Text

January - December 2002 Radioactive Effluent Release Report, Attachment 1 Through Section 4.2
	ML031290248
Person / Time
Site:	Nine Mile Point
Issue date:	05/01/2003
From:	Conway J; Constellation Energy Group
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML031290248 (126)
	v • d • e

NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT January - December 2002 Constellation I Energ Group Nine Mile Point Nucl ear Station

Page 1 of 2 NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2002 SUPPLEMENTAL INFORMATION Facility: Nine Mile Point Unit 2 Licensee: Nine Mile Point Nuclear Station, LLC

1. TECHNICAL SPECIFICATION ADMINISTRATIVE CONTROLS - (Off-Site Dose Calculation Manual (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 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 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/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 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 - December 2002 Liquid Effluents:

10CFR20.1001-20.2402, Appendix B, Table 2, Column 21 Average MEC - RiCi/ml (Qtr. 1) = 5.76E-03 Average MEC - pCi/ml (Qtr. 3) = 6.88E-03 Average MEC - iCi/ml {Qtr. 2) = 3.04E-03 Average MEC - FlCi/ml (Qtr. 4) = 8.17E-03 Average Energy (Fission and Activation gases - Mev):

Qtr. 1: Elgamma) = 4.27E-01 E(beta) = 2.79E-01 Qtr. 2: E(gamma) = 5.45E-01 E(beta) = 3.93E-01 Qtr. 3 E(gamma) = 1.59E-01 Elbeta) = 2.53E-01 Qtr. 4: E(gamma) = 6.96E-01 E(beta) = 6.01E-01 Liquid:

Number of batch releases : 57 Total time period for batch releases 4hrs) : 1.85E+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) : 3.13E+00 Total volume of water used to dilute the liquid effluent during the release il 2 d 3rd 4 th period (L) : 2.42E+08 4.30E+08 1.56E+08 3.17E+08 Total volume of water used to dilute the liquid effluent during reporting lo 2rd 3d 4th Period IL) : 1.13E+10 1.32E+10 1.38E+10 1.38E+10 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) : NIA 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 : 14 Total time period for batch releases (hrs) : 3.81E+02 Maximum time period for a batch release (hrs) : 1.08E+02 Average time period for a batch release (hrs) : 2.72E+01 Minimum time period for a batch release (hrs) : 4.57E+00 The Off-site Dose Calculation Manual limits 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, Reporting Penod January -December 2002 Unit 1 _ Unit 2 X penod.

Abnormal Releases: There were no abnormal releases during this report A. Liquids:

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

Number of releases 0 Total activity released NIA Ci

ATTACHMENT 2 Page 1 of 1 Unit 1 _ Unit 2 X Reporting Period January - December 2002 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL 1st 2nd 3rd 4th EST.

QUARTER QUARTER QUARTER QUARTER TOTAL ERROR. %

I I I A. Fission & Activation gases Ci 2.34E + 00 1.29E + 00 3.25E-01 9.99E+O0 5.00E+011

1. Total release

2. Average release rate j+/-Cilsec 3.02E-O1 1.64E-01 4.1 1E-02 1.25E+O0 B. lodines

1. Total lodine-131 Ci 1.69E-04 3.31 E-06 6.89E-06 1.84E-04 3.OOE+01

2. Average release rate for period ~LCi/sec 2.15E-05 4.21 E-07 9.49E-07 2.17E-05 C. Particulates

1. Particulates with half-lives >8 days Cl 1.12E-03 5.84E-04 1.26E-03 3.61E-04 3.OOE+01

2. Average release rate for period I.Ci/sec 1 .42E-04 7 .44E-05 1.74E-04 4.27E-05

3. Gross alpha radioactivity Cl 1.88E-05 1.86E-05 3.09E-05 1.50E-05 2.50E 401 D. Tritium Ci 1.09E+01 4.21E+00 7.15E+00 8.13E+00 5.001+011

1. Total release

2. Average release rate for period ItCilsec 1.40E+ 0 5.36E-01 9.85E-01 9.60E-01 E. Percent of ODCM Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose 2.27E-03 1.65E-03 1.05E-04 1.60E-02 Limit (5 mR)

Percent of Quarterly Beta Air Dose Limit 7.16E-05 5.51 E-05 9.16E-06 6.64E-04 (110 mrad)

Percent of Annual Gamma Air Dose Limit 1.13E-03 1.96E-03 2.01E-03 1.OOE-02 to Date (10 mR)

Percent of Annual Beta Air Dose Limit to 3.57E-05 6.29E-05 6.76E-05 3.99E-04 Date (20 mrad)

Percent of Whole Body Dose Rate Limit 8.93E-05 6.32E-05 4.03E-07 6.11 E-04 (500 mremlyr)

Percent of Skin Dose Rate Limit 1.79E-05 1.28E-05 8.62E-07 1.25E-04 (3000 mremlyr)

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

Percent of Quarterly Dose Limit 4.78E-02 1.OOE-02 1.60E-02 5.401E-02 (7.5 mrem)

Percent of Annual Dose Limit 2.41 E-02 2.90E-02 3.70E-02 6.42E-02 (15 mrem)

Percent of Organ Dose Rate Limit 9.64E-04 2.02E-04 3.47E-04 1.01E-03 (1500 mrem/yr) J ... -

ATTACHMENT 3 Page 1 of 1 Unit 1 _ Unit 2 X Reporting Period January - December 2002 GASEOUS EFFLUENTS - ELEVATED RELEASE 2

CONTINUOUS MODE 1'st 2nd 3rd 4th Nuclides Released QUARTER QUARTER QUARTER QUARTER

, I

1. Fission Gases' Argon-41 Ci 2.07E-01 2.53E-01 **

9.18E-02 Krypton-85 Ci *- 44 Krypton-85m Ci 1.7fE-+00 7.93E-01 3.25E-01 2.15E+00 Krypton-87 Ci **

1.74E-01 Krypton-88 Ci 2.03E-0Oi 2.79E-02 **

1.96E+00 Xenon-1 27 Ci 44_

Xenon-1 31 m Ci **

Xenon-1 33 Ci **

1.16-E+OO Xenon-1 33m Ci Ci 8.1 E-02 4*

5.84E-01 Xenon-1 35 Xenon-135m Ci 7.83E-02 1.29E-02 **

4.49E-01 Xenon-1 37 Ci 5.17E-02 44 1.92E + 00 Xenon-1 38 Ci *4 1.52E-01 1.49E + 00

2. Iodines1 lodine-1 31 Ci 1.24E-04 3.31E-06 6.89E-06 1.84E-04 lodine-1 33 Ci 7.16E-05 5.07E-05 1.53E-03 Ci ** ** ** 44 lodine-1 35

3. Particulates1 Strontium-89 Ci 7.54E-06 Strontium-90 Ci Cesium-1 34 Ci 44 44 *

44 Cesium-1 37 Ci Cobalt-60 Ci 2.08E-05 3.32E-05 3.79E-05 4.47E-05 Cobalt-58 Ci 3.72E-06 Manganese-54 Ci 7.43E-06 1.08E-05 Barium-Lanthanum-140 Ci 44 ** ** 44 44 44 ** 4V Antimony-1 25 Ci Niobium-95 Ci 44 ** ** 4*

44 4* ** 4*

Cerium-141 Ci Cerium-1 44 Ci 44 44 44 4*

4* ** ** **

Iron-59 Ci Cesium-1 36 Ci Chromium-51 Ci ** 44 ** **

Zinc-65 Ci ** 44 4* **

Iron-55 Ci 4.01E-05 ** **

44 ** ** **

Molybdenum-99 Ci 4* ** ** *4 Silver-11 Om Ci Zirconium-95 Ci 1.97E-06

4. Tritium Ci 9.25E+00 2.66+00 5.89E+00 6.57E+00 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 pCi/ml for required noble gases, 1.OOE-1 1 pCi/ml for required particulates, 1.OOE-12 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 Contributions from purges are included.

ATTACHMENT 4 Page 1 of 2 Unit 1 _ Unit 2 X Reporting Period January - December 2002 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE 1st - 2nd 3rd 4th QUARTER QUARTER QUARTER QUARTER

1. Fission Gases' Argon-41 Ci **

4*

Krypton-85 Ci 4_*

2.83E-05 Krypton-85m Ci 7**

44 Krypton-87 CI 4T*

Krypton-88 CI **

Xenon-1 27 Ci 4* **

Xenon-1 31 m Ci **

Xenon-1 33 Ci 4*

4*V 4*

Xenon-133m Ci ** **

Xenon-135 Ci 44 Xenon-135m Ci 4T*

Xenon-137 C1 Xenon-1 38 Ci

2. Iodines1 Cl 4.45E-05 lodine-1 31 Ci **V **3.76E-05 Iodine-133 ** ** ** **

lodine-1 35 Ci

3. Particulates' 4* 4* 4* .,

Strontium-89 Cl Strontium-90 Cl Cesium-1 34 Ci Cesium-1 37 Ci *7*2.79E-06 * **

Cobalt-60 Ci 2.21 E-04 2.75E-04 4.53E-04 2.36E-04 Cobalt-58 Ci 4.83E-06 1.65E-05 Manganese-54 Cl 1.24E-04 2.26E-04 3.39E-04 5.88E-05 Barium-Lanthanum-140 Cl ** ** ** 44 Antimony-1 25 Cl ** ** ** **

Niobium-95 Cl ** ** ** **

Cerium-141 Cl ** 4* ** **

Cerium-1 44 Ci Iron-59 Cl **1.43E-05 2.47E-05**

- ** ** 44 Cesium-1 36 Cl Chromium-51 Cl Zinc-65 Cl **2.18E-05 9.60E-05 1.60E-05 Iron-55 Ci 7.OOE-04 **2.81 E-04**

Molybdenum-99 Ci * * ** 8.85E-06**

Silver-1 1 Om Ci

4. Tritium Ci ti.69E+O00 1.55E+O00 1.26E +00 1.57E+O00 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 1.OOE-04 j.Ci/ml for required noble gases, 1.OOE-1 1 gCi/ml for required particulates, 1.OOE-12 piCi/ml for required lodines, and 1.OOE-06 +/-Ci/ml for Tritium, as required by the Off-Site Dose Calculation Manual (ODCM), has been verified.

ATTACHMENT 4 Page 2 of 2 Unit 1 Unit 2 X Reporting Period January - December 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 Gases1 Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 CI Krypton-88 Ci Xenon-1 27 Ci Xenon-131m Cl Xenon-1 33 Ci Xenon-1 33m Ci Xenon-1 35 Ci Xenon-135m Ci Xenon-1 37 Ci Xenon-1 38 Cl

2. lodines' lodine-131 Ci lodine-1 33 Ci lodine-1 35 Ci

3. Particulates1 Strontium-89 Ci Strontium-90 Ci Cesium-1 34 Ci Cesium-1 37 Cl Cobalt-60 Ci Cobalt-58 Ci Manganese-54 CI Barium-Lanthanum-140 Ci Antimony-125 Cl Niobium-95 Ci Cerium-141 Ci Cerium-144 CI Iron-59 Ci Cesium-136 Ci Chromium-51 Ci Zinc-65 Ci Iron-55 Ci Molybdenum-99 Ci Silver-i1 Om Ci

4. Tritium 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 .iCi/ml for required noble gases, 1.OOE-11ipCIml for required particulates, 1.OOE-12 pCi/ml for required lodines, and 1.OOE-06 plCi/ml for Tritium, as required by the Off-Site Dose Calculation Manual (ODCM),

has been verified.

ATTACHMENT 5 Page 1 of 2 Unit 1 _ Unit 2 X Reporting Period January - December 2002 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1st 2nd 3rd 4th EST. TOTAL QUARTER QUARTER QUARTER QUARTER ERROR, %

I I A. Fission & Activation Products

1. Total release (not including Cl 3.33E-02 8.79E-02 7.22E-03 1.01E-02 5.OOE+01 Tritium, gases, alpha)

2. Average diluted concentration 2.94E-09 6.65E-09 5.21E-10 7.31E-10

~tCi/ml during reporting period B. Tritium'

1. Total release Cl 4.69E+00 5.39E+00 2.48E+00 6.28E+00 5.OOE+01

2. Average diluted concentration jiCI/ml 4.14E-07 4.07E-07 1.79E-07 4.56E-07 during reporting period C. Dissolved and Entrained Gases2

1. Total release Ci *9 ** *9 ** 5.OOE+01

9 *f *f **

2. Average diluted concentration gCi/ml during reporting period D. Gross Alpha Radioactivity2

1. Total release Cl 6.44E-05 9.46E-05 2.46E-05 5.63E-05 5.OOE+01 E. Volumes

1. Prior to dilution Liters 1.24E+06 1.85E+06 7.08E+05 1.23E+06 5.001E+01

2. Volume of dilution water used Liters 2.42E+08 4.30E+08 1.56E+08 3.17E+08 5.OOE+01 during release period

3. Volume of dilution water available Liters 1.13E+10 1.32E+10 1.38E+10 1.38E+10 5.001E+01 during reporting period:

F. Percent of ODCM Limits Percent of Quarterly Whole Body Dose Limit (1.5 mrem) 2.25E-01 3.75E-01 2.77E-02 2.32E-02 Percent of Quarterly Organ Dose Limit (5 mrem) 2.79E-01 5.12E-01 3.55E-02 3.61E-02 Percent of Annual Whole Body Dose Limit to Date (3 mrem) 1.13E-01 3.00E-01 3.14E-01 3.26E-01 Percent of Annual Organ Dose Limit to Date (10 mrem) 1.40E-01 3.96E-01 4.14E-01 4.32E-01 Percent of 10CFR20 Concentration Limit 1.3 7.25E-03 1.36E-02 2.61 E-03 5.59E-03 Percent of Dissolved or Entrained Noble Gas Limit (2.OOE-04 ILCI/ml) 2.3

9* **

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

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 [tCi/ml for required gamma emitting nuclides, 1.OOE-05 pCi/ml for required dissolved and entrained noble gases and Tritium, 5.OOE-08 uCi/ml for Sr-89/90, 1.OOE-06 ItCilml for Fe-55 and 1.OOE-07 pCi/ml for gross alpha radioactivity, as required by the Off-Site Dose Calculation Manual (ODCM), has been verified.

3 The ODCM limits 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 5 Page 2 of 2 Unit 1 _ Unit 2 X Reporting Period January - December 2002 LIQUID EFFLUENTS RELEASED BATCH MODE 2 1st 2nd 3rd 4th Nuclides Released' QUARTER QUARTER QUARTER QUARTER Il Silver-1 1 Om 1.06E-04 1.04E-03 **

1.71 E-04 Arsenic-76 44 44 **

Gold-1 99 ** **

Barium-140 ** **

Cerium-141 **

Cerium-144 Cobalt-58 3.Oi E-04 1.911E-03 1.1E-04 6.91E-05 Cobalt-60 8.27E-03 2.88E-02 2.92E-03 3.58E-03 Chromium-51 6.27E-04 3.42E-03 3.47E-04 Cesium-1 34 4*

Cesium-136 44 Cesium-137 Copper-64 4*

4.71 E-05 1.41 E-03 Iron-55 1.19E-02 3.39E-03 1.29E-03 4.69E-04 Iron-59 8.86E-04 5.53E-03 1.17E-04 2.97E-04 lodine-1 31 lodine-I 32 Iodine-133 ** ** **

Lanthanum-140 Manganese-54 1 .03E-02 3.94E-02 2.55E-03 3.56E-03 Manganese-56 44 4*

Molybdenum-99 **

Sodium-24 **

Niobium-95 ** 3.6iE-05 **

Nickel-65 44 Neptunium-239 **

Antimony-1 24 44 3.51 E-04 **

4*

Strontium-89 44 4.

Strontium-90 44 2.96E-06 44 ** **

Strontium-92 **

Technecium-99m ** ** **

Tellurium-1 32 44 ** ** **

Tungsten-1 87 **

Zinc-65 8.48E-04 3.98E-03 2.29&E04 1.50E-04

- ** ***4 Zinc-69m Zirconium-95 4.02E-05 44 Zirconium-97 2.29E-04 Dissolved or Entrained Gases' Ci Ci 4.69E+00 5.39E+O00 6.28E+OO Tritium 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 j.Ci/ml for required gamma emitting nuclides, 1.OOE-05 gCi/ml for required dissolved and entrained noble gases and Tritium, 5.OOE-08 iCi/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), has been verified.

2 No continuous mode releases occurred during the reporting period.

ATTACHMENT 6 Page 1 of 7 Unit 1 _ Unit 2 X Reporting Period January - December 2002 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. TYPE Volume Activity 3

(m ) (CI)

Class Class A B C A B l C

1. Spent Resins (Dewatered) 5.83E+00 0 0 2.07E+01 0 0

2. Dry Active Waste (Compactible and 5.87E+00 0 0 1.58E+01 0 0 Non-Comoactible) I I I I

3. Suppression Pool Sludges 0 3.41E+00 0 0 2.80E+02 0

4. Other:

(to Vendor for Processing or Consolidation)

a. Dry Active Waste (Compactible 5.56E+02 0 0 7.91E+O0 0 0 and Non-Compactible) _

b. Spent Resins (Dewatered) 9.30E+01 0 0 3.68E+02 0 0

c. Other Waste (Contaminated Oil) 6.80E+01 0 0 1.42E-02 0 0

d. Evaporator Bottoms 1.75E+01 0 0 4.63E+01 0 0 The estimated total error is 5.OOE+01 %.

ATTACHMENT 6 Paqe 2 of 7 Unit 1 _ Unit 2 X Reporting Period January - December 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) Steel Liner STP None

3. Suppression Pool Sludges. HIC-Poly Type B None

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. Other Waste (Contaminated Oil) Metal Box STP None HIC STP None

d. Evaporator Bottoms

ATTACHMENT 6 Page 3 of 7 Unit 1 _ Unit 2 X Reporting Period January - December 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+OO (7) Other 1.86E+OO

2. Dry Compressible Waste (Compactible and Non-compactible):

Nuclide Percent (1) Fe-55 6.64E+01 (2) Mn-54 1.11E+01 (3) Co-60 8.98E+00 (4) Cr-51 6.45E+00 (5) Fe-59 3.50E+00 (6) Zn-65 1.79E+O0 (7) Co-58 1.02E+OO (8) Other 7.60E-01

3. Suppression Pool Sludges Nuclide Percent (1) Fe-55 6.38E+01 (2) Co-60 2.OOE+01 (3) Mn-54 9.14E+O0 (4) Zn-65 6.07E+O0 (5) Other 9.90E-01

ATTACHMENT 6 Page 4 of 7 Unit 1 _ Unit 2 X Reporting Period January - December 2002 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

4. Other: (to Vendor for Processing or Consolidation)

a. Dry Active Waste (Compactible and Non-Compactible)

Nuclide Percent (1) Fe-55 5.23E+01 (2) Zn-65 2.20E+01 (3) Co-60 1.34E+01 (4) Mn-54 6.46E+00 (5) Cr-51 2.88E+00 (6) Fe-59 1.57E+OO (7) Other 1.39E+O0

b. Spent Resins (Dewatered)

Nuclide Percent (1) Fe-55 3.94E+01 (2) Co-60 3.11 E+01 (3) Mn-54 1.50E+01 (4) Zn-65 1.05E+01 (5) Ni-63 1.04E+00 (6) Other 2.96E+00

c. Other 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+00 (6) Zn-65 1.79E+00 (7) Co-58 1.01E+00 (8) Other 8.OOE-01

d. Evaporator Bottoms Nuclide Percent (1) Fe-55 7.08E+01 (2) Co-60 2.1 1E+01 (3) Zn-65 4.34E+00 (4) Mn-54 2.27E+00 (5) Ni-63 1.27E+00 (6) Other 2.20E-01

ATTACHMENT 6 Page 5 of 7 Unit 1 _ Unit 2 X Reporting Period January - December 2002 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.3. SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 14 Truck GTS Duratek Oak Ridge, TN 5 Truck GTS Duratek Kingston, TN Truck Studsvik Processing Facility, LLC Erwin, TN 3 Truck Barnwell Waste Management Facility Barnwell, SC B. IRRADIATED FUEL SHIPMENTS (DISPOSITION): There were no shipments.

Number of Shipments Mode of Transportation Destination 0o NIA N/A

ATTACHMENT 6 Page 6 of 7 Unit 1 _ Unit 2 X Reporting Period January - December 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 - December 2002. These totals were reported separately from '10CFR61 Solid Waste Shipped for Burial" because waste classification and burial was performed by the vendors. The following data represents the actual shipments of our radwaste made to the off-site vendors (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 3

by vendor facilities prior to burial. (M ) (Ci) Error, %

6.74E+01 4.17E+02 5.00E+01 C.2 SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 77 Truck Clive. UT 16 Truck Barnwell, SC

ATTACHMENT 6 Page 7 of 7 Unit 1 Unit 2 X Reporting Period January - December 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.

WASTE OFFWSE-(in D. 1 TYPED.1TP Burial Volume 3

)

Activity (Ci) Error,Total Est. %

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

ATTACHMENT 7 Page 1 of 1 Unit 1 _ Unit 2 X Reporting Period January - December 2002

SUMMARY

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

The Unit 2 Off-Site Dose Calculation Manual (ODCM) Revision 23 was implemented in December 2002. Administrative changes were made to reflect a change in reportability of the Stack or Vent noble gas activity monitor inoperable from a 14-day special report to a corrective action process. The ODCM changes do not reduce the overall conformance with existing criteria in accordance with Technical Specifications. A copy of the ODCM, Revision 23 is attached. The following is a summary of the changes accepted by the Station Operations Review Committee.

Old Page # New Page # NewlAmended Change Reason for Change Section #

13.3-9 13.3-9 D 3.3.2 In F.2.2, replaces 'in lieu of another required Using the corrective action process report, prepare and submit to the NRC, rather than a Special Report does pursuant to D 4.1.1, a special report that:' not affect the levels of radioactive with 'Through a DER, determine: effluent control required by 10CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and does not adversely impact the accuracy of reliability of effluent, dose, or setpoint calculations. This is an administrative change.

13.3-9 13.3-9 D 3.3.2 In F.2.2(11 removed 'Identifies'. Editorial clarification.

13.3-9 13.3-9 D 3.3.2 In F.2.2(2) removed 'Outlines' and replaced Editorial clarification.

.action' with 'actions to be'

ATTACHMENT 8 Page 1 of 1 Unit 1 _ Unit 2 X Reporting Period January - December 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 - December 2002

SUMMARY

OF INOPERABLE MONITORS Radiation Monitors 2RMS-CAB170 (Stack Gaseous Effluent Monitoring System (GEMS) noble gas activity monitor) and 2RMS-CAB180 (Vent GEMS noble gas channel) were inoperable from 6/27/02 14:16 to 9113/02 16 09.

On 6/27/02 at 14:16, the exhaust stack was struck by two lightning strikes within 10 seconds of each other. The short duration between the two strikes did not allow sufficient time for the first strike to be completely discharged by the lightning suppression system. This resulted in an electrical surge which damaged the 10 2RMS-RAK1 70, and caused the GEMS system to fail.

The stack monitor was repaired on 7/9/02. After returning the stack monitor to service, the GEMS computer failure was identified. Repairs were not timely due to obsolescence of damaged components. On 9/13/02 all failed components had been identified and repaired/replaced, and the GEMS system was declared operable.

ATTACHMENT 10 Page 1 of 4 Unit 1 _ Unit 2 X Reporting Period January - December 2002 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Introduction An assessment of the radiation dose 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 2002.

This assessment considers the likely 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, fishing near the shoreline adjacent to the NMP Site was the onsite activity that resulted In the maximum dose received by a Member of the Public. Following September 11, 2001 access has been restricted and fishing by Members of the Public at locations on site Is prohibited Although fishing was not conducted during 2002 the annual dose to a fisherman was still evaluated.

In addition to the dose received by a fisherman, dose received by a member of the National Guard was also evaluated For this reporting period the National Guard was conservatively assumed to be a Member of the Pubiic.

Dose Pathways Dose pathways considered for this evaluation Included direct radiation, Inhalation and external ground (shoreline sediment or soil doses) In accordance with the NMP2 Off-site Dose Calculation Manual (ODCM) 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 stack and Vent were evaluated for the Inhalation pathway. Dose from liquid effluent pathways due to aquatic activities Isnot applicable since swimming Isprohibited and lake water Isnot utilized as a source of drinking water at NMPNS Dose to a fisherman is received through the following pathways while standing on the shoreline fishing:

External ground pathway, received from plant related radionuclides detected in the shoreline sediment,

Inhalation pathway, received through Inhalation of gaseous effluents released from NMP2 Stack and Vent and

Direct radiation pathway, resulting from the operation of NMP2, Nine Mile Point Unit 1 (NMP1) and James A. Fitzpatrick (JAF)

Similarly, dose to a member of the National Guard Isreceived through the following pathways while performing security functions at the site:

. Inhalation pathway, and

Direct radiation pathway Any dose received by a member of the National Guard through the external ground pathway Isconsidered Insignificant as compared to the dose received through Inhalation and direct radiation.

Methodologies for Determining Dose for Applicable Pathways External Ground (Shoreline Sediment) Pathway Dose from the external ground (shoreline sediment) Is based on the methodology In the NMP2 ODCM as adapted from Regulatory Guide 1.109. For this evaluation It Is assumed that the 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 2002 was calculated using the following Input parameters:

ATTACHMENT 10 Page 2 of 4 Unit 1 _ Unit 2 X Reporting Period January - December 2002 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY

Usage Factor = 312 hours0.00361 days 0.0867 hours 5.15873e-4 weeks 1.18716e-4 months (fishing 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per week. 39 weeks per year)

Density In grams per square meter = 40.000

Shore width factor = 0.3

Whole body and skin dose factor for each radionuclide = Regulatory Guide 1.109. Table E-6.

Fractional portion of the year = 1 (used average radionuclide concentration over total time period)

Average Cs-137 concentration = 0 20 pCI/g The total whole body and skin doses received by the maximum exposed fisherman from the external ground pathway Is presented In Table 1I Exposure Pathway Dose.

Inhalation Pathway The inhalation dose pathway is evaluated by utilizing the Inhalation equation in the NMP2 ODCM, as adapted from Regulatory Guide 1.109. The total whole body dose and organ dose received by the maximum exposed fisherman and member of the National Guard during 2002 Is calculated using the following Input parameters for gaseous effluents released from both the NMP2 Stack and Vent for the time period exposure is received:

NMP 2 Stack:

Variable Fisherman National Guard Average Stack flow rate (m/sec) 4 930E+01 5 012E+01 3 2.3E-05 X/Q (s/m ) 9.6E-07 Inhalation dose factor Regulatory Gu de 1.109 Table E-7 3 8000 Annual air Intake (m /year) (adult) 8000 Fractional portion of the year (hours) 0 0356 0.2630 H-3 (pCi/m) 1.278E+04 1.524E+04 3 1.402E-02 Mn-54 (pCi/m ) 1.264E-02 3 2.451 E-02 Fe-55 (pCi/m ) 0 OOE+00 Co-60 (pCI/m) 9.854E-02 8 622E-02 3 4.858E-03 Sr-89 (pCi/m ) 6 477E-03 Zr-95 (pCi/m3) 1.608E-03 1.206E-03 1-131 (pCi/m) 1.590E-01 1.950E-01 1-133 (pCi/m3) 1.292E+00 1.01 3E+00 NMP2 Vent:

Variable Fisherman l National Guard -

3 1.020E+02 Average Vent flow rate (m /sec) 1.01 0E+02 X/Q (s/m3) 2.8E-06 3.OE-07 Inhalation dose factor Regulatory Guide 1.109 Table E-7 3 8000 Annual air Intake (m /year) (adult) 8000 Fractional portion of the year (hours) 0.0356 0.2630

ATTACHMENT 10 Page 3 of 4 Unit 1 _ Unit 2 X Reporting Period January - December 2002 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY NMP2 Vent continued:

Variable Fisherman

National Guard' H-3 (pCI/m3 ) 1.822E+03 1.884E+03 Mn-54 (pCl/mn) 2.626E-01 2.349E-01 Fe-55 (jpCl/m) 1.21 OE-01 3 052E-01 Fe-59 (pCI/m&) 1.649E-02 1.237E-02 Co-58 (pCl/mr) 7.107E-03 6.810E-03 Co-60 (pCI/m) 4 045E-01 3.71 1E-01 Zn-65 (pCI/m) 5.682E-02 4 262E-02 Cs-137 (pCl/m) 1.141E-03 8 558E-04 Mo-99 (pCl/mn) 3.81 OE-03 2.858E-03 1-131 (pCI/mi) 0.OOE+00 1.363E-02 1-133 (pCI/m 3) 1.619E-02 1.215E-02

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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per week for 39 weeks per year equivalent to 312 hours0.00361 days 0.0867 hours 5.15873e-4 weeks 1.18716e-4 months for the year (fractional portion of the year = 0 0356)

Therefore, the Average Stock 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 maximum exposed member of the National Guard Isassumed to be on site 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per week for 48 weeks per year equivalent to 2304 hours0.0267 days 0.64 hours 0.00381 weeks 8.76672e-4 months per year (fractional portion of the year = 0 2630). Therefore average Stack and Vent flow rates and average radionuclide concentrations used to determine the dose are represented by first, second, third and fourth quarter gaseous effluent flow and concentration data.

The total whole body dose and maximum organ dose received by the maximum exposed fisherman and member of the National Guard from the Inhalation pathway Ispresented In Table 1, Exposure Pathway Dose.

Direct Radiation Pathway The direct radiation pathway Is evaluated 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 Isevaluated by the use of high sensitivity environmental Thermoluminescent Dosimeters (TLDs). Since fishing activitles occur between April 1

- December 31, TLD data for the second, third, and fourth quarters of 2002 from TLDs placed In the general area where fishing occurs were used to determine an average dose to the maximum exposed fisherman from direct radiation. The average dose to the maximum exposed member of the National Guard from direct radiation was determined from TLD data for the first second, third and fourth quarters 2002. All four quarters were used as a result of the assumption that the maximum exposed member of the National Guard spends 48 weeks per year onsite The following Isa summary of the average dose rates and assumed time spent on site used to determine the total dose received by both a maximum exposed fisherman and member of the National Guard Variable Fisherman National Guard Average Dose Rate (mRem/hour) 1.32E-03 2 11 E-04 Exposure time (hours) 312 2304

ATTACHMENT 10 Page 4 of 4 Unit 1_ Unit 2 X Reporting Period January - December 2002 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Total Doses received by the maximum exposed fisherman and member of the National Guard from direct radiation Is presented In Table 1, Exposure Pathway Dose.

Dose Received By The Maximum Exoosed Member Of The Public During 2002 The following Isa summary of the dose received by both the likely maximum exposed fisherman and likely maximum exposed member of the National Guard from Uquid and Gaseous effluents released from NMP2 during 2002:

Table 1 Exposure Pathway Dose Fisherman National Guard Exposure Pathway Dose Type (mRem/year) (mRem/year)

External Ground Whole Body 3 11 E-03 N/A Skin of Whole Body 3.62E-03 N/A Inhalation Whole Body 5.05E-05 5.86E-03 Maximum Organ Lung 8.03E-05 Thyroid: 7.23E-03 Direct Radiation Whole Body 0411 0.486 These doses are generally a result of the operation of NMP2, however, a portion of these doses for the direct radiation pathway may be attributable to the Nine Mile Point Unit 1 and James A. Fitzpatrick Facilities. Based on the above doses the total annual dose received by the maximum exposed Member of the Public as a result of their activities Inside the site boundary during 2002 are summarized below:

Table 2 Annual Dose Summary FIsherman National Guard Total Annual Dose for 2002 (mRem/year) (mRem/year)

Total Whole Body 0.414 0.487 Skin of Whole Body 3 62E-03 N/A Maximum Organ Lung: 8.03E-05 Thyroid: 7.23E-04

ATTACHMENT 11 Page I of 3 Unit I _ Unit 2 X Reporting Period January - December 2W32 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Introduction An assessment of radiation doses received by the likely most exposed Member of the Public located beyond the site boundary was conducted for the period January through December 2002 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 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 (NMP1) and the James A. FitzPatrick (JAF) facilities must be considered.

40 CFR 190 requires the annual radiation dose received by a Member 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 to the limits of 40 CFR 190.

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 likely most exposed Member of the Public, outside the site boundary, Isreceived through the following pathways-

Fish consumption pathway, received from plant radionuclides that have concentrated In fish that Is consumed by a Member of the Public,

Shoreline Sediment received as a result of an Individual's exposure to plant radionuclides deposited In the shoreline sediment, which Isused as a recreational area,

Deposition, Inhalation and Ingestion pathways resulting from gaseous effluents, this dose Is received through exposure of gaseous effluents released from NMP1, NMP2 and JAF operating facilities, and

. Direct Radiation pathway, resulting from the operation of NMP1, NMP2 and JAF facilities Methodologies for Determining Dose for ADplicable Pathways Fish ConsumDtion Dose received as a result of fish consumption Isbased on the methodology specified In the NMP2 Off-site Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. The dose for 2002 Iscalculated from actual analysis results of environmental fish samples taken near the site discharge points. For this evaluation It Isassumed that the likely most exposed Member of the Public consumes fish taken near the site discharge points.

The total dose received by the whole body and organs of the likely most exposed Member of the Public during 2002 Is calculated using the following Input parameters,

Average Cs-1 37 concentration 1.60E-02 pCi/g (wet)

Consumption Rate = 21 kg/yr

. Ingestion dose factor for Cs-1137 = Regulatory Guide 1.109 Table E-1 1

Fractional portion of the year = 1

ATTACHMENT 11 Page 2 of 3 Unit 1_ Unit 2 X Reporting Period January - December 2002 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY 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 is assumed that the likely most exposed Member of the Public spends 67 hour7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months s/year along the shoreline for recreational purposes.

The total dose received by the whole body and skin of the maximum exposed Individual during 2002 Is calculated using the following Input parameters:

Usage Factor = 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months per year

Density In grams per square meter = 40,000

Shore width factor = 0 3

Whole body and skin dose factor for each radionuclide = Regulatory Guide 1.109, Table E-6

Fractional portion of the year = 1

Average Cs-i 37 Concentration = 0.049 pCI/g Dose Pathways Resulting From Gaseous Effluents Dose received by the likely most exposed Member of the Public due to gaseous effluents Iscalculated In accordance with the methodology provided In the NMP2 ODCM, NMP1 ODCM, and the JAF ODCM. These calculations consider deposition.

Inhalation and ingestion pathways. The total sum of doses resulting from gaseous effluents from NMP1, NMP2 and JAF during 2002 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 shiner from the generating facilities, direct radiation from any overhead gaseous plumes, plume submersion and from ground deposition. This total dose Is measured by environmental Thermoluminescent Dosimeters (TLDs). The critical location Is based 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 2002 the closest residence and the critical downwind residence are at the same location.

Dose Received by a Member of the Public Outside the Site Boundary During 2002 The following Isa summary of doses received by the likely most exposed Member of the Public due to their activities outside the site boundary for 2002:

Exposure Pathway Dose Type Dose (mRem/year)

Fish Consumption Total Whole Body 0 0240 Total Maximum Organ Liver: 0 0366 Shoreline Sediment Total Whole Body 1.65E-04 Total Skin of Whole Body 1.93E-04 Gaseous Effluents Total Whole Body 1.18E-02 Total Maximum Organ Thyroid: 6.06E-02 Direct Radiation Total Whole Body No Dose

ATTACHMENT 11 Page 3 of 3 Unit 1 _ Unit 2 X Reporting Period January - December 2002 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Based on these values the maximum total annual dose received by the likely most exposed member of the public during 2002 Isas follows

Total Whole Body: 0.036 mRem / year

Total Skin of Whole Body: 1.93E-04 mRem / year

Maximum Organ: Thyroid 0.061 mRem / year 40 CFR 190 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. 0.061 mRem) and the maximum whole body dose (0.036 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 Off-Site Dose Calculation Manual (ODCM) Rev. 23

I EmrgyGmw-*

Nine W11. Point "10p Nudear station ZkrD NINE MILE POINT NUCLEAR STATION NINE MILE POINT UNIT 2 OFF-SITE DOSE CALCULATION MANUAL (ODCM)

DATE APPROVALS SIGNATURES REVISION 23 Prepared by: . ,9 /2-1 / R.o T. M. Kurtz Health Physicist Ii-.9 Z Reviewed by:

G. R Stinson Health Physicist Concurred by: /ee11V,,

T. G. Kulcz t Supervisor, Analysis Services 17-1 o0L L. A. Hopkins Plant General Manager B. S. Montgomery

"/2.-/ 0Z Man lr Enginjring ees

SUMMARY

OF REVISIONS Revision 23 (Effective December 2002)

PAGE DA TE I 3 3-13,14 August 2000 I 3.3-6 November 2000 I 4.0-1 November 2000 II 2-10,26,33-36,66,67,75,80 November 2000 ix, I 1.0-1, 1 1.0-2, I B 3.3-2, 14 1-1 & la, II 11, II 15, II 29, II 63, II 107, II 108 December 2001 I3.3-9 December 2002 i Unit 2 Revision 23 December 2002

TABLE OF CONTENTS PAGE List of Tables vii List of Figures ix Introduction x PART I - RADIOLOGICAL EFFLUENT CONTROLS I SECTION 1.0 DEFINITIONS - I 1.0-0 SECTION 2.0 Not Used SECTION 3.0 APPLICABILITY 13 0-0 D 3.1 Radioactive Liquid Effluents I3.1-1 D 3.1.1 Liquid Effluents Concentration I 3 1-1 D 3.1.2 Liquid Effluents Dose I 3.1-4 D 3.1.3 Liquid Radwaste Treatment System I 3.1-7 D 3.2 Radioactive Gaseous Effluents 13.2-1 D 3.2.1 Gaseous Effluents Dose Rate I 3.2-1 D 3.2.2 Gaseous Effluents Noble Gas Dose 1 3-2-4 D 3.2 3 Gaseous Effluents Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form I 3.2-7 D 3.2.4 Gaseous Radwaste Treatment System I 3.2-10 D 3.2.5 Ventilation Exhaust Treatment System I 3.2-12 D 3.2.6 Venting or Purging I 3.2-14 D 33 Instrumentation 13.3-1 D 3.3.1 Radioactive Liquid Effluent Monitoring Instrumentation I 3.3-1 D 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation I 3.3-7 D 3.4 Radioactive Effluents Total Dose I 3.4-1 D 3.5 Radiological Environmental Monitoring I 3.5-1 D 3.5.1 Monitoring Program I 3.5-1 D 3.5.2 Land Use Census I 3.5-13 D 3.5.3 Interlaboratory Comparison Program I 3.5-16 BASES IB 3.1-0 B31 Radioactive Liquid Effluents IB 3.1-1 B 3.1.1 Liquid Effluents Concentration IB 3.1-1 B 3.1 2 Liquid Effluents Dose IB 3.1-2 B 3.1.3 Liquid Radwaste Treatment System IB 3 1-3 ii Unit 2 Revision 23 December 2002

TABLE OF CONTENTS (Cont)

PAGE B 3.2 Radioactive Gaseous Effluents I B 3.2-1 B 3.2.1 Gaseous Effluents Dose Rate I B 3.2-1 B 3.2.2 Gaseous Effluents Noble Gas Dose I B 3-2-2 B 3.2 3 Gaseous Effluents Dose - Iodine-13 1, Iodine-133, Tritium, and Radioactive Material in Particulate Form IB 3.2-3 B 3.2.4 Gaseous Radwaste Treatment System IB 3.2-5 B 3.2.5 Ventilation Exhaust Treatment System IB 3 2-6 B 3.2.6 Venting or Purging IB 3.2-7 B 3.3 Instrumentation I B 3.3-1 B 3.3.1 Radioactive Liquid Effluent Monitoring Instrumentation I B 3.3-1 B 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation I B 3.3-2 B 3.4 Radioactive Effluents Total Dose I B 3.4-1 B 3.5 Radiological Environmental Monitoring I B 3.5-1 B 3.5.1 Monitoring Program I B 3.5-1 B 3 5.2 Land Use Census IB3 5-2 B 3.5.3 Interlaboratory Comparison Program I B 3.5-3 SECTION 4.0 ADMINISTRATIVE CONTROLS I 4.0-1 D 4.1 Reporting Requirements I4.1-1 D 4.1.1 Special Reports 14.1-1 D4.2 Major Changes to Liquid, Gaseous and Solid Radwaste Treatment Systems I 4.2-1 iii Unit 2 Revision 23 December 2002

TABLE OF CONTENTS (Cont)

SECTION SUBJECT REF SECTION PAGE PART II - CALCULATIONAL METHODOLOGIES II1 1.0 LIQUID EFFLUENTS II2 1.1 Liquid Effluent Monitor Alarm Setpoints II 2 1.1.1 Basis 3.1.1 II2 1.1.2 Setpoint Determination Methodology 3.3.1 II 2 1.1.2.1 Liquid Radwaste Effluent Radiation Alarm Setpoint II2 1.1.2.2 Contaminated Dilution Water Radwaste Effluent Monitor Alarm Setpoint Calculations II 5 1.1.2 3 Service Water and Cooling Tower Blowdown Effluent Radiation Alarm Setpoint II 6 1.2 Liquid Effluent Concentration Calculation 3 1.1 II7 DSR3 1.1.2 1.3 Liquid Effluent Dose Calculation Methodology 3.1.2 II 8 DSR 3.1.2.1 1.4 Liquid Effluent Sampling Representativeness Table D 3.1.1- 1 II 9 note b 1.5 Liquid Radwaste System Operability 3.1.3 1110 DSR 3.1.3.1 B 3.1.3 2.0 GASEOUS EFFLUENTS 1I 1 2.1 Gaseous Effluent Monitor Alarm Setpoints II 11 2.1.1 Basis . 3 21 11111 2.1.2 Setpoint Determination Methodology Discussion 3.3.2 H 11 2.1.2.1 Stack Noble Gas Detector Alarm Setpoint Equation II 12 2.1.2.2 Vent Noble Gas Detector Alarm Setpoint Equation 1 13 2.1.2.3 Offgas Pretreatment Noble Gas Detector Alarm Setpoint Equation II 14 2.2 Gaseous Effluent Dose Rate Calculation Methodology 3.2.1 II 15 2.2.1 X/Q and W, - Dispersion Parameters for Dose Rate, Table D 3-23 II 15 2.2.2 Whole Body Dose Rate Due to Noble Gases DLCO 3.2.1.a 11 16 DSR3.2.1 1 2 2.3 Skin Dose Rate Due to Noble Gases DLCO 3.2 L.a II 17 DSR 3.2. 1.1 iv Unit 2 Revision 23 December 2002

TABLE OFCONTENTS (Cont)

SECTION SUBJECT REF SECTION PAGE 2.24 Organ Dose Rate Due to 1-131, I-133, Tritium and DLCO 3.2.1.b Particulates with half-lives greater than 8 days DSR 3 2 1.2 II 18 2.3 Gaseous Effluent Dose Calculation Methodology 3.2.2 1 19 3.2.3 3.2.5 2.3 1 W, and W, - Dispersion Parameters For Dose, Table D 3-23 II 19 2.3.2 Gamma Air Dose Due to Noble Gases 3.2.2 1120 DSR3.2.2 1 2.3.3 Beta Air Dose Due to Noble Gases 3.3.2 1120 2.3.4 Organ Dose Due to I-13 1, I-133, Tritium and Particulates 3.2 3 with half-lives 3.2 5 Ii DSR 3.2.3.1 Z:

DSR 3.2.5.1 1120 I ii 24 I-133 and I-135 Estimation II21 25 Isokinetic Sampling II21 2.6 Use of Concurrent Meteorological Data vs. Historical Data II21 2.7 Gaseous Radwaste Treatment System Operation 3.2.4 II 21 28 Ventilation Exhaust Treatment System Operation 3 2.5 II22 3.0 URANIUM FUEL CYCLE 3.4 II23 3.1 Evaluation of Doses From Liquid Effluents DSR 3.1.2.1 II24 3.2 Evaluation of Doses From Gaseous Effluents DSR 3.2.2 1 II 26 3.3 Evaluation of Doses From Direct Radiation DSR 3.2.3.1 1126 3.4 Doses to Members of the Public Within the Site Boundary4.1 II26 4.0 ENVIRONMENTAL MONITORING PROGRAM 3.5 II 29 4.1 Sampling Stations 3.5 1 II29 DSR 3.5.1.1 4.2 Interlaboratory Comparison Program DSR 3.5.3.2 II 29 4.3 Capabilities for Thermoluminescent Dosimeters Used for Environmental Measurements 1130 v Unit 2 Revision 23 December 2002

TABLE OF CONTENTS (Cont)

SECTION SUBJECT REF SECTION PAGE Appendix A Liquid Dose Factor Derivation II 65 Appendix B Plume Shine Dose Factor Derivation II 68 Appendix C Dose Parameters for Iodine 131 and 133, Particulates and Tritium II72 Appendix D Diagrams of Liquid and Gaseous Radwaste Treatment Systems and Monitoring Systems II 82 Appendix E Nine Mile Point On-Site and Off-Site Maps II 105 vi Unit 2 Revision 23 December 2002

LIST OF TABLES PARTI - RADIOLOGICAL EFFLUENT CONTROLS TABLE NO TITLE PAGE D 3.1.1-1 Radioactive Liquid Waste Sampling and Analysis I 3.1-2 D 3.2.1-1 Radioactive Gaseous Waste Sampling and Analysis I 3.2-2 D 3.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation I 3.3-6 D 3.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation I 3.3-13 D 3.5.1-1 Radiological Environmental Monitoring Program I 3.5-6 D 3.5.1-2 Reporting Levels for Radioactivity Concentrations in

- Environmental Samples I 3.5-10 D 3.5.1-3 Detection Capabilities for Environmental Sample Analyses 1 3.5-11 Vll Unit 2 Revision 23 December 2002

LIST OF TABLES (Cont)

PARTHII- CALCULATIONAL METHODOLOGIES TABLE NO TITLE PAGE D 2-1 Liquid Effluent Detector Response 1132 D 2-2 thru D 2-5 Ai.3 Values - Liquid Effluent Dose Factor II 33 D 3-1 Offgas Pretreatment Detector Response - II37 D 3-2 Finite Plume - Ground Level Dose 1138 Factors from an-Elevated Release D3-3 Immersion Dose Factors II 39 4 D3-4 -i thru D 3-22 Dose And Dose Rate Factors, Ri II40 D-3-23 Dispersion Parameters at Controlling II 59 Locations, X/Q, W, and W. Values D 3-24 Parameters For the Evaluation of Doses to 11 60 Real Members of the Public From Gaseous And Liquid Effluents D 5.1 Radiological Environmental Monitoring II61 Program Sampling Locations viii Unit 2 Revision 23 December 2002

LIST OF FIGURES FIGURENO TITLE PA GE D 1.0-1 Site Area and Land Portion of Exclusion Area Boundaries 11.0-4 D 5.1-1 Nine Mile Point On-Site Map II 106 D5.1-2 Nine Mile Point Off-Site Map (page 1 of 2) 11107 D 5.1-2 Nine Mile Point Off-Site Map (page 2 of 2) II 108 ix Unit 2 Revision 23 December 2002

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the Technical Specifications Section 5.5.1. The previous Limiting Conditions for Operation that were contained in the Radiological Effluent Technical Specifications are now transferred to the ODCM as Radiological Effluent Controls. The ODCM contains two parts: Radiological Effluent Controls, Part I; and Calculational Methodologies, Part II. Radiological Effluent Controls, Part 1, includes the following: (1)

The Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification 5.5.1 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3. Calculational Methodologies, Part II, describes the methodology and parameters to be used in the calculation of liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints and the calculation of offsite doses due to radioactive liquid and gaseous effluents The ODCM also contains a list and graphical description of the specific sample locations for the radiological environmental monitoring program, and liquid and gaseous radwaste treatment system configurations.

The ODCM follows the methodology and models suggested byNUREG-0133 and Regulatory Guide 1.109, Revision 1. Simplifying assumptions have been applied in this manual where applicable to provide a more workable document.for implementing the Radiological Effluent Control requirements; this simplified approach will result in a more conservative dose evaluation for determining compliance with regulatory requirements.

The ODCM will be maintained for use as a reference and training document of accepted methodologies and calculations. Changes to the calculation methods or parameters will be incorporated into the ODCM to assure that the ODCM represents the present methodology in all applicable areas. Any changes to the ODCM will be implemented in accordance with Section 5.5.1 of the Technical Specifications x Unit 2 Revision 23 December 2002

- PART I - RADIOLOGICAL EFFLUENT CONTROLS Unit 2 Revision 23 I December 2002

Definitions 1.0 PART I - RADIOLOGICAL EFFLUENT CONTROLS SECTION 1.0 DEFINITIONS

, t Unit 2 Revision 23 I 1.0-0 December 2002

Definitions 1.0 1.0 DEFINITIONS

NOTE----------------------------------------------------

Technical Specifications defined terms and the following additional defined terms appear in capitalized type and are applicable throughout these specifications and bases.

TERM DEFINITION GASEOUS A GASEOUS RADWASTE TREATMENT SYSTEM shall be any system RADWASTE designed and installed to reduce radioactive gaseous effluents by collecting TREATMENT offgases from the main condenser evacuation system and providing for SYSTEM delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

MEMBER(S) MEMBER(S) OF THE PUBLIC shall include all persons who are not OF THE PUBLIC occupationally associated with the Nine Mile Point Nuclear Station and 1

James A. FitzPatrick Nuclear Power Plant. This category does not include employees of owners and operators of the Nine Mile Point Nuclear Station and James A. Fitzpatrick Nuclear Power Plant, their contractors or vendors Also excluded from this category are persons who enter the site to service equipment or to make deliveries This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with Nine Mile Point Nuclear Station and James A. FitzPatrick Nuclear Power Plant.

MILK SAMPLING A MILK SAMPLING LOCATION is a location where 10 or more head of LOCATION milk animals are available for collection of milk samples OFFSITE DOSE The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain CALCULATION the current methodology and parameters used in the calculation of offsite MANUAL doses that result from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the environmental radiological monitoring program.

The ODCM shall also contain: (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Program required by Specification 5.5.1 of Technical Specifications and, (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3.

(continued)

Unit 2 Revision 23 I 1.0-1 December 2002

Definitions 1.0 1.0 DEFINITIONS (continued)

TERM DEFINITION PURGE - PURGE and PURGING shall be the controlled process of discharging air PURGING or gas from a confinement to maintain temperature, pressure, concentration, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

REPORTABLE A REPORTABLE EVENT shall be any of those conditions specified in EVENT 10 CFR 50.73.

SITE BOUNDARY The SITE BOUNDARY shall be that line around the Nine Mile Point Nuclear Station beyond which the land is not owned, leased or otherwise controlled by the owners and operators of Nine Mile Point Nuclear Station and James A:Fitzpatrick Nuclear Power Plant. See Figure D 1.0-1.

SOURCE CHECK l A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

UNRESTRICTED An UNRESTRICTED AREA shall be any area at or beyond the SITE AREA BOUNDARY, access to which is not controlled by the owners and operators of Nine Mile Point Nuclear Station and James A. Fitzpatrick Nuclear Power, Plant for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the -

SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTILATION A VENTILATION EXHAUST TREATMENT SYSTEM shall be any EXHAUST system designed and installed to reduce gaseous radioiodine or radioactive TREATMENT material in particulate form in effluents by passing ventilation or vent SYSTEM exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered safety features (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

(continued)

Unit 2 Revision 23 I 1.0-2 December 2002

Definitions 1.0 1.0 DEFINITIONS (continued)

TERM DEFINITION VENTING VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

Unit 2 Revision 23 I 1.0-3 December 2002

Definitions NMP2 1.0 LIQUID

,DISCHARGE O /V T A E

Lycoming

-SITE AREA AND LAND PORTION OF EXCLUSION AREA BOUNDARIES SCALEMILE/4 SCALE - MILE S X Niagara Mohawk Power Corporation retains ownership in certain transmission line and switchyard facilities within the exclusion areo boundary. Access and usage are controlled by Nine Mile Point Nuclear Station, LLC by agreement.

Figure D 1.0-1 (Page 1 of 1)

Site Area and Land Portion of Exclusion Area Boundaries Unit 2 Revision 23 I 1.0-4 December 2002

PART I - RADIOLOGICAL EFFLUENT CONTROLS SECTION 3.0 APPLICABILITY Unit 2 Revision 23 I3.0-0 December 2002

Applicability 3.0 3.0 APPLICABILITY The Offsite Dose Calculation Manual (ODCM) Specifications are contained in Section 3.0 of Part I. They contain operational requirements, Surveillance Requirements, and reporting requirements.

Additionally, the Required Actions and associated Completion Times for degraded Conditions are specified The format is consistent with the Technical Specifications (Appendix A to the NMP2 Operating License)

The rules of usage for the ODCM Specification are the same as those for the Technical Specifications. These rules are found in Technical Specifications Sections 1.2, "Logical Connectors," 1.3, "Completion Times," and 1 4, "Frequency."

The ODCM Specifications are subject to Technical Specifications Section 3.0, "Limiting Condition for Operation (LCO) Applicability and Surveillance Requirement (SR) Applicability,"

with the following exceptions:

1. LCO 3.06, regarding support/supported system ACTIONS is not applicable to ODCM Specifications.

2. LCO 3.0.7, regarding allowances to change specified Technical Specifications is not applicable to ODCM Specifications.

3. Section 3.0 requirements are not required when so stated in notes within individual specifications Unit 2 Revision 23 1 3.0-1 December 2002

Liquid Effluents Concentration D 3.1 1 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.1 Liquid Effluents Concentration DLCO 3.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (Figure D 1.0-1) shall be limited to:

a Ten times the concentration specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases; and

b. 2 x 104 ,tCi/ml total activity concentration for dissolved or entrained noble gases APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of A.1 Initiate action to restore Immediately radioactive material concentration to within limits.

released in liquid effluents to UNRESTRICTED AREAS exceeds limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.1.1.1 Perform radioactive liquid waste sampling and activity In accordance with analysis Table D 3.1.1-1 DSR 3.1.1.2 Verify the results of the DSR 3.1.1.1 analyses to In accordance with assure that the concentrations at the point of release Table D 3.1.1-1 are maintained within the limits of DLCO 3 1 1.

Unit 2 Revision 23 I3.1-1 December 2002

Liquid Effluents Concentration D 3.1.1 TableD3.1.1-1 (Page 1 of 2)

Radioactive Liquid Waste Sampling and Analysis SAMPLE LOWER LIMIT OF SAMPLE SAMPLE ANALYSIS SAMPLE DETECTION LIQUID RELEASE TYPE TYPE FREQUENCY FREQUENCY ANALYSIS (LLD) (a)

I Batch Waste Release Grab Sample Each Batch (g) Each Batch (g) Principal 5 x 10'7 iCilml Tanks (b) Gamma Emutters (c)

a. 2LWS-TK4A b 2LWS-TK4B 1-131 Ix 104 p+/-Ci/ml c 2LWS-TK5A d 2LWS-TK5B Grab Sample One batchb31 31 days Dissolved and 1 x 10 5 peCirml days (g) Entrained Gases (gamma emitters) -

Proportional Each batch (g) 31 days H-3 1 x 10.

O-Clml Composite of grab samples Gross Alpha 1 x lo'" jCrIml (d)

Proportional Each batch (g) 92 days Sr-89 5 x lo-, , CiIml Composite of grab samples (d)

Sr-90 5 KIO'8 CdIml Fe-55 I x 10.6 FiCilml 2 Continuous Releases Grab Sample 31 days (e) 31 days (e) Principal 5 x 107 gCI/ml Gamma Emitters

a. Service Water (c)

Effluent A b Service Water Grab Sample 31 days (e) 31 days (e) 1-131 I x 106 Lci/mil Effluent B c Cooling Tower Blowdown Grab Sample 31 days (e) 31 days (e) Dissolved and I x I O-' pCsdml Entrained Gases (gamma emitters)

Grab Sample 31 days (e) 31 days (e) H-3 I x 10-iY pCi/ml Grab Sample 31 days (e) 31 days (e) Gross Alpha I x lo-" jiCi/ml Grab Sample 92 days (e) 92 days (e) Sr-89 5 x 10*' PCI/ml Grab Sample 92 days (e) 92 days (e) Sr-90 5 x 10'8 pCilml Grab Sample 92 days (e) 92 days (e) Fe-55 1 x 1046 pCmlrl

3. Continuous Release Grab Sample 31 days (f) 31 days (f) Principal 5 x 10*7 jICi/ml Gamma Emitters Auxiliary Boiler (c)

Pump Seal and Sample Cooling Grab Sample 92 days (f) 92 days (f) H-3 1 x lo-, pCI/mI Discharge (Service Water)

Unit 2 Revision 23 I 3.1-2 December 2002

Liquid Effluents Concentration D 3.1.1 Table D 3.1. 1-1 (Page 2 of 2)

Radioactive Liquid Waste Sampling and Analysis (a) The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 % probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal For a particular measurement system, which may include radiocheinical separation LLD = (4.66) (Sb)

(E) (V (2.22xlIO') (Y) eC>'t where:

LLD = The before-the-fact lower limit of detection (piCi per unit mass or volume),

Sb = The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E The counting efficiency (counts per disintegration),

V = The sample size (units of mass or volume),

2 22 x 106 = The number of disintegrations per minute per F&Ci, Y = - The fractional radiochemncal yield, when applicable, X= The radioactive decay constant for the particular radionuclide (seci), and At= The elapsed time between the mnidpount of sample collection and the time of counting (seconds)

Typical values of E, V, Y, and At should be used in the calculation It should be recognized that the LLD is defined as a before-the-fact limit representing the capability of a measurement system and not as an after-the-fact limut for a particular measurement.

(b) Abatch release is the discharge of liquid wastes of a discrete volume Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by the method described in Part II, Section 1 4 to assure representative sampling (c) The principal gamma emitters for which the LLD applies include the following radionuclides Mn-54, Fe-59, Co-5 8, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141 Ce-144 shall also be measured, butwith anLLD of 5 x 106pCi/m This list does notmeanthat only these nuclides are to be considered Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Technical Specification 5.6 3 in the format outlined in RG 1.21, Appendix B, Revision 1, June 1974 (d) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released (e) If the alarm setpoint of the effluent monitor is exceeded, the frequency of sampling shall be increased to daily until the condition no longer exists Frequency of analysis shall be mcreased to daily for principal gamma emitters andann ncident composite for H-3, gross alpha, Sr-89, Sr-90, and Fe-55.

(f) If the alarm setpoint of Service Water Effluent Monitor A and/or B is exceeded the frequency of sampling shall be increased to daily until the condition no longer exists Frequency of analysis shall be increased to daily for principal gamma emitters and an incident composite for H-3, gross alpha, Sr-89, Sr-90, and Fe-55.

(g) Complete prior to each release.

Unit 2 Revision 23 I 3.1-3 December 2002

Liquid Effluents Dose D3.1.2 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1 2 Liquid Effluents Dose DLCO 3 1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials released in liquid effluents from each unit to UNRESTRICTED AREAS (Figure D 1.0-1) shall be limited to.

a < 1.5 mrem to the whole body and < 5 mrem to any organ duriing any calendar quarter; and

b. < 3 mrem to the whole body and < 10 mrem to any organ during any calendar year.

APPLICABILITY: At all times ACTIONS

INTOTES.

1 LCO 3 0.3 is not applicable.

2. LCO 3.0.4 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated dose to a A.1 Prepare and submit to the 30 days MEMBER OF THE NRC, pursuant to D 4.1.1, a PUBLIC from the release Special Report that of radioactive materials in (1) Identifies the cause(s) for liquid effluents to exceeding the limit(s) and UNRESTRICTED AREAS (2) Defines the corrective exceeds limits actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with DLCO 3.1 2.

(continued)

Unit 2 Revision 23 I 3.1-4 December 2002

Liquid Effluents Dose D 3.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Calculated dose to a B.1 Calculate the annual dose to a Immediately MEMBER OF THE MEMBER OF THE PUBLIC PUBLIC from the release which includes contributions of radioactive materials in from direct radiation from the liquid effluents exceeds 2 units (including outside storage times the limits tanks, etc.).

AND B.2 Verify that the limits of DLCO Immediately -

3.4 have not been exceeded.

C. Required Action B.2 and C. 1 Prepare and submit to the 30 days Associated Completion NRC, pursuant to D 4.1.1, a time not met. Special Report, as defined in 10 CFR 20.2203 (a)(4), of Required Action A. I shall also include the following:

(1) The corrective action(s) to be taken to prevent recurrence of exceeding the limits of DLCO 3.4 and the schedule for achieving conformance, (2) An analysis that estimates the dose to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s), and (3) Describes the levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations.

Unit 2 Revision 23 I 3.1-5 December 2002

Liquid Effluents Dose D 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.1.2.1 Determine cumulative dose contributions from liquid 31 days effluents for the current calendar quarter and the current calendar year.

Unit 2 Revision 23 I 3.1-6 December 2002

Liquid Radwaste Treatment System D 3.1.3 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.3 Liquid Radwaste Treatment System DLCO 3.1.3 The liquid radwaste treatment system shall be OPERABLE.

APPLICABILITY: At all times:

ACTIONS

- -------------------------- N Or ES-----------------------------------------

1. LCO 3.0 3 is not applicable.

2 LCO 3.0.4 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive liquid waste A. 1 Prepare and submit to the 30 days being discharged without NRC, pursuant to D 4.1.1, a treatment. Special Report that includes.

(1) An explanation of why AND liquid radwaste was being discharged without Projected doses due to the treatment, identification of liquid effluent, from the any inoperable equipment unit, to UNRESTRICTED or subsystems, and the AREAS would exceed reason for the inoperability, 0.06 mrem to the whole (2) Action(s) taken to restore body or 0 2 mrem to any the inoperable equipment to organ in a 31 day period. OPERABLE status, and (3) Summary description of AND action(s) taken to prevent a recurrence.

Any portion of the liquid radwaste treatment system not in operation.

Unit 2 Revision 23 I 3.1-7 December 2002

Liquid Radwaste Treatment System D3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR3.1.3 1 --------------------------- NOTE-----------------------------

Only required to be met when liquid radwaste treatment systems are not being fully utilized.

Project the doses due to liquid effluents from each 31 days unit to UNRESTRICTED AREAS.

Unit 2 -

Revision 23 I 3.1-8 December 2002

Gaseous Effluents Dose Rate D3.2.1 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2 1 Gaseous Effluents Dose Rate DLCO 3.2.1 The dose rate from radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (Figure D 1.0-1) shall be limited to:

a For noble gases, < 500 mrem/yr to the whole body and

< 3000 mrem/yr to the skin and

b. For I-13 1, 1-13 3, H-3 and all radionuclides in particulate form with half-lives > 8 days,

1500 mrem/yr to any organ.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A The dose rate(s) at or A. 1 Restore the release rate to Immediately beyond the SITEwihntelmt BOUNDARY due to within the limit.

radioactive gaseous effluents exceeds limits SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.1.1 The dose rate from noble gases in gaseous effluents In accordance with shall be determined to be within the limits of DLCO Table D 3.2.1-1 3.2 l.a.

DSR 3.2 1.2 The dose rate from I-13 1, I-133, H-3 and all In accordance with radionuclides in particulate form with half-lives Table D 3.2 1-1

> 8 days in gaseous effluents shall be determined to be within the limits of DLCO 3 2 1.b Unit 2 Revision 23 13.2-1 December 2002

Gaseous Effluents Dose Rate D 3.2.1 Table D 3.2.1-1 (Page 1 of 2)

Radioactive Gaseous Waste Sampling and Analysis SAMPLE LOWER LIMIT OF GASEOUS RELEASE SAMPLE SAMPLE A,NALYSIS SAMPLE DETECTION TYPE TYPE FREQUENCY EQUENCY ANALYSIS (LLD) (a)

1. Containment (b) Grab Sample Each Purge (h) Principal I x 10 4jLCUml Gamma Emitters (c)

Each Purge H-3 (oxide) 1 x 10 6 iCi/ml Each Purge Principal 1 x lo- jCi/ml Gamma Emitters Wc) 2 Main Stack, Grab Sample 31 days (d) 31 days (d) Principal 1 x 104pCi/ml Radwaste/Reactor Gamma Emitters Building Vent (c)

Grab Sample 31 days (e) 31 days (e) H-3 (oxide) Ix 10'j+/-CLiml Charcoal Continuous (f) 7 days (g) I 131 lx 10.12 tCi/ml Sample Particulate Continuous (f) 7 days (g) Principal I x lo-,, Ceml Sample Gamma Emitters (c)

Gross Alpha Ix 1011 oCtfml Composite Continuous (f) 92 days Sr-89 1 x 10 " .LC/ml Particulate Sample Sr-90 01 1 x lo- LCdm]

See the notes on the next page.

Unit 2 Revision 23 I 3 2-2 December 2002

Gaseous Effluents Dose Rate D 3.2.1 Table D 3.2.1-1 (Page 2 of 2)

Radioactive Gaseous Waste Sampling and Analysis (a) The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability offalsely concluding that a blank observation represents a "real" signal For a particular measurement system, which may include radiochemical separation LLD (4 66

) (Sb)

(E) (V) (2.22x10 6 ) (Y) e~ 1 where-LLD = The before-the-fact lower limit of detection (pCi per unit mass or volume),

Sb= The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = The counting efficiency (counts per disintegration),

V The sample size (units of mass or volume),

2 22 x 106 The number of disintegrations per mnute per j.Ci, Y The fractional radiochemical yield, when applicable, A = The radioactive decay constant for the particular radionuclide (sec I), and t= The elapsed time between the midpoint of sample collection and the time of counting (seconds)

Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized that the LLD is defined as a before-the-fact limut representing the capability of a measurement system and not as an after-the-fact limit for a particular measurement.

(b) Sample and analysis before PURGE is used to detennine permissible PURGE rates Sample and analysis dunng actual PURGE is used for offsite dose calculations (c) The principal gamma enutters for which the LLD applies include the following radionuclides Kr-87, Kr-S8, .e-I33, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Ce-144 uinioduine andparticulate releases Thlist does not meanthat onlythese nuclides are to Cs-134, Cs-137, Ce-141 and are identifiable, together with those of the above nuclides, shall also be analyzed and reported in be considered Other gamma peaks that the pursuant to Technical Specification 563 in the format outied in RG .21, AppendLx B, Revision Radioactive Effluent Release Report 1, June 1974 (d) If the main stack or reactor/radwaste building isotopic monitor is not OPERABLE, sampling and following shutdown, startup, or when there is an alarm on the offgas pretreatment monitor analysis shall also be performed (e) H-3 grab samples shall be taken once every 7 days from the reactor/radwaste ventilation system when fuel is offloaded until stable H-3 release levels can be demonstrated.

(f) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period calculation made in accordance with DLCO 3 2.1 b and DLCO 3.2 3 covered by each dose or dose rate (g) When the release rate of the main stack or reactor/radwaste building vent exceeds its alarm setpomt, device shall be removed and analyzed to determine the changes in iodine and particulate release the iodine and particulate rates The analysis shall be done once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months until the release no longer exceeds the alarm setpoint. When samples collected corresponding LLDs may be increased by a factor of 10 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the (h) Complete prior to each release Unit 2 Revision 23 I 3.2-3 December 2002

Gaseous Effluents Noble Gas Dose D 3.2.2 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2 2 Gaseous Effluents Noble Gas Dose DLCO 3.2.2 The air dose from noble gases released in gaseous effluents from each unit to areas at or beyond the SITE BOUNDARY (Figure D 1.0-1) shall be limited to:

a During any calendar quarter: < 5 mrad for gamma radiation and

< 10 mrad for beta radiation and

b. During any calendar year: < 10 mrad for gamma radiation and

< 20 mrad for beta radiation APPLICABILITY: At all times.

ACTIONS

NOTES

1. LCO 3.0.3 is not applicable.

2. LCO 3.0.4 is not applicable CONDITION REQUIRED ACTION COMPLETION TIME The air dose at or beyond A.1 Prepare and submit to the 30 days the SITE BOUNDARY NRC, pursuant to D 4. 1.1, a due to noblegases releasedSpcaReotht in gaseous effluents Special Report that exceeds limits. (1) Identifies the cause(s) for exceeding the limit(s) and (2) Defines the corrective actions ihat have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with DLCO 3.2.2.

(continued)

Unit 2 Revision 23 1 3.2-4 December 2002

Gaseous Effluents Noble Gas Dose D 3.2.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Calculated dose to a B1 Calculate the annual dose to a Immediately MEMBER OF THE MEMBER OF THE PUBLIC PUBLIC from the release which includes contributions of radioactive materials in from direct radiation from the gaseous effluents due to units (including outside storage noble gases exceeds 2 times tanks, etc.)

the limits.

AND B.2 Verify that the limits of DLCO Immediately 3.4 have not been exceeded.

C. Required Action B.2 and C. 1 Special Report, as defined in 30 days Associated Completion 10 CFR 20 2203 (a)(4), of time not met. Required Action A 1 shall also include the following (1) The corrective action(s) to be taken to prevent recurrence of exceeding the limits of DLCO 3.4 and the schedule for achieving conformance, (2) An analysis that estimates the dose to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s), and (3) Describes the levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations Unit 2 Revision 23 I3.2-5 December 2002

Gaseous Effluents Noble Gas Dose D 3.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.2.1 Determine cumulative dose contributions for the 31 days current calendar quarter and current calendar year.

I Unit 2 Revision 23 I3.2-6 December 2002

Gaseous Effluents Dose 13 1, I-133, H-3 and Radioactive Material in Particulate Form D 3.2.3 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.3 Gaseous Effluents Dose - I-131, I-133, H-3 and Radioactive Material in Particulate Form DLCO 3.2.3 The dose to a MEMBER OF THE PUBLIC from I-13 1, I-133, H-3, and all radioactive material in particulate form with half-lives > 8 days in gaseous effluents released, from each unit, to areas at or beyond the SITE BOUNDARY (Figure D 1.0-1) shall be limited to:

a. During any calendar quarter: < 7.5 mrem to any organ and

b. During any calendar year: < 15 mrem to any organ APPLICABILITY: At all times ACTIONS

-- ----------------------NI OTES

1. LCO 3.0.3 is not applicable

2. LCO 3.0 4 is not applicable CONDITION REQUIRED ACTION COMPLETION TIME A The dose from I-13 1, I-133, A.I Prepare and submit to the NRC, 30 days H-3 and radioactive material pursuant to D 4 1.1, a Special in particulate form with half- Report that lives > 8 days released in (1) Identifies the cause(s) for gaseous effluents at or beyond exceeding the limit(s) and the SITE BOUNDARY (2) Defines the corrective actions exceeds limits that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with DLCO 3.2.3.

(continued)

Unit 2 Revision 23 I3.2-7 December 2002

Gaseous Effluents Dose - I-131, 1-133, H-3 and Radioactive Material in Particulate Form D 3.2.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Calculated dose to a B. I Calculate the annual dose to a Immediately MEMBER OF THE PUBLIC MEMBER OF THE PUBLIC from the release of radioactive which includes contributions from materials in gaseous effluents direct radiation from the units exceeds 2 times the limits. (including outside storage tanks, etc.).

AND B.2 Verify that the limits of DLCO Immediately 3.4 have not been exceeded.

C. Required Action B 2 and C. 1 Special Report, as defined in 10 30 days Associated Completion time CFR 20.2203 (a)(4), of Required not met Action A. 1 shall also include the following:

(I)The corrective action(s) to be taken to prevent recurrence of exceeding the limits of DLCO 3.4 and the schedule for achieving conformance, (2)An analysis that estimates the dose to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s), and (3)Descnbes the levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations.

Unit 2 Revision 23 13 2-8 December 2002

Gaseous Effluents Dose - I-131, 1-133, H-3 and Radioactive Material in Particulate Form D 3.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.3.1 Determine cumulative dose contributions for the 31 days current calendar quarter and current calendar year for I-13 1, I-133, H-3 and radioactive material in particulate form with half-lives > 8 days Unit 2 Revision 23 I 3.2-9 December 2002

Gaseous Radwaste Treatment System D 3.2.4 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2 4 Gaseous Radwaste Treatment System DLCO 3.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation.

APPLICABILITY: Whenever the main condenser air ejector system is in operation.

ACTIONS

N TOT]ES --------------------------------------

1. LCO 3.0.3 is not applicable.

2 LCO 3.0.4 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. The gaseous radwaste from A. I Restore treatment of gaseous 7 days the main condenser air radwaste effluent.

ejector system is being discharged without treatment.

B Required Action and B. 1 Prepare and submit to the 30 days

- Associated Completion NRC, pursuant to D 4.1 1, a Time not met. Special Report that includes the following:

(1) Identification of any inoperable equipment or subsystems and the reason for the inoperability, (2) Action(s) taken to restore the inoperable equipment to OPERABLE status, and (3) Summary description of action(s) taken to prevent a recurrence Unit 2 Revision 23 I 3.2-10 December 2002

Gaseous Radwaste Treatment System D 3.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.4 1 Check the readings of the relevant instruments to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ensure that the GASEOUS RADWASTE TREATMENT SVSTEM is functioning -

Unit 2 Revision 23 I 3.2-11 December 2002

Ventilation Exhaust Treatment System D 3.2.5 D 32 RADIOACTIVE GASEOUS EFFLUENTS D32 5 Ventilation Exhaust Treatment System DLCO 3.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE APPLICABILITY: At all times.

ACTIONS NOTES -----------------------------------------------

1. LCO 3 0.3 is not applicable

2. LCO 3.0 4 is not applicable CONDITION REQUIRED ACTION COMPLETION TIME A. The radioactive gaseous A. 1 Prepare and submit to the 30 days waste is being discharged NRC, pursuant to D 4 1 1, a without treatment Special Report that includes the following AND (1) Identification of any inoperable equipment or Projected doses in 31 days subsystems and the reason from iodine and particulate for the inoperability, releases, from each unit, to (2) Action(s) taken to restore areas at or beyond the the inoperable equipment to SITE BOUNDARY (see OPERABLE status, and Figure D 1.0-1) would (3) Summary description of exceed 0 3 mrem to any action(s) taken to prevent a organ of a MEMBER OF recurrence THE PUBLIC Unit 2 Revision 23 I 3.2-12 December 2002

Ventilation Exhaust Treatment System D 3.2.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2 5.1 -NOTE----------------------------

Only required to be met when the VENTILATION EXHAUST TREATMENT SYSTEM is not being fully utilized.

31 days Project the doses from iodine and particulate releases from each unit to areas at or beyond the SITE BOUNDARY.

Unit 2 Revision 23 I 3.2-13 December 2002

Venting or Purging D 3.2 6 D3 2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.6 Venting or Purging DLCO 3.2.6 VENTING or PURGING of the drywell and/or suppression chamber shall be through the standby gas treatment system APPLICABILITY MODES 1, 2, and 3 ACTIONS

-NOTES -----------------------------------------------

1. LCO 3.0 3 is not applicable 2 LCO 3.0 4 is not applicable CONDITION REQUIRED ACTION COMPLETION TIME A VENTING or PURGING A1 Suspend all VENTING and Immediately of the drywell and/or PURGING of the dry-well suppression chamber not and/or suppression chamber through the standby gas treatment system Unit 2 Revision 23 I 3 2-14 December 2002

Venting or Purging D 3.2 6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY I

DSR 3.2 6 1 The drywell and/or suppression chamber shall be Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months determined to be aligned for VENTING or PURGING before start of through the standby gas treatment system VENTING or PURGING AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter during VENTING or PURGING Unit 2 Revision 23 I 3 2-15 December 2002

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 D 3.3 INSTRUIvIENTATION D3.3 1 Radioactive Liquid Effluent Monitoring Instrumentation DLCO 3 3 1 The radioactive liquid effluent monitoring instrumentation channels shown in Table D 3 3 1-1 shall be OPERABLE with.

a The minimum OPERABLE channel(s) in service b The alarm/trip setpoints set to ensure that the limits of DLCO 3 1.1 are not exceeded.

APPLICABILITY: According to Table D 3 3 1-1 ACTIONS

NOTE= ------------------------------------------------

1. LCO 3.0.3 is not applicable.

2. LCO 3 0.4 is not applicable.

3 Separate condition entry is allowed for each channel CONDITION REQUIRED ACTION COMPLETION TIME A Liquid effluent monitoring A1 Suspend the release of Immediately instrumentation channel radioactive liquid effluents alarm/trip setpoint less monitored by the affected conservative than required. channel.

OR A.2 Declare the channel inoperable. Immediately OR A.3 Change the setpoint so it is Immediately acceptably conservative.

(continued)

Unit 2 Revision 23 I 3 3-1 December 2002

Radioactive Liquid Effluent Monitoring Instrumentation D 3 3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B One or more required B 1 Enter the Condition referenced Immediately channels inoperable in Table D 3.3 1-1 for the channel AND B.2 Restore inoperable channel(s) 30 days to OPERABLE status C As required by Required C 1 Analyze at least 2 independent Prior to initiating a Action B 1 and referenced samples in accordance with release in Table D 3.3.1-1 Table D 3 1.1-1.

AND C.2 ----------- NOTE----------------

Verification Action will be performed by at least 2 separate technically qualified members of the facility staff Independently verify the release Prior to initiating a rate calculations and discharge release line valving D As required by Required D1 Collect and analyze grab 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action B 1 and referenced samples for radioactivity at a in Table D 3 3.1-1. limit of detection of at least AND 5 x 10-7 pLCi/ml Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter (continued)

Unit 2 Revision 23 13 3-2 December 2002

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3 1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TINE E As required by Required E. 1 --------------- NOTE------------

Action B 1 and referenced Pump performance curves in Table D 3 3 1-1. generated in place may be used to estimate flow Estimate the flow rate during 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months actual releases.

AND Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter F As required by Required F. I Estimate tank liquid level Immediately Action B 1 and referenced in Table D 3 3.1-1 AND During liquid additions to the tank G Required Action B 2 and G 1 Explain in the next In accordance with associated Completion Radioactive Effluent Release Radioactive Time not met Report why the inoperability Effluent Release was not corrected in a timely Report manner H. Required Action and H. I Suspend liquid effluent Immediately associated Completion releases monitored by the Time for Condition C, D, inoperable channel(s) or E not met I Required Action and I I Suspend liquid additions to Immediately associated Completion Time the tank monitored by the for Condition F not met inoperable channel(s)

Unit 2 Revision 23 I3 3-3 December 2002

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 SURVEILLANCE REQUIREMENTS

NOTE --------------------------------------------------------

Refer to Table D 3.3 1-1 to determine which DSRs apply for each function SURVEILLANCE FREQUENCY DSR 3 3.1 1 Perform CHANNEL CHECK 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DSR 3.3 1 2 Perform CHANNEL CHECK by verifying indication 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on any of flow during periods of release. day on which continuous, periodic, or batch releases are made DSR 3.3 1 3 Perform SOURCE CHECK Prior to release DSR 3.3 1 4 Perform SOURCE CHECK 31 days DSR 3.3 1.5 Perform CHANNEL FUNCTIONAL TEST The 31 days CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the instrument indicates measured levels above the alarm/trip setpoint, and control room alarm annunciation occurs for instrument indication levels measured above the alarm setpoint, circuit failure, instrument indicating a downscale failure, or instrument controls not set in operate mode DSR 3-3 1 6 Perform CHANNEL FUNCTIONAL TEST 92 days (continued)

Unit 2 Revision 23 I 3.3-4 December 2002

Radioactive Liquid Effluent Monitoring Instrumentation D 3 3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY DSR 3 3.1 7 Perform CHANNEL FUNCTIONAL TEST The 184 days CHANNEL FUNCTIONAL TEST shall also demonstrate control room alarm annunciation occurs for instrument indication levels measured above the alarm setpoint, circuit failure, instrument indicating a downscale failure, or instrument controls not set in operate mode DSR 3 3.1 8 Perform CHANNEL CALIBRATION The initial 18 months CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST), standards that are traceable to NIST standards, or using actual samples of liquid effluents that have been analyzed on a system that has been calibrated with NIST traceable sources These standards shall permit calibrating the system over its intended range of energy and measurement. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used DSR 3 3.1 9 Perform CHANNEL CALIBRATION 11 months Unit 2 Revision 23 I 3 3-5 December 2002

Radioactive Liquid Effluent Monitoring Instrumentation D33 1 Table D 3.3 1-1 (page I of 1)

Radioactive Liquid Effluent Monitoring Instrumentation APPLICABILITY REQUIRED CONDITIONS OR OTHER CHANNELS REFERENCED SPECIFIED PER FROM REQUIRED SURVEILLANCE INSTRUMENT CONDITIONS INSTRUMENT ACTION B I REQUIREMENTS I Radioactivity Monitors Providing Alarm and Automatic Termination of Release Liquid Radwaste Effluent (a) I C DSR 3 3 11 Line DSR33 13 DSR33 15 DSR3.3 18 2 Radioactivity Monitors Providing Alarm but not Providing Automatic Temunation of Release a Service Water Effluent (a) 1 D DSR3 3 1 1 Line A DSR3314 DSR3 3 17 DSR3 3 1 8 b Service Water Effluent (a) I D DSR 3 3 11 Line B DSR 3 3 14 DSR 3 3 17 DSR 3 3 1.8 c CoolingTower-Blowdown (a) I D DSR33 11 Line DSR33 14 DSR33 17 DSR3 3 18

3. Flow Rate Measurement Devices a Liquid Radwaste (a) I E DSR 3 3 1 2 Effluent Line DSR 3 3 1 6 DSR33 19 b Service Water Effluent (a) 1 E DSR 3 3 1 2 Line A DSR 3 3 1 6 DSR 3.3 1 9 c Service Water Effluent (a) I E DSR 3 3 1 2 Line B DSR 3 3 1 6 DSR 3 3 1 9 d Cooling Tower (a) I E DSR3 3 12 Blowdown Line DSR3 3 1 6 DSR 3 3 1 9 4 Tank Level Indicating (b) 1 F DSR 3 3 1 1 Devices (c) DSR 3 3 16 DSR33 1 9 (a) During releases via thus pathway (b) During liquid addition to the associated tank (c) Tanks included in this DLCO are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have tank oerflows and surrounding area drains connected to the liquid radwaste treatment system, such as temporary tanks Unit 2 Revision 23 I 3.3-6 December 2002

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 D 33 INSTRUMENTATION D 3 32 Radioactive Gaseous Effluent Monitoring Instrumentation DLCO 3 3.2 The radioactive gaseous effluent monitoring instrumentation channels shown in Table D 3 3 2-1 shall be OPERABLE with a The minimum OPERABLE channel(s) in service.

b The alarm/trip setpoints set to ensure that the limits of DLCO 3 2.1 are not exceeded APPLICABILITY: According to Table D 3 3.2-1.

ACTIONS

-NOTES -----------------------------------------------

I LCO 3.0 3 is not applicable 2 LCO 3 0 4 is not applicable

3. Separate condition entry is allowed for each channel CONDITION REQUIRED ACTION COMPLETION TIME A Gaseous effluent A 1 Suspend the release of Immediately monitoring instrumentation radioactive gaseous effluents channel alarm/trip setpoint monitored by the affected less conservative than channel required OR A2 Declare the channel inoperable Immediately OR A3 Change the setpoint so it is Immediately acceptably conservative (continued)

Unit 2 Revision 23 13 3-7 December 2002

Radioactive Gaseous Effluent Monitoring Instrumentation D 3 3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B One or more channels B 1 Enter the Condition referenced Immediately inoperable in Table D 3.3 2-1 for the channel AND B 2 Restore inoperable channel(s) 30 days to OPERABLE status C As required by Required C 1 Place the inoperable channel 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action B 1 and referenced in the tripped condition in Table D 3 3 2-1 OR C 2 1 Take grab samples 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C 2 2 Analyze samples for gross 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from time activity of sampling completion (continued)

Unit 2 Revision 23 I 3 3-8 December 2002

Radioactive Gaseous Effluent Monitoring Instrumentation D3 3 2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required D. 1 Estimate the flow rate for the 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Action B 1 and referenced inoperable channel(s) in Table D 332-1. AND Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter E As required by Required E. I Continuously collect samples 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Action B 1 and referenced using auxiliary sampling in Table D 3.3 2-1. equipment as required in Table D 3 2 1-1 F As required by Required F 1.1 Take grab samples. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action B I and referenced in Table D 3 3.2-1 AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND F 12 Analyze samples for gross 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from time activity with a radioactivity of sampling limit of detection of at least completion 1 x 104 ViCi/ml AND F.2 1 Restore the inoperable 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months channel(s) to OPERABLE status OR F 2 2 Through a DER, determine 14 days (1) The cause(s) of the inoperability.

(2) The actions to be taken and the schedule for restoring the system to OPERABLE status.

(continued)

Unit 2 Revision 23 I 3.3-9 December 2002

Radioactive Gaseous Effluent Monitoring Instrumentation D 3 32 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action B 2 and G I Explain in the next In accordance with associated Completion Radioactive Effluent Release Radioactive Time not met Report why the inoperability Effluent Release was not corrected in a timely Report frequency manner H Required Action and H 1 Suspend gaseous effluent Immediately associated Completion releases monitored by the Time for Condition C, D, E inoperable channel(s) or F not met.

Unit 2 Revision 23 I 3.3-10 December 2002

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3 3.2.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DSR 3 3 2 2 Perform CHANNEL CHECK 7 days DSR 3 3.2 3 Perform SOURCE CHECK 31 days DSR 3 3 24 Perform CHANNEL FUNCTIONAL TEST The 31 days CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolation capability of this pathway and that control room alarm annunciation occurs if the instrument indicates measured levels above the alarm/trip setpoint (each channel will be tested independently so as to not initiate isolation during operation), and control room alarm annunciation occurs for instrument indication levels measured above the alarm setpoint, circuit failure, instrument indicating a downscale failure, and instrument controls not set in operate mode DSR 3.3 2 5 Perform CHANNEL FUNCTIONAL TEST. 92 days DSR 3 3.2 6 Perform CHANNEL FUNCTIONAL TEST The 92 days CHANNEL FUNCTIONAL TEST shall also demonstrate control room alarm annunciation occurs for instrument indication levels measured above the alarm setpoint, circuit failure, instrument indicating a downscale failure, and instrument controls not set in operate mode (continued)

Unit 2 Revision 23 I3 3-11 December 2002

Radioactive Gaseous Effluent Monitoring Instrumentation D 3 32 SURVEILLANCE REQUIREMENTS (continued)

I SURVEILLANCE FREQUENCY I

DSR 3 3.2 7 Perform CHANNEL CALIBRATION The initial 18 months CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST, or using actual samples of gaseous effluents that have been analyzed on a system that has been calibrated with NIST traceable sources These standards shall permit calibrating the system over its intended range of energy and measurement. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used The CHANNEL CALIBRATION shall also demonstrate that automatic isolation of this pathway occurs when the instrument channels indicate measured levels above the Trip Setpoint.

DSR 3.3 2.8 Perform CHANNEL CALIBRATION 18 months DSR 3 3 2 9 Perform CHANNEL CALIBRATION. The initial IS months CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST, or usina actual samples of gaseous effluents that have been anaOyzed on a system that has been calibrated with NIST traceable sources These standards shall permit calibrating the system over its intended range of energy and measurement For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used Unit 2 Revision 23 1 3 3-12 December 2002

Radioactive Gaseous Effluent Monitoring Instrumentation D332 Table D 3.3 2-1 (page 1 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation REQUIRED CONDITIONS APPLICABILITY OR CHANNELS REFERENCED OTHER SPECIFIED PER FROM REQUIRED SURVEILLANCE INSTRUMENT CONDITIONS INSTRUMENT ACTION B I REQUIREMENTS Offgas System a Noble Gas (a) 2 C DSR 3 3 21 Activity Monitor DSR 3 3 2 4

- Providing DSR 3 3 2 7 Alarm and Automatic Termination of Release b System Flovv-Rate (a) 1 D DSR 3 3 2 1 Measuring Device DSR 3 3 2 5 DSR 3 3 2 8 c Sample Flow- (a) 2 D DSR332 1 Rate Measuring DSR 3 3 2 5 Device DSR 3 3 2 g 2 Radwaste/Reactor Building Vent Effluent System a Noble Gas (b) I F DSR332 1 Activity Monitor DSR 3 3 2 3 (c) DSR3 326 DSR3329 b Iodine Sampler (b) I E DSR 3 3 2 2 c Particulate (b) I E DSR 3 3 2 2 Sampler d Flow-Rate (b) 1 D DSR3 3 21 Monitor DSR 3 3 2 5 DSR332 8 e Sample Flow- (b) I D DSR3 3 21 Rate Monitor DSR 3 3 2 5 DSR3 328 (continued)

(a) During offgas system operation (b) At all times (c) Includes high range noble gas monitonng capability Unit 2 Revision 23 I 3 3-13 December 2002

Radioactive Gaseous Effluent Monitoring Instrumentation D 3 3.2 Table D 3 3.2-1 (page 2 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation REQUIRED CONDITIONS APPLICABILITY OR CHANNELS REFERENCED OTHER SPECIFIED PER FROM REQUIRED SURVEILLANCE INSTRUMENT CONDITIONS INSTRUMENT ACTION B I REQUIREMENTS 3 Main Stack Effluent a NobleGas (b) I F DSR332.1 Activity Monitor DSR 3 3 2.3 (c) DSR3 326 DSR 3 3 2 9 b Iodine Sampler (b) I E DSR 3 3 2 2 c Particulate (b) I E DSR 3 3.22 Sampler d Flow-Rate (b) I D DSR 3 3 2 1 Momtor DSR 3 3 2 5 DSR 3.32 S e Sample Flow- (b) I D DSR3321 Rate Morutor DSR 3 3 2.5 DSR332S (b) At all tunes (c) Includes high range noble gas monitoring capability Unit 2 Revision 23 I 3 3-14 December 2002

Radioactive Effluents Total Dose D3 4 D 34 RADIOACTIVE EFFLUENTS TOTAL DOSE D 3.4 Radioactive Effluents Total Dose DLCO 3.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to < 25 mrem to the whole body or any organ, except the thyroid, which shall be limited to < 75 mrem APPLICABILITY At all times ACTIONS

-N------------------N OTES

1. LCO 3 0 3 is not applicable 2 LCO 3 0 4 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A Estimated dose or dose A. 1 Venfv the condition resulting in Immediately commitment due to direct doses exceeding these limits has radiation and the release of been corrected radioactive materials m liquid or gaseous effluents exceeds the limits B Required Action and B. 1 --------------NOTE-------------

associated Completion Time This is the Special Report required notmet. byD3 1.2,D322,orD323 supplemented with the following Submit a Special Report, 30 days pursuant to D 4.1.1, including a request for a vanance in accordance with the provisions of 40 CFR 190 This submission is considered a timely request, and a vanance is granted until staff action on the request is complete.

Unit 2 Revision 23 1 3.4-1 December 2002

Radiological Environmental Monitoring Program D3.5 1 D3 5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5 1 Monitoring Program DLCO 3.5 1 The Radiological Environmental Monitoring Program shall be conducted as specified in Table D 3 5 1-1 APPLICABILITY At all times ACTIONS IT T C?

_________________-__________---------------------------- INU' X,3 - - - - - - - - - - - - - - - - - - - - - - - -

L LCO 3.0 3 is not applicable 2 LCO 3 0 4 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A Radiological Environmental A 1 Prepare and submit to the NRC In accordance with Monitoring Program not in the Annual Radiological the Annual conducted as specified in Environmental Operating Report, Radiological Table D 3 5. 1-1. a description of the reasons for Environmental not conducting the program as Operating Report required and the plans for frequency preventing a recurrence B Level of radioactivity in an B 1 ------------ NOTES-------------

environmental sampling 1. Only applicable if the medium at a specified location radioactivity/radionuclides are exceeds the reporting levels of the result of plant effluents.

Table D 3 5 1-2 when 2For radionuclides other than averaged over any calendar those in Table D 3 5 1-2, this quarter report shall indicate the methodology and parameters OR used to estimate the potential annual dose to a MEMBER OF THE PUBLIC (continued)

Unit 2 Revision 23 I3 5-1 December 2002

Radiological Environmental Monitoring Program D 3.5 1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME More than one of the Prepare and submit to the NRC, 30 days radionuclides in Table pursuant to D 4.1 1, a Special D 3.5 1-2 are detected in the Report that environmental sampling (1) Identifies the cause(s) for medium and exceeding the limit(s) and (2) Defines the corrective actions Concentration I + to be taken to reduce reporting level I radioactive effluents so that the potential annual dose to a concentration 2 + ... 2 1.0 MEMBER OF THE PUBLIC reporting level 2 is less than the calendar year limits of D 3 1 2, D 3 2 2, or OR D323 Radionuclides other than OR those in Table D 3.5 1-2 are detected in an environmental B2 ------------ NOTES-------------

sampling medium at a 1 Only applicable if the specified location which are radioactivity/radionuclides are the result of plant effluents not the result of plant effluents and the potential annual dose 2 For radionuclides other than to a MEMBER OF THE those in Table D 3 5 1-2, this PUBLIC from all report shall indicate the radionuclides is 2 the methodology and parameters calendar year limits of used to estimate the potential D3.1 2,D 3.22 orD3 23 annual dose to a MEMBER OF THE PUBLIC In accordance with Report and describe the condition the Annual in the Annual Radiological Radiological Environmental Operating Report Environmental Operating Report frequency

____ ___ ____ ____ ___I (continued)

Unit 2 Revision 23 I 3 5-2 December 2002

Radiological Environmental Monitoring Program D 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Milk or fresh leafy C. I Identify specific locations for 30 days vegetation samples obtaining replacement unavailable from one or samples and add them to the more of the sample Radiological Environmental locations required by Table Monitoring Program D3 5 1-1.

AND C2 Delete the specific locations 30 days from which samples were unavailable from the Radiological Environmental Monitoring Program.

AND C3 Pursuant to Technical In accordance with Specification 5.6 3, submit in the Radioactive the next Radioactive Effluent Effluent Release Release Report Report documentation for a change in the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples D Environmental samples D.1 Ensure all efforts are made to Prior to the end of required in Table D 3 5.1-1 complete corrective action(s) the next sampling are unobtainable due to ANDD period sampling equipment malfunctions D.2 Report all deviations from the In accordance with sampling schedule in the the Annual Annual Radiological Radiological Environmental Operating Environmental Report. Operating Report (continued)

Unit 2 Revision 23 I 3 5-3 December 2002

Radiological Environmental Monitoring Program D 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E Samples required by Table E I Choose suitable alternative 30 days D 3 5.1-1 not obtained in media and locations for the the media of choice, at the pathway in question.

most desired location, or at the most desired time AND E2 Make appropriate 30 days substitutions in the Radiological Environmental Monitoring Program AND E3 Submit in the next In accordance with Radioactive Effluent Release the Radioactive Report documentation for a Effluent Release change in the ODCM Report reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new location(s) for obtaining samples Unit 2 Revision 23 I 3 5-4 December 2002

Radiological Environmental Monitoring Program D 3.5 1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3 5 1.1 Collect and analyze radiological environmental In accordance with monitoring samples pursuant to the requirements of Table D 3 5.1-1 Table D 3 5 1-1 and the detection capabilities required by Table D 3 5 1-3 Unit 2 Revision 23 I 3 5-5 December 2002

Radiological Environmental Monitoring Program D 3.5.1 TableD 3 5.1-1 (page 1 of 4)

Radiological Environmental Monitoring Program EXPOSURE NUMBER OF SAMPLING AND PATHWAY SAMPLES COLLECTION TYPE AND FREQUENCY AND/OR STATIONS SAMPLE FREQUENCY OF ANALYSIS SAMPLE LOCATIONS (a)

I Direct 32 routine (1) An inner ring of stations, Once per 3 months Gamma dose once per 3 Radiation monitoring one in each meteorological months stations (b) sector in the general area of the SITE BOUNDARY (2) An outer ring of stations, one in each land base meteorological sector in the 4 to 5 mile (c) range from the site (3) The balance of the stations should be placed in special interest areas such as population centers, nearby residences, schools, and mi one or two areas to serve as control stations (d) 2 Airborne 5 locations (1) 3 samples from offsite Continuous sampler Radioiodine canmster Analyze Radioiodine locations close to the site operation with weekly for 1-131 and boundary (within I mule) in sample collection Particulates different sectors (e) weekly or more Particulate sampler (2) I sample from the vicinity frequently if required (1) Analyze for gross beta of an established year- by dust loading radioactivity Ž 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months round community (e) following filter change (f)

(3) (2) Perform gamma Isotopic locsample from a control analysis on each sample location, at least 10 miles (g) in which gross beta distant and in a least activity is > 10 times the prevalent wind direction (d) precious yearly mean of control samples (3) Gamma isotopic analysis of composite sample (g)

(by location) once per 3 months 3 Waterbome

a. Surface I sample Upstream (d) (h) Composite sample (I) Gamma isotopic analysis over a one month of each sample (g) once period (i) per month I sample Site's downstream cooling water (2) H-3 analysis of each intake (h) composite sample and once per 3 months b Ground As required From one or two sources if likely Grab sample once per (1) Gamma Isotopic analysis to be affected 6) 3 months of each sample (g) once per 3 months (2) H-3 analysis of each sample once per 3 months (continued)

Unit 2 Revision 23 I 3 5-6 December 2002

Radiological Environmental Monitoring Program D3.5 1 Table D 3.5.1-1 (page 2 of 4)

Radiological Environmental Monitoring Program EXPOSURE PATHWAY SAMPLING AND AND/OR NUMBER OF SAMPLE COLLECTION TYPE AND FREQUENCY SAMPLE SAMPLES LOCATIONS (a) FREQUENCY OF ANALYSIS 3 Waterbome (continued) c Drinking I sample of each One tothree of the nearestwater When I-131 analysis (1) 1-131 analysis on each supplies that could be affected by Is performed, a composite sample when its discharge (k) composite sample the dose calculated for over a two week the consumption of the period (i), otherwise, "sater is greater than I a composite sample mrem/yr (I) monthly (2) Gross beta and gamma isotopic analyses of each composite sample (g) monthly (3) H-3 analysis of each composite sample once per 3 months d Sediment I sample From a downstream area with Twice per year Gamma isotopic analysis of from e'osting or potential recreational each sample (g)

Shoreline value 4 Ingestion

a. Milk (1) 3 samples from In 3 locations within 3 5 miles Twice per month, (1) Gamma isotopic (g) and MILK (e) April through 1-131 analysis of each SAMPLING December (m) sample twice per month LOCATIONS Apnil through December (2) Gamma isotopic (g) and (2) If there are none, In each of 3 areas 3 5-5 0 miles 1-131 analysis of each then I sample distant (e) sample once per month from MILK January through March SAMPLING ifrequired LOCATIONS (3) 1 sample from a At a control location 9-20 miles MILK distant and in a least prevalent SAMPLING wind direction (d)

LOCATION b Fish (1) I sample each of In the vicinity of a plant Twice per year Gamma isotopic analysis of 2 commercially discharge area each sample (g) on edible or recreationally portions twice per year important species (n)

(2) 1 sample of the In areas not influenced by station same species discharge (d)

(continued)

Unit 2 Revision 23 13 5-7 Decembei-2002

Radiological Environmental Monitoring Program D 3 5.1 Table D 3.5 1-1 (page 3 of 4)

Radiological Environmental Monitoring Program EXPOSURE PATHWAY SAMPLING AND TYPE AND FREQUENCY AND/OR NUMBER OF SAMPLE COLLECTION OF ANALYSIS SAMPLE SAMPLES LOCATIONS (a) FREQUENCY 4 Ingestion (continued) c Food (I) I sample of Any area that is irngated by At time of harvest (p) Gamma isotopic (g) and 1-131 Products each principal water in which liquid plant analysis of each sample of class of food wastes have been discharged (o) edible portions products (2) Samples of 3 Grown nearest to each of 2 Once per year during different kinds different offsite locations (e) the harvest season-of broad leaf vegetation (such as vegetables)

(3) 1 sample of Grown at least 9 3 miles distant Once per year during each ofthe in a least prevalent wind the harvest season sinular broad direction leaf vegetation Unit 2 Revision 23 I 3 5-8 December 2002

Radiological Environmental Monitoring Program D 35 1 Table D 3 5 1-1 (page 3 of 4)

Radiological Environmental Monitoring Program (a) Specific parameters of distance and direction sector from the centerline of one reactor, and additional descriptions where pertinent, shall be provided for each and every sample location in Table D 3 5 1-1 Refer to NUREG-0 133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. Deviations are pernutted from the required sampling schedule if specimens are unobtainable because of such circumstances as hazardous conditions, seasonal unavailability (which includes theft and uncooperative residents), or malfunction of automatic sampling equipment (b) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to integrating dosimeters Each of the 32 routine monitoring stations shall be equipped with 2 or more dosimeters or with 1 uistrument for measuring and recording dose rate continuously For the purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor, 2 or more phosphors in a packet are considered as 2 or more dosimeters Film badges shall not be used as dosimeters for measunng direct radiation (c) At this distance, 8 windrose sectors (W, WNW, NW, NNW, N, NNE, NE, and ENE) are over Lake Ontario (d) The purpose of these samples is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites, which provide valid background data, may be substituted (e) Having the highest calculated annual site average ground-level D/Q based on all site licensed reactors.

(f) Aerbome particulate sample filters shall be analyzed for gross beta activity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay (g) Gamma isotopic analysis means the identification and quantification of gamma -emitting radionuclides that may be attributable to the effluents from the facility (h) The upstream sample shall be taken at a distance beyond significant influence of the discharge The downstream sample shall be taken in an area beyond but near the mixing zone.

(i) In this program, representative composite sample aliquots shall be collected at time intervals that are very short (e g, hourly) relative to the compositing period (e g , monthly) in order to assure obtaining a representative sample (j) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas "here the hydraulic gradient or recharge properties are suitable for contamination.

(k) Drinking wvater samples shall be taken only when drinking "ater is a dose pathway (I) Analysis for 1-131 may be accomplished by Ge-Li analysis provided that the looser limit of detection (LLD) for 1-131 in water samples found on Table D 3 5 1-2 can be met Doses shall be calculated for the maximum organ and age group (m) Samples will be collected January through March if 1-131 is detected in November and December of the preceding year (n) In the event 2 commercially or recreationally important species are not available, after 3 attempts of collection, then 2 samples of one species or other species not necessarily commercially or recreationally important may be utilized (o) Applicable only to major imgation projects within 9 miles ofthe site in the general downcurrent direction.

(p) If harvest occurs more than once/year, sampling shall be performed during each discrete harvest If harvest occurs continuously, sampling shall be taken monthly Attention should be paid to including samples of tuberous and root food products Unit 2 Revision 23 I 3.5-9 December 2002

Radiological Environmental Monitoring Program D3 5 1 Table D 3 5.1-2 (page 1 of 1)

Reporting Levels for Radioactivity in Environmental Samples AIRBORNE FOOD RADIONUCLIDE PARTIUCLATE OR FISH MILK PRODUCTS 3

ANALYSIS WATER (pCu/L) GASES (pCirn ) (pCi/kg, wet) (pCiIL) (pCi/kg, wet)

H-3 20,000 (a)

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-95 400 Nb-95 400 1-131 2 (b) 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-140 200 300 La-140 200 300 (a) For drinking water samples Thls is a 40 CFR 141 value If no drmking water pathway exsts, a value of3O,000 pCi.L may be used (b) If no dnnking water pathway exists, a value of 20 pCiIL may be used Unit 2 Revision 23 I 3 5-10 December 2002

Radiological Environmental Monitoring Program D 3.5.1 Table D 3.5 1-3 (page 1 of 2)

Detection Capabilities for Environmental Sample Analysis (3)(b)

LOWER LIMIT OF DETECTION (LLD) ("

AIRBORNE PARTIUCLATE OR FOOD 3

RADIONUCLIDE WATER GASES (pCtIm ) FISH MILK PRODUCTS SEDIMENT ANALYSIS (pCfL) (pCi/kg, wet) (pCi/L) (pCi/kg, wet) (pCvikg, dry)

Gross Beta 4 001 H-3 2,000 0 Mn-S 4 15 130 Fe-59 30 260 Co-5 8 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 15 Nb-9 5 15 1-131 I ( 0 07 I 60 Cs-134 15 0 05 130 15 60 150 Cs-137 18 0 06 150 18 SO 180 Ba-140 15 15 La-140 15 15 See the notes on the next page Unit 2 Revision 23 1 3.5-11 December 2002

Radiological Environmental Monitoring Program D3.5 1 Table 3 5 1-3 (page 2 of 2)

Detection Capabilities for Environmental Sample Analysis (a) (b)

(a) This listdoes not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported m the Annual Radiological Environmental Operating Report (b) Required detection capabilities for thermolumunescent dosimeters used for environmental measurements are given in ANSI N-545, Section 4 3 1975 Allowable exceptions to ANSI N-545, Section 4 3 are contained in the ODCM (c) The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%,o probability of falsely concluding that a blank observation represents a "real" signal For a particular measurement system, which may include radiochemical separation LLD = (4 66 ) (Sb )

(E) (V) (2 2 2) m Y)>

,here:

LLD = The before-the-fact lower limit of detection (pCi per unit mass or volume),

Sb = The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = The counting efficiency (counts per disintegration),

V = The sample size (units of mass or volume),

2 22 = The number of disintegrations per minute per pCi, Y = The fractional radiochemical yield, when applicable,

= The radioactive decay constant for the particular radionuclide (seci'), and At= The elapsed time between environmental collection or end of the sample collection period, and the time of counting (seconds)

Typical values of E, V, Y, and At should be used in the calculation It should be recognized that the LLD is defined as a before-the-fact limit representing the capability of a measurement system and not as an after-the-fact limit for a particular measurement Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfenng nuclides, or other uncontrollable circumstances may render these LLDs unachievable In such cases, the contnbuting factors shall be identified and described in the Annual Radiological Environmental Operating Report.

(d) If no drinking water pathway exists, a value of 3,000 pCi'L may be used (e) If no drinking water pathway exists, a value of 15 pCiIL may be used Unit 2 Revision 23 I 3 5-12 December 2002

Land Use Census D3 52 D 35 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5 2 Land Use Census DLCO 3 52 A land use census shall.

a Be conducted, b Identify within a distance of 5 miles the location in each of the 16 meteorological sectors of the nearest milk animal and the nearest residence, and the nearest garden (broad leaf vegetation sampling controlled by Table D 3.5 1-1, part 5.c may be performed in lieu of the garden census) of > 500 ft2 producing broad leaf vegetation, and c For elevated releases, identify within a distance of 3 miles the locations in each of the 16 meteorological sectors of all milk animals and all gardens (broad leaf vegetation sampling controlled by Table D 3.5 1-1, part 5.c may be performed in lieu of the garden census) > 500 ft2 producing broad leaf vegetation.

APPLICABILITY: At all times ACTIONS

NOTES -----------------------------------------------

1 LCO 3 0 3 is not applicable 2 LCO 3 0 4 is not applicable CONDITION REQUIRED ACTION COMPLETION TIME A Land use census identifies A. 1 Identify the new location(s) in In accordance with location(s) that yields a the next Radioactive Effluent the Radioactive calculated dose, dose Release Report Effluent Release commitment, or D/Q value Report

> than the values currently being calculated in DSR 3 2.3 1 (continued)

Unit 2 Revision 23 I 3 5-13 December 2002

Land Use Census D3 52 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B Land use census identifies B I Add the new location(s) to the 30 days location(s) that yields a Radiological Environmental calculated dose, dose Monitoring Program commitment, or D/Q value (via the same exposure AND pathway) 50% > than at a location from which B.2 Delete the sampling After October 31 of samples are currently being location(s), excluding the the year in which obtained in accordance control station location, the land use census with Table D 3 5. 1- 1. having the lowest calculated was conducted dose, dose comrnmitment(s) or D/Q value, via the same exposure pathway, from the Radiological Environmental Monitoring Program.

AND B3 Submit in the next Radioactive In accordance with Effluent Release Report the Radioactive documentation for a change in Effluent Release the ODCM including revised Report figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

Unit 2 Revision 23 I3 5-14 December 2002

Land Use Census D 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3 5 2.1 Conduct the land use census during the growing 366 days season using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities DSR 3.5 2 2 Report the results of the land use census in the Annual In accordance with Radiological Environmental Operating Report the Annual Radiological Environmental Operating Report Unit 2 Revision 23 I 3 5-15 December 2002

Interlaboratory Comparison Program D 3 53 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3 5.3 Interlaboratory Comparison Program DLCO 3 5 3 The Interlaboratory Comparison Program shall be described in the ODCM AND Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the NRC, that correspond to samples required by Table D 3 5 1-1 Participation in this program shall include media for which environmental samples are routinely collected and for which intercomparison samples are available APPLICABILITY: At all times ACTIONS NOTES

1. LCO 3.0 3 is not applicable.

2. LCO 3 0 4 is not applicable CONDITION REQUIRED ACTION COMPLETION TIME A Analyses not performed as A1 Report the corrective actions In accordance with required taken to prevent a recurrence the Annual to the NRC in the Annual Radiological Radiological Environmental Environmental Operating Report Operating Report Unit 2 Revision 23 I 3.5-16 December 2002

Interlaboratory Comparison Program D3 53 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3 5.3.1 Report a summary of the results obtained as part of the In accordance with Interlaboratory Comparison Program in the Annual the Annual Radiological Environmental Operating Report Radiological Environmental Operating Report Unit 2 Revision 23 I 3 5-17 December 2002

PART I - RADIOLOGICAL EFFLUENT CONTROLS BASES Unit 2 Revision 23 I B 3 1-0 December 2002

Liquid Effluents Concentration B3 1 1 B31 RADIOACTIVE LIQUID EFFLUENTS B 3 1.1 Liquid Effluents Concentration BASES This is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than ten times the concentration levels specified in 10 CFR 20, Appendix B, Table 2, Column 2 This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II A design objectives of Appendix I to 10 CFR 50, to a MEMBER OF THE PUBLIC and (2) the levels required by 10 CFR 20 130 1(e) to the population The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its effluent concentration in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2 This applies to the release of radioactive materials in liquid effluents from all units at the site The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in L A Currie, "Lower Limit of Detection Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements,"

NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300 (revised annually)

Unit 2 Revision 23 I B 3 1-1 December 2002

Liquid Effluents Dose B3 12 B31 RADIOACTIVE LIQUID EFFLUENTS B 3.1 2 Liquid Effluents Dose BASES This is provided to implement the requirements of Sections II A, III A, and IV A of Appendix I to 10 CFR 50. This implements the guides set forth in Section II A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV A of Appendix I to assure that the releases of radioactive materials in liquid effluents to UNRESTRICTED AREAS will be kept as low as is reasonably achievable Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the potable drinking water that are in excess of the requirements of 40 CFR 141.

For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units including outside storage tanks, etc, are kept small The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR 190 limits For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBERS OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered The dose calculation methodology and parameters implement the requirements in Section III A of Appendix I that conformance with the guides of Appendix I be shown by Calculational procedures based on models and data, so that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified for calculating the doses that result from actual release rates of radioactive material in liquid effluents are consistent with the methodology provided in RG 1.109, "Calculation of Annual Doses To Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and R G 1 113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. This applies to the release of radioactive materials in liquid effluents from each unit at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are to be proportioned among the units sharing that system Unit 2 Revision 23 I B 3 1-2 December 2002

Liquid Radwaste Treatment System B3 1.3 B3 1 RADIOACTIVE LIQUID EFFLUENTS B 3 13 Liquid Radwaste Treatment System BASES The installed liquid radwaste treatment system shall be considered OPERABLE by meeting DLCO 3 1 1 and DLCO 3 1 2 The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment before release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonably achievable This implements the requirements of 10 CFR 50 36a, GDC 60 of Appendix A to 10 CFR 50 and the design objective given in Section II D of Appendix I to 10 CFR 50 The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II A of Appendix I to 10 CFR 50 for liquid effluents This applies to the release of radioactive materials in liquid effluents from each unit at the site For units with shared radwaste treatment systems, the liquid effluents from the shared system are to be proportioned among the units sharing that system Unit 2 Revision 23 IB3 1-3 December 2002

Gaseous Effluents Dose Rate B 3.2.1 B 32 RADIOACTIVE GASEOUS EFFLUENTS B 3.2.1 Gaseous Effluents Dose Rate BASES This is provided to ensure that the dose rate at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR 20 to UNRESTRICTED AREAS The annual dose limits are the doses associated with the concentrations of 10 CFR 20, Appendix B, Table 2, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10 CFR 20 or as governed by 10 CFR 20.1302(c) For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that NMEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in Part II. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mremlyear to the whole body or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year This applies to the release of radioactive materials in gaseous effluents from all units at the site The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs) Detailed discussion of the LLD, and other detection limits can be found in L. A Currie, "Lower Limit of Detection Definition and Elaboration of a Proposed Position for Radiological Effluent and Environments Measurements,"

NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300 (revised annually)

Unit 2 Revision 23 I B 3 2-1 December 2002

Gaseous Effluents Noble Gas Dose B322 B 32 RADIOACTIVE GASEOUS EFFLUENTS B 322 Gaseous Effluents Noble Gas Dose BASES This is provided to implement the requirements of Section II B, III A, and IV A of Appendix I to 10 CFR 50 The DLCO implements the guides set forth in Section II B of Appendix I The REQUIRED ACTIONS provide the required operating flexibility and, at the same time, implement the guides set forth in Section IV A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept as low as is reasonably achievable. The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guidelines of Appendix I be shown by calculational procedures based on models and data so that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units including outside storage tanks, etc, are kept small The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR 190 limits For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered The dose calculation methodology and parameters for calculating the doses from the actual release rates of radioactive noble in gaseous effluents are consistent with the methodology provided in RG 1 109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, and RG 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1," July 1977 The ODCM equations provided for determining the air doses at or beyond the SITE BOUNDARY are based upon real-time meteorological conditions or the historical average atmospheric conditions This applies to the release of radioactive material in gaseous effluents from each unit at the site Unit 2 Revision 23 I B 3.2-2 December 2002

Gaseous Effluents Dose - Iodine-13 1, Iodine-133, Tritium, and Radioactive Material In Particulate Form B 323 B 32 RADIOACTIVE GASEOUS EFFLUENTS B 32 3 Gaseous Effluents Dose - Iodine-13 1, Iodine-133, Tritium, and Radioactive Material In Particulate Form BASES This is provided to implement the requirements of Sections II C, III A, and IV A of Appendix I to 10 CFR 50 The DLCO implements the guides set forth in Section II C of Appendix I The REQUIRED ACTIONS provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept as low as is reasonably achievable The calculational methods specified in the Surveillance Requirements implement the requirements in Section III A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, so that the actual exposure of a MEMBER OF TIHE PUBLIC through appropriate pathways is unlikely to be substantially underestimated . For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEN'IBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units including outside storage tanks, etc., are kept small The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR 190 limits For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered The calculational methodology and parameters for calculating the doses from the actual release rates of the subject materials are consistent with the methodology provided in RG 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, " Revision 1, October 1977, and RG 1 111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977 These equations also provide for determining the actual doses based upon the historical average atmospheric conditions The release rate DLCO for iodme-13 1, iodine-133, tritium, and radioactive material in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at or beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were (1) individual inhalation of airborne radioactive material, (2) deposition of radioactive material onto green leafy vegetation Unit 2 Revision 23 I B 3.2-3 December 2002

Gaseous Effluents Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material In Particulate Form B 3.2 3 B 3.2 3 Gaseous Effluents Dose - Iodine-13 1, Iodine-133, Tritium, and Radioactive Material In Particulate Form (continued) with subsequent consumption by man, (3) deposition onto grassy areas where milk-producing animals and meat-producing animals graze (human consumption of the milk and meat is assumed),

and (4) deposition on the ground with subsequent exposure to man This applies to the release of radioactive materials in gaseous effluents from each unit at the site For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system Unit 2 Revision 23 IB 3 2-4 December 2002

Gaseous Radwaste Treatment System B 3 24 B 32 RADIOACTIVE GASEOUS EFFLUENTS B 324 Gaseous Radwaste Treatment System BASES The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment before release to the environment The requirement that the appropriate portions of this system be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable This implements the requirements of 10 CFR 50 36a, GDC 60 of Appendix A to 10 CFR 50, and the design objectives given in Section II D of Appendix I to 10 CFR 50. Limits governing the use of appropriate portions of the system were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I to 10 CFR 50, for gaseous effluents This applies to the release of radioactive materials in gaseous effluents from each unit at the site For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportional among the units sharing that system Unit 2 Revision 23 IB 3 2-5 December 2002

Ventilation Exhaust Treatment System B 3.2 5 B 3.2 RADIOACTIVE GASEOUS EFFLUENTS B 3.2 5 Ventilation Exhaust Treatment System BASES The OPERABILITY of the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment before release to the environment The requirement that the appropriate portions of this system be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable This implements the requirements of 10 CFR 50 36a, GDC 60 of Appendix A to 10 CFR 50, and the design objectives given in Section II D of Appendix I to 10 CFR 50 Limits governing the use of appropriate portions of the system were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II C of Appendix I to 10 CFR 50, for gaseous effluents This applies to the release of radioactive materials in gaseous effluents from each unit at the site For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportional among the units sharing that system The appropriate components, which affect iodine or particulate release, to be OPERABLE are

1) HEPA Filter - Radwaste Decon Area

2) HEPA Filter - Radwaste Equipment Area

3) HEPA Filter - Radwaste General Area Whenever one of these filters is not OPERABLE, iodine and particulate dose projections will be made for 31 -day intervals starting with filter inoperability, and continuing as long as the filter remains inoperable, m accordance with DSR 3 2.5 1 Unit 2 Revision 23 I B 3 2-6 December 2002

Venting or Purging B 326 B32 RADIOACTIVE GASEOUS EFFLUENTS B326 Venting or Purging BASES This provides reasonable assurance that releases from drywell and/or suppression chamber purging operations will not exceed the annual dose limits of 10 CFR 20 for unrestricted areas Unit 2 Revision 23 IB 3 2-7 December 2002

Radioactive Liquid Effluent Monitoring Instrumentation B33 1 B33 INSTRUMENTATION B 3.3 1 Radioactive Liquid Effluent Monitoring Instrumentation BASES The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Part II to ensure that the alarm/trip wvill occur before exceeding ten times the limits of 10 CFR 20 The OPERABILITY and use of this instrumentation is consistent with the requirements of GDC 60, 63, and 64 of Appendix A to 10 CFR 50 The purpose of tank level indicating devices is to assure the detection and control of leaks that if not controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS Tanks included are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system, such as temporary tanks Unit 2 Revision 23 I B 3.3-1 December 2002

Radioactive Gaseous Effluent Monitoring Instrumentation B 3 3.2 B 3.3 INSTRUMENTATION B 332 Radioactive Gaseous Effluent Monitoring Instrumentation BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Part II to ensure that the alarm/trip will occur before exceeding the limits of 10 CFR 20. Although the Offgas System Noble Gas Activity Monitor is listed in Table D 3.3.2-1, "Radioactive Gaseous Effluent Monitoring Instrumentation", these monitors are actually located upstream of the Main Stack noble gas activity monitor and are not effluent monitors They were included in Table D 3 3 2-1 in accordance with NLTREG-0473 As such, Offgas System Noble Gas Activity Monitor alarm and trip setpoints are not based on IOCFR20 The offgas system noble gas monitor alert setpoint is set at 1 5 times nominal full power background to assure compliance with ITS SR 3.7 4 1 which requires offgas sampling be performed within four hours of a 50% increase in offgas monitoring readings, and to support MSLRM trip removal The offgas system noble gas monitor trip setpoint is based on the 10CFRI0O limits for the limiting design basis gaseous waste system accident which is the offgas system rupture. The range of the noble gas channels of the main stack and radwaste/reactor building vent effluent monitors is sufficiently large to envelope both normal and accident levels of noble gas activity The capabilities of these instruments are consistent with the recommendations of Regulatory Guide 1.97, "Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident,"

December 1980 and NUREG-0737, "Clarification of the TMI Action Plan Requirements,"

November 1980 This instrumentation also includes provisions for monitoring and controlling the concentrations of potentially explosive gas mixtures in the offgas system The OPERABILITY and use of this instrumentation is consistent with the requirements of GDC 60, 63, and 64 of Appendix A to 10 CFR 50 Unit 2 Revision 23 I B 3 3-2 December 2002

Radioactive Effluents Total Dose B 3.4 B 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE BASES This is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20 by 46 FR 18525. This requires the preparation and submittal of a Special Report whenever the calculated doses from releases of radioactivity and from radiation from uranium fuel cycle sources exceed 25 mrem to the whole body or any organ, except the thyroid (which shall be limited to less than or equal to 75 mrem). If the dose to any MIEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR 20, as addressed in 3.1.1 and 3.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which the individual is engaged in carrying out any operation that is part of the nuclear fuel cycle.

Unit 2 Revision 23 I B 3.4-1 December 2002

Monitoring Program B 3.5.1 B 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING B 3.5.1 Monitoring Program BASES The Radiological Environmental Monitoring Program provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of MEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. Program changes may be initiated based on operational experience The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table D 3.5.1-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a before-the-fact limit representing the capability of a measurement system and not as an after-the-fact limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in L. A Currie, "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984),

and in the HASL Procedures Manual, HASL-300 (revised annually).

Unit 2 Revision 23 I B 3.5-1 December 2002

Land Use Census B 3.5.2 B3 5 RADIOLOGICAL ENVIRONMENTAL MONITORING B 3 5.2 Land Use Census BASES -

This is provided to ensure that changes in the use of areas at or beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by the results of this census. The best information, such as from a door-to-door survey, from an aerial survey, or from consulting with local agricultural authorities, shall be used.

This census satisfies the requirements of Section IV B.3 of Appendix I to 10 CFR 50.

Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in RG 1.109 for consumption by a child To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage) and (2) the vegetation yield was 2 kg/m2 .

A MILK SAMPLING LOCATION, as defined in Section 1.0, requires that at least 10 milking cows are present at a designated milk sample location It has been found from past experience, and as a result of conferring with local farmers, that a minimum of 10 milking cows is necessary to guarantee an adequate supply of milk twice a month for analytical purposes Locations with fewer than 10 milking cows are usually utilized for breeding purposes, eliminating a stable supply of milk for samples as a result of suckling calves and periods when the adult animals are dry.

Elevated releases are defined in RG 1.1 11, Revision 1, July 1977.

Unit 2 Revision 23 I B 3.5-2 December 2002

Interlaboratory Comparison Program B 3.5.3 B 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING B 3.5.3 Interlaboratory Comparison Program BASES The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B 2 of Appendix I to 10 CFR 50 Unit 2 Revision 23 I B 3.5-3 December 2002

PART I - RADIOLOGICAL EFFLUENT CONTROLS SECTION 4.0 ADMINISTRATIVE CONTROLS Unit 2 Revision 23 1 4.0-0 December 2002

Administrative Controls 4.0 4.0 ADMINISTRATIVE CONTROLS The ODCM Specifications are subject to Technical Specifications Section 5.5.4, "Radioactive Effluent Controls Program," Section 5.6.2, "Annual Radiological Environmental Operating Report," Section 5.6.3, "Radioactive Effluent Release Report," and Section 5.5.1, "Offsite Dose Calculation Manual."

Unit 2 Revision 23 1 4.0-1 December 2002

Special Reports D 4.1.1 D 4.1.2 D 4.1.3 D 4.1 REPORTING REQUIREMENTS D 4.1.1 Special Reports Special Reports shall be submitted in accordance with 10 CFR 50.4 within the time period specified for each report.

D 4.1 2 Annual Radiological Environmental Operating Reports In addition to the requirements of Technical Specification 5.6.2 the report shall also include the following:

A summary description of the Radiological Environmental Monitoring Program; at least two legible maps, one shall cover stations near the SITE BOUNDARY and the second shall include the more distant stations, covering all sample locations keyed to a table giving distances and directions from the centerline of one reactor; the results of license participation in the Interlaboratory Comparison Program, required by Control D 3.5.3; discussion of all deviations from the Sampling Schedule of Table D 3.5 1-1; and discussion of all analysis in which the LLD required by Table D 3.5.1-3 was not achievable.

D 4.1.3 Radioactive Effluent Release Report The Radiological Effluent Release Report described in Technical Specification section 5.6.3 shall include

An annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distribution-of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Radiological Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

An assessment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during the previous year.

(Continued)

Unit 2 Revision 23 I4.1-1 December 2002

Special Reports D 4.1.3 D 4.1.3 Radioactive Effluent Release Report (continued)

As assessment of radiation doses from the radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC from their activities inside the SITE BOUNDARY during the report period All assumptions used in making these assessments, i e., specific activity, exposure time, and location shall.be included in these reports. The assessment ,ofradiation doses shall be performed in accordance with the methodology and parameters in Part II.

As assessment of doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Part H.

A list of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

Any changes made during the reporting period to the PROCESS CONTROL PROGRAM and to the OFFSITE DOSE CALCULATION MANUAL (ODCM).

Any major changes to liquid, gaseous, or solid radwaste treatment systems pursuant to D 4.2.

A listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Control D 3.5.2.

An explanation of why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Controls D 3.3.1 and D 3.3.2.

Description of events leading to liquid holdup tanks exceeding the limits of TRM 3.7.7.

Unit 2 Revision 23 I 4.1-la December 2002

Major Changes to Liquid, Gaseous, and Solid Radwaste Treatment System D 4.2 D 4.2 MAJOR CHANGES TO LIQUID, GASEOUS, AND SOLID RADWASTE TREATMENT SYSTEM

NOTE--------------------------------------------------

Licensees may choose to submit this information as part of the annual FSAR update Licensee-initiated major changes to the radwaste treatment systems (liquid, gaseous, and solid):

a 'Shall be reported to the Commission in the Radioactive Effluent Release report for the period in which the evaluation was reviewed by the SORC. The discussion of each change shall contain

1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59.

2. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information,

3. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;

4. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;

5. An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto,

6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period that precedes the time when the change is to be made;

7. An estimate of the exposure to plant operating personnel as a result of the change; and (Continued)

Unit 2 Revision 23 I 4.2-1 December 2002

Major Changes to Liquid, Gaseous, and Solid Radwaste Treatment System D42 D 4.2 MAJOR CHANGES TO LIQUID, GASEOUS, AND SOLID RADWASTE TREATMENT SYSTEM (continued)

8. Documentation of the fact that the change was reviewed and found acceptable by the SORC.

b. Shall become effective upon review and acceptance by the SORC Unit 2 Revision 23 14.2-2 December 2002

ML031290248

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