No Roleeses No Roleeses Berium-Lanthenum-140 Ci No Releases No Releases Cerium-141 Ci No Releseos No Releases Tungsten-187 Ci No Roleseos No Releases Arsenic-76 Cl No Releases No Releones lodine-133 Ci No Releases No neleases 1 tron-55 Ci No Releases No Releases  ;

Neptunium-239 Ci No Rolesses No Releases Preseodymium-144 Ci No Relesses No Releseos Indine-135 Ci No Releases No Roleesee Dissolved or Entrained Geses Ci No Relee.u No Releases Tritium Ci No Rolesses No Releasee

' No continuous mode release occurred during the report period.

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ATTACHMENT 6 PSee 1 of 6 2

i Unit 1_2L Unit 2 , Reporting Period July - December 1996

, SOUD WASTE AND IRRADIATED FUEL SHIPMENTS:

4 A.1 TYPE Volume Activity' (m') (Cl) i Class g 1

j A B C A B C 4 ,

1. Spent Rosin

• 3.41E + 00 3.41E + 00 g 4.69E + 01 f,Jp7E + 01 g Filter Sludge 9 9 9 9 2 9 l Concentrated Waste g g g g o o

Evaporator Bottoms 4

Total 9 9 9 9 9 g i 2. Dry Compressible j Waste, Dry Nore

' Compressible Waste (Contaminated 0 0 0 0 2 0 Equipment) - - - - -

3. Irradiated Components 1

9 9 9 9 9 9

} 4. Other; incinerator Ash 1,10E + 01 9 g 3.26E - 02 9 9 4

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

2 There were 5 Unit 1 steel encased high integrity containers of waste Class A bead resin placed in interim storage at Nine Mile Point during the reporting period. The total activity, decay corrected to January 1,1997, was 1.26E + 02 curies and the volume was 2.81E + 01m .

e a --.4 .* -.4.-.e_ eL-.X. . . ,a-J.J. J .J-- a+J w ,a AJ L2L--%,. -,. 4 a 1

t ATTACHMENT 6 Page 2 of 6 Unit 11 Unit 2_ Reporting Period Julv December 1999 SOUD WASTE AND IRRADIATED FUEL SHIPMENTS A.1 TYPE Solidification

, Container Pockene Aaent

1. Spent Resin (Dewatered) Polv H6c Twee A None UV MC Type A NstDE Filter Sludge ElA EL4 ElA Concentrated Waste JL4 N/A jfA 1

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2. Dry Compressible Waste, 3/,A, N/A J/_4 Dry Non-Compressible Waste (Contaminated Equipment)

3. Irradiated Components J!A EL4 3/A

4. Other: Incinerator Ash Metal Box $_IF*, N!!gg

• STP = Strong Tight Packege

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ATTACHMENT 6 PSge 3 of 6 Unit 1.K_ Unit 2 Heporting Period Juiv - December 1998 SOUD WASTE AND IMADIATED FUEL SHIPMENTS A.2 ESTIMATE OF MAJOR NUCLtDE COMPOSITION (BY TYPE OF WASTE)

e. Spent Rosine, Filter Studges, Concentrated Weste:

Nuclide Percent (1) Co-60 8.09E + 01 (2) Mn-54 7.65E + 00 (3) Ni-63 5.15E + 00 (4) Co-137 3.33E + 00 '

(5) Co-134 1.95E + 00 (6) Other 1.02E + 00

b. Dry Compreseible Weste, Dry Non-Compreesible Weste (Contaminated Equipment): There were no shipmente.

Nuclide Percent e

c. Irradiated Componente: There were no shiprnente.

Nuclide Percent

d. Other: Incinerator Ash Nuclide Percent (1) Co 60 7.18E + 01 (2) Cs-137 1.70E + 01 (3) Mn-54 7.76E + 00 f (4) Fe-55 2.19E + 00 (5) Other 1.25E + 00 P

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ATTACHMENT 6 Page 4 of 6

,' Unit 1 L Unit 2 Reporting Period Juiv - December 1996 SOUD WASTE AND 1RRADIATED FUEL SHIPMENTS I

A.3. SOLID WASTE DISPOSITION I I

Number of Shlomonte Mode of Transportati20 Destination ,

I 2 Ifrys#_ Barnwell. SC i

B. IRRAD!ATED FUEL SHIPMENTS (DISPOSITION): There were no shipments.

Number of Shlomonto Mode of Tranenortation Destina' ion e

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ATTACHMENT 6 PSee 5 of 6 )

1 Urut 1.2L Unit 2_ Reporting Period Julv - December 1996 j l

SOUD WASTE AND IRRADIATED FUEL Sl#PMENTS j

0. SOLID WASTE SHIPPED OFF-SITE TO VENDORS FOR PROCESSING AND SUBSEQUENT BURIAL '

Below is a summary of NMP-1 redwaste buried by vendor facilities during July - December 1996 These totals were reported separately from "10CFR61 Solid Weste 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 j

solid waste (as defined by 10CFR61) shipped off-site during the reporting period." The following data represents the actual shipments made from the off-site vendors of our redwaste (e.g., non-compacted trash and high conductivity waste water), that was processed and commingled prior to burial.

C.1. TYPE OF WASTE noncompacted trash and high conductivity waste water processed by vendor facilities prior to burial at Bernwell, SC Bu.1al Volume Activity Est. Total (m2L,,,. A Error. %

7.78E + 00 4.20E - 01 5 00 + 01 C.2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent j (1) Co-60 6.92E + 01 l

(2) Mn-54 1.78E + 01 1 (3) Fe-55 5.59E+00 (4) Co 137 3.09E + 00 (5) Ni-63 2.05E + 00 (6) Other 2.27E + 00  ;

C.3. SOLID WASTE DISPOSITION' Number of Shioments Mode of Transportation Destination i l

16 Truck Samwell. SC 1

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' NOTE: During the report period 4 shipnients of NMP-1 radwaste were sent to offsite processors. This material will be processed by the vendor and can be commingled with other licensees' waste for burial. However, the vendor performs an analysis of each shipment to determine the volume and activity buried under each utilities' license, and prepares a separate report f ar each sicensee. This information is provided in the Semi-Annual Radioactive Effluere Release Report for l the period in which the material is byried.

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t ATTACHMENT 6 Page 6 of 6 Unit 1 X Unit 2_ Reporting Period July - Dr ember 1996 l SOUD WA8TE AND 1RRADIATED FUEL SHIPMENTS D. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIAL I There were no shipments of newege aludge with detectable quantities of plant-related nuclides from NMP to the I treatment facility during the reporting period.

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I ATTACHMENT 7 i

I Unit 1 ]L, Unit 2 - Reporting Period Julv - December 1996

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL There were no changes to the Unit 1 Off-Site Dose Calculation Met 'el during the reporting period.

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l ATTACHMENT 8 Unit 1 L Unit 2 - Reporting Period July - December 1996

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 l l

Unit 1,X_ Unit 2_ Reporting Period July - December 1996 -

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SUMMARY

OF INOPERABLE MONITORS l l

. There were no inoperable monitore for a period greater then 30 days during the reporting period.

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, ATTACHMENT 10 Page 1 of 3 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1996)

, NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES 3

INSIDE THE SITE BOUNDARY JANUARY - DECEMBER 1996 i

Doses to members of the public (as defined by the Technical Specifications) from the operation of  !

4 the NMP1 facility as a result of activity inside the site boundery are based on activities at the Energy Center. 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 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 q lake trout populations. Dose pathways considered for this activity include direct radiation, i 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 of% a.

Releases from the NMP1 stack and emergency condenser vents were evaluated for the it: & .,un 1 pathway.

l The direct radiation pathway is evaluated in accordance with the methodology found in the Off-S!te 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 l April through December, environmental TLD data for the approximate period April 1 - December 31, 1996 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 l average fishing area TLD dose rate was 7.2E-03 mrem per hour for the period. The average control  ;

1 TLD dose rate was 6.1E-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 3.4E-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 amall portion may be due to the NMP2 facility.

4 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 concentrations,

' times the average NMP1 stack and emergency condenser vent flowrate, times the applicable five- i 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 conscrvative, no radiological decay is assumed.

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ATTACHMENT 10 Page 2 of 3 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1996) i NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY - DECEMBER 1996 The 1996 calculation utilized the following information:

NMP1 Stack:

- Unit 1 average stack flowrate = 1.08E+02 m'/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' per 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 = 9.87E - 02 pCi/m'

- Fe-55 = 1.34E - 01 pCi/m'

- Sr 89 - 2.54E - 01 pCi/m' i Sr-90 = 2.97E - 02 pCi/m' l 1

- H-3 - 1.07E + 04 pCi/m 3 l 131 = 1.49E - 03 pCi/m'  !

- 1 133 = 1.12E + 00 pCi/m' I

- Cs-137 - 1.13E - 02 pCi/m' ,

- Mn-54 = 2.68E - 03 poi /m' I Emergency Condenser Vent:

- Average Vent Flowrate = 4.42E - 04 m'/sec  !

- X/O value = 6.63E - 06 (conservative ground level value) j

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

- Annual air intake - 8000 m' per year (adult)

- Fractic,nal 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 = 3.87E + 01 pCi/m'

- Sr 4.87E + 00 pCi/m'

- Cs-137 = 5.72 + 00 pCi/m'

- Co-60 = 6.90E + 02 pCi/m'

- Mn-54 = 1.11 E + 02 pCi/m'

- Fe 2 29E + 02 pCi/m'

- H-3 - 2.09E + 09 pCi/m'

- Cr-51 - 5.70E + 00 pCi/m'

- l-133 - 2.71 E + 00 pCi/m'

- Co-58 = 3.80E + 01 pCi/m' Fe-59 - 8.43E + 01 pCi/m'

- Ce-144 = 3.63E + 00 pCi/m' The inhaiation dose to a member of the public from NMP-1 as a result of activities inside the site boundary 8.84E-04 mrem to the thyroid (maximum organ dose) and 7.43-04 mrem to the whole body.

,a ATTACHMENT 10 Page 3 of 3 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1996)

NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY - DECEMBER 1996 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 1996, 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.

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,yisids the whole body and skin dose by multiplying the radionuclide concentration adjusted for any bacxground 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.

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 /> l

- 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 = 0.291 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 6.6E-03 mrem whole body and 7.6E-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 3.5E-01 mrem to the whole body and 8.8E-04 mrem to the maximum exposed internal organ (thyroid). The dose to the skin of an adult is 7.6E-03 mrem. These doses are generally a result of the operation of NMP1.

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However, a portion of these doses for the direct radiation pathway may be attributable to the NMP2 '

facility, i

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ATTACHMENT 11 Page 1 of 3 {

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2 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1996) '

4 NINE MILE POINT NUCLEAR STATION UNIT 1 i

RADIATION DOSES TO THE LIKELY MOST EXPOSED MEMBER OF THE PUBLIC  !

OUTSIDE THE SITE SOUNDARY

- JANUARY - DECEMBER 1996 .

Radiation doses to the likely most exposed member of the public outside of the site boundary are evaluated relative to 40CFR190 requirements. The dcse limits of 40CFR190 are 25'mRom (whole body or organ) per calendar year and 75 mRom (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, 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 environmental samples are also found in the facilities' ODCM's. These methods are based on Regulatory Guide 1.109 methodology.

1 Dose calculations from actual environmental samples are, at times, difficult to perform for some l 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 1996 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 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.

2. The milk ingestion dose is calculated utilizing the maximum milk cow location. As noted previously, in order to be conservativa and for the sake of simplicity, the 96/ 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. I

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 of 3 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1996)

NINE MILE POINT NUCLEAR STATION UNIT 1 i

RADIATION DOSES YO THE LIKELY MOST EXPOSED MEMBER OF THE PUBLIC l - OUTSIDE THE SITE BOUNDARY l

5 JANUARY - DECEMBER 1996 1

l 4. The maximum dose associated from consuming meat is based on the critical meat animal. The i 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 2

from the critical garden location.

i l 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 TLD.

t 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 1996, the closest residance and the critical downwind residence are at the same location.

The measured average dose for 1996 at the critical residence was 56.8 mrem. The average control dose was 53.6 mrem. The average dose at the critical residence is slightly greater than the average control location 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 in dose rate can be demonstrated by observing the 1996 average dose for an environmental TLD located near the critical residence TLD, but approximately 700 feet closer to the canerating facilities. The annual average dose for this TLD location was 56.0 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 dosa for 1996 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 1996. Adjusting the average concentration of Cs-137 in indicator samples by subtracting the average concentration of Cs-137 in control samples resulted in a value of zero.

Therefore, no dose was calculated and was assumed to be zero for this pathway.

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I ATTACHMENT 11 Page 3 of 3 i

) SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1996 1 NINE MILE POINT NUCLEAR STATION UNIT 1

. RADIATION DOSES TO THE LIKELY MOST EXPOSED MEMBER OF THE PUBLIC OUTSIDE THE SITE BOUNDARY JANUARY - DECEMBER 1996

8. The shoreline sediment pathway is considered rela 6ve to recreational activities. The dose due to recreational activities from shoreline sediment is t'ased 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 radioriuclide concentration is adjusted for background sample results, as applicable. The total whole body and skin dose from shoreline recreational activities are 5.3E- '

04 mrem whole body and 6.1E-04 mrem skin dose for the period.

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9. In summary, the maximum dose to the most likely exposed member of the public is 8.24E-02 mrem to the thyroid (maximum organ dose) and 7.22E-02 mrem to the whole body. It should ,

3 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 i 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 a dose from shoreline recreational activities are 5.3E-04 mrem whole body and 6.1E-04 mrem i skin dose for the period. The direct radiation dose to the critical residence from the generating i j facilities was insignificant or zero. The dose to an individual as a result of fish consumption 1 L was also zero. These maximum total doses are a result of operations at the Nine Mile Point Unit i

! 1, Nine Mile Point Unit 2 and the James A. Fitzpatrick facilities. The maximum organ dose and d

whole body dose are below the 40CFR190 cnteria of 25 mrem per calendar year to the i maximum exposed organ or the whole body, and below 75 mrem per calendar year to the i thyroid, i

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ENCLOSURE 1 l 1

I Update of Actual Data for the Second Quarter 1996 i

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. r Page 1 cf 1 Unit 11 Unit 2.,_ Reporting Period hparv - June 1996

'UPDNE 0F RELEASE AND DOGE DATA FOR GASEOUS (ELEVATED AND GROUN3 LEVEL) AND UQUID Update of date using actual results from the off site vendors for Strontium Tritium, and iron-55 for the second guarter 1996.

GASEOUS UQUID 2 d,9,U, ARTER 1996 22!QUARTER 1996 1 Activity (Cil Nuclide Activity (cil St-89 2.30E - 05 No Releases Sr-90 2 NoRoleseos H3 9.27E + 00 No Roleseos Fe-55 2 No Rolesees j l

i GASEOUS UQUID Particulates

1. Particulates with Ci 8.23E - 05 N,]&

half-lives >8 days

2. Average release rate pCi/sec 1.05E - 05 jg!&

for period Tritium 1. Total release Ci 9.27E + 00  !!/,A,,

2. Average release rate pCi/sec (gaseous) 1.18E + 00 jgA for period pCi/ml (liquid) j i

Tritium. lodines. and G ASEOUS LIQUID Particulates (with half-lives areater than 8 ARysl 2

1. Percent of Quarterly  % 1.15E - 01 jgg Dose Limit (Quarterly) (Quarterly) 2  % Id5J,-jl tyg

2. Percent of Annual Dose Limit to Date (Annual) (Annual)

3. Percent of Organ  % 2.31E - 03 (UA

- Dose Rate Limit (Quarterly) (Quarterly)

(Gaseous)(Quarterly) IUS ff8

- Dose Limit (Liquid) (Annual) (Annual)

(Annual & Quarterly)

4. Percent of 10CFR20  % [gg gyg Concentration Limit (Liquid)

5. Percent of Dissolved  % Jgg !Ug or Entrained Noble Gas (Liquid)

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

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

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