ML17059A423

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Semiannual Radioactive Effluent Release Rept Jan-June 1994.
ML17059A423
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 06/30/1994
From:
NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML17059A422 List:
References
NUDOCS 9409020221
Download: ML17059A423 (68)
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Text

NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUALRADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1994 NIAGARA MOHAWKPOWER CORPORA TION 9e0902022< 9eOS25 PDR

.R ..... 05000220 ADOCK PDR

0-Page 1 of 2 NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY - JUNE 1994 SUPPLEMENTAL INFORMATION

~Focttit: Nine Mile Point Unit ¹t Lichens: Niagara Mohawk Power Corporation TECHNICAL SPECIFICATION LIMITS A) FISSION AND ACTIVATIONGASES

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 mrems/year to the total body and less than or equal to 3000 mrems/year to the skin.
2. The air dose due to noble gases released in gaseous effluents from the Nine Mile Point 1 Station to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 milliroentgen for gamma radiation and less than or equal to 10 mrads for beta radiation, and during any calendar year to less than or equal to 10 milliroentgen for gamma radiation and less than or equal to 20 mrads for beta radiation.

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

1. The dose rate limit of Iodine-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 wastes from the site, shall be less than or equal to 1500 mrems/year to any organ.
2. The dose to a member of the public from Iodine-131, Iodine-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 mrems to any organ and, during any calendar year to less than or equal to 15 mrems 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 gas, 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 1 to unrestricted areas shall be limited during any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and during any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

Page 2 of 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 ACTIVATIONGASES Noble gas effluent activity is determined by on-line gamma spectroscopic monitoring (intrinsic germanium crystal) or gross activity monitoring (calibrated against gamma isotopic analysis of a 4.0L Marinelli grab sample) of an isokinetic stack sample stream.

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

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

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

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

E) LIQUID EFFLUENTS Isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emit ters.

F) SOLID EFFLUENTS Isotopic contents of waste shipments are determined by gamma spectroscopy, gross alpha 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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ATTACHMENT 1 Page 1 of 2 Summary Data Unit 1 X Unit2 Reporting Period Janus - June 199 Liquid Effluents:

10CFR20, Appendix B, Table II, Column 2 Average MPC (Qtr. ~1 ~NA Average MPC (Qtr. ~2 ~A Average Energy (Fission and Activation gases - Mev): There were no fission and activation gases detected during the first quarter 1994.

Qtr. 1 Ey ~ O.OOE+00 Ep ~ O.OOE+00 Qtr. 2 Ry ~ 7.41E-02 8> ~ 1.62E-01 Liquid: There were no liquid releases during the reporting period.

Number of batch releases 0 Total time period for batch releases (hrs) ~NA Maximum time period for a batch release (hrs): ~NA Average time period for a batch release (hrs): ~NA Minimum time period for a batch release (hrs): ~NA Total volume of water used to dilute the liquid effluent during release period (L)

Total volume of water available to dilute the liquid effluent during reporting period (L) 2.68E+ 11 UNIT 1 (OIyLYJ Gaseous (Emergency 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) ~NA Maximum time period for a batch release (hrs): ~NA Average time period for a batch release (hrs): ~NA Minimum time period for a batch release (hrs): ~NA Gaseous (Primary Containment Purge):

Number of batch releases 1 Total time period for batch releases (hrs) 8.00E+ 00 Maximum time period for a batch release (hrs) 8.00E+ 00 Average time period for a batch release (hrs) 8.00E+00 Minimum time period for a batch release (hrs) 8.00E+ 00

ATTACHMENT 1 Page 20f 2 Summary Data Unit 1 X Unit 2 Reporting Period Janus - June 199 Abnormal Releases: There were no abnormal releases during the reporting period.

A. Uquids:

Number of releases 0 Total activity released ~NA Ci B. Gaseous:

Number of releases 0 Total activity released ~NA Ci

ATTACHMENT2 Unit 1 X Unit 2 Reporting Period Janus - June 1994 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL 1

Et 2~ EST. TOTAL QUARTER QUARTER ~ERROR A. Fission & Activation Gases'.

Total release Ci ~Q 2.69E+ 00 5.00E+ 01

2. Average release rate pCi/sec ~Q 3.42E-01 B. lodinest
1. Total iodine-131 Ci ~ t 3.48E-05 3.00E+01
2. Average release rate for period pCi/sec ~0 4.43E-06 C. Particulates
1. )

Particulates with half-lives 8 days Ci 1 A4E-04 5.15E-04 3.00E+01

2. Average release rate for period pCi/sec 1.85E-05 6.55E-05
3. Gross alpha radioactivity Ci 2.82E-05 5.09E-05 2.50E+01 D. Tritiums
1. Total release Ci 5.77E+ 00 1.77E+01 5.00E+01
2. Average release rate for period pCi/sec 7.42E-01 2.25E+ 00 E. Percent of Tech S ec Limits Fission and Activation of Quarterly Gamma Air Dose Limit (5 mrem) ~0 3.48E- 03 Gases'ercent Percent of Quarterly Beta Air Dose Umit (10 mrem) ~0 2.71E-03 Percent of Annual Gamma Air Doso Umit to Date (10 mrem) ~0 1.74E-03 Percent of Annual Beta Air Dose Umit to Date (20 mrem) Q ~ 1.36E-03 Percent of Whole Body Dose Rate Umit (500 mrem/yr) ~0 8.82E-05 Percent of Skin Dose Rate Umit (3000 mrem/yr) ~0 3.37E-05 Tritium Iodines and Particulatess with half. lives rester than 8 da s Percent of Quarterly Dose Limit (7.5 mrem) 5.60E-02 9.86E-02 Percent of Annual Dose Limit (15 mrem) 2.81E-02 7.44E-02 Percent of Organ Dose Rate Umit (1500 mrem/yr) 1 143-03 1.98E-03 Concentrations less than the lower limit of detection of tho 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/ml for required particulates, 1.00E-12 pCi/ml for required lodines, and 1.00E-06 pCi/ml for Tritium, as required by Technical Specifications, has been verified.

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

ATTACHMENT3 Unit 1 X Unit 2 Reporting Period Januar - June 1994 GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODEs 1K gal Nuclides Released QUARTER QUARTER

1. Fission Gasest Argon-41 Ci ~ I ~ I Krypton-85 Ci ~ I 00 Krypton-85m Ci ~I 1.58E-01 Krypton-87 Ci ~I ~ I Krypton-88 Ci ~I 00 Xenon-127 Cl ~I Xenon-133 Ci ~ I 2.14E+ 00 Xenon-133m Ci ~ I ~ I Xenon-135 Ci I~ 2.95E-01 Xenon-135m Ci ~ I Xenon-137 Ci ~ I ~ I Xenon-138 Ci ~ I ~ I
2. Iodine s~

Iodine-131 Ci ~ I 3.48E-05 Iodine-133 Ci ~ I 9.12E-04 ladino-135 Ci ~I ~ I

3. Particulates

'trontium-89 Ci 2.48E-05 2.53E-04 Strontium-90 Ci ~ I 2.83E-05 Cesium-134 Ci ~I I~

Cesium-137 Ci ~I ~I Cobalt-60 Ci 1.19E-04 6.03E<<05 Cobalt-58 Ci ~I ~I Manganese-54 Ci ~I ~I Barium. Lanthanum-140 Ci ~I ~I Antimony-125 Ci ~I 00 Niobium-95 Ci 11 I~

Cerium-141 Ci ~I ~I Cerium-144 Ci ~ I ~I Iron-59 Ci ~ I I~

Cesium-136 Ci ~ I ~I Chromium-51 Ci ~ I ~I Zinc-65 Ci ~I ~I Iron-55 ~I 1.68E-04 Molybdenum-99 Ci ~I ~I

4. Tritiums Ci 1.78E+00 1.30E+ 01

'oncentrations loss than the lowor limit of detection of the counting system used aro indicated with a double asterisk. 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/ml for required lodinos, and 1.00E-06 pCi/ml for Tritium, as required by Technical Spocifications, has been vorified.

Tritium, Iron-55, and Strontium results woro not recoived from the off-site vendor at tho time of this rcport. These numbers include estimates, and actual numbers will be included in the next Semi-Annual Report.

s No batch mode release occurred during tho reporting period.

ATTACHMENT4 Unit 1 X Unit 2 Reporting Period Januar - June 199 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES There were no releases via the emergency condenser vent operation. Only leakage froin the vents results in an assumed release based on the concentrations In the condensate storage tanks and condenser shell.

CONTINUOUS MODE BATCH MODE 1>> gal 1 pe QUARTER QUARTER QUARTER QUARTER Nuclides Released

1. Fission Gases'rgon-41 Ci ~0 No Releases No Releases Krypton-85 Ci ~0 ~0 No Releases No Releases Krypton-85m Ci ~0 ~s No Releases No Releases Krypton-87 Ci ~0 ~0 No Releases No Releases Krypton-88 Ci ~4 0~ No Releasee No Releases Xenon-133 Ci ~0 9.53E-02 No Releases No Releases Xenon-133m Ci ~0 ~s No Releases No Releases Xenon-135 Ci ~0 ~s No Releases No Releases Xenon-135m Ci 0~ ~0 No Releases No Releases Xenon-137 Ci OO 0~ No Releases No Releases Xenon-138 Ci ~0 ~0 No Releases No Releases Xenon-127 Ci ~ t 0~ No Releases No Releases 2.

Iodines'odine-131 Ci ~0 ~0 No Releases No Releases Iodine-133 Ci ~0 ~0 No Releases No Releases Iodine-135 Ci OO ~0 No Releases No Releases

3. Particulates'trontium-89 Ci 7.16E-07 No Releasee No Releases Strontium-90 Ci OO 8.95E-OS No Releases No Releases Cesium-134 Ci ~0 ~0 No Releases No Releases Cesium-137 Ci 1.79E-07 No Releases No Releases Cobalt-60 Ci ~0 2.61E-06 No Releases No Releases Cobalt-59 Ci ~0 ~0 No Releases No Releases Manganese-54 Ci ~0 2.52E-07 No Releases No Releases Barium-Lanthanum-140 Ci ~0 ~0 No Releases No Releases Antimony-125 Ci ~0 ~0 No Releases No Releasee Niobium-95 Ci ~0 ~0 No Releases No Releases Cerium-141 Ci ~0 ~0 No Releases No Releases Cerium-144 Ci ~0 ~0 No Releases No Releases Iron-59 Ci ~ t No Releases No Releases Cesium-136 Ci ~0 ~0 No Releases No Releases Chromium-51 Ci ~0 ~ t No Releases No Releases Zinc-65 Ci ~0 ~s No Releases No Releasee Iron-55 Ci ~0 1.08E-06 No Releases No Releases Molybdenum-99 Ci ~0 4~ No Releases No Releases 4.Tritium Ci 3.99E+ 00 4.71E+ 00 No Releases No Releases

'oncentrations 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 yCi/mi for required noble gases, 1.00E-11 yCi/ml for required particulates, 1.00E-12yCi/ml for required lodines, and 1.00E-06 yCi/ml for Tritium, as required by Technical Specifications, has been verified.

ATTACHMENT5 Page 1 of 2 Unit1 X Unit 2 Reporting Period Janus - June 199 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1 2~ EST. TOTAL QUARTER QUARTER ~ERROR A. Fission SI Activation Products

1. Total release (not including Tritium, gases, alpha) Ci No Releases No Releases 5.00E+01
2. Average diluted concentration during reporting period /rCI/ml No Releases No Releases B. Tritium
1. Total release Ci No Releases No Releases 5.00E+01
2. Average diluted concentration during reporting period yCI/ml No Reieasea No Releases C. Dissolved and Entrained Gases 1 ~ Total release Ci No Releases No Releases 5.00E+01
2. Average diluted concentration during reporting period yCI/ml No Releases No Releases D. Gross Al ha Radioac'tlvi't
1. Total release Ci 'o Releases No Releases 5.00E+01 E. Volumes
1. Prior to dilution Liters No Releases No Releases 5.00E+01
2. Volume of dilution water used during release period Liters No Releases No Releases 5.00E+01
3. Volume of dilution water available during reporting period Liters 1.29E+ 11 1.29E+ 11 5.00E+01 F. Percent of Technical S ecification Limits Percent of Quarterly Whole Body Dose Limit (1.5 mrem) No Releases No Releases Percent of Quarterly Organ Dose Limit (5 mrem) No Releases No Releases Percent of Annual Whole Body Dose Umit to Data (3 mrem) 0/ No Releases No Releases Percent of Annual Organ Dose Limit to Date (10 mrem) No Releases No Releases Percent of 10CFR20 Concentration Umit No Releases No Releases Percent of Dissolved or Entrained Noble Gas Umit (2.00E-04/rCI/ml) 0/ No Releases No Releases

ATTACHMENT5 Page 2 of 2 Unit 1 X Unit 2 Reporting Period Janus - June 199 LIQUID EFFLUENTS RELEASED BATCH MODE 1" gal Nuclides Released QUARTER QUARTER Strontium-89 Ci No Releases No Releases Strontium-90 Ci No Releases No Releases Cesium-134 Ci No Releases No Releases Cesium-137 Ci No Releases No Releases Iodine-131 Ci No Releases No Releases Cobalt-58 Ci No Releases No Releasee Cobalt-60 Ci No Releases No Releases Iron-59 Ci No Releases No Releases Zinc-65 Ci No Releases No Releases Manganese-54 Ci No Releases No Releases Chromium-51 Ci No Releases No Releases Zirconium-Niobium-95 Ci No Releases No Releases Molybdenum-99 Ci No Releases No Releases Technetium-99m Ci No Releases No Releases Barium-Lanthanum-140 Ci No Releases No Releases Cerium-141 Ci No Releases No Releases Tungsten-187 Ci No Relenses No Releases Arsenic-76 Ci No Releases No Releases Iodine-133 Ci No Releases No Releases Iron-55 Ci No Releases No Releases Neptunium-239 Ci No Releases No Releases Praseodymium-144 Ci No Releases No Releases Iodine-135 Ci No Releases No Releases Dissolved or Entrained Gases Ci No Releases No Releases Tritium Ci No Releases No Releases

ATTACHMENT6 Page 1 of 6 Unit 1 X Unit 2 Reporting Period Janua - June 199 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.1 TYPE Volume ~Activit (me) 'Ci)

Class Class 1.75E+ 01 1.29E+ 01 0 3.25E+ 01 1.58E+ 02 0

1. Spent Resin Filter Sludge 4.84E+ 00 1.03E+ 01 0 1.68E+01 9.67E+ 01 0 Concentrated Waste 0 0 0 0 0 0 Evaporator Bottoms Total 2.23E+ 01 2.325+ 01 0 4.93E+ 01 2.55E+ 02 0
2. Dry Compressible Waste, Dry 5.03E+ 00 0 0 1.51E+00 0 0 Non-Compressible Waste (Contaminated Equipment)
3. Irradiated Components 0 1.64E+ 00 1.64E+ 00 0 4.18E+ 03 1.52E+ 04 The estimated total error is 5.00E+01%.

ATTACHMENT6 Page 2 of 6 Unit 1 X Unit 2 Reporting Period Janus - June 1994 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.1 TYPE Solidification Container ~Packa e ~Aae Spent Resin HIC ~TA None Filter Sludge HIC ~TA Cement Concentrated Waste ~NA ~NA ~NA

2. Dry Compressible Waste, Steel-Liner ~TP A None Dry Non-Compressible Waste (Contaminated Equipment)
3. Irradiated Components Steel-Liner ee None

ATTACHMENT6 Page 3 Of 6 Unit1 X Unit 2 Reporting Period Januar - June 199 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)

e. Spent Resins, Filter Sludges, Concentrated Waste:

Nuclide Percent (1) Co-60 5.27E+01 (2) Cs-137 1.71E+01 (3) Fe-55 1.13E+01 (4) Mn-54 9.79E+00 (5) Cs-134 4.05E+00 (6) Fe-59 1.47E+00 (7) Other 3.59E+00

b. Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment):

Nuclide Percent (1) Co-60 5.32E+01 (2) Mn-54 1.80E+01 (3) Cr-51 1.10E+01 (4) Cs-137 1.05E+01 (5) Fe-55 2.05E+00 (6) Fe-59 1.94E+00 (7) Co-58 1.91E+00 (8) Other 1 AOE+ 00

c. Irradiated Components:

Nuclide Percent (1) Fe-55 5.12E+01 (2) Co-60 3.98E+01 (3) Mn-54 6.61E+00 (4) Ni-63 2.39E+00 (5) Other (1.00E+00

d. Other: There were no shipments.

Nuclide Percent

ATTACHMENT6 Page 4 of 6 Unit1 X Unit 2 Reporting Period Janus - June 199 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.3. SOLID WASTE DISPOSITION Number of Shi ments Mode of Trans ortation Destination 13 Truck B wlSB B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)

There were no shipments.

Number of Shi ments Mode of Trans ortation Destination 0 ~NA ~NA

ATTACHIVIENT6 Page 5 of 6 Unit 1 X Unit 2 Reporting Period Janus - June 1994 SOLID WASTE AND IRRADIATED FUEL SHIPMENTSt C. SOLID WASTE SHIPPED OFF-SITE TO VENDORS FOR PROCESSING AND SUBSEQUENT BURIAL Below is a summary of Dry Active Waste that was shipped off-site for processing and burial by vendor facilities (i.e.,

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

C.1. TYPE OF WASTE - noncompacted commingled trash shipped to Oak Ridge, TN for processing prior to burial at Barnwell, SC Burial Volume Activity Est. Total

~nd ~CI ~gr r 2.06E+01 1.49E-01 5.00+01 C.2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent (1) Co-60 6.14E+01 (2) Cs-137 1.93E+01 (3) Mn-54 9.10E+00 (4) Cr-51 4.53E+00 (5) Co-58 2.89E+00 (6) Fe-59 1.45E+00 (7) Other 1.33E+00 C.3. SOLID WASTE DISPOSITIONS =

Number of Shi ments Mode of Trans ortation Destination 37 Truck S wIISC June results were not received from the off-site vendor at the time of this report. An updated attachment will be provided as necessary in the next Semi-Annual Report.

The number of shipments reported here represents the total number that was shipped from the off-site vendor for burial. This does not represent the number of shipments Niagara Mohawk sent to be processed.

ATTACHMENT6 Page 6 of 6 Unit 1 X Unit 2 Reporting Period Janus - June 1994 SOUD WASTE AND IRRADIATED FUEL SHIPMENTS D. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIAL Below is a summary of the sewage sludge and sanitary influent sand and grit which was removed from the site sanitary treatment facility and transferred to a municipal sewage treatment facility, for subsequent drying and disposal to a landfill. This is a site release, and therefore Includes the results from Unit 2 activities, also.

D.1. TYPE OF WASTE Activity

~LVolume Burial

~CI Sewage Sludge There were no shipments with detectable quantities of plant-related nuclides.

Sanitary Influent Sand and Grit 3.41E+02 2.04E-OS D.2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent Co-60 1.00E+02 D.3. SOLID WASTE DISPOSITION Number of Shi ments Mode of Trans ortetion ~Oesthado Landfill There was one shipment of, sanitary influent sand and grit with quantified Co-60 that was sent by vendor vacuum tank truck from NMP to the treatment facility. The number of shipments sent from NMP does not reflect the number of shipments to the ultimate destination (i.e. landfill). Wastes are mixed with other sludge, dried, and it Is our intention that the material will be transferred to a state approved landfill by municipal personnel.

I 0

ATTACHIVIENT7 Unit 1 X Unit 2 Reporting Period Janus - June 1994

SUMMARY

OF CHANGES TO THE OFFeSITE DOSE CALCULATIONMANUAL There was one revision to the Unit 1 ODCM during the reporting period. Copies of revisions 13 and 14 are attached and below ls a summary of changes presented to and approved by the Station Operations Review Committee in June 1994. The summary also includes a justification for each change.

Chan e Summa 11 ~P69 - An editorial change is mode to locations 4134 on Figure 61-2 (memo from Bg. Zncharek to gD. Thomas, dated January 6, 1994). The map revision lFigure 5.1-2) corrects an air sampling and an environmental TLD location which were not properly transferred during conversion to CAD. Calculations or deposition (D/0) parameters are not impacted.'1~F16-A change to section 3 2, 'Doss snd Dose Rote Determlnntlons's mode to ctsrify that for ground lovel releases from the Emergency Condenser Vent, without tube leakage, a condensate storage tank and emergency condenser shell isotopic distribution is to be used. This clarification improves the accuracy of dose calculations by applying correct isotopic distributions to the evaluation. No changes are made to the calculational methodology, with the exception of which isotopic distribution to apply. Without this clarification, an overly conservative off-gas isotopic distribution would have been applied lReference, NRC Assessment of ODCM, April 1994).

ATTACHMENT8 Unit 1 X Unit2 Reporting Period Janus - June 1994

SUMMARY

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

ATTACHMENT9 Unit 1 X Unit 2 Reporting Period Januer - June 1994

SUMMARY

OF INOPERABLE MONITORS Monitor Dates of Inoperability Cause and Corrective Actions There were no inoperabie monitors for a period greater than 30 days during the reporting period.

UPDATE TO THE PREVIOUS REPORTS

Unit 1 X Unit 2 Reporting Period Janus - June 199 UPDATE OF RELEASE AND DOSE DATA FOR GASEOUS (ELEVATED AND OROUND LEVEL) AND UOUID EFFLUENTS Update of data using actual results from tho off-site vendors for Strontium, Tritium, and Iron-55 for the fourth quarter of 1993.

GASEOUS LIQUID 4 QUARTER 4 QUARTER

~Aadvit Ci ~AGCvlt Ci Nuclide'r-89 2.28E-05 No Releases Sr-90 No Releases H-3 6.15E+ 00 No Releases Fe-55 1.41E-05 No Releasee Particulatos GASEOUS LIQUID

1. Particulates with Ci 3.69E-05 ~NA half-lives >8 days
2. Average release rate yCI/sec 4.64E- 06 ~NA for period Tritium
1. Total release Ci 6.15E+00 ~NA
2. Average release rate /ICI/soc 7.73E-01 ~NA for period Tritium lodines and GASEOUS LIQUID Particulates with half-lives rester than 8 da s
1. Percent of Quarterly 2.40E-03 ~NA Dose Limit (Quarterly) (Quarterly)
2. Percent of Annual 9.92E-01 ~NA Dose Umit to Dates (Annual) (Annual)
3. Percent of Organ 4.75E-05 ~NA

- Doss Rate Limit (Quarterly) (Quarterly)

(Gaseous)(Quarterly) ~NA ~NA

- Dose Limit (Uquid) (Annual) (Annual)

(Annual & Quarterly)

4. Percent of 10CFR20 ~NA ~NA Concentration Umit (Liquid)
5. Percent of Dissolved N/A or Entrained Noble Gas (Uquid)

Concentrations loss than the lower limit of detection, as required by Technical Specifications are indicated with a doublo asterisk.

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

0 ATTACHMENT61 Page 1 Of 6 Unit 1 X Unit 2 Reporting Period Jul - December 199 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.1 TYPE Volume ~Act vll

~(m ) (Ci)

Class Class

1. Spent Resin 5.83E+ 00 0 0 6.06E+ 00 0 0 Filter Sludge 5.50E+ 00 0 0 1.40E+01 0 0 Concentrated Waste, Evaporator 0 0 0 0 0 0 Bottoms Total 1.13E+01 0 0 2.01E+ 01 0 0
2. Dry Compressible Waste, Dry 0 0 0 0 0 0 Non-Compressible Waste (Contaminated Equipment)

There were no irradiated components shipped for burial during the reporting period.

3. Irradiated Components 0 0 0 0 0 0 This Attachment 6 supersedes the information provided in the July - December 1993 Semi-Annual Radioactive Effluent Release Report for Nine Mile Point Nuclear Station Unit 1 and includes a change to the class A filter sludge activity as a result of an independent technical evaluation of the off-site vendor analyses performed by Niagara Mohawk Power Corporation.

The estimated total error is 5.00E+01%.

Unit 1 X Unit 2 ATlACHMENT 6'age 2of 6 Reporting Period Jul - December 1993 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A.1 TYPE Solidification Container ~Peeke e ~Acne Spent Resin HIC ~Te A None Filter Sludge HIC ~TA Cement Concentrated Waste ~NA N/A NIA

2. Dry Compressible Waste, ~NA NIA ~NA Dry Non-Compressible Waste (Contaminated Equipment)
3. Irradiated Components ~NA ~NA ~NA

'his page is included in the update for completeness. There are no changes to information previously reported in the July.December 1993 Semi-Annual Report.

ATTACHMENT61 Page 3 of 6 Unit1 X Unit 2 Reporting Period Jul - December 199 SOUD WASTE AND IRRADIATED FUEL SHIPMENTS A.2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)

a. Spent Resins, Filter Sludges, Concentrated Waste:

Nuclide Percent (1) Co.60 3.55E+01 (2) Cs-137 3.07E+01 (3) Fe-55 2.27E+01 (4) Mn-54 6.54E+00 (5) Cs-134 2.89E+00 (6) Other 1.67E+00

b. Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment): There were no shipments.

Nuclide Percent

c. Irradiated Components: There were no shipments.

Nuclide Percent

d. Other: There were no shipments.

Nuclide Percent

'his Attachment 6 supersedes the information provided In the July - December 1993 Semi-Annual Radioactive Effluent Release Report for Nine Mile Point Nuclear Station Unit 1 and includes a change in the percentages of the major nuclide composition for A.2.a as a result of an independent technical evaluation of the off-site vendor analyses performed by Niagara Mohawk Power Corporation.

Unit 1 X Unit 2 ATTACHMENT 6'age 4 of 6 Reporting Period Jul - December 1993 SOUD WASTE AND IRRADIATED FUEL SHIPMENTS A.3. SOLID WASTE DISPOSITION Number of Shi ments Mode of Trans ortatlon Destinatlon ruck Bemwee BC B. IRRADIATED FUEL SHIPMENTS (DISPOSITION):

There were no shipments.

Number of Shi ments Mode of Trans ortation Destination 0 ~NA NIA

~

This page is included in the update for completeness. There are no changes to the information previously reported in the July - December 1993 Semi-Annual Report.

0 ATTACHNIENT61 Page 5 of 6 Unit 1 X Unit 2 Reporting Period Jul - December 199 SOUD WASTE AND IRRADIATED FUEL SHIPMENTS C. SOLID WASTE SHIPPED OFF-SITE TO VENDORS FOR PROCESSING AND SUBSEQUENT BURIAL Below is a summary of Dry Active Waste that was shipped off-site for processing and burial by vendor facilities (i.e.,

ALARON, QUADREX, and/or SCIENTIFIC ECOLOGY GROUP) during Jul - December 1993. These totals were reported separately from "10CFR61 Solid Waste Shipped for Burial" since (a) waste classification and burial was performed by the vendors, and (b) Technical Specification 6.9.1 requires reporting of "information for each class of solid waste (as defined by 10CFR61) shipped off-site during the reporting period". The information provided in this section, therefore, is in addition to that required by the Technical Specifications. The following data represents the actual shipments made from the off-site vendors of our non-compacted commingled trash that was processed prior to burial.

C.l. TYPE OF WASTE - noncompacted commingled trash and contaminated fuel pool equipment shipped to Oak Ridge, TN for Burial Volume Activity Est. Total processing prior to burial at Barnwell, SC ~mr ~CI ~Error 2.33E+ 01 5.94E-01 5.00+ 01 C.2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent (1) Co-60 6.17E+01 (2) Cs-137 2.09E+01 (3) Mn-54 8.09E+00 (4) Co-58 4.20E+00 (5) Fe-55 1.83E+00 (6) Fe-59 1.58E+00 (7) Other 1.65E+00 C 3 SOLID WASTE DISPOSITIONs Number of Shi ments Mode of Trans ortation Destination 32 Truck 8 row tt SC This Attachment 6 supersedes the information provided in the July - December 1993 Semi-Annual Radioactive Effluent Release Report with updated burial volume, activity, and number of shipments for Nine Mile Point Nuclear Station Unit 1.

The number of shipments reported here represents the total number that was shipped from the off-site vendor for burial. This does not represent the number of shipments Niagara Mohawk sent to be processed.

ATTACHMENT61 Page 6 of 6 Unit 1 X Unit 2 Reporting Period Jul - December 199 SOUD WASTE AND IRRADIATED FUEL SHIPMENTS D. SEWAGE SLUDGE SHIPPED TO A TREATMENT FACILITY CENTER FOR PROCESSING AND BURIAL There were no shipments of sewage sludge with detectable quantities of plant-related nuclides from NMP to the treatment facility during the reporting period.

This page is included in the update for completeness. There are no changes to the information previously reported in the July - December 1993 Semi-Annual Report.

I ATTACHMENT6 Page 1 of 6 Unit 1 X Unit 2 Reporting Period Janus - June 199 SOUD WASTE AND IRRADIATED FUEL SHIPMENTS A.1 TYPE Volume ~Activi )(

~(m ) (Ci)

Class Class

1. Spent Resin 4.79E+ 01 0 0 3.50E+02 0 0 Filter Sludge 0 1.65E+01 0 0 2.27E+ 02 0 Concentrated Waste Evaporator 0 .10E+01 0 0 3.06E+ 01 0 Bottoms Total 4.79E+ 01 2.75E+ 01 0 3.50E+ 02 2.58E+ 02 0
2. Dry Compressible Waste, Dry Non-Compressible Waste i . 44 4 4 4 01 0 0 4.06E+ 00 0 0 (Contaminated Equipment)

There were no irradiated components shipped for burial during the reporting period.

3. Irradiated Components 0 0 0 0 0 0 This Attachment 6 supersedes the information provided in the January - June 1993 Semi-Annual Radioactive Effluent Release Report for Nine Mile Point Nuclear Station Unit 1 and corrects an error in the Semi-Annual Report for the filter sludge classification and also includes a change to the class B filter sludge activity and class A D.A.W. activity as a result of an independent technical evaluation of the off-site vendor analyses performed by Niagara Mohawk Power Corporation.

The estimated total error is 5.00E+01%.

Unit 1 X Unit 2 ATTACHMENT 6'age Reporting Period Janus 2of 6

- June 1993 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A.l TYPE Solidification Container ~Peeke e ~eeet

1. Spent Resin HIC ~TA None Filter Sludge HIC ~T* A Cement Concentrated Waste HIC ~T* A Cement
2. Dry Compressible Waste, Steel. Liner ~TA None Dry Non-Compressible Waste (Contaminated Equipment)
3. Irradiated Components ~NA ~NA This Attachment 6 supersedes the information provided in the January - June 1993 Semi-Annual Radioactive Effluent Release Report with a correction to the package type for concentrated waste.

ATTACHMENT61 Page30f 6 Unit 1 X Unit 2 Reporting Period Janus - June 199 SOUD WASTE AND IRRADIATEDFUEL SHIPMENTS A.2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION {BYTYPE OF WASTE)

a. Spent Resins, Filter Sludges, Concentrated Waste:

Nuclide Percent (1) Co-60 6.22E+01 (2) Fe-55 1.41E+01 (3) Mn-54 1.17E+01 (4) Cs-137 8.24E+00 (5) Co-58 1.08E+00 (6) Other 2.68E+00

b. Dry Compressible Waste, Dry Non-Compressible Waste {Contamlnated Equipment):

Nuclide Percent (1) Co-60 5.31E+01 (2) Cs-137 2.47E+01 (3) Mn-54 1.14E+01 (4) Co-58 6.10E+00 (5) Fe-59 1.76E+00 (6) Fe-55 '1.12E+00 (7) Other 1.82E+00

c. Irradiated Components: There were no shipments.

Nuclide Percent

d. Other: There were no shipments.

Nuclide Percent This Attachment 6 supersedes the information provided in the January - June 1993 Semi-Annual Radioactive Effluent Release Report for Nine Mile Point Nuclear Station Unit 1 and includes changes to the nuclide order and percentages for A.2.a and percentages for A.2.b as a result of an independent technical evaluation of the off-site vendor analyses performed by Niagara Mohawk Power Corporation.

Unit 1 X Unit 2 ATTACHMENT 6'age Reporting Period Janus - June 4 of 6 1993 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.3. SOLID WASTE DISPOSITION Number of Shl ments Mode of Trans ortation Destination 17 Truck Berewee BB B. IRRADIATED FUEL SHIPMENTS (DISPOSITION):

There were no shipments.

Number of Shi ments Mode of Trans ortation Destination 0 N/A ~NA t This page is included in the update for completeness. There are no changes to the information previously reported in the January - June 1993 Semi-Annual Report.

ATTACHIVIENT61 Page 5 of 6 Unit 1 X Unit 2 Reporting Period Januar - June 199 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS C. SOLID WASTE SHIPPED OFF-SITE TO VENDORS FOR PROCESSING AND SUBSEQUENT BURIAL Below is a summary of Dry Active Waste that was shipped off-site for processing and burial by vendor facilities (i.e.,

ALARON, QUADREX, and/or SCIENTIFIC ECOLOGY GROUP) during Janus - June 1993. These totals were reported separately from "10CFR61 Solid Waste Shipped for Burial" (i.e., Section A of Table 3A) since (a) waste classification and burial was performed by the vendors, and (b) Technical Specification 6.9.1 requires reporting of "information for each class of solid waste (as defined by 10CFR61) shipped off-site during the reporting period". The information provided in this section, therefore, is in addition to that required by the Technical Specifications. The following data represents the actual shipments made from the off-site vendors of our non-compacted commingled trash that was processed prior to burial.

C.1. TYPE OF WASTE - noncompacted commingled trash and contaminated fuel pool equipment shipped to Oak Ridge, TN for Burial Volume Activity Est. Total processing prior to burial at Barnwell, SC ~mo ~CI ~Error 1.92E+01 2.71E-01 5.00+01 C.2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent (1) Co-60 5.98E+01 (2) Cs-137 2.27E+01 (3) Mn-54 9.54E+00 (4) Co-58 5.10E+00 (5) Fe-59 1.88E+00 (6) Other 9.34E -01 C.3. SOLID WASTE DISPOSITION2 Number of Shi ments Mode of Trans ortation Destination 29 Truck BmwltBC This Attachment 6 supersedes the updated January - June 1993 information provided with the July - December 1993 Semi-Annual Radioactive Effluent Release Report with an updated number of shipments and destination for all shipments for Nine Mile Point Nuclear Station Unit 1.

The number of shipments reported here represents the total number that was shipped from the off-site vendor for burial. This does not represent the number of shipments Niagara Mohawk sent to be processed.

Unit 1 X Unit 2 ATTACHMENT 6'age Reporting Period Janus 6 of 6

- June 1993 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS D. SEWAGE SLUDGE SHIPPED TO A TREATMENT FACILITY CENTER FOR PROCESSING AND BURIAL Below ls a summary of the sewage sludge which was removed from the site sanitary treatment facility and transferred to a municipal sewage treatment facility, for subsequent drying and disposal to a landfill. This is a site release, and therefore includes the results from Unit 2 activities, also.

D.1. TYPE OF WASTE Burial Volume Activity

~L ~CI sewage sludge 3.03E+04 2.4E-07 D.2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent Co.60 1.00E+02 D.3. SOLID WASTE DISPOSITION Number of Shi ments Mode of Trans ortation Destination Landfill Note: There wore two shipments of sewage sludge with quantified Co-60 that were sent by vendor vacuum tank truck from NMP to the treatment facility. The number of shipments sent from NMP does not reflect the number of shipments to tho ultimata dostination (i.o. landfill). Sludge is mixed with municipal sludge, dried, and subsequontly transferred to a state approved landfill by municipal personnel.

This pago is included in tho updato for completeness. There are no changes to the data previously reported in the January - June 1993 Semi-Annual Report.

OFF-SITE DOSE CALCULATIONMANUAL Revision 13 and 14 enclosed per Attachment 7 of the Semi-Annual Radioactive Effluent Release Report

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