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| number = ML17059A423
| number = ML17059A423
| issue date = 06/30/1994
| issue date = 06/30/1994
| title = Semiannual Radioactive Effluent Release Rept Jan-June 1994.
| title = Semiannual Radioactive Effluent Release Rept Jan-June 1994
| author name =  
| author name =  
| author affiliation = NIAGARA MOHAWK POWER CORP.
| author affiliation = NIAGARA MOHAWK POWER CORP.
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=Text=
=Text=
{{#Wiki_filter:NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUALRADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1994 NIAGARA MOHAWKPOWER CORPORA TION 9e0902022<   9eOS25 PDR
{{#Wiki_filter:NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY - JUNE 1994 NIAGARAMOHAWKPOWER CORPORA TION 9e0902022<
.R     ..... 05000220 ADOCK PDR
9eOS25 PDR ADOCK 05000220
.R PDR


0-Page 1 of 2 NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY - JUNE 1994 SUPPLEMENTAL INFORMATION
0-
~Focttit: Nine Mile Point Unit  &#xb9;t                                          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.
Page 1 of 2 NINE MILEPOINT NUCLEAR STATION - UNIT 1 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY-JUNE 1994 SUPPLEMENTAL INFORMATION
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.
~Focttit:
B)     IODINES Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly)     of charcoal cartridges sampled from an isokinetic stack sample stream.
Nine Mile Point Unit&#xb9;t Lichens:
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.
Niagara Mohawk Power Corporation TECHNICALSPECIFICATION LIMITS A)
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.
FISSION AND ACTIVATIONGASES 1.
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.
The dose rate limitof 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.
E)     LIQUID EFFLUENTS Isotopic analysis of a representative sample of each batch and composite analysis   of non-gamma emit ters.
2.
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.
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, HALFLIVES ) 8 DAYS 1.
The dose rate limitof 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)
LIQUIDEFFLUENTS 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 of2 MEASUREMENTS AND APPROXIMATIONSOF TOTALRADIOACTIVITY 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 Activityreleased 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 ofTritium 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)
LIQUIDEFFLUENTS Isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters.
F)
SOLID EFFLUENTS Isotopic contents of waste shipments are determined by gamma spectroscopy, gross alpha and water content 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.


  ~
S
S
~


ATTACHMENT 1                                          Page 1   of 2 Summary Data Unit 1 X     Unit2                                                               Reporting Period Janus     - June 199 Liquid Effluents:
ATTACHMENT1 Summary Data Page 1 of 2 Unit 1 X
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.
Unit2 Liquid Effluents:
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.
Reporting Period Janus
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)
- June 199 10CFR20, Appendix B, Table II, Column 2 Average MPC (Qtr. ~1 Average MPC (Qtr. ~2
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.
~NA
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):
~A Average Energy (Fission and Activation gases - Mev): There were no fission and activation gases detected during the first quarter 1994.
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
Qtr. 1 Qtr. 2 Ey
~ O.OOE+00 Ep ~
O.OOE+00 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 Total time period for batch releases (hrs) 1 8.00E+ 00 Maximum time period for a batch release (hrs)
Average time period for a batch release (hrs) 8.00E+ 00 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.
ATTACHMENT1 Summary Data Page 20f 2 Unit 1 X
A. Uquids:
Unit 2 Abnormal Releases:
Number of releases       0 Total activity released ~NA Ci B. Gaseous:
There were no abnormal releases during the reporting period.
Number of releases       0 Total activity released ~NA Ci
A.
Uquids:
Reporting Period Janus
- June 199 Number of releases 0
B.
Gaseous:
Total activity released
~NA Ci 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
ATTACHMENT2 Unit 1 X
Et           2~         EST. TOTAL QUARTER         QUARTER       ~ERROR A.     Fission & Activation   Gases'.
Unit 2 Reporting Period Janus
Total release                               Ci           ~Q         2.69E+ 00       5.00E+ 01
- June 1994 GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES, ELEVATEDAND GROUND LEVEL 1 Et 2~
: 2.                  Average release rate                      pCi/sec        ~Q          3.42E-01 B.     lodinest
EST. TOTAL QUARTER QUARTER
: 1.                 Total iodine-131                           Ci             ~ t       3.48E-05         3.00E+01
~ERROR A.
: 2.                  Average release rate for period            pCi/sec        ~0        4.43E-06 C.     Particulates
Fission & Activation Gases'.
: 1.                                             )
Total release 2.
Particulates with half-lives 8 days         Ci        1 A4E-04      5.15E-04        3.00E+01
Average release rate Ci pCi/sec
: 2.                  Average release rate for period           pCi/sec     1.85E-05       6.55E-05
~ Q
: 3.                   Gross alpha radioactivity                  Ci        2.82E-05       5.09E-05         2.50E+01 D. Tritiums
~ Q 2.69E+ 00 5.00E+ 01 3.42E-01 B.
: 1.                 Total release                               Ci       5.77E+ 00       1.77E+01       5.00E+01
lodinest 1.
: 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.
2.
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.
Total iodine-131 Average release rate for period Ci pCi/sec
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.
~t
~ 0 3.48E-05 3.00E+01 4.43E-06 C.
Particulates 1.
2.
3.
Particulates with half-lives )8 days Average release rate for period Gross alpha radioactivity Ci pCi/sec Ci 1 A4E-04 1.85E-05 2.82E-05 5.15E-04 3.00E+01 6.55E-05 5.09E-05 2.50E+01 D.
Tritiums 1.
Total release 2.
Average release rate for period Ci pCi/sec 5.77E+ 00 7.42E-01 1.77E+01 5.00E+01 2.25E+ 00 E.
Percent of Tech S ec Limits Fission and Activation Gases'ercent of Quarterly Gamma Air Dose Limit (5 mrem)
Percent of Quarterly Beta Air Dose Umit (10 mrem)
Percent of Annual Gamma Air Doso Umit to Date (10 mrem)
Percent of Annual Beta AirDose Umit to Date (20 mrem)
Percent of Whole Body Dose Rate Umit (500 mrem/yr)
Percent of Skin Dose Rate Umit (3000 mrem/yr)
Tritium Iodines and Particulatess with half.lives rester than 8 da s
Percent of Quarterly Dose Limit (7.5 mrem)
Percent of Annual Dose Limit (15 mrem)
Percent of Organ Dose Rate Umit (1500 mrem/yr)
~ 0
~ 0
~ 0 Q ~
~ 0
~ 0 5.60E-02 2.81E-02 1 143-03 3.48E- 03 2.71E-03 1.74E-03 1.36E-03 8.82E-05 3.37E-05 9.86E-02 7.44E-02 1.98E-03 Concentrations less than the lower limitof detection of tho counting system used are indicated with a double asterisk.
A lower limitof 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 willbe 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
ATTACHMENT3 Unit 1 X
: 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
Unit 2 Reporting Period Januar
: 2. Iodine s~
- June 1994 GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODEs Nuclides Released 1.
Iodine-131                                      Ci            ~ I                 3.48E-05 Iodine-133                                      Ci            ~  I                  9.12E-04 ladino-135                                      Ci            ~I                       ~  I
Fission Gasest Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-127 Xenon-133 Xenon-133m Xenon-135 Xenon-135m Xenon-137 Xenon-138 2.
: 3. Particulates
Iodine s~
                                  'trontium-89 Ci        2.48E-05                2.53E-04 Strontium-90                                   Ci            ~ I                  2.83E-05 Cesium-134                                     Ci            ~I                      I~
Iodine-131 Iodine-133 ladino-135 Ci Ci Ci Ci Ci Cl Ci Ci Ci Ci Ci Ci Ci Ci Ci 1K QUARTER
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~
~I
Cerium-141                                     Ci             ~I                       ~I Cerium-144                                      Ci            ~ I                     ~I Iron-59                                        Ci            ~ I                     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
~I
: 4. Tritiums                                        Ci        1.78E+00                  1.30E+ 01
~I
'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.
~I
~I
~I
~II~
~I
~I
~I
~I
~I
~I gal QUARTER
~I 00 1.58E-01
~I 00 2.14E+ 00
~I 2.95E-01
~I
~I 3.48E-05 9.12E-04
~I 3.
Particulates
'trontium-89 Strontium-90 Cesium-134 Cesium-137 Cobalt-60 Cobalt-58 Manganese-54 Barium.Lanthanum-140 Antimony-125 Niobium-95 Cerium-141 Cerium-144 Iron-59 Cesium-136 Chromium-51 Zinc-65 Iron-55 Molybdenum-99 4.
Tritiums Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 2.48E-05
~I
~I
~I 1.19E-04
~I
~I
~I
~I 11
~I
~I
~I
~I
~I
~I
~I
~I 1.78E+00 2.53E-04 2.83E-05 I~
~I 6.03E<<05
~I
~I
~I 00I~
~I
~II~
~I
~I
~I 1.68E-04
~I 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.
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.
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.
ATTACHMENT4 Unit 1 X
CONTINUOUS MODE                   BATCH MODE 1>>           gal             1             pe QUARTER     QUARTER        QUARTER        QUARTER Nuclides Released
Unit 2 Reporting Period Januar
: 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.
- June 199 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES There were no releases via the emergency condenser vent operation.
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
Only leakage froin the vents results in an assumed release based on the concentrations In the condensate storage tanks and condenser shell.
: 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
CONTINUOUS MODE BATCH MODE Nuclides Released 1>>
'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.
QUARTER gal QUARTER 1
QUARTER pe QUARTER
: 1. Fission Gases'rgon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-133 Xenon-133m Xenon-135 Xenon-135m Xenon-137 Xenon-138 Xenon-127 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci
~ 0
~ 0
~ 0
~ 4
~ 0
~ 0
~ 0 0 ~
OO
~ 0
~t
~ 0
~ 0
~ s
~ 0 0 ~
9.53E-02
~ s
~ s
~ 0 0 ~
~ 0 0 ~
No Releases No Releases No Releases No Releases No Releasee No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases 2.
Iodines'odine-131 Iodine-133 Iodine-135 Ci Ci Ci
~ 0
~ 0 OO
~ 0
~ 0
~ 0 No Releases No Releases No Releases No Releases No Releases No Releases 3.
Particulates'trontium-89 Strontium-90 Cesium-134 Cesium-137 Cobalt-60 Cobalt-59 Manganese-54 Barium-Lanthanum-140 Antimony-125 Niobium-95 Cerium-141 Cerium-144 Iron-59 Cesium-136 Chromium-51 Zinc-65 Iron-55 Molybdenum-99 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci OO
~ 0
~ 0
~ 0
~ 0
~ 0
~ 0
~ 0
~ 0
~ 0
~ 0
~ 0
~ 0
~ 0
~ 0 7.16E-07 8.95E-OS
~ 0 1.79E-07 2.61E-06
~ 0 2.52E-07
~ 0
~ 0
~ 0
~ 0
~ 0
~t
~ 0
~t
~ s 1.08E-06 4 ~
No Releasee No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releasee No Releases No Releases No Releases No Releases No Releases No Releases No Releasee 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 limitof 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
ATTACHMENT5 Page 1 of 2 Unit1 X Unit 2 Reporting Period Janus
: 1. Total release (not including Tritium, gases, alpha)             Ci      No Releases    No Releases      5.00E+01
- June 199 LIQUIDEFFLUENTS - SUMMATIONOF ALLRELEASES 1
: 2. Average diluted concentration during reporting period           /rCI/ml No Releases      No Releases B. Tritium
2~
: 1. Total release                                                   Ci      No Releases    No Releases      5.00E+01
EST. TOTAL QUARTER QUARTER
: 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
~ERROR A.
: 2. Average diluted concentration during reporting period           yCI/ml No Releases       No Releases D. Gross Al ha Radioac'tlvi't
Fission SI Activation Products 1.
: 1. Total release                                                   Ci     'o Releases     No Releases     5.00E+01 E. Volumes
Total release (not including Tritium, gases, alpha) 2.
: 1. Prior to dilution                                               Liters  No Releases    No Releases      5.00E+01
Average diluted concentration during reporting period B.
: 2. Volume of dilution water used during release period             Liters  No Releases    No Releases      5.00E+01
Tritium 1.
: 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
Total release 2.
Average diluted concentration during reporting period Ci
/rCI/ml Ci yCI/ml No Releases No Releases No Releases No Reieasea No Releases No Releases No Releases No Releases 5.00E+01 5.00E+01 C.
Dissolved and Entrained Gases 1 ~
Total release 2.
Average diluted concentration during reporting period Ci yCI/ml No Releases No Releases No Releases No Releases 5.00E+01 D.
Gross Al ha Radioac'tlvi't 1.
Total release Ci
'o Releases No Releases 5.00E+01 E.
Volumes 1.
Prior to dilution 2.
Volume of dilution water used during release period 3.
Volume of dilution water available during reporting period Liters Liters Liters No Releases No Releases 1.29E+ 11 No Releases No Releases 1.29E+ 11 5.00E+01 5.00E+01 5.00E+01 F.
Percent of Technical S ecification Limits Percent of Quarterly Whole Body Dose Limit(1.5 mrem)
Percent of Quarterly Organ Dose Limit (5 mrem)
Percent of Annual Whole Body Dose Umit to Data (3 mrem)
Percent of Annual Organ Dose Limitto Date (10 mrem)
Percent of 10CFR20 Concentration Umit Percent of Dissolved or Entrained Noble Gas Umit (2.00E-04/rCI/ml) 0/
0/
No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases 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
ATTACHMENT5 Page 2 of 2 Unit 1 X
Unit 2 LIQUIDEFFLUENTS RELEASED Reporting Period Janus
- June 199 BATCH MODE Nuclides Released 1"
QUARTER gal QUARTER Strontium-89 Strontium-90 Cesium-134 Cesium-137 Iodine-131 Ci Ci Ci Ci Ci No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases Cobalt-58 Cobalt-60 Iron-59 Zinc-65 Manganese-54 Chromium-51 Ci Ci Ci Ci Ci Ci No Releases No Releases No Releases No Releases No Releases No Releases No Releasee No Releases No Releases No Releases No Releases No Releases Zirconium-Niobium-95 Molybdenum-99 Technetium-99m Barium-Lanthanum-140 Cerium-141 Ci Ci Ci Ci Ci No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases Tungsten-187 Arsenic-76 Iodine-133 Iron-55 Neptunium-239 Praseodymium-144 Iodine-135 Ci Ci Ci Ci Ci Ci Ci No Relenses No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases Dissolved or Entrained Gases Tritium Ci Ci No Releases No Releases 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)
ATTACHMENT6 Page 1 of 6 Unit 1 X
Class                                   Class 1.75E+ 01   1.29E+ 01       0       3.25E+ 01       1.58E+ 02             0
Unit 2 A.1 TYPE SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS Volume (me)
: 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
Reporting Period Janua
: 2.     Dry Compressible Waste, Dry     5.03E+ 00       0         0       1.51E+00             0               0 Non-Compressible Waste (Contaminated Equipment)
- June 199
: 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%.
~Activit
'Ci)
Class Class 1.
Spent Resin 1.75E+ 01 1.29E+ 01 0
3.25E+ 01 1.58E+ 02 0
Filter Sludge 4.84E+ 00 1.03E+ 01 0
1.68E+01 9.67E+ 01 0
Concentrated Waste Evaporator Bottoms 0
0 0
0 0
0 Total 2.23E+ 01 2.325+ 01 0
4.93E+ 01 2.55E+ 02 0
2.
Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) 5.03E+ 00 0
0 1.51E+00 0
0 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
ATTACHMENT6 Page 2 of 6 Unit 1 X
: 2. Dry Compressible Waste,                                     Steel-Liner      ~TP    A          None Dry Non-Compressible Waste (Contaminated Equipment)
Unit 2 Reporting Period Janus
: 3. Irradiated Components                                       Steel-Liner           ee           None
- June 1994 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A.1 TYPE Container
~Packa e
Solidification
~Aae Spent Resin Filter Sludge Concentrated Waste 2.
Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) 3.
Irradiated Components HIC HIC
~NA Steel-Liner Steel-Liner
~TA
~TA
~NA
~TP A ee None Cement
~NA None 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)
ATTACHMENT6 Page 3 Of 6 Unit1 X Unit 2 Reporting Period Januar
: e. Spent Resins, Filter Sludges, Concentrated Waste:
- June 199 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A.2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE) e.
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
Spent Resins, Filter Sludges, Concentrated Waste:
: b. Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment):
Nuclide Percent (1)
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
(2)
: c. Irradiated Components:
(3)
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
(4)
: d. Other:   There were no shipments.
(5)
Nuclide                                               Percent
(6)
(7)
Co-60 Cs-137 Fe-55 Mn-54 Cs-134 Fe-59 Other 5.27E+01 1.71E+01 1.13E+01 9.79E+00 4.05E+00 1.47E+00 3.59E+00 b.
Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment):
Nuclide Percent (1)
(2)
(3)
(4)
(5)
(6)
(7)
(8)
Co-60 Mn-54 Cr-51 Cs-137 Fe-55 Fe-59 Co-58 Other 5.32E+01 1.80E+01 1.10E+01 1.05E+01 2.05E+00 1.94E+00 1.91E+00 1 AOE+00 c.
Irradiated Components:
Nuclide Percent (1)
(2)
(3)
(4)
(5)
Fe-55 Co-60 Mn-54 Ni-63 Other 5.12E+01 3.98E+01 6.61E+00 2.39E+00 (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)
ATTACHMENT6 Page 4 of 6 Unit1 X Unit 2 A.3.
SOLID WASTE DISPOSITION Reporting Period Janus
- June 199 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS Number of Shi ments Mode of Trans ortation Destination 13 Truck B
wlSB B.
IRRADIATEDFUEL SHIPMENTS (DISPOSITION)
There were no shipments.
There were no shipments.
Number of Shi ments               Mode of Trans ortation                 Destination 0                               ~NA                               ~NA
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.,
ATTACHIVIENT6 Page 5 of 6 Unit 1 X
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.
Unit 2 Reporting Period Janus
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
- June 1994 SOLID WASTE AND IRRADIATEDFUEL 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.,
                                                                                  ~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       =
ALARON, AMERICANECOLOGY 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.
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 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
~nd Activity
~CI Est. Total
~gr r 2.06E+01 1.49E-01 5.00+01 C.2.
ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent (1)
(2)
(3)
(4)
(5)
(6)
(7)
Co-60 Cs-137 Mn-54 Cr-51 Co-58 Fe-59 Other 6.14E+01 1.93E+01 9.10E+00 4.53E+00 2.89E+00 1.45E+00 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.
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.
ATTACHMENT6 Page 6 of 6 Unit 1 X
D.1. TYPE OF WASTE Activity
Unit 2 Reporting Period Janus
                                                    ~LVolume Burial
- June 1994 SOUD WASTE AND IRRADIATEDFUEL SHIPMENTS D. SEWAGE WASTES SHIPPED TO A TREATMENTFACILITYFOR 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.
                                                                            ~CI Sewage Sludge       There were no shipments with detectable quantities of plant-related nuclides.
D.1. TYPE OF WASTE Burial Volume
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.
~L Activity
~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 Co-60 Percent 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
I 0


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


==SUMMARY==
==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.
OF CHANGES TO THE OFFeSITE DOSE CALCULATIONMANUAL There was one revision to the Unit 1 ODCM during the reporting period.
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).
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
ATTACHMENT8 Unit 1 X
Unit2 Reporting Period Janus
- June 1994


==SUMMARY==
==SUMMARY==
OF CHANGES TO THE PROCESS CONTROL PROGRAM There were no changes to the Process Control Program during the reporting period.
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
ATTACHMENT9 Unit 1 X
Unit 2 Monitor


==SUMMARY==
==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.
OF INOPERABLE MONITORS Dates of Inoperability Reporting Period Januer
- June 1994 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
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.
Unit 1 X
GASEOUS                                    LIQUID 4 QUARTER                                  4 QUARTER
Unit 2 Reporting Period Janus
                                                          ~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
- June 199 UPDATE OF RELEASE AND DOSE DATAFOR GASEOUS (ELEVATEDAND 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.
: 1. Particulates with                   Ci                3.69E-05                  ~NA half-lives >8 days
Particulatos Tritium Nuclide'r-89 Sr-90 H-3 Fe-55 1.
: 2. Average release rate             yCI/sec               4.64E- 06                 ~NA for period Tritium
Particulates with half-lives >8 days 2.
: 1. Total release                       Ci                6.15E+00                  ~NA
Average release rate for period GASEOUS 4
: 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
QUARTER
: 1. Percent of Quarterly                                   2.40E-03                  ~NA Dose Limit                                             (Quarterly)            (Quarterly)
~Aadvit Ci 2.28E-05 6.15E+ 00 1.41E-05 Ci yCI/sec LIQUID 4
: 2. Percent of Annual                                     9.92E-01                  ~NA Dose Umit to Dates                                       (Annual)              (Annual)
QUARTER LIQUID
: 3. Percent of Organ                                       4.75E-05                  ~NA
~NA
                                  - Doss Rate Limit                                     (Quarterly)            (Quarterly)
~NA
(Gaseous)(Quarterly)                                       ~NA                    ~NA
~AGCvlt Ci No Releases No Releases No Releases No Releasee GASEOUS 3.69E-05 4.64E- 06 Tritium lodines and Particulates with half-lives rester than 8 da s
                                  - Dose Limit (Uquid)                                    (Annual)              (Annual)
: 1. Total release 2.
(Annual & Quarterly)
Average release rate for period Ci
: 4. Percent of 10CFR20                                         ~NA                    ~NA Concentration Umit (Liquid)
/ICI/soc 6.15E+00 7.73E-01 GASEOUS
: 5. Percent of Dissolved                                       N/A or Entrained Noble Gas (Uquid)
~NA
Concentrations loss than the lower limit of detection, as required by Technical Specifications are indicated with a doublo asterisk.
~NA LIQUID 1.
Percent of Quarterly Dose Limit 2.
Percent of Annual Dose Umit to Dates 3.
Percent of Organ
- Doss Rate Limit (Gaseous)(Quarterly)
- Dose Limit (Uquid)
(Annual & Quarterly) 4.
Percent of 10CFR20 Concentration Umit (Liquid) 5.
Percent of Dissolved or Entrained Noble Gas (Uquid) 2.40E-03 (Quarterly) 9.92E-01 (Annual) 4.75E-05 (Quarterly)
~NA (Annual)
~NA N/A
~NA (Quarterly)
~NA (Annual)
~NA (Quarterly)
~NA (Annual)
~NA Concentrations loss than the lower limitof detection, as required by Technical Specifications are indicated with a doublo asterisk.
The dose is to the maximally exposed organ for gaseous offluents.
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
0
                                                        ~(m   )                                             (Ci)
 
Class                                           Class
ATTACHMENT61 Page 1 Of 6 Unit 1 X Unit 2 Reporting Period Jul
: 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
- December 199 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A.1 TYPE Volume
: 2. Dry Compressible Waste, Dry               0              0              0              0                  0                0 Non-Compressible Waste (Contaminated Equipment)
~(m )
There were no irradiated components shipped for burial during the reporting period.
~Act vll (Ci)
: 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.
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 Bottoms Total 0
1.13E+01 0
0 0
0 0
2.01E+ 01 0
0 0
0 2.
Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) 0 0
0 0
0 0
3.
Irradiated Components There were no irradiated components shipped for burial during the reporting period.
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%.
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
ATlACHMENT6'age 2of 6 Unit 1 X
: 2.     Dry Compressible Waste,                                                 ~NA              NIA              ~NA Dry Non-Compressible Waste (Contaminated Equipment)
Unit 2 Reporting Period Jul
: 3.     Irradiated Components                                                   ~NA             ~NA               ~NA
- December 1993 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A.1 TYPE Container
'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.
~Peeke e
Solidification
~Acne Spent Resin Filter Sludge Concentrated Waste 2.
Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) 3.
Irradiated Components HIC HIC
~NA
~NA
~NA
~Te A
~TA N/A NIA
~NA None Cement NIA
~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)
ATTACHMENT61 Page 3 of 6 Unit1 X
: a. Spent Resins, Filter Sludges, Concentrated Waste:
Unit 2 Reporting Period Jul
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
- December 199 SOUD WASTE AND IRRADIATEDFUEL SHIPMENTS A.2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE) a.
: b. Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment): There were no shipments.
Spent Resins, Filter Sludges, Concentrated Waste:
Nuclide                                                       Percent
Nuclide Percent (1)
: c. Irradiated Components:     There were no shipments.
(2)
Nuclide                                                       Percent
(3)
: d. Other:   There were no shipments.
(4)
Nuclide                                                       Percent
(5)
'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.
(6)
Co.60 Cs-137 Fe-55 Mn-54 Cs-134 Other 3.55E+01 3.07E+01 2.27E+01 6.54E+00 2.89E+00 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):
ATTACHMENT6'age 4 of 6 Unit 1 X
Unit 2 Reporting Period Jul
- December 1993 SOUD WASTE AND IRRADIATEDFUEL SHIPMENTS A.3.
SOLID WASTE DISPOSITION Number of Shi ments Mode of Trans ortatlon ruck Destinatlon Bemwee BC B.
IRRADIATEDFUEL SHIPMENTS (DISPOSITION):
There were no shipments.
There were no shipments.
Number of Shi ments                       Mode of Trans ortation                       Destination 0                                      ~NA                                     NIA
Number of Shi ments 0
~
Mode of Trans ortation
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.
~NA Destination 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


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.,
ATTACHNIENT61 Page 5 of 6 Unit 1 X
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.
Unit 2 Reporting Period Jul
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.
- December 199 SOUD WASTE AND IRRADIATEDFUEL 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 processing prior to burial at Barnwell, SC Burial Volume
~mr 2.33E+ 01 Activity
~CI 5.94E-01 Est. Total
~Error 5.00+ 01 C.2.
ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent (1)
Co-60 (2)
Cs-137 (3)
Mn-54 (4)
Co-58 (5)
Fe-55 (6)
Fe-59 (7)
Other 6.17E+01 2.09E+01 8.09E+00 4.20E+00 1.83E+00 1.58E+00 1.65E+00 C 3 SOLID WASTE DISPOSITIONs Number of Shi ments 32 Mode of Trans ortation Truck Destination 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.
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.
ATTACHMENT61 Page 6 of 6 Unit 1 X
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.
Unit 2 Reporting Period Jul
- December 199 SOUD WASTE AND IRRADIATEDFUEL SHIPMENTS D.
SEWAGE SLUDGE SHIPPED TO A TREATMENTFACILITYCENTER 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


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 )(
ATTACHMENT6 Page 1 of 6 Unit 1 X
                                                            ~(m  )                                          (Ci)
Unit 2 A.1 TYPE SOUD WASTE AND IRRADIATEDFUEL SHIPMENTS Volume
Class                                         Class
~(m )
: 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
Reporting Period Janus
: 2. Dry Compressible Waste, Dry Non-Compressible Waste i . 44 4 4 4 01       0             0           4.06E+ 00           0                 0 (Contaminated Equipment)
- June 199
~Activi )(
(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 Bottoms 0
.10E+01 0
0 3.06E+ 01 0
Total 4.79E+ 01 2.75E+ 01 0
3.50E+ 02 2.58E+ 02 0
2.
Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment)
: i. 44 444 4 01 0
0 4.06E+ 00 0
0 3.
Irradiated Components 0
0 0
0 0
There were no irradiated components shipped for burial during the reporting period.
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.
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%.
The estimated total error is 5.00E+01%.


Unit 1   X     Unit 2 ATTACHMENT          6'age          Reporting Period Janus 2of 6
ATTACHMENT6'age 2of 6 Unit 1 X
                                                                                                                - June 1993 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A.l   TYPE                                                                                                 Solidification Container         ~Peeke e     ~eeet
Unit 2 Reporting Period Janus
: 1. Spent Resin                                                             HIC            ~TA                None Filter Sludge                                                           HIC            ~T* A            Cement Concentrated Waste                                                     HIC            ~T* A            Cement
- June 1993 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A.l TYPE Container
: 2. Dry Compressible Waste,                                             Steel. Liner      ~TA                None Dry Non-Compressible Waste (Contaminated Equipment)
~Peeke e
: 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.
Solidification
~eeet 1.
Spent Resin Filter Sludge Concentrated Waste 2.
Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) 3.
Irradiated Components HIC HIC HIC Steel. Liner
~TA
~T*A
~T*A
~TA
~NA None Cement Cement None
~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)
ATTACHMENT61 Page30f 6 Unit 1 X
: a. Spent Resins, Filter Sludges, Concentrated Waste:
Unit 2 Reporting Period Janus
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
- June 199 SOUD WASTE AND IRRADIATEDFUEL SHIPMENTS A.2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION {BYTYPE OF WASTE) a.
: b. Dry Compressible Waste, Dry Non-Compressible Waste {Contamlnated Equipment):
Spent Resins, Filter Sludges, Concentrated Waste:
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
Nuclide Percent (1)
: c. Irradiated Components:   There were no shipments.
(2)
Nuclide                                                       Percent
(3)
: d. Other:   There were no shipments.
(4)
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.
(5)
(6)
Co-60 Fe-55 Mn-54 Cs-137 Co-58 Other 6.22E+01 1.41E+01 1.17E+01 8.24E+00 1.08E+00 2.68E+00 b.
Dry Compressible Waste, Dry Non-Compressible Waste {Co Nuclide ntamlnated Equipment):
Percent (1)
(2)
(3)
(4)
(5)
(6)
(7)
Co-60 Cs-137 Mn-54 Co-58 Fe-59 Fe-55 Other 5.31E+01 2.47E+01 1.14E+01 6.10E+00 1.76E+00
'1.12E+00 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):
ATTACHMENT6'age 4 of 6 Unit 1 X
Unit 2 Reporting Period Janus
- June 1993 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A.3.
SOLID WASTE DISPOSITION Number of Shl ments 17 Mode of Trans ortation Truck Destination Berewee BB B.
IRRADIATEDFUEL SHIPMENTS (DISPOSITION):
There were no shipments.
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.
Number of Shi ments 0
Mode of Trans ortation N/A Destination
~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.,
ATTACHIVIENT61 Page 5 of 6 Unit 1 X
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.
Unit 2 Reporting Period Januar
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.
- June 199 SOLID WASTE AND IRRADIATEDFUEL 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 processing prior to burial at Barnwell, SC Burial Volume
~mo Activity
~CI Est. Total
~Error 1.92E+01 2.71E-01 5.00+01 C.2.
ESTIMATE OF MAJOR NUCLIDE COMPOSITION (1)
(2)
(3)
(4)
(5)
(6)
Nuclide Co-60 Cs-137 Mn-54 Co-58 Fe-59 Other Percent 5.98E+01 2.27E+01 9.54E+00 5.10E+00 1.88E+00 9.34E -01 C.3.
SOLID WASTE DISPOSITION2 Number of Shi ments 29 Mode of Trans ortation Truck Destination 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.
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
ATTACHMENT6'age 6 of 6 Unit 1 X
                                                                                                                - 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.
Unit 2 Reporting Period Janus
D.1. TYPE OF WASTE Burial Volume                     Activity
- June 1993 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS D. SEWAGE SLUDGE SHIPPED TO A TREATMENTFACILITYCENTER 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.
                                          ~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.
D.1. TYPE OF WASTE sewage sludge Burial Volume
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.
~L 3.03E+04 Activity
~CI 2.4E-07 D.2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Co.60 Percent 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}}
OFF-SITE DOSE CALCULATIONMANUAL Revision 13 and 14 enclosed per Attachment 7 of the Semi-Annual Radioactive Effluent Release Report}}

Latest revision as of 11:58, 9 January 2025

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


Text

NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY - JUNE 1994 NIAGARAMOHAWKPOWER CORPORA TION 9e0902022<

9eOS25 PDR ADOCK 05000220

.R PDR

0-

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

~Focttit:

Nine Mile Point Unit¹t Lichens:

Niagara Mohawk Power Corporation TECHNICALSPECIFICATION LIMITS A)

FISSION AND ACTIVATIONGASES 1.

The dose rate limitof 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, HALFLIVES ) 8 DAYS 1.

The dose rate limitof 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)

LIQUIDEFFLUENTS 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 of2 MEASUREMENTS AND APPROXIMATIONSOF TOTALRADIOACTIVITY 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 Activityreleased 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 ofTritium 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)

LIQUIDEFFLUENTS Isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters.

F)

SOLID EFFLUENTS Isotopic contents of waste shipments are determined by gamma spectroscopy, gross alpha and water content 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.

S

~

ATTACHMENT1 Summary Data Page 1 of 2 Unit 1 X

Unit2 Liquid Effluents:

Reporting Period Janus

- June 199 10CFR20, Appendix B, Table II, Column 2 Average MPC (Qtr. ~1 Average MPC (Qtr. ~2

~NA

~A Average Energy (Fission and Activation gases - Mev): There were no fission and activation gases detected during the first quarter 1994.

Qtr. 1 Qtr. 2 Ey

~ O.OOE+00 Ep ~

O.OOE+00 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 Total time period for batch releases (hrs) 1 8.00E+ 00 Maximum time period for a batch release (hrs)

Average time period for a batch release (hrs) 8.00E+ 00 8.00E+00 Minimum time period for a batch release (hrs) 8.00E+ 00

ATTACHMENT1 Summary Data Page 20f 2 Unit 1 X

Unit 2 Abnormal Releases:

There were no abnormal releases during the reporting period.

A.

Uquids:

Reporting Period Janus

- June 199 Number of releases 0

B.

Gaseous:

Total activity released

~NA Ci Number of releases 0

Total activity released

~NA Ci

ATTACHMENT2 Unit 1 X

Unit 2 Reporting Period Janus

- June 1994 GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES, ELEVATEDAND GROUND LEVEL 1 Et 2~

EST. TOTAL QUARTER QUARTER

~ERROR A.

Fission & Activation Gases'.

Total release 2.

Average release rate Ci pCi/sec

~ Q

~ Q 2.69E+ 00 5.00E+ 01 3.42E-01 B.

lodinest 1.

2.

Total iodine-131 Average release rate for period Ci pCi/sec

~t

~ 0 3.48E-05 3.00E+01 4.43E-06 C.

Particulates 1.

2.

3.

Particulates with half-lives )8 days Average release rate for period Gross alpha radioactivity Ci pCi/sec Ci 1 A4E-04 1.85E-05 2.82E-05 5.15E-04 3.00E+01 6.55E-05 5.09E-05 2.50E+01 D.

Tritiums 1.

Total release 2.

Average release rate for period Ci pCi/sec 5.77E+ 00 7.42E-01 1.77E+01 5.00E+01 2.25E+ 00 E.

Percent of Tech S ec Limits Fission and Activation Gases'ercent of Quarterly Gamma Air Dose Limit (5 mrem)

Percent of Quarterly Beta Air Dose Umit (10 mrem)

Percent of Annual Gamma Air Doso Umit to Date (10 mrem)

Percent of Annual Beta AirDose Umit to Date (20 mrem)

Percent of Whole Body Dose Rate Umit (500 mrem/yr)

Percent of Skin Dose Rate Umit (3000 mrem/yr)

Tritium Iodines and Particulatess with half.lives rester than 8 da s

Percent of Quarterly Dose Limit (7.5 mrem)

Percent of Annual Dose Limit (15 mrem)

Percent of Organ Dose Rate Umit (1500 mrem/yr)

~ 0

~ 0

~ 0 Q ~

~ 0

~ 0 5.60E-02 2.81E-02 1 143-03 3.48E- 03 2.71E-03 1.74E-03 1.36E-03 8.82E-05 3.37E-05 9.86E-02 7.44E-02 1.98E-03 Concentrations less than the lower limitof detection of tho counting system used are indicated with a double asterisk.

A lower limitof 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 willbe provided in tho next Semi-Annual Report.

ATTACHMENT3 Unit 1 X

Unit 2 Reporting Period Januar

- June 1994 GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODEs Nuclides Released 1.

Fission Gasest Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-127 Xenon-133 Xenon-133m Xenon-135 Xenon-135m Xenon-137 Xenon-138 2.

Iodine s~

Iodine-131 Iodine-133 ladino-135 Ci Ci Ci Ci Ci Cl Ci Ci Ci Ci Ci Ci Ci Ci Ci 1K QUARTER

~I

~I

~I

~I

~I

~I

~I

~II~

~I

~I

~I

~I

~I

~I gal QUARTER

~I 00 1.58E-01

~I 00 2.14E+ 00

~I 2.95E-01

~I

~I 3.48E-05 9.12E-04

~I 3.

Particulates

'trontium-89 Strontium-90 Cesium-134 Cesium-137 Cobalt-60 Cobalt-58 Manganese-54 Barium.Lanthanum-140 Antimony-125 Niobium-95 Cerium-141 Cerium-144 Iron-59 Cesium-136 Chromium-51 Zinc-65 Iron-55 Molybdenum-99 4.

Tritiums Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 2.48E-05

~I

~I

~I 1.19E-04

~I

~I

~I

~I 11

~I

~I

~I

~I

~I

~I

~I

~I 1.78E+00 2.53E-04 2.83E-05 I~

~I 6.03E<<05

~I

~I

~I 00I~

~I

~II~

~I

~I

~I 1.68E-04

~I 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 Nuclides Released 1>>

QUARTER gal QUARTER 1

QUARTER pe QUARTER

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

~ 0

~ 0

~ 0

~ 4

~ 0

~ 0

~ 0 0 ~

OO

~ 0

~t

~ 0

~ 0

~ s

~ 0 0 ~

9.53E-02

~ s

~ s

~ 0 0 ~

~ 0 0 ~

No Releases No Releases No Releases No Releases No Releasee No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases 2.

Iodines'odine-131 Iodine-133 Iodine-135 Ci Ci Ci

~ 0

~ 0 OO

~ 0

~ 0

~ 0 No Releases No Releases No Releases No Releases No Releases No Releases 3.

Particulates'trontium-89 Strontium-90 Cesium-134 Cesium-137 Cobalt-60 Cobalt-59 Manganese-54 Barium-Lanthanum-140 Antimony-125 Niobium-95 Cerium-141 Cerium-144 Iron-59 Cesium-136 Chromium-51 Zinc-65 Iron-55 Molybdenum-99 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci OO

~ 0

~ 0

~ 0

~ 0

~ 0

~ 0

~ 0

~ 0

~ 0

~ 0

~ 0

~ 0

~ 0

~ 0 7.16E-07 8.95E-OS

~ 0 1.79E-07 2.61E-06

~ 0 2.52E-07

~ 0

~ 0

~ 0

~ 0

~ 0

~t

~ 0

~t

~ s 1.08E-06 4 ~

No Releasee No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releasee No Releases No Releases No Releases No Releases No Releases No Releases No Releasee 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 limitof 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 LIQUIDEFFLUENTS - SUMMATIONOF ALLRELEASES 1

2~

EST. TOTAL QUARTER QUARTER

~ERROR A.

Fission SI Activation Products 1.

Total release (not including Tritium, gases, alpha) 2.

Average diluted concentration during reporting period B.

Tritium 1.

Total release 2.

Average diluted concentration during reporting period Ci

/rCI/ml Ci yCI/ml No Releases No Releases No Releases No Reieasea No Releases No Releases No Releases No Releases 5.00E+01 5.00E+01 C.

Dissolved and Entrained Gases 1 ~

Total release 2.

Average diluted concentration during reporting period Ci yCI/ml No Releases No Releases No Releases No Releases 5.00E+01 D.

Gross Al ha Radioac'tlvi't 1.

Total release Ci

'o Releases No Releases 5.00E+01 E.

Volumes 1.

Prior to dilution 2.

Volume of dilution water used during release period 3.

Volume of dilution water available during reporting period Liters Liters Liters No Releases No Releases 1.29E+ 11 No Releases No Releases 1.29E+ 11 5.00E+01 5.00E+01 5.00E+01 F.

Percent of Technical S ecification Limits Percent of Quarterly Whole Body Dose Limit(1.5 mrem)

Percent of Quarterly Organ Dose Limit (5 mrem)

Percent of Annual Whole Body Dose Umit to Data (3 mrem)

Percent of Annual Organ Dose Limitto Date (10 mrem)

Percent of 10CFR20 Concentration Umit Percent of Dissolved or Entrained Noble Gas Umit (2.00E-04/rCI/ml) 0/

0/

No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases

ATTACHMENT5 Page 2 of 2 Unit 1 X

Unit 2 LIQUIDEFFLUENTS RELEASED Reporting Period Janus

- June 199 BATCH MODE Nuclides Released 1"

QUARTER gal QUARTER Strontium-89 Strontium-90 Cesium-134 Cesium-137 Iodine-131 Ci Ci Ci Ci Ci No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases Cobalt-58 Cobalt-60 Iron-59 Zinc-65 Manganese-54 Chromium-51 Ci Ci Ci Ci Ci Ci No Releases No Releases No Releases No Releases No Releases No Releases No Releasee No Releases No Releases No Releases No Releases No Releases Zirconium-Niobium-95 Molybdenum-99 Technetium-99m Barium-Lanthanum-140 Cerium-141 Ci Ci Ci Ci Ci No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases Tungsten-187 Arsenic-76 Iodine-133 Iron-55 Neptunium-239 Praseodymium-144 Iodine-135 Ci Ci Ci Ci Ci Ci Ci No Relenses No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases Dissolved or Entrained Gases Tritium Ci Ci No Releases No Releases No Releases No Releases

ATTACHMENT6 Page 1 of 6 Unit 1 X

Unit 2 A.1 TYPE SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS Volume (me)

Reporting Period Janua

- June 199

~Activit

'Ci)

Class Class 1.

Spent Resin 1.75E+ 01 1.29E+ 01 0

3.25E+ 01 1.58E+ 02 0

Filter Sludge 4.84E+ 00 1.03E+ 01 0

1.68E+01 9.67E+ 01 0

Concentrated Waste Evaporator Bottoms 0

0 0

0 0

0 Total 2.23E+ 01 2.325+ 01 0

4.93E+ 01 2.55E+ 02 0

2.

Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) 5.03E+ 00 0

0 1.51E+00 0

0 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 IRRADIATEDFUEL SHIPMENTS A.1 TYPE Container

~Packa e

Solidification

~Aae Spent Resin Filter Sludge Concentrated Waste 2.

Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) 3.

Irradiated Components HIC HIC

~NA Steel-Liner Steel-Liner

~TA

~TA

~NA

~TP A ee None Cement

~NA None None

ATTACHMENT6 Page 3 Of 6 Unit1 X Unit 2 Reporting Period Januar

- June 199 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A.2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE) e.

Spent Resins, Filter Sludges, Concentrated Waste:

Nuclide Percent (1)

(2)

(3)

(4)

(5)

(6)

(7)

Co-60 Cs-137 Fe-55 Mn-54 Cs-134 Fe-59 Other 5.27E+01 1.71E+01 1.13E+01 9.79E+00 4.05E+00 1.47E+00 3.59E+00 b.

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

Nuclide Percent (1)

(2)

(3)

(4)

(5)

(6)

(7)

(8)

Co-60 Mn-54 Cr-51 Cs-137 Fe-55 Fe-59 Co-58 Other 5.32E+01 1.80E+01 1.10E+01 1.05E+01 2.05E+00 1.94E+00 1.91E+00 1 AOE+00 c.

Irradiated Components:

Nuclide Percent (1)

(2)

(3)

(4)

(5)

Fe-55 Co-60 Mn-54 Ni-63 Other 5.12E+01 3.98E+01 6.61E+00 2.39E+00 (1.00E+00 d.

Other:

There were no shipments.

Nuclide Percent

ATTACHMENT6 Page 4 of 6 Unit1 X Unit 2 A.3.

SOLID WASTE DISPOSITION Reporting Period Janus

- June 199 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS Number of Shi ments Mode of Trans ortation Destination 13 Truck B

wlSB B.

IRRADIATEDFUEL 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 IRRADIATEDFUEL 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, AMERICANECOLOGY 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

~nd Activity

~CI Est. Total

~gr r 2.06E+01 1.49E-01 5.00+01 C.2.

ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent (1)

(2)

(3)

(4)

(5)

(6)

(7)

Co-60 Cs-137 Mn-54 Cr-51 Co-58 Fe-59 Other 6.14E+01 1.93E+01 9.10E+00 4.53E+00 2.89E+00 1.45E+00 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 IRRADIATEDFUEL SHIPMENTS D. SEWAGE WASTES SHIPPED TO A TREATMENTFACILITYFOR 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 Burial Volume

~L Activity

~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 Co-60 Percent 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 Monitor

SUMMARY

OF INOPERABLE MONITORS Dates of Inoperability Reporting Period Januer

- June 1994 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 DATAFOR GASEOUS (ELEVATEDAND 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.

Particulatos Tritium Nuclide'r-89 Sr-90 H-3 Fe-55 1.

Particulates with half-lives >8 days 2.

Average release rate for period GASEOUS 4

QUARTER

~Aadvit Ci 2.28E-05 6.15E+ 00 1.41E-05 Ci yCI/sec LIQUID 4

QUARTER LIQUID

~NA

~NA

~AGCvlt Ci No Releases No Releases No Releases No Releasee GASEOUS 3.69E-05 4.64E- 06 Tritium lodines and Particulates with half-lives rester than 8 da s

1. Total release 2.

Average release rate for period Ci

/ICI/soc 6.15E+00 7.73E-01 GASEOUS

~NA

~NA LIQUID 1.

Percent of Quarterly Dose Limit 2.

Percent of Annual Dose Umit to Dates 3.

Percent of Organ

- Doss Rate Limit (Gaseous)(Quarterly)

- Dose Limit (Uquid)

(Annual & Quarterly) 4.

Percent of 10CFR20 Concentration Umit (Liquid) 5.

Percent of Dissolved or Entrained Noble Gas (Uquid) 2.40E-03 (Quarterly) 9.92E-01 (Annual) 4.75E-05 (Quarterly)

~NA (Annual)

~NA N/A

~NA (Quarterly)

~NA (Annual)

~NA (Quarterly)

~NA (Annual)

~NA Concentrations loss than the lower limitof 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 IRRADIATEDFUEL SHIPMENTS A.1 TYPE Volume

~(m )

~Act vll (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 Bottoms Total 0

1.13E+01 0

0 0

0 0

2.01E+ 01 0

0 0

0 2.

Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) 0 0

0 0

0 0

3.

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

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%.

ATlACHMENT6'age 2of 6 Unit 1 X

Unit 2 Reporting Period Jul

- December 1993 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A.1 TYPE Container

~Peeke e

Solidification

~Acne Spent Resin Filter Sludge Concentrated Waste 2.

Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) 3.

Irradiated Components HIC HIC

~NA

~NA

~NA

~Te A

~TA N/A NIA

~NA None Cement NIA

~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 IRRADIATEDFUEL SHIPMENTS A.2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE) a.

Spent Resins, Filter Sludges, Concentrated Waste:

Nuclide Percent (1)

(2)

(3)

(4)

(5)

(6)

Co.60 Cs-137 Fe-55 Mn-54 Cs-134 Other 3.55E+01 3.07E+01 2.27E+01 6.54E+00 2.89E+00 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.

ATTACHMENT6'age 4 of 6 Unit 1 X

Unit 2 Reporting Period Jul

- December 1993 SOUD WASTE AND IRRADIATEDFUEL SHIPMENTS A.3.

SOLID WASTE DISPOSITION Number of Shi ments Mode of Trans ortatlon ruck Destinatlon Bemwee BC B.

IRRADIATEDFUEL SHIPMENTS (DISPOSITION):

There were no shipments.

Number of Shi ments 0

Mode of Trans ortation

~NA Destination 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 IRRADIATEDFUEL 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 processing prior to burial at Barnwell, SC Burial Volume

~mr 2.33E+ 01 Activity

~CI 5.94E-01 Est. Total

~Error 5.00+ 01 C.2.

ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent (1)

Co-60 (2)

Cs-137 (3)

Mn-54 (4)

Co-58 (5)

Fe-55 (6)

Fe-59 (7)

Other 6.17E+01 2.09E+01 8.09E+00 4.20E+00 1.83E+00 1.58E+00 1.65E+00 C 3 SOLID WASTE DISPOSITIONs Number of Shi ments 32 Mode of Trans ortation Truck Destination 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 IRRADIATEDFUEL SHIPMENTS D.

SEWAGE SLUDGE SHIPPED TO A TREATMENTFACILITYCENTER 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 A.1 TYPE SOUD WASTE AND IRRADIATEDFUEL SHIPMENTS Volume

~(m )

Reporting Period Janus

- June 199

~Activi )(

(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 Bottoms 0

.10E+01 0

0 3.06E+ 01 0

Total 4.79E+ 01 2.75E+ 01 0

3.50E+ 02 2.58E+ 02 0

2.

Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment)

i. 44 444 4 01 0

0 4.06E+ 00 0

0 3.

Irradiated Components 0

0 0

0 0

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

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%.

ATTACHMENT6'age 2of 6 Unit 1 X

Unit 2 Reporting Period Janus

- June 1993 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A.l TYPE Container

~Peeke e

Solidification

~eeet 1.

Spent Resin Filter Sludge Concentrated Waste 2.

Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) 3.

Irradiated Components HIC HIC HIC Steel. Liner

~TA

~T*A

~T*A

~TA

~NA None Cement Cement None

~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)

(2)

(3)

(4)

(5)

(6)

Co-60 Fe-55 Mn-54 Cs-137 Co-58 Other 6.22E+01 1.41E+01 1.17E+01 8.24E+00 1.08E+00 2.68E+00 b.

Dry Compressible Waste, Dry Non-Compressible Waste {Co Nuclide ntamlnated Equipment):

Percent (1)

(2)

(3)

(4)

(5)

(6)

(7)

Co-60 Cs-137 Mn-54 Co-58 Fe-59 Fe-55 Other 5.31E+01 2.47E+01 1.14E+01 6.10E+00 1.76E+00

'1.12E+00 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.

ATTACHMENT6'age 4 of 6 Unit 1 X

Unit 2 Reporting Period Janus

- June 1993 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A.3.

SOLID WASTE DISPOSITION Number of Shl ments 17 Mode of Trans ortation Truck Destination Berewee BB B.

IRRADIATEDFUEL SHIPMENTS (DISPOSITION):

There were no shipments.

Number of Shi ments 0

Mode of Trans ortation N/A Destination

~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 IRRADIATEDFUEL 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 processing prior to burial at Barnwell, SC Burial Volume

~mo Activity

~CI Est. Total

~Error 1.92E+01 2.71E-01 5.00+01 C.2.

ESTIMATE OF MAJOR NUCLIDE COMPOSITION (1)

(2)

(3)

(4)

(5)

(6)

Nuclide Co-60 Cs-137 Mn-54 Co-58 Fe-59 Other Percent 5.98E+01 2.27E+01 9.54E+00 5.10E+00 1.88E+00 9.34E -01 C.3.

SOLID WASTE DISPOSITION2 Number of Shi ments 29 Mode of Trans ortation Truck Destination 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.

ATTACHMENT6'age 6 of 6 Unit 1 X

Unit 2 Reporting Period Janus

- June 1993 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS D. SEWAGE SLUDGE SHIPPED TO A TREATMENTFACILITYCENTER 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 sewage sludge Burial Volume

~L 3.03E+04 Activity

~CI 2.4E-07 D.2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Co.60 Percent 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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