ML022820175

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January - June 2002 Radioactive Effluent Release Report for Nine Mile Point, Unit 2
ML022820175
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 09/26/2002
From: Montgomery B
Constellation Generation Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NMPE 0334
Download: ML022820175 (25)
v • d • e


Text

  • "

P.O. Box 63 "Lycoming, New York 13093 I Constellation Generation Group Nine Mile Point Nuclear Station September 26, 2002 NMPE 0334 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE:

Nine Mile Point Unit 2 Docket No. 50-410 NPF-69

Subject:

January - June 2002 Radioactive Effluent Release Report Gentlemen:

In conformance with the Nine Mile Point Unit 2 (NMP2) Technical Specifications, enclosed is the Radioactive Effluent Release Report for the period January through June 2002. Included in this report is a summary of gaseous, liquid and solid effluents released from the station during the reporting period (Attachments 1 through 6), a summary of any revisions to the Offsite Dose Calculation Manual and the Process Control Program during the reporting period (Attachments 7 and 8), and an explanation as to the cause and corrective actions regarding the inoperability of any station liquid and/or gaseous effluent monitoring instrumentation (Attachment 9). 0 to this report provides an update of actual data for the last quarter of the preceding report period. Attachment 11 to this report provides a correction to the calculated whole body dose and skin dose to a member of the public due to shoreline recreational activities located outside the site boundary reported in the previous report period.

The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1. Dose assessments were made in accordance with the NMP2 Offsite Dose Calculation Manual. Distribution is in accordance with 10CFR50.4(b)(1).

During the reporting period from January-June 2002, NMP2 did not exceed any 10CFR20, IOCFR50, or Offsite Dose Calculation Manual limits for gaseous or liquid effluents.

zz~~1-w/

Page 2 NMPE 0334 If you have any questions concerning the attached report, please contact Mr. Anthony M.

Salvagno at (315) 349-1456.

Very truly yours, c

on mery Gae rNucle Engineering BSM/CW/jm Enclosures

Page 3 NMPE 0334 cc:

Mr. H. J. Miller, Regional Administrator, Region I Mr. G. K. Hunegs, NRC Senior Resident Inspector, Region 1 Mr. P. S. Tam, Senior Project Manager, NRR (2 copies)

NINE MILE POINT NUCLEAR STATION -

RADIOACTIVE EFFLUENT RELEASE REPORT January-June 2002 Constellation Generation Group Nine Mile Point Nuclear Station A M4embero f the constafiatoin Et'stgy Group

(

UNIT 2

Page 1 of 2 NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 2002 SUPPLEMENTAL INFORMATION Facility:

Nine Mile Point Unit 2 Licensee:

Nine Mile Point Nuclear Station, LLC

1. TECHNICAL SPECIFICATION PROGRAM - (ODCM Limits - Radioactive Effluent Controls Program)

A)

FISSION AND ACTIVATION GASES

1.

The dose rate limit of noble gases released in gaseous effluents from the site to areas at or beyond the site boundary shall be less than or equal to 500 mrem/year to the whole body and less than or equal to 3000 mrem/year to the skin.

2.

The air dose from noble gases released in gaseous effluents from Nine Mile Point Unit 2 to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and during any calendar year to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad 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 in gaseous effluents from the site to areas at or beyond the site boundary shall be less than or equal to 1500 mrem/year to any organ.

2.

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

D)

LIQUID EFFLUENTS

1.

The concentration of radioactive material released in the liquid effluents to unrestricted areas shall be limited to ten times the concentrations specified in 10CFR Part 20.1001-20.2402, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 microcuries/mi total activity.

Page 2 of 2

2.

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

2.

MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents.

A)

FISSION AND ACTIVATION GASES Noble gas effluent activity is determined by on-line gamma spectroscopic monitoring of an isokinetic sample stream.

B)

IODINES Iodine effluent activity is determined by gamma spectroscopic analysis once every seven days of charcoal cartridges sampled from an isokinetic sample stream.

C)

PARTICULATES Activity released from the main stack and the combined Radwaste/Reactor Building vent is determined by gamma spectroscopic analysis once every seven days of particulate filters sampled from an isokinetic sample stream and composite analysis of the filters for non-gamma emitters.

D)

TRITIUM Tritium effluent activity is measured by liquid scintillation or gas proportional counting of samples taken once every 31 days with an air sparging/water trap apparatus.

E)

LIQUID EFFLUENTS Isotopic contents of liquid effluents are determined by isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters.

F)

SOLID EFFLUENTS Isotopic contents of waste shipments are determined by gamma spectroscopy 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.

ATTACHMENT 1 Summary Data Page 1 of 2 Unit 1 Unit 2 X

Reporting Period January - June 2002 Liquid Effluents:

10CFR20.1001-20.2402, Appendix B, Table 2, Column 21 Average MEC - lICi/ml (Qtr. 1) = 5.76E-03 Average MEC - jCXiml (Qtr. 3) = N/A Average MEC - iCi/ml (Qtr. 2) = 3.34E-03 Average MEC - +/-CI/ml (Qtr. 4) = N/A Average Energy (Fission and Activation gases - Mev):

Qtr. 1:

Ey

= 4.27E-01 Pp = 2.79E-01 Qtr. 2:

ty

= 5.45E-01 p

= 3.93E-01 Qtr.3:

3y

=

N/A

]

=

N/A Qtr. 4 :t

=

NIA P

=

N/A Liquid:

Number of batch releases 35 Total time period for batch releases (hrs) 1.14E+02 Maximum time period for a batch release (hrs) 3.33E+00 Average time period for a batch release (hrs) 3.25E+00 Minimum time period for a batch release (hrs) 3.15E+00 Total volume of water used to dilute the liquid effluent during the release ill 2._d 3_.d 4 th period (L) 2.42E+08 4.27E+08 NIA N/A Total volume of water used to dilute the liquid effluent during reporting lt 2nd 3rd 4_th Period (LM 1.13E+10 1.32E+10 NIA N/A Gaseous (Emergency Condenser Vent): "Not Applicable for Unit 2*

Number of batch releases N/A Total time period for batch releases (hrs)

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

N/A Average time period for a batch release (hrs)

NIA Minimum time period for a batch release (hrs)

NIA Gaseous (Primary Containment Purge):

Number of batch releases 8

Total time period for batch releases (hrs) 2.58E+02 Maximum time period for a batch release (hrs) 1.08E+02 Average time period for a batch release (hrs) 3.22E+01 Minimum time period for a batch release (hrs) 4.67E+00

¶ Improved Technical Specifications limit the concentration of radioactive material released in the liquid effluents to unrestricted areas to ten times the concentrations specified in 10CFR20.1001-20.2402, Appendix B, Table 2, Column 2.

Maximum Effluent Concentrations (MEC) numerically equal to ten times the 10CFR20.1001-20.2402 concentrations were adopted to evaluate liquid effluents.

ATTACHMENT,1 Summary Data Page 2 of 2 Unit 1 -

Unit 2 X

Reporting Period January - June 2002 Abnormal Releases: There were no abnormal releases during this report period.

A.

Liquids:

Number of releases 0

Total activity released N/A Ci B.

Gaseous:

Number of releases 0

Total activity released N/A Ci

V ATTACHMENT 2 Page 1 of 1 Unit 1 Unit 2 X

° -

Reporting Period January - June 2002 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL 1st 2nd 3rd 4th EST.

QUARTER QUARTER QUARTER QUARTE TOTAL R

ERROR, %

A.

Fission & Activation gases

1.

Total release

2.

Average release rate B.

lodines

1.

Total Iodine-131

2.

Average release rate for period C.

Particulates 1

1.

Particulates with half-lives >8 days

2.

Average release rate for period

3.

Gross alpha radioactivity D.

Tritium 1

1.

Total release

2.

Average release rate for period E.

Percent of Tech. Spec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose Limit (5 mR)

Percent of Quarterly Beta Air Dose Limit (10 mrad)

Percent of Annual Gamma Air Dose Limit to Date (10 mR)

Percent of Annual Beta Air Dose Limit to Date (20 mrad)

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

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

Tritium, lodines, and Particulates 1 (with half-lives greater than 8 days)

Percent of Quarterly Dose Limit (7.5 mrem)

Percent of Annual Dose Limit (15 mrem)

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

Cl

/iCi/sec Ci jsCilsec Ci juCi/sec Ci Ci juCi/sec 2.34E + 00 3.02E-01 1.29E+00 1.64E-01 NA NA NA NA 1.69E-04 3.31E-06 NA NA 2.15E-05 4.21E-07 NA NA 1.12E-03 1.38E-03 NA NA 1.42E-04 1.76E-04 NA NA 1.88E-05 1.86E-05 NA NA 1.09E+01 7.18E+00 NA NA 1.40E+00 9.13E-01 NA NA 2.27E-03 1.65E-03 NIA NIA 7.16E-05 5.51E-05 N/A N/A 1.13E-03 1.96E-03 N/A N/A 3.57E-05 6.29E-05 N/A N/A 8.93E-05 6.32E-05 N/A N/A 1.79E-05 1.28E-05 N/A N/A 4.78E-02 2.41 E-02 9.64E-04 2.04E-02 3.80E-02 4.09E-04 N/A N/A NIA N/A N/A N/A 5.001E+011 3.OOE+ 01 3.OOE+01 2.50E+01 5.OOE+01 1

Tritium, Iron-55, and Strontium results for the second quarter were not received from the off-site vendor at the time of this report. These values include estimates, and actual numbers will be provided In the next Radioactive Effluent Release Report.

ATTACHMENT 3 Page 1 of 1 Unit 1 -

Unit 2 X Reporting Period January - June 2002 GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODE 3 1st 2nd 3rd 4th Nuclides Released QUARTER QUARTER QUARTER QUARTER

1.

Fission Gases1 Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-1 27 Xenon-131 m Xenon-1 33 Xenon-1 33m Xenon-1 35 Xenon-1 35m Xenon-1 37 Xenon-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci

2.

lodines 1

Iodine-131 Iodine-133 Iodine-135

3.

Particulates 1 '2 Strontium-89 Strontium-90 Cesium-1 34 Cesium-1 37 Cobalt-60 Cobalt-58 Manganese-54 Barium-Lanthanum-1 40 Antimony-125 Niobium-95 Cerium-141 Cerium-144 Iron-59 Cesium-1 36 Chromium-51 Zinc-65 Iron-55 Molybdenum-99 Silver-11 Om

4.

Tritium 2

2.07E-01 1.77E+ 00 t*

2.03E-01 4*

4*

44 8.10E-02 7.83E-02 4*

4*

2.53E-01 7.93E-01 9*

2.79E-02

  • 4 44 1i29E-02 5.17E-02 1.52E-01 N/A N/A N/A N/A N/A N/A N/A N/A NIA N/A N/A NIA NIA N/A N/A N/A NIA NIA N/A MIA NIA N/A N/A N/A N/A N/A 1.24E-04 3.31 E-06 N/A N/A 7.16E-05 N/A NIA N/A N/A 2.38E-05 N/A N/A 4.51 E-06 NIA N/A 77**

N/A NIA 7*

  • 7 N/A N/A 2.08E-05 3.32E-05 N/A N/A
  • NIA NIA 7.43-E-06 1..08E-05 N/A N/A

N/A NIA 9

N/A N/A 7

TV NIA N/A 7*

7 N/A N/A 9*

7*

7 NIA NIA 4.01-E-05 3.90E-05 N/A N/A NIA N/A

  • 7 NIA N/A 9.25E+00 5.35E+00 N/A N/A 1

Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.OOE-04 ;.Ci/ml for required noble gases, 1.00E-1 1 jiCi/ml for required particulates, 11.00E-1 2 pCi/ml for required lodines, and 1.OOE-06 pCi/ml for Tritium, as required by the Off-Site Dose Calculation Manual (ODCM),

has been verified.

2 Tritium, Iron-55, and Strontium results for the second quarter were not received from the off-site vendor at the time of this report. These values include estimates. Actual values will be included in the next Radioactive Effluent Release Report.

3 Contributions from purges are included.

4.

ATTACHMENT 4.

Paqe 1 of 2 Unit 1 Unit 2 X

Reporting Period January - June 2002 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE 1st 2nd 3rd 4th QUARTER QUARTER QUARTER QUARTER

1.

Fission Gases' Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-127 Xenon-131 m Xenon-1 33 Xenon-1 33m Xenon-1 35 Xenon-1 35m Xenon-1 37 Xenon-1 38

2.

lodines1 Iodine-1 31 Iodine-1 33 Iodine-1 35

3.

Particulates"'

2 Strontium-89 Strontium-90 Cesium-134 Cesium-137 Cobalt-60 Cobalt-58 Manganese-54 Barium-Lanthanum-140 Antimony-1 25 Niobium-95 Cerium-1 41 Cerium-1 44 Iron-59 Cesium-1 36 Chromium-51 Zinc-65 Iron-55 Molybdenum-99 Silver-11 Om

4.

Tritium 2

Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci C1 Ci C,

Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci C0 4*

77 W7 4*

4*

4*

4*

4*

  • 4
  • 4 77 77 77 77 77 77 44 44 NIA NIA NIA NIA NIA N/A N/A NIA NIA N/A N/A NIA N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 4.45E-05 N/A N/A NIA N/A 7

77 NIA N/A 4.72E-05 N/A NIA 8.77E-06 N/A N/A

  • I*

N/A NIA

  • 4 2.79E-06 N/A NIA 2.21 E-04 2.75E-04 N/A N/A 4.83E-06 N/A N/A 1.24E-04 2.26E-04 N/A N/A N/A N/A 7*

N/A N/A 7

V N/A N/A W7

  • 77 N/A N/A 77 1.43E-05 NIA N/A
  • 7*

N/A N/A

  • 7 N/A N/A 2.18E-05 N/A NIA 7.00E-04 6.73E-04 N/A N/A
  • N/A N/IA N/A N/A 1.69E+00 1.83E+00 NIA N/A 1

Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.OOE-04,uCi/ml for required noble gases, 1.OOE-11 /uCi/mI for required particulates, 11.00E-12

,uCi/ml for required lodines, and 1.OOE-06 juCi/ml for Tritium, as required by the Off-Site Dose Calculation Manual (ODCM),

has been verified.

2 Tritium, Iron-55 and Strontium 89 and 90 results for the second quarter were not received from the off-site vendor at the time of this report. These values include estimates, and actual values will be included in the next Radioactive Effluent Release Report.

ATTACHMENT 4.

Page 2 of 2 Unit 1 Unit 2 X Reporting Period January - June 2002 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES BATCH MODE There were no batch releases during the reporting period.

1st 2nd 3rd 4th QUARTER QUARTER QUARTER QUARTER

1.

Fission Gases 1

Argon-41 Ci Krypton-85 CI Krypton-85m Ci Krypton-87 C1 Krypton-88 Ci Xenon-1 27 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-1 35 Ci Xenon-135m CI Xenon-1 37 Ci Xenon-1 38 Ci

2.

lodines' Iodine-131 Ci Iodine-1 33 C1 Iodine-135 CI

3.

Particulates 1.2 Strontium-89 Ci Strontium-90 Ci Cesium-1 34 Ci Cesium-1 37 Ci Cobalt-60 Ci Cobalt-58 Ci Manganese-54 Ci Barium-Lanthanum-140 Ci Antimony-1 25 Ci Niobium-95 Ci Cerium-141 Ci Cerium-1 44 Ci Iron-59 Ci Cesium-1 36 CI Chromium-51 Ci Zinc-65 Ci Iron-55 Ci Molybdenum-99 Ci Silver-1 1Om Ci

4.

Tritium 2 Ci Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.OOE-04 pCi/ml for required noble gases, 1.OOE-11 pCi/ml for required particulates, 1.OOE-1 2

/uCi/ml for required lodines, and 1.OOE-06 Cil/ml for Tritium, as required by the Off-Site Dose Calculation Manual (ODCM),

has been verified.

2 Tritium, Iron-55 and Strontium 89 and 90 results for the second quarter were not received from the off-site vendor at the time of this report. These values include estimates, and actual values will be included in the next Radioactive Effluent Release Report.

ATTACHMENT 5 Page 1 of 2 Unit 1 Unit 2 X

Reporting Period January - June 2002 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1st 2nd 3rd 4th EST. TOTAL QUARTER QUARTER QUARTER QUARTER ERROR. %

A.

Fission & Activation Products1

1.

Total release (not including Tritium, gases, alpha)

2.

Average diluted concentration during reporting period B.

Tritium 1

1.

Total release

2.

Average diluted concentration during reporting period C.

Dissolved and Entrained Gases 3

1.

Total release

2.

Average diluted concentration during reporting period D.

Gross Alpha Radioactivity 3

1.

Total release E.

Volumes

1.

Prior to dilution

2.

Volume of dilution water used during release period

3.

Volume of dilution water available during reporting period:

Percent of Technical SDecification Ci pUCiml Ci p*C/mI Ci Ci Liters Liters Liters 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 Limit to Date (3 mrem)

Percent of Annual Organ Dose Limit to Date (10 mrem)

Percent of 1 OCFR20 Concentration Limit 2.4 Percent of Dissolved or Entrained Noble Gas Limit 12.OOE-04 UCilml) 3.4 3.33E-02 2.94E-09 8.81E-02 6.66E-09 N/A N/A N/A N/A 4.69E+00 6.22E+00 N/A N/A 4.14E-07 4.70E-07 N/A NIA N/A N/A

  • 7*

N/A N/A 6.44E-05 9.46E-05 NIA N/A 1.24E+06 1.85E+06 N/A N/A 2.42E+08 4.27E+08 N/A N/A 1.13E+10 1.32E+ 10 NIA N/A 2.25E-01 4.16E-01 N/A NIA 2.79E-01 5.60E-01 N/A N/A 1.13E-01 3.19E-01 N/A N/A 1.40E-01 4.17E-01 N/A N/A 7.25E-03 1.43E-02 N/A N/A

Iron-55, Strontium 89 and 90 and Tritium results for the second quarter were not received from the off-site vendor at the time of this report. These values include estimates, and actual values will be included in the next Radioactive Effluent Release Report.

2 The percent of 1 OCFR20 concentration limit is based on the average concentration during the quarter.

3 Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 5.OOE-07 pCi/ml for required gamma emitting nuclides, 1.OOE-05 /Ci/ml for required dissolved and entrained noble gases and Tritium, 5.OOE-08 pCi/ml for Sr-89/90, 1.00E-06,uCi/ml for Fe-55 and 1.OOE-07 uCi/mi for gross alpha radioactivity, as required by the Off-Site Dose Calculation Manual (ODCM), has been verified.

4 Improved Technical Specifications limit the concentration of radioactive material released in the liquid effluents to unrestricted areas to ten times the concentrations specified in 10CFR20.1001-20.2402, Appendix B, Table 2, Column 2. Maximum Effluent Concentrations (MEC) numerically equal to ten times the 10CFR20.1001-20 2402 concentrations were adopted to evaluate liquid effluents.

5.00E+01 5.OOE+01 5.OOE+01 5.OOE+01 5.OOE+01 5.OOE+01 5.OOE+01 I-.

ATTACHMENT 5 Page 2 of 2 Unit 1 Unit 2 X

Reporting Period January - June 2002 LIQUID EFFLUENTS RELEASED BATCH MODE 3

1st 2nd 3rd 4th Nuclides Released1'2 QUARTER QUARTER QUARTER QUARTER Silver-11 Om Ci 1.06E-04 1.04E-03 N/A N/A Arsenic-76 Ci N/A N/A Gold-199 Ci NIA N/A Barium-140 Ci N/A N/A Cerium-141 Ci N/A N/A Cerium-144 Ci N/A N/A Cobalt-58 Ci 3.01E-04 1.91E-03 NIA NIA Cobalt-60 Ci 8.27E-03 2.88E-02 N/A N/A Chromium-51 Ci 6.27E-04 3.42E-03 N/A N/A Cesium-134 Ci NIA N/A Cesium-136 C1 N/A NIA Cesium-137 C1 N/A N/A Copper-64 C1 4.715E-05 N/A NIA Iron-55 Ci 1.19E-02 3.58E-03 N/A N/A Iron-59 Ci 8.86E-04 5.53E-03 N/A NIA lodine-131 Ci N/A NIA Iodine-132 Ci

  • 7*

N/A N/A Iodine-133 Ci N/A N/A Lanthanum-140 Ci N/A N/A Manganese-54 Ci 1.03E-02 3.94E-02 NIA N/A Manganese-56 Ci N/A N/A Molybdenum-99 Ci N/A N/A Sodium-24 Ci N/A N/A Niobium-95 Ci 3.61E-05 N/A N/A Nickel-65 C1 N/A N/A Neptunium-239 Ci 7

77 N/A NIA Antimony-1 24 Ci 3.51E-04 N/A N/A Strontium-89 Ci 1.40E-05 N/A N/A Strontium-90 Ci W

6.34E-06 N/A NI/A Strontium-92 Ci N/A N/A Technecium-99m Ci N/A N/A Tellurium-132 Ci 7

TV N/A N/A Tungsten-187 C,7W

_N/_*

N/A N/A Zinc-65 C1 8.48E-04 3.98E-03 N/A N/A Zinc-69m C*

N/_A N/A Zirconium-95 Ci 4.02E-05 N/A N/A Zirconium-97 Ci 77 N/A N/A Dissolved or Entrained Gases1 Ci NIA NIA Tritium 2 Ci 4.69E+00 6.22E+00 NIA NIA 1

Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 5.OOE-07 uCi/ml for required gamma emitting nuclides, 1.OOE-05,uCi/ml for required dissolved and entrained noble gases and Tritium, 5.00E-08 pCi/ml for Sr-89/90, 1.00E-06 pCi/ml for Fe-55 and 1.OOE-07,uCi/ml for gross alpha radioactivity, as required by the Off-Site Dose Calculation Manual (ODCM), has been verified.

2 Iron-55, Strontium 89 and 90 and Tritium results for the second quarter were not received from the off-site vendor at the time of this report. These values include estimates, and actual values will be included in the next Radioactive Effluent Release Report.

3 No continuous mode releases occurred during the reporting period.

ATTACHMENT 6 Page 1 of 6 Unit 1 _

Unit 2 X

Reporting Period January - June 2002 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. TYPE Volume Activity 1 (m 3)

(Ci)

Class Class A

B C

A B

C

1. Spent Resins (Dewatered) 5.83E+00 0

0 2.07E+01 0

0

2. Dry Active Waste 0

0 0

0 0

0

3. Irradiated Components, Control Rods, 0

0 0

0 etc.

4. Other:

(to Vendor for Processing or Consolidation)

a.

Dry Active Waste (Compactible 4.51E+02 0

0 6.54E+00 0

0 and Non-Compactible)

b.

Spent Resins (Dewatered) 4.05E+01 0

0 1.92E+02 0

0

c.

Other Waste (Contaminated Oil) 6.80E+01 0

0 1.42E-02 0

0 The estimated total error is 5.OOE+0 %.

ATTACHMENT 6 Paqe 2 of 6 Unit 1 Unit 2 X Reporting Period January - June 2002 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.1 TYPE Solidification Container Package Agent

1.

Spent Resins (Dewatered)

HIC - Poly STP None

2.

Dry Active Waste (Compactible and Non-Compactible)

N/A N/A N/A

3.

Irradiated Components, Control Rods, etc.

N/A N/A NIA

4.

Other: (To Vendor for Processing or Consolidation)

a.

Dry Active Waste (Compactible and Non-Compactible)

Metal Box STP None

b.

Spent Resins (Dewatered)

HIC STP None HIC Type A None

c.

Mixed Waste (Contaminated Oil)

Metal Box STP None

ATTACHMENT 6

-Page 3 of 6 Unit 1 -

Unit 2 X

Reporting Period January - June 2002 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)

1.

Spent Resins (Dewatered):

Nuclide Percent (1) Fe-55 4.32E+01 (2) Co-60 2.42E+01 (3) Mn-54 1.98E+01 (4) Zn-65 7.25E+00 (5) Fe-59 2.01E+00 (6) Co-58 1.68E+00 (7) Other 1.86E+00

2.

Dry Compressible Waste:

Nuchide Percent

3.

Irradiated Components, Control Rods, etc.:

Nuclide Percent

4.

Other:

(to Vendor for Processing or Consolidation)

a.

Dry Active Waste (Compactible and Non Compactible)

Nuclide Percent (1) Fe-55 5.85E+01 (2) Co-60 1.48E+01 (3) Zn-65 1.37E+01 (4) Mn-54 6.86E+00 (5) Cr-51 3.04E+00 (6) Fe-59 1.65E+00 (7) Other 1.45E+O0

b.

Spent Resins (Dewatered)

Nuclide Percent (1) Co-60 3.47E+01 (2) Fe-55 3.46E+01 (3) Mn-54 1.40E+01 (4) Zn-65 1.06E+01 (5) Ni-63 1.66E+00 (6) Fe-59 1.08E+00 (7) Co-58 1.01E+00 (8) Other 2.35E+00

c.

Mixed Waste (Contaminated Oil)

Nuclide Percent (1) Fe-55 6.67E+01 (2) Mn-54 1.11E+01 (3) Co-60 9.02E +00 (4) Cr-51 6.17E+00 (5) Fe-59 3.41E+O0 (6) Zn-65 1.79E+00 (7) Co-58 1.01E+O0 (8) Other 8.00E-01

ATTACHMENT 6 Page 4 of 6 Unit 1 Unit 2 X

Reporting Period January - June 2002 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.3.

SOLID WASTE DISPOSITION Number of Shipments 9

5 2

1 Mode of Transportation Truck Truck Truck Truck Destination GTS Duratek Oak Ridge, TN GTS Duratek Kingston, TN Studsvik Processing Facility, LLC Erwin, TN Barnwell Waste Management Facility Barnwell, SC B.

IRRADIATED FUEL SHIPMENTS (DISPOSITION):

There were no shipments.

Number of Shipments Mode of Transportation Destination NIA 0

N/A

ATTACHMENT 6 Page 5 of 6 Unit 1 -

Unit 2 X

Reporting Period January - June 2002 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS C.

SOLID WASTE SHIPPED OFF-SITE TO VENDORS FOR PROCESSING AND SUBSEQUENT BURIAL Below is a summary of NMP-2 radwaste buried by vendor facilities during January - June 2002. 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) Improved Technical Specification (ITS) Section 5.6.3 requires reporting of "information for each class of solid waste (as defined by 10CFR61) shipped off-site during the reporting period." The following data represents the actual shipments made from the off-site vendors of our radwaste (e.g., non-compacted trash, dry non-compressible waste, scrap metal, and resins) that were processed and commingled prior to burial.

C.1. TYPE OF WASTE - Non-compacted trash, dry non compressible waste, scrap metals, and resins processed Burial Volume Activity Est. Total by vendor facilities prior to burial.

(m3)

(Ci)

Error, %

1.77E+01 9.11E+01 5.OOE+01 C.2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent (1) Fe-55 4.29E+01 (2) Co-60 2.37E+01 (3) Mn-54 1.75E+01 (4) Zn-65 1.16E+01 (5) Fe-59 1.21E+00 (6) Co-58 1.13E+00 (7) Other 1.96E+00 C.3 SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 26 Truck Envirocare, UT 7

Truck Barnwell, SC

=P

  • z4

ATTACHMENT 6 Page 6 of 6 Unit 1 Unit 2 X

Reporting Period January - June 2002 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS D.

SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIAL There was no sewage sludge shipped off site during the reporting period.

D. 1 TYPE OF WASTE -

Burial Volume Activity Est. Total D.

STEdge(m

3)

(CI)

Error, %

Sewage Sludge N/A N/A 5.OOE+01 D. 2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent D. 3 SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination N/A N/A N/A

ATTACHMENT 7 Page 1 of 1 Unit 1 _

Unit 2 X

Reporting Period January - June 2002

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL (ODCM)

There were no revisions to the ODCM during the reporting period.

ATTACHMENT 8 Page 1 of 1 Unit 1 Unit 2 X

Reporting Period January - June 2002

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM (RPCP)

There were no changes to the RPCP during this reporting period.

ATTACHMENT 9 Page 1 of 1 Unit 1 -

Unit 2 X

Reporting Period January - June 2002

SUMMARY

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

ATTACHMENT 10 Paqe 1 of 1 Unit 1 Unit 2 X Reporting Period January - December 2001 UPDATE OF RELEASE AND DOSE DATA FOR GASEOUS (ELEVATED AND GROUND LEVEL) AND LIQUID EFFLUENTS Update of data using actual results from the off-site vendors for Strontium, Tritium, and Iron-55 and corrections for the fourth quarter 2001.

GASEOUS LIQUID 4th QUARTER 2001 4th QUARTER 2001 Nuclide 1 Activity (Ci)

Activity (Ci)

Sr-89 Sr-90 H-3 7.50E-+ 00 1.15EE+01 Fe-55 7.01E-04 4.85E-03 Fe-59 4 N/A 4.61 E-03 Average MEC iCi/ml NIA 6.11E-03 GASEOUS LIQUID Particulates 4th QUARTER 4th QUARTER

1. Particulates with half-lives >8 days Ci 1.16E-03 7.05E-02
2. Average release rate (gaseous) or diluted concentration (liquid) for reporting period jiCi/sec (gaseous) 1.48E-04

)pCi/ml (liquid) 5.07E-09 Tritium

1. Total release Ci 7.50E+00 1.15E+01
2. Average release rate for period (gaseous)

ItCi/sec (gaseous) 9.52E-01 or diluted concentration (liquids) for the IiCi/ml (liquid) 8.27E-07 reporting period Tritium, lodines, and Particulates (with half-GASEOUS LIQUID lives greater than 8 days)1 4th QUARTER 4th QUARTER

1.

Percent of Quarterly 2 1.19E-01 2.18E-01 Dose Limit (Gaseous - 7.5 (Quarterly (Quarterly)

mrem, Liquid - 1.5 mrem)
2.

Percent of Annual2 8.87E-02 2.37E-01 Dose Limit to Date (Gaseous -

(Annual)

(Annual) 15 mrem, Liquid - 3 mrem)

3.

Percent of Organ 2.39E-03 3.67E-01

- Dose Rate Limit Quarterly (Quarterly)

(Gaseous - 1500 mrem/yr) 3.46E-01

- Dose Limit (Liquid - 5 mrem Quarter, (Annual) 10 mrem Annual)

4. Percent of 10CFR20 3 N/A 1.36E-02 Concentration Limit (Liquid)

(Quarterly)

5.

Percent of Dissolved or Entrained Noble N/A Gas (Liquid - 2.OOE-04 liCi/ml)

(Quarterly)

I Concentrations less than the lower limit of detection, as required by the Off-Site Dose Calculation Manual (ODCM) are indicated with a double asterisk.

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

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

4 Fe-59 was updated to correct a typographical error for liquid releases. Gaseous release of Fe-59 was correct.

ATTACHMENT 11 Page 1 of 1 Unit 1.

Unit 2 X Reporting Period January - December 2001 UPDATE OF DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY FOR 2001 The total whole body and skin dose from shoreline recreational activities for 2001 were previously reported in the January

- December 2001 Radioactive Effluent Release Report as 7.51 E-04 mRem whole body and 8.77E-04 mRem skin dose. As a result of a calculation error and updated analysis results the correct total whole body and skin dose from shoreline recreational activities for 2001 are 2.26E-04 mRem whole body and 2.64E-04 mRem skin dose.

The calculation error resulted in the whole body and skin doses being reported higher than their correct values. This error has been entered into our corrective action program.

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