ML20106G459

NMPNS Unit 1 Semi-Annual Radioactive Effluent Release Rept,Jul-Dec 1995

ML20106G459
Person / Time
Site:	Nine Mile Point
Issue date:	12/31/1995
From:	NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML17059B068	List: ML20106G456 ML20106G459
References
NUDOCS 9603050141
Download: ML20106G459 (30)

Text

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i NINE MILE POINT NUCLEAR STATION - UNIT 1 1

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1995 N/AGARA MOHAWK POWER CORPORATION 9603050141 960228 PDR ADOCK 05000220 R PDR

Pass 1 of 2 NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT )

JULY - DECEMBER 1995 SUPPLEMENTAL INFORMATION I fasuity: Nine Mile Point Unit #1 Licename: Niagara Mohawk Pbwer Corporation j l

1. TECHNICAL SPECIFICATION LIMITS I A) FISSION AND ACTIVATION GASES l

1. & dose rate limit of noble gases from the site to areas at and beyond the site be d.iy 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. N sir 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 nr. rad for beta radiation i and during any calender 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

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

2. b dose to a member of the public from Iodine-131, Iodine-133, Tritium and all radionuclides in r W'- 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 aball be limited during any calender 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 mrom to any organ.

D) LIQUID EFFLUENTS j 4

1. 'Ibe concentrahon of radioactive material released in liquid effluents to unrestricted areas shall be l limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for l radionuclides other than dissolved or entramed noble gases. For dissolved or entrained noble gases, the mtration shall be limited to 2E-04 microcuries/ml total activity. 3

2. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 1 to unrestricted areas shall be limited during any calendar quarter 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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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 detemuned 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 deternuned by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled from an isokmetic 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 c=ta-r vent releases, effluent curie quantities are estimated h==~1 on the isotopic distribution in the CA=*a Storage Tank water and the Emergency C-l=aar 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 steammg 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 of liquid 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 determmed by gamma spectroscopy and water content 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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4 ATTACHMENT 1 P ge 1 cf 2 Summary Data Unit 1,2L Unit 2_ Reporting Period July - December 1996

( Uguld Effluents:

i 10CFR20, Appendix B, Table 11, Column 2 l

Average MPC uCi/ml (Otr. 2) = Na Average MPC uCi/ml (Qtr. () = NJA Average Energy IFiaolon and Activation gases Mov):

i Otr. 3_  : Er = Ma E, = Ma Otr. d_  : Er - MIA E, = N!/A Uguid: There were no liquid releases during the reporting period.

Number of batch roleseos  : J 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)

• NL&

Minimum time period for a batch release thrs)  : N/A Total volume of water used to dilute the liquid effluent during release period (L)

• M/A Total volume of water used to dilute the liquid effluent during reporting period (L)  : 2.69E 411 Gaseous (Ernergency condenser Vent): There were no releases from the operation of the emergency condenser vent.

Number of batch releases -

0 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 rolesse (hrs) . N/A Mnimum time period for a batch rolesse (hrs)  : N/A Geseous (Primary Containment Purge):

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 i

e 1 ATTACHMENT 1 Pag) 2 cf 2  ;

Summary Data )

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Unit 1 J_ Unit 2_ Reporting Period July - December 1996 l Abnormal Releases: There were no abnormal reiseseo during the reporting period.

A. Ligulde Number of releasee 1 Total activity roleesed N/A Ci B. Gemoeus' Number of roleseos 1 Total activity roleseed R Ci i i

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. ATTACHMENT 2 Unit 1 l_ Unit 2__ Reporting Period July - December 1996

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GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES, ELEVATED AND OROUND LEVEL 1 4* EST. TOTAL QUARTER QUARTER ERROR. %

A. Fission & Activation cases' Ci ** ** 5.00E + 01

1. Total release ,

2. Average release rete pCi/sec " ",

B. iggirgg

1. Total iodine-131 Ci 6,73E- 06 1.40E - 04 3.00E + 01

2. Average rolesse rate for period pCi/sec ) 47E - 06 1.76E - 05 C. Particulates'

1. Particulates with half-lives >8 days Ci 169E- 04 3,18E - 03 3.00E + 01

2. Average rolesse rate for period pCi/sec 1.99E - 05 4.00E - 04

3. Grose alpha radioactivity Ci 4.21E - 05 4.37E- 05 2.50E + 01 D. Tritium'

1. Total release Ci 7,00E + 00 2.76E + 01 5.00E + 01

2. Average release rate for period pCi/sec 6 SSE-01 3.46E + 00 4

E. Percent of Tech. Spec. Umits Fission and Activation Games' Percent of Quarterly Gamma Air Dose  % ** **

Limit (5 mR)

Percent of Quarterly Beta Air Dose Limit  % " **

(10 mrad)

Percent of Annual Gamma Air Dose Limit  % 9 90E-03 9 90E-C3 to Date (10 mR)

Percent of Annual Beta Air Dose Limit to  % 6.90E- 03 6.90E- 03 Date (20 mrad)

Percent of Whole Body Dose Rete Limit  % " ",

(500 mrom/yr)

Percent of Skin Dose Rete Limit  % " "

(3000 mrom/yr)

Tritium. lodines. and Particulates' (with half-lives arenter than 8 deve)

Percent of Quarterly Dose Linit  % 8 92E-02 2.91E - 01 (7.5 mrom)

Percent of Annual Dose Limit  % 1.88E - 01 3.05E- 01 (15 mrom)

Percent of Organ Dose Rate Limit  % 1.77E - 03 5.78E- 03 (1500 mrom/yr) l l

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

' 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 Report.

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Unit 1 l_ Unit 2__ Reporting Period July Dooember 1995 )

l GASEOUS EFFLUENTS . ELEVATED RELEASE CONTINUOUS MODES J 1 1 Nuolides 14eieased QUARTER QUARTER 1.

l I Fission Geses' Argon-41 Ci l " "

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

Xenon-127 Cl _

Ci ". "

Xenon-133 Xenon-133m Cl ,,.

i Xenon-135 Ci l Xenon 135m Ci .

Xenon-137 Ci ,.

Xenon-138 Cl

2. l 126218' i lodine-131 Ci 6 73E-05 1.40E-04 i 9.26E-04 l lodine-133 Ci 5.10E-04 Ci **

• lodine-135 3.

Particulatest .:

Strontium-89 Ci 2 50E-05 5.53E-04 l Strontium-90 Ci " 6.81E-05 '

Ci " "

Cesium-134 Cosium-137 Ci 8.07E - 06 8.19E - 06 Cobalt-60 Ci 8.45E - 05 2.91 E - 04 Cl " 2.32E - 04 Cobalt-58 ,

4,71 E - 05 "

Manganese-54 Ci BariurwLanthanum-140 Ci " U 1 l

Antimony-125 Ci )

Niobium-95 Ci U U Ci ** ..

Coriurm141 l

Cerium-144 Ci U U iron-59 Ci U U Cl .. ..

Cesium 136 Chromium-51 Cl " 1.76E - 03 Ci ** ..

Zino-65 Ci " 2,60E - 04 iron-55 Ci MolybdenurwS9 4.

Tritium' Ci 1.44E + 00 2.19E + 01 l

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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 limit of detection of 1.00E-04 pCi/rni for required noble gases,1.00E-11 pCi/mi for reovired  !

particulates,1.00E-12 pCi/rnl for required lodines, and 1.00E-06 pCi/ml for Tritium, 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 estimates and actual numbers will be included in the next Semi-Annual Report.

8 No batch mode release occurred during the reporting period.

ATTACHMENT 4

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Unit 1 J._ Unit 2_ Reporting Period July - December 1995 GASEOUS EFFLUENTS . GROUND LEVEL RELEASES There were no rolessee via the emergency condeneer vent operation. Only leakege from the vente reeutto in en assumed release based on the conoontratione in the condeneste storage tanks and condenser shell.

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

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QUARTER QUARTER QUARTER QUARTER

1. Fission Gasee' Arpon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Xenon-127 Ci

2. Lod!n,gg i

Ci a "

lodine-131 lodine-133 Ci lodine 135 Ci 3 3

3. Particulatest .:

Strontium-89 Ci " 4.28E - 07 Strontium-90 Ci 2.01 E - 09 5,37E-08 Ci " "

Cesium-134 Cesium 137 Ci 1.29E - 08 5.19E - 08 Cobalt-60 Ci 1.90E - 06 1.74E - 06 Ci ++ ++

Cobalt-58 Manganese-54 Ci 4.71 E - 09 "

Barium-Lanthanum-140 Ci ++ U Antimony-125 Ci " ++

Ci ++ ++

Niobium-95 Cerium-141 Ci a ++

Ci " ++

Cerium-144 1ron-59 Ci U U Cesium 136 Ci U U Ci ++ ++

Chromium-51 Zinc-65 Ci U U Iron-55 Molybdenum-99 Ci Ci b++

1.15E - 06

++

4. Tritium' Ci 5.62E + 00 5.62E + 00

' Concentrations less than the lower limit of detection of the counting system used are indicated with a double esterisk. 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/rni for required lodines, and 1.00E-06 pCi/mi for Tritium, 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 estimates, and actual numbers will be included in the next Semi Annual Report.

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ATTACHMENT 5 Page 1 Of 2 l

l Unit 11 Unit 2_ Reporting Period July December 1996 l UQUID EFFLUENTS - SUMMATION OF ALL RELEASES l l

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1 4* EST. TOTAL QUARTER QUARTER ERROR % i A. Fission & Activation Products I

1. Total release (not including Tritium, gases, elpha) Ci No Releasee No hiseses 5.00E + 01 l l 2. Average diluted concentration during reporting period pCi/mi No Reiseees No Reissees  !

B. Tritium

1. Total reloose Ci No Reiseees No Reisenes 5.00E + 01

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

1. Total reisese Ci No Releasee No blessee 5.00E + 01

2. Average diluted concentration during reporting period pCi/mi No blessee No Relooses D. Gross Alphe Radiometivity

1. Total release Ci No blesses No Releases 5.00E + 01 E. Volumes

1. Prior to dilution Uters No hionees No Robesee 5.00E + 01

2. Volume of dilution water used during release period Uters No Releases No Releasee 5.00E + 01

3. Volume of dilution water available during reporting period Uters 1.37E + 11 1.32E + 11 5.00E + 01 F. Percent of Technical Specification Limits Percent of Quarterfy Whole Body Dose Limit (1.5 mrom)  % No Releasee No Reiseees Percent of Quarterly Organ Dose Limit (5 mrom)  % No Reneeses No Releases Percent of Annual Whole Body Dose Limit to Date (3 mrom)  % No Reisesee No Releases Percent of Annual Organ Dose Limit to Date (10 mrom)  % No Releases No blesses Percent of 10CFR20 Concentration Limit  % No Releases No Releases Percent of Dissolved or Entrained Noble Gas Limit  % No Releases No Reksees (2.00E-04 pCi/ml)

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ATTACHMENT 5 Page 2 of 2 Unit 12_ Unit 2_ Reporting Period July - December 1996 UQUID EFFLUENTS RELEASED BATCH MODE' 3d 4*

Nuohdas Released QUARTER QUARTER Strontiurn-89 Cl No Releasee No Releases Strontium-90 Cl No Roleeses No Roleseos Coelum-134 Cl No Releases No Releasee Cesium-137 Ci No Releasee No Releases lodine-131 Cl No Releases No Roleseos Cobalt 58 Ci No Releasee No Releases Cobalt-60 Cl No Releases No Releases iron-59 Cl No Reloemee No Releases i Zino-65 Ci No bleseos No Reisesee Manganese-54 Ci No Roleseos No Releases Chromium-51 Ci No Robesee No Roleeses I

Zirconium-Niobium 95 Ci No Releasee No Releases )

Molybdenurn-99 Ci No Releases No Releases  !

Technetium 99m Ci No Rolesses No Releases  ;

Berium-Lanthanum-140 Ci No Rolessee No Releases  !

Cerium-141 Ci No Releases No blesses Tungsten-187 Ci No blesses No Releases l Ateenic-76 Ci No Releases No Releeses i lodine-133 Cl No Releases No Releases iron 55 Ci No Heleseos No Releasee Neptunium-239 Ci No Releases No Releases )

Preseodymium-144 Ci No Releasee No Releases lodine-135 Ci No Roleesee No Reneeses Dissolved or Entreined Geses Ci No Reiseees No blessee Tritium Ci No Releases No Releasee

'No continuous modo release occurred during the report period.

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Unit 11 Unit 2 .,,,, Reporting Period Juhr - December 1995 SOLD WASTE AND IRRADIATED FUEL SHIPMENTS: There were no shipmente sent for burial.

A.1 TYPE y.ghgng Ag,tlygg' l (m') (Cl)

G!ans Glata A B C A B C l

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1. Spent Roein'

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Fdter Siudge 9 9 9 2 9 9 Coneontrated Weste 2 2 g 2 9 2  :

Evaporator Bottoms i Total 9 9 9 9 9 9 l

2. Dry Compressible Weste, Dry Non-  ;

Compreeeible Weste j (Contaminated 2 2 2 2 2 2 i Equipment) i

3. Irradiated Componente 9 9 9 9 9 2

4. other*

9 9 9 9 9 2 )

The estimated total error is 5.00E + 01 %.

s One Unit 1 eteel oncesed high integrity container of weste Cless A bead resin was placed in interim storage et Nine Mile Point during the reporting period. The total activity, decoy corrected to January 1,1996, was 4.30E + 00 curies and the volume was 5.69E + 00m'.

• One Unit 1 steel encased high integrity container of weste Class A bead resin and weste Class B filter sludge was placed in interim storage et Nine Mile Point during the reporting period. The total activity, decoy corrected to January 1,1996, wee 5.20E +01 curies and the volume was 5.69E + 00m'.

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ATTACHMENT 6 Page 2 of 6  !

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{ Unit 1 E_ Unit 2_ Reporting Period Julv December 1996

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Soun WASTE AND IRRADIATED FUEL SHIPMENTS I A.1 TYPE Solidification container Pockene Anent ,

1. Spent Reein NIA N/A, Ela, I

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Filter Sludge E LA El&. El&_ j Concentrated Weste N/A ELA Ele _

2. Dry Compressible Weste, N/A EfA Ela Dry Non-Compressible Weste (Contaminated Equipment)

3. Irrediated Componente N/A N/A Ele _

4. Other N/A E!A B l

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ATTACHMENT 6 Page 3 of 6 Unit 1 L Unit 2_ Reporting Period Julv - December 1996 SOUD WASTE AND MRADIATED FUEL SHIPMENTS A.2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)

e. Spent Rosine. Fiher Studges. Concentrated Weste: There were no shipments Nuclide EgLennt j l

b. Dry C _ ,

" '- Weste, Dry Non-C: ., ' Weste (Conteminated Equipment): There were no shipments.

Nuclido Percent I

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c. Irrediated Components: There were no shipments.

Nuclide Percent

d. Other: There were no shipments.

Nuclide Percent I

ATTACHMENT 6 Page 4 of 6 Unit 1 J_ Unit 2_ Reportino Period Juiv - December 1996 i SOUD WASTE AND IRRADIATED FUEL SHIPMENTS A.3. SOLID WASTE DISPOSITION There were no shipmente Number of Shismente Mode of Transportation Doetination ,

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l B. IRRADIATED FUEL SHIPMENTS (DISPOSITION): There were no shipments. l Number of Shismente Mode of Transportation Doetination j I

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1 ATTACHMENT 6 Page 5 of 6  ;

Unit 11._ Unit 2,,_ Reporting Period Julv - Desernber 1995 l SOUD WASTE AND IRRADIATED FUEL SHIPMENTS C. SOLID WASTE SHIPPED OFF-SITE TO VENDORS FOR PROCESSING AND SUBSEQUENT BURIAL Below is e summary of NMP-1 redweste buried by vendor facilities (i.e., SCIENTIFIC ECOLOGY GROUP) during Juhr - Deemmber 1995 These totals were reported separately from *10CFR61 Solid Weste Stupped for Burial

• since (a) weste classification and buriel wee perforrned by the vendors, and (b) Technical Specification 6.9.1 requires reporting of "information for each class of solid weste (as defined by 10CFR61) ehipped off-site during the reporting period." The following data represente the octual shipments made from the off site vendors of our non-compacted commingled trash that wee processed prior to buriel.

C.1. TYPE OF WASTE - noncompacted commingled trosh shipped to Oak Ridge, TN for procoesing prior to buriel at Burial Volume Activity Est. Total Bomwell, SC (m8) A Error. %

1.51E + 01 4.42E- 01 5.00 + 01 C.2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuohde f.sr,s3D1 (1) Co-60 5.33E + 01 (2) Mn 54 1.81 E + 01 (3) Cr-51 1.09E + 01 4 1

(4) Co-137 1.07E + 01 (5) Fe-55 2.04E + 00 (6) Fe-59 1.89E + 00 (7) Co 58 1.87E + 00 (8) Other 1.20E + 00 C.3. SOLID WASTE DISPOSITION' Number of Shiomente Mode of Transportation Destination 39,. latglL BernweL SC

• Four shipmente to offehe processore were made during the report period.

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ATTACHMENT 6 Page 6 of 6 J

Unit 1 X Unit 2 __ Reporting Period July - December 1996 SOUD WASTE AND 1RRADIATED FUEL SHIPMENTS D. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIAL i

, There were no shipmente of eewege eludge with detectable quantities of plant <eleted nuolideo from NMP to the treatment fooli6ty during the reporting period, a

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ATTACHMENT 7 Unit 1,X._ Unit 2__ Reporting Period July December 1995  ;

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SUMMARY

OF CHANGES TO TM OFF SITE DOSE CALCULATION MANUAL The Unit 1 off Site Dose calculation Manuel was changed during the reporting period to include e new garden location and to incorporate two editorial changes. A copy of revision 16 is attached and below is e summary of the changes presented to and approved by the Station Operation Review Committee in December 1995. The summary also includes the justification for the changes

1. A change to Table 5.1, "Nine Mile Point Nuclear Station Radiological Environmental Monitoring Program Sampling Locations" and to Figure 5.12, "Nine Mile Point Off Site Map", was made to include a new garden location. This change le in accordance with the Unit 1 Technical Specification requirements of Section 3.6.20.

The change is required due to the identification of a new garden locetion with a higher D/O during the 1995 annual garden census. This D/O value is less then the D/O values found in Table 31, " Critical Receptor Dispersion Parameters for Ground Level and Elevated Reiseees", of the Unit 1 Off-Site Does Calculation Manual.

Therefore, this change does not reduce the accuracy or reliability of the does calculations or set-point determinations in accordance with Technical Specifications.

2. - An editorial change to Section 3.1.1 was made to revise the responsible department for implementing setpoint changes from 'C&RM' to ' Chemistry' eupervision. The change corrects department nomenclature only and does not reflect any change in actual responsible organization. Therefore, this change does not reduce the accuracy or reliability of the dose ceiculations or set-point determinations in accordance with Technical Specifications.

3. An editorial change to Section 3.2.1.1 was made which revises the unite for the constant accounting for the 8

gamme air does rate from immersion in the semi-infinite cloud (M,), from 'mrom/yr por pCi/m ' to 'mredlyr per pCi/m. The correct units are applied for M,in the belance of the off-Site Dose Calculation Manuel and are 4:onsistent with the units in the Unit 1 Technical Specifications. Therefore, this change does not reduce the accuracy or reliability of the dose calculations or eet-point determinations in accordance with Technical Specifications.

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ATTACHMENT 8 Unit 1 X_ Unit 2__ Reporting Period Juiv 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 ,

Unit 1 L Unit 2,_ Reporting Period July - December 1995

SUMMARY

OF INOPERABLE MONITORS The Uquid Redweste Effluent une Gross Radioactivity Monitors were declared inoperable during the reporting period and were recorded in the Equipment Status Log because the instrument channel celibrations were not performed. The Technical SWietions do riot require these monitors to be operable for the specific system configuration (i.e., blank f6enge it'suA l LA 4N discharge line), and, therefore, the channel calibrations were not performed. There were no liquid redweer c/4,oAg a via this pathway during the reporting period. Any future liquid redweste discharges via this pathway will be vunducted in accordance with the requirements established in the Technical Specifications. This ooeneno will not be reported in future Semi-Annual Radioactive Effluent Release Reports unless other causes of ,

inoperability are identified.

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i ATTACHMENT 10 Page 1 of 3 SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1995)

NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES l- INSIDE THE SITE BOUNDARY l JANUARY DECEMBER 1995 l 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 educational information, summer j picnicking activities and fishing. Any possible doses received by a member of the public by utilizing l the private road that transverses the east and west site boundaries are not considered here since it ]

l takes a matter of minutes to travel the distance.

! The activity at the Energy Center that is used for the dose analysis is fiching 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, j 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 j 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.

l 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 j 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 l' 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,

! 1995 were considered. Data from two environmental TLD's from the approximate area where the I - fishing occurs were compared to control environmental TLD locations for the same time period.

The average fishing area TLD dose rate was 7.6E-03 mrem per hour for the period. The average l control TLD dose rate was 6.3E-03 mrem per hour for the period (approximate second, third and j fourth calendar quarters of the year). The average increase in dose as a result of fishing in this 4 area at a conservative frequency of eight hours per week for thirty-nine weeks is 4.1E-01 mrem I

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 i i NMP2 facility. j

1 i The inhalation dose pathway is evaluated by utilizing the inhalation equations in the ODCM, as l adapted from the Regulatory Guide 1.109. The equation basically gives a total inhalation dose in  ;

mRom 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- ,

year average calculated X/Q, times the inhalation dose factors from Regulatory Guide 1.109, Table i 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 (1995)

NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY - DECEMBER 1995 The 1995 calculation utilized the following information:

i

' NMP1 Stock:

- Unit 1 average stack flowrote = 1.10E+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 = 1.86E-01 pCi/m' ,

- Fe-55 = 1.11E-01 pCi/m' l

- St-89 = 2.33E-01 pCi/m'

- Sr 90 = 2.64E-02 pCi/m'

- H-3 = 9.49E + 03 pCi/m'

- 1 131 - 9.30E-02 pCi/m'

- 1-133 = 8.97E-01 pCi/m'

- Cs-137 = 7.31E-03 pCi/m' Co-58 = 9.00E-02 pCi/m'

- Mn-54 = 1.79E-02 pCl/m'

- Cr 51 = 6.83E-01 pCi/m'

. Emergency Condenser Vent:

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

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

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

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

- Fractional portbn 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 = 4.15E + 01 pCi/m'

- Sr 90 - 5.29E + 00 pCi/m'

- Cs 137 - 6.16E + 00 pCi/m' Co-60 = 6.00E + 02 pCi/m' )

- Mn-54 - 3.41E + 00 pCi/m' ,

- Fe-55 - 1.09E + 02 pCi/m'  !

- H3 = 1.53E + 09 pCi/m' The inhalation dose to a member of the public from NMP-1 as a result of activities inside the site boundary is 7.24E-04 mrem to the thyroid (maximum organ dose) and 6.24E-04 mRom 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 1995, it was noted that fishing was performed l 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.

4.

ATTACHMENT 10 Page 3 of 3 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1995)

NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEM8ERS OF THE PUBLIC DUE TO THElR ACTIVITIES INSIDE THE SITE BOUNDARY i l

JANUARY DECEMBER 1995 )

i 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, I 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 1 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 j 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. ,

1 The calculation utilized the following information:

Usan factor = 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> i

- 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 = 0.306 pCi/g The total whole body and skin dose from standing on the shoreline to fish is 4.8E-03 mrem whole body and 5.6E-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 4.2E-01 mrem to the whole body and 7.2E-04 mrem to the maximum exposed internal organ (thyroid). The dose to the skin of an adult is 5.6E-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 attributeble to the NMP2 facility.

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ATTACHMENT 11 Page 1 of 3 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1995)

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 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 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 effiucnts 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.

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 ars not based on actual environmental data for 1995 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 j approach is utilized because the doses are very low and the computations are greatly simplified. j 1

The following pathways are considered. l l

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 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 established for item *2", above (ingestion of cow's milk).

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I ATTACHMENT 11 Page 2 of 3 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1995)

NINE MILE POINT NUCLEAR STATION UNIT 1 RADIATION DOSE.S TO THE LIKELY MOST EXPOSED MEMBER OF THE PUBLIC OUTSIDE THE SITE BOUNDARY JANUARY DECEMBER 1995

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.

i

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 l from the critical garden location.

I

6. The dose, as a result of direct gamma radiation from the site, encompasses doses from direct i I

" 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 l both direct radiation from the generating facilities and gaseous plumes as determined by the local meteorology. During 1995, the closest residence and the critical downwind residence are at the same location.

The measured average dose for 1995 at the critical residence was 54.2 mrem. The average control dose was 53.2 mrem. The average dose at the critical residence is slightly greater than 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 in dose rate can be demonstrated by observing the 1995 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 53.9 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 1995 is calculated from actual results of the analysis of environmental fish sampies.

For the sake of being conservative, the average plant-related radionuclide concentra8cus were j

~

utilized from fish samples taken near the site discharge points. Only Cs-137 was detected during 1995. 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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ATTACHMENT 11 Page 3 of 3 SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1995 NINE MILE POINT NUCLEAR STATION UNIT 1

j. RADIATION DOSES TO THE LIKELY MOST EXPOSED MEMBER OF THE PUBLIC OUTSIDE THE SITE BOUNDARY JANUARY - DECEMBER 1995

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 J 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 5.3E-04 mRom whole body and 6.2E-04 mrem skin dose for the period.

9. In summary, the maximum dose to the most likely exposed member of the public is 7.05E-02 mRom to the thyroid (maximum organ dose) and 7.79E-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 5.3E-04 mRom whole body and 6.2E-04 mRom 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 Nine Mile Point Unit 1, Nine Mile Point Unit 2 and the James A. Fitzpatrick facilities. The

~eximum organ dose and whole body dose are below the 40CFR190 criteria of 25 mrem per undar year to the maximum exposed organ or the whole body, and below 75 mRom per calendar year to the thyroid.

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ENCLOSURE 1 Update of Actual Data for the Second Quarter 1995 and Corrections to the Gaseous Effluents Data for the Period January-June 1995

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

Page 1 cf 4

, Unit 1 2L Unit 2_ Reporting Period January - June 1996 i l UPDATE OF RELEASE AND DOSE DATA FOR GASEOUS (ELEVATED AND GROUND LEVEL) AND UQUID EFFLUENTS Update of date using estuel resuhe from the off e6ee venders for Strontium, Tritium, and iron-55 for the neoend guerter 1996.

GASEOUS UQUID l 2" QUARTER 1996 2** QUARTER 1996 NHghdi' At tivity (Ci) Activity (Cil St-89 2,30E- 06 No Rolesses Sr-90 " No Reneeses H3 6 02E + 00 No Reneeses Fe-55 2 96E-06 No Rennenes GASEOUS UQUID I Particulates I

1. Particulates with Cl 1,66E- 04 Hla I half-lives >8 days I

2. Average roleses rate pCi/sec 2.11E - 06 N/A for period

1. Totel release Cl 6 02E + 00 N/A

2. Average reloose rate pCi/sec (gessous) 7.66E-01 N/A Innum for p.riod pCi/ml tisquidi Tritium. lodines, and GASEOUS MQMQ,  !

Particulates (with half-l lives areeter then 8 )

AAXII

1. Percent of  % S 86E-02 N/A Quarterty: Dose (Quarterly) (Quarterly)

Umit 1.43E- 01 N/A

2. Percent of Annual *  % (Annuel) (Annuel)

Does Umit to Date 1.78E- 03 !E&

3. Percent of orgen  % (Quarterly) (Quarterly)

. Dose Rete Umit N!A $!A (Geseous)(Quarterty) (Annual) (Annuel)

Dose Umit (Uguid)

(Annuel & Quarterly)

4. Percent of 10CFR20  % M!A N!&

Concentration Umst (Uguid)

5. Percent of Dissolved ,N,[la N/A or Entrained Noble  %

Gas (Liquid) 1 Concentrations lost then the lower limit of detection, as required by Technical Specifications are indicated with a double esterisk, a The dose is to the maximally exposed organ for gaseous effluente.

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e Peoe 2 sf 4 ATTACHMENT 2' Unit 1.K_ Unit 2 _ Reporting Period Januerv -June 1995 UPDATE OF GASEOUS EFFLUENTS SUMMATION OF ALL nELEASES, ELEVATED AND OnOUND LEVEL i

f f ESTmTOTAL ouARus ouAmTEn Ennon.s A. Fission & Activation nasee'

1. Total release Cl 1.3eE + 01 **

5.00E + 01 l

2. Average release rate pCi/sec 1.77E + 00 ,."

B. leshneE

1. Totel iodine-131 Ci 5,59E- 05 3,43E- g 3.00E + 01

2. Averece release rete for period pCi/sec 7.19E - 08 4 36E-06 C. Particulates t

1. Particulates with half-lives >8 days Cl E.31E- 04 1.66E - 04 3.00E + 01 J

2. Average reisese rete for period pCi/sec 6.83E- 95 2.11 E - 06

3. Gross eiphe radioactivity Ci 3.61E - 06 5,47E- 05 2.50E + 01 D. Insigm

1. Total release C1 3 63E + 00 6.02E + 00 5.00E + 01

2. Average reloose rete for period pCl/sec 4.67E - 01 7.66E - 01 E. Percent of Tech. Sooe. Umits Fission and Activation Gaeos' j Percent of Quarterly Gemme Air Dose  % 1.90E- 02

j Umit (5 mR) i Percent of Quarterly Bote Air Does umit  % 1.38E - 02 "

(10 mrads)

Percent of Annual Gemme Air Dose Umit  % 9 90E-03 9.90E- 03 )

to Date (10 mR)

Percent of Annual Beta Air Dose Umit to  % 6 90E-03 6.90E- 03 Date (20 mrads)

Percent of Whole Body Does Rate Limit  % 6.10E- 04 *'

(500 mrom/yr)

Percent of Skin Dose Rate Umit  % 1.89E - 04 "

(3000 mrom/yr)

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

Percent of Quarterly Dose Limit  % 1.97E - 01 8 86E-02 (7.5 mrom)

Percent of Annual Dose Umit  % 9 92E-02 1.43E- 01 (15 mrom)

Percent of Organ Dose Rate Umit  % 4.00E - 03 1,70E - 03 11500 mrom/yr)

' This Attachment 2 supersedes the information provided in the January - June 1995 Semi- Annual Radioactive l Effluent Release Report for Nine Mile Point Nuclear Station Unit 1. The following 1st Quarter categories have been updated: A.1, A.2, C.2, D.1, D.2, and E,

• Fission and Activation Geses". The following 2nd Quarter categories have been updated and include octual off-site vendor results where appropriate: B.1, B.2, C.1, C.2, D.1, D.2, and E.

2 Concentrations less than the lower limit of detection of the counting system used are indicated with a double estoriek. A lower limit of detection of 1.00E-04 pCi/ml 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/ml for Tritium, as required by Technical Specifications, has been verified.

P*ge 3 a f 4 AWACHMENT 3' Unit 1.2L, Unit 2_ Reportmg Period January - June 1996 I

UPDATE OF GASEOUS EFFLUENTS ELEVATED RELEASE i l

CONTINUOUS MODE 8 L f NuoEdes Released QUARTER QUARTER 1.

Fission Gasosa Argorw41 Cl " "

Kryptorv85 Ci " "

KryptorwS5m Ci 1.87E - 01 " I Krypton-87 Ci " ", 1 Krypton-SS Ci ' "

Xenore127 Ci " "

J Xenore133 Ci 1.11E + 01 Xenon-133m Ci " "

l Xenon-135 C1 2.48E + 00 "

1 Xenore135m Ci " ", 1 Xenore137 Ci " " I Xenore138 Ci " "

2.

lad! NEE' lodine-131 Ci 5.59E-06 3.43E-06 lodine-133 Ci 1.05E-04 6,94E-04 lodine-135 Ci **

3.

Particulates StrontiurwS9 Ci 5.25E-06 2,30E-06 Strontiurw90 Ci " "

Cosiurre134 Ci ** "

Cosiunv137 Ci 2,56E- 06 4.79E -06 Cobalt-60 Ci 3.95E - 04 1,09E - 04 Cobalt-58 Ci 2.23E- 06 "

Manganese-54 Ci 6.24E - 06 "

Barium-Lenthenurre140 Antimony-125 Ci Ci n

a Niobium 95 Ci a "

Cerium 141 Ci a **

Conunw144 Ci ** **

iron-59 Ci " "

Cesium-136 Ci a "

Chromium-51 Ci " "

Zino-65 Cl a "

trorwSS Cl 1.95E - 06 2 65E-06 Molybdenum 99 Ci **

4.

Tritium Ci 1.17E + 00 1.16E + 00

' This Attachment 3 oupersedes the information provided in the January - June 1995 Semi-Annual Radioactive Effluent Release Report for Nine Mile Point Nuclear Station Unit 1. The following 1st Quarter categories have been updated: 1. The following 2nd Quarter categories have been updated and include actual off site vendor results where appropriate: 2., 3. and 4.

2 Concentrations less than the lower limit of detection of the counting system used are indicated with a double esterisk. A lower limit of detection of 1.00E-04 pCi/mi 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/mi for Tritium, es required by Technical Spooifications, has been verified, a No batch mode release occurred during the reporting period.

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e Page 4 ef 4 ATTACHMENT 4' Unit 1_X_ Unit 2_ Reporting Period Januarv June 1995 UPDATE OF GASEOUS EFFLUENTS . GROUND LEVEL RELEASES There were no releases wie the emergency condenser went operation. Only leakege from the wente results in en assumed release based on the conoontrations in the condeneste storece tanke and condeneer shell.

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

.1*. .2" .1*. .2" QUARTER QUARTER QUARTER QUARIEB

1. Fission Genes 8 Argon-41 Ci ** **

Krypton-85 Ci ** **

Kryptorr85m Ci ** **

' KryptorF87 Ci ** *+

Krypton-88 Ci " **

Xenon-133 Ci 6 53E-04 **

Xenore133m Ci ** **

Xenon-135 Ci *' *'

Xenon-135m Ci " **

Xenon-137 **

Cl 2'*

Xenon-138 Ci _ O" Xenon-127 Ci 2 8

2. lodinee lodine-131 Ci ** **

lodine-133 Ci G W lodine-135 Ci 3 3

3. Particulates Strontium-89 Ci *7 3 57E-og Strontium-90 Ci ** *+

Cosium-134 Ci ++ .+

Cesium-137 Ci ++ +*

Cobalt-60 Ci 5.53E - 07 2.65E- 06 Cobalt 58 Ci +e ++

Mengenese-54 Ci **

3 09E-06 Berium-Lanthanum-140 Ci ++ ++

Antimony-125 Ci ++ ..

Niobium-95 Ci ++ ..

Cerium-141 Ci ++ ++

Cerium-144 Ci ++ ++

tron-59 Ci ++ *+

Cesium-136 Ci ** ++ '

l Chromium-51 Ci ++ ++

Zinc-65 Ci ++ ++

Iron-55 Ci ** ++

Molybdenum-99 Ci -

++

4. h Ci 2 46E + 00 4.86E + 00

' This Attachment 4 supereedes the information provided in the January - June 1995 Semi-Annual Radioactive Effluent Release Report for Nine Mile Point Nuclear Station Unit 1. The following ist Quarter categories have been updated: 1. and

4. The following 2nd Quarter categories have been updated and include actual off-site vendor results where appropriate: 3.

and 4, 8 Concentrations less then the lower limit of detection of the counting system used are indicated with a double esterisk. A lower limit of detection of 1.00E-04 pCi/mi 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.