ML051300263

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Annual Radioactive Effluent Release Report January - December 2004
ML051300263
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
NMPE 1942
Download: ML051300263 (23)
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Text

NINE MILE POINT NUCLEAR STATION - UNIT 1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January - December 2004 Constellation Energy' Nine Mile Point Nuclear Station

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

1. TECHNICAL SPECIFICATION LIMITS 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 due to noble gases released in gaseous effluents from Nine Mile Point Unit 1 to areas 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 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 1 to areas 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. The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20, 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.
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

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 gross activity monitoring (calibrated against gamma isotopic analysis of a 4.OL Marinelli grab sample) of an isokinetic stack sample stream.

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

C) PARTICULATES Activity released from the main stack is determined by gamma spectroscopic analysis (at least weekly) 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 monthly samples taken with an air sparging/water trap apparatus. Tritium effluent activity is measured during purge and weekly when fuel is offloaded until stable tritium release rates are demonstrated.

E) EMERGENCY CONDENSER VENT EFFLUENTS The effluent curie quantities are estimated based on the isotopic distribution in the Condensate Storage Tank water and the Emergency Condenser shell water. Actual isotopic concentrations are found via gamma spectroscopy. Initial release rates of Sr-89, Sr-90 and Fe-55 are estimated by applying scaling factors to release rates of gamma emitters and actual release rates are determined from offsite analysis results. The activity of fission and activation gases released due to tube leaks is based on reactor steam leak rates using offgas isotopic analyses.

F) 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. Tritium concentration is estimated to be the same as the most recent analysis of the Condensate Storage Tank water. Initial release rates of Sr-89, Sr-90, and Fe-55 are estimated by applying scaling factors to release rates of gamma emitters and actual release rates are determined from post offsite analysis results.

G) SOLID WASTE Isotopic contents of waste shipments are determined by gamma spectroscopy analysis 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 X( Unit 2 _ Reporting Period January - December 2004 Liquid Effluents:

ODCM Required MEC = 10 x 10CFR20 Appendix B, Table 2, Column 2 There were no discharges of Liquid Radwaste requiring use of MEC to determine allowable release rate.

MECs for discharges from Emergency Condenser Vents are as follows:

Average MEC - pCi/ml (Qtr. 11 = 9.91E03 Average MEC - pCi/ml (Qtr. 3) = N/A Average MEC - pCi/ml (Qtr. 21 = MIA verage MEC - pCi/ml (Qtr. 4) N/A Average Energy (Fission and Activation gases - Mev):

Qtr. 1: y = 1.61E 01 Ep = 2.39E-01 Qtr. 2: Ey = 2.47E-01 Ep = 3.17E-01 Qtr. 3: Ey = 2.47E-01 Ep = 3.17E-01 Qtr. 4 Sy = N/A Ep = NA Liquid: Radwaste EC Vent Number of batch releases  : 0 2 Total time period for batch releases (hrs)  : N/A 1.03E+00 Maximum time period for a batch release (hrs)  : N/A 5.33E-01 Average time period for a batch release (hrs)  : N/A 5.17E-01 Minimum time period for a batch release (hrs)  : N/A 5.00E-01 Total volume of water used to dilute the liquid effluent during release 1" 2nd 3 Id 4 th period (L) . 7.33E+02 N/A N/A N/A Total volume of water available to dilute the liquid effluent during report 2d 3Id 4th period (L)  : 1.58E+07 N/A N/A N/A Gaseous - (There were three releases from the operation of the Emergency Condenser Vent):

Number of batch releases . 3 Total time period for batch releases (hrs)  : 1.1OE+00 Maximum time period for a batch release (hrs)  : 5.33E-01 Average time period for a batch release (hrsl  : 3.67E-01 Minimum time period for a batch release (hrs) 6.67E.02 Gaseous (Primary Containment Purge):

Number of batch releases  : 2 Total time period for batch releases (hrs)  : 1.57E+01 Maximum time period for a batch release (hrs) 1.03E+01 Average time period for a batch release (hrs)  : 7.86E+00 Minimum time period for a batch release (hrs)  : 5.40E+00

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

A. Liquids:

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

Number of releases 0 Total activity released N/A Ci

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

V . .

A. Fission & Activation oases

1. Total release CI 1,37E+/-00 1.71 E-01 5.OOE+01
2. Average release rate pCi/sec 1,74E-01 2.15E-02 2_

B. Iodines

1. Total Iodine-131 Ci 8.82E.05 1,13E04 1,92E-04 2,35E-04 3.OOE+01
2. Average release rate for period pCi/sec 1.12E-05 1.44E.05 2.42E-05 2,96E-05 C. Particulotes
1. Particulates with half-lives >8 days Ci 315E0 5.62E.04 4.14E.04 2,16E-03 3.OOE+01
2. Average release rate for period uCi/sec 5,02E.04 7Z15E05 5.21 E-05 2,72E-04
3. Gross alpha radioactivity Ci Z201 F-0 4.78E-05 5.95E-05 4.5?E-05 2.50E+0 I D. Tritium
1. Total release Ci 1.33E+01 8.12E400 1.13E+01 1.41 E.01 5.OOE+01
2. Average release rate for period pCi/sec 1.69E+00 1.03E+00 1,42E+00 .1.77E+00 E. Percent of Tech. Soec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose Limit (5 mR)  % 8,96E-06 6.28E.04 7.82E-04 2 Percent of Quarterly Beta Air Dose Limit (10 mrad)  % 6,64E20 2.57E-04 3.1 9E-04 2 Percent of Annual Gamma Air Dose Limit to Date (10 mR)  % 4,48E.06 3.1 4E-04 7.05E.04 7.05E.04 Percent of Annual Beta Air Dose Limit to Date (20 mrad)  % 3,32E.06 1,29E-03 1,45E-03 1.45E-03 Percent of Whole Body Dose Rate Limit (500 mrem/yr)  % 2,33E20 1,67E-04 2,06E.05 2 Percent of Skin Dose Rate Limit (3000 mrem/yr)  % 1,03E-07 5.85E.05 7.21E-06 0 Tritium. lodines. and Particulates (with half-lives greater than 8 davs)

Percent of Quarterly Dose Limit (7.5 mrem)  % 1.32E-01 6,18E.02 5,75E-02 1.58E-01 Percent of Annual Dose Limit to Date (15 mrem)  % 6.67E-02 9.78E-02 1.42E-01 2,22E-01 Percent of Organ Dose Rate Limit (1500 mrem/yr)  % 2,66E-03 1.24E.03 1.14E.03 3.1 4E-03 9

ATTACHMENT 3 Page I of 1 Unit I X Unit2_ Reporting Period January - December 2004 GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODE 2 1st 2nd 3rd 4th Nucildes Released QUARTER QUARTER QUARTER QUARTER

1. Fission Gases Argon-41 Ci .5 *5 S.

Krypton-85 Ci .5 *5 .5 Krypton-85m Ci S. .5 7. .5 S. .5 7. 7.

Krypton-87 Krypton-88 Ci Cl *5 .5 .5 7**

.5 .5 .5 5.

Xenon-127 Cl

.5 .5 55 55 Xenon-131m Ci 5* .5 *5 S.

Xenon-133 Ci

.5 .5 75 Xenon-133m Ci Xenon-135 Cl 5.

11,7501 .5

.5 Xenon-135m Ci 55 Zs 7* .5 5.

Xenon-137 Cl 5* .5 Xenon-138 Cl

2. lodines' Iodine-131 Cl 8.82E-05 1.13E-04 1,92E-04 2.35E-04 Iodine-133 Ci 1.33E-04 7.35E-06 1.77E-04 8.1 8E-05 Iodine-135 Cl
3. Particulates Strontium-89 Cl 1.34E-05 3.91E-05 Strontium-90 Ci Cesium-134 Cl Cesium-137 Ci 1.57E-05 8.86E-06 6.66E-06 Cobalt-60 CI 1,93E-0 3.99E-04 3.1 1E-04 1.48E-03 Cobalt-58 Ci 1.21 E-04 6.04E-06 7.59E-06 3.37F-05 Manganese-54 Ci 7.14E-04 9,25E-05 5,48E-05 2.87E-04 Barium-Lanthanum-140 Ci Antimony-125 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 655E*505 Iron-59 Cl Cesium-136 Ci Chromium-51 Cl 15.9ZE-04 5.07E-05 3.20E-05 Zinc-65 Ci Iron-55 CI 5,14E-04 7 *3,16E-04 Molybdenum-99 Ci Neodymium-147
4. Tritium Ci 7.16E+00 6.32E+00 8.35E+00 1.19E401 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. i .OOE-l1 I vCi/ml for required particulates, 1.OOE-1 2 pCi/ml for required lodines, and 1.OOE-06 pCI/ml for Tritium, as required by ODCM, has been verified.

2 Contributions from purges are included. There were no other batch releases during the reporting period.

ATTACHMENT 4 Page 1 of 2 Unit I Xt Unit2_ Reporting Period January - December 2004 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Ground level releases are determined in accordance with the Off-Site Dose Calculation Manual and Chemistry procedures.

CONTINUOUS MODE 2nd 3rd 4th QUARTER QUARTER QUARTER QUARTER

1. Fission Gases S.

Argon-41 Ci S.

Krypton-85 Cl Krypton-85m Cl 7*

7*

Krypton-87 Ci S.

Krypton-88 Cl **

Xenon-127 Ci .5 *P Xenon-131m Ci **

Xenon-133 Ci 1.43E-04 Xenon-133m Ci 7*_

Xenon-135 Ci 1.9OE-04 1.7FE-05 7*

0. .5 Xenon-135m Cl S.0 Z*-

Xenon-137 Cl zo5

.5 7*

Xenon-138 Ci

2. Iodines' Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci 00555 55
3. Particulates S. 55 55 5 Strontium-89 Ci Strontium-90 Ci 55 55 55 55 Cesium-134 Ci Cesium-137 Cl Cobalt-60 Ci 55 5S 55 5 Cobalt-58 Cl 5S . 5 55 Manganese-54 Ci 5* 55 5 55 Barium-Lanthanum-140 CI 5* ** 5
  • Antimony-125 Ci 5* 55 70 Niobium-95 Cl TO 55 Zs 5*

Cerium-141 Ci W55 5*0 5 Cerium-144 Cl *5 55 *5

  • Iron-59 Cl T5* 55 5* 5 Cesium-136 CI 55 55 5*5 Chromium-51 Cl S. 555*5 Zinc-65 Ci Iron-55 Ci L75E5 L9Es0 557E0 25*E0 Molybdenum-99 Ci Neodymium- 147 Cl
4. Tritium Ci 1 Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.

ATTACHMENT 4 Page 2 of 2 Unit I X Unit 2 Reporting Period January - December 2004 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Ground level releases are determined in accordance with the Off-Site Dose Calculation Manual and Chemistry procedures.

BATCH MODE 1st 2nd 4th QUARTER QUARTER QUARTER QUARTER

1. Fission Gases' Argon-41 Ci .. ..

4.

Krypton-85 Ci .. .. ..

Krypton-85m Ci Kryplon-87 Ci . .

Krypton-88 Ci .. ..

Xenon-127 Ci .. .. .

Xenon-131m Cl Xenon-133 Cl 1.09E-03 Xenon-133m Ci .. 44 Xenon-135 Ci .. .. .. ..

Xenon-135m Cl .. .. ..

Xenon-137 CI 07 Xenon-138 Cl _- -

2. lodines' Iodine-131 Cl 1.32E-08 ..

Iodine-133 Cl 1.20E-07 ..

Iodine-135 Cl .. .. .. ..

3. Particulgtes Strontium-89 Ci .. ..

Stronlium-90 Ci ...

Cesium-134 Ci ..

Cesium-137 Ci 1.74E-09 . .

Cobalt-60 Cl 8.10E-08 ..

Cobalt-58 Ci 3.06E-08 ..

Manganese-54 Cl 2.58E-08 To Barium-Lanthanum-140 Ci .. .. .

Antimony-125 Ci .. .. ..

Niobium-95 Ci .. .. ..

Cerium-141 Cl .. so ..

Cerium-144 Cl .. .. ..

Iron-59 Ci .

Cesium-136 Ci ..

Chromium-51 Ci .. ..

Zinc-65 Ci .. .. .. ..

Iron-55 Ci .. ..

Molybdenum-99 Ci . ..

Neodymium-147 Ci ..'l

4. Tritium Ci 4.38E+00 Concentrations less than Ihe lower limit of detection of the counting system used are Indicated with a double asterisk.

ATTACHMENT 5 Paae I of 2 Unit 1 X Unit 2 _ Reporting Period January - December 2004 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 3! 2nd 3rd 4th EST. TOTAL QUARTER' QUARTER QUARTER QUARTER ERROR. %

A. Fission & Activation Products

1. Total release (not Including Tritium, gases, alpha) Ci 1I84Ez06 44 44

.5.OOE+01

2. Average diluted concentration during reporting period pCi/ml 1.1715-11 so 44 B. Tritium
1. Total release Ci 4.84E-02 . . 5.OOE+01
2. Average diluted concentration during reporting period jCi/ml 3.08E-06 44 .. ..

C. Dissolved and Entrained Gases

1. Total release Ci 5.OOE4O1
2. Average diluted concentration during reporting period pCi/ml 44 44 44 *4 D. Gross Aloha Radioactivity
1. Total release C; 5.OOE+01 E. Volumes2
1. Prior to dilution Liters 3.79E+03 . .. 4. 5.OOE+01
2. Volume of dilution water used during release period Liters 7.33E+02 .. .. 5.OOE+0 I
3. Volume of dilution water available during reporting period Liters 1.58E+07 .. .. 5.OOE+01 F. Percent of Technical Specification Limits Percent of Quarterly Whole Body Dose Limit (1.5 mrem) 2.41E-02 44 ..

Percent of Quarterly Organ Dose Limit (5 mrem) 1.42E-02 . . 44 Percent of Annual Whole Body Dose Limit to Date (3 mrem) 1.20E-02 .. 4.

Percent of Annual Organ Dose Limit to Date (10 mrem) 7.09E-03 . ..

Percent of IOCFR20 Concentration Limit 3.11 E+01 .. ..

Percent of Dissolved or Entrained

.. 4 .. 4.

Noble Gas Limit (2.OOE-04 pCi/ml)

Liquid Batch Releases associated with Emergency Condenser operation are assumed to be discharged via storm drain in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2 Dilution water volumes based on SPDES report storm drain flow estimates for EC vent releases only.

ATTACHMENT 5 Page 2 of 2 Unit 1JX. Unit2_ Reporting Period January - December 2004 LIQUID EFFLUENTS RELEASED BATCH MODE1M Nucildes Released ISt QUARTER 2nd QUARTER 3rd QUARTER 4th QUAR-TER Strontium-89 Cl . . I" Strontium-90 Cl . .

Cesium-134 Cl Cesium-137 CI Iodine-131 CI Cobolt-58 CI 5.36E-08 Cobalt-60 CI 1.27E-06 Iron-59 CI Zinc-65 Ci ..

Manganese-54 Ci 5.15E-07 Chromium-51 Ci Zirconium-Niobium-95 Ci Molybdenum-99 Ci Technetium-99m Ci Barium-Lanthanum-140 Cl .

Cerium-141 Ci . . . .

Tungsten-187 Cl Iodine-133 Ci Iron-55 Ci Neptunium-239 Cl . .

Iodine-135 CI Dissolved or Entrained Gases Ci .

Tritium Cl 4.86E-02 No continuous mode release occurred during the report period as indicated by effluent sampling. Liquid Batch Releases associated with Emergency Condenser operation In January 2004 are reflected.

2 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 jCi/ml for required gamma emitting nuclides, I .OOE-05 pCi/ml for required dissolved and entrained noble gases and tritium, 5.OOE-08 pCilml for Sr 89/90, 1.OOE-06 pCi/ml for 1-131 and Fe-55, and 1.OOE-07 pCI/ml for gross alpha radioactivity, as Identified In the Off-Site Dose Calculation Manual, has been verified.

ATTACHMENT 6 Page 1 of 4 Unit 1 X( Unit 2 Reporting Period January - December 2004 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.1 TYPE Volume Activit I (in3 l(Ci)

A B C A B C

a. Spent Resins 5.55E+01 3.07E+01 Q (Dewatered) 0
b. Dry Active Waste 5.13E+02 2 Q 3.96E+00 Q 2 (Compactible and Non-Compoctible, Contaminated Equipment)
c. Irradiated Q Q 2 QQ Components, Control R od s_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
d. Other:

(to vendor for processing)

1. Sewage Sediment 2.72E+01 2 0 2,21 E-05 l Q
2. Torus Sediment 5.55E+00 Q Q 536E+00 I Q Q The estimated total error Is5.OOE+01%.

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

a. Spent Resins (Dewatered) Polv Liner General Deslan None Type A
b. Dry Active Waste Metal Box General Design None (Compactible and Non-Compactible, Contaminated Equipment)
c. Irradiated Components. Control Rods NA NIA N/A
d. Other: (To Vendor for Processing)
1. Sewage Sediment Metol Box Generol Deslan None
2. Torus Sediment Pao LvIner General Design None

ATTACHMENT 6 Pciae 3of 4 Unit I _X.. Unit2_ 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) Co-60 (1) 46.4 (2) Fe-55 (2) 33.5 (3) Mn-54 (3) 13.8 (4) Cs-137 (4) 4.4 (5) Other (5) 1.9

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

Nuclide Percent (1) Fe-55 (1) 76.6 (2) Co-60 (2) 17.2 (3) Mn-54 (3) 2.5 (4) Cs-137 (4) 2.2 (5) Other (5) 1.5

c. Irradiated Components. Control Rods Nuclide Percent
d. Other: (to Vendor for Processing)
1. Sewage Sediment Nuclide Percent (1) Co-60 (1) 79.3 (2) Mn-54 (2) 18.4 (3) Cs-137 (3) 2.3
2. Torus Sediment Nuclide Percent (1) H-3 (1) 97.8 (2) C-14 (2) 1.5 (3) Other (3) 0.7

ATTACHMENT 6 Page 4 of 4 Unit 1 X Unit 2 _ Reporting Period January -December 2004 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.3. SOLID WASTE DISPOSITION:

Number of Shipments Mode of Tronsportotion Destinotion Truck - Hiltmon Transport Duratek Services. Inc.

Truck - R & RTrucking RACE. LIC Truck - RACE Logistics. LLC RACE. LIC 10 Truck - HMmon Tronsport Studsvik Processina Facility. LLC B. IRRADIATED FUEL SHIPMENTS (DISPOSITION): There were no shipments.

Number of Shipments Mode of Tronsportotion Destination Q N/A

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

SUMMARY

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

The Unit 1 Off-Site Dose Calculation Manual (ODCM) was revised during the reporting period to clarify required alarm point for the offgas noble gas radiation monitor, provide separate minimum channel operable and actions for stack noble gas high and low range monitors, require two minimum channels operable for offgas process monitor, revise table notes to specify one less and two less operable actions for stack and offgas radiation monitors, revise table D 4.6.14-2 Instrument names to agree with table D 3.6.14-2, and to update BASES to delete the offgas monitor and effluent monitor historical reference and to clarify the offgas monitor and stack high range and low range functions. 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 do not adversely Impact the accuracy or reliability of effluent, dose, or setpolnt calculations. A copy of the ODCM, Revision 25 Is attached and a summary of the changes presented to and approved by the Station Operations Review Committee on January 20, 2004 Is provided below. The summary also Includes the iustification for the chanae.

aReVision 25 Page # New/Amended Descriptlon of Change Reason for Change 13.1-7 D 3.6.14.b Added a clarification that the This change was initiated to incorporate offgas process monitor alarm the resolution as determined by the setpoint Isset to ensure that the corrective action program (NM-2003-2431)

Offgas Process Monitor shall meet to the conflict between Technical the limits of Technical Specification Specification and ODCM indicated 3.6.15. setpoint limits for the Offgas Noble Gas monitor. The conclusion was that incorporating offgas monitors Into the effluent monitor table was only to establish consistent surveillance requirements and not for meeting dual regulatory criteria of O1CFR100 and IOCFR20.

13.1-8 Table D 3.6.14-2 Divided Instrument 1.a. Stack Noble This change Isconsistent with system Gas Monitor, into High Range and design which requires 2 High Range Low Range Monitors with High channels to effect Purge and Vent trip Range requiring two and Low and 1 Channel for Effluent Monitoring.

Range requiring 1 Minimum Previous requirement for only one channel Channels Operable. did not adequately provide for the trip function, although relevant practice has been to assure the appropriate operability.

13.1-9 Table D 3.6.14-2 Instrument 3, Condenser Air Ejector This change Isconsistent with the two-Monitor, changed to require 2 channel logic Isolation logic described in Minimum Channels Operable. NMP1 UFSAR Section VIII.C.3.1 Instrumentation Systems.

13.1-10 Table D 3.6.14-2 Note a. (Stack High Range This change provided to address addition Monitor) and Note g (Condenser Air of minimum channels operable 2 as Ejector Monitor) revised to provide discussed above (pages I 3.1.8 and 13.1 -

actions for 1 less and 2 less than the 9).

Minimum Channels required.

New Note i. added to provide actions for less than Minimum Required Channels for Stack Low Range Monitor.

13.1-9, Table D 3.6.14-2 and Changed Instrument titles to clarify This change provided clarity In 13.1-11 Table D 4.6.14-2 status as Process and Effluent applicability of limits.

and monitors consistent with change on 13.1-12 page 13.1-7 above.

I B 3.1-1 Bases for DLCO The Bases was updated to delete These changes are provided to more 3.6.14 and DSR 4.6.14 the historical Information on the accurately describe the monitoring and Offgas and Emergency Condenser trip functions.

Vent Monitors, to add information about the Offgas Technical Specification trip point and required operability and to clarify the stack effluent monitoring and isolation functions.

ATTACHMENT 8 Page 1 of 1 Unit 1 X Unit 2 _ Reporting Period January - December 2004

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

There were no changes to the Unit 1 Process Control Program (PCP) during the report period.

ATTACHMENT 9 Page 1 of 1 Unit 1 X Unit 2 _ Reporting Period January- December 2004

SUMMARY

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

ATTACHMENT 10 Page 1 of 3 Unit 1 X_ Unit 2 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 1 (NMP1) 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 NMP 1 stack and emergency condenser vent were evaluated for the inhalation pathway.

Dose due to aquatic pathways such as liquid effluents Isnot 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 is received through Inhalation of gaseous effluents released from NMP1 Stack and Emergency Condenser Vent.
  • Direct radiation pathway; dose resulting from the operation of NMP1, Nine Mile Point Unit 2 (NMP2) and the James A.

Fitzpatrick (JAF) Facilities.

Methodologies for Determining Dose for Applicable Pathways External Ground (Shoreline Sediment) oathwav Dose from the external ground (shoreline sediment) Isbased on the methodology in the NMP1 Offsite Dose Calculation Manual (NMP1 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-0i 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 3 Unit 1 X Unit 2 _ 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 is evaluated by utilizing the Inhalation equation in the NMP1 ODCMK as adapted 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 NMP I Stack and Emergency Condenser Vent for the time period exposure Is received:

NMP 1 Stack:

Variable Fisherman 3

X/Q (s/M ) 8.9E-06 Inhalation dose factor Table E-7 Regulatory Guide 1.109 3

Annual air Intake m /year (adult) 8000 Fractional portion of the year (hours) 0.0356 H-3 (pCi/Sec) 1.13E+06 Cr-51 (pCi/sec) 3.50E+00 Mn-54 (pCi/sec) 1.84E+01 Fe-55 (pCi/sec) 1.34E+01 Co-58 (pCi/sec) 2.01 E+00 Co-60 (pCi/sec) 9.30E+01 Sr-89 (pCi/sec) 2.23E+00 Cs-137 (pCi/sec) 6.58E-01 1-131 (pCi/sec) 2.29E+01 1-133 (pCi/sec) 1.13E+01 NMP1 Emer ency Condenser Vent:

Variable Fisherman

  • 3 X/Q (s/m1 6.63E-06 Inhalation dose factor Table E-7 Regulatory Guide 1.109 Annual air Intake m 3/year (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) 2.94E+05 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.

ATTACHMENT 10 Paae 3 of 3 Unit I X Unit 2 _ Reporting Period January - December 2004 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Direct Radiation Pathwav The direct radiation pathway Is evaluated In accordance with the methodology found In the NMP I 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 Isa 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) l1.15E-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 Exposed 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 NMPI during 2004:

TABLE 1 Exnosure Pathway Annual Dose Exposure Pathway Dose Type Fisherman (mRem)

Extemal Ground Whole Body 2.95E-03 Skin of Whole Body 3.44E-03 Inhalation Whole Body 5.40E-04 Maximum Organ Lung: 7.25E-04 Direct Radiation Whale Body 0.36 Based on these values the total annual dose received by a hypothetical maximum exposed member of the public inside the site boundary Isas follows:

TABLE 2 Annual Dose Summary Total Annual Dose for 2004 Fisherman Total Whole Body JmRemlrr 0.36 Skin of Whole Body (mRem) 3.44E-03 Maximum Organ WmRem) I Lung: 7.25E-04

ATTACHMENT 11 Page 1 of 2 Unit 1 X Unit2_ Reporting Period Januory - 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 40 CFR 190 annual dose limits.

The Intent of 40 CFR 190 requires that the effluents of Nine Mile Point Unit 1 (NMP1), as well as other nearby uranium fuel cycle facilities, be considered. In this case, the effluents of NMPI, Nine Mile Point Unit 2 (NMP2) and the James A. FitzPatrick (JAF) facilities must be considered.

40 CFR 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 NMP1, NMP2 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 Isreceived 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 NMPI, NMP2 and JAF facilities.

Methodologies for Determinina Dose for ADDlicable Pathways Fish Consumatlon Dose received as a result of fish consumption Isbased on the methodology specified In the NMPI Off-site Dose Calculation Manual (NMPI ODCM) as adapted from Regulatory Guide 1.109. The dose for 2004 is calculated from actual analysis results of environmental fish samples taken near the site discharge points. For this evaluation It Isassumed 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.

ATTACHMENT 11 Page 2 of 2 Unit I X Unit2_ Reporting Period January - December 2004 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Shoreline Sediment Dose received from shoreline sediment Isbased on the methodology in the NMP1 ODCM as adopted from Regulatory Guide 1.109. For this evaluation It is assumed 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.

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 pCl/g Dose Pathways Resultina 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 NMP1 ODCM. NMP2 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 NMP . 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 some location.

Dose Potentially Received by the Likely Most Exposed Member of the Public Outside the Site Boundary Durina 2004 I Exposure Pathway l Dose Type l 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-01 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 40CFR1 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.

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