ML051300172

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Unit 2, Radioactive Effluent Release Report, January - December 2004
ML051300172
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 12/31/2004
From:
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NMPE2121
Download: ML051300172 (26)
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Text

NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT January- December 2004

- Constellation Energy A Nine Mile Point Nuclear Station

Page 1 of 2 NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2004 SUPPLEMENTAL INFORMATION Facility: Nine Mile Point Unit #2 Licensee: Nine Mile Point Nuclear Station, LLC

1. TECHNICAL SPECIFICATION LIMITS(ODCM1 Limits following implementation of Improved Technical Specifications (ITS) on 12/2/00)

A) FISSION AND ACTIVATION GASES

1. The dose rate limit for 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 for 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 radioactive material 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 quarter to less than or equal to 7.5 mrem to any organ and, during any calendar year to less than or equal to 15 mrem to any organ.

D) LIQUID EFFLUENTS

1. Improved Technical Specifications (ITS) and the ODCM limit the concentration of radioactive material released in the liquid effluents to unrestricted areas to ten times the concentrations specified in IOCFR20.1001-20.2402, 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/ml 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 released from the main stack and from the combined Radwaste/Reactor Building vent is determined by on-line gamma spectroscopic monitoring (intrinsic germanium crystal) of each isokinetic sample stream.

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

C) PARTICULATES Particulate activity released from the main stack and from the combined Radwaste/Reactor Building vent is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from each 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 monthly samples taken from each sample stream 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 - December 2004 Liquid Effluents:

10CFR20.1001-20.2402, Appendix 8, Table 2, Column 21 Average MEC - pCi/ml (Qtr. 1) = NIA Average MEC - pCi/ml (Qtr. 3) = 9.54E-03 Average MEC - pCi/ml (Qtr. 2) = 2I2ffi2 Average MEC - pCi/ml (Qtr. 4) 7.25E-03 Average Energy (Fission and Activation gases - Mev):

Qtr. 1: Fy = 5.00E-01 = 2.15E-01 Qtr. 2: y = 815E-01 = 5.34E-01 Qtr. 3: y = 403E-01 = 2.76E-01 Qtr. 4: y = 5,60E-01 = 2.35E-01 Liquid:

Number of batch releases  : 11 Total time period for batch releases (hrs)  : 3.50E+01 Maximum time period for a batch release (hrs): 3.25E+00 Average time period for a batch release (hrs) 3.18E+00 Minimum time period for a batch release (hrs) 2.95E+00 Total volume of water used to dilute the liquid effluent during the release ilt 2 nd 3 Id 4th period (Li  : N/A 1.54E+08 1.89E+07 3.34E+07 Total volume of water available to dilute the liquid effluent during reporting " 2nd 3 1d 4th Period (Li 1.10E+10 1.26E+10 1.28E+10 1.20E+10 Gaseous (Emergency Condenser Vent): 'Not Applicable for Unit 2' Number of batch releases  : NIA Total time period for batch releases (hrs) N/A Maximum time period for a batch release (hrs) NIA Average time period for a batch release (hrs) N/A Minimum time period for a batch release (hrs): N/A Gaseous (Primary Containment Purge):

Number of batch releases  : 5 Total time period for batch releases (hrs)  : 1.91E+02 Maximum time period for a batch release (hrs): 9.87E+01 Average time period for a batch release (hrs) 3.82E+01 Minimum time period for a batch release (hrs): 6.73E+00 Improved Technical Specificalions 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 I OCFR20.100l-20.2402 concentrations were adopted to evaluate liquid effluents.

ATTACHMENT 1 Summary Data Page 2 ofa Unit 1 _ Unit 2 X Reporting Period January - December 2004 Abnormal Releases:

A. Liquids:

Number of releases 0 Total activity released N/A Ci B. Gaseous:

Number of releases 0 Total activity released N/A Ci

ATTACHMENT 2 Page 1 of I Unit I _ Unit 2 X Reporting Period January - December 2004 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES. ELEVATED AND GROUND LEVEL Ist 2nd 3rd 4th EST. TOTAL QUARTER QUARTER QUARTER QUARTER ERROR. %

A. Fission & Activation gases

1. Total release Ci 5.28E+01 I4.90E-01 1.82E-01 8.61 E+00 5.OOE+01
2. Average release rate pCi/sec 6.71 E+00O 6.24E-02 2.3015-02 1.08E+00 B. Iodines
1. Total lodine-131 Cl 1.43E-04 6.61 E-05 1J41 E05 4,79E-06 3.OOE+01
2. Average release rate for period pCi/sec 1.82E-05 8.36E-06 1.79E-06 6,09E-07 C. Particulates
1. Particulates with half-lives >8 days Ci 2.12E.04 7.30E-04 1,12E.04 2,35E.04 3.OOE+01
2. Average release rate for period pCI/sec 2.71 E-05 924EA.05 1,42E-05 2.99E*05
3. Gross alpha radioactivity Ci 1,38EQ0 2,32E-05 2,62E-05 1.34E-05 2.50E+01 D. Tritium
1. Total release Ci 2.811E+01 9,44E+00 1,59E+/-01 1.70E+01 5.OOE+01
2. Average release rate for period pCi/sec 3..59E+00 1.20E400 2.02E+00 2.16E+00 E. Percent of Tech. Spec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose Limit (5 mR)  % 6,22E-02 9,57E-04 1,66E-04 1.OVE-02 Percent of Quarterly Beta Air Dose Limit (10 mrad)  % 5,5E0 2.82E-05 5,54E-06 2,24E-04 Percent of Annual Gamma Air Dose Limit to Date ( 10mR)  % 3,11E.02 3.16E-02 3,17E*02 3,71E-02 Percent of Annual Beta Air Dose Limit to Date (20 mrad)  % 2,3E0 2.64E-03 2,64E*03 2.75E-03 Percent of Whole Body Dose Rate Limit (500 mrem/yr)  % 2.40E-03 3.68E-05 6,35E-06 4.20E-04 Percent of Skin Dose Rate Limit (3000 mrem/yr)  % 4.86EQ0 7.44E-06 1.27E-06 8.22E-05 Tritium. lodines. and Particulates (with half-lives areater than 8 davsl Percent of Quarterly Dose Limit (7.5 mrem)  % 4,60E-02 3.03E.02 102Ei02 1.OOE-02 Percent of Annual Dose Limit (I 5 mrem)  % 2.32E.02 3.84E-02 4.36E-02 4.86E-02 Percent of Organ Dose Rate Limit (1500 mrem/yr)  % 9,29E-04 6.06E-04 2.04E-04 2.01 E-04

ATTACHMENT 3 Page 1 of 1 Unit I _ Unit 2 X Reporting Period January - December 2004 GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODE2 1St 2nd 3rd 4th Nuclides Released QUARTER QUARTER QUARTER QUARTER

1. Fission Gases Argon-41 Cl 1.71 E-01 8.53E-03 2.91 E-02 Krypton-85 Cl 7*4 *5 Krypton-85m Cl 1.04iE+01 7*

1.54E-01 2,860E+00 Krypton-87 Cl 154-O Krypton-88 Cl 1.19 E+01 1.9TE-02 Xenon-127 CI Xenon-131m Cl Xenon-133 Cl 2.35E401 S.

3.6ZE+00 75 .5 Xenon-133m Cl Xenon-135 Ci 8,15E-0i .5 .5-Xenon-135m Ci 1.82E-01 ;0. .5 Ci 4.14E-02 S.

Xenon-137 Ci 1.23E-01 S.

Xenon-138

2. lodines1 Iodine-131 Ci 6.73E-05 1,24E-05 1.41 E-05 47E0 Iodine-133 CI 9,94E-05 1.3E05 192E-04 1.21 E-05 Iodine-135 CI
3. Particulate Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci 2,30E-06 Cesium-137 Ci Cobalt-60 CI 5.895E-06 2.3FE-05 5.2i6E-06 .5.396E-06 Cobolt-58 Cl Manganese-54 Cl j1T1106 Barium-Lanthanum-140 CI S. 5* 55 5 Antimony-125 Cl S. 55 *5 5 Niobium-95 CI Cerium-141 Cl Cerium-144 Cl 5* *5 5* 5 Iron-59 Ci S. S. 55
  • Cesium-136 CI 55 S5 5* 5 Chromium-51 Ci Zinc-65 Cl Iron-55 Cl S58E0 9517E 0*

Molybdenum-99 Cl 1.87E*0 8.0 5*

Neodymium-147 Cl

4. Tritium' Ci I Concentrations less thon 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 pCl/ml for required noble gases, 1.OOE-1 I jpCi/ml for required particulates and gross alpha. 1.OOE-12 pCI/ml for required lodines, and i.OOE-06 pCI/ml for Tritium, as required by the Off-Site Dose Calculation Manual (ODCM).

2 Contributions from purges are included.

ATTACHMENT 4 Paae 1 of 1 Unit 1 _ Unit2 X Reporting Period January -December 2004 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE 2 There were no ground level batch releases during the reporting period 1s 2nd ard 4t QUARTER QUARTER QUARTER QUARTER

1. Fission Goses' Argon-41 CI S. .5 Krypton-85 CI S. 7*

Krypton-85m CI es zo Krypton-87 Cl Krypton-88 Ci 6.3E0 *0 S. **

.5 Xenon-127 Ci S. S.

Xenon-131m CI **

Xenon-133 ci 70.

.5 7*

7.

S.

.5

.5 Xenon-133m CI .5 S.

Xenon-135 Cl 55 S.

Xenon-135m Cl .5-Xenon-137 Cl Xenon-138 Cl

2. lodines Iodine-131 Ci 7.52E-05 5.37E-05
  • 5 555.5 Iodine-133 Cl Iodine-135 Ci
3. Particulates Strontium-89 Ci Strontium-90 Ci Cesium-134 Cl Cesium-137 CI Cobolt-60 Cl 1.337E-04 4.1i3E-04 9.2ZE--05 1.7i6E-04 Cobalt-58 CI Manganese-54 CI 6.953E-05 2.04E-04 1,460E-05 51E-05 Barium-Lanthanum-140 CI Antimony-125 CI 55 55 * *5 Niobium-95 Cl Cerium-i 41 Cl Cerium-144 CI Iron-59 Ci 2.41 E-05 Cesium-136 CI Chromium-51 Cl - 6,66E-05 Zinc-65 Ci Iron-55 Cl Molybdenum-99 Cl Neodymium-147 Ci
4. Tritium Ci 1.63E+01 5.57E400 7.81 E400 7.81 E+00 X 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/mI for required noble gases, i.OOE- I1ICi/ml for required particulates and gross alpha, 1.00E- 12 pCI/ml for required lodines, and 1.OOE-06 pCi/ml for Tritium, as required by the Oft-Site Dose Calculation Manual (ODCM).

ATTACHMENT 5 Page 1 of 2 Unit 1 _ Unit 2 X Reporting Period January - December 2004 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1st 2nd 3rd 4t EST. TOTAL QUARTER QUARTER QUARTER QUARTER ERROR, %

A. Fission & Activation Products

1. Total release (not including Tritium, gases, alpha) Ci No Releases 1.41 E-03 1.02E-04 1.99E-02 5.001E+01
2. Average diluted concentration during reporting period pCi/ml No Releases 1.12E-10 7.96E-12 1.66E-09 B. Tritium
1. Total release Ci No Releases 4.55E+00 4.79E-01 7.72E-01 5.OOE+01
2. Average diluted concentration during reporting period VCi/ml No Releases 3.61 E-07 3.74E-08 6.43E-08 C. Dissolved and Entrained Gases'
1. Total release Ci No Releases 4* 44 5.OOE +01
2. Average diluted concentration during reporting period pCi/ml No Releases D. Gross Alpha Radioactivity'
1. Total release Ci No Releases 5.OOE+01 E. Volumes
1. Prior to dilution Liters No Releases 7.04E+05 8.82E+04 1.78E+05 5.OOE+01
2. Volume of dilution water used during release period Liters No Releases 1.54E+08 1.89E+07 3.34E+07 5.OOE+01
3. Volume of dilution water available during reporting period: Liters No Releases 1.26E+10 1.28E+ 1 1.20E + 10 5.OOE+01 Percent of Technical Specification F.

Limits Percent of Quarterly Whole Body Dose Limit 01.5 mrem) No Releases 1.04E-02 5.14E.04 5.65E-02 Percent of Quarterly Organ Dose Limit (5 mrem) No Releases 8.03E-03 5.59E-04 8.35E-02 Percent of Annual Whole Body Dose Limit to Date (3 mrem) No Releases 5.21E-03 5.45E-03 3.37E-02 Percent of Annual Organ Dose Limit to Date (10 mrem) No Releases 4.09E-03 4.37E-03 4.61E-02 Percent of 10CFR20 Concentration Limit 2.3 No Releases 3.90E-03 3.92E-04 3.91E-03 Percent of Dissolved or Entrained Noble Gas Limit (2.00E-04 pCi/ml) No Releases .00E+00 O.OOE+00 0.OOE+00 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 pCi/ml for required dissolved and entrained noble gases and Tritium, 5.OOE-08 pCi/ml for Sr-89/90, 1.OOE-06 pCi/ml for Fe-55 and 1.OOE-07 pCi/ml for gross alpha radioactivity, as required by the Off-Site Dose Calculation Manual (ODCM).

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

3 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 (MECI numerically equal to ten times the 10CFR20.1001-20.2402 concentrations were adopted to evaluate liquid effluents.

ATTACHMENT 5 Page 2 of 2 Unit I _ Unit 2 X Reporting Period January- December 2004 LIQUID EFFLUENTS RELEASED BATCH MODE2 fis 2nd 3rd 4th Nuclides Releasedl,2 QUARTER QUATER QUARTER QUARTER Silver-I 1Om No Releases 3.75E-04 Gold-199 No Releases Barium-140 No Releases 7*

7*

.5 Cerium-141 No Releases Cerium-144 No Releases S.

5.

Cobolt-58 No Releases Cobalt-60 No Releases 7*

6,5iE-05 1.08E-02 55 55 Chromium-51 No Releases 55 Cesium-134 No Releases a.

Cesium-136 No Releases S.

Cesium-137 No Releases 7*

No Releases 7* 5*

Copper-64 Iron-55 No Releases 3.21iE-O3 S.

3.91 E-03 Iron-59 No Releases S.

7.

5.81 E-05 Iodine-131 No Releases .5 7*

Z.

Iodine-132 No Releases S. **

S.

Iodine-133 No Releases .Z S.

Lanthanum-140 No Releases .5 Manganese-54 No Releases 3.58iE-05 4.47E-03

.5 55 Monganese-56 No Releases 55 S.

Molybdenum-99 No Releases 7. 55 Sodium-24 No Releases S.

Niobium-95 No Releases S.

Nickel-65 No Releases 3.2E0

.5 7*

Neptunium-239 No Releases 7.

Antimony-124 No Releases 55 Z.

.5 S.

Strontium-89 No Releases 5.

.5 .*

Strontium-90 No Releases 7*.

    • 5*

Strontium-92 No Releases S.

70. 7*

.5 Technecium-99m No Releases S.

.5 Tellurium-132 No Releases

0.

Tungsten-187 No Releases

.5 Zinc-65 No Releases 3.1 8E-04 Zinc-69m No Releases 7. 0.

55 55 Zirconium-95 No Releases 55 Zirconium-97 No Releases *5 Dissolved or Entrained Gases' Ci No Releases 55 S. .5 Tritium' Ci No Releases 4.55E+00 4.79E-01 7,2E-01 I Concentrations less than the lower limit of detection of the counting system used are Indicated with a double asterisk. A lower limit of detection of 5.OOE-07 pCI/ml for required gamma emitting nuclides, I.OOE-05 pCI/ml for required dissolved and entrained noble gases and Tritium, 5.OOE-08 pCI/ml for Sr-89/90, i.OOE-06 pCi/ml for Fe-55 and 1-131, and I.OOE-07 pCI/ml for gross alpha radioactivity, as required by the Off-Site Dose Calculation Manual (ODCM).

2 No continuous mode releases occurred during the reporting period.

ATTACHMENT 6 Page 1 of 4 Unit 1 _ Unit 2 X Reporting Period Jonuary -December 2004 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.1 TYPE Volume Activity 3

(m ) (Ci)

Clos Cl=s A B I c A J B C

a. Spent Resins (Dewatered) AE l B l 5.38E+01 2
b. Dry Active Waste l 9.03E+02 l Q 7,15E+00 0Q (Compactible and Non-Compactible, Contaminated Equipment)
c. Irradiated Components. Control Rods, l Q l Q l Q 2Q l Q 2 etc.IIII
d. Other (to Vendor for Processing or Consolidation)
a. Tank Sediment 2.70E+01 2 0 2.65E+02 Q 2 The estimated total eror is 5.OOE+01%.

ATTACHMENT 6 Paae 2 of 4 Unit 1_ Unit 2 X Reporting Period January - December 2004 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.1 TYPE Solidification Container Packae Aaent

a. Spent Resins (Dewatered] Polyliner General Design None Tvoe A
b. Dry Active Waste Metal Box General Deslan None (Compoctible and Non-Compactible, Contaminated Equipment) c, Irradiated Components, Control Rods, etc. l LA WA WlA
d. Other: (To Vendor for Processing or Consolidation) N/A l NA l NA
1. Tank Sediment l PoiyvLiner General Deslan None

ATTACHMEFNT A Panea 3 of A Unit 1 _ Unit2 X Reporting Period January - December 2004 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)

a. Spent Resins (Dewatered):

Nuclide Percent (1) Fe-55 (1) 49.8 (2) Co-60 (2) 29.7 (3) Mn-54 (3) 10.4 (4) Zn-65 (4) 8.3 (5) Other (5) 1.8

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

Nuclide Percent (1) Fe-55 (1) 76.9 (2) Co-60 (2) 13.9 (3) Mn-54 (3) 7.6 (4) Other (4) 1.6

c. Irradiated Components. Control Rods, etc.: There were no shipments.

Nclide Percent

d. Other: (to Vendor for Processing or Consolidation)
1. Tank Sediment Nuclide Percent (1) Fe-55 (1) 74.1 (2) Co-60 (2) 18.5 (3) Mn-54 (3) 4.9 (4) Zn-65 (4) 1.3 (5) Other (5) 1.2

ATTACHMENT 6 Page 4 of 4 Unit 1 _ Unit 2 X Reporting Period January - December 2004 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.3. SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 1 Hittman Transoort - Truck Duratek Services. Inc.

2 Hittmon Transport -Truck StudvIk Processing Facility. LLC 9 R&R Trucking Race. LLC 4 Race Logistics. tLC Race. tLC

_ Taa Tronsport Race. LLC 22 Hittmon Trons~ort Studsvik Processing Facility. ttC B. IRRADIATED FUEL SHIPMENTS (DISPOSITIONJ: There were no shipments.

Number of Shipments Mode of Transportation Destination Q NA NA

ATTACHMENT 7 Page 1 of 1 Unit I _ Unit 2 X Reporting Period January - December 2004

SUMMARY

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

The Unit 2 Off-Site Dose Calculation Manual (ODCM) was revised during the reporting period to extend the channel calibration frequency for the Offgas Noble Gas Activity Monitors, Sample Flow -Rate Monitors and System Flow-Rate Monitor (section D 3.3.2) to 24 months (30 months with a 25% grace period). The revision also included a clarification to section D 3.3.2 describing that the Offgas System required alarm setpoint is Technical Specification LCO 3.7.4 and not the Effluent Dose Rate Limit of DLCO 3.2.1.

These changes do not affect the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50 Appendix 1,and does not adversely Impact the accuracy or reliability of effluent, dose, or setpoint calculations. A copy of the ODCM, Revision 25 Is attached and a summary of the changes presented to and approved by the Stations Operations Review Committee on January 20. 2004 Is provided below. The summary also Includes the justification for the change.

- ,'.VRSi

' . i 25

  • Page # New/Amended Description of Change Reason for Change 13.3-7 D 3.3.2 Revised ODCM section D 3.3.2 DLCO This change Isconsistent with the 3.3.2 to clarify that Offgos System corrective action program resolution in (Instrument 1)required alarm point is NM-2004-2431 that the Offgas Monitor is Technical Specification LCO 3.7.4 not required to meet both requirements.

and not the Effluent Dose Rate Limit of DLCO 3.2.1. _

13.3-12 and DSR 3.3.2.7. DSR DSR 3.3.7 was revised and DSR The frequency for performing the 1.3.3-13 3.3.2.10 and Table 3.3.2.10 was added to extend CHANNEL CALIBRATION for Unit 2 Offgas D 3.3.2-1 channel calibration frequency for Noble Gas Activity Monitors. Offgas the Offgas Noble Gas Activity System Flow-Rate Measuring Device, and Monitors. Sample flow-rate monitors. Offgas Sample Flow-Rate Measuring and System flow rate monitor to 24 Devices have been extended from 18 months (30 months with 25% grace months to 24 months to correspond to the period). Table D 3.3.2-1 was revised NMP2 24 month refueling cycle. A review to add reference to the added of the surveillance test history for the surveillance requirement. affected monitors demonstrates that there are no failures that would invalidate the conclusion that the Impact, if any, on system availability is minimal. The proposed 24 month surveillance frequencies do not Invalidate any assumptions in the plant licensing basis. Therefore, the change maintains the levels of radioactive effluent controls and dose not adversely affect the accuracy or reliability of effluent, dose, or setpoint calculations.

ATTACHMENT 8 Page I of I Unit1_ Unit2 X Reporting Period January - December 2004

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

There were no changes to the Unit 2 Process Control Program (PCPJ during the report period.

ATTACHMENT 9 Page 1 of 1 Unit'l_ Unit 2 X Reporting Period Januory - December 2004

SUMMARY

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

ATTACHMENT 10 Page 1of 4 Unit 1_ Unit 2 _X Reporting Period January - December 2004 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Introduction An assessment of the radiation dose potentially received by a Member of the Public due to their activities inside the site boundary from Nine Mile Point Unit 2 (NMP2) liquid and gaseous effluents has been conducted for the period January through December 2004.

This assessment considers the maximum exposed Individual and the various exposure pathways resulting from liquid and gaseous effluents to Identify the maximum dose received by a Member of the Public during their activities within the site boundary.

Prior to September 11. 2001. the public had access to the Energy Information Center for purposes of observing the educational displays or for picnicking and associated activities. Fishing also occurred near the shoreline adjacent to the NMP. Fishing near the shoreline adjacent to the NMP Site was the onsite activity that resulted In the potential maximum dose received by a Member of the Public. Following September 11 2001 public access to the Energy Information Center has been restricted and fishing by Members of the Public at locations on site is also prohibited. Although fishing was not conducted during 2004 the annual dose to a hypothetical fisherman was still evaluated to provide continuity of data for the location.

Dose Pathways Dose pathways considered for this evaluation included direct radiation. Inhalation and external ground (shoreline sediment or soil doses). Other pathways, such as ingestion pathways, are not considered because they are either not applicable, insignificant, or are considered as part of the evaluation of the total dose to a member of the public located off-site. In addition, only releases from the NMP2 stock and vent were evaluated for the inhalation pathway. Dose due to aquatic pathways such as liquid effluents Is not applicable since swimming Isprohibited at the Nine Mile Point Site.

Dose to a hypothetical fisherman Isreceived through the following pathways while standing on the shoreline fishing:

  • External ground pathway; this dose is received from plant related radionuclides detected In the shoreline sediment.

. Inhalation pathway; this dose Isreceived through Inhalation of gaseous effluents released from NMP2 Stack and Vent.

  • Direct radiation pathway; dose resulting from the operation of NMP2, Nine Mile Point Unit 1 (NMPI) and the James A.

Fitzpatrick (JAF) Facilities.

Methodologies for Determining Dose for Applicable Pathways External Ground (Shoreline Sediment) pathway Dose from the external ground (shoreline sediment) Isbased on the methodology in the Unit 2 Offsite Dose Calculation Manual (NMP2 ODCM) as adapted from Regulatory Guide 1.109. For this evaluation It is assumed that the hypothetical maximum exposed individual fished from the shoreline at all times.

  • The total dose received by the whole body and skin of the maximum exposed individual during 2004 was calculated using the following Input parameters: Usage Factor = 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> (fishing 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per week, 39 weeks per year)
  • Density in grams per square meter = 40,000
  • Shore width factor = 0.3
  • Fractional portion of the year = 1 (used average radionuclide concentration over total time period)
  • Average Cs-137 concentration = 1.85E-01 pCi/g The total whole body and skin doses received by a hypothetical maximum exposed fisherman from the external ground pathway Ispresented In Table 1, Exposure Pathway Dose.

ATTACHMENT 10 Page 2 of 4 Unit 1_ Unit 2 _X Reporting Period January - December 2004 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Inhalation Pathway The Inhalation dose pathway Isevaluated by utilizing the Inhalation equation in the NMP2 ODCM as adopted from Regulatory Guide 1.109. The total whole body dose and organ dose received by the hypothetical maximum exposed fisherman during 2004 is calculated using the following Input parameters for gaseous effluents released from both the NMP2 Stock and Vent for the time period exposure Isreceived:

NMP2 Stack:

Variable Fisherman

Annual air intake m /year (adult) 8000 Fractional portion of the year (hours) 0.0356 H-3 (pCi/sec) 8.92E+05 Mn-54 (pCi/sec) 4.70E-02 Co-60 (pCl/sec) 1.43E+00 Cs-134 (pCilsec) 9.73E-02 1-131 (pCi/sec) 1.32E+00 1-133 (pCi/sec) 9.1 OE+00 NMP2 Vent:

Variable Fisherman

Annual air intake m /year (adult) 8000 Fractional portion of the year (hours) 0.0356 H-3 (pCI/sec) 8.98E+05 Cr-51 (pCi/sec) 2.79E+00 Mn-54 (pCi/sec) 1.14E+01 Fe-59 (pCIl/sec) 1.02E+00 Co-60 (pCi/sec) 2.88E+01 1-131 IpCi/seci 2.27E+00

  • The maximum exposed fisherman Isassumed to be present on site during the period of April through December at a rate of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per week for 39 weeks per year equivalent to 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> for the year (fractional portion of the year =

0.0356). Therefore, the Average Stack and Vent flow rates and radionuclide concentrations used to determine the dose are represented by second, third and fourth quarter gaseous effluent flow and concentration values.

The total whole body dose and maximum organ dose received by the hypothetical maximum exposed fisherman is presented In Table 1, Exposure Pathway Dose.

ATTACHMENT 10 Page 3 of 4 Unit I _ Unit 2 X Reporting Period January - December 2004 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY The maximum exposed fisherman is assumed to be present on site during the period of April through December at a rate of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per week for 39 weeks per year equivalent to 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> for the year (fractional portion of the year = 0.0356).

Therefore, the Average Stack and Vent flow rates and radionuclide concentrations used to determine the dose are represented by second, third and fourth quarter gaseous effluent flow and concentration values.

The total whole body dose and maximum organ dose received by the hypothetical maximum exposed fisherman Is presented In Table 1, Exposure Pathway Dose.

Direct Radiation Pathway The direct radiation pathway Isevaluated In accordance with the methodology found In the NMP2 ODCM. This pathway considers four components: direct radiation from the generating facilities, direct radiation from any possible overhead plume, direct radiation from ground deposition and direct radiation from plume submersion. The direct radiation pathway is evaluated by the use of high sensitivity environmental Thermoluminescent Dosimeters (TLDs). Since fishing activities occur between April 1- December 31, TLD data for the second, third, and fourth quarters of 2004 from TLDs placed in the general area where fishing once occurred were used to determine an average dose to the hypothetical maximum exposed fisherman from direct radiation. The following is a summary of the average dose rate and assumed time spent on site used to determine the total dose received:

Variable Fisherman Average Dose Rate (mRem/hr) 1.15E-03 Exposure time (hours) 312 Total Doses received by the hypothetical maximum exposed fisherman from direct radiation Is presented in Table 1, Exposure Pathway Dose.

Dose Received By A Hypothetical Maximum ExDosed Member Of The Public Inside the Site Boundary Durina 2004 The following is a summary of the dose received by a hypothetical maximum exposed fisherman from Liquid and Gaseous effluents released from NMP2 during 2004:

Table 1 Exposure Pathway AnnulI Dose Exposure Pathway Dose Type Fisherman (mRem)

External Ground Whole Body 2.95E-03 Skin of Whole Body 3.44E-03 Inhalation Whole Body 1.52E-04 Maximum Organ Lung: 1.71E044 Direct Radiation Whole Body 0.36

ATTACHMENT 10 Page 4 of 4 Unit I _ Unit 2 _.X Reporting Period January - December 2004 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Based on these values the total annual dose received by a hypothetical maximum exposed member of the public Is as follows:

Table 2 Annual Dose Summary Total Annual Dose for 2004 Fisherman (mRem)

Total Whole Body 0.36 Skin of Whole Body 3.44E-03 Maximum Organ Lung: 1.71E-04

ATTACHMENT 11 Page 1of 2 Unit I _ Unit 2 X Reporting Period January - December 2004 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Introduction An assessment of radiation doses potentially received by the likely most exposed member of the public located beyond the site boundary was conducted for the period January through December 2004 for comparison against the 40CFR 190 annual dose limits.

The Intent of 40 CFR 190 requires that the effluents of Nine Mile Point Unit 2 (NMP2). as well as other nearby uranium fuel cycle facilities, be considered. In this case, the effluents of NMP2, Nine Mile Point Unit 1 (NMPI) and the James A. FitzPatrick (JAF) facilities must be considered.

40CFR 190 requires the annual radiation dose received by members of the public in the general environment, as a result of plant operations, be limited to:

  • < 25 mRem wholebody
  • < 25 mRem any organ (except thyroid]
  • < 75 mRem thyroid This evaluation compares doses resulting from Liquid and Gaseous effluents and direct radiation originating from the site as a result of the operation of the NMP2, NMP1 and JAF nuclear facilities.

Dose Pathways Dose pathways considered for this evaluation Included doses resulting from liquid effluents, gaseous effluents and direct radiation from all nuclear operating facilities located on the Nine Mile Point Site.

Dose to the most likely member of the public, outside the site boundary, Isreceived through the following pathways:

  • Fish consumption pathway; this dose Is received from plant radionuclides that have concentrated In fish that is consumed by a member of the public.
  • Shoreline Sediment; this dose Isreceived as a result of an Individual's exposure to plant radionuclides deposited In the shoreline sediment, which is used as a recreational area.
  • Deposition, Inhalation and Ingestion pathways resulting from gaseous effluents: this dose Is received through exposure to gaseous effluents released from NMPI, NMP2 and JAF operating facilities.
  • Direct Radiation pathway; radiation dose resulting from the operation of NMP1, NMP2 and JAF facilities.

Methodologies for Determinina Dose for ADDlicable Pathways Fish Consumption Dose received as a result of fish consumption Isbased on the methodology specified In the NMP2 Off-site Dose Calculation Manual (NMP2 ODCM) as adapted from Regulatory Guide 1.109. The dose for 2004 Iscalculated from actual analysis results of environmental fish samples taken near the site discharge points. For this evaluation it is assumed that the most likely exposed member of the public consumes fish taken near the site discharge points.

No radionuclides were detected In fish samples collected and analyzed during 2004; therefore no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2004.

Shoreline Sediment Dose received from shoreline sediment is based on the methodology in the NMP2 ODCM as adapted from Regulatory Guide 1.109. For this evaluation It Isassumed that the most likely exposed member of the public spends 67 hour7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br />s/year along the shoreline for recreational purposes.

ATTACHMENT 11 Page 2 of 2 Unit 1_ Unit 2 X Reporting Period January - December 2004 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Shoreline Sediment continued:

The total dose received by the whole body and skin of the maximum exposed Individual during 2004 Iscalculated using the following Input parameters:

  • Usage Factor = 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> per year
  • Density In grams per square meter = 40,000
  • Shore width factor = 0.3
  • Fractional portion of the year = 1
  • Average Cs-137 Concentration = 0.039 pCI/g Dose Pathways Resulting From Gaseous Effluents Dose received by the likely most exposed member of the public due to gaseous effluents is calculated In accordance with the methodology provided In the NMP2 ODCM, NMP1 Offsite Dose Calculation Manual, and the JAF Offsite Dose Calculation Manual. These calculations consider deposition, Inhalation and ingestion pathways. The total sum of doses resulting from gaseous effluents from NMP1. NMP2 and JAF during 2004 provide a total dose to the whole body and maximum organ dose for this pathway.

Direct Radiation Pathway Dose as a result of direct gamma radiation from the site, encompasses doses from direct "shine" from the generating facilities, direct radiation from any overhead gaseous plumes, plume submersion and from ground deposition. This total dose is measured by environmental TLDs. The critical location Isbased on the closest year-round residence from the generating facilities as well as the closest residence In the critical downwind sector In order to evaluate both direct radiation from the generating facilities and gaseous plumes as determined by the local meteorology. During 2004, the closest residence and the critical downwind residence are at the same location.

Dose Potentially Received by the Likely Most Exposed Member of the Public Outside the Site Boundary Durina 2004 Exposure Pathway Dose Type Dose (mRem)

Fish Consumption Total Whole Body No Dose Total Maximum Organ No Dose Shoreline Sediment Total Whole Body 1.32E-04 Total Skin of Whole Body 1.54E-04 Gaseous Effluents Total Whole Body 2.20E-02 Total Maximum Organ Thyroid: 1.12E-O1 Direct Radiation Total Whole Body 0.16 Based on these values the maximum total annual dose potentially received by the most likely exposed member of the public during 2004 is as follows:

  • Total Whole Body: 0.18 mRem
  • Total Skin of Whole Body: 2.01 E-02 mRem
  • Maximum Organ: Thyroid: 1.12E-01 mRem 40CFRI 90 Evaluation The maximum total doses presented In this attachment are the result of operations at the NMP1, NMP2 and the JAF facilities.

The maximum organ dose (Thyroid: 0.112 mRem) and the maximum whole body dose (0.18 mRem) are below the 40 CFR 190 criteria of 25 mRem per calendar year to the maximum exposed organ or the whole body, and below 75 mRem per calendar year to the thyroid.

ATTACHMENT 12 Updates Update of Actual Data for 2003

ATTACHMENT 12 - Addendum to the 2003 Report ATTACHMENT 1 Summary Data Page 1 of 2 Unit 1 _ Unit 2 X Reporting Period January - December 2003 Liquid Effluents:

10CFR20.1001-20.2402, Appendix B, Table 2, Column 21 Average MEC - pCilml (Otr. 1) = NiAA Average MEC - pCi/ml (Qtr. 3) = 3.48E-03 Average MEC - pCi/ml (Qtr. 2) = NLA Average MEC - pCi/ml (Otr. 4) = N/A Average Energy (Fission and Activation gases - Mev):

Qtr. 1: iy = 6.78E-01 2.84E-01 Qtr. 2: Py 3.43E-091= j9E-01 Qtr. 3: E = 3.81E-01 Ep = 2.63E-01 Qtr. 4:y = 5.78E-01 Ep = 2.27E-01 Liquid:

Number of batch releases  : 16 Total time period for batch releases (hrs)  : 5.11 E+01 Maximum time period for a batch release (hrs): 3.30E+00 Average time period for a batch release Ihrs) : 3.19E+00 Minimum time period for a batch release (hrs): 2.95E+00 Total volume of water used to dilute the liquid effluent during the release 18 2nd 3d 4 th period (L) 4.OOE+08 __

Total volume of water available to dilute the liquid effluent during reporting v 2nd 3rd 4th Period (L)  : 1.14E+10 1.28E+10 1.44E+10 1.23E+10 Gaseous (Emergency Condenser Vent): 'Not Applicable for Unit 2 Number of batch releases NIA 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): N/A

_Primary Containment Purge):

Gaseous Number of batch releases  : 11 Total time period for batch releases (hrs)  : 1.96E+02 Maximum time period for a batch release (hrs): 4.88E+01 Average time period for a batch release (hrs) : 1.79E+01 Minimum time period for a batch release (hrs) 3.12E+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 IOCFR20.1001-20.2402, Appendix B,Table 2. Column

2. Maximum Effluent Concentrations (MEC) numerically equal to ten times the IOCFR20.1001-20.2402 concentrations were adopted to evaluate liquid effluents.

ATTACHMENT 12 - Addendum to the 2003 Report ATTACHMENT 1 Summary Data Page 2 of 2 Unit 1 _ Unit 2 X Reporting Period January - December 2003 Abnormal Releases:

A. Liquids:

Number of releases 0 Total activity released NWA Ci

8. Gaseous:

Number of releases 1 Total activity released 5.24E-03 Ci BACKGROUND Valve 2ASR-VI 90 is located on the radwaste steam supply line which is common to the steam supply from the clean steam reboilers and the turbine gland sealing steam system. The valve is outside the RCA in the Screenwell Building above the Service Water Pump Rooms.

RELEASE A steam packing leak on 2ASR-V190 was identified on June 22, 2003. Operations requested status of the repair on 10/7/2003, it became apparent that the steam leak was outside the RCA; the condensate system was the source of water for this steam line; the potential exists for an unmonitored release of radioactivity through this packing leak, the screenwell atmosphere to the environment. The steam packing leakage was stopped on 10/9/2003.

ANALYSIS Local air and contamination surveys showed no detectable activity. The amount of radioactivity released during the period June 22, 2003 through 10/9/2003 was calculated to be 5.24E-03 Ci. This activity did not change the total activity and resulting dose in Attachment 2.

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