ML12089A612

Entergy Prefiled Hearing Exhibit ENT00316B - Gaseous Effluents Dose Rate D 3.2.1 - Table D 3.2.1-1 (Page 2 of 2), Radioactive Gaseous Waste Sampling and Analysis. Part 2 of 3

ML12089A612
Person / Time
Site:	Indian Point
Issue date:	04/23/2008
From:	Entergy Corp
To:	Atomic Safety and Licensing Board Panel
SECY RAS
Shared Package
12089A599	List: ML12089A611 ML12089A612 ML12094A124
References
RAS 22132, ASLBP 07-858-03-LR-BD01, 50-247-LR, 50-286-LR
Download: ML12089A612 (309)

Text

ENT00316B Submitted: March 29, 2012 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, for purposes of these Specifications, 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.

The LlD shall be determined in accordance with the methodology and parameters in the ODCM.

It should be recognized that the LLD is defined as an g priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

(b) The principal gamma emitters for which the LLD Control applies exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. Other identifiable gamma peaks (1-131 in particulate form, for example), together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Section D 5.2.

(c) lE following a shutdown, startup, or a thermal power change (within one hour) exceeding 15 percent of RATED THERMAL POWER, analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has increased by a factor of 3 or more, AND the noble gas monitor shows that effluent activity has increased by a factor of 3 or more THEN:

1) Sample the main Plant Vent (unit 2) for Noble Gases within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, AND

2) Sample the main Plant Vent (unit 2) for Iodine and Particulate once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days with analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of sample changeout. The LLDs of these samples may be increased by a factor of 10.

(d) This value is the established Radiation Monitor sensitivity (minimum).

(e) Grab samples can be used as altemative to continuous sampling, provided the periodiCity of these grab samples is increased from monthly to once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded, or at least once per 7 days when spent fuel is in the Spent Fuel Pool.

(f) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with SpeCifications 0 3.2.1, D 3.2.2 and D 3.2.3.

(g) Continuous samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.

Additionally, lE routine Iodine sampling indicates 1-131 in the main Plant Vent (unit 2) or the Stack Vent (unit 1), THEN collect a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> sample from the applicable vent (within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) for short-lived Iodine isotope quantification, on a periodicity not to exceed once per 31 days. The LLDs of these samples may be increased by a factor of 10.

(h) Complete prior to each release.

(i) Vapor Containment noble gas shall be sampled at least monthly to ensure Pressure Reliefs are quantified with an accurate isotopiC mixture. Containment noble gas radiation monitor readings can be used for quantification of Pressure Reliefs, provided the monitor readings are consistent with those observed during recent (at least monthly) grab samples. Sample data is adjusted by the noble gas radiation monitor reading for purposes of quantification of each release. Should the monitor be inoperable, a containment noble gas grab sample is required within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the Pressure Relief. Should BOTH the containment noble gas and particulate I 'J07 monitors be inoperable, two independent samples of the VC are required prior to a Pressure Relief.

Indian Point 2 D 3.2.1 - 3 Revision 10

Gaseous Effluent Dose - Noble Gas D 3.2.2 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.2 Gaseous Effluent Dose - Noble Gas 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 4.1-1) shall be limited to:

a. ~ 5 mrad to the whole body from gamma radiation and

~ 10 mrad to the skin from beta radiation during any calendar quarter, and

b. ~ 10 mrad to the whole body from gamma radiation and

~ 20 mrad to the skin from beta radiation during any calendar year.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The calculated air dose at A.1 Prepare and submit to the 30 days or beyond the SITE NRC, pursuant to D 5.3, a BOUNDARY due to noble gases released in gaseous Special Report that effluents exceeds limits. (1) Identifies the cause(s) for exceeding the limit(s) and (2) Defines the corrective 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 OLCO 3.2.2.

Indian Point 2 03.2.2 -1 Revision 10

Gaseous Effluent Dose - Noble Gas o 3.2.2 ACTIONS (continued)

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

AND Immediately B.2 Verify that the limits of DLCO 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 0 5.3, a time not met. .Special Report, as defined in 10 CFR 20.2203 (a)(4), of 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 dire,ct 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.

Indian Point 2 03.2.2 - 2 Revision 10

Gaseous Effluent Dose - Noble Gas 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.

Indian Point 2 D 3.2.2 - 3 Revision 10

Gaseous Effluent Dose - Iodine and Particulate 03.2.3

/~.'" o 3.2 RADIOACTIVE GASEOUS EFFLUENTS C......

o 3.2.3 Gaseous Effluent Dose - Iodine and Particulate DLCO 3.2.3 The dose to a MEMBER OF THE PUBLIC from 1-131, tritium, and all radionuclides in particulate form with half-lives> 8 days, in gaseous effluents, released from each unit to areas at or beyond the SITE BOUNDARY (Figure 0 4.1-1) shall be limited to:

a. $ 7.5 mrem to any organ during any calendar quarter, and

,b.  ::;; 15 mrem to any organ during any calendar year.

APPLICABILITY: At a" times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The dose from 1-131, A.1 Prepare and submit to the 30 days tritium, and radioactive NRC, pursuant to 0 5.3, a material in particulate form Special Report that with half-lives> 8 days (1) Identifies the cause( s) released in gaseous for exceeding the limit(s) effluents at or beyond the and SITE BOUNDARY (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 3.2.3.

Indian Point 2 03.2.3 - 1 Revision 10

Gaseous Effluent Dose - Iodine and Particulate o 3.2.3 ACTIONS lcontinued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Calculated dose to a B.1 Calculate the annual dose to Immediately MEMBER OF THE a MEMBER OF THE PUBLIC from the release PUBLIC which includes of radioactive materials in contributions from direct liquid effluents exceeds 2 radiation from the units 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 Prepare and submit to the 30 days Associated Completion NRC, pursuant to 0 5.3, a time not met. Special Report, as defined in 10 CFR 20.2203 (a)(4), of Required Action A.1 shall also include the following:

(1 ) The corrective action( 5) 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.

Indian Point 2 D 3.2.3 - 2 Revision 10

Gaseous Effluent Dose - Iodine and Particulate 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 1-131, tritium, and radioactive material in particulate form with half-lives> 8 days.

Indian Point 2 D 3.2.3 - 3 Revision 10

Gaseous Radwaste Treatment System D 3.2.4 i

o 3.2 RADIOACTIVE GASEOUS EFFLUENTS

\.~....

D 3.2.4 Gaseous Radwaste Treatment System OLCO 3.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation when projected gaseous effluent doses, from each unit, at and beyond the SITE BOUNDARY (Figure 04.1-1) would be:

a. > 0.2 mrad for gamma radiation; and

b. > 0.4 mrad for beta radiation in a 31 day period.

APPLICABILITY: Prior to each release.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive gaseous A.1 Prepare and submit to the 30 days waste is being discharged NRC, pursuant to D 5.3, a without treatment. Special Report that includes the following:

AND (1) Identification of any Projected doses due to the inoperable equipment or gaseous effluent, from the subsystems and the unit, at and beyond the reason for the SITE BOUNDARY would inoperability, exceed limits. (2) Action(s) taken to restore the inoperable equipment to OPERABLE status, and (3) Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 3.2.4.1 Project the doses due to gaseous effluents from each 31 days unit at and beyond the SITE BOUNDARY.

Indian Point 2 D 3.2.4 - 1 Revision 10

Ventilation Exhaust Treatment System D 3.2.5 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.5 Ventilation Exhaust Treatment System DLCO 3.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM shall be in operation when projected gaseous effluent doses, from each unit, at and beyond the SITE BOUNDARY (Figure D 4.1-1) would be:

a. > 0.2mrad air dose from gamma radiation; and

b. > 0.4 mrad air dose from beta radiation in a 31 day period; or

c. > 0.3 mrem to any organ in a 31 day period.

APPLICABILITY: Prior to each release.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive gaseous A.1 Prepare and submit to the 30 days waste is being discharged NRC. pursuant to D 5.3, a without treatment. Special Report that includes the following:

(1) Identification of any inoperable equipment or Projected doses due to subsystems and the gaseous effluent, from reason for the each unit, to areas at or inoperability, beyond the SITE (2) Action(s) taken to restore BOUNDARY would the inoperable equipment exceed limits. to OPERABLE status, and (3) Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.5.1 Project the doses from gaseous releases from each 31 days unit to areas at and beyond the SITE BOUNDARY when the GASEOUS RADWASTE TREATMENT SYSTEMS are not being fully utilized.

Indian Point 2 D 3.2.5 - 1 Revision 10

Gas Storage Tanks 03.2.6 o 3.2 GASEOUS EFFLUENTS o 3.2.6 Gas Storage Tanks DLCO 3.2.6 The radioactivity contained in each gas storage tank shall be limited to

~ 29,761 Curies of noble gas (considered as Xe-133).

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Level*of radioactivity A.1 Suspend addition of Immediately exceeds the limits. radioactive material.

A.2 Reduce content to within the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.6.1 Sample and analyze radioactive material contained in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during gas storage tank for level of radioactivity. addition of radioactive material to the tank Indian Point 2 03.2.6 -1 Revision 10

Radioactive Liquid Effluent Monitoring Instrumentation 03.3.1

.r., ...* 03.3 INSTRUMENTATION

[

03.3.1 Radioactive liquid Effluent Monitoring Instrumentation OLCO 3.3.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 0 3.3.1-1 shall be OPERABLE with:

a. The minimum OPERABLE channel(s) in service.

h. The alarm/trip setpoints set to ensure that the limits of OLCO 3.1.1 are not exceeded ..

APPLICABILITY: According to Table 0 3.3.1-1.

ACTIONS

---

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

Separate condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. liquid effluent monitoring A.1 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 Immediately inoperable.

OR Immediately A.3 Change the setpoint so it is acceptably conservative.

Indian Point 2 03.3.1 - 1 Revision 10

Radioactive Liquid Effluent Monitoring Instrumentation 03.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required B.1 Enter the Condition Immediately channels inoperable. referenced in Table 03.3.1*1 for the channel.

AND B.2 Restore inoperable 30 days channel(s) to OPERABLE status.

C. As required by Required C.1 Analyze at least 2 Prior to initiating a Action B.1 and referenced independent samples in release in Table 03.3.1-1. accordance with Table 0 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 Prior to initiating a release rate calculations and release discharge line valving.

D. As required by Required 0.1 Collect and analyze grab 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Action B.1 and referenced samples for radioactivity at a in Table 03.3.1-1. limit of detection of at least AND 5 x 10-7 ~Ci/ml.

Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter Indian Point 2 03.3.1 - 2 Revision 10

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Collect and analyze grab 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Action B.1 and samples for radioactivity at referenced in a limit of detection of at AND Table D 3.3.1-1. least 5 x 10.7 )lCi/ml, when specific activity is Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

> 0.01 )lCi/gm DOSE thereafter EQUIVALENT 1-131.

OR E.2 Collect and analyze grab 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> samples for radioactivity at a limit of detection of at AND least 5 x 10.7 )lCi/ml, when specific activity is Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

~ 0.01 )lCi/gm DOSE thereafter EQUIVALENT 1-131.

F. As required by Required F.1 ---------------NOTE------------

Action B.1 and Pump performance curves referenced in generated in place may be Table D 3.3.1-1. used to estimate flow.

Estimate the flow rate during 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> actual releases.

AND Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter G. As required by Required G.1 Estimate tank liquid level. Immediately Action B.1 and referenced in AND Table D 3.3.1-1.

During liquid additions to the tank H. Required Action B.2 and H.1 Explain in the next In accordance with associated Completion Radioactive Effluent Radioactive Effluent Time not met. Release Report why the Release Report inoperability was not corrected in a timely manner.

Indian Point 2 D 3.3.1 - 3 Revision 10

Radioactive Liquid Effluent Monitoring Instrumentation 03.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. Required Action and 1.1 Suspend liquid effluent Immediately associated Completion releases monitored by the Time for Condition C, 0, E, inoperable channel(s).

or F not met.

J. Required Action and J.1 Suspend liquid additions to Immediately associated Completion the tank monitored by the Time for Condition G not inoperable channel(s).

met.

SURVEillANCE REQUIREMENTS

---

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

Refer to Table 0 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DSR 3.3.1.2 Perform CHANNEL CHECK by verifying indication of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on any 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 OPERATIONAL TEST 92 days Indian Point 2 03.3.1 - 4 Revision 10

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY DSR 3.3.1.6 Perform CHANNEL OPERATIONAL TEST. The 92 days CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation (or control panel indications/display) occurs if the instrument indicates measured levels above the alarm/trip setpoint DSR 3.3.1.7 Perform CHANNEL OPERATIONAL TEST. The 92 days CHANNEL OPERATIONAL TEST shall also demonstrate control room alarm annunciation (or control panel indications/display) occurs if any of the following conditions exist. instrument indicates measured levels above the alarm setpoint. instrument controls not set in operate mode.

DSR 3.3.1.8 Perform CHANNEL CALIBRATION 92 DAYS DSR 3.3.1.9 Perform CHANNEL CALIBRATION. 24 months Indian Point 2 03,3.1 - 5 Revision 10

Radioactive liquid Effluent Monitoring Instrumentation 03.3.1

. Table 03.3.1-1 (page 1 of 2)

Radioactive liquid Effluent Monitoring Instrumentation CONDITIONS APPLICABILITY REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE INSTRUMENT CONDITIONS INSTRUMENT ACTION B.1 REQUIREMENTS

1. Gross Radioactivity Monitors Providing Alann and Automatic Termination of Release

a. liquid Radwaste Effluent Line (R-54) (a) C DSR 3.3.1.1.

DSR 3.3.1.3 DSR 3.3.1.6 (e)

DSR 3.3.1.9 (d)

b. Steam Generator Effluent Blowdown Line (R-49) (a) E DSR 3.3.1.1 DSR 3.3.1.4 DSR 3.3.1.6 (e)

DSR 3.3.1.9 (d)

2. Gross Beta or Gamma Radioactivity Monitors Providing Alann but not Providing Automatic Tennination of Release

{', a. Service Water Effluent Lines (a) 1 (g) 0 DSR 3.3.1.1

- VC FCU (R-46 or R-53) DSR 3.3.1.4

- 21 CCW HX (R-39) DSR 3.3.1.7 (e~ Y()1

- 22 CCWHX (R-40) DSR3.3.1.9(d

- Sec Boiler BPS (R-52)

b. Unit 1 - (a) 0 . DSR 3.3.1.1 Secondary Boiler DSR 3.3.1.4 Slowdown Effluent DSR 3.3.1.7> (e)

Line (R-51) DSR 3.3.1.9 (d)

c. Unit 1 - (a) 0 DSR 3.3.1.1 Sphere Foundation DSR 3.3.1.4 Drain Sump Effluent DSR 3.3.1.7 (e)

Line (R-62) DSR 3.3.1.9 (d)

3. Flow Rate Measurement Devices DSR 3.3.1.2

a. Liquid Radwaste Effluent (a) F DSR 3.3.1.5 Line DSR 3.3.1.9

b. Steam Generator DSR 3.3.1.2 Slowdown Effluent Line (a) F DSR 3.3.1.5 DSR 3.3.1.9

c. North Curtain Drain DSR 3.3.1.2 Effluent Line (f) (a) F DSR 3.3.1.9

d. Sphere Foundation DSR 3.3.1.2 (a) F DSR 3.3.1.9 Drain Sump (f)

Indian Point 2 03.3.1 - 6 Revision 10

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 Table D 3.3.1-1 (page 2 of 2)

Radioactive Liquid Effluent Monitoring Instrumentation CONDITIONS APPLICABILITY REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE INSTRUMENT CONDITIONS INSTRUMENT ACTION B.1 REQUIREMENTS

4. Tank Level IndicatIng Devices (e)

a. 13 Waste Distillate (a) G DSR 3.3.1.1 (b)

Storage Tank DSR 3.3.1.5 DSR 3.3.1.9

b. 14 Waste Distillate (a) G DSR 3.3.1.1 (b)

Storage Tank DSR 3.3.1.5 DSR 3.3.1.9

e. Primary Water (a) G DSR 3.3.1.1 (b)

Storage Tank DSR 3.3.1.5 DSR 3.3.1.9

d. Refueling Water (a) G DSR 3.3.1.1 (b)

Storage Tank DSR 3.3.1.5 DSR3.3.1.B (a) DUring release via this pathway. Channels shall be OPERABLE and in service on a continuous basis, except that outages are permitted, within the time frame of the speCified action for the purpose of maintenance and performance of required CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION or CHANNEL OPERATIONAL TEST.

(b) During liquid addition to the associated tank.

J.

(c) Tanks included in this Specification 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.

(d) Radioactive calibration standards used for CHANNEL CALIBRATIONS shall be analyzed with instrumentation which is calibrated with NBS (NIST) traceable standards. Standards from suppliers who participate in measurement assurance activities with NBS (NIST) are acceptable). NBS or National Institute of Standards and Technology (NIST) are acceptable traceable standards.

(e) Test will include: Low sample flow, no counts per minute failure, and alarm setpoint reached. The CHANNEL OPERATIONAL TEST does not include testing or trouble shooting and equipment diagnostic capabilities provided with the monitor installation.

(f) Flow rate for these continuous intermittent release pathways is normally obtained from a flow totalizer on the system outlet.

(g) One instrument per operating Service Water system is required. For example, R-46 and R-53 (VC FCUs) are redundant, but operating 22 Component Cooling Water Heat Exchanger would require R-40 to be in service.

Indian Point 2 D 3.3.1 - 7 Revision 10

Radioactive Gaseous Effluent Monitoring Instrumentation 03.3.2 03.3 INSTRUMENTATION o 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation OLCO 3.3.2 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 03.3.2-1 shall be OPERABLE with:

a. The minimum OPERABLE channel(s) in service.

h. The alarm/trip setpoints' set to ensure that the limits of OLCO 3.2.1 are not exceeded.

APPLICABILITY: According to Table 0 3.3.2-1.

ACTIONS

---

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

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 channel alarm/trip setpoint effluents monitored by the less conservative than affected channel.

required.

OR A.2 Declare the channel Immediately inoperable.

OR A.3 Change the setpoint so it is Immediately acceptably conservative.

B. One or more channels B.1 Enter the Condition Immediately inoperable. referenced in Table 0 3.3.2-1 for the channel.

AND B.2 Restore inoperable 30 days channel(s) to OPERABLE status.

Indian Point 2 03.3.2 - 1 Revision 10

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. As required by Required C.1 Take grab samples. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Action B.1 and referenced in Table D 3.3.2-1. AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND C.2 Analyze samples for gross 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from time of activity. sampling completion D. As required by Required D.1 Estimate the flow rate for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Action B.1 and referenced the inoperable channel(s).

in Table D 3.3.2-1. AND Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter E. As required by Required E.1 Continuously collect 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Action B.1 and referenced samples using auxiliary in Table D 3.3.2-1. sampling equipment as required in Table D 3.2.1-1.

Indian Point 2 D 3.3.2 - 2 Revision 10

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 ACTIONS ( continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required F.1 Determine radioactive 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Action B.1 and referenced content of gas decay tank in Table D 3.3.2-1. is in compliance with AND DLCO 3.2.1.

Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter G. As required by Required G.1 Analyze at least 2 Prior to initiating a Action B.1 and referenced independent samples in gas decay tank in Table D 3.3.2-1, for gas accordance with release decay tank releases. Table D 3.2.1-1.

AND G.2 ----------NOTE--------------

Verification Action will be performed by at least 2 separate technically qualified members of the facility staff.

Independently verify the Prior to initiating a release rate calculations and gas decay tank discharge line valving. release H. Required Action B.2 and H.1 Explain in the next In accordance with associated Completion Radioactive Effluent Radioactive Effluent Time not met. Release Report why the Release Report inoperability was not frequency corrected in a timely manner.

\. Required Action and 1.1 Suspend gaseous effluent Immediately associated Completion releases monitored by the Time for Condition C, D, E inoperable channel(s).

or F not met.

J. Required Action and J.1 Suspend gaseous effluent Immediately associated Completion releases from Waste Gas Time for Condition G not Holdup System.

met.

Indian Point 2 D 3.3.2 - 3 Revision 10

Radioactive Gaseous Effluent Monitoring Instrumentation

. 03.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.3.2.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OSR 3.3.2.2 Perform CHANNEL CHECK. 7 days OSR 3.3.2.3 Perform SOURCE CHECK. Prior to release OSR 3.3.2.4 Perform SOURCE CHECK. 31 days DSR 3.3.2.5 Perform CHANNEL OPERATIONAL TEST. The 92 days CHANNEL OPERATIONAL TEST shall also demonstrate the automatic isolation capability of this pathway and that control room alarm annunciation (or control panel indications/display) occurs if the .

instrument indicates measured levels above the alarm/trip setpoint.

DSR 3.3.2.6 Perform CHANNEL OPERATIONAL TEST. The 92 days CHANNEL OPERATIONAL TEST shall also demonstrate control room alarm annunciation (or .

control panel indications/display) occurs if any of the following conditions exist, instrument indicates measured levels above the alarm setpoint, instrument controls not set in operate mode.

. OSR 3.3.2.7 Perform CHANNEL CALI BRATION. 18 months DSR 3.3.2.8 Perform CHANNEL CALIBRATION. 24 months Indian Point 2 03.3.2 - 4 Revision 10

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 1 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation REQUIRED CONDITIONS APPLICABILITY CHANNELS REFERENCED OR OTHER PER FROM SURVEILLANCE INSTRUMENT SPECIFIED INSTRUMENT REQUIRED REQUIREMENTS CONDITIONS ACTION B.1

1. Waste Gas Holdup System DSR 3.3.2.1

a. Noble Gas (b) F DSR 3.3.2.4 Activity Monitor DSR 3.3.2.6 (d)

Providing Alarm DSR 3.3.2.8 (c)

(R-SO)

2. Condenser Evacuation System DSR 3.3.2.1

a. Noble Gas (a) C DSR 3.3.2.4 Activity DSR 3.3.2.6 (e)

(R-45) DSR 3.3.2.8 (c)

3. Plant Vent Radiation Monitor:

a. Noble Gas Activity (a) & (b) C&G DSR 3.3.2.1 Radiation DSR 3.3.2.4 Monitor (R-44) DSR 3.3.2.5 ~d)

DSR 3.3.2.8 c)

Other Effluent Instrumentation:

b. Iodine Sampler (a) E DSR 3.3.2.2

c. Particulate Sampler (a) E DSR 3.3.2.2

d. Flow-Rate Monitor (a) D DSR 3.3.2.1

e. Sample Flow- DSR 3.3.2.7 Rate Monitor (a) D DSR 3.3.2.1 DSR 3.3.2.8 Indian Point 2 D 3.3.2 - 5 Revision 10

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 2 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation CONDITIONS APPLICABILITY REQUIRED REFERENCED OR OTHER CHANNELS FROM SURVEILLANCE INSTRUMENT SPECIFIED PER REQUIRED REQUIREMENTS CONDITIONS INSTRUMENT ACTION B.1

4. Main Stack Effluent (Unit 1)

Radiation Monitor:

a. Noble Gas Activity (a) C DSR 3.3.2.1 Monitor DSR 3.3.2.4 (R-60) DSR 3.3.2.6 (d)

DSR 3.3.2.8 (c)

Other Effluent Instrumentation:

b. Iodine (a) E DSR 3.3.2.2 Sampler

c. Particulate (a) E DSR 3.3.2.2 Sampler

d. Flow-Rate (a) D DSR3.3.2.1 Monitor DSR 3.3.2.7

e. Sample (a) D DSR 3.3.2.1 Flow-Rate DSR 3.3.2.8 Monitor (a) During release via this pathway. Channels shall be OPERABLE and in service on a continuous basis, except that outages are pennitted. within the time frame of the specified action for the purpose of maintenance and performance of required CHANNEL CHECK, SOURCE CHECK. CHANNEL CALIBRATION or CHANNEL OPERATIONAL TEST.

(b) During waste gas holdup system operation (treatment for primary system off-gases).

(c) Radioactive Calibration Standards used for channel calibrations shall be traceable to the National Bureau of Standards or an aliquot of calibration gas shall be analyzed with instrumentation which is calibrated with NBS traceable standards (standards from suppliers who participate in measurement assurance activities with NBS are acceptable). NBS or National Institute of Standards and Technology (NIST) are acceptable traceable standards.

(d) Test will include: Low sample flow, no counts per minute failure, and alarm setpoint reached. The CHANNEL OPERATIONAL TEST (COT) does NOT include testing of troubleshooting and equipment diagnostic capabilities provided with the monitor installation.

(e) Test will include: no counts per minute failure and alarm setpoint reached. The COT does NOT include testing of troubleshooting and equipment diagnostic capabilities provided with the monitor installation.

Indian Point 2 D 3.3.2 - 6 Revision 10

Radioactive Effluents Total Dose 03.4.1 o 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE 03.4.1 Radioactive Effluents Total Dose DLCO 3.4.1 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 CONDITION REQUIRED ACTION COMPLETION TIME A. Estimated dose or dose A.1 Verify the condition resulting Immediately commitment due to direct in doses exceeding these radiation and the release limits has been corrected.

of radioactive materials in liquid or gaseous effluents exceeds the limits.

i B. Required Action and B.1 ------------NOTE-------------

associated Completion This is the Special Report Time not met. required by 0 3.1.2, 0 3.2.2, or 0 3.2.3 supplemented with the following.

Submit a Special Report, 30 days 1

pursuant to 0 5.3, including a request for a variance in accordance with the provisions of 40 CFR 190.

This submission is considered a timely request, and a variance is granted until staff action on the request is complete.

Indian Point 2 03.4.1 - 1 Revision 10

Radioactive Effluents Total Dose 03.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 3.4.1.1 Perform a cumulative dose calculation due to 12 months radioactive material in gaseous and liquid effluents to determine compliance with OLCO 3.4.1.

Indian Point 2 03.4.1 - 2 Revision 10

Radiological Environmental Monitoring Program 03.5.1 o 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 03.5.1 Monitoring Program OLCO 3.5.1 The Radiological Environmental Monitoring Program shall be conducted as specified In Table 0 3.5.1-1.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radiological A.1 Prepare and submit to the In accordance with Environmental Monitoring NRC in the Annual the Annual Program not conducted as Radiological Environmental Radiological specified in Operating Report, a Environmental Table 0 3.5.1-1. description of the reasons Operating Report for not conducting the frequency program as required and the plans for preventing a recurrence.

B. Level of radioactivity in an B.1 ------------NOTES------------

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

Table 0 3.5.1-2 when 2. For radionuclides other averaged over any than those in Table calendar quarter. o 3.5.1-2, this report shall indicate the methodology OR and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC.

Indian Point 2 03.5.1 -1 Revision 10

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 i 30 days radionuclides in Table NRC, pursuant to D 5.3, a D 3.5.1-2 are detected in Special Report that the environmental (1) Identifies the cause( 5) for sampling medium and exceeding the Iimit(s) and Concentration 1 + (2) Defines the corrective reporting level 1 actions to be taken to reduce radioactive concentration 2 + ... ~ 1.0. effluents so that the reporting level 2 potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Radionuclides other than SpeCifications D 3.1.2, those in Table D 3.5.1-2 D 3.2.2, or D 3.2.3.

are detected in an environmental sampling OR medium at a specified location which are the B.2 ----------NOTES----------

(' result of plant effluents and 1. Only applicable if the

\"... - the potential annual dose radioactivitylradionuclides to a MEMBER OF THE are not the result of plant PUBLIC from all effluents.

radionuclides is ~ the 2.For radionuclides other calendar year limits of than those in Table SpeCifications D 3.1.2, D 3.5.1-2, this report shall D 3.2.2 or D 3.2.3. indicate the methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC.

Report and describe the In accordance with condition in the Annual the Annual Radiological Environmental Radiological Operating Report. Environmental Operating Report frequency Indian Point 2 D 3.5.1 - 2 Revision 10

Radiological Environmental Monitoring Program D 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Milk or fresh lea~ C.1 Identify specific locations 30 days vegetation samp es for obtaining replacement unavailable from one or sam~les and add them to more of the sample the adiological locations required by Environmental Monitoring Table D 3.5.1-1. Program.

AND C.2 Delete the specific 30 days locations from which samples were unavailable from the Radiological Environmental Monitoring Program.

AND C.3 Pursuant to D 5.2, submit In accordance with in the next Radioactive the Radioactive Effluent Release Report Effluent Release documentation for a Report chan~e in the ODCM reflec in~ the new location s} with supporting informatron identifyin~ the cause of the unavaila ility of samples and tustifying the selection of he new location(s) for obtaining samples.

D. Environmental samples' D.1 Ensure all efforts are made Prior to the end of required in Table 0 3.5.1-1 to complete corrective . the next sampling are unobtainable due to action(s). period samplin~ equipment malfunc Ions. AND 0.2 Report all deviations from In accordance with the sam~lin9 schedule in the the Annual Annual adlolo~cal Radiological Environmental perating Environmental Report. Operating Report Indian Point 2 D 3.5.1 - 3 Revision 10

Radiological Environmental Monitoring Program D 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Samples required by Table E.1 Choose suitable alternative I 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.

E.2 Make appropriate 30 days substitutions in the Radiological Environmental Monitoring Program.

AND E.3 Submit in the next In accordance with Radioactive Effluent the Radioactive Release Report Effluent Release documentation for a Report change in the ODCM 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.

Indian Point 2 D 3.5.1 - 4 Revision 10

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 0 3.5.1-3.

Indian Point 2 03.5.1 - 5 Revision 10

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

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

1. Direct 41 routine (1) An inner ring of stations Quarterly Gamma dose quarterly Radiation monitoring (DR1-DR16), one in each stations (b) meteorological sector in (DR1-DR41) the general area of the SITE BOUNDARY (2) An outer ring of stations (DR17-DR32), one in each meteorological sector in the 6 to 8 km range from the site (3) The balance of the stations (DR33-DR41), should be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations

2. Airbome 5 locations (1) 3 samples (A1-A3) from Continuous sampler Radioiodine canister:

Radioiodine (A1-A5) offsite locations close to operation with sample Analyze weekly for 1-131 and the site boundary in collection weekly or Particulates different sectors, of the more frequently if Particulate sampler:

highest calculated annual (1 ) Analyze for gross beta average ground level DIQ required by dust loading radioactivity ~ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change (2) 1 sample (A4) from the (d).

vicinity of an established (2) Perform gamma isotopic year-round community analysis on each sample having the highest (e) in which gross beta calculated annual average activity is > 10 times the ground level D/Q previous yearly mean of control samples.

(3) 1 sample (A5) from a control location, 15-30 km (3) Gamma isotopiC analysis of composite distant and in the least sample (e) (by location) prevalent wind direction (c) once per 3 months.

3. Waterbome

a. Surface (f) 1 sample Upstream (Wa1) Composite sample (1 ) Gamma isotopiC over a one month analYSis of each sample perlod (g) (e) once per month.

1 sample Downstream (Wa2) (2) CompOSite and analyze for H-3 quarterly.

b. Drinking 1 sample Nearest water supply (Wb1) Grab sample: Monthly (1 ) Gross beta and gamma isotopic analyses(e) of each sample monthly.

(2) Composite and analyze for H-3 quarterly.

Indian Point 2 D 3.5.1-6 Revision 10

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

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

3. Waterborne (continued)

c. Sediment 2 samples Downstream area (Wc1) Twice per year at least 90 Gamma isotopic analysis (e).

from with existing or potential days apart H-3, and Sr-OO, of each Shoreline recreational value sample semiannually.

Upstream area (Wc2) control sample

d. Ground 2 samples Site Boundary Monitoring Quarterly Gamma isotopic analysis (e),

Water Wells, drilled near the SW H-3, and Sr-OO, of each site boundary sample quarterly.

4. Ingestion

a. Milk (1) 3 samples from In 3 locations (la1-la3) Twice per month when (1 ) Gamma isotopic (e) and 1-MILK within 5 km having the animals are on pasture; 131 analysis of each SAMPLING highest dose potential monthly at other times sample twice per month LOCATIONS April through December (2) Gamma isotopic (g) and 1-131 analysis of each (2) If there are none, In each of 3 areas (la1-la3) sample once per month then 1 sample 5 to 8 km distance, if January through March if from MILK available, where doses are required SAMPLING calculated to be > 1mrem LOCATIONS per year (h)

(3) 1 sample from a At a control location (la4), Concurrently with indicator MILK 15 to 30 km distant and in locations SAMPLING the least prevalent wind LOCATION direction

b. Fish and (1) 1 sample each In the vicinity of a plant Sample in season, Gamma isotopic analysis of Invertebrates from edible discharge area (lb1) or each sample (e) , and Sr-90.

portions of Semiannually if sample is commercially or not seasonal recreationally important species (2) 1 sample of the If available in areas not same species influenced by plant discharge (lb2)

Indian Point 2 03.5.1 -7 Revision 10

Radiological Environmental Monitoring Program 03.5.1 Table 0 3.5.1-1 (page 3 of 3)

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

4. Ingestion (continued)

c. Food (1) Samplesof3 Grown nearest to each Monthly when Gamma isotopic (e) and 1-131 Products different kinds of 2 different offsite available analysis of broad leaf locations of highest vegetation (such , predicted annual as vegetables) average ground level (2) 1 sample of DIQ if milk sampling is each of the not performed (lc1-lc2) similar broad leaf vegetation.

Grown 15 to 30 km distant in the least prevalent wind direction if milk sampling is not performed (lc3)

(a) The code letters in parenthesis, e.g., DR1, A1'define generic sample locations. 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-0133, "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 permitted from the required sampling schedule if specimens are unobtainable because of such circumstances as hazardous conditions, seasonal unava.ilability, malfunction of automatic sampling equipment and other legitimate reasons.

(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 40 routine monitoring stations shall be equipped with 2 or more dosimeters or with 1 instrument 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 measuring direct radiation.

(c) 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.

(d) Airbome particulate sample filters shall be analyzed for gross beta activity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay.

(e) Gamma isotopic analysis means the identification and quantification of gamma -emitting radionuclides that m'ay be attributable to the effluents from the facility.

(f) The "upstream" samples shall be taken near the intake structures as described in the ODCM. The

• "downstream" sample shall be taken from the mixing zone at the diffuser of the discharge canal.

(g) In this program, a composite sample is one in which the quantity (aliquot) 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.

(h) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in theODCM.

Indian Point 2 03.5.1 - 8 Revision 10

Radiological Environmental Monitoring Program 03.5.1 Table 0 3.5.1-2 (pa~e 1 of 1)

Reporting Levels for Radioactivity In nvironmental Samples **

I Y()7 AIRBORNE FOOD RADlONUCLlDE PARTIUCLATE 9,R FISH MILK PRODUCTS ANALYSIS WATER GASES (pCi/m ) (pCi/kg, wet) (pCi/L) (pCi/kg, wet)

(pCilL)

H-3 20,000

• 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

'1-/0 ,

Sr-90 *** 8* 40 Zr-95 400 Nb-95 400 1-131 2* 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 Values provided are for drinking water pathways. If no drinking water pathway exists, higher values are allowed, as follows:

H-3 30,000 pCi/L (This is a 40 CFR 141 value)

Sr-90 12 pCi/L 1-131 20pCi/L These reporting levels are associated only with the REMP requirements. The Ground Water Monitoring Program may involve unique reporting level criteria, independent of the REMP, and defined in station procedures.

Sr-90 is added to this table due to its potential pathway via ground water.

Indian Point 2 03.5.1 - 9 Revision 10

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

Detection Capabilities for Environmental Sample Analysis (a) (e) I Y07 LOWER LIMIT OF DETECTION (LLD) (b) (c)

AIRBORNE PARTIUCLATE FOOD RADIONUCLIDE WATER OR GASES FISH MILK PRODUCTS SEDIMENT ANALYSIS (pCi/L) (pCi/m3) (pCi/kg, wet) (pCi/L) (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 H-3 2,000 (d)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Sr-gO (f) 5 5000 I 'lor Zr-95 15 Nb-95 15 1-131 1 (d) 0.07 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 15 15 La-140 15 15 Indian Point 2 D 3.5.1 -10 Revision 10

Radiological Environmental Monitoring Program D 3.5.1

(

/ Table D 3.5.1-3 (page 2 of 2)

'-- Detection Capabilities for Environmental Sample Analysis Table Notation (a) This list does 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 in the Annual Radiological Environmental Operating Report pursuant to SpeCification D 5.1.

(b) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

(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% probability of falsely concluding that a blank observation represents a "real" signal.

It should be recognized that the LLD is defined as an g priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (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 interfering nuclides. or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to RECS 0 5.1.

(d) These LLDs are for drinking water samples. If no drinking water pathway exists, the LLDs may be increased to 3,000 for H-3 and 15 for 1-131.

(e) These required lower limits of detection are associated only with the REMP requirements. The Ground Water Monitoring Program may involve unique reporting level criteria, independent ofthe REMP. and defined in station procedures.

(f) Sr-90 is added to this table due to its potential pathway via ground water.

Indian Point 2 D 3.5.1 - 11 Revision 10

Land Use Census 03.5.2 03.5 RADIOLOGICAL ENVIRONMENTAL MONITORING o 3.5.2 Land Use Census DLCO 3.5.2 A land use census shall:

a. Be conducted,

b. Identify within a distance of 8 km (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 0 3.5.1-1, pan 4.c may be performed in lieu of the garden census) of> 50 m 2 (500 ft ) producing broad leaf vegetation, and

c. For elevated releases, identify within a distance of 3 miles the locations, in each of the 19 meteorological sectors, of all milk animals and all gardens> 50 m producing broad leaf vegetation.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Land use census identifies A.1 Identify the new location( s) In accordance with location( s) that yields a in the next Radioactive the Radioactive calculated dose, dose Effluent Release Report. Effluent Release commitment, or D/Q value Report

> than the values currently being calculated in DSR 3.2.3.1.

Indian Point 2 D 3.5.2 - 1 Revision 10

Land Use Census D 3.5.2 ACTIONS (continued)

(

........ , CONDITION REQUIRED ACTION COMPLETION TIME B. Land use census identifies B.1 Add the new location( s) to 30 days location(s) that yields a the Radiological calculated dose, or dose Environmental Monitoring commitment (via the same Program.

exposure pathway) a factor

> 2 than at a location from AND which samples are currently being obtained in B.2 Delete the sampling After October 31 of accordance with location(s), excluding the the year in which the Table D 3.5.1-1. control station location, land use census was having the lowest conducted calculated dose, dose commitment(s} or D/Q value, via the same exposure pathway, from the Radiological Environmental Monitoring Program.

AND B.3 Submit in the next In accordance with Radioactive Effluent the Radioactive Release Report Effluent Release documentation for a change Report in the ODCM including revised figure(s) and table( s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

Indian Point 2 D 3.5.2 - 2 Revision 10

Land Use Census 03.5.2 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 In accordance with Annual Radiological Environmental Operating Report. the Annual Radiological Environmental Operating Report Indian Point 2 03.5.2 - 3 Revision 10

Interlaboratory Comparison Program D 3.5.3 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.

Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Analyses not performed as A. 1 Report the corrective In accordance with required. actions taken to prevent a the Annual*

recurrence to the NRC in Radiological the Annual Radiological Environmental Environmental Operating Operating Report Report.

SURVEILLANCE REQUIREMENTS

. SURVEILLANCE FREQUENCY DSR 3.5.3.1 Report a summary of the results obtained as part of In accordance with the Interlaboratory Comparison Program in the the Annual Annual Radiological Environmental Operating Report. Radiological Environmental Operating Report Indian Point 2 D 3.5.3 - 1 Revision 10

Solid Radwaste Treatment System D 3.6.1 D 3.6 SOLID RADIOACTIVE WASTE D 3.6.1 Solid Radwaste Treatment System DLCO 3.6.1 The appropriate equipment of the Solid Radwaste Treatment System shall be in operation process wet radioactive wastes in accordance with the Process Control Program.

APPLICABILITY: During solid radwaste processing ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive solid waste A.1 Suspend shipments of Immediately does not comply with solid radioactive waste.

Process Control Program requirements.

(

\,

Indian Point 2 D 3.6.1 - 1 Revision 10

Solid Radwaste Treatment System 03.6.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.6.1.1 Verify solidification of specimens in accordance with Prior to each the Processing Control Program. shipment DSR 3.6.1.2 Record the following information for each class of . Prior to each solid waste (as defined by 10 CFR Part 61) shipment shipped offsite during the Radioactive Effluent Release Report period:

a. Container volume.

b. total curie quantity (specify determined by measurement or estimate),

c. principal radionuclides (specify determined by measurement or estimate),

d. source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

e. type of container (e.g., LSA Type A, Type B, Large Quantity), and

f. solidification agent or absorbent (e.g., cement, urea formaldehyde):

Indian Point 2 03.6.1 - 2 Revision 10

Solid Radwaste Treatment System 03.6.1 o 3.6. SOLID RADIOACTIVE WASTE o 3.6.1 Solid Radwaste Treatment System DLCO 3.6.1 The appropriate equipment of the Solid Radwaste Treatment System shall be in operation process wet radioactive wastes in accordance with the Process Control Program.

APPLICABILITY: During solid radwaste processing ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive solid waste A.1 Suspend shipments of Immediately does not comply with solid radioactive waste.

Process Control Program requirements.

Indian Point 2 03.6.1 -1 Revision 10

Solid Radwaste Treatment System 03.6.1

( SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.6.1.1 Verify solidification of specimens in accordance with Prior to each the Processing Control Program. shipment DSR 3.6.1.2 Record the following information for each class of Prior to each solid waste (as defined by 10 CFR Part 61) shipment shipped offsite during the Radioactive Effluent Release Report period:

a. Container volume,

b. total curie quantity (specify determined by measurement or estimate),

c. principal radionuclides (specify determined by measurement or estimate),

d. source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste. evaporator bottoms).

e. type of container (e.g., LSA Type A, Type B.

Large Quantity). and

f. solidification agent or absorbent (e.g., cement, urea formaldehyde).

Indian Point 2 03.6.1 - 2 Revision 10

UNRESTRICTED AREA 04.1 04.0 DESIGN FEATURES o 4.1 UNRESTRICTED AREA 04.1.1 The definition of UNRESTRICED AREA used in implementing the Radiological Effluent Controls (RECS or ODCM Part I) has been expanded over that in 10 CFR 20.1003. For calculations performed pursuant to 10 CFR 50.36a, the concept of UNRESTRICTED AREAS refers to areas "at or beyond the SITE BOUNDARY" and does not include areas over water bodies.

A map representing the UNRESTRICTED AREA is shown in Figure 0 4.1-1 Information which will allow identification of structures and release. points for radioactive gaseous and liquid effluents is shown in Figure 0 4.1-2.

04.1.2 For the purpose of satisfying 10 CFR Part 20, the "Restricted Area" is the same as the "Exclusion Area" defined in Figure 2.2-2 of Section 2.2 of the UFSAR.

Indian Point 2 04.1 - 1 Revision 10

NRESTRICTED AREA 04.1.

Figure 04.1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS

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I RESTRICTED AREAS within .,_ __ Ir*-*~

I U\I) SITE 800NDARY are identified ~ith postlngs and do NOT apply over water.

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o I

I

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I I

\

I j

I I

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\ ...--......

\ _.... { I - - - MW-51

\. --_ / ......

MW-40

.-...........," Gypsum Plant Hudson ~

Indian Point 2 04.1 Revision 10

• • r-"':':>."

NRESTRICTED AREA D 4.1 Figure D 4.1-2 MAP DEFINING RELEASE POINTS

• GASEOUS EFFLUENT RELEASE POINT

• LIQUID EFFLUENT RELEASE POINT RWSTO N

DiSCHARGE CANAL U-3 TURBINE BLDG.

U-1 TURBINE BLDG.

U-2 TURBINE BLDG.

Indian Point 2 D 4.1 - 3 Revision 10

Annual Radiological Environmental Operating Report D 5.1 D 5.0 ADMINISTRATIVE CONTROLS o 5.1 Annual Radiological Environmental Operating Report An annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 15th of each year, according to Technical Specification 5.6.2. A single submittal may be made for a multiple unit station.

The Annual Radiological Environmental Operating Report shall include:

• Summaries, interpretations, and an analysis of trends of the results of the Radiological Environmental Monitoring Program for the report period, including a comparison, as appropriate, with preoperational studies, with operational controls, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

• At least two legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor. One map shall cover stations near the site boundary and the second shall include the more distant stations.

• The results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

• A summary deSCription of the Radiological Environmental Monitoring Program.

• A discussion of the reasons for not conducting the Radiological Environmental Monitoring Program as specified by D 3.5.1 and the plans for preventing recurrence.

• A discussion of environmental sample measurements that exceed the reporting levels of Table D 3.5.1-2 but are not the result of plant effluents.

• A discussion of all deviations from the sampling schedule of Table 0 3.5.1-1.

• A discussion of the contributing factors for cases in which the LLD required by Table o 3.5.1-3 was not achievable.

• A discussion of identifiable nuclide peaks, including those of nuclides specified in Table 03.5.1-3.

• The results of the land use census.

• The corrective actions taken to prevent a recurrence if the Interlaboratory Comparison Program is not being performed as required.

• The results of licensee participation in the Interlaboratory Comparison Program.

Indian Point 2 05.1 - 1 Revision 10

Radioactive Effluent Release Report D5.2 D 5.0 ADMINISTRATIVE CONTROLS D 5.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report to be submitted by May 1 of each year shall include:

a. A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid Gaseous Effluents from light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

b. 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 Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data onsite in a file that shall be provided to the NRC upon request

c. An assessment of the radiation doses due to the radioactive liquid and gaseous effluents releases from the unit or station during the previous calendar year.

d. An assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the SITE BOUNDARY (Figure D 4.1-1) 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. Gaseous pathway doses are determined from sampling and measurements at the exhaust pOints, coupled with the use of annual-averaged meteorological data collected from a period of live data to verify its validity. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM).

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

e. The following information for each class of solid waste (in compliance with 10 CFR Part 61) shipped offsite during the report period:

1. Container volume,

2. total curie quantity (specify whether determined by measurement or estimate),

Indian Point 2 D 5.2 - 1 Revision 10

Radioactive Effluent Release Report D 5.2 D 5.2 Radioactive Effluent Release Report (continued)

3. principal radionuclides (specify whether determined by measurement or estimate),

4. source of waste and processing employed (e.g., dewatered spent resin, compacted dry-waste, evaporator bottoms),

5. type of container (e.g., LSA, Type A, Type B, Large Quantity), and

6. solidification agent or absorbent (e.g., cement, urea formaldehyde).

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

g. Any changes made during the reporting period to the Process Control Program (PCP) and to the Offsite Dose Calculation Manual (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to SpeCification D 3.5.2.

Indian Point 2 D 5.2 - 2 Revision 10

Special Reports D 5.3 D 5.0 ADMINISTRATIVE CONTROLS D 5.3 Special Reports Special reports shall be submitted to the NRC Regional Administrator of the Region I Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the applicable Specification:

a. Radioactive Effluents (Specifications D 3.1, D 3.2 and D 3.4)

b. Radiological environmental monitoring (Specification D 3.5)

Indian Point 2 D 5.3 - 1 Revision 10

• Major Changes to Radioactive Waste Systems D5.4 D 5.0 ADMINISTRATIVE CONTROLS D 5.4 Major Changes to Radioactive Waste Systems Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid) shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the change was made. The discussion of each change shall contain:

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

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

c. a detailed description of the equipment, components and processes involved and the interfaces with other plant systems, d 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,

e. an evaluation of the change, which shows the expected maximum exposures to individuals in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto,

f. 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 in which the changes are to be made;

g. an estimate of the exposure to plant operating personnel as a result of the change,and

h. documentation of the fact that the change was reviewed and found acceptable by the OSRC.

Indian Point 2 D 5.4 - 1 Revision 10

Process Control Program 05.5 05.0 ADMINISTRATIVE CONTROLS o 5.5 Process Control Program Licensee initiated changes to the Process Control Program (PCP):

a. Shall be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:

1. sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information,

2. a determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes, and

3. documentation of the fact that the change has been reviewed and found acceptable by the OSRC.

b. Shall become effective upon review and acceptance by the OSRC.

o 5.6 Ground Water Monitoring Program (GWMP)

The GWMP shall be defined in station procedures and shall include detailed information regarding the following:

• Purpose and scope of the program

• Sample locations, types, and spedes analyzed

• Methods of archiving and retrieving historical records of analytical results

• Reporting instructions, including limits of detection

• Summary information characterizing the condition of site ground water

• An annual summary report for submittal to the NRC and/or general publication Indian Point 2 05.5 - 1 Revision 10

Indian Point 2

. Offsite Dose Calculation Manual Part I (REeS)

BASES

Applicability B 03.0 3.0 APPLICABILITY BASES DLCOs 3.0.1, 3.0.2, and 3.0.5, and DSRs 3.0.1, 3.0.2, and 3.0.3 reflect parallel requirements in the Technical Specifications. Refer to Technical Specification Bases for appropriate discussions.

ODCM Specification DLCO 3.0.3, in lieu of imposing a plant shutdown as paralleled in Technical Specification LCO 3.0.3, requires: (a) an Action to initiate efforts to restore compliance with the ODCM or associated Actions; and (b) an Action that requires entering the circumstances into the Corrective Action Program (CAP). These requirements ensure that the appropriate actions continue to be focused on and that the circumstances concerning failure to comply with the ODCM Actions would be reviewed. This review will be conducted in accordance with the procedural guidance for CAP Notifications.

There are no ODCM 3.0 SpeCifications that parallel Technical Specification LCO 3.0.4 or SR 3.0.4. Restrictions in entering MODES or other specified conditions in the Applicability have historically not been applied to ODCM SpeCifications. There are also no ODCM 3.0 SpeCifications that parallel Technical Specification LCO 3.0.6 and LCO 3.0.7, which allow for exceptions and revisions of other Technical Specifications. They are not applicable to the ODCM since it is not permitted to allow the ODCM to revise a Technical Specification.

(Note, currently no identified ODCM DLCOs support Technical Specification systems; however, this discussion is presented to address the philosophy that would be applied.) An allowance similar to Technical Specification LCO 3.0.6 does not apply to the ODCM. When a Technical Specification supported system LCO is discovered to be not met solely due tO,a ODCM support system DLCO not met, appropriate Technical Specification ACTIONS are required to be entered immediately. This applies even inlinstances where the ODCM contains a delay prior to declaring a Technical Specification supported system inoperable. In this case, certain ODCM inoperabilities may not directly impact the OPERABILITY of the Technical Specification supported system and delayed declaration of inoperability of the supported system is acceptable. In other cases, discovered support system inoperabilities that directly result in supported system inability to perform the safety function, should result in immediate declaration .

of inoperability of the supported system.

Technical Specification LCO 3.0.7 has no parallel in the ODCM since it provides for explicit changes to specified Technical Specifications by the Section 3.1.8 Specifications. However, in the event that LCO 3.0.7 provides for changes to the Technical Specification MODE definitions by the Section 3.1.8 Specifications, the revised MODE definitions apply to all plant references, including ODCM references.

Indian Point 2 B 03.0-1 Revision 10

Liquid Effluent Concentrations B D 3.1.1 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.1 Liquid Effluent Concentrations BASES It is expected that the release of radioactive materials in liquid and gaseous effluents to UNRESTRICTED AREAS will not exceed the concentration limits specified in 10 CFR Part 20 and should be as low as reasonably achievable (ALARA) in accordance with the requirement of 10 CFR 50.36a. While providing reasonable assurance that the design objectives will be met, these Specifications permit the flexibility of operation, compatible with considerations of health and safety, to ensure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the concentration limits specified in 10 CFR Part 20. It is expected that using this operational flexibility under unusual operation conditions, and exerting every effort to keep levels of radioactive materials in liquid and gaseous wastes as low as reasonably achievable, releases will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20.

The design objectives have been developed based on operating experience, taking into account a combination of variables including defective fuel, primary system leakage, primary to secondary system leakage, steam generator blowdown and the performance of the various waste treatment systems, and are consistent with 10 CFR Part 50.36a.

The Indian Point site is a multiple-unit site. There exist shared radwaste treatment systems and shared effluent release points. Where site limits must be met, the effluents of all the units will be combined to determine site compliance. For instances where unit-specific information may be required for radwaste processed or released via a shared system, the effluents shall be proportioned among the units sharing the system(s) in accordance with the methods and agreements set forth in the ODCM.

This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20. 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, 10 CFR Part 50, to a member of the public and (2) the limits of 10 CFR Part 20.1302 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 MPC 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 specification applies to the release of liquid effluents from all units on site.

Indian Point 2 B D 3.1.1 - 1 Revision 10

Liquid Effluents Dose D 3.1.2 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.2 Liquid Effluents Dose BASES This Specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The OLCO 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 material in liquid effluents will be kept "as low as reasonably achievable". Also, for fresh water sites to UNRESTRICTED AREA with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not resul~ in radionuclide concentration in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in the ODCM 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, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are.

consistent with the methodology provided in Regulatory Guide 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, Odober1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", April 1977.

In addition to the limiting conditions for operation, the reporting requirements specify that the licensee shall identify the cause whenever the dose from. the 'release of radioactive materials in

. liquid waste effluent exceeds the above limits and describe the proposed program of action to reduce such releases to design objective levels on a timely basis.

Indian Point 2 B 0 3.1.2 - 1 Revision 10

Liquid Radwaste Treatment System D 3.1.3 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.3 Liquid Radwaste Treatment System BASES This Specification requires that the licensee maintain and operate appropriate eqUipment installed in the liquid waste systems, when necessary, to provide assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonably achievable". This Specification implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objective given in Section 11.0 of Appendix I to 10 CFR Part 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 Part 50 for liquid effluents.

Indian Point 2 B D 3.1.3 - 1 Revision 10

Liquid Holdup Tanks 03.1.4 03.1 RADIOACTIVE LIQUID EFFLUENTS o 3.1.4 Liquid Holdup Tanks BASES The tanks listed in this Specification include outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. These tanks include the following:

a. Refueling Water Storage Tank

b. Primary Water Storage Tank

c. 13 Waste Distillate Storage Tank

d. 14 Waste Distillate Storage Tank

e. Outside Temporary tank Restricting the quantity of radioactive material contained in the specified tanks provides assurance that, in the event of an uncontrolled release of any such tank's contents, the resulting concentration would be less than the limits of 10 CFR 20 at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

Indian Point 2 B 03.1.4 - 1 Revision 10

Gaseous Effluents Dose Rate D 3.2.1 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS -

D 3.2.1 Gaseous Effluents Dose Rate BASES This Control provides 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 at or beyond the SITE BOUNDARY in excess of the design objectives of Appendix I to 10 CFR Part 50. This Control is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.A and II.C design objectives of Appendix I to 10 CFR Part 50.

For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be suffiCiently low to compensate for the reduced atmospheric dispersion of gaseous effluents relative to that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total 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 Control does not affect the requirement to comply with the annual limitations of 10 CFR 20.

This Control applies to the release of gaseous effluents from all units at the site.

Indian Point 2 . B D 3.2.1 - 1 Revision 10

Gaseous Effluents Dose - Noble Gas o 3.2.2 o 3.2 RADIOACTIVE GASEOUS EFFLUENTS o 3.2.2 Gaseous Effluents Dose - Noble Gas BASES This Specification is provided to implement the requirements of Sections II.B, III.A, and IV.A of Appendix I to 10 CFR Part 50. The DLCO implements the guides set forth in Section II.B 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 material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable." The Surveillance Requirements implement the requirements in Section liLA of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 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 Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases form Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

This Control applies to the release of gaseous effluents from Indian Point Units Nos. 1 and 2.

Indian Point 2 B 0 3.2.2 - 1 Revision 10

Gaseous Effluents Do'se - Iodine and Particulate o 3.2.3 o 3.2 RADIOACTIVE GASEOUS EFFLUENTS 03.2.3 Gaseous Effluents Dose -Iodine and Particulate BASES This Specification is provided to implement the requirements of Section II.C, III.A and IV.A of Appendix I to 10 CFR Part 50. The DLCOs are the guides set forth in Section II.C 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 gaseous effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable." The ODCM 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, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 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 Regulatory Guide 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 specifications for iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.

This Control applies to the release of gaseous effluents from Indian Point Units Nos. 1 and 2.

Indian Point 2 B 0 3.2.3 - 1 Revision 10

Gaseous Radwaste Treatment System D 3.2.4 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.4 Gaseous Radwaste Treatment System BASES This Specification requires that the appropriate portions of the Gaseous Radwaste Treatment System be used, when specified, to provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This*

Specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.0 of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.6 and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

This Specification applies to the release of gaseous effluents from Indian Point Units Nos. 1 and 2.

Indian Point 2 603.2.4 - 1 Revision 10

Ventilation Exhaust Treatment System o 3.2.5 o 3.2 RADIOACTIVE GASEOUS EFFLUENTS o 3.2.5 Ventilation Exhaust Treatment System BASES This Specification requires that the appropriate portions of the Ventilation Exhaust Treatment System be used, when specified, to provide reasonable assurance that the releases Of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This Specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.0 of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.8 and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

This Specification applies to the release of gaseous effluents from Indian Point Units Nos. 1 and 2.

Indian Point 2 803.2.5 - 1 Revision 10

Gas Storage Tanks D 3.2.6 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.6 Gas Storage Tanks BASES The tanks included in this Specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by other specifications to a quantity that is less than the quantity that provides assurance that, in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem in an event of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurances that, in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem. This is consistent with Branch Technical Position ETSB 11-5 in NUREG-0800, July 1981.

Indian Point 2 B D 3.2.6 - 1 Revision 10

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 D 3.3 INSTRUMENTATION D 3.3.1 Radioactive Liquid Effluent Monitoring Instrumeritation BASES The radioactive liquid effluent instrumentation, required OPERABLE by this Specification, is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with methods set forth in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of

. Appendix A to 10 CFR Part 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.

Indian Point 2 B D 3.3.1 - 1 Revision 10

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 D 3.3 INSTRUMENTATION D 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation BASES The radioactive gaseous effluent instrumentation, required OPERABLE by this Specification, is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODeM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design criteria 60, 63 and 64 in Appendix A to 10 CFR Part 50.

Indian Point 2 B D 3.3.2 - 1 Revision 10

Radioactive Effluents Total Dose D 3.4.1 D 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE D 3.4.1 Radioactive Effluents Total Dose BASES This Specification is provided to meet the dose limitation of 40 CFR Part 190 that has been incorporated into 10 CFR Part 20 by 46 FR 18525. The Specification requires the preparation and submittal of a special report whenever the calculated doses from plant-generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than.or equal to 75 mrem.

For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks 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 Part 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 contribution from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the special report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(a)(4), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in SpeCifications D 3.1.1 and D 3.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

Indian Point 2 B D 3.4.1 - 1 Revision 10

Radiological Environmental Monitoring Program D 3.5.1 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.1 Radiological Environmental Monitoring Program BASES The radiological environmental monitoring program required by this specification provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of members of the public resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 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. Program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limitsof 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 an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Indian Point 2 B D 3.5.1 - 1 Revision 10

Land Use Census D 3.5.2 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.2 Land Use Census BASES This specification is provided to ensure that changes in the use of areas at and 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 from the door-to-door survey, from aerial surveyor 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 Part 50.

Restricting the census to gardens of greater than 50 m2 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 Regulatory Guide 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 (Le., similar to lettuce and cabbage), and (2) a vegetation yield of 2kg/m2.

Indian Point 2 B D 3.5.2 - 1 Revision 10

Interlaboratory Comparison Program ci 3.5.3 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 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 material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring (developed using the guidance in Regulatory Guide 1.21, Revision 1, April 1974 and Regulatory Guide 4.1, Revision 1, April 1975) in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

Indian Point 2 B D 3.5.3-1 Revision 10

Solid Radwaste Treatment System D 3.6.1 D 3.6 SOLID RADWASTE TREATMENT SYSTEM D 3.6.1 Solid Radwaste Treatment System BASES This Specification implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the process control program may include, but are not limited to, waste type, waste pH, waste/liquid/solidification agent/catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times. .

Indian Point 2 B D 3.6.1 - 1 Revision 10

Indian Point 2 Offsite Dose Calculation Manual PART 11- CALCULATIONAL METHODOLOGIES

ODCM Part II - Calculational Methodologies 1.0 LIQUID EFFLUENT METHODOLGY 1.1 liquid Effluent Model Assumptions and Information Concentrations of radionuclides in liquid wastes are determined by sampling and analyses in accordance with the Radiological Effluent Controls (RECS.). The types of releases include both batch (Distil/ate Tanks), and continuous (Steam Generator Blowdown, North Curtain Drain, Sphere Foundation Drain Sump, etc). '

All activity concentration determinations for liquid releases are performed in a manner to ensure results are representative of the bulk water. Distillate Storage Tanks are weI/-

mixed through agitation or recirculation of contents (at least two tank contents volumes prior to sampling). Continuous Steam Generator releases are sampled daily for compositing on a weekly basis. Other continuous pathways are sampled at least weekly for generation of a flow-proportional composite. Volume calculations are derived from tank volume for batch releases, and measured flow rate or totalizer readings for continuous releases.

After mixing a tank for batch release, a sample(s) is taken to allow calculations for monitor setpoint, maximum discharge flow rate and, optionally, a monitor conversion factor (uCi/ml per net cpm) as provided in Appendices E and F. Calculations of setpoints and conversion factors are performed for continuolJ? boiler blowdown discharges to the river primarily from the most recent radioactivity analysis. If there has been a significant change in the composition of the discharge, the conversion factor may need adjustment. Simplifications to these requirements can be made in conservative approved setpoint calculations, monitor conversion factor computations, and in standard operating procedures, as long as the instantaneous concentration limits are not exceeded when considering the several release paths.

A completed and authorized discharge permit, prepared by SOP, is required prior to batch releases. Each tank discharged requires its own permit. Continuous releases should be documented but do not require a permit. Both batch and continuous releases generally include concentration limiting criteria for additional assurance of compliance with effluent regulations with minimum dilution flow.

A near-field dilution factor may be assumed with regard to dose (Part 50 compliance) calculations only. In accordance with NUREG-0133, New York University has determined that the appropriate value for use at IPEC is 5.0 [Ref. 18].

Several normally non-radioactive systems are periodically analyzed for radioactivity.

Examples include the Spent Fuel Pool Auxiliary Heat Exchanger Secondary Cooling' System (when in use), and Site Storm Drains, etc. The monitoring program for these types of release points is consistent with the direction set forth in NRC IE Bulletin 80-10 '/01 "Contamination of Non-radioactive Systems and Resulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to Environment". Should a system become contaminated, releases are evaluated and quantified (as either batch or continuous) in accordance with the requirements listed in the RECS and the IPEC 80-10 program, or as defined in the Ground Water Monitoring Program.

Indian Point 2 Page 1 Revision 10

ODCM*Part II - Calculational Methodologies Radioactivity content in outdoor tanks is to be limited to less than 10 curies, excluding tritium and noble gas, as per the RECS. Compliance with this requirement is demonstrated by limiting the radioactive concentration in these tanks to the value which results in 10 curies when the tank is at full liquid capacity, except as modified below.

The radioactive concentration limits for these tanks are:

. x *lO-~- j.1C'I 6

RWST: -lOcuriesxl0

- - - - - - 'j.1Cilcurie

- - - - - = 73 I m I

358,500gal x 3785mll gal lO curies xl 0 ~Ci I curie = 1.6 xl 0- 2 ~Ci I ml 6

PWST:

l65,000gals x 3785mll gal 13 & 14 WDST:

10 curies x 10 6 ~Cil curie 1.1 X 10- 1 ~lCii ml 23,577 gals x 3785 mIl gal Outside Temporary Tanks:

10 curies x 10-6 j.1Ci I curie

')c-r

- - - - - - - - - - = j.1Ci I ml Volume (gal) x 3785mll gal Integrated curies in a tank can similarly be determined by calculating the curies added from known inlet concentrations and volumes, which would then be combined with previously determined tank curie levels.

Investigations from the Ground Water Monitoring Program (GWMP) may result in a determination of liquid effluent. A quantification and dose assessment of radioactive groundwater or storm water leaving the site shall be performed at least annually.

This quantification shall include, as a minimum, the source term from samples obtained near the effluent points of each applicable pathway (eg, ground water wells nearest the site boundary), and a determination of release rate and dilution flow.

Release rates to the river from both the bedrock pathways and collective storm drain pathways are provided from modeling by hydrologists, as determined from the annual average rainfall, the condition of the surface area over the effected zones, and other studies of ground water .

movement, per Reference 24.

Dilution flow is directly measured in the Discharge Canal for the Storm Drain component. For groundwater reaching the Hudson via a direct path under the canal, a dilution factor equivalent to a 6-hour half-tidal surge in the effected area of the Hudson applies, as discussed in Reference 25.

Dose calculations are otherwise then completed per Section 1.4, with results included in the annual effluent report, as defined in the GWMP.

See Table 1-1 for a listing of applicable liquid effluent control specifications.

Indian Point 2 Page 2 Revision 10

ODCM Part II - Calculational Methodologies 1.2 Determination of Setpoints for Liquid Effluent Monitors Section 4.1 and Appendix E identify methods of establishing liquid effluent radiation monitor setpoints. Normally, a calculation is performed with each release to determine the Allowed Diluted Concentration (ADC). However, a method is also provided in Attachment E to use an isotope-specific fraction of the Maximum Permissible Concentration. The ADC method is preferred because it includes an estimate of the impact of Beta emitters to the proximity of the 10CFR20 limit, despite the fact that the radiation monitor sees only gamma radiation. A diluted concentration limit of 2E-4 uCi/ml is applied to all dissolved and entrained noble gases.

Radiation Monitor Setpoints and associated compliance with 10CFR20 involve an awareness of all radioactive liquid waste releases on site. For example, setpoints may be increased with additional dilution flow "borrowed" from unit 3, provided there is documented communication between the shift managers. Conservatively, a minimum dilution flow of 100,000 gpm is normally dedicated to one unit's routine liquid effluent to ensure sufficient operational margin to comply with 10CFR20 limitations.

The Liquid Radwaste Effluent monitor shall alarm and suspend a release in the event that setpoints are exceeded or approached. The setpoints derived in Section 4.1 and Appendix E ensure diluted concentrations of each isotope is below the required MPC for all release pathways and modes. The setpoint does not account for decay or dispersion beyond the restricted area boundary and thus conservatively controls the effect at the junction of the discharge canal and river.

Monitor conversion factors are generally determined experimentally with actual plant fluid or with calibration mixtures. Noble gases may contribute to monitor response and must be included in the determination of a monitor conversion factor, as shown in Appendix F. The general requirements for setpoints and conversion factors apply to all releases.

1.3 Determining the Dose for Radioactive Liquid Effluents The RECS require a calculation at least once per 31 days, to verify required operation of the radwaste cleanup systems when cumulative releases of radioactivity in liquid effluents are expected to cause a dose in excess of 0.06 mrem total body, or 0.2 mrem to any organ. The 10CFR50 quarterly and annual time averaged limits are also defined in the RECS as follows:

Total Body Any Organ Quarterly limit 1.5 mrem 5mrem Annual limit 3mrem 10 mrem The drinking water pumping station on the Hudson River (Chelsea) is beyond the distance requiring impact consideration. Similarly, REMP samples and calculations of doses from historical shoreline deposits indicate that potable water and shoreline deposit pathways need not be considered for offsite dose calculations. Therefore, consumption of fish and shellfish (invertebrates) alone is considered.

The Hudson River at Indian Point is a mixture of fresh and saltwater. The average salinity of the river is about 15% of ocean salinity so that there is an admixture of freshwater and saltwater fish and shellfish in the plant environs. Using data provided from References 18 and 20. the optimum bioaccumulation factors for Indian Point are the values from Reg Guide 1.109 for fresh water fish and salt water invertebrates, Indian Point 2 Page 3 Revision 10

ODCM Part II - Calculational Methodologies coupled with those site-specific values identified in the referenced studies. Resulting site-specific bioaccumulation and dose factors, as well as their justification are further explained in part II of the Indian Point 3 ODCM, section 2.6.

Carbon 14 is released at a rate of .07 curies per GW(e)/yr with an average make up rate of 0.5 gal/min based upon studies performed by the New York State Department of Health. The estimate of Carbon 14 releases are included in the Radiological Impact on Man section of the Annual Radioactive Effluent Release Report. Although the calculations use the same models, these estimates are not included in dose calculations for routine releases due to their inflated contribution from natural causes.

1.4 Dose Calculations The organ dose from all radionuclides i released in a specific calendar period, T, is:

DT =L (AiDFi L .1tpij P) (L-1 )

j Where:

DT - organ dose commitment (mrem)

Ai - site related ingestion dose commitment factor (mrem/hr per fJCi/ml) for nuclide i Lly - incremental release period j for release of nuclide i within the calendar period (hours)

DFI - Environmental Transit Time,factor (tp from RG 1.109 and unitless),

represented as e -I..t, where t is the delay between sampling and start of release, and A is the decay constant (sec -1) for nuclide i.

. This term is conservatively set to 1.0, but may be applied as needed, in rare cases of short-lived isotopes in liquid waste.

undiluted concentration of nuclide i during release period Lltj (fJCi/ml)

F' near-field average dilution (unitless)

= liquid radioactive waste flowl (circulating flow x K)

K site specific applicable factor (determined by New York University to have a value of 5)

To better manage a hand calculation, a limited analysis based on the dominant contributors to dose can be performed. The 1988-90 data shows that, in orderof decreasing impact, the following nuclides require consideration in the limited analysis:

Cs-137, Cs-134, Ni-63, H-3, Co-60. It is advisable to also include Fe-55, Co-58, and any Iodine identified, especially in Steam Generator Slowdown, where Iodine can dominate the total activity.

Indian Point 2 Page 4 Revision 10

ODCM Part II - Calculational Methodologies From Appendix E, with the dilution applied to the isotopic concentrations, the equation becomes:

DT = 2: (AiDF 2: ~tjCij) (L-2) i < j where; Cij = (f/F) X Cij = dilute concentration From NUREG-0133 (page 17), the summary dose factor is defined as:

A;r = K[(UF)BF; + (UI)BI; ]DF; (L-3)

Where:

AiT = Composite dose parameter for the total body or critical organ for nuclide, i, for all appropriate pathways, mrem/hr per ).lCi/ml.

K = Units conversion factor, 114155 = (1 E6pCi/uCi) * (1 E3ml/kg) 8760 hr/yr UF = kg/yr fish consumption from Table E-5 of Regulatory Guide 1.109:

21 Adult 6.9 Child 16 Teen o Infant BFi = Fresh Water Fish Bioaccumulationfactor for nuclide, i, in pCi/kg per pCi/1 from Table A-1 of Regulatory Guide 1.109..

UI = kg/yr invertebrate consumption from Table E-5 of Regulatory Guide 1.109:

5.0 Adult 1.7 Child 3.8 Teen o Infant Bli = Salt Water Invertebrates Bioaccumulation factor for nuclide, i, in pCi/kg per pCi/1 from Table A-1 of Regulatory Guide 1.109.

DFi = Dose conversion factor for nuclide i, for age groups in pre-selected organs, T, in .mrem/pCi, from Tables E-11, 12 & 13 of Regulatory Guide 1.109.

Compiled AiT factors for 3 age groups and various organs for the maximum exposed individual are provided in Tables 1.2, 1.3, and 1.4. Bio-accumulation factors for liquid effluent isotopes are provided in Table 1.5. These tables include all isotopes found in Reg Guide 1.109. Some non-routine isotopes and site-specific data were added from studies at Indian Point units 2 and 3, including bioaccumulation factors for Antimony, Silver, Cesium, and Niobium.

Indian Point 2 Page 5 Revision 10

aDCM Part II - Calculational Methodologies TABLE 1*1

SUMMARY

OF LIQUID RECS DOSE RATE RECS The diluted concentration of each isotope in UNRESTRICTED AREAS is limited to the Maximum Permissible Concentration identified per RECS Section 01.1. The diluted concentration of dissolved or entrained noble gases are limited to 2E-4 uCilml.

DOSE RECS Dose commitment to any member of public in UNRESTRICTED AREAS is limited to:

1) In any calendar quarter, 1.5 mrem to the total body and 5 mrem to any organ.

2) In a calendar year, 3 mrem to the total body and 10 mrem to any organ.

PROJECTIONS Projection of liquid doses shall be computed at least every 31 days, as follows:

major ]

Dose ] Current Month Dose + Previous months' Dose I d

[ Projection = +/- P anne number of months used [ evolutions The term for planned evolutions is routinely determined from previous similar evolutions, such as releases associated with plant shutdown.

If projected doses would exceed the limits in the RECS:

0.06 mrem total body, or 0.2 mrem critical organ, clean-up treatment systems are required to be operational.

Indian Point 2 Page 6 Revision 10

ODCM Part II - Calculational Methodologies TABLE 1-2 Page 1 of 2 Site Related Adult Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 BE-7 3.29E-01 7.45E-01 3.69E-01 O.OOE+OO 7.83£-01 O.OOE+OO 1. 28E+02 NA-24 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.08E+02 P-32 4.96E+07 3.08E+06 1.92E+06 O.OOE+OO O.OOE+OO O.OOE+OO 5.57E+06 CR-51 O.OOE+OO O.OOE+OO 4.31E+00 2.58E+00 9.50E-Ol 5.72E+00 1.08E+03 r'IN-54 O.OOE+OO 5.43E+03 1.04E+03 O.OOE+OO 1.61E+03 O.OOE+OO 1.66E+04 MN-56 O.OOE+OO 1.37E+02 2.42E+Ol O.OOE+OO 1.73E+02 O.OOE+OO 4.36E+03 FE-55 3.21E+04 2.21E+04 5.16E+03 O.OOE+OO O.OOE+OO 1.24E+04 1.27E+04 FE-59 5.06E+04 1.l9E+05 4.56E+04 O.OOE+OO O.OOE+OO 3.32E+04 3.96E+05 CO-58 O.OOE+OO 5.15E+02 1.15E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E+04 CO-60 O.OOE+OO 1.48E+03 3.26E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.78E+04 NI-63 4.97E+04 3.45E+03 1.67E+03 O.OOE+OO O.OOE+OO O.OOE+OO 7.19E+02 NI-65 2.02E+02 2.62E+01 1.20E+01 O.OOE+OO O.OOE+OO O.OOE+OO 6.65E+02 CU-64 O.OOE+OO 9.08E+01 *4.26E+Ol O.OOE+OO 2.29E+02 O.OOE+OO 7.74E+03 ZN-65 1.61E+05 5.13E+05 2.32E+05 O.OOE+OO 3.43E+05 O.OOE+OO 3.23E+05 ZN-69 3.43E+02 6.57E+02 4.57E+Ol O.OOE+OO 4.27E+02 O.OOE+OO 9.87E+01 BR-83 O.OOE+OO O.OOE+OO 4.05E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 5.84E+01 BR-84 O.OOE+OO O.OOE+OO 5.25E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 4.13E-04 BR-85 O.OOE+OO O.OOE+OO 2.16E+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 1.01E+05 4.72E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.00E+04 RB-88 O.OOE+OO 2.91E+02 1.54E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.02E-09 RB-89 O.OOE+OO 1.93E+02 1.35E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.12E-11 SR-89 2.57E+04 O.OOE+OO 7.37E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.12E+03 SR-90 6.32E+05 O.OOE+OO 1.55E+05 O.OOE+OO O.OOE+OO O.OOE+OO 1.82E+04 SR-91 4.72E+02 O.OOE+OO 1.91E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 2.25E+03 SR-92 ./1.79E+02 O.OOE+Oo. 7.75E+00 O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+03 Y-90 6.07E+00 O.OOE+OO 1.63E-Ol O.OOE+OO O.OOE+OO O.OOE+OO 6.43E+04 Y-91M 5.73E-02 O.OOE+OO 2.22E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.68E-Ol Y-91 8.89E+01 O.OOE+OO 2.38E+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.89E+04 Y-92 5.33E-01 O.OOE+OO 1.56£-02 O.OOE+OO O.OOE+OO O.OOE+OO 9.33E+03 Y-93 1.69E+00 O.OOE+OO 4.67E-02 O.OOE+OO O.OOE+OO O.OOE+OO 5.36E+04 ZR-95 1.63E+00 5.22E-Ol 3.54E-01 O.OOE+OO 8.20E-Ol O.OOE+OO 1.66E+03 ZR-97 9.00E-02 1.82E-02 8.30E-03 O.OOE+OO 2.74E-02 O.OOE+OO 5.63E+03 NB-95 4.83E+00 2.69E+00 1.44E+00 O.OOE+OO 2.65E+00 O.OOE+OO 1.63E+04 MO-99 O.OOE+OO 1.28E+02 2.43E+Ol O.OOE+OO 2.90E+02 0.00£+00 2.97£+02 TC-99M 1.59E-02 4.50£-02 5.73E-Ol O.OOE+OO 6.24E-Ol 2.21E-02 2.66E+Ol TC-I01 1.64E-02 2.36E-02 2.32E-01 O.OOE+OO 4.25E-Ol 1.21E-02 7.*09E-14 RU-103 1.10E+02 O.OOE+OO 4.74E+01 O.OOE+OO 4.20E+02 O.OOE+OO 1.28E+04 RU-105 9.16E+00 O.OOE+OO 3.62E+00 O.OOE+OO 1.18E+02 O.OOE+OO 5.60E+03 RU-106 1.64E+03 O.OOE+OO 2.07E+02 O.OOE+OO 3.16E+03 O.OOE+OO 1.06E+05 AG-llOM 4.58E+02 4.23E+02 2.51E+02 O.OOE+OO 8.32E+02 O.OOE+OO 1.73E+05 SB-122 3.47£+01 7.99E-Ol 1.20E+01 5.38S-01 O.OOE+OO 2.08E+01 1.32E+04 SB-124 4.86E+02 9.20E+OO 1.91E+02 1.182+00 O.OOE+OO 3.79E+02 1.38E+04 3B-125 3.llE+02 3.47E+00 7.40E+01 3.16E-01 O.OOE+OO 2.402+02 3.42E+03 Indian Point 2 Page 7 Revision 10

aDCM Part II - Calculational Methodologies TABLE 1-2 Page 2 of 2 Site Related Adult Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr' per uCi/ml ISOTOPE BONE LIVER TOT 'BODY THYROID KIDNEY LUNG GI-LLI TE-125M 2.72E+03 9.87E+02 3.65E+02 8.19E+02 1.11E+04 O.OOE+OO 1.09E+04 TE-127M 6.88E+03 2.46E+03 8.38E+02 1. 76E+03 2.79E+04 O.OOE+OO 2.'31E+04 TE-l27 1.12E+02 4.01E+01 2.42E+01 8.28E+01 4.55E+02 O.OOE+OO 8.82E+03 TE-129M 1.17E+04 4.36E+03 1.85E+03 4.01E+03 4.88E+04 O.OOE+OO 5.88E+04 TE-129 3.19E+01 1.20E+01 7.77E+00 2.45E+01 1. 34E+02 O.OOE+OO 2.41E+01 TE-cl31M 1.76E+03 8.60E+02 7.16E+02 1.36E+03 8.71E+03 O.OOE+OO 8.53E+04 TE-l31 2.0.oE+01 8.36E+00 6.32£+00 1.65E+01 8.77E+01 O.OOE+OO 2.83E+00 TE-l32 2.56E+03 1.66E+03 1.55E+03 1. 83E+03 1.60E+04 O.OOE+OO 7.83E+04 1-130 4.88E+01 1.44E+02 5.68E+01 1. 22E+04 2.24E+02 O.OOE+OO 1.24E+02 1-131 2.68E+02 3.84E+02 2.20E+02 1. 26E+05 6.58E+02 O.OOE+OO ,1.01E+02 1-132 1.31E+01 3.50E+01 1.23E+01 1. 23E+03 5.58E+01 O.OOE+OO 6.58E+00 1-133 9.16E+01 1. 59E+02 4 . .86E+01 2.34E+04 2.78E+02 O.OOE+OO 1.43E+02 1-134 6.84E+00 1.86E+01 6.64E+00 3.22E+02 2.95E+01 O.OOE+OO 1.62E-02 1-135 2.86E+01 7.48E+01 2.76E+01 4.93E+03 1.20E+02 O.OOE+OO 8.45E+01 CS-134 4.14E+04 9.84E+04 8.04E+04 O.OOE+OO 3.18E+04 1.06E+04 1.72E+03 CS-l36 4.33E+03 1.71E+04 1.23E+04 O.OOE+OO 9.51E+03 1.30E+03 1.94E+03 CS-l37 5.30E+04 7.25E+04 4.75E+04 O.OOE+OO 2.46E+04 8.18E+03 1.40E+03 CS-138 3.67E+01 7.25E+01 3.59E+01 O.OOE+OO 5.33E+01 5.26E+00 3.09E-04 BA-l39 6.47E+00 4.61E-03 1.89E-01 O.OOE+OO 4.31E-03 2.61E-03 1.15E+01 BA-140 1.3SE+03 1.70E+00 8.87E+01 O.OOE+OO 5.78E-01 9.73E-01 2.79E+03 BA-l4l 3;14E+00 2.37E-03 1. 0.6E~01 O.. OOE+OO 2.21E-03 1.35E-03 1.48E-09 BA~142 1. 42E+00 1.46£,..03 '8.93E"02 O.*OOE+OO 1.23E.,.03 8.27E-04 2.00E-'18 LA"140 1. 58E+00 7.95E~01 2.10E:"01 O.OOE+OO O.OOE+OO O.OOE+OO 5.83E+04 LA-142 8.07E-02 3.67E-02 9.1SE-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.68E+02 CE-l4l 3.23E+00 2.18E+00 2.48£-01 O.OOE+OO 1.01E+00 O.OOE+OO 8.35E+03 CE-143 S.69E-01 4.21E+02 4.66E-02 O.OOE+OO 1.85E-01 O.OOE+OO 1.57E+04 CE-144 1.68E+02 7.04E+Ol 9.04E+00 O.OOE+OO 4.17E+Ol O.OOE+OO 5.69E+04 PR-143 5.80E+00 2.33E+00 2,88E.,.01 O.OOE+OO 1.34E+00 O.OOE+OO 2.54E+04 PR-144 1.90E-02 7.88E-03 9.65E-04 O.OOE+OO 4.4SE-03 O.OOE+OO 2.73E-09 ND-l47 3.97E+00 4.59E+00 2.74E-01 O.OOE+OO 2.68E+00 O.OOE+OO 2.20E+04 W-187 2.98E+02 2.49E+02 8.71E+01 ' O. OOE+OO O.OOE+OO O.OOE+OO 8.16E+04 NP-239 3.53E-02 3.47E-03 1. 91E-03 O.OOE+OO 1.08E-02 O.OOE+OO 7.12E+02 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-57 O.OOE+OO 1.21E+02 2.01E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.07E+03 SR-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-97 4.05E-.o2 1.02E-02 3.74E-03 O.OOE+OO 1.20E-02 O,.OOE+O.O 3.78E+01 CD-109 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SN-113 O,OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-I33 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-134 3.29E+01 2.1SE+01 1.32E+01 2.88E+01 2.08E+02 O.OOE+OO 3.65E-02 CE-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO HG-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 2 Page 8 Revision 10

ODCM Part II - Calculational Methodologies TABLE 1-3 Page 1 of 2 Site Related Teen Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 2.17E-Ol 2.17E-Ol 2.17E-Ol 2.17E-Ol 2.17E-Ol 2.17E-Ol BE-7 3.58£-01 8.02E-01 4.01E-Ol O.OOE+OO 8.50E-Ol O.OOE+OO 9.76E+Ol NA-24 4.20£+02 4.20E+02 4.20E+02 4.20£+02 4.20E+02 4.20E+02 4.20£+02 P-32 5.40E+07 3.35E+06 2.09E+06 O.OOE+OO O.OOS+OO a.oos+OO 4.54£+06 CR-51 0.00£+00 O.OOE+OO 4.44E+00 2.47E+00 9.73E-Ol 6.34E+00 7.46E+02

~lN-54 O.OOE+OO 5.33E+03 1.06£+03 O.OOE+OO 1.59E+03 O.OOE+OO 1.09E+04

~-56 O.OOE+OO 1.43E+02 2.54E+Ol O.OOE+OO 1.81E+02 O.OOE+OO 9.40E+03 FE-55 3.35E+04 2.37E+04 5.54E+03 O.OOE+OO O.OOE+OO 1. 51E+04 1.03E+04 FE-59 5.20E+04 1.21E+05 4.69E+04 O.OOE+OO O.OOE+OO 3.83E+04 2.87E+05 CO-58 O.OOE+OO 5.10E+02 1.18E+03 O.OOE+OO O.OOE+OO O.OOE+OO 7.04E+03 CO-60 O.OOE+OO 1.48E+03 3.32E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1. 92E+04 NI-63 5.15E+04 3.64E+03 1.75E+03 O.OOE+OO O.OOE+OO O.OOE+OO 5.79E+02 NI-65 2.18E+02 2.79E+Ol 1.27E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.51E+03 CU-64 O.OOE+OO 9.53E+Ol 4.48E+01 O.OOE+OO 2.41E+02 O.OOE+OO 7.39E+03 ZN-'65 1.46E+05 5:07E+05 2.36E+05 O.OOE+OO 3.24E+05 O.OOE+OO 2.15E+05 ZN-69 3.73E+02 7.10E+02 4.97E+01 O.OOE+OO 4.64E+02 O.OOE+OO 1.31E+03 BR-83 O.OOE+OO O.OOE+OO 4.41E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-84 O.OOE+OO O.OOE+OO 5.55E+Ol O.OOE+OO O.OOE+OO O'.OOE+OO O.OOE+OO BR-85 O.OOE+OO O.OOE+OO 2.34E+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 o :OOE+OO 1. 09E+05 5.12E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.61E+04 RB-88 O.OOE+OO 3.12E+02 1.66E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.67E-05 RB-89 O.OOE+OO 2.01E+02 1.42E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.09E-07 SR-89 2.79E+04 O.OOE+OO 8.00E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.33E+03 SR-90 5.27E+05 O.OOE+OO 1.30E+05 O.OOE+OO O.OOE+OO O.OOE+OO 1.48E+04 SR-91 ' 5.12E+02 O.OOE+OO 2.04E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 2.32E+03 SR-92 1.94E+02 O.OOE+OO 8.25E+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.93E+03 Y-90 6.57E+00 O.OOE+OO 1.77E-01 O.OOE+OO O.OOE+OO O.OOE+OO 5.42E+04 Y-91M 6.18E-02 O.OOE+OO 2.36E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.92E+00 Y-91 9.64E+01 O.OOE+OO 2.58E+00 O.OOE+OO O.OOE+OO O.OOE+OO 3.95E+04 Y-92 5.80E-01 O.OOE+OO 1.68E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.59E+04 Y-93 1.84E+00 O.OOE+OO 5.03E-02 O.OOE+OO O.OOE+OO O.OOE+OO 5.61E+04 ZR-95 1.68E+00 5.29E-01 3.64E-01 O.OOE+OO 7.78E-01 O.OOE+OO 1.22E+03 ZR-97 9.65E-02 1.91E-02 8.80E-03 O.OOE+OO 2.90E-02 O.OOE+OO 5.17E+03 NB-95 4.86E+00 2.70E+00 1.48E+00 O.OOE+OO 2.61E+00 O.OOE+OO 1. 15E+04 MO-99 O.OOE+OO 1.36E+02 2.60E+01 O.OOE+OO 3.12E+02 O.OOE+OO 2.44E+02 TC-99M 1.63E~02 4.55E-02 5.89E-01 O.OOE+OO 6.77£-01 2.52E-02, 2.98E+01 TC-101 1.77E-02 2.51E-02 2.47E-Ol 0.00£+00 4.55E-01 1.53E-02 4.30E-09 RU-103 1.15£+02 O.OOE+OO 4.93E+01 O.OOE+OO 4.06£+02 O.OOE+OO 9.63E+03 "U-I05 9.85E+00 O.OOE+OO 3.82E+00 O.OOE+OO 1.24E+02 O.OOE+OO 7.96E+03 RU-106 1.77£+03 0.00£+00 2.23E+02 0.00£+00 3.42E+03 0.00£+00 8.50E+04 AG-l10M 4.45E+02 4.22£+02 2.56E+02 O.OOE+OO 8.04E+02 0.00£+00 1.18E+05 SB-122 4.35E+01 8.47£-01 1.27E+Ol 5.53£-01 O.OOE+OO 2.72E+Ol 9.13E+03 S8-124 5.09£+02 9.40E+00 1.99£+02 1. 16E+00 O.OOE+OO 4.45E+02 1.03E+04 SB-125 3.27E+02 3.58E+00 7.64E+Ol 3.11E-01 O.OOE+OO 2.85E+02 2.53E+03 Indian Point 2 Page 9 Revision 10

aDCM Part II - Calculational Methodologies

/

TABLE 1-3 Page 2 of 2 Site Related Teen Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Irivertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI TE-125M 2.96E+03 1.07E+03 3.96E+02 8.28E+02 O.OOE+OO O.OOE+OO 8.75E+03 TE-127M 7.48E+03 2.65E+03 8.90E+02 1. 78E+03 3.03E+04 O.OOE+OO 1.87E+04 TE-127 1.22E+02 4.33E+01 2.63E+01 8.44E+01 4.95E+02 O.OOE+OO 9.44E+03 TE-129M 1.26E+04 4.68E+03 2.00E+03 4.07E+03 5.28E+04 O.OOE+OO 4.74E+04 TE-129 3.47E+01 1.29E+01 8.44E+00 2.48E+01 1.46E+02 O.OOE+OO 1.90E+02 TE-131M 1.89E+03 9.06E+02 7.55E+02 1. 36E+03 9.44E+03 O.OOE+OO 7.27E+04 TE-131 2.16E+01 8.90E+00 6.75E+00 1. 66E+01 9.44E+01 O.OOE+OO 1.77E+00 TE-132 2.70E+03 1.71E+03 1.61E+03 1.80E+03 1.64E+04 O.OOE+OO 5.42E+04 1-130 5.06E+01 1.46E+02 5.84E+01 1.19E+04 2.25E+02 O.OOE+OO 1.12E+02 1-131 2.87E+02 4.02E+02 2.16E+02 1.17E+05 6.92E+02 O.OOE+OO 7.95E+01 I-132 1.37E+01 3.58E+01 1.29E+01 1.21E+03 5.64E+01 O.OOE+OO 1. 56E+01 1-133 9.87E+01 1.67E+02 5.11E+01 2.34E+04 2.94E+02 O.OOE+OO 1.27E+02 I-134 7.17E+00 1. 90E+01 6.82E+00 3.17E+02 2.99E+01 O.OOE+OO 2.50E-01 1-135 2.99E+01 7.71E+01 2.86E+01 4.96E+03 1. 22E+02 O.OOE+OO 8.54E+01 CS-134 4.24E+04 9.97E+04 4.63E+04 O.OOE+OO 3.17E+04 1.21E+04 1.24E+03 CS-136 4.35E+03 1. 71E+04 1.15E+04 O.OOE+OO 9.32E+03 1.47E+03 1.38E+03 CS-137 5.67E+04 7.54E+04 2.63E+04 O.OOE+OO 2.57.8+04 9.97E+03 1.07E+03 CS-138 3.93E+01 7.54E+01 3.77E+0.1 O.OOE+OO 5.57E+01 6.48E+00 3.42E-02 BA-139 7.05E+00 4.96E-03 2.05E-01 O.OOE+OO 4.67E-03 3.42£-03 6.28E+01 BA-140 1.44E+03 1.76E+00 9.28E+01 O.OOE+OO 5.98E-01 1.19E+00 2.22E+03 BA-141 3.40E+00 2.54E-03 1.14E-01 O.OOE+OO 2.36E-03 1. 74£-03 7. 25E:"'06 BA-142 1.52E+00 1.52E-03 9.33E-02 O.OOE+OO 1. 28E-03 1. 01E-03 4.65E-12 LA-14 0 1.67E+00 8.20E-01 2.18E-01 O.OOE+OO O.OOE+OO O.OOE+OO 4.71E+04 LA-142 8.58E-02 3.81E-02 9.49E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.16E+03 CE-141 3.49E+00 2.33E+00 2.67E-01 O.OOE+OO 1.10E+00 O.OOE+OO 6.66E+03 CE-143 6.16E-01 4.48E+02 5.01E-02 O.OOE+OO 2.01E-01 O.OOE+OO 1.35E+04 CE-144 1.82E+02 7.55E+01 9.80E+00 O.OOE+OO 4.51E+01 O.OOE+OO 4.59E+04 PR-143 6.28E+00 2.51E+00 3.13E-01 O.OOE+OO 1.46E+00 O.OOE+OO 2.07E+04 PR-144 2.06E-02 8.44E-03 1.05E-03 O.OOE+OO 4.84E-03 O.OOE+OO 2.27E-05 ND-I47 4.50E+00 4.89E+00 2.93E-01 O.OOE+OO 2.87E+00 O.OOE+OO 1.76E+04 W-187 3.22E+02 2.62E+02 9.19E+01 O.OOE+OO O.OOE+OO O.OOE+OO 7.10E+04 NP-239 3.98E-02 3.75E-03 2.08E-03 O.OOE+OO 1.18E-02 O.OOE+OO 6.03E+02 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-57 O.OOE+OO 1.25E+02 2.10E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E+03 SR-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO' Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00:0:+00 O.OOE+OO NB-97 4.36E-02 1.08E-02 3.95E-03 O.OOE+OO 1.27E-02 O.OOE+OO 2.58E+02 CD-109 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00:0:+00 O.OOE+OO SN-113 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-134 3.46E+01 2.22E+01 2.32E+01 2.84E+01 2.12E+02 O.OOE+OO 1.28E+00 CE-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO HG-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 2 Page 10 Revision 10

ODCM Part II - Calculational Methodologies TABLE 1-4 Page 1 of 2 Site Related Child Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 1.81E-Ol 1.81E-Ol 1.81E-01 1. 81E-01 1.81E-Ol 1.81E-01 3E-7 4.77E-01 8.08E-01 5.33E-01 O.OOE+OO 7.96E-01 O.OOE+OO 4.52E+01 NA-24 4.57E+02 4.57E+02 4.57E+02 4.57E+02 4.57E+02 4.57E+02 4.57E+02 P-32 6.98E+07 3.27E+06 2.69E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1.93E+06 CR-51 O.OOE+OO O.OOE+OO 4.86E+00 2.70E+00 7.37E-01 4.92E+00 2.58E+02 MN-54 O.OOE+OO 4.20E+03 1.12E+03 O.OOE+OO 1. 18E+03 O.OOE+OO 3.53E+03 MN-56 O.OOE+OO 1.31E+02 2.96E+01 O.OOE+OO 1.59E+02 O.OOE+OO 1.90E+04 FE-55 4.55E+04 2.42E+04 7.48E+03 O.OOE+OO O.OOE+OO 1.37E+04 4.47E+03 FE-59 6.53E+04 1. 06E+05 5.27E+04 O.OOE+OO O.OOE+OO 3.07E+04 1.10E+05 CO-58 O.OOE+OO 4.20E+02 1.29E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.45E+03 CO-60 O.OOE+OO 1. 23E+03 3.64E+03 O.OOE+OO O.OOE+OO O.OOE+OO 6.84E+03 NI-63 6.85E+04 3.67E+03 2.33E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.47E+02 NI-65 2.83E+02 2.66E+01 1. 55E+01 O.OOE+OO O.OOE+OO O.OOE+OO 3.26E+03 CU-64 O.OOE+OO 9.05E+01 5.47E+Ol O.OOE+OO 2.19E+02 O.OOE+OO 4.25E+03 ZN-65 1.55E+05 4.12E+05 2.56E+05 O.OOE+OO 2.59E+05 O.OOE+OO 7.23E+04 ZN-69 4.94E+02 7.14E+02 6.60E+01 O.OOE+OO 4.33E+02 O.OOE+OO 4.50E+04 BR-83 O.OOE+OO O.OOE+OO 5.67E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-84 O.OOE+OO O.OOE+OO 6.56E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-85 O.OOE+OO O.OOE+OO 3.02E+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 1.06E+05 6.50E+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.80E+03 RB-88 0.00£+00 3.00E+02 2.08E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1. 47E+01 RB-89 O.OOE+OO 1.85E+02 . 1.64E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.61E+00 SR-89 3.63E+04 O.OOE+OO 1.04E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.41E+03 SR-90 4.68E+05 O.OOE+OO 1. 19E+05 O.OOE+OO O.OOE+OO O.OOE+OO 6.30E+03 SR-91 6.60E+02 O.OOE+OO 2.49E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.46E+03 SR-92 2.48E+02 O.OOE+OO 9.96E+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.70E+03 Y-90 8.79E+00 O.OOE+OO 2.35E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.50E+04 Y-91M 8.17E-02 O.OOE+OO 2.97E-03 O.OOE+OO ,O.OOE+OO O.OOE+OO 1.60E+02 Y--91 1.29E+02 O.OOE+OO 3.44E+00 O.OOE+OO O.OOE+OO O.OOE+OO 1.71E+04 Y-92 7.70E-01 O.OOE+OO 2.20E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.22E+04 Y-93 2.44E+00 O.OOE+OO 6.69E-02 O.OOE+OO O.OOE+OO O.OOE+OO 3.63E+04 ZR-95 2.10E+00 4.62E-01 4.llE-01 O.OOE+OO 6.62E-01 O.OOE+OO 4.82E+02 zR-1n 1.27E-01 1.83E-02 1. 08E-02 ' O. OOE+OO 2.63E-02 O.OOE+OO 2.77E+03 NB-95 5.75E+00 2.24E+00 1.60E+00 O.OOE+OO 2.10E+00 O.OOE+OO 4.14E+03 110-99 O.OOE+OO 1.31E+02 3.23E+01 O.OOE+OO . 2.79E+02 O.OOE+OO 1.08E+02 TC-99M 1.99E-02 3,89E-02 6.46E-01 O.OOE+OO 5.66E-01 1. 98E-02 2.22E+01 TC-101 2.30E-02 2.4lE-02 3.06E-01 O.OOE+OO 4.llE-01 1.27E-02 7.66E-02 RU-103 1.48E+02 0.00£+00 5.67E+01 O.OOE+OO 3.72£+02 O.OOE+OO 3.82E+03 RU-105 1.30E+01 O.OOE+OO 4.73E+00 O.OOE+OO 1.15E+02 O.OOE+OO 8.50E+03 RU-106 2.36E+03 O.OOE+OO 2.95E+02 O.OOE+OO 3.19E+03 O.OOE+OO 3.68E+04 AG-llOM 5.24E+02 3.54E+02 2.83E+02 O.OOE+OO 6.59E+02 O.OOE+OO 4.21E+04 SB-122 5.80E+01 8,56E-Or 1. 70E+01 7.43E-01 O.OOE+OO 2.36E+01 4.46£+03 SB-124 6.55E+02 8.50£+00 2.29E+02 1.44E+OO O.OOE+OO 3.63E+02 4.09E+03 SB-125 4.22E+02 3.25E+00 8.85E+01 3.91E-01 O.OOE+OO 2.35E+02 1.01E+03 Indian Point 2 Page 11 Revision 10

ODCM Part II - Calculational Methodologies TABLE 1-4 Page 2 of 2 Site Related Child Ingestion Dose Commitment Factors (Freshwater Fish and Sa1.twater Invertebrate Consumption)

(AiT) mR/hr per uCi/m1 ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI TE-125M 3.81E+03 l. 03E+03 5.08E+02 1. 07E+03 O.OOE+OO O.OOE+OO 3.68E+03 TE-I27M 9.67E+03 2.60E+03 1.15E+03 2.31E+03 2.76E+04 O.OOE+OO 7.83E+03 TE-I27 1.58E+02 4.25E+01 3.38E+Ol 1.09E+02 4.48E+02 O.OOE+OO 6.15E+03 TE-129M 1.63E+04 4.55E+03 2.53E+03 5.25E+03 4.78E+04 O.OOE+OO l.99E+04 TE-129 4.48E+01 1.2SE+01 1.06E+Ol 3.20E+Ol 1.31E+02 O.OOE+OO 2.79E+03 TE-131M 2.41E+03 8.33E+02 8.86E+02 1.71E+03 8.06E+03 O.OOE+OO 3.38E+04 TE-131 2.78E+01 8.46E+00 8.26E+00 2.12E+Ol 8.40E+Ol O.OOE+OO l.46Et02 TE-132 3.38E+03 l. 50E+03 1.81E+03 2.18E+03 1.39E+04 O.OOE+OO 1.51E+04 1-130 6.28E+01 1.27E+02 6.54E+Ol 1.40E+04 1.90E+02 O.OOE+OO 5.94E+01 1-131 3.70E+02 3.72E+02 2.12E+02 1.23E+05 6.11E+02 O.OOE+OO 3.31E+01 1-132 1.72E+01 3.16E+01 1.4SE+01 1.47E+03 4.84E+01 O.OOE+OO 3.72E+01 1-133 1.27E+02 1.58M02 S.96E+01 2.93E+04 2.63E+02 O.OOE+OO 6.35E+01 1-134 9.02E+00 1.67E+01 7.70E+00 3.85E+02 2.56E+01 O.OOE+OO 1.11E+01 1-135 3.77E+01 6.78£+01 3.21E+01 6.00E+03 1.04E+02 O.OOE+OO 5.16E+01 CS-134 S.15E+04 8.44E+04 1.78E+04 O.OOE+OO 2.62E+04 9.39E+03 4.55E+02 CS-136 5.17E+03 l. 42E+04 9.19E+03 O.OOE+OO 7.56E+03 1.13E+03 4.99E+02 CS-137 7.19E+04 6.88E+04 1.02E+04 O.OOE+OO 2.24E+04 8.07E+03 4.31E+02 C3-138 5.01E+01 6.97E+01 4.42E+01 O.OOE+OO 4.90E+01 5.28E+00 3.21E+Ol BA-139 9.34E+00 4.99E-03 2.71E-01 O.OOE+OO 4.35E-03 2.93E-03 5.39E+02 BA-140 1.87E+03 1.64E+00 1.09E+02 O.OOE+OO 5.35E-01 9.79E-01 9.S0E+02 BA-141 4.S1E+00 2.S3E-03 1. 47E-01 O.OOE+OO 2.19E-03 1.48E-02 2.S7E+00 BA-142 1.97E+00 1. 42E-03 1.10E-01 O.OOE+OO 1.1SE-03 8.3SE-04 2.S7E-02 LA-140 2.16E+00 7.SSE-01 2.54E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+04 LA-142 1.12E-01 3.57E-02 1.12E-02 O.OOE+OO O.OOE+OO O.OOE+OO 7.08E+03 C£-141 4.6SE+00 2.32E+00 3.4SE-01 *O.OOE+OO 1.02E+00 O.OOE+OO 2.90E+03 CE-143 8.l9E-01 4.44E+02 6.44£-02 O.OOE+OO 1.86E-01 O.OOE+OO 6.51E+03 CE-144 2.44E+02 7.64E+01 1.30E+01 O.OOE+OO 4.23E+01 O.OOE+OO 1.99E+04 PR-l43 8.40E+00 2.S2E+00 4.17E-01 O.OOE+OO 1.37E+00 O.OOE+OO 9.06E+03 PR-144 , 2.76E-02 8.53E-03 1.39E-03 O.OOE+OO 4.S1E-03 O.OOE+OO 1.84E+01 ND-147 5.96E+00 4.83E+00 3.74E-01 O.OOE+OO 2.65E+00 O.OOE+OO 7.65E+03 W-187 4.08E+02 2.42E+02 1.08E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.40E+04 NP-239 5.1SE-02 3.70E-03 2.60E-03 O.OOE+OO 1.07E-02 O.OOE+OO 2.74E+02 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-57 O.OOE+OO 1.15E+02 2.33E+02 O.OOE+OO O.OOE+OO O.OOE+OO 9.43E+02 SR-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-94 O.OOE+OO O.OOE+OO 0.002+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-97 5.55E-02 l. 00E-02 4.682-03 O.OOE+OO 1.11E-02 O.OOE+OO 3.09E+03 CD-109 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SN-l13 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-l33 O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-134 4.31E+01 1.9t1E+01 2.5%+01 3.41E+01 1.80E+02 O.OOE+OO 1.97E+02 CE-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.002+00 O.OOE+OO O.OOE+OO HG-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO Indian Point 2 Page 12 Revision 10

aDeM Part II - Calculational Methodologies TABLE 1-5 Bio-Accumulation Factors for Liquid Effluent Isotopes (pCi/kg per pCi/liter)

Freshl-later Sa1tl-later Freshl-later Sa1tl-later ISOTOPE Fish Invertebrates I ISOTOPE Fish Invertebrates BFi Bli I BFi Bli

---

1------------------------------------

H-3 9.000£-01 9.300£-01 1 T£-125M 4.000E+02 1.000£+02 B£-7 2.000E+00 2.000£+02 1 T£-127M 4.000E+02 1.000£+02 NA-24 1.000£+02 1.900E-01 1 TE-127 4.000E+02 1.000£+02 P-32 1.000£+05 3.000E+04 I TE-129M 4.000E+02 1.000£+02 CR-51 2.000£+02 2.000E+03 1 TE-129 4.000E+02 1.000£+02 MN-54 4.000E+02 4.000E+02 I TE-131M 4.000E+02 1.000£+02 MN-56 4.000E+02 4.000E+02 1 TE-131 4.000E+02 1.000E+02 FE-5°5 1.000E+02 2.000E+04 1 TE-132 4.000E+02 1.000E+02 FE-59 1.000E+02 2.000E+04 1 1-130 1.500E+Ol 5.000E+Ol CO-58 5.000E+Ol 1.000£+03 I 1-131 1.500E+Ol 5.000E+Ol CO-60 5.000E+Ol 1.000E+03 1 1-132 1.500E+Ol 5.000E+Ol NI-63 1.000£+02 2.500£+02 I 1-133 1.500E+01 5.000E+01 N1-65 1.000£+02 2.500E+02 I 1-134 1.500E+Ol 5.000E+01 CU-64 5.000E+01 1. 700£+03 1 1-135 1.500E+01 5.000E+Ol ZN-65 2.000E+03 5.000£+04 1 CS-134 2.240E+02 2.240E+02 ZN-69 2.000E+03 5.000£+04 I CS-136 2.240E+02 2.240£+02 BR-83 4.200£+02 3.100£+00 I CS-137 2.240E+02 2.240E+02 BR-84 4.200£+02 3.100£+00 I CS-138 2.240E+02 2.240E+02 BR-85 4.200£+02 3.100E+00 I BA-139 4.000E+00 1.000E+02 RB-86 2.000£+03 1.700E+Ol 1 BA-140 4.000E+00 1.000£+02 RB-88 2.000£+03 1. 700£+01 I BA-141 4.000£+00 1.000£+02 RB-89 2.000£+03 1. 700£+01 I BA-142 4.000E+00 1.000£+02 SR-89 3.000E+Ol 2.000E+Ol I LA-140 o 2.500E+01 1.000E+03 SR-90 3.000£+01 2.000E+01 1 LA-142 2.500E+01 1.000E+03 SR-91 3.000£+01 2.000E+01 1 CE-141 1.000E+00 6.000E+02 SR-92 3.000E+01 2.000E+01 I C£-143 1.000E+00 6.000E+02 Y-90 2.500E+01 1.000E+03 I C£-144 1.000E+00 6.000E+02 Y-91M 2.500E+01 1.000E+03 1 PR-143 2.500E+01 1.000E+03 Y-91 2.500E+01 1.000E+03 PR-144 2.500E+01 1.000E+03 Y-92 2.500E+01 1.000E+03 ND-147 2.500E+01 1.000E+03 Y-93 2.500£+01 1.000E+03 W-187 1.200E+03 3.000E+01 ZR-95 3.300E+00 8.000E+01 NP-239 1.000E+01 1.000£+01 ZR-97 3.300E+00 8.000E+01 K-40 O.OOOE+OO O.OOOE+OO NB-95 3.000E+02 1.000E+02 CO-57 5.000E+01 1.000E+03

~10-9 9 1.000£+01 1.000E+01 SR-85 O.OOOE+OO O.OOOE+OO TC-99M 1.500E+01 5.000E+01 Y-88 O.OOOE+OO O.OOOE+OO TC-IOI 1.500E+01 5.000£+01 NB-94 3.000E+02 1.000E+02 RU-103 1.000E+Ol 1.000£+03 NB-97 3.000E+02 1.000E+02 RU-I05 1.000E+Ol 1.000E+03 CD-109 O.OOOE+OO O.OOOE+OO RU-I06 1.000E+01 1.000E+03 SN-1l3 O.OOOE+OO O.OOOE+OO AG-I10M 2.300E+00 5.000E+03 BA-133 O.OOOE+OO O.OOOE+OO 3B-122 1.000E+00 3.000E+02 TE-134 4.000£+02 1.000£+02 3B-124 1.000E+00 3.000E+02 CE-139 0.000£+00 0.000£+00 SB-125 1.000E+00 3.000E+02 HG-203 O.OOOE+OO O.OOOE+OO Bio-Accumulation Factors and DFi's for Noble Gases 0 Indian Point 2 Page 13 Revision 10

ODCM Part II - Calculational Methodologies 2.0 GASEOUS EFFLUENT METHODOLOGIES 2.1 Gaseous Effluent Model Assumptions and Information Gaseous effluents discharge primarily through the Unit 2 plant vent (el 267') and to a much lesser extent through the following:

o Unit 1 Stack (el 400');

o .Secondary Boiler Blowdown Flash Tank, i.e. Blowdown Tank Vent (eI120');

o Secondary Boiler Blowdown Purification System Vent (el 165');

o Unit 2 Condenser Air Ejector Vent (el 75');

o Maintenance and Outage Building Exhaust.

Airborne releases up to early 1992 have been treated as ground releases. Site specific data collection in 1992 and again in 2004 has provided 10-yr averaged meteorological dispersion and deposition data for mixed-mode releases, as well as the application of Finite Cloud correction (applied to Revision 4 of this manual and thereafter). The methodology for finite cloud and mixed-mode realistic releases was provided in NYPA Calculation IP3-CALC-RAD-00001 Rev. 0, and updated in Entech Engineering Reports P115-196-EC1 through EC3. Specific dispersion and deposition factors are given in Appendix A, along with ground-level factors, appropriate for condenser air ejector releases. A discussion of the derivation of the resulting equations and their use can be found in IPEC unit 3 ODCM, sections 3.5 and 3.6.

Dose and setpoint calculations employ historical annual average dispersion factors in the highest of sixteen sectors. The sector annual average methodology is defended on the basis that there are no seasonal or daily biases in the times in which releases occur.

Tables 2-2 through 2-12 include dose factors for all nuclides expected in effluents.

Should a nuclide be detected that is not represented in these tables, the dose factors are determined from applicable references and the pertinent calculations performed in accordance with this manual. Conversely, nuclides that are represented in these tables but not detected are reported absent from the sample and assigned a zero value. Lower limits of detection (LLD) methods are described in Section 5.0.

Condenser Air Ejector (CAE) releases may become significant for computations of cumulative dose, but are not significant for instantaneous set pOint consideration. As a result, radiation monitor setpoints for CAE releases are selected to assure less than 1% .

instantaneous impact at release rates limits. Station procedures provide methodology to calculate release rate setpoints in accordance with 10CFR20 and show the relative insignificance of this pathway with respect to approaching the applicable release rate limits.

Because the limits in 10CFR20 for individuals in unrestricted areas apply to site effluents, some adjustment must be made for the fact that both units 2 and 3 discharge gaseous effluents and that the unit 3 vent is closer to the critical sector site boundary than unit 2's. The partition, then, is not precisely 50-50. The noble gas dose is split approximately 53%/47% (IP3/IP2), while the organ dose from Iodine and Particulate is split approximately 67%133%.

Indian Point 2 Page 14 Revision 10

ODCM Part II - Calculational Methodologies Appendix I demonstrates the equivalent uCi/sec from instantaneous, quarterly, and annual dose rate limitations for use in setpoint calculations or management of effluent release rate. The annual limit is normally used for routine Plant Vent release rates. The quarterly limit may be applied with permission from the Site Operations Manager. The instantaneous limit may be applied with permission from the General Manager - Plant Operations (per Section 4.2).

All releases (including batch) are considered "long term" in relation to the definition in NUREG 0133 because they total greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> and are sufficiently random.

However, if short-term releases occur, the appropriate short-term dispersion factor should be utilized. Such factors can be derived from the cited calculation in unit 3's ODCM or taken from another appropriate reference. The impact of short-term releases is considered simultaneously with all other releases with regard to setpoint selection and dose or dose rate computations.

Normally, releases of noble gases are the most limiting with regard to approaching site limits. For this reason and because it is considered impractical to apply trip points and alarms to ,integrating monitors sensitive to iodines and particulates, radiation monitor trip points for release points are based on the noble gas component of gaseous effluents.

Because the particulate and iodine contribution to receptor dose equivalents is historically very low, and full analytical results from associated radiochemical analyses require months to complete, releases are administratively controlled from noble gas values. Typically, the ratio of noble gas to iodine is greater than 10,000. The ratio is conservatively reduced to 100 when applied to the deSign basis accident scenario for IPEC to ensure Iodine is conservatively modeled in accident calculations after a SG Tube Rupture. Despite this modeling used to justify administratively using noble gas setpoints for control, actual calculations are performed in detail after-the-fact, per the ODCM, in the case of any actual Iodine or particulate releases.

The RECS require a dose projection at least once per 31 days to determine the need for use of the cleanup systems. Although most of these systems are in service at all times, cleanup systems such as iodine removal charcoal beds or gas tank holdup would be required if the 31-day dose projection approached the associated limits in the RECS.

Proximity to these limits can be evaluated at any time from the use of a database tracking system for 10CFR50 doses to date.

Carbon 14 is released at a rate of 9.6 curies per GW(e)/yr based upon studies performed by the New York State Department of Health at Indian Point 3. This is released in a gaseous form, the primary dose from which is in the CO 2 form. Therefore, these are exempt from the dose limits specified in Sections 2.4.1, 2.4.3 and 2.4.4 of the RECS. The Carbon 14 doses resulting from these releases are calculated in accordance with the methodology in Reg. Guide 1.109 and listed in the Radiological Impact on Man section of the Annual Radioactive Effluent Release Report. This calculation is performed using the fraction of Carbon-14 released in the CO2 form (26%).

Though the methodologies for calculating doses for noble gases, iodines and particulates allow for accurate dose modeling with any type of mixture, it is beneficial to back-calculate release rates (uCi/sec) for use in Operations procedures with a standard conservative mix. Mixtures established in Table 2-8, and methodology demonstrated in Appendix I were used to derive annual, quarterly, and instantaneous release rate setpoints shown is Section 4.2.

Indian Point 2 Page 15 Revision 10

aDCM Part II - Calculational Methodologies Table 2-1 is a compilation of gaseous RECS dose and dose rate criteria. The dose rate criteria are used in radiation monitor setpoint calculations in Appendix I. The integrated dose limits are applied in the database tracking mechanism for 10CFR50 compliance.

Tables 2-2 through 2-12 are listings of dose factors, descriptions of various release mixtures, distances to the site boundary and nearest residence, and other data required to calculate doses in the following sections.

2.2 Determination of Releases from Indirectly Monitored Sources The effluents from the Slowdown Flash Tank Vent and the Secondary Purification System Vent are not directly monitored. This section describes appropriate methodology for determining release rates from these vents. The methodology is based on NUREG-0133 Section 5.6.3. Usually, only H-3 and potentially 1-131 and 1-133 are of interest.

A determination of the iodine releases via a flash tank can be made by calculating the iodine content in secondary water and using the following equation:

q =CRj (1-S0) (release rate from tank vent in ~LCi/sec)

Where:

C == iodine concentration in secondary coolant water (~Ci/ml) averaged over a time not in excess of one week R == letdown rate to the tank (mllsec) j == The fraction of liquid flashed in the tank as determined by a heat balance taken around the tank at the applicable reactor power level so == measured steam quality, or an assumed value of 0.85, at the vent Appendix D provides guidance on the calculation of f. C and R are process variables and SO is assumed to be 0.85 in the absence of a measurement.

2.3 Noble Gas Releases Dose Rates for Total Body and Skin The following is the calculational method for determining instantaneous noble gas dose rates to the total body and skin. According to approved maximum-individual methodology, all releases use the annual average meteorological constants, unless a ground level or short-term release is identified. Maximum total body and skin dose rates are assumed to occur in the critical receptor (highest dose). Ground level x/O values are used for Condenser Air Ejector releases.

The total body dose rate from noble gas releases is:

(G-1 )

Indian Point 2 Page 16 Revision 10

aDCM Part II - Calculational Methodologies and the skin dose rate from noble gas releases is:

(G-2)

Where:

total body dose rate from noble gas releases (mrem/yr)

DRsKIN skin dose rate from noble gas releases (mrem/yr)

. (X/Q) highest of 16 sectors site boundary annual average relative concentration (sec/m 3 ) ,

whole body dose transfer factor for nuclide i (mrem/yr per /lCi/m 3 )

[from RG 1.109]

beta skin dose transfer factor for nuclide i (mrem/yr per /lCi/m 3 )

[from RG 1.109]

air dose transfer factor for gamma emissions of nuclide i (mrad/yr' per /lCi/m 3 ) [from RG1.1 09]

1.1 conversion from gamma air dose rate to tissue dose equivalent rate (mrem/mrad) release rate of nuclide i (/lCi/sec) total release rate of all noble gas nuclides, (/lCi/sec)

From an evaluation of past releases, a simplification introduced in Section 2.1 can be adopted for total body dose rate calculations. If the appropriate long-term distribution of q (the total releases of noble gases) is known, then it follows that there is some weighted factor which, multiplied byq, yields the same dose rate computed by using equation G-1.

Where:

= Weighted average of all isotopes' K factor per the following general equation: .

Keu = (1/ qr> I i=!

(qj )(Ki)

. Leading to:

(G-3)

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aDCM Part II - Calculational Methodologies When this type of calculation is performed for Radiation Monitor setpoint calculations, a conservative factor (not to exceed 1.25) may be applied as a final step to reflect maximum expected radiation monitor error. Simply multiply the final Dose Rate by the chosen factor.

Kelf is normally calculated with each release. For setpoint calculations, a back-calculation (similar to that of Appendix I), is performed with an expected Kelf such that uCi/cc or uCi/sec values can be obtained. Values of Ki and other noble gas dose factors are taken from Tables 2-4 through 2-7 of this section.

2.4 Determining the Radioiodine. a-day Particulate and Tritium Instantaneous Dose Rates from Gaseous Releases Total dose rates for radioiodine, a-day particulate and tritium releases are calculated for 4 age groups and each organ at the critical site boundary location. Typically, a computer code calculates and reports dose rate for each organ and age group at the highest site boundary location. Although ground plane and milk pathways are also included in the reference source (NUREG-0133), only the inhalation pathway is applicable to IPEC. The ground plane pathway has been shown to be insignificant, and the land use census identifies no milk pathway at the site boundary. Since it is very unlikely that a milch animal will ever be identified at the site boundary, the terms in NUREG-0133 for this pathway need not be included routinely, and simply added if the land use census should later include this pathway.

Therefore, the general equation for the single organ dose rate is:

DR = (X/Q) L (Pi

• qi) (inhalation only) (G-4) i Where:

DR = single organ total dose rate (mrem/year)

X/Q = as previously defined Pi = ( dose parameters for inhalation pathway (mrem/year per J.,lCi/m3) for nuclide i qi = release rate of nuclide i (J.,lCi/sec)

Computed values of Pi for all age groups, organs, and nuclides for the inhalation pathway are represented in Tables 2-2a through 2-2d in this section. X/Q values may be obtained from Appendix A or other source as allowed in Section 2.1.

Should the land use census be updated to include a the cow-milk pathway, the equation above would be updated as follows:

(mrem/year) (G-5)

Where:

Pit = inhalation dose parameter for all pathways for all organs except bone (bone 0) in mrem/yr per J.,lCi/m 3

=

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ODCM Part II - Calculational Methodologies Pmt = milk ingestion dose parameter (bone =0) in mrem/yr per /lCi/m 3 X/Q = as previously defined X/Q 5 = highest of 16 sectors 5 mile annual average relative concentration, in sec/ m 3 (only used when the 5-mile cow-milk pathway is utilized) qt = total Iodine and Particulate, H-3 release rate, in /lCi/sec The parameter Pi is calculated as follows:

Pi = K'

• BR

• OFi (G-6)

K' = Conversion constant 1E6 pCi/uCi BR* = Breathing rate for each age group per Reg Guide 1.109, Table E-5, as follows:

Infant = 1400 m3/yr Child = 3700 m 3/yr AdultlTeen = BOOO m 3/yr

= Inhalation dose factor for each age group, organ, and nuclide, in mrem/pCi. These values were taken from Reg Guide 1.109, Tables E-7 through E-9, reproduced in Tables 2-2a through 2-2d.

The age group and organ with the highest dose rate is the limiting organ.

For practical reasons, monitor setpoints for the total control of gaseous releases will not depend directly on the monitor responses to radioiodines, B-day particulate and tritium.

The noble gas monitors can be used to indirectly control release rates such that the instantaneous organ dose rates are maintained below the RECS or administrative limits.

If a computer code is not available, a simple calculation using Iodine dose factors can yield a bounding dose rate. Total organ dose rate to the thyroid by radioiodines can be considered for instantaneous releases as follows:

ORT "'. OR thy = (X/Q) [I*Pi*qi] iodines (inhalation only) (G-7) 2.5 Gamma Air Dose for Noble Gas Releases RECS require calculation of gamma air dose from cumulative noble gas releases. The dose for any selected time (month, quarter, year) is:

gamma air mrad = 3.17E-8*IMi[(XIQ)(Qi)+(xlq)(qi)j (G-B)

Gamma Air dose is limited to 5 mrad per quarter and 10 mrad per year; Indian Point 2 Page 19 Revision 10

OOCM Part II - Calculational Methodologies (XJO) =The highest calculated annual average relative concentration for the unrestricted area boundary in the controlling sector for long term releases (greater than 500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />s/year or 150 hour0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />s/quarter), in sec/m 3 (x/q) = The relative concentration for the unrestricted area boundary for short term releases (equal to or less than 500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />s/year or 150 hour0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />s/quarter and NOT sufficiently random as defined in NUREG 0133, Section 3.3).

Mi = The air dose factor due to gamma emission for each identified noble gas radionuclide in mrad/yr per IlCi/m3.

Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide in mrad/yr per !lCi/m 3.

qi = The total release of noble gas radionuclides in gaseous effluents, i, for short term releases (equal to or less than 500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />s/year or 150 hour0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />s/quarter and NOT random as defined in NUREG 0133, Section 3.3) from all vents, in IlCi, over the calendar quarter or year as appropriate.

Qi = The total release of noble gas radionuclides in gaseous effluents, i, for long term releases (greater than 500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />s/year or 150 hour0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />s/quarter) from all vents in IlCi, over the calendar quarter or year as appropriate.

.O( = The total release rate of all noble gas nuclides, in uCi/sec (the sum of all 0 1).

3.17 E-8 = The inverse of the number of seconds in a year.

The air dose factors Mi and Ni were obtained from Table 8-1 of Reg Guide 1.109 and are listed in Table 2-6 and 2-7. The M air dose factors are finite cloud corrected.

A single effective gamma air dose rate factor of noble gases can be derived from a known mi~ture by weighting each isotope's factor (M) and deriving Meff in similar fashion to the earlier expression Keff:

Which leads to:

Oair. gamma = (x/a) * (Meff )

• at (G-9)

Indian Point 2 Page 20 Revision 10

ODCM Part II - Calculational Methodologies Monthly, quarterly, and annual gamma air doses are computed with actual release data (with an appropriately weighted M factor). Doses are also projected for the 31-day dose projection requirements to allow comparison with RECS limits.

2.6 Beta Air Dose for Noble Gas Releases In similar fashion, the beta air dose from cumulative releases of noble gases can be calculated. The dose for any selected time (month, quarter, year) is:

beta air mrad = 3.17 E - 8 *I Ni r(X/Q) (fli) + (r/q)( qiJj (G-10)

Where beta air mrad is limited to 10 mrad per quarter and 20 mrad per year, with other terms defined in previous steps.

One can also determine Neff in a similar fashion to Meff:

=

and also write D air , beta = (X/Q)Neff Qt (G-11 )

Monthly, quarterly, and annual beta air doses are computed with actual release data (with an appropriately weighted N factor). Doses are also projected for the 31-day dose projection requirements to allow comparison with RECS limits. '

2.7 Determining the Radioiodines. a-Day Particulate and Tritium Cumulative Doses from Gaseous Releases The pathways considered in this analysis are inhalation, ground plane, and vegetable ingestion at the nearest resident. The meat and milk ingestion pathways are not considered because of the lack of milk-producing animals within ten miles of the plant, and because of the high degree of commercial, industrial, and residential land usage in the area, as defined by the land use census. Doses are ,calculated at a critical receptor, identified as the nearest resident with the worst meteorological data. Although the nearest resident is in the ESE direction, the worst sector and most conservative data for dose calculations is in the SSW, per Table 2-9, Appendix I, and Reference 9.

The equations for calculating the dose limitations are obtained from NUREG 0133 and reduce to the following:

During any calendar quarter:

(3.17E-08)*I (Ri(WQi + wqi) must be less than 7.5 mrem (G-12)

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aDCM Part II - Calculational Methodologies During any calendar year:

(3.J7E-08)*I (Ri(WQi + }vqi) must be less than 15mrem (G-13)

Where:

Qi = The plant releases of radioiodine 131 and radioactive materials in particulate form with half-lives greater than 8 days for long term releases, in ~Ci. Releases shall be cumulative over the calendar quarter or year, as appropriate.

qi = The plant releases of radioiodine 131 and radioactive materials in' particulate form'with half-lives greater than 8 days for short term releases, in ~Ci. Releases shall be cumulative over the calendar quarter or year, as appropriate.

W = The dispersion or deposition parameter for estimating the dose to' an individual at the nearest resident for long term releases.

w = The vent dispersion or deposition parameter for estimating the dose to an individual at the nearest resident for short term releases.

3.17 E-08 =The inverse number of seconds in a year.

Ri = The dose factor for each identified pathway, organ, and radionuclide, i, in m2 - mrem/yr per J,lCi/sec, or mrem/yr per ~Ci/m3. These dose factors are determined as described the following steps.

Utilizing the assumptions above, these equations for the nearest resident reduce to the following:

DN=(3.17E-8iijRi(I)* [Wn(in)& +wn(in)qi} +(Ri(G)+ Ri(V))* [Wn(dep)iji + wn(depfiij] (G-14)

Where:

DN = total dose at the nearest residence, and must be less than or equal to 7.5 mrem per quarter, and less than or equal to 15 mrem annually.

Wn(in) = The highest calculated annual average dispersion parameter for the inhalation pathway for the nearest residence in the unrestricted area at the controlling location, in sec/m 3, wn(in) = The dispersion parameter for the inhalation pathway for the nearest residence in the unrestricted area at the controlling location, in sec/m 3 , corrected for short term releases, Indian Point 2 Page 22 Revision 10

aDCM Part II - Calculational Methodologies Wn(dep) = The highest calculated annual average deposition parameter for the nearest residence in the unrestricted area at the controlling location, in m-2 , for all isotopes except Tritium, which uses the X/Q value instead (sec/m 3 ).

wn(dep)= The deposition parameter for the nearest residence in the unrestricted area at the controlling location, in m-2 , for all isotopes except Tritium, which uses the X/Q value instead (sec/m 3 ), corrected for short term releases.

Qi = The. plant releases of radioiodine 131 and radioactive' material~ in particulate form with half-lives greater than 8 days for long term releases as defined earlier, (uCi)_

qi = The plant releases of radioiodine 131 and radioactive materials in particulate form with half-lives greater than 8 days for short term releases as defined earlier (uCi).

Ri (I). = Inhalation pathway factor for each radionuclide, i.

= K' * [(BR) a] * [(DFi) a] (mrem/yr per I-lCi/m 3 ) (G-15)

Where; K' = 1E6 pCi/uCi BRa = Age-specific breathing rate (see 2.4)

DFia= Inhalation dose factor for age group, organ, and isotope, per Table 2~2a through 2-2d (from Reg Guide 1.109, Tables E-7 through' E-10).

Ri (G) = Ground plane pathway factor for each radionuclide, i.

K' K"(SF)(DFGi)(l- e<-kit>> m 2

• mreml yr (G-16)

Ki uci Isec Where:

and K" = 8760 hr/yr ki = Decay constant for the ith radionuclide, sec- 1 .

t = The exposure time, 4.73 x 108 sec (15 years)

DFGi ~ The ground plane dose conversion factor for ith radionuclide, in mrem/hr per pCi/m 2 (Table 2.2e, from Reg Guide 1.109 Table E-6).

SF = Shielding factor (dimensionless) = 0.7 (from Reg Guide 1.109, Table E-1S).

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aDCM Part II - Calculational Methodologies Ri (V) = Vegetation pathway factor for each radionuclide, i.

K:(r) * (DFLi)a * [(UaL).IL

• e(-kilL) + (UaS)fg

• e(-kirIJ)] (G-17)

YV(kl + hI!)

Where:

K' = 1E6 pCi//.lCi

= Dimensionless correction factor for the fraction of deposited activity retained on crops for Iodine and Particulate from Table E-15 of Reg Guide 1.109, as follows:

0.2 for particulates 1.0 for radioiodine DFLia = Ingestion dose factors for each nuclide in mrem/pCi (Tables 2-3a thru 2-3d, from Reg Guide 1.109 Tables E-11 through E-14).

UaL = Consumption rate of fresh leafy vegetation by the receptor in age group (a) in kg/yr (Reg Guide 1.109, Table E-5).

ki = Decay constant for the radionuclide, in sec *1 UaS = Consumption rate of non-leafy vegetables by the receptor in age group (a) in kg/yr (Reg Guide 1.109, Table E-5).

fL = The fraction of the annual intake of leafy vegetation grown locally (Reg Guide 1.109, Table E-15).

fg = The fraction of the annual intake of non-leafy vegetation grown locally (Reg Guide 1.109, Table E-15).

kw = Decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73E-7 sec -1 (corresponding to a 14dayhalf-lifefrom Reg Guide 1.109, Table E-15).

tL = The average time between harvest of leafy vegetation and its consumption in seconds (Reg Guide 1.109, Table E-15).

th = The average time between harvest of stored vegetation and its consumption in seconds (Reg Guide 1.109, Table E-15).

Yv = The vegetation area density in kg/m 2 (Reg Guide 1.109, Table E-15).

Indian Point 2 Page 24 Revision 10

aDCM Part II - Calculational Methodologies For tritium, the concentration in vegetation is based on airborne concentration rather than deposition. Therefore, for Ri(V) is based on X/Q instead of D/Q:.

RiV (H-3) = K'K"[(UaL)fL +(UaS)fg](DFi)a (0.75)(0.5/H) (mrem/yr per f..lCilm3) (G-18)

Where:

K" = A constant of unit conversion, 1000 gm/kg H =. Absolute humidity of the atmosphere in gm/m 3 . This value may be considered as 8 gm/m 3 (NUREG 0133, pg 34) iii lieu of site specific information.

0.75 = The fraction of total feed that is water (NUREG 0133, pg 34).

0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water (NUREG 0133, pg 34).

DFia for each age/ group is given in Tables 2-3a through 2-3d (from Reg Guide 1.109 Tables E-11 through E-14).

Ri(I), Ri(V), and Ri(G) values are listed in Tables 2-10a-d, 2-11a-c, and 2-12.

Ri(V) Parameters:

Reg Guide 1.109 PARAMETER VALUE Source Table 1.0 for radioiodines R (dimensionless) E-15 0.2 for particulates (DFLi) a (mrem/pCi) Each radionuclide E-11 to E-14 UaL (kg/yr) - infant 0 E-5

- child 26 E-5

- teen 42 E-5

- adult 64 E-5 UaS (kg/yr) - infant 0 E-5

- child 520 E-5

- teen 630 E-5

- adult 520 E-5 fL (dimensionless) 1.0 E-15.

fg dimensionless) 0.76 E-15 tL seconds) 8.6E4(1 day) E-15 th seconds) 5.18E6 (60 days) E-15 Yv kg/m<!) 2.0 E-15 Total organ dose is the sum of all pathway doses, calculated separately for each age group and organ, from all applicable nuclides.

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aDCM Part II - Calculational Methodologies 2.8 Gas Storage Tank Activity Limit NUREG-0133 Section 5.6.1 provides the expression for tank activity in terms of Xe-133 equivalent, assuming no potential tank interconnections:

(500mrem)* 3.15£+7 seelyr 0133= = 29.761 Ci (lE6,uCii Ci)(294mrem - m 3 I,uCi - yr)(1.81E - 3 seel m 3 )

Where; 294 mrem-m 3/f.lCi-yr =the Xe-133 whole body dose factor from Reg Guide 1.109, table B-1 (K).

1.81 E-3 sec/m 3 = Design Basis Accident XlO from Indian Point 2 FSAR 2.8.1 Actual Limits An actual curie limit may be calculated by substituting the actual mixture Keft into the equation above. For example, the Kef! for the accident mix computed using Table 14.2-5 of the FSAR is 476 mrem-m3/f.lCi-Yr. Thus, the actual activity limit (for an expected mixture of radionuclides, not just Xe-133) is:

(500mrem)

• 3.15E + 7 seel yr 0133= = 18.300 Ci (lE6/lCiICi)(476mrem-m 3 1 /lCi- yr)(1.81E-3 seelm 3 )

Similar calculations could be performed with actual Keft and XlO data.

2.8.2 R-50 Setpoints As demonstrated above, the setpoints calculated from NUREG 0133 modeling assume Xe-133 equivalent and no tank interconnections (29,761 Ci of Xe-133 equivalent or 18,300 Ci for an expected accident mixture).

However, the tanks are, in fact, generally interconnected, requiring a more conservative approach. The unit 2 FSAR (14.2.3) has established a specific gas decay tank limit of 6000 Ci each. This value is based on the original RECS required 29,761 curies of Xe-133 equivalent, divided into 4 large and all 6 small gas decay tanks. Given the actual atmospheric volume of the tanks (525 fe for each large and 40 fe for each small), the total volume is approximately 4.5 tanks:

29,761

-'--- = 6000 Ci Xe - 133 Equivalent 4.5 Warn setpoints are established by procedure, usually with consideration for measured tank contents and anticipated release rate.

Indian Point 2 Page 26 Revision 10

aDCM Part II - Calculational Methodologies 2.8.3 Indirect Radiation Monitoring In the event R-50 becomes inoperable, but a depressurized sample can be taken, the quantity limits can still be verified.

Compliance with the appropriate quantity limit is assured if the following inequality holds:

[A1m < 14.7 (a)

(14.7 + P)V or

[AJeq < 14.7 (0133)

(14.7 + P)V Where:

[A1m - total measured depressurized sample concentration

(~Ci/cc)

[AJeq - Xe-133 equivalent measured depressurized sample concentration (~Ci/cc)

V - tank volume (cc)

P - tank pressure (psig) a - activity limit for selected mix (~Ci) 0133 - dose equivalent Xe-133 activity limit (~Ci) 2.8.4 Routine SetpointiSampling Conservatism In accidental releases of large magnitude (tank failure) it is assumed that the entire tank contents escapes through the rupture point. In some routine releases, the tank pressure decreases t6 a value around 1 atmosphere (0 psig) so that the tank is never fully voided. The setpoint conservatism vary by a factor, which accounts for incomplete tank emptying, equal to 1+(14.7/P).

Note that for lower tank pressures, the conservatism is higher. Procedures may account for this conservatism in establishing specific tank release setpoints.

Indian Point 2 Page 27 Revision 10

ODCM Part II - Calculational Methodologies TABLE 2-1

SUMMARY

OF GASEOUS RECS DOSE RATE RECS At or beyond the SITE BOUNDARY:

500 mrem/yr per site; noble gases, whole body.

3000 mrem/yr per site, noble gases, skin.

1500 mrem/yr per site; iodine-131, tritium, 8 day particulates; any organ.

DOSE RECS Air Dose at the SITE BOUNDARY is limited to:

. 5 mrad per quarter and 10 mrad per year for noble gases, gamma air dose 10 mrad per quarter and 20 mrad per year for noble gases, beta air dose Maximum Individual Dose to a Member of the Public at the nearest resident is limited to:

7.5 mrem per qtr and 15 mrem per yr for Iodine, H-3, & 8 day particulates to any organ REAL MEMBER OF THE PUBLIC 25 mrem/yr, all sources, whole body or any organ except thyroid.

75 mrem/yr, all sources, thyroid ..

PROJECTIONS Projections of airborne doses shall be computed at least every 31 days as follows:

Dose 1 Current Month Dose + Previous months' Dose . major I d J

[ Projection = +/- P anne number of months used [

evolutions The term for planned evolutions is routinely determined from previous similar evolutions, such as releases associated with plant shutdown.

If projected doses would exceed the limits in the RECS:

0.2 mrad gamma air dose, or 0.4 mrad beta air dose, or 0.3 mrem to any organ at the nearest residence, clean-up treatment systems are required to be operational.

Indian Point 2 Page 28 Revision 10

aDCM Part II - Calculational Methodologies Table 2-2a ADULT INHALATION DOS£ FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 Be-7 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 1. 28E-06 1.28E-06 1. 28E-06 1.2BE-06 1.2BE-06 1.2BE-06 1.28£-06 P-32 1.65E-04 9.64E-06 6.26E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.08E-OS Cr-51 O.OOE+OO O.OOE+OO 1.25E-08 7.44E-09 2.85£-09 1.80E-06 4.15£-07 Hn-54 O.OOE+OO 4.95£-06 7.87E-07 O.OOE+OO 1.23E-06 1.75£-04 9.67E-06 H'n-S6 0.00£+00 1.55£-10 2.29E-11 O.OOE+OO 1.63£-10 1.1BE-06 2.S3E-06 Fe.-:-S5 3.07E-06 2.12E-06 4.93£-07 O.OOE+OO O.OOE+OO 9.01E-06 7.54E-07 Fe-59 1. 47E-06 3.47E-06 1.32£-06 O.OOE+OO O.OOE+OO 1.27E-04 2.35E--05 Co-58 O.OOE+OO 1.9B£-07 2.59E-07 O.OOE+OO O.OOE+OO 1.16E-04 1.33E-OS Co-60 O.OOE+OO L 44E-06 1. 85E-06 O.OOE+OO O.OOE+OO 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1. B1E-06 O.OOE+OO O.OOE+OO 2.i3E-05 1.67E-06 Ni-65 1. 92E-10 2.62E-11 1.14E-11 O.OOE+OO O.OOE+OO 7.00E-07 1.54E-06 Cu-64 O.OOE+OO 1.83E-10 7.69E-11 O.OOE+OO 5.7BE-10 8.4BE-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 O.OOE+OO 8.62E-06 1.0BE-04 6.6B£-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 O.OOE+OO 5.27E-12 'l.15E-07 2.04E-09 Br-B3 O.OOE+OO O.OOE+OO 3.01E-OB O.OOE+OO O.OOE+OO O.OOE+OO 2.90E-OB Br-84 O.OOE+OO O.OOE+OO 3.91E-08 O.OOE+OO O.OOE+OO O.OOE+OO 2.05£-13 Br-B5 O.OOE+OO O.OOE+OO 1. 60E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-B6 O.OOE+OO 1.69E-05 7.37E-06 O.OOE+OO O.OOE+OO 0.00£+00 2.0B£-06 Rb-8B O.OOE+OO 4.B4E-OB 2.41£-08 O.OOE+OO 0.00£+00 0.00£+00 4.1B£-19 Rb-B9 O.OOE+OO 3.20E-08 2.12E-08 O.OOE+OO O.OOE+OO O.OOE+OO 1. 16E-2l Sr-B9 3.80E-05 O.OOE+OO 1.09E-06 O.OOE+OO O.OOE+OO 1. 7SE-04 4.37E-05 Sr-90 1.24E-02 O.OOE+OO 7.62E-04 O.OOE+OO 0.00£+00 1. 20E-03 9.02E-OS Sr-91 7.74E-09 O.OOE+OO 3.13E-10 O.OOE+OO O.OOE+OO 4.56E-06 2.39E-OS Sr-92 B.43E-10 O.OOE+OO 3.64E-11 O.OOE+OO O.OOE+OO 2.06E-06 5.3BE-06 Y-90 2.61E-07 O.OOE+OO 7.01E-09 O.OOE+OO O.OOE+OO 2.12E-05 6.32E-05 Y-91m 3.26E-11 O.OOE+OO 1.27E-12 O.OOE+OO O.OOE+OO 2.40E-07 1.66E-10 Y-91 5.7BE-05 O.OOE+OO 1.55E-06 O.OOE+OO 0.00£+00 2.13E-04 4.81E-05 Y-92 1.29E-09 O.OOE,+OO 3.77E-11 O.OOE+OO 0.00£+00 1.96£-06 9.19£-06 Y-93 1.1B£-08 O.OOE+OO 3.26£-10 O.OOE+OO 0.00£+00 6.06£-06 5.27£-05 Zr-95 1.34E-05 4.30£-06 2.91E-06 O.OOE+OO 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 O.OOE+OO 3.71£-09 9.84E-06 6.54£-05 Nb-95 1. 76£-06 9.77£-07 5.26E-07 O.OOE+OO 9.67£-07 6.31E-05 1.30E-05 Ho-99 O.OOE+OO 1.51E-OB 2.87E-09 O.OOE+OO 3.64E-08 1.14E-05 3.10E-05, Tc-99m 1.29£-13 3.64E-13 4.63£-12 O.OOE+OO 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52£-15 7.38E-14 O.OOE+O~ 1.35E-13 4.99E-OB 1.36E-21 Ru-103 1.9I'E-07 O.OOE+OO B.23E-08 O.OOE+OO 7.29E-07 6.31E-05 1. 3B£-05 Ru-105 9.88E-11 O.OOE+OO 3.B9E-11 O.OOE+OO 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64£-06 O.OOE+OO 1.09E-06 O.OOE+OO 1.57E-05 1. 17E-03 1.14£-04 Ag-110rn L 35E-06 1.25E-06 7.~3E-07 O.OOE+OO 2.46E-06 5.79E-04 3.7BE-05 Sb-122 0.00£+00 0.00£+00 0.00£+00 0.00£+00 O.OOE+OO 0.00£+00 0.00£+00 Sb-124 3.90£-06 7.36£-OB 1.55£-06 9.44E-09 0 .. 00£+00 3.10E-04 S.08E-05 Sb-12S 6.67E-06 7.44E-OB 1.58E-06 6.75E-09 O.OOE+OO 2.18E-04 1.26E-05 Indian Point 2 Page 29 Revision 10

aDCM Part II - Calculational Methodologies Table 2-2a ADULT INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDN£Y LUNG GILLI Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1. 55£-06 3.92E-05 8.83£-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20£-04 1.87E-05 Te-127 1. 75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.S8E-09 3.86E-OS 1.82£-05 6.95£-05 Te-131 1.39£-12 7.44£-13 4.49E-13 1.17E-12 5.46E-12 1. 74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 1-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 O.OOE+OO 9.61E-07 1-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 O.OOE+OO 7.85E-07 1-132 1.45E-07 4.07E-07 1.45E-07 1.43E-*05 6.48E-07 O.OOE+OO 5.08E-08 1-133 1. 08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 O.OOE+OO 1. 11E-06 1-134 8.05E-OS 2.16E-07 7.69E-08 3.73E-06 3.44E-07 O.OOE+OO 1.26E-10 1-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 O.OOE+OO 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 O.OOE+OO 3.59E-05 1. 22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 O.OOE+OO 1.07E-05 1. 50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 O.OOE+OO 2.78E-05 9.40E-06 1.05£-06 Cs-138 4. l4E-08 7.76E-08 4.05E-08 O.OOE+OO 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 O.OOE+OO 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 O.OOE+OO 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 O.OOE+OO 8.75E-15 2.42E-07 1. 45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 O.OOE+OO 2.86E-15 1.49E-07 1. 96E-26 La-l40 4.30E-08 2.17E-08 5.73E-09 O.OOE+OO O.OOE+OO 1.70E-05 5.73E-05 La-l42 8.54E-11 3.88E-11 9.65E-12 O.OOE+OO O.OOE+OO 7.91E-07 2.64E-07 Ce-141 2.49E-06 1. 69E-06 1.91E-07 O.OOE+OO 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-OB 1. 72E-OB 1.91E-09 O.OOE+OO 7.60E-09 9.97E-06 2.B3E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 O.OOE+OO 1.06E-04 9.72E-04 1.02E-04 Pr-l43 1. 17E-06 4.69E-07 5.80E-08 O.OOE+OO 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1. 91E-13 O.OOE+OO B.B1E-13 1. 27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 O.OOE+OO 4.45E-07 2.76E-05 2.16E-05 W-187 '1. 06E-09 8.B5E-IO 3.10E-10 O.OOE+OO O.OOE+OO 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 O.OOE+OO B.75E-09 4.70E-06 1.49E-05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 8.65E-08 8.39E-OB O.OOE+OO O.OOE+OO 4.62E-05 3.93E-06 Sr-85 4.00E-06 O.OOE+OO 9.70E-05 0.00£+00 O.OOE+OO 6.00E-05 7.60E-06 Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 2.78E-11 7.03E-12 2.56E-12 0.00£+00 8.18E-12 3.00E-07 3.02£-08 Cd-l09 O.OOE+OO 4.90E-05 1.60E-06 0.00£+00 4.70E-05 9.10E-05 8.20E-06 Sn-113 8.20E-06 2.70E-07 5.60E-07 1.70E-07 O.OOE+OO 1.20E-04 1.50E-06 Ba-133 9.50E-06 4.20E-07 2.50E-06 O.OOE+OO 2.10E-09 1.90E-04 1.00E-05 Te-134 3.84E-12 3.22E-12 1. 57E-12 3.44E-12 2.18E-11 4.34E-07 2.97E-11 Ce-139 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O. 'OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 2 Page 30 Revision 10

aDCM Part II - Calculational Methodologies Table 2-2b TEEN INHALATION DOSE FlI.CTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLl H-3 O.OOE+OO 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 Be-7 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 1. 72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.9SE-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.16E-05 Cr-51 O.OOE+OO O.OOE+OO 1.69E-08 9.37E-09 3.B4E-09 2.62E-06 3.75E-07 Nn-54 O.OOE+OO 6.39E-06 1. 05E-06 O.OOE+OO 1.59E-06 2.4BE-04 8.35E-06 Mn-56 O.OOE+OO 2.12E-10 3.15E-11 O.OOE+OO 2.24E-10 1.90E-06 7.1BE-06 Fe-S5 4.1BE-06 2.98E-06 6.93E-07 O.OOE+OO O.OOE+OO 1.55E-05 7.99E-07 Fe-59 1. 99E-06 4.62E-06 1. 79E-06 O.OOE+OO O.OOE+OO 1.91E-04 2.23E-05 Co-58 O.OOE+OO 2.59E-07 3.47E-07 O.OOE+OO O.OOE+OO 1. 68E-04 1. 19E-05 Co-60 O.OOE+OO 1. B9E-06 2.4BE-06 O.OOE+OO O.OOE+OO 1.09E-03 3.24E-OS Ni-63 7.25E-OS 5.43E-06 2.47E-06 O.OOE+OO O.OOE+OO 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 O.OOE+OO O.OOE+OO 1.17E-06 4.59E-06 Cu-64 O.OOE+OO 2.S4E-10 1.06E-10 O.OOE+OO B.01E-10 1. 39E-06 7.6BE-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 O.OOE+OO 1.0BE-05 1.55E-04 5.B3E-06 Zn-69 6.04E-12 1. 15E-11 8.07E-13 O.OOE+OO 7.53E-12 1.98E-07 3.56E-08 Br-B3 O.OOE+OO O.OOE+OO 4.30E-OB O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-B4 O.OOE+OO O.OOE+OO 5.41E-OB O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-B5 O.OOE+OO O.OOE+OO 2.29E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-B6 O.OOE+OO 2:3BE-05 1.0SE-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.21E-06 Rb-88 O.OOE+OO 6.82E-08 3.40E"':08 O.OOE+OO O.OOE+OO O.OOE+OO 3.65E-15 Rb-89 O.OOE+OO 4.40E-08 2.91E-08 O.OOE+OO O.OOE+OO O.OOE+OO 4.22E-17 Sr-89 5.43E-05 O.OOE+OO 1.56E-06 O.OOE+OO O.OOE+OO 3.02E-04 4.64E-05 Sr-90 1.35E-02 O.OOE+OO 8.35E-04 O.OOE+OO O.OOE+OO 2.06E-03 9.56E-05 Sr-91 1.10E-08 O.OOE+OO 4.39E-10 O.OOE+OO O.OOE+OO 7.59E-06 3.24E-05 Sr-92 1.19E-09 O.OOE+OO 5.0BE-11 O.OOE+OO O.OOE+OO 3.43E-06 1.49E-05 Y-:90 3.73E-07 O.OOE+OO 1.00E-08 O.OOE+OO O.OOE+OO 3.66E-05 6.99E-05 Y-91m 4.63E-11 O.OOE+OO 1. 77E-12 O.OOE+OO O.OOE+OO 4.00E-07 3.77E-09 Y-91 8.26E-05 O.OOE+OO 2.2lE-06 O.OOE+OO O.OOE+OO 3.67E-04 5.11E-05 Y-92 1. 84E-09 O.OOE+OO 5.36E-11 O.OOE+OO O.OOE+OO 3.35E-06 2.06E-05 Y-93 1.69E-08 O.OOE+OO 4.65E-10 O.OOE+OO O.OOE+OO 1.04E-05 7.24E-05 Zr-95 1. B2E-05 S.73E-06 3.94E-06 O.OOE+OO 8.42E-06 3.36E-04 1.86E-05 Zr-97 1. 72E-08 3.40E-09 1.57E-09 O.OOE+OO 5.15E-09 1.62E-05 7.88E-05 Nl::;-95 2.32E-06 1.29E-06 7.08E-07 O.OOE+OO 1.25E-06 9.39E-05 1.21E-05 l~o-99 O.OOE+OO 2.11E-08 4.03E-09 O.OOE+OO 5.l4E-08 1.92E-05 3.36E-05 Tc-99m 1. 73E-13 4.83E-13 6.24E-12 O.OOE+OO 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1. 03E-13 O.OOE+OO 1. 90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 O.OOE+OO 1.12E-07 O.OOE+OO 9.29E-07 9.79E-05 1.36E-05 Ru-105 1. 40E-10 O.OOE+OO 5.42E-11 O.OOE+OO 1.76E-10 2.272-06 1.13E-05 Ru-106 1.23E-05 O.OOE+OO 1.55E-06 O.OOE+OO 2.38E-05 2.01E-03 1.20E-04 F.g-110m 1. 73E-06 1.64E-06 9.99E-07 O.OOE+OO 3.13E-06 8.44E-04 3.41E-05 Sb-122 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 S.38E-06 9.92E-OB 2.10E-06 1.222-08 O.OOE+OO 4.81E-04 4.98£-05 Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 O.OOE+OO 3.42E-04 1.24E-05 Indian Point 2 Page 31 Revision 10

ODCM Part II - Calculational Methodologies Table 2-2b TEEN INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 6.10E-07 2.80E-07 8.34E-08 1. 75E-07 O.OOE+OO 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-l27 2.51E-10 1.14E-10 5.52E-11 1. 77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1. 74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.B7E-12 4.22E-12 2.20E-12 6.4BE-12 3.32E-ll 4.12E-07 2.02E-07 Te-131m 1.23E-OB 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-OB 3.63E-OB 2.74E-OB 3.07E-OB 2.44E-07 5.61E-05 5.79E-05 1-130 7.80E-07 2.24E-06 B.96E-07 1.B6E-04 3.44E-06 O.OOE+OO 1. 14E-06 1-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1. 05E-05 O.OOE+OO 8.11E-07 1-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 O.OOE+OO 1.59E-07 1-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 O.OOE+OO 1.29E-06 1-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 O.OOE+OO 2.55E-09 1-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 O.OOE+OO 8.69E-07 Cs-134 6.2BE-05 1.41E-04 6.B6E-05 O.OOE+OO 4.69E-05 1. 83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 O.OOE+OO 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.B9E-05 O.OOE+OO 3.80E-05 1.51E-05 1.06E-06 Cs-13B 5.B2E-OB 1.07E-07 5.58E-08 O.OOE+OO 8,28E-08 9.B4E-09 3.3BE-11 Ba-139 1.67E-10 1.lBE-13 4.B7E-12 O.OOE+OO 1. 11E-13 B.08E-07 B.06E-07 Ba-140 6.84E-06 8.3BE-09 4.40E-07 O.OOE+OO 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 O.OOE+OO 1.23E-14 4.11E-07 9.33E-14 i Ba-142 4.62E-12 4.63E-15 2.84E-13 O.OOE+OO 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-OB 2.95E-08 7.82E-09 O.OOE+OO O.OOE+OO 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 O.OOE+OO O.OOE+OO 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 O.OOE+OO 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 O.OOE+OO 1.0BE-OB 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.2BE-05 O.OOE+OO 1.51E-04 1.67E-03 1.0BE-04 Pr-143 1.67E-06 6.64E-07 B.28E-OB O.OOE+OO 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2. 72E-13 O.OOE+OO 1. 26E-12 2.19E-07 2.94E-14 Nd-147 9.B3E-07 1.07E-06 6.41E-OB O.OOE+OO 6.2BE-07 4.65E-05 2.2BE-05 W-1B7 1.50E-09 1.22E-09 4.29E-l0 O.OOE+OO O.OOE+OO 5.92E-06 2.21E-05 Np-239 4.23E-OB 3.99E-09 2.21E-09 O.OOE+OO 1.25E-08 B.11E-06 1.65E-05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 1.lBE-07 1.15E-07 O.OOE+OO O.OOE+OO 7.33E-05 3.93E-06 Sr-85 5.00E-06 O.OOE+OO 1.30E-06 O.OOE+OO O.OOE+OO 8.80E-05 6.90E-06 Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 3.93E-11 9.72E-12 3.55E-12 O.OOE+OO 1. 14E-ll 4.91E-07 2.71E-07 Cd-109 O.OOE+OO 1.00E-04 3.40E-06 O.OOE+OO 6.70E-05 1.60E-04 8.60E-06 Sn-113 1.50E-05 4.70E-07 9.70E-07 2.90E-07 O.OOE+OO 2.00E-04 1.50E-06 Ba-133 4.70E-05 8.00E-07 3.30E-06 O.OOE+OO 2.808-09 2.90E-04 9.70E-06 Te-134 5.31E-12 4.35E-12 3.64E-12 4.468-12 2.91E-11 6.75E-07 1.37E-09 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O. OOE+OO. O.OOE+OO O.OOE+OO Indian Point 2 Page 32 Revision 10

aDCM Part II - Calculational Methodologies T3.ble 2-2c CHILD INHALATION DOSE fACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY TEYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 Be-7 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.14E-05 Cr-51 O.OOE+OO O.OOE+OO 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 0.00£+00 1. 16E-05 2.57E-06 O.OOE+OO 2.71E-06 4.26E-04 6.19E-06 t1n-56 O.OOE+OO 4.48E-10 8.43E-11 O.OOE+OO 4.52E-10 3.55E-06 3.33E-05 Fe-55 1. 28E-05 6.80E-06 2.10E-06 O.OOE+OO O.OOE+OO 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 O.OOE+OO O.OOE+OO 3.43E-04 1.91E-05 Co-58 O.OOE+OO 4.79E-07 8.55E-07 O.OOE+OO O.OOE+OO 2.99£-04 9.29E-06 Co-60 O.OOE+OO 3.55E-06 6.12E-06 O.OOE+OO O.OOE+OO 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 O.OOE+OO O.OOE+OO 7.43E-05 1. 71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 O.OOE+OO O.OOE+OO 2.21E-06 2.27E-05 Cu-54 O.OOE+OO 5.39E-10 2.90E-10 O.OOE+OO 1.63E-09 2.59E-06 9.92£-06 Zn-65 1. 15E-05 3.06E-05 1.90E-05 0.00£+00 1.93E-05 2.69E-04 4.41E-06 Zn-69 1. 81E-ll 2.61E-ll 2.41E-12 O.OOE+OO 1.58E-ll 3.84E-07 2.75E-06 Br-83 O.OOE+OO O.OOE+OO 1.28E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 1.48E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 6.84E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 5.36E-05 3.09E-05 0.00£+00 0.00£+00 O.OOE+OO 2.16£-06 Rb-88 O.OOE+OO 1.52£-07 9.90£-08 O.OOE+OO O.OOE+OO O.OOE+OO 4.66E-09 Rb-89 O.OOE+OO 9.33E-08 7.83E-08 O.OOE+OO O.OOE+OO O.OOE+OO 5.llE-10 Sr-89 1.62E-04 O.OOE+OO 4.66E-06 O.OOE+OO O.OOE+OO 5.83E-04 4.52E-05 Sr-90 2.73E-02 O.OOE+OO 1.74E-03 O.OOE+OO O.OOE+OO 3.99E-03 9.28E-05 Sr-91 3.28E-08 O.OOE+OO 1.24E-09 O.OOE+OO O.OOE+OO 1.44E-05 4.70E-05 Sr-92 3.54E-09 O.OOE+OO 1. 42E-10 O.OOE+OO O.OOE+OO 6.49E-06 6.55E-05 Y-90 1. llE-06 O.OOE+OO 2.99E-08 O.OOE+OO O.OOE+OO 7.07E-05 7.24E-05 Y-91m 1.37£-10 O.OOE+OO 4.98E-12 O.OOE+OO O.OOE+OO 7.60E-07 4.64E-07 Y-91 2.47E-04 O.OOE+OO 6.59E-06 O.OOE+OO O.OOE+OO 7.10E-04 4.97E-05 Y-92 5.50E-09 O.OOE+OO 1.57E-10 O.OOE+OO O.OOE+OO 6.46E-06 6.46E-05 Y-93 5.04E-08 O.OOE+OO 1. 38E-09 O.OOE+OO O.OOE+OO 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 O.OOE+OO 1.61E-05 6.03E-04 1.65£-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 O.OOE+OO 1. 05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1. 77E-06 O.OOE+OO 2.33E-06 1.66E-04 1.00E-05 Mo-99 O.OOE+OO 4.66E-08 1. 15E-08 O.OOE+OO 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 O.OOE+OO 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2. 91E-13 O.OOE+OO 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 O.OOE+OO 2.90E-07 O.OOE+OO 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-I0 O.OOE+OO 1.50E-I0 O.OOE+OO 3.63E-I0 4.30E-06 2.69E-05 Ru-106 3.68E-05 O.OOE+OO 4.57E-06 O.OOE+OO 4.97E-05 3.87£-03 1. 16E-04 Ag-llOm 4.56E-06 3.08E-06 2.47E-06 O.OOE+OO 5.74E-06 1.48E-03 2. HE-OS Sb-122 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 Sb-124 1.5SE-05 2.00E-07 5.41E-06 3.4l£-08 O.OOE+OO 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46£-08 O.OOE+OO 6.27E-04 1.09E-05 Indian Point 2 Page 33 Revision 10

aDCM Part II - Calculational Methodologies Table 2-2c CHILD INHALATION DOSE FACTORS (rnrern per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te'-125rn 1. 82E-06 6.29E-07 2.47E-07 5.20E-07 O.OOE+OO 1.29E-04 9.13E-06 Te-127rn 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-OS 4.00E-04 1.93E-OS Te-127 7.49E-10 2.57E-10 1.6SE-10 5.30E-I0 1.91E-09 2.71E-06 1.S2E-05 Te-129rn S.19E-06 1.8SE-06 8.22E-07 1.71E-06 1.36E-OS 4.76E-04 4.91E-OS Te-129 2.64E-11 9.4SE-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131rn 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.0SE-07 S.S6S-0S 8.32E-OS Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.S9E-11 5.S5E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 1-130 2.21E-06 4.43E-06 2.2SE-06 4.99E-04 6.61E-06 O.OOE+OO 1. 38E-06 1-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 O.OOE+OO 7.68E-07 1-132 5.72E-07 1.10E-06 5.07E-07 5.23E-OS 1.69E-06 O.OOE+OO 8.65E-07 1-133 4.4SE-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 O.OOE+OO 1. 48E-06 1-134 3.17E-07 S.84E-07 2.69E-07 1. 37E-OS 8.92E-07 O.OOE+OO 2.S8E-07 I-US 1. 33E-06 2.36E-06 1. 12E-06 2.14E-04 3.62E-06 O.OOE+OO 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-OS O.OOE+OO 8.93E-05 3.27E-OS 1.04E-06 C8-136 1.76E-05 4.62E-OS 3.14E-05 O.OOE+OO 2.58E-OS 3.93E-O'6 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 O.OOE+OO 7.63E-OS 2.81E-OS 9.78E-07 C8-13S 1.71E-07 2.27E-07 1.50E-07 O.OOE+OO 1.6SE-07 1.S4E-OS 7.29E-OS Ba-139 4.98E-10 2.66E-13 1.45E-11 O.OOE+OO 2.33E-13 1.56E-06 1. 56E-05 Ba-140 2.00E-05 1. 75E-OS 1.17E-06 O.OOE+OO 5.71E-09 4.71E-04 2.7SE-05 Ba-141 5.29E-11 2.9SE-14 1.72E-12 O.OOE+OO 2.S6E-14 7.89E-07 7.44E-OS

( Ba-142 1.3SE-11 9.73E-1S 7.54E-13 O.OOE+OO 7.87E-15 4.44E-07 7.4lE-I0 La-140 1. 74E-07 6.0SE-08 2.04E-08 O.OOE+OO O.OOE+OO 4.94E-05 6.10E-05 La-142 3.S0E-10 1. 11E-10 3.49E-11 O.OOE+OO O.OOE+OO 2.3SE-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 O.OOE+OO 2'.31E-06 1. 47E-04 1.S3E-05 Ce-143 9.89E-08 S.37E-OS 7.77E-09 O.OOE+OO 2.26E-08 3.12E-05 3.44E-05 Ce-144 1. 83E-03 S.72E-04 9.77E-05 O.OOE+OO 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1. 50E-06 2.47E-07 O.OOE+OO 8.11E-07 1. 17E-04 2.63E-OS Pr-144 1. 61E-11 4.99E-12 8.10E-13 O.OOE+OO 2.64E-12 4.23E-07 S.32E-08 Nd-147 2.92E-06 2.36E-06 1.S4E-07 O.OOE+OO 1.30E-06 8.87E-OS 2.22E-05 W-187 4.4lE-09 2.61E-09 1.17E-09 O.OOE+OO O.OOE+OO 1.11E-05 2.46E-05 Np-239 1. 26E-07 9.04E-09 6.3SE-09 O.OOE+OO 2.63E-08 1.57E-05 1.73E-05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 2.44E-07 2.88E-07 O.OOE+OO O.OOE+OO 1.37E-04 3.5SE-06 Sr-S5 1.20E-05 O.OOE+OO 3.20E-06 O.OOE+OO O.OOE+OO 1.50E-04 5.50E-06 Y-SS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 1.16E-10 2.08E-11 9.73E-12 O.OOE+OO 2.31E-11 9.24E-07 7.51E-06 Cd-109 O.OOE+OO 1.90E-04 S.00E-06 O.OOE+OO 1.70E-04 3.00£-04 S.10E-06 Sn-113 3.20E-05 8.90E-07 2.30E-06 7.10S-07 O.OOE+OO 3.60£-04 1.30£-06 Ba-133 1.10E-04 1.10E-06 1.00E-05 O.OOE+OO 5.40£-09 5.20£-04 8.30E-06 Te-134 1.53E-11 8.S1E-12 9.40E-12 1.24E-11 5.71E-l1 1.23E-06 4.87E-07 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 2 Page 34 Revision 10

aDCM Part II - Calculational Methodologies Table 2-2d INFANT INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 Be-7 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 7.54E-06 7.S4E-06 7.S4E-06 7.S4E-06 7.S4E-06 7.S4E-06 7.54E-06 P-32 1.4SE-03 8.03E-OS 5.S3E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.lSE-OS Cr-51 O.OOE+OO O.OOE+OO 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.S5E-07 Mn-S4 O.OOE+OO 1.81E-OS 3.56E-06 O.OOE+OO 3.S6E-06 7.14E-04 S.04E-06 Mn-S6 O.OOE+OO 1.10E-09 1.S8E-10 O.OOE+OO 7.86E-10 8.9SE-06 5.12E-05 Fe-55 1. 41E-05 8.39E-06 2.38E-06 O.OOE+OO O.OOE+OO 6.21E-05 7.82E-07 Fe-59 9.69E-06 1. 68E-05 6.77E-06 O.OOE+OO O.OOE+OO 7.25E-04 1.77E-05 Co-58 O.OOE+OO 8;71E-07 1.30E-06. O.OOE+OO O.OOE+OO 5.5SE-04 7.95E-06 Co-60 O.OOE+OO 5.73E-06 8.41E-06 O.OOE+OO O.OOE+OO 3.22E-03 2.28£-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 O.OOE+OO O.OOE+OO 1.49E-04 1. 73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 O.OOE+OO O.OOE+OO 5.80E-06 3.58£-05 Cu-64 O.OOE+OO 1.34E-09 5.53E-10 O.OOE+OO 2.84E-09 6.64E-06 1.07E-05 Zn-6S 1.38E-05 4.47E-OS 2.22E-05 O.OOE+OO 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.8SE-11 6.91E-11 S.13E-12 O.OOE+OO 2.87E-11 1.05E-06 9.44E-06 Br-83 O.OOE+OO O.OOE+OO 2.72E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 2.86E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-8S O.OOE+OO O.OOE+OO 1.46E-08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1. 36E-04 6.30E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.17E-06 Rb-88 O.OOE+OO 3.98E-07 2.0SE-07 O.OOE+OO O.OOE+OO O.OOE+OO 2.42E-07 Rb-89 O.OOE+OO 2.29E-07 1. 47E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.87E-08 Sr-89 2.84E-04 O.OOE+OO 8.1S£-06 O.OOE+OO O.OOE+OO 1.45E-03 4.57E-05.

Sr-90 2.92E-02 O.OOE+OO 1.8SE-03 O.OOE+OO O.OOE+OO 8.03E-03 9.36E-05 Sr-91 6.83E-08 O.OOE+OO 2.47E-'-09 O.OOE+OO O.OOE+OO 3.76E-OS 5.24E-05 Sr-92 7.50E-09 O.OOE+OO 2.79E-I0 O.OOE+OO O.OOE+OO 1. 70£-OS 1.00E-04 Y-90 2.35E-06 O.OOE+OO 6.30£-08 O.OOE+OO O.OOE+OO 1. 92E-04 7.43E-05 Y-91m 2.91E-I0 O.OOE+OO 9.90E-12 O.OOE+OO O.OOE+OO 1.99E-06 1. 68E-06

','-91 4.20E-04 O.OOE+OO 1.12E-OS O.OOc+OO O.OOE+OO 1. 75E-03 S.02E-OS Y-92 1.17£-08 O.OOE+OO 3.29E-10 O.OOE+OO O.OOE+OO 1.75E-05 9.04E-OS Y-93 1. 07E-07 O.OOE+OO 2.91E-09 O.OOE+OO O.OOE+OO 5.46E-05 1.19E-04 Zr-95 8.24E-OS 1. 99E-05 1.45E':'05 O.OOE+OO 2.22E-05 1.25E-03 1.5SE-OS Zr-97 1.07E-07 1. 83E-08 8.36E-09 O.OOE+OO 1.8SE-08 7.88E-OS 1.00E-04 Nb-9S 1.12E-OS 4.59E-06 2.70E-06 O.OOE+OO 3.37E-06 3.42E-04 9.05E-06 Mo-99 O.OOE+OO 1.18E-07 2.31E-08 O.OOE+OO 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E-13 2.06E-12 2.66E-11 O.OOE+OO 2.22E-11 5.79E-07 1. 45E-06 Tc-101 4.6SE-14 S.88E-14 5.80E-13 O.OOE+OO 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 O.OOE+OO 4.85E-07 O.OOE+OO 3.03E-06 3.94E-04 1.1SE-05 Ru-l05 8.74E-10 O.OOE+OO 2.93E-10 O.OOE+OO 6.42E-10 1.12E-05 3.46E-05 Ru-l06 6.20E-05 O.OOE+OO 7.77E-06 O.OOE+OO 7.61E-05 8.26£-03 1.17E-04 Ag-llOm 7.13c-06 S.16£-06 3.57E-06 O.OOE+OO 7.80E-06 2.62£-03 2.36E-OS Sb-122 0.00£+00 0.00£+00 O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO Sb-124 2.71£-05 3.97E-07 8.56E-06 7.18E-08 O.OOE+OO 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 O.OOE+OO 1.17E-03 1.05E-OS Indian Point 2 Page 35 Revision 10

aDCM Part II - Calculational Methodologies Table 2-2d INFANT INHALATION DOSE FACTORS (mrem per pCi inhaled)

Isotope BON£ LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 3.40E-06 1. 42£-06 4.70E-07 1.16E-06 O.OOE+OO 3.19E-04 9.22E-06 Te-127m 1. 19E-05 4.93£-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-05 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63£-11 2.48£-11 1. 34E-11 4.82E-11 1.25E-10 2.14£-06 1.8SE-05 Te-131m 7.62£-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 S.51E-05 Te-131 1. 24E-11 5.87E-12 3.57E-12 1. 13E-11 2.85E-11 1. 47E-06 5.S7E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1. 99E-07 7.39£-07 2.43E-04 3.15E-05 1-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 O.OOE+OO 1.42E-06 1-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 O.OOE+OO 7.56E-07 1-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 O.OOE+OO 1.36E-06 1-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 O.OOE+OO 1.54E-06 1-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1. 49E-06 O.OOE+OO 9.21E-07 I-US 2.76E-06 5.43E-06 1. 98E-06 4.97E-04 6.05E-06 O.OOE+OO 1. 31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 O.OOE+OO 1. 36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 O.OOE+OO 4.03E-05 8.40E-06 1.02£-06 Cs-137 3.92£-04 4.37E-04 3.25£-05 0.00£+00 1. 23£-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.5SE-07 2.84£-07 0.00£+00 2.93E-07 4.67E-OS 6.26E-07 Ba-139 1.06£-09 7.03£-13 3.07£-11 0.00£+00 4.23£-13 4.25£-06 3.64£-05 Ba-140 4.00£-05 4.00E-08 2.07£-06 O.OOE+OO 9.59£-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-11 3.55E-12 O.OOE+OO 4.64£-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40£-12 O.OOE+OO 1. 36E-14 1.11E-06 4.95E-07 La-l40 3.61E-07 1.43£-07 3.68E-08 0.00£+00 O.OOE+OO 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-:10 6.46E-11 O.OOE+OO O.OOE+OO 5.87E-06 4.25E-05 Ce-141 1. 9SE-05 1. 19E-05 1. 42E-06 O.OOE+OO 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.5SE-08 O.OOE+OO 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 O.OOE+OO 3.S4E-04 7.03E-03 1. 06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 O.OOE+OO 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1. 72E-12 O.OOE+OO 4.80£-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 O.OOE+OO 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 O.OOE+OO O.OOE+OO 2.83£-05 2.54E-05 Np-239 2.65E-07 2.37E-OS 1.34E-08 O.OOE+OO 4.73E-OS 4.25£-05 1.7SE-05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O:OOE+OO O.OOE+OO Co-57 O.OOE+OO 4.65E-07 4.5SE-07 0.00£+00 O.OOE+OO 2.71E-04 3.47E-06 Sr-S5 2.70E-05 O.OOE+OO 5.40E-06 O.OOE+OO O.OOE+OO 3.00E-04 4.80E-06 Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 Nb-97 2.44E-10 5.21E-11 1.8SE-11 O.OOE+OO 4.07E-11 2.37E-06 1. 92E-05 Cd-l09 O.OOE+OO 2.60E-04 1.00E-05 O.OOE+OO 2.00E-04 6.20E-04 S.00E-06 Sn-113 6.00E-05 1.60E-06 3.60E-06 1.30E-06 O.OOE+OO 7.80E-04 1.20E-06 Ba-l33 1.90E-04 1.70E-06 1.30E-05 0.00£+00 8.90£-09 9.10£-04 7.70£-06 Te-134 3.18E-11 2.04E-11 1. 68E-11 2.91E-11 9.59E-11 2.93E-06 2.53E-06 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 Indian Point 2 Page 36 Revision 10

aDCM Part II - Calculational Methodologies Table 2-2e 2

Total Body & Skin Ground Plane Dose Factors (mrem/hr per pCi/m )

with Isotope half-life and Stable Element Tranfer Data (Fm, cow)

Ground Plane Dose Factors Isotope Halflife unit Fm TotBody(DFg) Skin(DFs)

H-3 12.350 Y 1.00E-02 O.OOE+OO 0.00£+00 Be-7 53.300 o 1.00E-04 O.OOE+OO O.OOE+OO Na-24 15.000 H 4.00E-02 2.50E-08 2.90E-08 P-32 14.290 o 2.50E-02 O.OOE+OO O.OOE+OO Cr-5l 27.704 o 2.20E-03 2.20£-10 2.60E-10 Mn-54 312.500 o 2.50E-04 5.80E-09 6.80E-09 Mn-56 2.578 H 2.50E-04 1.10E-OS 1. 30E-08 Fe-55 2.700 Y 1. 20E-03 0.00£+00 O.OOE+OO Fe-59 44.529 o 1. 20E-03 S.00E-09 9.40E-09 Co-58 70.800 o 1. 00E-03 7.00E-09 8.20E-09 Co-60 5.271 Y 1. 00E-03 1.70E-08 2.00£-08 Ni-63 96.000 'I 6.70E-03 O.OOE+OO O.OOE+OO Ni-65 2.520 H 6.70E-03 3.70E-09 4.30£-09 Cu-64 12.701 H 1.40E-02 1.50E-09 1.70£-09 Zn-65 243.900 o 3.90E-02 4.00E-09 4.60E-09 Zn-69 0.950 H 3.90E-02 O.OOE+OO O.OOE+OO Br-83 2.390 H 5.00E-02 6.40E-11 9.30E-11 Br-84 0.530 H 5.00E-02 1.20E-08 1.40E-08 Br-85 0.050 H 5.00E-02 O.OOE+OO O.OOE+OO Rb-86 18.660 o 3.00E-02 6.30E-10 7.20E-10 Rb-88 0.297 H 3.00E-02 3.50E-09 4.00E-09 Rb-89 0.253 H 3.00E-02 1. 50E-OS 1. 80E-08 Sr-89 50.500 o 8.00E-04 5.60E-13 6.50E-13 Sr-90 29.120 'I 8.00E-04 O.OOE+OO O.OOE+OO Sr-91 9.500 H 8.00E-04 7.10E-09 8.30E-09 Sr-92 2.710 H 8.00E-04 9.00E-09 1.00E-08

'I-90 2.667 o 1. 00E-05 2.20£-12 2.60E-12 Y-91m 0.829 H 1. 00E-05 3.80E-09 4.40E-09 Y-91 58.510 o 1.00E-05 2.40E-11 2.70E-11 Y-92 3.540 H 1. 00E-05 1.60£-09 1. 90E-09 Y-93 10.100 H 1. 00E-05 5.70£-10 7.80E-10 Zr-95 63.9S0 o 5.00E-06 5.00E-09 5.80E-09 Zr-97 16.900 H 5.00E-06 5.50£-09 6.40£-09 Nb-95 35.150 o 2.50E-03 5.10E-09 6.00£-09 Mo-99 2.750 o 7.50E-03 1.90E-09 2.20£-09 Tc-99m 6.020 H 2.50E-02 9.60£-10 1.10E-09 Tc-101 0.237 H 2.50E-02 2.70£-09 3.00E-09 Ru-103 39.280 o 1. 00E-06 3.60E-09 4.20£-09 Ru-105 4.440 H 1.00E-06 4.50E-09 5.10E-09 Ru-106 368.200 o 1. 00E-06 1.50E-09 1.80E-09

].l.g-11Om 249.900 D 5.00E-02 1.80E-08 2.10E-08 Sb-122 2.700 o 1. 50E-03 O.OOE+OO O.OOE+OO Sb-124 60.200 o 1.50E-03 1.30E-08 1.50E-08 Sb-125 2.770 'I 1. 50E-03 3.10E-09 3.50E-09 Indian Point 2 Page 37 Revision 10

ODCM Part II - Calculational Methodologies Table 2-2e 2

Total Body & Skin Ground Plane Dose Factors (mrem/hr per pCi/m )

with Isotope half-life and Stable Element Tranfer Data (Fm, cow)

Ground Plane Dose Factors Isotope Halflife unit Fm TotBody(DFg) Skin (DFs)

Te-125m 58;000 D 1.00E-03 3.50E-11 4.80£-11 Te-127m 109.000 D 1.00E-03 1.10E-12 1.30E-12 Te-127 9.350 H 1.00E-03 1.00E-11 1.10E-11 Te-129m 33.600 D 1.00E-03 7.70E-10 9.00E-I0 Te-129 1.160 H 1.00E-03 7.10E-10 8.40E-10 Te-131m 30.000 H 1.00E-03 8.40E-09 9.90E-09 Te-131 0.417 H 1. 00E-03 2.20E-09 2.60E-06 Te-132 3.258 D 1.00E-03 1.70E-09 2.00E-09 1-130 12.360 H 6.00E-03 1.40£-08 1. 70E-08 1-131 8.040 D 6.00E-03 2.80E-09 3.40E-09 1-132 2.300 H 6.00E-03 1.70E-08 2.00E-08 1-133 20.800 H 6.00E-03 3.70E-09 4.50E-09 1-134 0.877 H 6.00E-03 1. 60E-08 1.90E-08 1-135 6.610 H 6.00E-03 1.20E-08 1. 40E-08 Cs-134 2.062 Y 1. 20E-02 1. 20E-08 1.40E-08 Cs-136 13.100 D 1. 20E-02 1. 50E-08 1.70E-08 Cs-137 30.000 Y 1.20E-02 4.20E-09 4.90E-09 Cs-138 0.537 H 1.20E-02 2.10E-08 2.40E-08 Ba-139 1.378 H 4.00E-04 2.40E-09 2.70E-09 Ba-140 12.740 D 4.00E-04 2.10E-09 2.40E-09 Ba-141 0.304 H 4.00E-04 4.30E-09 4.90E-09 Ba-142 0.177 H 4.00E-04 7.90E-09 9.00E-09 La-140 1. 678 D 5.00E-06 1. 50E-08 1.70E-08 La-142 1. 542 H 5.00E-06 1.50E-08 1.80E-08 Ce-141 32.501 D 1.00E-04 5.50E-I0 6.20E-I0 Ce-143 33.000 H 1.00E-04 2.20E-09 2.50E-09 Ce-144 284.300 D 1. 00E-04 3.20E-I0 3.70E-10 Pr-143 13.560 D 5.00E-06 O.OOE+OO O.OOE+OO Pr-144 0.288 H 5.00E-06 2.00E-I0 2.3.0E-10 Nd-147 10.980 D 5.00E-06 1. 00E-09 1. 20E-09 W-187 23.900 H 5.00E-04 3.10E-09 3.60E-09 Np-239 2.360 D 5.00E-06 9.50E-I0 1.10E-09 K-40 1. 28E+09 Y 1.00E-02 O.OOE+OO O.OOE+OO Co-57 270.900 D 1.00E-03 9.10E-I0 1. 00E-09 Sr-85 64.840 D 8.00E-04 0.00£+00 O.OOE+OO Y-88 106.640 D 1. 00E-05 O.OOE+OO O.OOE+OO Nb-94 2.03E+04 Y 2.50E-03 O.OOE+OO O.OOE+OO Nb-97 1. 202 H 2.50E-03 4.60E-09 5.40E-09 Cd-109 1.271 Y 1. 20E-04 0.00£+00 O.OOE+OO So-113 115.100 D 2.50E-03 O.OOE+OO O.OOE+OO Sa-133 10.740 y 4.00E-04 0.00£+00 0.00£+00 Te-134 0.697 H 1.00E-03 1. 00E-09 1.20E-09 Ce-139 137.660 D 1.00E-04 0.00£+00 O.OOE+OO Hg-203 46.600 D 3.80£-02 O.OOE+OO O.OOE+OO Indian Point 2 Page 38 Revision 10 .

aDCM Part II - Calculational Methodologies Table 2-3a ADULT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 1.05E-07 1.05E-07 1.052:-07 1.05E-07 1.05E-07 1.05E-07 Be-7 2.77E-09 6.26E-09 3.10E-09 O.OOS+OO 6.58E-09 O.OOE+OO 1.08E-06 Na-24 1. 70E-06 1.70E-06 1. 70E-06 1. 702:-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.17E-05 Cr-51 O.OOE+OO O.OOE+OO 2.662:-09 1. 59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 O.OOE+OO 4.57E-06 S.72E-07 O.OOE+OO 1. 36E-06 O.OOE+OO 1.40E-05 Mn-56 0.002:+00 1.15E-07 2.04£-08 O.OOE+OO 1.46E-07 O.OOE+OO 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 O.OOE+OO O.OOE+OO 1~06E-06 1.09E-06 Fe-59 4.34£-06 1.02E-05 3.91E-06 O.OOE+OO O.OOE+OO 2.85E-06 3.40E-05 Co-58 O.OOE+OO 7.45E-07 1.67E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.51E-05 Co-60 O.OOE+OO 2.14E-06 4.72E-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.B8£-06 Ni-65 5.28E-07 6.B6E-OB 3.13E-08 0.00£+00 0.00£+00 O.OOE+OO 1.74E-06 Cu-64 O.OOE+OO 8.33E-OB 3.91E-OS O.OOE+OO 2.10E-07 O.OOE+OO 7.10E-06 Zn-65 4.B4E-06 1.54E-05 6.96E-06 O.OOE+OO 1.03E-05 0.00£+00 9.70£-06 Zn-69 1.03E-08 1.97E-08 1. 37E-09 O.OOE+OO 1.28E-OB O.OOE+OO 2.96E-09 Br-83 O.OOE+OO O.OOE+OO 4.02E-08 0.00£+00 0.00£+00 O.OOE+OO 5.79E-OB Br-B4 0.00£+00 O.OOE+OO 5.21E-08 O.OOE+OO O.OOE+OO O.OOE+OO 4.09E-13 Br-B5 O.OOE+OO O.OOE+OO 2.14E-09 O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 Rb-S6 O.OOE+OO 2.llE-05 9.83£-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.16E-06 Rb-B8 O.OOE+OO 6.05E-OB 3.21E-OB 0.00£+00 O.OOE+OO O.OOE+OO B.36E-19 Rb-S9 O.OOE+OO 4.01E-08 .2 . 82E-08 0.00£+00 O.OOE+OO 0.00£+00 2.33E-21 Sr-89 3.08£-04 O.OOE+OO 8.84£-06 O.OO£tOO O.OOE+OO 0.00£+00 4.94E-05 Sr-90 7.58E-03 0.00£+00 1.86E-0,3 O.O'OE+OO O.OOE+OO 0.00£+00 2.19£-04 Sr-91 5.67E-06 O.OOE+OO 2.29E-07 O.OOE+OO 0.00£+00 O.OOE+OO 2.70£-05 Sr-92 2.15E-06 O.OOE+OO 9.30E-OS O.OOE+OO O.OOE+OO O.OOE+OO 4.26E-05 Y-90 9.62E-09 O.OOE+OO 2.5SE-10 0.00£+00 O.OOE+OO O.OOE+OO 1.02£-04 Y-91m 9.09E-ll O.OOE+OO 3.52E-12 O.OOE+OO O.OOE+OO 0.00£+00 2.67E-I0 Y-91 1.41E-07 O.OOE+OO 3.77E-09 O.OOE+OO O.OOE+OO 0.00£+00 7.76E-05 Y-92 8.45E-I0 O.OOE+OO 2.47E-ll O.OOE+OO O.OOE+OO 0.00£+00 1.48£-05 Y-93 2.68E-09 O.OOE+OO 7.40E-ll O.OOE+OO 0.00£+00 O.OOE+OO 8.50E-05 Zr-95' 3.04E-08 9.75E-09 6.60E-09 O.OOE+OO 1. 53E-08 O.OOE+OO 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-I0 O.OOE+OO 5.12E-10 O.OOE+OO 1. 05E-04 Nb-95 6.22£-09 3.46£-09 1.86E-09 O.OOE+OO 3.42E-09 O.OOE+OO 2.10E-05 Mo-99 O.OOE+OO 4.31E-06 8.20E-07 O.OOE+OO 9.76E-06 O.OOE+OO 9.99E-06 Tc-99m 2.47£-10 6.98E-I0 8.S9E-09 O.OOE+OO 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-I0 3.66E-I0 3.59E-09 O.OOE+OO 6.59E-09 1. B7E-10 1.10E-21 Ru-103 l.85E-07 O.OOE+OO 7.97E-OS O.OOE+OO 7.06E-07 0.00£+00 2.16E-05 Ru-105 1.54E-08 O.OOE+OO 6.08E-09 O.OOE+OO 1.99E-07 0.00£+00 9.42E-06 Ru-l06 2.75E-06 O.OOE+OO 3.48E-07 O.OOE+OO 5.31£-06 O.OOE+OO 1.7B£-04 Ag-l10m 1.60£-07 1. 48E-07 8.79E-08 O.OOE+OO 2.91E-07 O.OOE+OO 6.04E-05 Sb-122 2.00E-07 4.60£-09 6.90E-08 3.10E-09 0.00£+00 1.20E-07 7.60£-05 Sb-124 2.80E-06 5.30E-08 1.l0E-06 6.80E-09 O.OOE+OO 2.18E-06 7.95E-05 Sb-125 1.79E-06 2.00£-OB 4.26E-07 1.82£-09 0.00£+00 1.38E-06 1.97E-05 Indian Point 2 Page 39 Revision 10

ODCM Part II - Calculational Methodologies Table 2-3a

.ZI.DULT ING£STION DOSE: FACTORS (mrem per pCi ingested)

Isotope BONE LIV£R TOT BODY THYROID KIDN£Y LUNG GILLI Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06£-07 1.09E-05 0.00£+00 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75£-05 O.OOE+OO 2.27E-05 Te-l27 1.10E-07 3 .. 95E-08 2.38E-08 8.15£-08 4.48E-07 O.OOE+OO 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95£-06 4.80E-05 O.OOE-'-OO 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 O.OOE+OO 2.37E-08 Te-l31m 1. 73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 O.OOE+OO 8.40E-05 Te-l31 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0.00£+00 2.79£-09 Te-l32 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1. 57E-05 0.00£+00 7.71£-05 1-130 7.56E-07 2.23E-06 8.80E-07 1. 89E-04 3.48E-06 0.00£+00 1. 92E-06 I-l31 4.16£-06 5.95E-06 3.41£-06 1. 95£-03 1.02E-05 O.OOE+OO 1.57£-06 1-l32 2.03E-07 5.43E-07 1. 90E-07 1.90E-05 8.65£-07 0.00£+00 1.02E-07 1-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31£-06 O.OOE+OO 2.22E-06 1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58£-07 O.OOE+OO 2.51E-10 I-l35 4.43E-07 1.16E-06 4.28£-07 7.65E-05 1.86E-06 O.OOE+OO 1.31£-06 C5-l34 6.22E-05 1.48E-04 1.21£-04 0.00£+00 4.79E-05 1.59£-05 2.59E-06 Cs-l36 6.51£-06 2.57£-05 1.85£-05 O.OOE+OO 1.43E-05 1. 96E-06 2.92£-06 Cs-l37 7.97E-05 1.09E-04 7. l4E-05 O.OOE+OO 3.70£-05 1.23E-05 2.llE-06 Cs-138 5.52E-08 1.09£-07 5.40£-08 O.OOE+OO 8.01£-08 7.91E-09 4.65£-l3 Ba-139 9.70£-08 6. 91£-ll 2.84£-09 0.00£+00 6.46E-ll 3.92£-ll 1.72£-07 Ba:-140 2.03£-05 2.55£-08 1.33E-06 O.OOE+OO 8.67E-09 1.46£-08 4.18E-05 Ba-141 4.71E-08 3.56£-ll 1.59E-09 0.00£+00 3.31E-11 2.02E-11 2.22E-17 13a-142 2.13E-08 2.19E-ll 1.34E-09 O.OOE+OO 1.85E-ll 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33£-10 0.00£+00 0.00£+00 0.00£+00 9.25E-05 La-142 1.28£-10 5.82£-ll 1.45E-11 O.OOE+OO O.OOE+OO O.OOE+OO 4.25E-07 Ce-141 9.36E-09 6.33£-09 7.18E-I0 0.00£+00 2.94E-09 O.OOE+OO 2.42E-05 Ce-143 1. 65£-09 1.22E-06 1.35E-I0 0.00£+00 5.37E-10 O.OOE+OO 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62£-08 O.OOE+OO 1.21E-07 O.OOE+OO 1.65£-04 Pr-l43 9.20E-09 3.69E-09 4.56E-I0 O.OOE+OO 2.13E-09 O.OOE+OO 4.03£-05 Pr-144 3.01E-11 1. 25E-ll 1.53E-12 O.OOE+OO 7.05E-12 O.OOE+OO 4.33E-18 Nd-147 6.29E-09 7.27£-09 4.35E-10 O.OOE+OO 4.25E-09 0.00£+00 3.49E-05 W-187 1. 03E-07 8.61E-08 3.01£-08 O.OOE+OO 0.00£+00 O.OOE+OO 2.82£-05 Np-239 1.19E-09 1.17E-10 6.45E-11 O.OOE+OO 3.65E-10 O.OOE+OO 2.40E-05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO Co-57 0.00£+00 1. 75E-07 2.91E-07 O.OOE+OO 0.00£+00 0.00£+00 4.44£-06 Sr-85 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 Y-88 0.00£+00 O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 Nb-94 O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO Nb-97 5.22E-11 1.32£-11 4.82E-12 O.OOE+OO 1.54E-11 O.OOE+OO 4.87E-08 Cd-109 O.OOE+OO O.OOE+OO O.OOE+OO 0.008+00 O.OOE+OO O.OOE+OO O.OOE+OO Sn-1l3 0.002+00 0.00£+00 O.OOE+OO 0.008+00 O.OOE+OO O.OOE+OO O.OOE+OO Ba-133 O.OOE+OO 0.008+00 O.OOE+OO 0.00£+00 0.00£+00 O.OOE+OO 0.002+00 Te-134 3.24£-08 2.12£-08 1.308-08 2.83£-08 2.05£-07 O.OOE+OO 3.59E-11 Ce-139 O.OOE:+OO 0.00£+00 0.00£+00 0.00£+00 O.OOE+OO 0.00£+00 0.00£+00 Hg-203 0.00£+00 0.00£+00 0.00£+00 O.OOE:+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 2 Page 40 Revision 10

aDCM Part II - Calculational Methodologies Table 2-30 TEEN INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDN£Y LONG GILU H-3 O.OOE+OO 1.06£-07 1.06E-07 1.06E-07 1.06E-07 1.06E~07 1.06£-07 Be-7 3.96E-09 8.87£-09 4.43£-09 0.00£+00 9.40£-09 O.OOE+OO 1.08E-06 Na-24 2.30£-06 2.30£-06 2.30E-06 2.30E-06 2.30E-06 2.30£-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 O.OOE+OO O.OOE+OO 0.00£+00 2.32E-05 Cr-51 O.OOE+OO O.OOE+OO 3.60E-09 2.00E-09 7.89£-10 5.14E-09 6.05E-07 JYln-54 O.OOE+OO 5.90E-06 1. 17E-06 O.OOE+OO 1.76E-06 O.OOE+OO 1. 21E-05 Mn-56 0.00£+00 1.58E-07 2.81E-08 O.OOE+OO 2.00E-07 O.OOE+OO 1. 04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 O.OOE+OO O.OOE+OO 1. 70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29£-06 O.OOE+OO O.OOE+OO 4.32£-0'6 3.24E-05 Co-58 0.00£+00 9.72E-07 2.24E-06 O.OOE+OO 0.00£+00 0.00£+00 1.34£-05 Co-60 0.00£+00 2.81E-06 6.33E-06 0.00£+00 O.OOE+OO 0.00£+00 3.66E-05 Ni-63 1.77E-04 1.25£-05 6.00£-06 0.00£+00 0.00£+00 O.OOE+OO 1.99£-06 Ni-65 7.49E-07 9.57£-08 4.36E-08 0.00£+00 O.OOE+OO O:OOE+OO 5.19E-06 Cu-64 O.OOE+OO 1.15£-07 5.41£-08 0.00£+00 2.91E-07 0.00£+00 8.92£-06 Zn-65 5.76£-06 2.00E-05 9.33E-06 O.OOE+OO 1.28E-05 0.00£+00 8.47£-06 Zn-69 1.47E-08 2.80£-08 1.96E-09 O.OOE+OO 1.83£-08 O.OOE+OO 5.16£-08 Br-83 O.OOE+OO O.OOE+OO 5.74£-08 O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 Br-84 O.OOE+OO 0.00£+00 7.22£-08 O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO Br-S5 O.OOE+OO O.OOE+OO 3.05E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.98E-05 1. 40!~~05 O.OOE+OO O.OOE+OO O.OOE+OO 4.41E-06 Rb-88 O.OOE+OO 8.52E-08 4.54E-08 O.OOE+OO O.OOE+OO O.OOE+OO 7.30E-15 Rb-S9 O.OOE+OO 5.50E-OS 3.89E-OS O.OOE+OO O.OOE+OO O.OOE+OO S.43E-17 Sr,-S9 4.40E-04 O.OOE+OO 1.26£-05 O.OOE+OO O.OOUOO 0.00£+00 5.24£-05 Sr-90 8.30E-03 O.OOE+OO 2.05E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E-04 Sr-91 8.07E-06 O.OOE+OO 3.21E-07 0.00£+00 O.OOE+OO O.OOE+OO 3.66£-05 Sr-92 3.05£-06 O.OOE+OO 1.30£-07 O.OOE+OO 0.00£+00 0.00£+00 7.77E-05 Y-90 1.37E-08 O.OOE+OO 3.69E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.13E-04 Y-91m 1.29E-10 O.OOE+OO 4.93E-12 O.OOE+OO O.OOE+OO O.OOE+OO 6.09E-09 Y-91 2.01E-07 O.OOE+OO 5.39E-09 O.OOE+OO O.OOE+OO O.OOE+OO 8.24E-05 Y-92 ,1.21E-09 O.OOE+OO 3.50E-11 O.OOE+OO O.OOE+OO O.OOE+OO 3.32E-05 Y-93 3.S3E-09 O.OOE+OO 1.05E-10 O.OOE+OO 0.00£+00 O.OOE+OO 1. 17£-04 Zr-95 4.12£-OS 1.30£-OS 8.94£-09 O.OOE+OO 1.91E-08 O.OOE+OO 3. '00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 0.00£+00 7.11E-10 O.OOE+OO 1.27E-04 Nb-95 8.22£-09 4.56E-09 2.51E-09 O.OOE+OO 4.42E-09 0.00£+00 1.95£-05 Mo-99 0.00£+00 6.03E-06 1.15E-06 O.OOE+OO 1.3SE-05 O.OOE+OO 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-08 O.OOE+OO 1. 3S£-08 5.14E-lO 6.08E-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 O.OOE+OO 9.26E-09 3.12£-10 8.75E-17 Ru-103 2.55E-07 O.OOE+OO 1.09E-07 O.OOE+OO S.99E-07 O.OOE+OO 2.l3E-05 Ru-105 2.18E-08 O.OOE+OO 8.46E-09 0.00£+00 2.75E-07 O.OOE+OO 1. 76E-05 Ru-106 3.92E-06 O.OOE+OO 4.94E-07 O.OOE+OO 7.56E-06 O.OOE+OO 1. 88E-04 Ag-llOm 2.05E-07 1.94E-07 1.18E-07 0.00£+00 3.70E-07 O.OOE+OO 5.45E-05 Sb-l22 3.30£-07 6.42£-09 9.64E-08 4.19E-09 O.OOE+OO 2.06E-07 6.92E-05 Sb-124 3.86E-06 7.122-08 1.SlE-06 8.79E-09 O.OOE+OO 3.37E-06 7.S1E-05 Sb-125 2.48£-06 2.71E-08 5.79£-07 2.36£-09 O.OOE+OO 2.16E-06 1.92E-05 Indian Point 2 Page 41 Revision 10

aDCM Part II - Calculational Methodologies Table 2-3b TEEN INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 O.OOE+OO O.OOE+OO 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 O.OOE+OO 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 O.OOE+OO 1. 22E-05 Te-129m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 O.OOE+OO 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 O.OOE+OO 2.45E-07 Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 O.OOE+OO 9.39E-05 Te-131 2.79E-08 1.15E-08 8.722-09 2.15E-08 1.22£-07 O.OOE+OO 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 O.OOE+OO 7.00E-05 I-l30 1.03E-06 2.98E-06 1. 19E-06 2.43E-04 4.59E-06 O.OOE+OO 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1. 41E-05 O.OOE+OO 1. 62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 O.OOE+OO 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 O.OOE+OO 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 O.OOE+OO 5.10E-09 I-135 6.10E-07 1. 57E-06 5.82E-07 1. 01E-04 2.48E-06 O.OOE+OO 1. 74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 O.OOE+OO 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 O.OOE+OO 1.84E-05 2.90E-06 2.72E-06 C5-137 1.12E-04 1. 49E-04 5.19E-05 O.OOE+OO 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 O.OOE+OO 1.10E-07 1.28E-08 6.76E-11 Ba-139 1.39E-07 9.78E-11 4.05E-09 O.OOE+OO 9.22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.488-08 1.83E-06 O.OOE+OO 1.18E-OS 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01E-11 2.24E-09 O.OOE+OO 4.65E-11 3.43E-11 1. 43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 O.OOE+OO 2.53E-11 1. 99E-11 9.18E-20 La-140 3.48E-.o9 1. 71E-09 4.55E-I0 O.OOE+OO O.OOE+OO O.OOE+OO 9.82E-05 La-142 1. 79E-I0 7.95E-11 1. 98E-11 O.OOE+OO O.OOE+OO O.OOE+OO 2.42E-06 Ce-141 1.33E-08 8.88E-09 1. 02E-09 O.OOE+OO 4.18E-09 O.OOE+OO 2.54E-05 Ce-143 2.35E-09 1. 71E-06 1.91E-I0 O. .oOE+OO 7.67E-I0 O.OOE+OO 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 O.OOE+OO 1.72E-07 O.OOE+OO 1.75E-04 Pr-143 1. 31E-08 5.23E-09 6.52E-I0 O.OOE+OO 3.04E-09 O.OOE+OO 4.31E-05 Pr-144 4.30E-11 1. 76E-11 2.18E-12 O.OOE+OO 1.0IE-11 O.OOE+OO 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-I0 O.OOE+OO 5.99E-09 O.OOE+OO 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 O.OOE+OO O.OOE+OO O.OOE+OO 3.22E-05 Np-239 1. 76E-09 1.66E-I0 9.22E-11 O.OOE+OO 5.21E-10 O.OOE+OO 2.67E-05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 2.38E-07 3.99E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.44E-06 Sr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 7.37E-11 1.83E-11 6.68E-12 O.OOE+OO 2. 14E-11 O.OOE+OO 4.37E-07 Cd-109 O.OOE+OO O.OOE+OO O.OOE+OO O.OO'E+OO O.OOE+OO O.OOE+OO O.OOE+OO Sn-1l3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-133 O.OOE+OO O.OOE+OO Q.002+00 0.002+00 O.OOE+OO O.OOE+OO O.OOE+OO Te-134 4.47E-08 2.S7E-08 3.00E-08 3.67E-08 2.74E-07 O.OOE+OO 1.66E-09 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 2 Page 42 Revision 10

aDCM Part II - Calculational Methodologies Table 2-3c CHILD INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI B-3 O.OOE+OO 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 Be-7 1.18E-08 2.00E-08 1.32E-08 O.OOE+OO 1.97E-08 O.OOE+OO 1.12E-06 Na-24 S.80E-06 S.80E-06 S.80E-06 S.80E-06 S.80£-06 S.80E-06 S.80E-06 P-32 8.2SE-04 3.86E-05 3.18E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.28E-OS Cr-S1 O.OOE+OO O.OOE+OO 8.90E-09 4.94E-09 1. 35E-09 9.02E-09 4.72E-07 Mn-S4 O.OOE+OO 1. 01£-05 2.8SE-06 O.OOE+OO 3.00E-06 O.OOE+OO 8.98E-06 Mn-56 O.OOE+OO 3.34£-07 7.S4E-08 O.OOE+OO 4.04E-07 O.OOE+OO 4.84E"'-OS Fe-55 1.lSE-05 6.10E-06 1.89E-06 O.OOE+OO O.OOE+OO 3.4SE-06 1.13E-06 Fe-S9 1.6SE-OS 2.67E-OS 1.33E-05 O.OOE+OO O.OOE+OO 7.74E-06 2.78E-OS Co-S8 O.OOE+OO 1.80E-06 S.SlE-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.0SE-OS Co-60 O.OOE+OO S.29E-06 1.S6E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.93E-OS Ni-63 5.38E-04 2.88E-OS 1.83E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E-06 Ni-6S 2.22E-06 2.09E-07 1.22E-07 O.OOE+OO O;OOE+OO O.OOE+OO 2.S6E-05 Cu-64 O.OOE+OO 2.4SE-07 1. 48E-07 O.OOE+OO 5.92E-07 0.00E+00,1.1SE-OS Zn-65 1.37E-OS 3.6SE-OS 2.27E-05 O.OOE+OO 2.30E-05 O.OOE+OO 6.41E-06 Zn-69 4.38E-08 6.33E-08 S.8SE-09 O.OOE+OO 3.B4E-OB O.OOE+OO 3.99E-06 Br-B3 O.OOE+OO O.OOE+OO 1. 71E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-B4 O.OOE+OO O.OOE+OO 1.9BE-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-8S O.OOE+OO O.OOE+OO 9.12E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 6.70E-OS 4.12E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.31E-06 Rb-88 O.OOE+OO 1.90E-07 1.32E-07 O.OOE+OO O.OOE+OO O.OOE+OO 9.32E-09 Rb-89 O.OOE+OO 1.17E-07 1.04E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1. 02E-09 Sr-89 1.32E-03 O.OOE+OO 3.77E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.llE-05 Sr-90 1.70E-02 O.OOE+OO 4.31E-03 0.00.£+00 O.OOE+OO O.OOE+OO 2.29E-04 Sr-91 2.40E-OS O.OOE+OO 9.06E-07 O.OOE+OO O.OOE+OO O.OOE+OO 5.30E-OS Sr-92 9.03E-06 O.OOE+OO 3.62E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.71E-04 Y-90 4.llE-OB O.OOE+OO 1.10E-09 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E-04 Y-91m 3.B2E-10 O.OOE+OO 1.39E-11 O.OOE+OO O.OOE+OO O.OOE+OO 7.48E-07 Y-91 6.02E-07 O.OOE+OO 1.61E-:08 O.OOE+OO O.OOE+OO O.OOE+OO B.02E-05 Y-92 3.60E-09 O.OOE+OO 1.03E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1. 04E-04 Y-93 1.l4E-OB O.OOE+OO 3.l3E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.70E-04 Zr-9S 1.16E-07 2.5SE-08 2.27E-08 O.OOE+OO 3.65E-OB 0.00£+00 2.66E-OS Zr-97 6.99E-09 1.01E-09 5.96E-10 O.OOE+OO 1.4SE-09 O.OOE+OO 1.S3E-04 Nb-9S 2.2SE-08 B.76E-09 6.26E-09 O.OOE+OO B.23E-09 O.OOE+OO 1.62E-05 Mo-99 O.OOE+OO 1.33E-OS 3.29E-06 O.OOE+OO 2.84E-OS O.OOE+OO 1.10E-05 Tc-99m 9.23E-10 1.81E-09 3.00E-08 O.OOE+OO 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 O.OOE+OO 1.91E-OB 5.92E-I0 3.56E-09 Ru-103 7.31E-07 O.OOE+OO 2.B1E-07 O.OOE+OO 1.84E-06 O.OOE+OO 1.89E-05 Ru-10S 6.45E-OB O.OOE+OO 2.34E-08 O.OOE+OO 5.67E-07 O.OOE+OO 4.21E-05 Ru-106 1.11£-05 O.OOE+OO 1.46£-06 O.OOE+OO 1.58E-OS O.OOE+OO 1.82E-04 Ag-llOm 5.39E-07 3.64E-07 2.91E-07 O.OOE+OO 6.78E-07 O.OOE+OO 4.33E-05 Sb-l22 9.83E-07 1. 45E-08 2.88E-07 1.26E-08 O:OOE+OO 4.00E-07 7.56E-OS Sb-124 1.11E-05 1.442-07 3.88E-06 2.44E-08 O.OOE+OO 6.15E-06 6.93E-05 Sb-125 7.15E-06 5.S1£-08 1.50E-06 6.63£-09 O.OOE+OO 3.98E-06 1.71E-05 Indian Point 2 Page 43 Revision 10

aDCM Part II - Calculational Methodologies Table 2-3c CHILD ING£STION DOS£ FACTORS (mrem per pCi ingested)

Isotope BON£ LIV£R TOT BODY THYROID KIDN£Y LUNG GILLI Te-125m 1.14£-05 3.09£-06 1.52£-06 3.20£-06 0.00£+00 0.00£+00 1.10£-05 Te-l27m 2.89£-05 7.78£-06 3.43£-06 6.91£-06 8.24£-05 0.00£+00 2.34E-05 Te-127 4.71£-07 1.27£-07 1.01£-07 3.26£-07 1.34£-06 0.00£+00 1.34£-05 Te-129m 4.87£-05 1.36£-05 7.56£-06 1.57£-05 1.43E-04 0.00£+00 5.94£-05 Te-129 1.34£-07 3.74E-08 3.18£-08 9.56£-08 3.92E-07 O.OOE+OO 8.34£-06 Te-131m 7.20£-06 2.49E-06 2.65£-06 5.12£-06 2.41£-05 0.00£+00 1. 01£-04 Te-131 8.30£-08 2.53£-08 2.47£-08 6.35£-08 2.51£-07 0.00£+00 4.36£-07 Te-132 1.01£-05 4.47E-06 5.40E-06 6.51£-06 4.15£-05 0.00£+00 4.50£-05 I-130 2.92E-06 5.90£-06 3.04£-06 6.50£-04 8.82£-06 0.00£+00 2.76E-06 I-131 1. 72£-05 1.73E-05 9.83£-06 5.72£-03 2.84£-05 0.00£+00 1.54£-06 I-132 8.00£-07 1.47£-06 6.76£-07 6.82£-05 2.25£-06 0.00£+00 1. 73£-06 I-133 5.92£-06 7.32£-06 2.77£-06 1.36£-03 1.22£-05 0.00£+00 2.95£-06 I-134 4.19£-07 7.78£-07 3.58£-07 1.79£-05 1.19£-06 0.00£+00 5.16E-07 I-135 1. 75£-06 3.15£-06 1.49£-06 2.79£-04 4.83£-06 0.00£+00 2.40E-06 Cs-134 2.34£-04 3.84£-04 8.10£-05 0.00£+00 1. 19E-04 4.27£-05 2.07£-06 Cs-13 6 2.35£-05 6.46£-05 4.18£-05 0.00£+00 3.44£-05 5.13E-06 2.27£-06 Cs-137 3.27£-04 3.13£-04 4.62£-05 0.00£+00 1. 02£-04 3.67£-05 1. 96E-06 Cs-138 2.28£-07 3.17E-07 2.01E-07 O.OOE+OO 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14£-07 2.21E-I0 1.20E-08 O.OOE+OO 1. 93E-I0 1.30E-10 2.39£-05 8a-140 8.31E-05 7.28E-08 4.85£-06 0.00£+00 2.37£-08 4.34£-OS 4.21£-05 Ba-141 2.00E-07 1.12E-I0 6.51E-09 0.00£+00 9.69E-11 6.5S£-10 1. 14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 O.OOE+OO 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-OS 3.53£-09 1.19E-09 0.00£+00 0.00£+00 0.00£+00 9.S4£-05 La-142 5.24E-10 1.67E-I0 5.23£-11 O.OOE+OO O.OOE+OO O.OOE+OO 3.31E-05 Ce-141 3.97£-08 1.98£-08 2.94E-09 O.OOE+OO 8.68E-09 O.OOE+OO 2.47E-05 Ce-143 6.99£-09 3.79E-06 5.49£-10 0.00£+00 1. 59£-09 0.00£+00 5.55£-05 Ce-144 2.08£-06 6.52£-07 1.11£-07 0.00£+00 3.61E-07 0.00£+00 1. 70£-04 Pr-143 3.93E-08 1.1S£-OS 1.95£-09 0.00£+00 6.39£-09 0.00£+00 4.24£-05 Pr-144 1.29£-10 3.99£-11 6.49£-12 O.OOE+OO 2.11£-11 0.00£+00 8.59£-08 Nd-147 2.79E-08 2.26£-08 1. 75£-09 0.00£+00 1.24£-08 O.OOE+OO 3.58E-05 W-187 4.29E-07 2.54£-07 1.14E-07 O.OOE+OO 0.00£+00 0.00£+00 3.57£-05 Np-239 5.25E-09 3.77E-10 2.65£-10 O.OOE+OO 1.09E-09 0.00£+00' 2.79£-05 K-40 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 0.00£+00 Co-57 O.OOE+OO 4.93E-07 9.9S£-07 0.00£+00 O.OOE+OO O.OOE+OO 4.04E-06 Sr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 0.00£+00 Y-8S O.OOE+OO 0.00£+00 0.00£+00 O.OOE+OO O.OOE+OO 0.00£+00 0.00£+00 Nb-94 O.OOE+OO 0.00£+00 0.00£+00 0.00£+00 0.00£+00 0.00£+00 0.00£+00 Nb-97 2.17E-10 3.92£-11 I.S3E-11 0.00£+00 4.35E-11 0.00£+00 1.21E-05 Cd-109 O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO 0.00£+00 0.00£+00 O.OOE+OO Sn-1l3 0.00£+00 O.OOE+OO 0.00£+00 0.00£+00 0.00£+00 0.00£+00 0.00£+00 Ba-l33 0.00£+00 O.OOE+OO 0.00£+00 0.00£+00 0.00£+00 0.00£+00 0.00£+00 Te-134 1.29£-07 5.80£-OS 7.74£-08 1.02E-07 5.37£-07 0.00£+00 5.S9£-07 Ce-139 0.00£+00 0.00£+00 0.00£+00 0.00£+00 0.00£+00 0.00£+00 O.OOE+OO Hg-203 0.00£+00 0.00£+00 0.00£+00 0.00£+00 0.00£+00 0.00£+00 0.00£+00 Indian Point 2 Page 44 Revision 10

aDCM Part II - Calculational Methodologies Table 2-3d INE'ANT INGESTION DOSE FACTORS (mrem per pCi ingested)

Iso1:ope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08£-07 Be-7 2.26£-08 4.72£-08 2.51E-08 0 ..00£+00 3.34£-08 O.OOE+OO 1.l1E-06 Na-24 1.01E-05 1.01E-05 1.01£-05 1.01£-05 1.01E-05 1.01£-05 1.01£-05 P-32 1. 70£-03 1. 00£-04 6.59£-05 O.OOE+OO O.OOE+OO 0.00£+00 2.30£-05 Cr-51 O.OOE+OO O.OOE+OO 1.41£-08 9.20£-09 2.01£-09 1.79E-08 4.11£-07 t1n-54 O.OOE+OO 1.99E-05 4.51E-06 0.00£+00 4.41£-06 0.00£+00 7.31£-06 Mn-56 0.00£+00 8.18E-07 1.41E-07 0.00£+00 7.03£-07 O.OOE+OO 7.43£-05 Fe-55 1.39E-05 8.98£-06 2.40E-06 O.OOE+OO 0.00£+00 4.39£-06 1.14£-06 Fe-59 3.08E-05 5.38E-05 2.12£-05 0.00£+00 0.00£+00 1.59E-05 2.57£-05 Co-58 0.00£+00 3.60E-06 8.98£-06 O.OOE+OO 0.00£+00 O.OOE+OO 8.97E-06 Co-60 O.OOE+OO 1.08E-05 2.55E-05 O.OOE+OO 0.00£+00 O.OOE+OO 2.57£-05 Ni-63 6.34E-04 3.92£-05 2.20E-05 0.00£+00 0.00£+00 O.OOE+OO 1.95E-06 Ni-65 4.70E-06 5.32£-07 2.42E-07 0.00£+00 0.00£+00 0.00£+00 4.0SE-OS Cu-64 0.00£+00 6.09£-07 2.82E-07 0.00£+00 1. 03E-06 O.OOE+OO 1.25£-OS Zn-6S 1.84£-OS *6.31E-OS 2.91£-OS O.OOE+OO 3.06E-OS 0.00£+00 S.33£-OS Zn-69 9.33E-08 1.68£-07 1.25£-08 O.OOE+OO 6.98£-08 0.00£+00 1.37£-05 Br-83 O.OOE+OO O.OOE+OO 3.63E-07 0.00£+00 0.00£+00 0.00£+00 0.00£+00 Br-84 O.OOE+OO O.OOE+OO 3.82£-07 0.00£+00 0.00£+00 O.OOE+OO 0.00£+00 Br-8S O.OOE+OO O.OOE+OO 1.94E-08 0.00£+00 0.00£+00 0.00£+00 0.00£+00 Rb-86 0.00£+00 1. 70E-04 8.40£-OS 0.00£+00 0.00£+00 0.00£+00 4.3S£-06 Rb-88 O.OOE+OO 4.98E-07 2.73E-07 O.OOE+OO 0.00£+00 O.OOEIOO 4.85£-07 Rb-89 0.00£+00 2.86E-07 1.97E-07 0.00£+00 O.OOE+OO 0.00£+00 9.74£-08 Sr-89 2.51£-03 0.00£+00 7.20E-05 O.OOE+OO 0.00£+00 0.00£+00 S.16£-OS Sr-90 1. 85E-02 0.00£+00 4.71£-03 O.OOE+OO 0.00£+00 0.00£+00 2.31£-04 Sr-91 5.00£-05 0.00£+00 1.81£-06 0.00£+00 0.00£+00 0.00£+00 5.92£-OS Sr-92 1.92£-05 0.00£+00 7.13£-07 0.00£+00 0.00£+00 O.OOE+OO 2.07£-04 Y-90 8.69£-08 O.OOE+OO 2.33£-09 O.OOE+OO 0.00£+00 0.00£+00 1.20£-04 Y-91m 8.10E-I0 0.00£+00 2.76£-11 0.00£+00 0.00£+00 0.00£+00 2.70£-06 Y-91 1.l3£-06 0.00£+00 3.01£-08 0.00£+00 0.00£+00 0.00£+00 8.10£-05 Y-92 7.65£-09 0.00£+00 2.15£-10 0.00£+00 O.OOE+OO 0.00£+00 1.46£-04 Y-93 2.43£-08 O.OOE+OO 6.62£-10 0.00£+00 0.00£+00 O.OOE+OO 1.92£-04 Zr-9S 2.06E-07 5.02E-08 3.S6E-08 0.00£+00 5.41£-08 O.OOE+OO 2.50£-OS Zr-97 1.48£-08 2.S4£-09 1.16£-09 0.00£+00 2.S6£-09 0.00£+00 1.62£-04 Nb-95 4.20£-08 1.73E-08 1.00£-08 0.00£+00 1.24£-08 O.OOE+OO 1.46£-05 Mo-99 0.00£-'-00 3.40E-OS 6.63E-06 O.OOE+OO 5.08£-OS O.OOE+OO 1.12E-05 Tc-99m 1.92E-09 3.96£-09 5.10£~08 0.00£+00 4.26£-08 2.07£-09 1.1S£-06 Tc-101 2.27£-09 2.86£-09 2.83£-08 0.00£+00 3.40£-08 1. 56E-09 4.86£-07 Ru-l03 1.48£-06 0.00£+00 4.9S£-07 0.00£+00 3.08£-06 O.OOE+OO 1.80£-05 Ru-l05 1.36£-07 O.OOE+OO 4.58£-08 0.00£+00 1.00E-06 O.OOE+OO 5.41£-05 Ru-106 2.41E-05 O.OOE+OO 3.01£-06 0.00£+00 2.8SE-05 O.OOS+OO 1.83£-04 J'..g-110m 9.96E-07 7.27£-07 4.81£-07 O.OOE+OO 1.04£-06 0.00£+00 3.77£-05 Sb-122 2.10£-06 3.85E-08 6.13£-07 3.14E-08 O.OOE+OO 1.0%-06 7.65E-05 Sb-124 2.HE-05 3.15£-07 6.63E-06 5.68£-08 0.00£+00 1. 34£-05 6.60E-05 Sb-125 1.23£-05 1.19£-07 2.53£-06 1.54£-08 0.00£+00 7.72E-06 1.64£-05 Indian Point 2 *Page 45 Revision 10

ODCM Part II - Calculational Methodologies Table 2-3d INFANT INGESTION DOSE FACTORS (mrem per pCi ingested)

Isotope BONE LIVER TOT BODY THYROID' KIDNEY LUNG GILLI Te-12Sm 2.33E-05 7.79E-06 3.15E-06 7.84E-06,0.00E+00 O.OOE+OO 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-OA O.OOE+OO 2.36E-05 Te-l:h 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 O.OOE+OO 2.10E-05 Te-129m 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 O.OOE+OO 5.97E-05 Te-129 2.B4E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 O.OOE+OO 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.05E-06 1. 24E-05 4'.21E-05 O.OOE+OO 1.03E-04 Te-131 1. 76E-07 6.50E-OB 4.94E-08 1.57E-07 4.50E-07 O.OOE+OO 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 O.OOE+OO 3.BIE-05 1-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 O.OOE+OO 2.83E-06 1-131 3.59E-05 4.23E-05 1. 86E-05 1.39E-02 4.94E-05 O.OOE+OO 1.51E-06 1-132 1. 66E-06 3.37E-06 1. 20E-06 1.58E-04 3.76E-06 O.OOE+OO 2.73E-06 1-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2 ~ 14E-05 O.OOE+OO 3.08E-06 1-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 O.OOE+OO 1.84E-06 1-135 3.64E-'06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 O.OOE+OO 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 O.OOE+OO 1.81E-04 7.42E-05 1. 91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 O.OOE+OO 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.llE-04 4.33E-05 O.OOE+OO 1.64E-04 6.64E-05 1. 91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 O.OOE+OO 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-I0 2.55E-08 O.OOE+OO 3.51E-10 3.54E-10 5.58E-05 Ba-140 1. 71E-04 1.71E-07 8.. B1E-06 O.OOE+OO 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1. 34E-08 O.OOE+OO 1.75E-10 h 77E-10 5.19E-06 Ba-142 ,1.84E-07 1.53E-10 9.06E-09 O.OOE+OO 8.81E-11 9.26E-11 7.59E-07 La-140 2.llE-08 8.32E-09 2.14E-09 O.OOE+OO O.OOE+OO O.OOE+OO 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 O.OOE+OO O.OOE+OO O.OOE+OO 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 O.OOE+OO 1. 48E-08 O.OOE+OO 2.48E-05 Ce-l43 1.48E-08 9.B2E-06 1.12E-09 O.OOE+OO 2.B6E-09 O.OOE+OO, 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 O.OOE+OO 4.93E-07 O.OOE+OO 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 O.OOE+OO 1.13E-08 O.OOE+OO 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-ll O.OOE+OO 3.84E-ll O.OOE+OO 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 O.OOE+OO 2.l9E-08 O.OOE+OO 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.69E-05 Np-239 1. 11E-08 9.93E-10 5.61E-10 O.OOE+OO 1.98E-09 O.OOE+OO 2.87E-05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 1.15E-06 1.87E-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.92E-06 Sr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cd-l09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sn-113 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 2 Page 46 Revision 10

ODCM Part'li - Calculational Methodologies Table 2-4 TOTAL BODY DOSE FACTORS Ki FROM NOBLE GASES (GAtvJMA)

FINITE CLOUD ....

CORRECTION NUCLIDE GaJ'Tlma T8* x (pCi/uCi) X fACTOR Ki*"*

Kr-83m 7.56E-08 1.00E+6 8.86E-01 6.70E-02 Kr-85m 1.17E-03 1.00E+6 7.49E-01 8.76E+02 Kr-85 1.61E-05 1.00E+6 6.73E-01 1. 08E+01 Kr-87 5.92E-03 1.00E+6 5.68E 3.36E+03 Kr-88 1.47E-02 1.00E+6 5.40E-01 7.93E+03 Kr-89 1. 66E-02 1. 00E+6 5.60E-01 9.30E+03 Kr-90 1.56E-02 1.00E+6 5.97E-01 9.31E+03 Xe-131m 9.15E-05 1.00E+6 8.67E-01 7.94E+01 Xe-133m 2.51E-04 1.00E+6 8.17E-01 2.05E+02 Xe-133 2.94E-04 1.00E+6 8.86E-01 2.60E+02 Xe-135m 3.12E-03 1.00E+6 6.75E-01 2.11E+03 Xe-135 1.81E-03 1.00E+6 7.60E-01 1.38E+03 Xe-137 1.42E-03 1. 00E+6 6.46E-01 9.18E+02 Xe-138 8.83E-03 1. 00E+6 5.75£-01 5.07E+03 JI.r-41 8.84E-03 1. 00E+6 5.89E-01 5.21E+03

• from Regulatory Guide 1.109, Table 8-1 (mrem/yr per pCilcu mtr)

+-* The .finite cloud correction factor is described in Section 2.1.

-k'k "k Ki (mrem/yr per uCi/cu mtr)

Indian Point 2 Page 47 Revision 10

aDeM Part II - Calculational Methodologies Table 2-5 SKIN DOSE FACTORS Li FROM NOBLE GASES (BETA)

NUCLIDE Beta Skin* x (pCi/uCi) Li**

Kr-8Jrn O.OOE+OO 1.00E+6 O.OOE+OO Kr-85m 1.46E-03 1.00E+6 1.46E+03 Kr-85 1.34E-03 1. OOE+6 1.34E+03 Kr-87 9.73E-03 1. OOE+6 9.73E+03 Kr-88 2.37E-03 1. OOE+6 2.37E+03 Kr-89 1. 01E-02 1. OOE+6 1.01E+04 Kr-90 7.29E-03 1.00E+6 7.29E+03 Xe-131rn 4.76E-04 1.00E+6 4.76E+02 Xe-133m 9.94E-04 1.00E+6 9.94E+02 Xe-133 3.06E-04 1.00E+6 3.06E+02 Xe-135m 7.l1E-04 1.00E+6 7.11E+02 Xe-135 1.86E-03 1.00E+6 1.86E+03 Xe-137 1. 22E-02 1. OOE+6 1. 22E+04 Xe-138 4.13E-03 1. 00E+6 4.13E+03 Ar-41 2.69E-03 1.00E+6 2.69E+03

• From Regulatory Guide 1.109, Table B-1 (mrem/yr per pCi/cu mtr)

Li (mrem/yr per uCi/cu mtr)

Indian Point 2 Page 48 Revision 10

aDCM Part /I - Calculational Methodologies Table 2-6 AIR DOSE FACTORS

~li FROM NOBLE GASES (GAMMA)

E'INITE CLOUD **

CORRECTION NUCLIDE Garnrna* x (pCi/uCi) X FACTOR Mi***

Kr-83m 1.93E-05 1. 00£+6 8.86E-Ol 1. 71E+Ol Kr-85m 1. 23E-03 1.00£+6 7.49E-01 9.21E+02 Kr-85 1.72E-05 1. 00E+6 6.73E-Ol 1.16E+Ol Kr-87 6.17E-03 1.00E+6 5.68E-Ol 3.50E+03 Kr-88 1.52E-02 1.00E+6 5.40E-01 8.20E+03 Kr-89 1.73E-02 1.00E+6 5.60E-Ol 9.69E+03 Kr-90 1.63E-02 1.00E+6 5.97E-Ol 9.73E+03 Xe-131m 1.56E-04 1.00E+6 8.67E-Ol 1.35E+02 Xe-133m 3.27E-04 1.00E+6 8.17E-Ol . 2. 67E+02 Xe-133 3.53E-04 1. 00E+6 8.86E-01 3.13E+02 Xe-135m 3.36E-03 1. 00E+6 6.75£-01 2.27E+03 Xe-135 1. 92E-03 1.00E+6 7.60E-Ol 1.46E+03 Xe-137 1.51E-03 1. 00E+6 6.46E-01 9.76E+02 Xe-138 9.21E-03 1.00E+6 5.75E-01 5.29E+03 Ar-41 9.30E-03 1. 00E+6 5.89E-Ol 5.48E+03

• F::-om Regulatory Guide 1.109, Table 8-1 (mrad/yr per pCi!cu mtr)

• • The finite cloud correction factor is described in Section 2.1.

• • • r1i (rnrad/yr per uCi/cu mtr)

Indian Point 2 Page 49 Revision 10

aDCM Part II - Calculational Methodologies Table 2-7 AIR DOSE FACTORS Ni FROM NOBLE GASES (BET.I\)

NUCLIDE Beta* x (pCi/uCi) Ni**

Kr-83m 2.88E-04 1.00E+6 2.88E+02 Kr-,85m 1. 97E-03 1.00E+6 1.97E+03 Kr-85 1.95£-03 1.00E+6 1.95£+03 Kr-87 1.03£'--02 1. 00£+6 1. 03£+04 Kr-88 2.93£-03 1. 00E+6 2.93E+03 Kr-89 1. 06£-02 1.00£+6 1.06£+04 Kr-90 7.83£-03 1. 00E+6 7.83E+03 Xe-'131m 1. llE-03 1.00E+6 1. 1l£+03 Xe-133m 1.48E-03 1. 00E+6 1.48E+03 Xe-133 1.05£-03 1.00E+6 1.05£+03 Xe~135m 7.39£-04 1.00E+6 7.39£+02 Xe-135 2.46£-03 1. 00E+6 2.46E+03 Xe-137 1.27E-02 1. 00E+6 1. 27E+04 Xe-138 4.75E-03 1.00E+6 4.75£+03' Ar-41 3.28E-03 1.00E+6 3.28E+03

• Fro~ Regulatory Guide 1.109, Table B-1 (mrad/yr per pCi/cu mtrJ

• • Ni (mrad/yr per uCi/cumt;J Indian Point 2 Page 50 Revision 10

aDCM Part II - Calculational Methodologies TABLE 2-8 NOBLE GAS DOSE FACTORS For Instantaneous and Time Average Mixtures at the Site Boundary Radionuclide Instantaneous Time Average Mix (%) Mix (%)

Kr-85m 3.09 Kr-85 0 18.98 Kr-87 2.80 Kr-88 5.22 Xe-131m 0 0.162 Xe-133m 1.39 0.485 Xe-133 56.8 78.1 Xe-135m 1.34 Xe-135 19.2 2.21 Xe-138 2.81 Ar-41 7.43 Total 100 100 Unit 2 effective Unit 3 effective Unit 2 effective Unit 3 effective t""

instantaneous instantaneous average average dose factors dose factors units dose factors dose factors K = 1507 K = 849 mremlyr per uCilm 3 K = 237 K = 153 L = 1310 L = 1310 mremlyr per uCi/m3 L =540 L = 540 M= 1601 M = 905 mrad/yr per uCilm3 M = 281 M = 181 N = 1977 -N= 1977 mrad/yr per uCi/m 3 N = 1254 = 1254 N

Instantaneous Mixture Basis:

This mix defines the shared-site noble gas limits between the two units, and is used for administrative guidelines for instantaneous releases based on an RCS noble gas mix at 1.6 yrs into a 24-month cycle, with two failed fuel rods, per Reference 21. These mixtures provide conservative application for calculating setpoints per 10CFR20, in terms of uCi/sec before an actual sample of the release is available, per Appendix I.

Time Averaged Release Mixture Basis:

This mix defines the routine (time-averaged) releases from either unit. It was derived from average noble-gas releases from year 2000-2003 at IPEC units 2 and 3 per Reference 21. They are used in conjunction with calculations to determine representative quarterly and annual time averaged release rates in curies/sec for administrative purposes only, per Appendix I.

Indian Point 2 Page 51 Revision 10

ODCM Part II - Calculational Methodologies TABLE2-9 LOCATIONS OF SITE BOUNDARY AND NEAREST RESIDENCE S~ctbr .- " Distance Distance Distance to Site to Site to nearest B()undary Boundary '. reSid~nt; '. .

by from'Unit 2 . fromUriit3 fromuriitf

'. compass

. point**,' Plant Vent, Plant Verit, su perheater,

" in meters I in meters,'* in meters' N RIVER RIVER 1788.1 NNE RIVER RIVER 3111.3 NE 550 636 1907.3 ENE 600 775 1478.2 E 662 785 1370.9 ESE 569 622 715.2 SE 553 564 1168.2 SSE 569 551 1239.7 S 700 566 1132.5 SSW 755 480 1573.5 SW 544 350 3015.9 WSW RIVER RIVER 2169.6 W RIVER RIVER 1918.7 WNW RIVER RIVER 1752.4 NW RIVER RIVER 1692.7 NNW RIVER RIVER 1609.3 Distances are measured from the unit-specific Plant Vent to the Site Boundary. The distance to the Nearest Resident is measured from the Unit 1 Superheater Stack for both units 2 and 3. (Reference 22)

Indian Point 2 Page 52 Revision 10

ODCM Part II - Calculational Methodologies Table 2-10a 3

ADULT INHALATION Ri(I) (mrem!yr per ueUm )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 1.26E+03 1.26E+03 1.26E+03 1.26E+03 *1.26E+03 1.26E+03 Be-7 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 1.02E+04 1.02E+04 1.02E+04 1. 02E+04 1.02E+04 1.02E+04 1. 02E+04.

P-,32 1.32E+06 7.71E+04 5.01E+04 0.00£+00 O.OOE+OO O.OOE+OO 8.64E+04 Cr-51 0.00£+00 O.OOE+OO 1.00£+02 5.95£+01 2.28£+01 1.44E+04 3.32E+03.

Mn-54 O.OOE+OO 3.96E+04 6.30E+03 0.00£+00 9.84£+03 1. 40E+06 7.74£+04 Mn-56 O.OOE+OO 1.24E+00 1. 83£-01 0.00£+00 1. 30£+00 9.44E+0*3 2.02E+04 Fe-55 2.46E+04 1.70E+04 3.94E+03 0.00£+00 O.OOE+OO 7.21E+04 6.03E+03 Fe-59 1.18£+04 2.78E+04 1.06£+04 O.OOE+OO O.OOE+OO 1.02E+06 1. 88E+05 Co-58 O.OOE+OO 1.58E+03 2.07E+03 O.OOE+OO O.OOE+OO 9.28£+05 1.06£+05 Co-60 O.OOE+OO 1.15E+04 1.48E+04 O.OOE+OO O.OOE+OO 5.97E+06 2.85E+05 Ni-63 4.32E+05 3.14E+04 1.45E+04 O.OOE+OO O.OOE+OO 1.78E+05 1.34E+04 Ni-65 1.51E+00 2.10E-01 9.12E-02 O.OOE+OO O.OOE+OO 5.60E+03 1.23E+04 Cu-64 O.OOE+OO 1.46E+00 6.15E-01 O.OOE+OO 4.62E+00 6.78E+03 4.90E+04 Zn-65 3.24E+04 1.03E+05 4.66E+04 O.OOE+OO 6.90E+04 8.64E+05 5.34E+04 Zn-69 3.38E-02 6.51E-02 4.52E-03 O.OOE+OO 4.22E-02 9.20E+02 1.63E+01 Br-83 O.OOE+OO O.OOE+OO 2.41E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.32E+02 Br-84 O.OOE+OO O.OOE+OO 3.13E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.64E-03 Br-85 O.OOE+OO O.OOE+OO 1.28E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.35E+05 5.90E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.66E+04 Rb-88 O.OOE+OO 3.87E+02 1.93E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.34E-09 Rb-89 O.OOE+OO 2.56E+02 1.70E+02 O.OOE+OO O.OOE+OO O.OOE+OO 9.28E-12 Sr-89 3.04E+05 O.OOE+OO 8.72E+03 O.OOE+OO O.OOE+OO 1. 40E+06 3.50E+05 Sr-90 9.92E+07 O.OOE+OO 6.10E+06 O.OOE+OO O.OOE+OO 9.60E+06 7.22E+05 Sr-91 6.19E+01 O.OOE+OO 2.50E+00 O.OOE+OO O.OOE!-OO 3.65E+04 1. 91E+05 Sr-92 *6.74E+00 O.OOE+OO 2.91E-Ol O.OOE+OO O.OOE+OO 1.65E+04 4.30E+04 Y-90 2.09E+03 O.OOE+OO 5.61E+Ol O.OOE+OO O.OOE+OO 1.70E+05 5.06E+05 Y-91m 2.61E-01 O.OOE+OO 1.02E-02 O.OOE+OO O.OOE+OO 1. 92E+03 1.33E+00 Y-91 . 4. 62E+05 O.OOE+.oO 1.24E+04 O.OOE+OO O.OOE+OO 1.70E+06 3.85E+05 Y-92 1.03E+01 O.OOE+OO 3.02E-01 O.OOE+OO O.OOE+OO 1.57E+04 7.35E+04 Y-93 9.44E+01 O.OOE+OO 2.61E+00 O.OOE+OO O.OOE+OO 4.85E+04 4.22E+05 Zr-95 1.07E+05 3.44E+04 2.33E+04 O.OOE+OO 5.42E+04 1. 77E+06 1,50E+05 Zr-97 9.68E+01 1.96E+01 9.04E+00 O.OOE+OO 2.97E+01 7.87E+04 5.23E+05 Nb-95 1.41E+04 7.82E+03 4.21E+03 O.OOE+OO 7.74E+03 5.05E+05 1. 04E+05 Mo-99 O.OOE+OO 1.21E+02 2.30E+Ol O.OOE+OO 2.91E+02 9.12E+04 2.48E+05 Te-99)!l 1.03E-03 2.91E-03 3.70E-02 O.OOE+OO 4.42E-02 7.64E+02 4.16E+03 Te-l01 4.18E-05 6.02E-05 5.90E-04 O.OOE+OO 1.08E-03 3.99E+02 1.09E-11 Ru-103 1. 53E+03 O.OOE+OO 6.58E+02 O.OOE+OO 5.83E+03 5.05E+05 1.10E+05 Ru-105 7.90E-01 O.OOE+OO 3.11E-01 O.OOE+OO 1.02E+00 1.10E+04 4.82E+04 Ru-106 6.91E+04 O.OOE+OO 8.72E+03 O.OOE+OO 1.34E+05 9.36E+06 9.12E+05 Ag-llOm 1.08E+04 1.00E+04 5.94E+03 O.OOE+OO 1.97E+04 4.63E+06 3.02E+05 Sb-122 O.OOE+OO O.O.OE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 3.12E+04 5.89E+02 1.24E+04 7.55E+01 O.OOE+OO 2.48E+06 4.06E+05 Sb-125 5.34E+04 5.95E+02 1.26E+04 5.40E+Ol O.OOE+OO 1. 74E+06 1.01E+05 Indian Point 2 Page 53 Revision 10

aDCM Part II - Calculational Methodologies Table 2-l0a 3

ADULT INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BON£ LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.248+04 3.14E+05 7.06E+04 Te-127m 1. 26E+04 5.77E+03 1. 57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 Te-127 1.40E+00 6.42E-01 3.10£-01 1.06E+00 5.10£+00 6.51£+03 5.74£+04 Te-129m 9.76E+03 4.67£+03 1.58£+03 3.44E+03 3.668+04 1.16E+06 3.838+05 Te-129 4.98£-02 2.39£-02 1.248-02 3.90E-02 1.878-01 1.94E+03 1.57E+02 Te-131m 6.99£+01 4.36E+01 2.90E+01 5.50E+01 3.098+02 1.46E+05 5.56E+05 Te-131 1. EE-02 5.95E-03 3.59E-03 9.36E-03 4.37E-02 1.39E+03 1.84E+01 Te-132 2.60£+02 2.15E+02 1.62E+02 1.90£+02 1.46E+03 2.88E+05 5.10E+05 1-130 4.58£+03 1.34E+04 5.28E+03 1.14E+06 2.09£+04 0.00£+00 7.69E+03 1-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 O.OOE+OO 6.28E+03 1-132 1.16E+03 3.26E+03 1.16E+03 1.14E+05 5.18E+03 O.OOE+OO 4.06E+02 1-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 O.OOE+OO 8.88E+03 1-134 6.44E+02 1.73E+03 6.15E+02 2.98E+04 2.75E+03 O.OOE+OO 1.01£+00 1-135 2.68E+03 6.98E+03 2.57E+03 4.48£+05 1.118+04 O.OOE+OO 5.25E+03 Cs-134 3.73E+05 8.48E+05 7.28E+05 O.OOE+OO 2.87E+05 9.76£+04 1.048+04 Cs-136 3.90E+04 1.46E+05 1.10E+05 O.OOE+OO 8.56E+04 1.20E+04 1.17E+04 Cs-137 4.78E+05 6.21£+05 4.28E+05 O.OOE+OO 2.22E+05 7.52E+04 8.40£+03 Cs-138 3.31E+02 6.21E+02 3.24E+02 O.OOE+OO 4.80E+02 4.86E+01 1.86E-03 Ba-139 9.36E-01 6.66E-04 2.74E-02 0.00£+00 6.22E-04 3.76E+03 8.96E+02 Ba-140 3.90E+04 4.90E+01 2.57E+03 O.OOE+OO 1.67E+01 1.27£+06 2.18E+05 Ba-141 1. 00E-01 7.53E-05 3.36E-03 O.OOE+OO 7.00E-05 1.94E+03 1.16E--07 Ba-142 2.63E-02 2.70E-05 1.66E-03 O.OOE+OO 2.29£-05 1. 19E+03 1.57E-16 La-140 3.44E+02 1.74E+02 4.58E+01 O.OOE+OO O.OOE+OO 1. 36E+05 4.58E+05 La-142 6.83E-01 3.10E-01 7.72E-02 O.OOE+OO O.OOE+OO 6.33E+03 2.11E+03 Ce-141 1. 99E+04 1.35E+04 1.53E+03 0.00£+00 6.26E+03 3.62E+05 1.2oE+05 Ce-143 1.86E+02 1.38E+02 1.53E+01 O.OOE+OO 6.08E+01 7.98E+04 2.26E+05 Ce-144 3.43E+06 1.43E+06 1.84E+05 O.OOE+OO 8.48E+05 7.78E+06 8.16E+05 Pr-143 9.36E+03 3.75E+03 4.64E+02 O.OOE+OO 2.16E+03 2.81E+05 2.00E+05 Pr-144 3.01E-02 1.25E-02 1.53E-03 O.OoE+oO 7.05E-03 1.02E+03 2.15E-08 Nd-147 5.27£+03 6.10£+03 3.65E+02 o.OOE+OO 3.56E+03 2.21E+05 1.73E+05 W-187 8.48E+00 7.08E+00 2.48E+00 o.OOE+OO O.OOE+OO 2.90E+04 1.55E+05 Np-239 2.30£+02 2.26E+01 1.24E+01 O.OOE+OO 7.00E+01 3.768+04 1.19E+05 K-40 O.OOE+OO 0.008+00 o.OOE+OO 0.008+00 O.OOE+OO O.OOE+OO O.OOE+oO Co-57 O.OOE+-oo 6.92E+02 6.71£+02 O.OoE+oo O.OoE+OO 3.70E+05 3.14E+04 Sr-85 3.20E+04 O.OOE+OO 7.76E+05 O.OoE+OO 0.00£+00 4.80E+05 6.08E+04 Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OoE+oo o.OoE+oO 0.008+00 O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 2.22E-01 5.62E-02 2.05E-02 0.008+00 6.54E-02 2.40E+03 2.42E+02 Cd-109 O.OOE+OO 3.92E+05 1.28E+04 O.OOE+OO 3.76E+05 7.28E+05 6.56E+04 Sn-1l3 6.56E+04 2.16E+03 4.48E+03 1.36E+03 O.OOE+OO 9.60E+05 1.20E+04 Ba-133 7.60E+04 3.36E+03 2.008+04 O.OOE+OO 1.68£+01 1.52E+06 8.00E+04 Te-134 3.07E-02 2.58E-02 1.26E-02 2.75E-02 1. 748-01 3.47E+03 2.33E-Ol Ce-139 O.OOE+OO O.OOE+OO 0.008+00 0.008+00 O.OOE+OO O.OOE+OO O.OOE+OO Hg-2G3 O.OOE+OO O.OOE+OO O.OOE+OO 0.008+00 O.OOE+OO 0.008+00 O.OOE+OO Indian Point 2 Page 54 Revision 10

aDeM Part II - Calculational Methodologies Table 2-l0b 3

TEEN INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 1.27£+03 1.27£+03 1.27£+03 1.27£+03 1.27£+03 1.27£+03 Be-7 0.00£+00 O.OOE+OO 0.00£+00 0.00£+00 0.00£+00 0.00£+00 0.00£+00 Na-24 1.38£+04 1.38£+04 1.38£+04 1.38£+04 1.38£+04 1.38£+04 1.38£+04 P-32 1.89E+06 1.10£+05 7.16;;:+04 0.00£+00 O.OOE+OO O.OOE+OO 9.28E+04 Cr-51 0.00£+00 0.00£+00 1.35£+02 7.50£+01 3.07£+01 2.10E+04 3.00£+03 Nn-54 O.OOE+OO 5.11£+04 8.40£+03 0.00£+00 1. 27£+04 1.98£+06 6.68£+04 t-ln-56 0.00£+00 1.70£+00 2.52£-01 0.00£+00 1. 79£+00 1.52E+04 5.74£+04 Fe-55 3.34£+04 2.38£+04 5.54£+03 0.00£+00 0.00£+00 1. 24E+05 6.39£+03 Fe-59 1.59£+04 3.70£+04 1.43E+04 O.OOE+OO O.OOE+OO 1.53E+06 1.78E+05 Co-58 0.00£+00 2.07£+03 2.78E+03 O.OOE+OO 0.00£+00 1. 34E+06 9.52£+04 Co-60 0.00£+00 1. 51E+04 1.98E+04 O.OOE+OO O.,oOE+OO 8.72E+06 2.59£+05 Ni-63 5.80£+05 4.34£+04 1.98E+04 O.OOE+OO O.OOE+OO 3.07E+05 1.42£+04 Ni-65 2.18£+00 2.93E-01 1.27E-01 O.OOE+OO O.OOE+OO 9.36E+03 3.67E+04 Cu-64 O.OOE+OO 2.03E+00 8.48E-01 O.OOE+OO 6.41E+00 1.11E+04 6.14E+04 Zn-65 3.86£+04 1.34£+05 6.24E+04 O.OOE+OO 8.64E+04 1.24£+06 4.66£+04 Zn-69 4.83£-02 9.20E-02 6.46E-03 O.OOE+OO 6.02E-02 1.58E+03 2.85£+02 Br-83 O.OOE+OO O.OOE+OO 3.44E+02 0.00£+00 0.00£+00 0.00£+00 0.00£+00 Br-84 O.OOE+OO 0.00£+00 4.33£+02 0.00£+00 0.00£+00 0.00£+00 O.OOE+OO Br-85 0.00£+00 0.00£+00 1.83E+01 0.00£+00 O.OOE+OO 0.00£+00 0.00£+00 Rb-86 O.OOE+OO 1.90E+05 8.40E+04 0.00£+00 O.OOE+OO 0.00£+00 1.77E+04 Rb-88 O.OOE+OO 5.46E+02 2.72E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.92E-05 Rb-89 O.OOE+OO 3.52E+02 2.33E+02 O.OOE+OO O.OOE+OO 0.00£+00 3.38E-07 Sr-89 4.34E+05 O.OOE+OO 1.25E+04 O.OOE+OO O.OOE+OO 2.42E+06 3.71E+05 Sr-90 1.08E+08 O.OOE+OO 6.68E+06 O.OOE+OO O.OOE+OO 1.65E+07 7.65E+05 Sr-91 8.80E+01 O.OOE+OO 3.51E+00 0.00£+00 O.OOE+OO 6.07E+04 2.59£+05 Sr-92 9.52E+00 0.00£+00 4.06£-01 0.00£+00 O.OOE+OO 2.74E+04 1.19£+05 Y-90 2.98£+03 0.00£+00 8.00£+01 O.OOE+OO O.OOE+OO 2.93E+05 5.59E+05 Y-91m 3.70E-01 0.00£+00 1. *12£-02 O.OOE+OO O.OOE+OO 3.20E+03 3.02E+01 Y-91 6.61£+05 O.OOE+OO 1.77£+04 O.OOE+OO O.OOE+OO 2.94E+06 4.09£+05 Y-92 1.47£+01 O.OOE+OO 1.29E-01 O.OOE+OO O.OOE+O.O 2.68E+04 1.65£+05 Y-93 1. 35£+02 O.OOE+OO 3.72E+00 O.OOE+OO O.OOE+OO 8.32E+04 5.79E+05 Zr-95 1. 46E+05 4.58£+04 3.15E+04 O.OOE+OO 6.74E+04 2.69E+06 1.49E+05 Zr-97 1.38E+02 2.72E+01 1.26E+01 O.OOE+OO 4.12E+Ol 1.30E+05 6.30E+05 Nb-95 1.86E+04 1. 03E+01 5.66E+03 O.OOE+OO 1.00E+04 7.51E+05 9.68E+04 No-99 O.OOE+OO 1.69E+02 3.22E+Ol O.OOE+OO 4.11E+02 1.54£+05 2.69£+05 Tc-99m 1.38E-03 3.86£-03 4.99E-02 O.OOE+OO 5.76E-02 1.15E+03 6.13£+03 Tc-101 5.92E-05 8.40E-05 8.24E-04 0.00£+00 1.52E-03 6.67E+02 8: 72£-07 Ru-103 .2.10E+03 0.00£+00 8.96E+02 O.OOE+OO 7.43£+03 7.83E+05 1.09£+05 Ru-105 1.12£+00 0.00£+00 4.34£-01 0.00£+00 1.41E+00 1.82£+04 9.04E+04 Ru-106 9.84E+04 0.00£+00 1.24£+04 0.00£+00 1.90E+05 1.6lS+07 9.60E+05 Ag-110m 1. 38E+01 1.31£+04 7.99E+03 O.OOE+OO 2.50E+04 6.75E+06 2.73E+05 Sb-122 O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO 0.00£+00 0.00£+00 Sb-124 4.30E+04 7.94£+02 1.62E+04 9.76E+01 O.OOE+OO 3.85E+06 3.98E+05 Sb-125 7.38£+04 8.08£+02 1.72E+04 7.04E+01 0.00£+00 2.74E+06 9.92E+04 Indian Point 2 Page 55 Revision 10

aDCM Part II - Calculational Methodologies _

Table 2-10b 3

TEEN INHALATION Ri(I) (mrerrl/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.00£+00 5.36£+05 7.50E+04 Te-127m 1.80E+04 8.16£+03 2.18E+03 4.38E+03 6.54E+04 1. 66E+06 1. 59E+05 Te-127 2.01E+-OO 9.12E-01 4.42E-01 1.42E+-00 7.28E+-00 1. 12E+04 8.08E+04 Te-129m 1. 39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 Te-129 7.10E-02 3.38E-02 1.76E-02 5.18E-02 2.66E-01 3.30E+03 1.62E+03 Te-131m 9.84E+01 6.01E+01 4.02E+-01 7.25E+01 4.39E+02 2.38E+05 6.21E+05 Te-131 1.58E-02 8.32E-03 5.04E-03 1.24E-02 6.18E-02 2.34E+03 1. 51E+-01 Te-132 3.60E+02 2.90E+02 2.19E+-02 2.46E+02 1.95E+03 4.49E+05 4.63E+05 1-130 6.24E+03 1. 79E+04 7.17E+03 1. 49E+06 2.75E+04 O.OOE+OO 9.12E+03 1-131 3.54E+-04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 O.OOE+OO 6.49E+03 1-132 1.59E+03 4.38E+03 1.58E+03 1.51E+05 6.92E+03 O.OOE+OO 1. 27E+03 1-133 1. 22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 O.OOE+OO 1:03E+04 1-134 8.88E+02 2.32E+03 8.40E+02 3.95E+04 3.66E+03 O.OOE+OO 2.04E+01 1-135 3.70E+03 9.44E+03 3.49E+03 6.21E+05 1.49E+04 O.OOE+OO 6.95E+03 Cs-134 5.02E+05 1. 13E+06 5.49E+05 O.OOE+OO 3.75E+05 1.46E+05 9.76E+03 Cs-136 5.15E+04 1.94E+05 1.37E+05 O.OOE+OO 1.10E+05 1.78E+04 1.09E+04 Cs-137 6.70E+05 8.48E+05 3.11E+05 O.OOE+OO 3.04E+05 1.21E+05 8.48E+03 Cs-138 4.66E+02 8.56E+02 4.46E+02 O.OOE+OO 6.62E+02 7.87E+01 2.70E-01 Ba-139 1.34E+00 9.44E-04 3.90E-02 O.OOE+OO 8.88E-04 6.46E+03 6.45E+03 Ba-140 5.47E+04 6.70E+Ol 3.52E+03 O.OOE+OO 2.28E+Ol 2.03E+06 2.29E+05 Ba-141 1.42E-01 1. 06E-04 4.74E-03 O.OOE+OO 9.84E-05 3.29E+03 7.46E-04 Ba-142 3.70E-02 3.70E-05 2.27E-03 O.OOE+OO 3.14E-05 1.91E+03 4.79E-10 La-140 4.79E+02 2.36E+02 6:26E+01 O.OOE+OO. O.OOE+OO 2.14E+05 4.87E+05 La-142 9.60E-Ol 4.25E-01 1.06E-Ol O.OOE+OO O.OOE+OO 1.02E+04 1.20E+04 Ce-141 2.84E+04 1.90E+04 2.17E+03 O.OOE+OO 8.88E+03 6.14E+05 1.26E+05 Ce-143 2.66E+02 1.94E+02 2.16E+Ol O.OOE+OO 8.61E+01 1.30E+05 2.55E+05 Ce-144 4.89E+06 2.02E+06 2.62E+05 O.OOE+OO 1.2lE+06 1.34E+07 8.64E+05 Pr-143 1.34E+04 5.31E+03 6.62E+02 O.OOE+OO 3.09E+03 4.83E+05 2.14E+05 Pr-144 4.30£-02 1. 76E-02 2.18E-03 O.OOE+OO 1.01E-02 1.75E+03 2.35E-04 Nd-147 7.86E+03 8.56E+03 5.13E+02 O.OOE+OO 5.02E+03 3.72E+05 1.82E+05 W-187 1.20E+01 9.76E+00 3.43E+00 O.OOE+OO O.OOE+OO 4.74E+04 1.77E+05 Np-239 3.38£+02 3.19E+01 1.77E+01 O.OOE+OO 1.00E+02 6.49E+04 1.32E+05 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 9.44E-!-02 9.20E+02 O.OOE+OO O.OOE+OO 5.86E+05 3.14E+04 Sr-85 4.00E+04 O.OOE+OO 1.04E+04 O.OOE+OO O.OOE+OO 7.04£+05 5.52E+04 Y-88 O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 3.14E-01 7.78E-02 2.84E-02 O.OOE+OO 9.12E-02 3.93£+03 2.17E+03 Cd-lOg O.OOE+OO 8.00E+05 2.72E+04 O.OOE+OO 5.36E+05 1.28E+06 6.88E+04 Sn-1l3 1.20E+05 3.76E+03 7.76E+-03 2.32E+03 O.OOE+OO 1.60E+-06 1.20£+04 Ba-133 3.76E+05 6.40E+03 2.64E+04 O.OOE+OO 2.24E+Ol 2.32E+06 7.76E+04 Te-134 4.25£-02 3.48E-02 2.91£-02 3.57E-02 2.33E-01 5.40E+03 1.10E+Ol Ce-139 O.OOE+OO O.OOS+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 Hg-203 O.OOE+-OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 2 Page 56 Revision 10

aDCM Part II - Calculational Methodologies Table 2-10c 3

CHILD INHALATION  !<.i (I) (mrem!yr per uCi!m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLl H-3 O.OOE+OO 1.12E+03 1.12E+03 1.12£+03 1.12£+03 1.12E+03 1.12E+03 Be-7 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 1.618+04 1. 61E+04 1.61E+04 1.61E+04 1.61E+04 1. 61E+04 1.61E+04 P-32 2.60E+06 1.14E+05 9.88E+04 O.OOE+OO O.OOE+OO O.OOE+OO 4.22E+04 Cr-51 O.OOE+OO O.OOE+OO 1. 54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 Mn-54 O.OOE+OO 4.29E+04 9.51E+03 O.OOE+OO 1.00E+04 1. 58E+06 2.29E+04 tvln-56 O.OOE+OO 1. 66E+00 3.12E-01 O.OOE+OO 1.67E+00 1.31E+04 1.23E+05 Fe-55 4.74E+04 2.52E+04 7.77E+03 O.OOE+OO O.OOE+OO 1.11E+05 2.87E+03 Fe-59 2.07E+04 3.34E+04 1.67E+04 O.OOE+OO O.OOE+OO 1.27E+06 7.07E+04 Co-58 O.OOE+OO 1.77E+03 3.16E+03 O.OOE+OO O.OOE+OO 1. 11E+06 3.44E+04 Co-60 O.OOE+OO 1.31E+04 2.26E+04 O.OOE+OO O.OOE+OO 7.07E+06 9.62E+04 Ni-63 8.21E+05 4.63E+04 2.80E+04 O.OOE+OO O.OOE+OO 2.75E+05 6.33E+03 Ni-65 2.99E+00 2.96E-01 1.64E-01 O.OOE+OO O.OOE+OO 8.18E+03 8.40£+04 Cu-64 O.OOE+OO 1.99E+00 1.07E+00 O.OOE+OO 6.03E+00 9.58E+03 3.67E+04 Zn-65 4.26E+04 1. 13E+05 7.03E+04 O.OOE+OO 7.14E+04 9.95E+05 1.63E+04 Zn-69 6.70E-02 9.66E-02 8.92E-03 O.OOE+OO 5.85E-02 1. 42E+03 1.02E+04 Br-83 O.OOE+OO O.OOE+OO 4.74E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 5.48E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 2.53E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.98E+05 1. l4E+05 0.00£+00 O.OOE+OO O.OOE+OO 7.99E+03 Rb-88 O.OOE+OO 5.62E+02 3.66E+02 o .tOOE+OO O.OOE+OO O.OOE+OO 1. 72E+01 Rb-89 O.OOE+OO 3.45E+02 2.90E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.89E+00 Sr-89 5.99E+05 O.OOE+OO 1.72E+04 O.OOE+OO O.OOE+OO 2.16E+06 1.67E+05.

Sr-90 1.01E+08 O.OOE+OO 6.44E+06 O.OOE+OO O.OOE+OO 1.48E+07 3.43E+05 Sr-91 1.21E+02 O.OOE+OO 4.59E+00 O.OOE+OO O.OOE+OO 5.33E+04 1.74E+05 Sr-92 1. 31E+01 O.OOE+OO 5.2.5E-01 O.OOE+OO O:OOE+OO 2.40E+04 2.42E+05 Y-90 4.11E+03 O.OOE+OO 1.11E+02 O.OOE+OO O.OOE+OO 2.62E+05 2.68E+05 Y-91m 5.07£-01 O.OOE+OO 1.84E-02 O.OOE+OO O.OOE+OO 2.81E+03 1.72E+03 Y-91 9.14£+05 O.OOE+OO 2.44E+04 O.OOE+OO O.OOE+OO 2.63E+06 1.84E+05 Y-92 2.04E+01 O.OOE+OO 5.81E-01 O.OOE+OO O.OOE+OO 2.39E+04 2.39E+05 Y-93 1.86£+02 0.00£+00 5.11E+00 O.OOE+OO O.OOE+OO 7.44E+04 3.89E+05 Zr-95 1.90E+05 4.18E+04 3.70E+04 O.OOE+OO 5.96E+04 2.23E+06 6.11E+04 Zr-97 1.88E+02 2.72E+01 1. 60E+01 O.OOE+OO 3.88E+01 1.13E+05 3.51E+05 Nb-95 2.35E+04 9.18E+03 6.55E+03 O.OOE+OO 8.62E+03 6.14E+05 3.70E+04 tvlo-99 O.OOE+OO 1.72E+02 4.25E+01 0.00£+00 3.92E+02 1.35E+05 1.27E+05 Tc-99m 1.78E-03 3.48E-03 5.77E-02 O.OOE+OO 5.07E-02 9.51E+02 4.81E+03 Tc-101 8.10£-05 8.51E-05 1.08E-03 O.OOE+OO 1. 45E-03 5.85E+02 1.63E+01 Ru-103 2.79£+03 O.OOE+OO 1.07E+03 O.OOE+OO 7.03E+03 6.62E+05 4.48E+04 Ru-105 1.53E+00 O.OOE+OO 5.55E-01 O.OOE+OO 1.34E+00 1. 59E+04 9.95E+04 Ru-106 1.36E+05 O.OOE+OO 1.69E+04 O.OOE+OO 1.84E+05 1.43E+07 4.29E+05

.l\g-11 Om 1.*69E+04 1.14E+04 9.14E+03 O.OOE+OO 2.12E+01 5.48E+06 1.00£+05 Sb-122 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 5.74E+04 7.40E+02 2.00E+04 1.26E+02 O.OOE+OO 3.24E+06 1.64E+05 Sb-125 9.84E+04 7.59E+02 2.07£+04 9.10E+01 O.OOE+OO 2.32E+06 4.03E+04 Indian Point 2 Page 57 Revision 10

aDCM Part II - Calculational Methodologies Table 2-10c 3

CHILD INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLl Te-125m 6.73E+03 2.33E+03 9.14E+02 1.92E+03 O.OOE+OO 4.77E+05 3.38E+04 Te-127m 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36£+04 1.48£+06 7.14E+04 Te-127 2.77E+00 9.51E-01 6.10E-01 1.96E+00 7.07E+OO 1.00E+04 5.62E+04 Te-129m 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82£+05 Te-129 9.77E-02 3.50E-02 2.38E-02 7.14E-02 2.57E-01 2.93E+03 2.55E+04 Te-l31m 1.34E+02 5.92E+01 5.07E+01 9.77E+01 4.00E+02 2.06E+0.5 3.08E+05 Te-l31 2.17E-02 8.44E-03 6.59E-03 1.70E-02 5.88E-02 2.05E+03 1.33E+03 Te-l32 4.81E+02 2.72E+02 2.63E+02 3.17E+02 1.77E+03 3.77E+05 1.38E+05 I-130 8.18E+03 1.64E+04 8.44E+03 1. 85E+06 2.45E+04 O.OOE+OO 5.11E+03 I-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 O.OOE+OO 2.84E+03 I-132 2.12E+03 4.0n+03 1.88E+03 1.94E+05 6.25E+03 O.OOE+OO 3.20E+03 I-133 1.66£+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 O.OOE+OO 5.48E+03 I-134 1. 17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 O.OOE+OO 9.55E+02 I-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 O.OOE+OO 4.44E+03 Cs-l34 6.51E+05 1.01E+06 2.25E+05 O.OOE+OO 3.30E+05 1.21E+05 3.85E+03 Cs-l36 6.51E+04 1.71E+05 1. 16E+05 O.OOE+OO 9.55E+04 1.45E+04 4.18E+03 Cs-l37 9.07E+05 8.25E+05 1.28E+05 O.OOE+OO 2.82E+05 1.04E+05 3.62E+03 Cs-138 6.33E+02 8.40E+02 5.55E+02 O.OOE+OO 6.22E+02 6.81E+01 2.70E+02 Ba-l39 1.84E+00 9.84E-04 5.36E-02 O.OOE+OO 8.62E-04 5.77E+03 5.77E+04 Ba-140 7.40E+04 6.48E+01 4.33E+03 O.OOE+OO 2.11E+01 1.74E+06 1.02E+05 Ba-141 1. 96E-01 l.09E-04 6.36E-03 O.OOE+OO 9.47E-05 2.92E+03 2.75E+02 Ba-142 4.99E-02 3.60E-05 2.79E-03 O.OOE+OO 2.91E-05 1.64E+03 2.74E+00 La-l40 6.44E+02 2.25E+02 7.55E+01 O.OOE+OO O.OOE+OO 1.83E+05 2.26E+05 La-142 1.29E+00 4.11E-01 1.29E-01 O.OOE+OO O.OOE+OO 8.70E+03 7.59E+04 Ce-141 3.92E+04 1. 95E+04 2.90E+03 O.OOE+OO 8.55E+03 5.44E+05 5.66E+04 Ce-143 *3.66E+02 1.99E+02 2.87E+01 O.OOE+OO 8.36E+01 1.15E+05 1. 27E+05 Ce-144 6.77E+06 2.12E+06 3.61E+05 O.OOE+OO 1.17E+06 1. 20E+07 3.89E+05 Pr-l43 1.85E+04 5.55E+03 9.14E+02 O.OOE+OO 3.00E+03 4.33E+05 9.73E+04 Pr-144 5.96E-02 1.85E-02 3.00E-03 O.OOE+OO 9.77E-03 1.57E+03 1.97E+02 Nd-147 1.08E+04 8.73£+03 6.81E+02 O.OOE+OO 4.81E+03 3.28E+05 8.21E+04 W-187 1.63E+01 9.66E+00 4.33E+00 O.OOE+OO O.OOE+OO 4.11E+04 9.10E+04 Np-239 4.66E+02 3.31E+01 2.35E+01 0.00£+00 9.73E+01 5.81E+04 6.40E+04 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 9.03E+02 1.07E+03 O.OOE+OO O.OOE+OO 5.07E+05 l. 32E+04 Sr-85 4.44E+04 O.OOE+OO 1.18E+04 O.OOE+OO O.OOE+OO 5.55E+05 2.04E+04 Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 4.29E-01 7.70E-02 3.60E-02 O.OOE+OO 8.55E-02 3.42E+03 2.78E+04 Cd-l09 O.OOE+OO 7.03E+05 2.96E+04 O.OOE+OO 6.29E+05 l.l1E+06 3.00E+04 Sn-113 1.41E+05 3.29E+03 8.51E+03 2.63E+03 O.OOE+OO 1.33E+06 1.81E+03 Ba-l33 4.078+05 4.07E+03 3.70E+04 O.OOE+OO 2.00E+01 1.92E+06 3.07E+04 Te-l34 5.66E-02 3.26E-02 3.48E-02 4.59E-02 2.11E-01 4.55E+03 1.80E+03 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 2 Page 58 Revision 10

aDCM Part II - Calculational Methodologies Table 2-10d 3

INFANT INHALATION Ri(I) (mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 Be-7 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06£+04 1.06E+04 1.06E+04 P-32 2.03E+06 1.12E+05 7.74E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.61E+04 Cr-51 O.OOE+OO O.OOE+OO 8.95E+01 5.75E+01 1.32E+Ol 1. 28E+04 3.57E+02 Mn-54 O.OOE+OO 2.53E+04 4.98E+03 O.OOE+OO 4.98E+03 1.00E+06 7.06E+03 t1n-56 O.OOE+OO 1.54E+00 2.21E-Ol O.OOE+OO 1.10E+00 1. 25E+04 7.17£+04 Fe-55 1. 97E+04 1.17E+04 3.33E+03 O.OOE+OO O.OOE+OO 8.69E+04 1.09E+03 Fe-59 1. 36E+04 2.35E+04 9.48E+03 O.OOE+OO O.OOE+OO 1.02E+06 2.48E+04 Co-58 O.OOE+OO 1.22E+03 1.82E+03 O.OOE+OO O.OOE+OO 7.77E+05 1.11E+04 Co-60 O.OOE+OO 8.02E+03 1.18E+04 O.OOE+OO O.OOE+OO 4.51E+06 3.1%+.04 Ni-63 3.39E+05 2.04E+04 1.16E+04 O.OOE+OO O.OOE+OO 2.09E+05 2.42E+03 Ni-65 2.39E+00 2.84E-Ol 1.23E-Ol O.OOE+OO 0.00E+60 8.12E+03 5.01E+04 eu-64 O.OOE+OO 1. 88E+00 7.74E-01 O.OOE+OO 3.98E+00 9.30E+03 1. 50E+04 Zn-.65 1.93E+04 6.26E+04 3.11E+04 O.OOE+OO 3.25E+04 6.47E+05 5.14E+04 Zn-69 5.39E-02 9.67E-02 7.18E-03 O.OOE+OO 4.02E-02 1. 47E+03 1.32E+04 Br-83 O.OOE+OO O.OOE+OO 3.81E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 4.00E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 2.04E+Ol O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.90E+05 8.82E+04 O.OOE+OO O.OOE+OO O.OOE+OO 3.04E+03 Rb-88 O.OOE+OO 5.57E+02 2.87E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.39E+02 Rb-89 O.OOE+OO 3.21E+02 2.06E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.82E+01 Sr-89 3.98E+05 O.OOE+OO 1.14E+04 O.OOE+OO O.OOE+OO 2.03E+06 6.40E+04 Sr-90 4.09E+07 O.OOE+OO 2.59E+06 O.OOE+OO O.OOE+OO 1.12E+07 1.31E+05 Sr-91 9.56E+01 O.OOE+OO 3.46E+00 O.OOE+OO O.OOE+OO 5.26E+04 7.34E+04 Sr-92 1.05E+Ol O.OOE+OO 3.91E-01 O.OOE+OO O.OOE+OO 2.38E+04 1.40E+05

• Y-90 3.29E+03 O.OOE+OO 8.82E+01 O.OOE+OO O.OOE+OO 2.69E+05 1.04E+05 Y-91m 4.07E-Ol O.OOE+OO 1. 39E-02 O.OOE+OO O.OOE+OO 2.79E+03 2.35E+03 Y-91 5.88E+05 O.OOE+OO 1.57E+04 O.OOE+OO O.OOE+OO 2.45E+06 7.03E+04 Y-92 1.64E+01 O.OOE+OO 4.61E-01 O.OOE+OO O.OOE+OO 2.45E+04 1.27E+05 Y-93 1.50E+02 O.OOE+OO 4.07E+00 O.OOE+OO O.OOE+OO 7.64£+04 1.67E+05 Zr-95 1.15E+05 2.79E+04 2.03E+04 0.00£+00 3.11E+04 1.75E+06 2.17E+04 Zr-97 1.50E+02 2.56E+Ol 1.17E+Ol O.OOE+OO 2.59E+01 1.10E+05 1. 40E+05 Nb-95 1.57E+04 6.43E+03 3.78E+03 O.OOE+OO 4.72E+03 4.79E+05 1.27E+04 Mo-99 O.OOE+OO 1.65E+02 3.23E+Ol O.OOE+OO 2.65E+02 1.35E+05 4.87E+04 Tc-99m 1. 40E-03 2.88E-03 3.72E-02 0.00£+00 3.11£-02 8.11E+02 2.03£+03 Tc-l0l 6.51E-05 8.23£-05 8.12E-04 O.OOE+OO 9.79E-04 5.84£+02 8.44E+02 Ru-l03 2.02£+03 O.OOE+OO 6.79E+02 O.OOE+OO 4.24E+03 5.52E+05 1. 61E+04 Ru-105 1:22E+00 0.00£+00 4.10E-Ol O*.OOE+OO 8.99E-01 1.57E+04 4.84E+04 Ru.-106 8.68E+04 O.OOE+OO 1.09E+04 O.OOE+OO 1.07E+05 1.16E+07 1.64E+05 Ag-llOm 9.98E+03 7.22E+03 5.00E+03 O.OOE+OO 1.09E+04 3.67E+06 3.30E+04 Sb-122 O*.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO Sb-124 3.79£+04 5.56E+02 1.20E+04 1.01E+02 O.OOE+OO 2.65E+06 5.91E+04 Sb-125 5.17E+04 4.77E+02 1.09E+04 6.23£+01 O.OOE+OO 1. 64E+06 1.47E+04 Indian Point 2 . Page 59 Revision 10

aDCM Part II - Calculational Methodologies Table 2-10d 3

INFANT INHp.LATION Ri(I) (mrem!yr per uCi/m )

Isotope BON£ LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 4.76£+03 1.99E+03 6.58E+02 1.62E+03 O.OOE+OO 4.47E+05 1.29£+04 Te-127m 1.67E+04 6.90£+03 2.07E+03 4.87E+03 3.75£+04 1.31E+06 2.73E+04 Te-l27 2.23E+04 9.53E-Ol 1.89E-Ol 1. 85£+00 4.86£+00 1.03£+04 2.44E+04 Te-129m 1.41E+04 6.09;:;+03 2.23E+03 5.47E+03 3.18£+04 1.68E+06 6.90E+04 Te-129 7.88£-02 3.47E-02 1.88E-02 6.75;:;-02 1.75£-01 3.00£+03 2.63E+04 Te-131m 1.07E+02 5.50E+01 3.63£+01 8.93E+01 2.65E+02 1.99£+05 1.19£+05 Te-131 1.74£-02 8.22£-03 5.00£-03 1.58£-02 3.99E-02 2.06E+03 8.22E+03 Te-132 3.72£+02 2.37£+02 1.76E+02 2.79E+02 1.03E+03 3.40E+05 4.41E+04 1-130 6.36E+03 1.39E+04 5.57E+03 1.60E+06 1.53E+04 0.00£+00 1.99E+03 1-131 3.79£+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.00£+00 1.06E+03 1-132 1.69£+03 3.54£+03 1.26£+03 1.69E+05 3.95E+03 0.00£+00 1.90£+03 1-133 1. 32£+04 1.92E+04 5.60£+03 3.56£+06 2.24E+04 O.OOE+OO 2.16E+03 1-134 9.21E+02 1.88£+03 6.65E+02 4.45£+04 2.09£+03 0.00£+00 1. 29E+03 1-135 3.86E+03 7.60E+03 2.77E+03 6.96E+05 8.47£+03 O.OOE+OO 1.83E+03 Cs-134 3.96E+05 7.03£+05 7.45E+04 O.OOE+OO 1.90E+05 7.97E+04 1.33E+03 Cs-136 4.83E+04 1.35E+05 5.29£+04 O.OOE+OO 5.64E+04 1.18£+04 1. 43E+03 Cs-137 5.49E+05 6.12E+05 4.55E+04 O.OOE+OO 1.72£+05 7.13£+04 1.33E+03 Cs-138 5.05E+02 7.81E+02 3.98E+02 O.OOE+OO 4.10E+02 6.54E+01 8.76E+02 Ba-139 1.48E+00 9.84£-04 4.30E-02 O.OOE+OO 5.92E-04 5.95E+03 5.10E+04 Ba-140 5.60E+04 5.60E+01 2.90E+03 O.OOE+OO 1.34£+01 1.60E+06 3.84£+04 Ba-l41 1.57£-01 1.08£-04 4.97E-03 0.00£+00 6.50£-05 2.97£+03 4.75£+03 Ba-142 3.98£-02 3.30E-05 1.96£-03 O.OOE+OO 1.90E-05 1.55£+03 6.93£+02 La-l40 5.05E+02 2.00E+02 5.15E+Ol O.OOE+OO O.OOE+OO 1.68£+05 8.48E+04 La-142 1.03E+00 3.77£-01 9.04E-02 O.OOE+OO O.OOE+OO 8.22E+03 5.95E+04 Ce-l41 2.77E+04 1.67E+04 1.99E+03 O.OOE+OO 5.25£+03 5.17£+05 2.16E+04 Ce-143 2.93£+02 1.93£+02 2.21£+01 0.00£+00 5.64E+Ol 1.16E+05 4.97E+04 Ce-l44 3.19£+06 1.21£+06 1.76E+05 O.OOE+OO 5.38E+05 9.84E+06 1.48E+05 Pr-143 1.40£+04 5.24E+03 6.99£+02 0.00£+00 1.97£+03 4.33E+05 3.72E+04 Pr-144 4.79E-02 1.85E-02 2.41E-03 O.OOE+OO 6.72E-03 1.61E+03 4.28E+03 Nd-147 7.94E+03 8.13E+03 5.00E+02 O.OOE+OO 3.15E+03 3.22E+05 3.12E+04 W:"'187 1.30E+01 9.02E+00 3.12E+00 O.OOE+OO O.OOE+OO 3.96E+04 3.56E+04 Np-239 3.71£+02 3.32E+01 1.88E+01 O.OOE+OO 6.62E+Ol 5.95E+04 2.49E+04 K-40 O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 6.51E+02 6.41E+02 O.OOE+OO O.OOE+OO 3.79E+05 4.86E+03 Sr-85 3.78E+04 O.OOE+OO 7.56E+03 O.OOE+OO O.OOE+OO 4.20E+05 6.72E+03 Y-88 0.00£+00 O.OOE+OO 0.00£+00 0.00£+00 0.00£+00 O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO 0.00£+00 0.00£+00 Nb-97 3.42E-01 7.29E-02 2.63E-02 0.00£+00 5.70E-02 3.32E+03 2.69E+04 Cd-109 O.OOE+OO 3.64E+05 1. 40£+04 O.OOE+OO 2.80£+05 8.68£+05 1.12£+04 Sn-113 8.40E+04 2.24E+03 5.04E+03 1.82£+03 O.OOE+OO 1.09E+06 1.68E+03 Sa-133 2.66E+05 2.38E+03 1.82E+04 O.OOE+OO 1.25E+01 1. 27E+06 1.08E+04 Te-134 4.45E-02 2.86E-02 2.35E-02 4.07E-02 1.34E-01 4.10E+03 3.54E+03 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO 0.00£+00 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 2 Page 60 Revision 10

aDCM Part II - Calculational Methodologies Table 2-11a

.J;DULT INGESTION (Leafy Vegetable) Ri(V) 2 3 m

• mrem/yr per uCi/sec (H-3: mrem/yr per uCi/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI H-3 O.OOE+OO 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 Be-7 9.36E+04 2.11£+05 1.05£+05 O.OOE+OO 2.22E+05 O.OOE+OO 3.65E+07 Na-24 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 P-32 1.40E+09 8.73E+07 5.43E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.58E+08 Cr-5l O.OOE+OO O.OOE+OO 4.64E+04 2.78E+04 1.02E+04 6.16E+04 1.17E+07 Mn-54 O.OOE+OO 3.13E+08 5.97E+07 O.OOE+OO 9.31E+07 O.OOE+OO 9.58E+08.

~1n-56 O.OOE+OO 1.59E+01 2.82E+00 O.OOE+OO 2.02E+01 O.OOE+OO 5.07E+02 Fe-55 2.10E+08 1.45E+08 3.38E+07 O.OOE+OO O.OOE+OO 8.08E+07 8.31E+07 Fe-59 1.26E+08 2.96E+08 1.13E+08 O.OOE+OO O.OOE+OO 8.27E+07 9.86E+08 Co-58 O.OOE+OO 3.07E+07 6.89E+07 O.OOE+OO O.OOE+OO O.OOE+OO 6.23E+08 Co-60 O.OOE+OO 1.67E+08 3.69E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.14E+09 Ni-63 1. 04E+10 7.21E+08 3.49E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.50E+08 Ni-65 6.15E+Ol 7.99E+00 3.64E+00 O.OOE+OO O.OOE+OO O.OOE+OO 2.03E+02 Cu-64 O.OOE+OO 9.20E+03 4.32E+03 O.OOE+OO 2.32E+04 O.OOE+OO 7.84E+05 Zn-65 3.17E+08 1.01E+09 4.56E+08 O.OOE+OO 6.75£+08 O.OOE+OO 6.36E+08 Zn-69 8.73E-06 1.67E-05 1.16E-06 O.OOE+OO 1.09E-05 O.OOE+OO 2.51E-06 Br-83 O.OOE+OO O.OOE+OO 3.11E+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.47E+00 Br-84 O.OOE+OO O.OOE+OO 2.48E-11 O.OOE+OO O.OOE+OO O.OOE+OO 1. 94E-16 Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.19E+08 1.02E+08 O.OOE+OO O.OOE+OO O.OOE+OO 4.33E+07 Rb-88 O.OOE+OO 3.43E-22 1.82E-22 O.OOE+OO O.OOE+OO O.OOE+OO 4.74E-33 Rb-89 O.OOE+OO 1. 39E-26 9.74E-27 O.OOE+OO O.OOE+OO O.OOE+OO 8.05E-40 Sr-89 9.96E+09 O.OOE+OO 2.86E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.60E+09 Sr-90 6.05E+11 O.OOE+OO 1.48E+11 O.OOE+OO O.OOE+OO O.OOE+OO 1. 75E+I0 Sr-91 3.05E+05 O.OOE+OO 1. 23E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1. 45E+06 Sr-92 4.27E+02 O.OOE+OO 1.85E+01 O.OOE+OO O.OOE+OO O.OOE+OO 8.45E+03 Y-90 1.33E+04 O.OOE+OO 3.56E+02 O.OOE+OO O.OOE+OO O.OOE+OO* 1.41E+08 Y-91m 5.22E-09 O.OOE+OO 2.02E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1. 53E-08 Y-91 5.11E+06 O.OOE+OO 1.37E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.81E+09 Y-92 9.15E-Ol O.OOE+OO 2.68;<;-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.60E+04 Y-93 1.70E+02 O.OOE+OO 4.68£+00 O.OOE+OO O.OOE+OO O.OOE+OO 5.38E+06 Zr-95 1.17E+06 3.77E+05 2.55£+05 O.OOE+OO 5.91E+05 O.OOE+OO 1.19E+09 Zr-97 3.37E+02 6.81E+Ol 3.11E+01 O.OOE+OO 1.03E+02 O.OOE+OO 2.11E+07 Nb-95 1.43£+05 7.94E+04 4.27E+04 O.OOE+OO 7.85E+04 O.OOE+OO 4.82E+08 Mo-99 O.OOE+OO 6.15E+06 1. 17E+06 O.OOE+OO 1.39E+07 O.OOE+OO 1.43E+07 Tc-99m 3.10E+00 8.77E+00 1.12E+02 O.OOE+OO 1.33E+02 4.30E+00 5.19E+03 Tc-101 8.22E-31 1. 18E-30 1. 16E-29 O.OOE+OO 2.13E-29 6.05E-31 3.56E-42 Ru-103 4.76E+06 O.OOE+OO 2.05E+06 O.OOE+OO 1.82E+07 O.OOE+OO 5.56E+08 Ru-l05 5.39£+01 O.OOE+OO 2.13E+Ol O.OOE+OO 6.96E+02 O.OOE+OO 3.29E+04 Ru-l06 1.93E+08 O.OOE+OO 2.44E+07 O.OOE+OO 3.72E+08 O.OOE+OO 1.25E+10 l\.g-llOm 1.05E+07 9.75E+06 5.79E+06 O.OOE+OO 1.92E+07 0.00£+00 3.98E+09 Sb-122 2.80E+05 6.43E+03 9.65E+04 4.34E+03 O.OOE+OO 1.68E+05 1.06E+08 Sb-124 1.04E+08 1. 96E+06 4.07E+07 2.52E+05 O.OOE+OO 8.07E+07 2.94E+09 5b-125 1.37E+08 1. 53E+06 3.25E+07 1.39E+05 O.OOE+OO 1.05E+08 1.50E+09 Indian Point 2 Page 61 Revision 10

aDCM Part /I - Calculational Methodologies Table 2-11a ADULT INGESTION (Le'afy Vegetable ). Ri(V) 2 3 m

• mrem/yr per uCi/sec (H-3: mrem/yr per uCi/m Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 O.OOE+OO 3.86£+08 Te-127m 3.49E+08 1.25E+08 4.26E+07 8.92E+07 1.42£+09 O.OOE+OO 1. 17£+09 Te-l27 5.66E+03 2.03E+03 1.22E+03 4.19E+03 2.31E+04 O.OOE+OO 4.47£+05 Te-129m ' 2. 51E+08 9.38E+07 3.98£+07 8.63E+07 1. 05E+09 O.OOE+OO 1.27£+09 Te-129 7.62E-04 2.87E-04 1.86E-04 5.'85E-04 3~20E-03 O.OOE+OO 5.75E-04 Te-131m 9.12E+05 4.46E+05 3.72E+05 7.06E+05 4.52E+06 O.OOE+OO 4.43E+07 Te-131 1. 50E-15 6.27E-16 4.74E-16 1.23E-15 6.57E-15 O.OOE+OO 2.13E-16 Te-132 4.30E+06 2.78E+06 2.61E+06 3.07E+06 2,.68E+07 O.OOE+OO 1.32E+08 I-130 3.92E+05 1.16E+06 4.57E+05 9.81E+07 1.81E+06 O.OOE+OO 9.96E+05 I-131 8.08E+07 1.16£+08 6.62E+07 3:79E+10 1.98£+08 O.OOE+OO 3.05E+07 I-132 5.76E+01 1.54E+02 5.39E+01 5.39E+03 2.45E+02 O.OOE+OO 2.89E+01 I-133 2.09E+06 3.63E+06 1.11E+06 5.33E+08 6.33E+06 O.OOE+OO 3.26£+06 I-134 9.65E-05 2.62E-04 9.38E-05 4.54E-03 4.17£-04 O.OOE+OO 2.29E-07 I-135 3.90E+04 1.02E+05 3.77E+04 6.,73E+06 1. 64E+05 O.OOE+OO 1.15£+05 Cs-134 4.67E+09 1. l1E+10 9.08E+09 O.OOE+OO 3.59E+09 1.19E+09 1.94E+08 Cs-136 4.24E+07 1.68E+08 1.21E+08 O.OOE+OO 9.32E+07 1.28E+07 1.90E+07 Cs-137 6.36E+09 8.70E+09 5.70E+09 O.OOE+OO 2.95E+09 9.81E+08 1.68E+08 Cs-138 .3.91E-11 7.73E-11 3.83E-11 O.OOE+OO 5.68E-11 5.61E-1'2 3.30E-16 Ba-139 2.68E-02 1.91E-05 7.86E-04 O.OOE+OO 1.79E-05 1.08E-05 4.76E-02 Ba-140 1.28E+08 1.61E+05 8.38E+06 O.OOE+OO 5.46E+04 9.20E+04 2.63E+08 Ba-141 1.15E-21 8.70E-25 3.89E-23 O.OOE+OO 8.09E-25 4;94E-25 5.43E-31 Ba-142 2.46E-39 2.53E-42 1. 55E-40 O.OOE+OO 2.14E-42 1. 43E-42 O.OOE+OO La-110 1.98E+03 9.98E+02 2.64E:,02 O.OOE+OO O.OOE+OO O.OOE+OO 7.33E+07 La-142 1.41E-04 6.43E-05 1.60E"-05 O.OOE+OO O.OOE+OO O.OOE+'OO 4.69E-01 Ce-141 1.97E+05 1.33E+05 1.51E+04 O.OOE+OO 6,'19E+04 O.OOE+OO 5.10E+08 Ce-143 9.98E+02 7.38E+05 8.16E+01 O.OOE+OO 3.25E+02 O.OOE+OO 2.76E+0.7 Ce-144 3.29E+07 1.38E+07 1.77E+06 O.OOE+OO 8.16E+06 O.OOE+OO 1.11E+10 Pr-143 6.26E+04 2.51E+04 3.10E+03 O.OOE+,OO ,1. 45E+04 O.OOE+OO 2.74E+08 Pr-144 3.09E-26 1.28E-26 1. 57E-27 O.OOE+OO 7.23E-27 O.OOE+OO 4.44E-33 Nd-147 3.33E+04 3.85E+04 2.31E+03 O.OOE+OO 2.25E+04 O.OOE+OO 1.85E+08 Vi-187 3.82E+04 3.19E+04 1.12E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1. 05E+07 Np-239 1.43E+03 1.41E+02 7.76E+01 O.OOE+OO 4.39E+02 O.OOE+OO 2.89E+07 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 1.17E+07 1.95E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.97E+08 Sr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 ' O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O'.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 2.15E-06 5.45E-07 1.99E-07 O.OOE+OO 6.35E-07 O.OOE+OO 2.01E-03 Cd-109 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 8n-113 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-134 3.56E-08 2.33E-08 1.43E-08 3.11E-08 2.25E-07 O.OOE+OO 3.95E-11 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 2 Page 62 Revision 10

aDCM Part II - Calculational Methodologies Table 2-11b TEEN INGESTION (Leafy Vegetable) Ri (V) 2 3 m

• mrem/yr per uCi/sec (H-3: mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI E-3 O.OOE+OO 2.59£+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 Be-7 1.43E+05 3.20E+05 1.60£+05 O.OOE+OO 3.39E+05 O.OOE+OO 3.90E+07 Na-24 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 P-32 1. 61E+09 9.97E+07 6.24E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.35E+08 Cr-51 O.OOE+OO O.OOE+OO 6.17E+04 3.43E+04 1.35E+04 8.81E+04 1.04£+07 Mn-54 O.OOE+OO 4.54E+08 9.01E+07 O.OOE+OO 1.36E+08 O.OOE+OO 9.32E+08 Mn-56 O.OOE+OO 1.43E+Ol 2.55E+00 O.OOE+OO 1.81E+Ol O.OOE+OO 9.44E+02 Fe-55 3.26E+08 2.31E+08 5.39E+07 O.OOE+OO O.OOE+OO 1. 47E+08 1.00E+08 Fe-59 1.79E+08 4.18E+08 1.61E+08 O.OOE+OO O.OOE+OO 1.32E+08 9.88E+08 Co-58 O.OOE+OO 4.36E+07 1.00E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.01E+08 Co-60 O.OOE+OO 2.49E+08 5.60E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.24E+09 Ni-63 1. 61E+10 1.13E+09 5.45E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.81E+08 Ni-65 5.72E+Ol 7.31E+00 3.33E+00 O.OOE+OO O.OOE+OO O.OOE+OO 3.97E+02 Cu-64 O.OOE+OO 8.34E+03 3.92E+03 O.OOE+OO 2.11E+04 O.OOE+OO 6.47E+05 Zn-65 4.24E+08 1.47E+09 6.86E+08 O.OOE+OO 9.42E+08 O.OOE+OO 6.23E+08 Zn-69 8.18E-06 1.56E-05 1.09E-06 O.OOE+OO 1.02E-05 O.OOE+OO 2.87E-05 Br-83 O.OOE+OO O.OOE+OO 2.91E+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 2.25E-11 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.74E+08 1.29E+08 *O.OOE+OO O.OOE+OO O.OOE+OO 4.05E+07 Rb-88 O.OOE+OO 3.17E-22 1.69E-22 O.OOE+OO O.OOE+OO O.OOE+OO 2.71E-29 Rb-89 O.OOE+OO 1.25E-26 8.82E-27 O.OOE+OO O.OOE+OO O.OOE+OO 1.91E-35 Sr-89 1. 51E+10 O.OOE+OO 4.33E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.80E+09 Sr-90 7.51E+11 O.OOE+OO 1.85E+11 O.OOE+OO O.OOE+OO O.OOE+OO 2.11E+I0 Sr-91 2.85E+05 O.OOE+OO 1. 13E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.29E+06 Sr-92 3.97£+02 O.OOE+OO 1.69E+01 O.OOE+OO ~.OOE+OO O.OOE+OO 1.01E+04 Y-90 1.24E+04 O.OOE+OO 3.34E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E+08 Y-91m 4.86E-09 O.OOE+OO 1.86E-I0 O.OOE+OO O.OOE+OO O.OOE+OO 2.29E-07 Y-91 7.84E+06 O.OOE+OO 2.10E+05 O.OOE+OO O.OOE+OO O.OOE+OO 3.21E+09 Y-92 8.60E-Ol O.OOE+OO 2.49E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.36E+04 Y-93 1.59E+02 O.OOE+OO 4.36E+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.86E+06 Zr-95 1. 72E+06 5.43E+05 3.73E+05 O.OOE+OO 7.98E+05 O.OOE+OO 1.25E+09 Zr-97 3.12E+02 6.18E+Ol 2.85E+01 O.OOE+OO 9.37E+Ol O.OOE+OO 1.67E+07 Nb-95 1.93E+05 1.07E+05 5.89E+04 O.OOE+OO 1.04E+05 O.OOE+OO 4.57E+08 Mo-99 O.OOE+OO 5.65E+06 1.08E+06 O.OOE+OO 1.29E+07 O.OOE+OO 1.0IE+07 Tc-99m 2.74E+00 7.63E+00 9.89E+Ol O.OOE+OO 1.14E+02 4.24E;+00 5.01E+03*

Tc-l01 7.64E-31 1.09E-30 1. 07E-29 O.OOE+OO 1. 97E-29 6.62E-31 1. 86E-37 Ru-l03 6.81E+06 O.OOE+OO 2.91E+06 O.OOE+OO 2.40E+07 O.OOE+OO 5.69E+08 Ru-105 5.00E+01 0.00£+00 1.94E+01 O.OOE+OO 6.31E+02 O.OOE+OO 4.04E+04 Ru-l06 3.10E+08 O.OOE+OO 3.90E+07 O.OOE+OO 5.97E+08 O.OOE+OO 1. 48E+10 Ag-llOm 1.52E+07 1.43E+07 8.72E+06 O.OOE+OO 2.74E+07 O.OOE+OO 4.03E+09 Sb-122 3.03£+05 5.89E+03 8.85E+04 3.85E+03 O.OOE+OO 1. 89E+05 6.35E+07 Sb-124 1. 54E+08 2.84E+06 6.02E+07 3.50E+05 O.OOE+OO 1.34E+08 3.11£+09 Sb-125 2.14E+08 2.34S+06 5.00E+07 2.04£+05 O.OOE+OO 1.86E+08 1.66E+09 Indian Point 2 Page 63 Revision 10

aDCM Part II - Calculational Methodologies Table 2-11b TEEN INGESTION (Leafy Vegetable) Ri(V) 2 3 m

• mrem/yr per uCi/sec (H-3: mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 1.48E+08 5.34E+07 1.98E+07 4.14E+07 O.OOE+OO O.OOE+OO 4.37E+08 Te-127m 5.51E+08 1.96£+08 6.56E+07 1.31E+08 2.24E+09 O.OOE+OO 1.37E+09 Te-127 5.34E+03 1.89E+03 1.15E+03 3.68E+03 2.16E+04 O.OOE+OO 4.12E+05 Te-129m 3.62E+08 1.34E+08 5.73E+07 1.17E+08 1.51E+09 O.OOE+OO 1.36E+09 Te-129 7.14E-04 2.66E-04 1.74E-04 5.10E-04 3.00E-03 O.OOE+OO 3.90E-03 Te-131m 8.44E+05 4.05E+05 3.38E+05 6.09E+05 4.22E+06 O.OOE+OO 3.25E+07 Te-131 1. 39E-15 5.75E-16 4.36E-16 1.07E-15 6.10E-15 O.OOE+OO 1.14E-16 Te-132 3.91E+06 2.47E+06 2.33E+06 2.61E+06 2.37E+07 O.OOE+OO 7.84E+07 1-130 3.51E+05 1. 01E+06 4.05E+05 8.28E+07 1.56E+06 O.OOE+OO 7.80E+05 1-131 7.69E+07 1.08E+08 5.78E+07 3.14E+10 1.85E+08 O.OOE+OO 2.13E+07 1-132 5.19E+01 1.36E+02 4.88E+01 4.58E+03 2.14E+02 O.OOE+OO 5.92E+01 1-133 1.94E+06 3.29E+06 1.00E+06 4.59E+08 5.76E+06 O.OOE+OO 2.49E+06 I-134 8.73E-05 2.31E-04 8.31E-05 3.85E-03 3.65E-04 O.OOE+OO 3.05E-06 I-135 3.52E+04 9.07E+04 3.36E+04 5.83E+06 1.43E+05 O.OOE+OO 1.00E+05 Cs-134 7.10E+09 1.67E+10 7.75E+09 O.OOE+OO 5.31E+09 2.03E+09 2.08E+08 Cs-136 4.34E+07 1. 71E+08 1.15E+08 O.OOE+OO 9.30E+07 1.47E+07 1.37E+07 Cs-137 1. 01E+10 1.35E+10 4.69E+09 O.OOE+OO 4.59E+09 1.78E+09 1.92E+08 Cs-138 3.61E-11 6.93E-11 3.47E-11 O.OOE+OO 5.12E-11 5.96E-12 3.15E-14 Ba-139 2.52E-02 1.78E-05 7.35E-04 O.OOE+OO 1. 67E-05 1.22E-05 2.25E-01 Ba-140 1. 37E+08 1.68E+05 8.85E+06 O.OOE+OO 5.70E+04 1.13E+05 2.12E+08 Ba-141 1.08E-21 8.04E-25 3.59E-23 O.OOE+OO .I.46E-25 5.50E-25 2.29E-27 Ba-142 2.27E-39 2.27E-42 1.40E-40 O.OOE+OO 1. 92E-42 1.51E-42 O.OOE+OO La-140 1.81E+03 8.89E+02 2.37E+02 O.OOE+OO O.OOE+OO O.OOE+OO 5.11E+07 La-142 1. 30E-04 5.76E-05 1.43E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.75E+00 Ce-141 2.83E+05 1.89E+05 2.17E+04 O.OOE+OO 8.89E+04 O.OOE+OO 5.40E+08 Ce-143 9.33E+02 6.79E+05 7.58E+01 O.OOE+OO 3.04E+02 O.OOE+OO 2.04E+07 Ce-144 5.27E+07 2.18E+07 2.83E+06 O.OOE+OO 1.30E+07 O.OOE+OO 1.33E+10 Pr-143 7.00E+04 2.80E+04 3.49E+03 O.OOE+OO 1.63E+04 O.OOE+OO 2.30E+08 Pr-144 2.89E-26 1.18E-26 1. ~ 7E-27 O.OOE+OO 6.80E-27 O.OOE+OO 3.19E-29 Nd-147 3.62E+04 3.94E+04 2.36E+03 O.OOE+OO 2.31E+04 O.OOE+OO 1.42E+08 Iv-1S7 3.55E+04 2.90E+04 1.02E+04 O.OOE+OO O.OOE+OO O.OOE+OO 7.84E+06 Np-239 1.39E+03 1.31E+02 7.28E+01 O.OOE+OO 4.11E+02 O.OOE+OO 2.11E+07 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 1.79E+07 3.00E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.33E+OS Sr-S5 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-8S O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 2.00E-06 4.95E-07 1.81E-07 O.OOE+OO 5.79E-07 O.OOE+OO 1.18E-02 Cd-109 O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO Sn-l13 O.OOE+OO O.OOE+OO O.OOE+OO 0.00£+00 O.OOE+OO O.OOE+OO O.OOE-'-'JO Ba-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-134 3.23E-08 2.07£-08 2.17£-08 2.65E-08 1.98E-07 O.OOE+OO 1.20E-09 Ce-IJ9 0.00£+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 2 Page 64 Revision 10

aDCM Part II - Calc'ulational Methodologies Table 2-11c CHILD INGESTION (Leafy Vegetable) Ri(lJ) 2 3 m

• mrem/yr per uCi/sec (H-3: mrem/yr per uCilm )

Isctope BONE LIVER TOT BODY THYROID KIDNEY LONG GILLI H-3 O.OOE+OO 4.01E+03 4.01E+03 4.01E+03 4.01£+03 1. 01E+03 4.01E+03 Be-.7 3.37E+05 5.72E+05 3.77E+05 O.OOE+OO 5.63E+05 O.OOE+OO 3.20E+07 Na-24 3.73E.+05 3.73£+05 3.73E+05 3.73£+05 3.73£+05 3.73E+05 3.73£+05 P-32 3.37£+09 1.58E+08 1.30E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.31E+07 Cr-51 O.OOE+OO 0.00£+00 1. 17E+05 6.50E+04 1.78E+04 1. 19E+05 6.21E+06 tvln-54 O.OOE+OO 6.65E+08 1. 77E+08 O.OOE+OO 1.86E+08 O.OOE+OO 5.58E+08 tvln-56 O.OOE+OO 1.88E+01 4.24E+00 O.OOE+OO 2.27E+01 O.OOE+OO 2.72E+03 Fe-55 8.01E+08 4.25E+08 1.32E+08 O.OOE+OO O.OOE+OO 2.40E+08 7.87E+07 Fe-59 3.97E+08 6.42E+08 3.20E+08 O.OOE+OO O.OOE+OO 1.86E+08 6.68E+08 Co-58 O.OOE+OO 6.44E+07 1.97E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.76E+08 Co-60 O.OOE+OO 3.78E+08 1.12E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+09 Ni-63 3.95E+I0 2.11E+09 1.34E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.42E+08 Ni-65 1.05E+02 9.89E+00 5.77E+00 O.OOE+OO O.OOE+OO O.OOE+OO 1.21E+03 Cu-64 O.OOE+OO 1.10E+04 6.64E+03 O.OOE+OO 2.66E+04 O.OOE+OO 5.16E+05 Zn-65 8.12E+08 2.16E+09 1.35E+09 O.OOE+OO 1.36E+09 O.OOE+OO 3.80E+08 Zn-69 1.51E-05 2.18E-05 2.02E-06 O.OOE+OO 1.32E-05 O.OOE+OO 1.37E-03 Br-83 O.OOE+OO O.OOE+OO. 5.37E+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 3.82E-11 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 4.52E+08 2.78E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.91E+07 Rb-88 O.OOE+OO 4.37E-22 3.04E-22 O.OOE+OO O.OOE+OO O.OOE+OO 2.15E-23 Rb-89 O.OOE+OO 1.64E-26 1. 46E-26 O.OOE+OO O.OOE+OO O.OOE+OO 1. 43E,..28 Sr-89 3.59E+10 O.OOE+OO 1.03E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E+09

.Sr-90 1.24E+12 O.OOE+OO 3. 15E+11 O.OOE+OO O.OOE+OO O.OOE+OO "1.67E+10 Sr-91 5.24E+05 O.OOE+OO 1. 98E+0 4 O.OOE+OO O.OOE+OO O.OOE+OO 1.16E+06 Sr-92 7.28E+02 O.OOE+OO 2.92E+01 O.OOE+OO O.OOE+OO O.OOE+OO. 1.38E+04 Y-90 2.30E+04 O.OOE+OO 6.17E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.56E+07 Y-91m 8.91E-09 O.OOE+OO 3.24E-I0 O.OOE+OO O.OOE+OO O.OOE+OO 1. 74E-05 Y-91 1. 86E+07 O.OOE+OO 4.99E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.48E+09 Y-92 1.58E+00 O.OOE+OO 4.53E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.58E+04 Y-93 2.93E+02 O.OOE+OO 8.04E+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.37E+06 Zr-95 3.86E+06 8.48E+05 7.55E+05 O.OOE+OO 1.21E+06 O.OOE+OO 8.84E+08 Zr-97 5.70E+02 8.24E+01 4.86E+01 O.OOE+.OO 1.18E+02 O.OOE+OO 1.25E+07 Nb-95 4.12E+05 1.60E+05 1.15E+05 O.OOE+OO 1.51E+05 O.OOE+OO 2.97E+08 Mo-99 O.OOE+OO 7.71E+06 1.91E+06 O.OOE+OO 1.65E+07 O.OOE+OO 6.38E+06

) Tc-99m 4.71E+00 9.24E+00 1.53E+02 O.OOE+OO 1.34E+02 4.69E+00 5.26E+03 Tc-101 1.41E-30 1. 47E-30 1.87E-29 O.OOE+OO 2.51E-29 7.78E-31 4.68E-30 Ru-103 1.53E+07 O.OOE+OO 5.88E+06 O.OOE+OO 3.85E+07 O.OOE+OO *3. 96E+08 Ru-l05 9.16E+Ol O.OOE+OO 3.32E+01 O.OOE+OO 8.05E+02 O.OOE+OO 5.98E+04 Ru-106 *7.45E+08 O.OOE+OO 9.30E+07 O.OOE+OO 1. 01E+09 O.OOE+OO 1. 16E+10 Ag-llOm 3.21E+07 2.17E+07 1.73E+07 O.OOE+OO 4.04E+07 O.OOE+OO 2.58E+09 Sb-122 5.58E+05 8.24E+03 1.64E+05 7.16£+03 O.OOE+OO 2.27E+05 4.30£+07 Sb-124 3.52E+08 4.56E+06 1.23E+08 7.73E+05 0.00£+00 1.95£+08 2.20E+09 Sb-125 4.99E+08 3.84E+06 1.05E+03 4.63E+05 O.OOE+OO 2.78E+08. 1.19E+09 Indian Point 2 Page 65 Revision 10

aDCM Part II - Calculational Meth~dologies Table 2-11c CHILD INGESTION (Leafy Vegetable) Ri (V) 2 3 m

• mrem/yr per uei/sec (H-3 : mrem/yr per uCi/m )

Isotope BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI Te-125m 3.51E+08 9.50E+07 4.67E+07 9.84E+07 O.OOE+OO O.OOE+OO 3.38E+08 Te-127m 1.32E+09 3.56E+08 1.57E+08 3.16£+08 3.77E+09 O.OOE+OO 1.07E+09 Te-127 9.85E+03 2.65E+03 2.11E+03 6.81E+03 2.80E+04 O.OOE+OO 3.85E+05 Te-129m 8.41E+08 2.35E+08 1.31E+08 2.71E+08 2.47E+09 O.OOE+OO 1.03E+09 Te-129 1.32E-03 3.69E-04 3.14E-04 9.43E-04 3.87E-03 O.OOE+OO 8.23£-02 Te-131m 1.54E+06 5.33E+05 5.68E+05 1.10E+06 5.16E+06 O.OOE+OO 2.16E+07 Te-131 2.57E-15 7.83E-16 7.64E-16 1.97E-15 7.77E-15 O.OOE+OO l.35E-14 Te-132 7.00E+06 3.10E+06 3.74E+06 4.51E+06 2.88E+07 O.OOE+OO 3.12E+07 1-130 6.16E+05 1.24E+06 6.41E+05 1.37E+OB l. 86E+06 O.OOE+OO 5.82E+05 1-131 l.43E+08 l.44E+08 8.17E+07 4.75E+10 2.36E+08 O.OOE+OO 1.28E+07 1-132 9.22E+01 1.69E+02 7.79E+Ol 7.86E+03 2.59E+02 O.OOE+OO 1.99E+02 1-133 3.53E+06 4.37E+06 1.65E+06 8.11E+08 7.2BE+06 O.OOE+OO 1. 76E+06 1-134 1.55E-04 2.88E-04 1.32E-04 6.62E-03 4.40E-04 O.OOE+OO 1.91E-04 I-US 6.26E+04 l.13E+05 5.33E+04 9.97E+06 1.73E+05 O.OOE+OO B.58E+04 Cs-134 1.60£+10 2.63E+10 5.55£+09 O.OOE+OO 8.15E+09 2.93E+09 1.42E+08 Cs-136 8.17E+07 2.25E+08 1.45E+08 O.OOE+OO 1.20E+08 1.78E+07 7.90E+06 Cs-137 2.39E+I0 2.29E+10 3.38E+09 O.OOE+OO 7.46E+09 2.68E+09 1.43E+08 Cs-138 6.57E-11 9.13E-ll 5.79E-11 O.OOE+OO 6.43E-11 6.91E-12 4.21E-11 Ba-139 4.65E-02 2.48E-05 1.35E-03 O.OOE+OO 2.17E-05 l. 46E-05 2.69E+00 Ba-140 2.75E+08 2.41E+05 1.60E+07 O.OOE+OO 7.84E+04 1.44E+05 1.39E+08 Ba-141 l.99E-21 1.11E-24 6.47E-23 O.OOE+OO 9.62E-25 6.53E-24 1. 13E-21 Ba-142 4.11E-39 2.96E-42 2.29E-40 O.OOE+OO 2.39E-42 l. 74E-42 5.36E-41 La-140 3.25E+03 1.14E+03 3.83E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.17E+07 La-142 2.35E-04 7.49E-05 2.35E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.48E+01 Ce-141 6.56E+05 3.27E+05 4.86E+04 O.OOE+OO 1.43E+05 O.OOE+OO 4.08E+08 Ce-143 1.72E+03 9.31E+05 1.35E+02 O.OOE+OO 3.91E+02 O.OOE+OO 1.36E+07 Ce-144 1.27E+08 3.98E+07 6.78E+06 O.OOE+OO 2.21E+07 O.OOE+OO 1.04E+10 Pr-143 1.46E+05 4.37E+04 7.23E+03 O.OOE+OO 2.37E+04 O.OOE+OO 1.57E+08 Pr-144 5.37E-26 1. 66E-26 2.70E-27 O.OOE+OO 8.79E-27 O.OOE+OO 3.58E-23 Nd-147 7.15E+04 5.79E+04 4.48E+03 O.OOE+OO 3.18E+04 O.OOE+OO 9.17E+07 W-187 6.47E+04 3.83E+04 1.72E+04 O.OOE+OO O.OOE+OO O.OOE+OO 5.38E+06 Np-239 2.57E+03 1 ..84E+02 1.29E+02 O.OOE+OO 5.33E+02 O.OOE+OO 1.36E+07 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-57 O.OOE+OO 2.99E+07 6.04E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.45E+08 Sr""'85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-97 3.64E-06 6.57E-07 3.07E-07 O.GOE+OO 7.29E-07 O.OOE+OO 2.03E-01 Cd-109 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sn-113 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+GO Ba-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-134 5.76E-08 2.59E-08 3.46E-08 4.56E-08 2.40E":07 O.OOE+OO 2.63E-07 Ce-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Hg-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Indian Point 2 Page 66 Revision 10

aDCM Part II - Calculational Methodologies Table 2-12 Total Body & Skin Ground Plane Dose Factors Ri(G) and Ri(S) 2 (m ~. mrem/Y,r per uCi/sec)

-1 Isotope Decay Constant (sec) Ri (G) Ri(S)

H-3 1.780E-09 O.OOE+OO O.OOE+OO Be.-7 1.505E-07 O.OOE+OO O.OOE+OO Na-24 1.284E-05 1.19£+07 1.39£+07 P-32 5.614£-07 O.OOE+OO O.OOE+OO Cr-51 2.896E-07 4.66E+06 5.51E+06 Mn-54 2.567E-08 1.39E+09 1.62E+09 t<1n-56 7.467E-05 9.03E+05 1.07E+06 Fe-55 8.141E-09 O.OOE+OO O.OOE+OO Fe-59 1.802E-07 2.72E+08 3.20E+08 Co-58 1.l33E-07 3.79E+08 4.44E+08 Co-60 4.170E-09 2.15E+10 2.53E+10 Ni-63 2.290E-10 O.OOE+OO O.OOE+OO Ni-65 7.641E,-05 2.97E+05 3.45E+05 Cu-64 1.516E-05 6.07E+05 6.88E+05 Zn-65 3.289E-08 7.46E+08 8.58E+08 Zn-69 2.027E-04 O.OOE+OO O.OOE+OO Br-83 8.056E-05 4.87E+03 7.08E+03 Br-84 3.633E-04 2.03E+05 2.36E+05 Br-85 3.851E-03 O.OOE+OO O.OOE+OO Rb-86 4.299E-07 8.99E+06 1.03E+07 Rb-88 6.490E-04 3.31E+04 3.781;:+04 Rb-89 7.600E-04 L 21E+05 1.45E+05 Sr-89 1.589E-07 2.16E+04 2.51E+04 Sr-90 7.548E-I0 O.OOE+OO O.OOE+OO Sr-91 2.027E-05 2.15E+06 2.51E+06 Sr-92 7.105E-05 7.77E+05 8.63E+05 Y-90 3.008E-06 4.48E+03 5.30E+03 Y-91m 2.324E-04 1.00E+05 1.16E+05 Y-91 1. 371E-07 1.07E+06 1.21E+06 Y-92 5.439E-05 1.80E+05 2.14E+05 Y-93 1.906E-05 1.83E+05 2.51E+05 Zr-95 1.254E-07 2.45E+08 2.84E+08 Zr-97 1.139E-05 2.96E+06 3.44E+06 Nb-95 2.282E-07 1.37E+08 1. 61E+08 Mo-99 2.917£-06 3. 99E-'-06 4.62E+06 Tc-99m 3.198£-05 1.84E+05 2.11E+05 Tc-lOl 8.136E-04 2.04£+04 2.26E+04

, Ru-lo.3 2.042E-07 1.08E+08 1.26E+08 Ru-l05 4.337S-05 6.36E+05 7.21E+05 Ru-l06 2.179£-08 4.22£+08 5.07£+08 Ag-llOm 3.210E-08 3.44E+09 4.01E+09 Sb-122 2.971E-06 O.OOE+OO 0.00£+00 Sb-124 1.333£-07 5.98E+08 6.90E+08 Sb-l25 7.935E-09 2.34E+09 2.64E+09 Indian Point 2 Page 67 Revision 10

ODCM Part II - Calculational Methodologies Table 2-12 Total Body & Skin. ~round Plane Dose Factors Ri(G) and Ri(S) 2 (m

• mrem/yr per uCi/sec)

-1 Isotope Decay Constant (sec) Ri(G) Ri(S)

Te-125m 1.383E-07 1.55E+06 2.13E+06 Te-127m 7.360E-08 9.16E+04 1.08E+05 Te-127 2.059E-05 2.98E+03 3.28E+03 Te-129m 2.388E-07 1.98E+07 2.31E+07 Te-129 1.660E-04 2.62E+04 3.10E+04 Te-131m 6.418E-06 8.03E+06 9.46E+06, Te-131 4.621E-04 2.92E+04 3.45E+07 Te-132 2.462E-06 4.23E+06 4.98E+06 1-130 1.558E-05 5.51E+06 6.69E+06 1-131 9.978£-07 1.72E+07 2.09E+07 1-132 8.371E-05 1.25£+06 1.46E+06 1-133 9.257E-06 2.45E+06 2.98E+06 1-134 2.196E-04 4.47E+05 5.30E+05 1-135 2.913£-05 2.53E+06 2.95£+.06 Cs-134 1.066£-08 6.86£+09 8.00£+09 Cs-136 6.124£-07 1.50£+08 1.70E+08 Cs-137 7.327E-10 1.03E+10 1. 20E+10 C5-138 3.588E-04 3.59£+05 4.10£+05 Ba-139 1.397E-04 1.05E+05 1.19E+05 Ba-140 6.297E-07 2.04E+07 2.34E+07 Ba-141 6.323E-04 4.17E+04 4.75E+04 Ba-142 1.090E-03 4.44E+04 5.06E+04 La-140 4.781E-06 1.92E+07 2.18E+07 La-l42 1. 24 9E-04 7.36E+05 8.84E+05 Ce-141 2.468E-07 1.37E+07 1.54E+07 Ce-143 5.835E-06 2.31E+06 2.63E+06 Ce-144 2.822E-08 6.95E+07 8.04E+07 Pr-143 5.916E-07 O.OOE+OO O.OOE+OO Pr-144 6.685E-04 1.83E+03 2.11E+03 Nd-147 7.306E-07 8.39E+06 1. 01E+07 W-187 8.056E-06 2.36E+06 2.74E+06 Np-239 3.399E-06 1.71E+06 1.98E+06 K-40 1.717E-17 O.OOE+OO O.OOE+OO Co-57 2.961E-08 1. 88E+08 2.07E+08 Sr-85 1.237E-07 O.OOE+OO O.OOE+OO Y-88 7.523£-08 O.OOE+OO O.OOE+OO Nb-94 1.083£-12 O.OOE+OO O.OOE+OO Nb-97 1.602£-04 1.76E+05 2.07E+05 Cd-l09 1.729E-08 O.OOE+OO 0.00£+00 8n-113 6.970E-08 0.00£+00 0.00£+00 Ba-l33 2.047£-09 O.OOE+OO O.OOE+OO Te-134 2.764E-04 2.22E+04 2.66E+04 Ce-1J9 5.828E-08 O.OOE+OO O.OOE+OO Hg-203 1. 722E-07 O.OOE+OO O.OOE+OO Indian Point 2 Page 68 Revision 10

aDCM Part II - Calculational Methodologies

\.

3.0 TOTAL DOSE DETERMINATIONS 3.1 10CFR 190 Dose Evaluation RECS require that the impact of uranium fuel cycle activities be limited to 25 mrem to the whole body or any organ and 75 mrem to the thyroid of real identifiable individual in any twelve month period. Direct radiation effects are added to the effects of liquid and gaseous effluents. NUREG-133 section 3.8 may be used to show compliance. Site and environmental TLD results may be incorporated along with projected doses to show compliance. Per RECS Section 4 (bases) and the discussion regarding gaseous effluent dose rate, visiting MEMBERS OF THE PUBLIC will receive negligible dose, as calculated per ODCM Part II, Sections 2.5, 2.6, and 2.7, due the application of multiplicative occupancy factors. These factors are determined by comparing the expected hours on site to 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> (the number of hours in a year, which is used in the calculations demonstrated in 2.5, 2.6, 2.7. Examples of these calculations are as follows:

example 1: Several students visit the site for an 8-hour guided tour.

Their occupancy factor is: 8 / 8760 or .0009.

example 2: A man drives his wife to work and drops her off at the security gate each morning, with a total stay-time on site for 2 minutes per day. His occupancy factor is calculated as follows:

2 min/60 min per hour =.0333 hr; 0.0333 / 8760 = 3.8E-6 These factors, when multiplied by doses calculated per Sections 2.5 through 2.7, demonstrate that dose to these MEMBERS OF THE PUBLIC is negligible, despite any potential reduction in the atmospheric dispersion.

3.2 Doses From Liquid Releases If doses for real individuals are desired, the same calculational method for cumulative liquid dose can be used. However, more realistic assumptions regarding dilution, diet and occupancy can be employed. Actual levels of radionuclides in consumed foodstuffs, as shown in the Radiological Environmental Monitoring Program (REMP), can provide more meaningful information, in lieu of projected intakes using models only.

3:3 Doses From Atmospheric Releases Similarly, real individual methodology can be substituted for maximum individual modeling for airborne releases. Specific dose transfer factors can be used in lieu of weighted dose transfer factors. Information on the location and occupancy of real individuals, as well as more precise meteorological information and the consumption of foodstuffs, can be employed to show actual doses.

Data from the land use census can be used to either extend times from food production to consumption or otherwise show that the exposure of the critical receptors is reduced.

Also, estimates of direct exposure through calculation may be supplanted by REMP results since these are often more indicative of the true impact at specific locations.

Default values used in NUREG-0133 and Reg Guide 1.109 methodology can be supplanted by more specific values.

Indian Point 2 Page 69 Revision 10

aDCM Part II - Calculational Methodologies 4.0. SETPOINT CALCULATIONS The RECS require alarm/trip setpoints for effluent monitors. Setpoints assure that alarm and trip actions occur such that limits of 10CFR20 at the release point in the unrestricted area are not instantaneously exceeded.

4.1 Liquid Effluent Monitor Setpoints 4.1.1 Liquid Effluent Monitors have setpoints based on limiting the concentrations in the discharge canal to the MPCW identified in RECS 01.1 Monitor setpoints are inherently conservative due to the routine use of Circulating Water Pumps for liquid waste releases, and Service Water for continuous releases. In actuality, both Circulating and Service Water systems contribute to site dilution.

Alarm setpoints are calculated as follows:

S = [(ADC) (F)]/[f] =Maximum alarm setpoint in uCi/rnl where:

F = Available discharge canal dilution flow for this release *in gal/min f = calculated allowable release rate in gal/min ADC = Allowed Diluted Concentration is the equivalent MPCW for gamma emitting isotopes weighted for total specific activity (beta and gamma emitters). This gamma equivalent MPCW (or ADC) must be used due to the insensitivity of the radiation monitor to beta emitters and the time necessary to analyze liquid releases for these beta emitters. This parameter is further clarified in Attachment E.

4.1.2 The basis for the WARN setpoint for Liquid Waste Effluent monitors (batch releases) is to ensure the contents of the batch tank have not changed since sampling. The warn setpoint for this type of monitor is calculated as follows:

WS = (C) * (M) where:

WS = Warn setpoint in uCi/ml C = Average monitor reading at time of sample M = A conservative factor based upon the mixing ratio of two tank volumes and an expected monitor response error term (typically 1.25, coinciding with 25%).

Liquid Effluent Radiation Monitor WARN setpoints do not control any auto functions but simply provide indication to operators. WARN setpoints for other monitors are typically set at approximately 75% of the ALARM value.

Indian Point 2 Page 70 Revision 10

aDCM Part" - Calculational Methodologies 4.1.3 Methods of determining a valid conversion factor (CF) for liquid effluent monitors are shown in Appendix F. These methods include direct measurement of process fluid with radiochemical analyses, as well as determining the CF from a NIST traceable mixture during primary calibration.

4.1.4 Additional conservatism is required for compliance with 10CFR20 if continuous (blowdown) releases are coincident with batch releases (distillate tanks). Typically, at least 10,000 gpm from Service Water is apportioned to continuous releases to ensure sufficient. dilution ..

However, if there is identified gamma activity in these continuous releases, the required dilution factor may need to be re-evaluated, apportioning circulator flow as necessary.

4.2 Gaseous Monitor Setpoints 4.2.1 Setpoints for gaseous monitors are based on the permissible discharge rates identified in Section 2.1 and demonstrated in Appendix I. These setpoints are inherently conservative due to the assumed mixture (Table 2-8) and the use of the most restrictive setpoints (annual average dose limit), which are used whenever practical. Higher release rates (for alarm setpoint considerations) may be authorized with the proper concurrence, as delineated in Section 2.1.

Permissible Discharge Rates (uGi/sec) at Indian Point Unit 2 Basis of Limit lodine/Particulate* Noble Gases Annual Average 4.01 E-2 7.20E+3 Quarterly Average ** 8.02E-2 1.44E+4 Instantaneous *** 1.38E+1 7.00E+4 Half-lives greater than 8 days These limits are not part of the REGS, but are included for information, as these limits are used for operational control of releases.

Derived in Appendix I for purposes of assurance of compliance with 10GFR20.

4.2.2 The Plant Vent radiation monitor (R-44), as well as most others, reads out in uCi/cc, so the maximum alarm set point is calculated as follows:

s =D / [(F) .. (4.72E+2)]

where:

S = Maximum alarm setpoint in /lCi/cc D = Permissible discharge rate in /lCi/sec.

F =Vent duct flow in fe/min

. 4.72E+2 = unit conversion factor (28317 cc.min/fe.60sec) 4.2.3 If the monitor reads and alarms in cpm, the conversion factor must be applied to convert the reading to uCi/cc.

Indian Point 2 Page 71 Revision 10

aDCM Part II - Calculational Methodologies 4.2.4 Normally, maximum allowable limits are calculated using a standard nuclide mix (Table 2-8). However, setpoints may be determined based on the actual mix, on a case by case basis. This method is usually performed when the instantaneous release rate is applied. Should this method be applied, extra care should be applied to setpoint partitioning (for all release points) to ensure site dose rate limits are not approached.

4.2.5 During normal operation, the unit Plant Vent is the only significant release point. Hence, monitors on the plant vent are routinely set at the annual limit, which is approximately 10% of the conservative instantaneous limit.

Monitor setpoints on other pathways are routinely set to 1% of the instantaneous limit. If multiple pathways become significant, each pathway's permissible release rate is apportioned with the Plant Vent's to ensure the total discharge rate for all release points remains less than the maximum permissible discharge rate.

4.3 Warn Alarms Warn alarms are set at the discretion of the CRS, generally 75% of the ALARM.

They can be based on an application of 10CFR50 Appendix I limits, or a portion of the expected monitor response from preliminary grab sample results.

Indian Point 2 Page 72 Revision 10

aDCM Part II - Calculational Methodologies 5.0 LOWER LIMIT OF DETECTION The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

2.71 +3.29 sb

• J1+(Tb)

LLD Ts Ts E

• V

• k

• Y

• e-J.t where:

LLD = The lower limit of detection as defined above (as picocurie per unit mass or volume)

The sample counting time in minutes The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

The background count time in minutes E= The counting efficiency (as counts per transformation)

V= The sample size (in units of mass or volume) k= A constant for the number of transformations per minute per unit of activity (normally, 2.22E+6 dpm per )..lCi) y= The fractional radiochemical yield (when applicable)

'A. = The radioactive decay constant for the particular radionuclide t= The elapsed time between midpoint of sample collection and time of counting Note: The above LLD formula accounts for differing background and sample count times. The Radiological Environmental Monitoring Program (REMP), uses an LLD formula that assumes equal background and sample count times (per the RECS). For the effluents program, the constants above are more appropriate.

The constants 2.71 and 3.29 and the general LLD equation were derived from the following two sources:

1) Currie, L.A. "Limits for Qualitative Detection of Quantitative Determination". (Anal.

Chern. 40:586-593,1968); and, Indian Point 2 Page 73 Revision 10

ODCM Part II - Calculational Methodologies

2) Mayer, Dauer "Application of Systematic Error Bounds to Detection Limits for Practical Counting". (HP Journal 65(1): 89-91, 1993)

The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples.

Typical values of E, V, Y, and t shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be within .:t one FWHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement process and not as an a posteriori (after the fact) limit for a particular measurement.

To handle the a posteriori problem, a decision level must be defined. The Critical Level concept is defined below. Following an experimental observation, one must decide whether or not a real signal was, in fact, detected. This type of binary qualitative decision is subject to two kinds of error:

1) deciding that radioactive material is present when it is not (a: Type I error), and the converse,

2) failing to decide that it is present when it is (b: Type II error).

The maximum acceptable Type I error (a), together with the standard deviation, Snel, of the net signal when the net signal equals zero, establish the Critical Level, Lc, upon which decisions may be based.

Operationally, an observed signal, S, must exceed Lc to yield the decision, detected.

Lc =kasb( 1+TtIT5)°*5 where:

ka is related to the standardized normal distribution and corresponds to a probability level of 1-a. For instance, selection of a = 0.01 corresponds to a 99% confidence level that activity is present. When determining the Lc for different measurement processes, it is allowable to set a at less than or equal to 0.05 as long as the following condition is met:

To set a for Lc determination at less than 0.05, the equation for the LLD (which places a less than or equal to 0.05) should be employed to verify that the calculated LLD is less than or equal to the LLDs specified in the RECS.

This calculation, if necessary, will be performed on a case by case basis.

Indian Point 2 Page 74 Revision 10

ODCM Part II - Calculational Methodologies REFERENCES

1. Indian Point Unit 2 Technical Specifications.

2. Indian Point Unit 2 Final Safety Analysis Report.

3. 10CFR20, "Standards for Protection Against Radiation."

4. 40CFR190, "Environmental Rad Protection Standards for Nuclear Power Operations."

5. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFRSO Appendix I."

6. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants."

7. NUREG-0133, "Guidance Manual for Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants."

8. NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors."

9. NYPA IP3-CALC-RAD-00001, Rev. 0, "IP3 - Revised ODCM Atmospheric Dispersion Parameters (Multi-Year Hourly Data, Mixed-Mode Releases and Valley Effects, 1994)"

and the updated work from Entech Engineering: Reports P11S-196-EC1, EC2, and EC3 (2004).

10. G. Knoll, "Radiation Detection and Measurement," (1979)

11. IPI-91-015N, "Commitments from March 26 th Meeting on Shared Site Noble Gas Limits."

12. IPI-91-019N, "Corrections to Memo IPI-91-01SN."

13. IPI-91-019, "IP2 and IP3 Isotope-Specific Site Boundary Atmospheric Dispersion Parameters (Mixed-Mode Releases)."

14. JNH-91-020, "IP3 - Dispersion Parameters at the Nearest Residences and at 5 Miles."

15. TS (RS) 92-24, "Ingestion Dose Factor Methodology."

16. NPG (RS) 92-88, "Process and Effluent Monitor Energy Calibration."

17. NPG (RS) 92-97, "Effective Stack Height for Blowdown Flash Tank Vent."

18. New York University Medical Center, "Radiological Studies of the Hudson River Progress Report (1987-1988)" (1988).

19. IP-CHM-96-0S0, "Updated IP3 ODCM and Unit 2 Impact."

20. M.E. Wrenn and J.W. Lentsch, "The Fate of Gamma-Emitting Radionuclides Released into the Hudson River Estuary and an Evaluation of Their Environmental Significance",

New York University Medical Center, Institute of Environmental Medicine, 1974.

21. IPEC CHM-04-03S, "Nuclide Mixtures for Instantaneous and Time Average Releases".

22. IPEC CHM-OS-003, "Site Specific Distances to Site Boundary and Nearest Resident".

23. IPEC-CHM-05-022, "Alternative Methods for Liq Rad Monitor Setpointsl Conv Factors."

24.

2S.

IPEC-CHM-06-012, "Updated Ground Water Dose Evaluations", April 2006 IPEC-CHM-OS-042, "Update to Initial Monitoring Well Offsite Dose Calculation", Dec os. I'/0; Indian Point 2 Page 75 Revision 10

aOCM Part II - Calculational Methodologies APPENDIX A DISPERSION and DEPOSITION FACTORS X/Q highest of 16 sectors site boundary annual average relative 2.22E-6 concentration (sec/m3) [SSW] (2.B7E-5)

(X/Q), highest of 16 sectors nearest residence annual average relative 1.03E-6 concentration (sec/m 3) [SSW] (5.16E-6)

(X/Q)5 highest of 16 sectors at 5 miles annual average relative 7.22E-7 concentration (sec/m 3) [S] (used only when activated)

O/Q highest of 16 sectors site boundary annual average relative 1.41 E-B deposition (11m2) [SSW] (B.76E-B)

(O/Q), highest of 16 sectors nearest residence annual relative 7.52E-9 deposition (11m2) [S] (1:B8E-B)

(O/Q)s highest of 16 sectors at 5 miles annual average relative 1.34E-9 deposition (11m2) [S] (used only when activated)

Notes:

1) Ground-level values are shown parenthetically with each parameter, when applicable.

2) Ground-level deposition factors (O/Q) are provided, but not routinely utilized.

3) The bases information for these meteorological factors is provided in Reference 9.

Indian Point 2 Page 76 Revision 10

aDCM Part II - Calculational Methodologies APPENDIX B LIQUID EFFLUENT SIMPLIFIED FLOW DIAGRAM 121 SG _I R55A t--- canal 122 SG ~I R55B t--- canal canal canal canal R51 canal I SBBPSI I NCD I r

r- SFDS R62 ~

113 WDST I R54 114 WDST I Others' / - - - - - - - - - - - - -__ canal Storm Drains canal and Ground Water Hudson River

• e.g.: House Service Soilers Slowdown; Steam Condensate; Service Water Return; Utility Tunnel Sump (expectedly <LLD for gamma emitters in effluents). These and other systems are monitored per the IPEC 80-10 compliance program.

Indian Point 2 Page 77 Revision 10

aDCM Part II - Calculational Methodologies APPENDIX C (Page 2 of 2)

GASEOUS EFFLUENT SIMPLIFIED FLOW DIAGRAM Containmcnr Pressure Relief C\)ntailllllent Purge Unit 2 Vent ---+~ atmosphere Fuel Storage Building Condenser * ~f------------+. atmosphere Air Ejl.'Ctor

+

~ontainment r-~M:O:B~EX:h~au~st~1--------+*~~-----------+* atmosphere Blowdown Flash 1-------.,... BID FI as h T an k - - - - - - - - - - . . atmosphere

,--_T_"_nk....;I_Un_it_2.:...)--' Vent( Unit 2) l*****ili;;;:d;;;;*;.:i;;~******i-;------1... BID Flash Tank - - - - - - - - - - . . atmosphere L.._.:!.~~I~.!.l!.~i~.. ~? .....1 Vent (Unit I, for SBBPS)

to from other unit CSB Exhaust NSB Exhaust 1----+ Unit 1 Staek ~--+. atmosphere Unit 1 Annulus Exhaust House St

r\,kt:

Boilers Indian Point 2 Page 78 Revision 10

aOCM Part.1I - Calculational Methodologies APPENDIX D STEAM PARTITION FACTOR CALCULATION Cf) .

The Steam Partition Factor / for the Unit 2 flash tank vent is given by:

/ =hBO -180 970 .

For the secondary boiler blowdown purification system flash tank, the factor / is calculated by:

/= hBO - 291 895 Where; hBO is the enthalpy of blowdown liquid, as taken from SOP 15.1, "Calorimetric Thermal Power Calculation," in BTU/Ibm. A typical value = 500 BTU/Ibm.

180 or 291 is the enthalpy of condensed water in each flash tank, in BTU/Ibm 970 or 895 is the enthalpy of associated with the latent heat of vaporization in each tank, in BTU/Ibm

/ = A multiplicative factor used to determine the curies of H-3 escaping the flash tank vent, as follows:

/

• SGBO activity (uCilml)

• SGBO flowrate (gpm)

• 3785 ml/gal

• min = uCi released from vent (1-/)

• SGBO activity (uCi/ml)

• SGBO flowrate (gpm)

• 3785 ml/gal

• min =Liquid uCi released Indian Point 2 Page 79 Revision 10

aDCM Part II - Calculational Methodologies APPENDIX E ALLOWED DILUTED CONCENTRATION (ADC)

The Allowed Diluted Concentration (ADC) is derived and calculated as follows:

ADC= MPCWt

• CG or MPCWt *C.G AD C= - - - - . , - - or ADC= MPCWt Total activity CGtCB CBI 1+ ICG Where; ADC = Allowed diluted concentration in j.lCilml MPCWt = Maximum permissible concentration in water for all isotopes (beta &

gamma), in uCilml, as defined in RECS 03.1.1, as follows:

Where; Ci and MPCWi = Concentration and MPCW for each isotope CB = The concentration of the non gamma emitters, in j.lCi/cc CG = The concentration of the gamma emitters in uCilml Applications of ADC:

If simultaneous liquid radioactive discharges are being performed from one unit, dilution flows may need to be re-apportioned. This may be performed by allocation or by calculation. The required dilution flow is calculated as follows:

E = Dr*CO

. ADC where; Dr = Current release discharge rate, gpm E = Required dilution for current existing release(s), gpm The permissible discharge rate is then calculated as follows:

ADC*B D

CO Where:

o = Permissible discharge rate in gal/min B = Adjusted dilution flow (Available - E, above), ingpm Note that when there is no other releases (E=O), B simply becomes the available dilution flowrate.

Indian Point 2 Page 80 Revision 10

ODCM Part II - Calculational Methodologies APPENDIX F CONVERSION FACTORS FOR LIQUID EFFLUENT MONITORS Monitor conversion factors are derived from circulating a representative sample (or NIST traceable fluid) through the monitor until a stable reading is obtained. The conversion factor is then determined by quantifying the uCilcc (by gamma spectroscopy or known activity) and dividing this value by the net cpm displayed on the monitor.

Fluid may be recirculated within the monitoring system, or introduced into a closed loop, to provide elevated, stable readings on the monitor. This fluid should be representative of the expected nuclide mixture in the system, as the conversion factor is energy-dependent.

When the process fluid itself is of sufficient activity to provide this function, it is this fluid that is measured and applied to develop a typical conversion factor.

When the process fluid is usually free of contamination, NIST traceable fluid must be injected into the sample chamber to accomplish this task.

Once the sample chamber is providing a stable reading, an alequate of the fluid is measured by gamma spectroscopy to determine the average energy and the monitor's conversion factor.

Conversion Factors for effluent monitors are maintained by Chemistry and updated when standard mixtures change which would warrant an improved average energy representation.

If desired, a more robust method can be applied per Reference 23.

Indian Point 2 Page 81 Revision 10

ODCM Part II - Calculational Methodologies APPENDIX G (Page 1 of 7)

ENVIRONMENTAL SAMPLING POINTS SAMPLE DESIGNATIONI STATION LOCATION DISTANCE DR1/57 Roa Hook 2.0 mi - N DR2/59 Old Pemart Avenue 1.8 mi -NNE DR3/90 Charles Point 0.88 mi - NE DR4/28 Lents Cove 0.45 mi - ENE DR5/35 Broadway and Bleakley Avenue 0.37 mi - E DR6/88 Reuter-Stokes Pole #6 0.32 mi - ESE DR7/14 Water Meter House 0.3 mi - SE DR8/03 Service Center Building 0.35 mi - SSE DR9/34 South East Corner of Site 0.52 mi - S DR10105 NYU Tower 0.88 mi-SSW DR11/53 White Beach 0.92mi-SW DR12/74 West Shore Drive - South 1.59 mi-WSW DR13/76 West Shore Drive - North 1.21 mi-W DR14/78 Rt. 9W, across from RlS #14 1.2 mi-WNW DR15/80 Rt. 9W - South of Ayers Road 1.02 mi - NW DR16/82 Ayers Road 1.01 mi - NNW DR17/58 Rt. 9D - Garrison 5.41 mi-N DR18/60 Gallows Hill Road and Sprout Brook Road 5.02 mi - NNE DR19/62 West Brook Drive (near the Community Center) 5.03 mi - NE DR20/64 Lincoln Road - Cortlandt (School Parking Lot) 4.6 mi-ENE DR21/66 Croton Ave. - Cortlandt 4.87 mi - E DR22/67 Colabaugh Pond Rd. - Cortlandt 4.5 mi - ESE DR23/69 Mt. Airy & Windsor Road 4.97 mi - SE DR24/92 Warren Rd. - Cortlandt 3.84 mi - SSE DR25/71 Warren Ave. - Haverstraw 4.83 mi - S DR26/72 . Railroad Ave. & 9W Haverstraw 4.53mi-SSW DR27173 Willow Grove Rd. & Captain Faldermeyer Drive 4.97mi-SW DR28/81 Palisades Parkway, Lake Welch Exit 4.96 mi-WSW DR29/77 Palisades Parkway 4.15 mi - W DR30179 Anthony Wayne Park 4.57 mi-WNW DR31/75 Palisades Parkway .4.65mi-NW DR32/83 Rt. 9W Fort Montgomery . 4.82 mi- NNW DR33/33 Hamilton Street (Substation) 2.88 mi - NE DR34/38 Furnace Dock (Substation) 3.43 mi - SE DR35/89 Highland Ave. & Sprout Brook Rd. (near Rock Cut) 2.89 mi - NNE DR36/61 Lower South Street and Franklin Street 1.3mi-NE DR37/56 Verplanck - Broadway & 6th St. 1.25 mi - SSW DR38/20 Cortlandt Yacht Club (aka Montrose Marina) 1.5 mi-S DR39/29 Grassy Point 3.37 mi -SSW DR40/23 *Roseton 20.7 mi - N DR41/27 Croton Point 6.36 mi- SSE

• Control Station Indian Point 2 Page 82 Revision 10

ODCM Part II - Calculational Methodologies APPENDIXG (Page 2 of 7)

ENVIRONMENTAL SAMPLING POINTS SAMPLE DESIGNATIONI STATION LOCATION DISTANCE Airborne A1/4 Algonquin Gas Line 0.28 mi ~SW A2/94 IPEC Training Center 0.39 mi - S A3/95 Meteorological Tower 0:46 mi - SSW A4/5 NYU Tower 0.88 mi -SSW A5/23 *Roseton 20.7mi-N Waterborne.,.. Surface (Hudson River Water)

Wa1/9 *Plant Inlet (Hudson River Intake)0.16 mi - W .

Wa2/10 Discharge Canal (Mixing Zone)0.3 mi - WSW Waterborne - Drinking.

Wb1/7 Camp Field Reservoir 3.4 mi - NE, Soil From Shoreline Wc1/53 White Beach 0.92 mi -SW Wc2/50 *Manitou Inlet 4.48 mi-NNW Exposure PathwaviSample: Milk There are no milch animals whose milk is. used for human consumption within 8 km distance of Indian Point; therefore. no milk samples are taken.

Exposure Pathway/Sample: Ingestion-Fish and Invertebrates The RECS designate two required sample locations labeled Ib1/25 and Ib2/23. The downstream Ib1 location and samples will be chosen where it is likely to be affected by plant discharge. Ib2 will be a location upstream that is not likely to be affected by plant disch~rge.

The following species along with other commercially/recreationally important species are considered acceptable:

Striped Bass Pumpkin Seed American Eel Bluegill Sunfish White Catfish Crabs White Perch Blueback Herring Exposure Pathway/Sample: Ingestion-Food Products (Broad Leaf Vegetation)

Ic1/95 Meteorological Tower 0.46 mi - SSW Ic2/94 IPEC Training Center 0.39 mi - S Ic3/23 *Roseton 20.7 mi - N

• Control Station

. Indian Point 2 Page 83 Revision 10

ODCM Part II - Calculational Methodologies APPENDIXG (Page 3 of 7)

ENVIRONMENTAL SAMPLING POINTS SAMPLE DESIGNATIONI SAMPLE STATION LOCATION DISTANCE TYPES DR8/3 Service Center Building 0.35 mi - SSE 3 A1/4 Algonquin Gas Line 0.28 mi -SW 1,2 A4,DR10/5 NYU Tower 0.88 mi -SSW 1,2,3 Wb1/7 Camp Field Reservoir 3.4 mi - NE 6

• • /8 Croton Reservoir 6.3 mi - SE 6 I Yo1 Wa1/9 "Plant Inlet (Hudson River Intake) 0.16 mi - W 7 Wa2/10 Discharge Canal (Mixing Zone) 0.3mi-WSW 7,8 DR7/14 Water Meter House 0.3 mi - SE 3

""/17 Off Verplanck 1.5 mi-SSW 8,9,10 I '/07 DR38/20 Cortlandt Yacht Club (AKA 1.5 mi - S 3 Montrose Marina)

"*/22 Lovett Power Plant 1.6 mi-WSW 1,2 I YO?

Ib2,A5,DR40,lc3/23 "Roseton 20.7mi-N 1,2,3,4,5,11,12 Ib1/25 where available, downstream N/A 12 DR41/27 Croton Point 6.36 mi -SSE 1,2,3 DR4/28 Lents Cove 0.45 mi - ENE 3,8,9,10 DR39/29 Grassy Point 3.37 mi -SSW 1,2,3 DR33/33 Hamilton Street (Substation) 2.88 mi - NE 3

(

DR9/34 South East Corner of Site 0.52 mi - S 3 DR5/35 Broadway & Bleakley Avenue 0.37 mi - E 3 DR34/38 Furnace Dock (Substation) 3.43 mi - SE 3

• • /44 Peekskill Gas Holder Building . 1.84 mi - NE 1,2,11 Wc2l50 "Manitou Inlet 4.48 mi - NNW 10 I '/07 Wc1,DR11/53 White Beach 0.92 mi -SW 3,10 DR37/56 Verplanck - Broadway & 6th Street 1.25 mi - SSW 3 DR1/57 Roa Hook 2.0 mi - N 3 DR17/58 Rt. 90 Garrison 5.41 mi - N 3 DR2/59 Old Pemart Ave. 1.8 mi - NNE 3 DR18/60 Gallows Hill Road and Sprout Brook 5.02 mi - NNE 3 Road DR36/61 Lower South Street and Franklin 1.3mi-NE 3 Street DR19/62 West Brook Drive (near the 5.03 mi - NE 3 Community Center)

DR20/64 Lincoln Road - Cortlandt (School 4.6 mi - ENE 3 Parking Lot)

DR21/66 Croton Ave. - Cortlandt 4.87 mi - E 3 DR22/67 Colabaugh Pond Rd. - Cortlandt 4.5 mi - ESE 3 DR23/69 Mt. Airy & Windsor Road 4.97 mi-SE 3

• Control Station ** Items are in excess of RECS requirements I ,((11 Indian Point 2 Page 84 Revision 10

ODCM Part II - Calculational Methodologies APPENDIX G (Page 4 of 7)

ENVIRONMENTAL SAMPLING POINTS SAMPLE DESIGNATION/ SAMPLE STATION LOCATION DISTANCE TYPES DR25/71 Warren Avenue - Haverstraw 4.83 mi - S 3 DR26/72 Railroad Ave. & 9W - Haverstraw 4.53mi-SSW 3 DR27/73 Willow Grove Rd. & Captain Faldermeyer Dr 4.97mi-SW 3 DR12/74 West Shore Drive - South 1.59 mi -WSW 3 DR31/75 Palisades Parkway 4.65 mi - NW 3 DR13/76 West Shore Drive - North 1.21 mi-W 3 DR29/77 Palisades Parkway 4.15 mi - W 3 DR14/78 Rte. 9W, across from RlS #14 1.2 mi-WNW 3 DR30/79 Anthony Wayne Park 4.57 mi-WNW 3 DR15/80 Rte. 9W - South of Ayers Road 1.02 mi- NW 3 DR28/81 Palisades Parkway, Lake Welch Exit 4.96 mi-WSW 3 DR16/82 Ayers Road 1.01 mi - NNW 3 DR32/83 Rte. 9W - Fort Montgomery 4.82 mi- NNW 3

• • /84 Cold Spring 10.88 mi - N 8,9,10 I \/°1

"'*/85 Quality Control 6 DR6/88 Reuter-Stokes Pole #6 0.32 mi- ESE 3 DR35/89 Highland Ave. & Sprout Brook Road (near 2.89 mi - NNE 3 rock cut)

DR3/90 Charles Point 0.88 mi - NE 3 DR24/92 Warren Rd. - Cortlandt 3.84 mi - SSE 3 A2, Ic2/94 IPEC Training Center 0.39 mi - S 1,2,4,5 A3,lc1/95 Meteorological Tower 0.46 mi - SSW 1,2,4,5 MW-40/104 Boundary Well #40 0.21 mi - SW 13 MW-51/105 Boundary Well #51 0.18 mi-SSW 13

• • Items are in excess of RECS requirements Sample types are:

1. Air particulates 8. H.R. bottom sediment-silt

2. Radioiodine 9. H.R. aquatic vegetation

3. Direct gamma 10. H.R. shoreline soil

4. Broadleaf vegetation 11. Fallout

5. Soil 12. Fish and invertebrates

6. Drinking water 13. Ground Water Boundary Monitoring I ~ol

7. Hudson River (H.R.) water (see ODCM Part J, Figure 04.1-1)

Indian Point 2 Page 85 Revision 10

ODCM Part II - Calculational Methodologies APPENDIXG (Page 5 of 7)

ENVIRONMENTAL SAMPLING POINTS SAMPLING LOCATIONS Within Two Miles of Indian Point N

~

Peekskill Westchester County Indian pOint~~

Ib1 rn (7) 1 mile 13J(2)

Hudson Ic1 Ic2 11 9

@m Buchanan verplanc~

\.......~'

38 Key: l:l - Waterborne: Surface (HR) Wa# Ic# - Broadleaf Vegetation o - Direct Radiation Sample Location DR# Ib1 - Fish and Invertebrates (where available downstream) o - Air Particulate & Radioiodine A#

<> - HR Shoreline Sediment Wc#

Indian Point 2 Page 86 Revision 10

ODCM Part II - Calculational Methodologies APPENDIXG (Page 6 of 7)

ENVIRONMENTAL SAMPLING POINTS I Yo..,

SAMPLING LOCATIONS Within Ten Miles of Indian Point N

~ Roseton (20.7 mi. N); [II @ le3 Upstream: Ib2 Orange County Putnam County Bear Mountain Bridge 5 miles Ro~kland County Westchester County Key: 0 - Direct Radiation Sample Location DR# Ic3

• Broadleaf Vegetation o -Air Particulate & Radioiodine A# Ib2

• Fish and Invertebrates

<> . HR Shoreline Sediment Wc# (where available o . Waterborne: Drinking Wb# upstream)

Indian Point 2 Page 87 Revision 10

ODCM Part II - Calculational Methodologies APPENDIXG (Page 7 of 7)

ENVIRONMENTAL SAMPLING POINTS I V07 ADDITIONAL SAMPLING LOCATIONS Roseton (20.7 mi. N): 23 : p +

Orange County Putnam County Cold Spring (10.88 rni. N) : 84 :l' Bear Mountain Bridge 10:

• 17: l'

<>r----_~

• 22:. -104l105:gw I '/07 29:. ----41.

Rockland County Westchester County

• 8:dw 5 miles Key: * - Air Particulate & Radioiodine <>- HR Shoreline Sediment

- l' - Aquatic Vegetation +-Soil

• - HR Bottom Sediment p - Precipitation gN - Ground Water Boundary Monitoring (see detailed site map)

I 101 dw - Drinking Water Indian Point 2 Page 88 Revision 10

ODCM Part II - Calculational Methodologies APPENDIX H INTERLABORATORY COMPARISON PROGRAM The James A. Fitzpatrick NPP Environmental Laboratory participates in the EPA Interlaboratory Comparison program or comparable program with a certified vendor. Samples of various media containing known activities of radionuclides were sent to participating laboratories for analyses.

Results of the analyses are compared to the known values.

Results are reported in term of normalized deviations from a known value. Interlaboratory results are considered acceptable if the laboratory's normalized deviation for a sample is less than 3 or greater than minus 3.

Annual results of participation are summarized in the Annual Environmental Operating Report. \

Indian Point 2 Page 89 Revision 10

ODCM Part" - Calculational Methodologies APPENDIX I Page 1 of 6 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 Primary Assumptions:

1. Units 2 and 3 effective dose factors (KLMN) are equivalent, except for site-specific finite cloud correction, as required.

2. Each unit shares 50% of the total allowable release rate, Q, in Ci/sec.

Therefore, Q3 = Q2 for instantaneous releases.

Given the following long-term meteorological data:

Unit 112:

Concentration Finite-Cloud Deposition Unit 1 or 2 Receptor XlQ GammaXlQ D/Q Release Points (sec/ml) l(sec/m3} - Xe133 (11m2) 2.219E-06 1.974E-06 1.407E-OB Site Boundary

[SSW, 755 mJ [SSW, 755 mJ [SSW, 755 ml Primary Vent 1.030E-06 9.714E-07 7.517E-09 Nearest Residence Releases [SSW, 1574 m] [SSW, 1574 m] is, 1133 m]

2.B73E-05 1.215E-05 B.759E-OB Site Boundary Ground Level [SSW, 440 mJ [SSW, 440 mJ [SSW, 440 mJ Releases 5.15BE-06 3.06BE-06 1.B7BE-OB Nearest Residence

[SSW, 1374 m] [SSW, 1374 mJ [S, 933 m]

Unit 3:

Concentration Finite-Cloud Deposition Unit 3 Receptor XlQ Gamma XlQ D/Q Release Point (sec/mJ) fsec/mJ) - Xe133 (11m2) 4.473E-06 3.171 E-06 2.599E-OB Site Boundary

[SW, 350 mJ [SSW, 4BO mJ [SSW, 4BO mJ Primary Vent 1.016E-06 9.606E-07 7.451E-09 Nearest Residence Releases [SSW, 1574 ml [SSW, 1574 m) is, 1133 m) 6.9BOE-05 2.350E-05 2.012E-07 Site Boundary Ground Level [SSW, 250 mJ [SSW, 250 m] [SSW, 250 mJ Releases 5.15BE-06 3.06BE-06 1.B7BE-OB Nearest Residence

[SSW, 1374 ml [SSW, 1374 mJ IS; 933 mJ Indian Point 2 Page 90 Revision 10

aDCM Part" - Calculational Methodologies APPENDIX I Page 2 of 6 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 Instantaneous Release Rates vs Dose Rates Indian Point units 2 and 3 share a common site boundary limit of 500 mrem/yr. This 500 mrem/yr limit was divided between the units based upon a 50-50 split of the release rate in

~lCi/sec. Because each unit has its own X/Q and K-bar, equal ~lCi/sec discharges from each plant will result in different dose rates for each plant at the most restrictive site boundary location. In order to define the split of the 500 mrem/yr limit, IPEC units 2 and 3 must base the dose split on the mixture presented in Table 2-8.

Dose Split Between IP2 and IP3 A. Instantaneous Dose Rates and Calculation of Allowable Release Rate in uCi/sec:

i. Whole Body Dose Rate Calculations:

Given:

a) site limit is 500 mrem/yr b) IP3 worst sector X/Q =4.47E-6 sec/m3 mremem 3 c) IP3 K-bar for instantaneous mixture =849 - - - -

JlO. yr 3

d) IP2 worst sector X/Q = 2.22E-6 sec/m mrem e m 3 e) IP2 K-barfor instantaneous mixture = 1507 - - - -

JlCi e yr f) Q =~Ci/sec Solve for Q:

Q [(X/Q 3) (K bar3) + (X/Q2) (K bar2)] = 500 mrem/yr Q [(4.47E-6) (849) + (2.22E-6) (1507) J = 500 mrem/yr Solving for Q' a default back-calculated instantaneous release rate for either unit:

Q = 7.00E+4 ~Ci/sec In other words, if both units were releasing at this rate, with the default instantaneous mixture identified in Table 2-8, IPEC would be releasing at 500 mrem/yr (the RECS and 10CFR20 release rate limit).

Since this value assumes ALL releases are included (per unit), a partitioning factor should be applied for each applicable release point when this limit is used. Should it become necessary to "borrow" from the other unit, isotopic mixtures from specific sample results should replace the dose factors used in this default calculation. Without specific sample data, the default SITE release rate limit is then: 1.40E5 uCi/sec.

Indian Point 2 Page 91 Revision 10

aDCM Part II - Calculational Methodologies APPENDIX I Page 3 of 6 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINl" UNITS 2 and 3 ii. Skin Dose Rate Calculations:

Given:

a) site limit is 3,000 mrem/yr b) IP3 worst sector XJQ = 4.47E-6 sec/m 3 3

c) IP3 (Li + 1.1 Mi) =2306 mrem e m

}lei e yr d) IP2 XJQ for SSW sector =2.22E-6 sec/m 3 mremem 3 e) IP2(Li + 1.1 Mi) =3071 ---

}lei e yr f) Q =uCi/sec Solve for Q:

Q [(X/Qh (Li + 1.1 Mi)a + (X/Q)2 (Li + 1.1 Mih] = 3,000 mrem/yr Q[(4.47E-6) (2306) + (2.22E-6) (3071)] =3,000 mrem/yr Q = 1. 75E+5 ~Ci/sec (less restrictive than Whole Body) iii. Solve for WB dose rate commitments per site (with Q =7.00E+4 uCi/sec)

Indian Point 2:

. . mremem 3 (7.00E+4 ~Ci/sec) (2.22E-6 sec/m 3 ) (1507 . ) = 234 mrem/yr

}lO e yr Indian Point 3:

mreme m 3 (7.00E+4 ~Ci/sec) (4.47E-6 sec/m 3 ) (849 . ) = 266 mrem/yr

}lO e yr The less restrictive skin dose rate limit for each unit (information only):

3 Unit 2: (1.75E+5 uCi/sec) (2.22E-6 sec/m 3 ) (3071 mrem. m ) = 1194 mrem/yr

}lei e yr

. mremem 3 Unit 3: (1.75E+5 uCi/sec) (4.47E-6 sec/m 3 ) (2306 = 1806 mrem/yr

}lei e yr Indian Point 2 P~ge92 Re~s~n10

ODCM Part II - Calculational Methodologies APPENDIX I Page 4 of 6 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 RELEASE RATE LIMITS FOR QUARTERLY AND ANNUAL AVERAGE NOBLE GAS RELEASES For a Calendar Quarter For a Calendar Year Gamma air dose 5 mrad limit 10 mrad limit Beta air dose 10 mrad limit 20 mrad limit I. Assumptions: 1. Doses are delivered to the air at the site boundary.

2. Finite cloud geometry is assumed for noble gas releases at site boundary.

=

3. X/Q for Unit 2 2.22E-6 sec/m 3 , (Q = release rate uCi/sec)

4. X/Q for Unit 3 =4.47E-6 sec/m (Q =release rate uCi/sec) 3

5. Gamma and Beta air dose factors (M and N), Corrected for finite cloud geometry (as described on Table 2-8) are as follows:

Unit 2 effective Unit 3 effective Units average dose factors average dose factors M = 281 M = 181 mrad/yr per uCi/m 3 N = 1254 N = 1254 mrad/yr per uCi/m 3 II. Calculation of Quarterly Release Rates:

a) for gamma dose: (Q )*[(M)(X/Q)] less than or equal to 5 mrad/qtr b) for beta dose: (Q )*[(N)(X/Q)] less than or equal to 10 mrad/qtr unit 2 unit 3 5mrad / qtr gamma dose rate Q = (l/4yr)(M)(X /Q)

= 3.21 E+4 /lCi/sec 2.47E+4/lCi/sec beta dose rate Q = (1/ lOmrad / qtr 4yr)(N)(X / Q)

= 1.44E+4 /lCi/sec 7.14E+3 /lCi/sec Based on the above analysis, the beta dose.is limiting for time average doses.

Therefore, the allowable quarterly average release rates are 1.44E+4 /lCi/sec for unit 2 and 7 .14E+3 j.lCi/sec for unit 3.

III. Calculation of Calendar Year Release Rate Annual limits are one half of quarterly limits. Therefore, using Beta air dose as most limiting, the maximum annual average release rates are 7.20E+3 ~lCi/sec for unit 2 and 3.57E+3 ~lCi/sec for unit 3.

Indian Point 2 Page 93 Revision 10

ODCM Part II - Calculational Methodologies APPENDIX I Page 5 of 6 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 ALLOWABLE INSTANTANEOUS RELEASE RATE for 1-131 & Particulates wi TYz > 8 DAYS)

Given: Wv(in): X/Q at the Site Boundary for IP3 = 4.47E-6 sec/m 3 Wv(in): X/Q at the Site Boundary for IP2 = 2.22E-6 sec/m 3 PI(c) =1.62 E7 mremlyr pCi 1m 3 Assumed Pathway: Child Inhalation at Unrestricted Area Boundary Solve the following equation for Q:

[(Q)PI(c)(Wv(in>> Unit 3] + [(Q)PI(c)(Wv(in>> Unit 2] = 1500 mrem/yr IP3: (Q )PI(c)(Wv(in>>3 = Q.

• 1.62E7 mrem I yr 3 4.47E-6 s/m 3

= Q. mrem I yr

• 72.4 ----"--

pCi I m' pG / sec IP2: (Q)PI(c)(Wv(in>>2 = Q

• 1.62E7 mreml yr 2.22E-6 s/m3 = Q

• 36.0 mreml yr pCi I m3 . pCi I sec The sum equals: (108) ( Q) mrem/yr per uCi/sec Limit is 1500 mrem/yr per site:

Therefore: 108

• Q mrem I yr. = 1500 mrem/yr pCi / sec Q =1.38E+1 JlCi/sec (for each unit) 3 IP3 Dose Contribution: 1.38E+1 pG

• 1.62£7 mrem m

• 4.47 £ _ 6 sec = 1003 mrem/yr sec yr pG m3 3

IP2 Dose Contribution: 1.38E+1 pCi

• 1.62£7 mrem m

• 2.22£ _ 6 sec = 497 mrem/yr sec yr pG m3 Sum = 1500 mrem/yr Approximately a 67 133 % dose split for IP3 and IP2 respectively.

Indian Point 2 Page 94 Revision 10

ODCM Part II - Calculational Methodologies APPENDIX I Page 6 of 6 CALCULATION OF ALLOWABLE RELEASE RATES FOR INDIAN POINT UNITS 2 and 3 ALLOWABLE RELEASE RATES FOR IODINE / PARTICULATE TIME AVERAGE QUARTERLY AND ANNUAL DOSE LIMITS AT THE NEAREST RESIDENT Dose factors for the child, thyroid (for Iodine 131) are used for this category as a conservative assumption since this nuclide has the highest thyroid dose factor of all iodines and particulates, and its most significant effect in on the child age group. The H-3 dose factor is about 4 orders of magnitude less significant and its contribution to the total dose is considered negligible. The back-calculated release rate for Iodine and Particulate is as follows:

Given: Unit 2 Unit 3 X/Q (in sec/m 3 at the nearest reSident) 1.03E-6 1.02E-6 D/Q (in m-2 at the nearest resident) 7.52E-9 7.45E-9 RI(c) = 1.62E+7 mreml y;, child thyroid inhalation dose factor for 1-131 (for both units) pCi I m*

mreml vr RG = 1.72E+7 m 2 -_........::...-, ground plane dose factor for 1-131 (for both units) pCi I sec RV(c) = 4.75E+10 m2 mreml yr, child thyroid vegetation dose factor for 1-131 (for both units) pCi Isec Calculating the allowable" time average release rate by solving the following equation" for Q:

Q [(Rlc)(X/Q) + (RG)(D/Q) + (RVc)(D/Q)] =limit in mrem/yr Unit 2 Unit 3 Q (Rlc)(X/Q) in mrem/yr per uCi/sec = 16.7

• Q 16.5

• Q Q (RG) (D/Q) in mrem/yr per uCi/sec = 0.129

• Q 0.128*Q Q (RVc)(D/Q) in mrem/yr per uCi/sec = 357

• Q 354

• Q The sum for each unit ( X *Q ) in mrem/yr per uCi/sec. 374

• Q 371

• Q Quarterly time average limit is 7.5 mrem to any organ (or 30 mrem/yr). Solving"for Q yields:

. mreml yr .

(IP2) Q

• 374 =30 mrem/yr Q =8.02E-2 )lCi/sec (Quarterly Limit) pCi I sec Annual limit is Y:! quarterly limit, or 15 mrem to any organ/yr = 4.01E-2 )lCi/sec (Annual Limit)

. mremlyr . '

(IP3) Q

• 371 =30 mrem/yr Q =8.1 OE-2 )lCi/sec (Quarterly Limit) pCi Isec "

( Annual limit is Y:! quarterly limit, or 15 mrem to any organ/yr = 4.0SE-2 )lCi/sec (Annual Limit)

Indian Point 2 Page 95 Revision 10

Unit 2 aDCM Revision 11 Justification Package Prepared by: Steven Sand ike Brief Summary of Changes February, 2007 UNIT 2 aDCM Part I 1 Modified REGS 01. 1, Definition of "MPGW" to specifically identify application of NEW 1OGFR20 and 10 times the EG values, for implementation of Unit 2 Technical Specification Amendment 250, December 2006.

2 Modified REGS 803. 1. 1-1, last paragraph to specifically identify application of NEW 10GFR20 and 10 times the EG values, for implementation of Unit 2 Technical Specification Amendment 250, December 2006.

Note: Other sections of the ODGM involving 10GFR20 applications refer back to these definitions and do not need updating.

Each change is discussed in detail on the following pages. This information is to be included in the aSRC presentation, the 50.59 package, and the next Annual Effluent Release Report sent to the Commission per Reg Guide 1.21

Unit 2 aDeM Revision 11 Justification Package item # 1 of 2 Feb, 2007 OBJECTIVE:

Update RECS 0.1.1-1 definition of "MPCW" to conform with the new 10CFR20 application of EC*10, per Unit 2 Technical Specification Amendment 250 and TSTF-258.

DESCRIPTION OF CHANGES:

Changed definition of MPCW in RECS 01.1 to :

" ... concentration of a radionuclide equal to 10 times the EFFLUENT CONCENTRATIONS specified in 10CFR20, Appendix B, Table 2, Column 2."

IMPACT:

None. Lower tier procedures and software are already effective to comply with the Amendment.

JUSTIFICATION:

Per the SER for this Amendment, the error introduced during ITS implementation is resolved. The Technical Specifications now accurately refer to the new 10CFR20 in all applications. The aDCM was updated to capture the.correct definition of "MPCW", which had already been established in the RECS as the means of complying with liquid waste instantaneous release rate limits of either version of 10CFR20.

Unit 2 aDeM Revision 11 Justification Package item # 2 of 2 Feb, 2007 OBJECTIVE:

Update RECS BASES (BD3.1.1-1, last paragraph) to conform with the new 10CFR20 application of EC*10, per Unit 2 Technical Specification Amendment 250 and TSTF-258.

DESCRIPTION OF CHANGES:

Updated this passage in the BASES to :

" ... will be less than 10 times the EFFLUENT CONCENTRA TIONS specified in 10 CFR Part 20."

IMPACT:

None. Lower tier procedures and software are already effective to comply with the Amendment.

JUSTIFICATION:

Per the SER for this Amendment, the error introduced during ITS implementation is resolved. The Technical Specifications now accurately refer to the new 10CFR20 in all applications. The aDCM was updated to capture the correct definition of "MPCW", which had already been established in the RECS as the means of complying with liquid waste instantaneous release rate limits of either version of 10CFR20.

Entergy Nuclear Northeast Indian Point Units 1, 2 TITLE: OFFSITE DOSE CALCULATION MANUAL (ODCM)

Rev. 11

(

WRITTEN BY:

REVIEWED BY:

date OSRC REVIEW: rJ iC) I/O::';

date APPROVED BY:

EFFECTIVE DATE:

date

Definitions 01.1 01.0 USE AND APPLICATION o 1.1 Definitions

---

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

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

Definition GASEOUS A GASEOUS RADWASTE TREATMENT SYSTEM is any system RADWASTE designed and installed to reduce radioactive gaseous effluents by TREATMENT collecting primary coolant system offgases from the primary system and SYSTEM providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

MEMBER(S) OF MEMBER(S) OF THE PUBLIC includes all persons who are not THE PUBLIC occupationally associated with the site. This category does not include employees of the utility, their contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

MAXIMUM MPCW is that concentration of a radionuclide equal to ten times the PERMISSIBLE EFFLUENT CONCENTRATIONS specified in 10CFR20, Appendix B, 217 CONCENTRATION Table 2, Column 2.

WATER (MPCW)

OFFSITE DOSE The OFFSITE DOSE CALCULATION MANUAL shall contain the CALCULATION current methodology and parameters used in the calculation of offsite MANUAL doses due to 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.

PRIMARY TO A PRIMARY TO SECONDARY LEAK is defined by a quantifiable leak SECONDARY rate equal to or greater than 0.5 gpd, AND LEAK a) The presence of fission or activation products in the secondary fluid, verified as Steam Generator U-tube leaks (and not from other known contamination, such as IVSWS leaks), OR ~

b) Tritium activity in the secondary fluid indicating an increase above historical baseline (normal diffusion) of 5.00E-6 uCi/ml or greater.

PROCESS The PROCESS CONTROL PROGRAM is a manual containing and/or CONTROL referencing selected operational information concerning the PROGRAM solidification of radioactive wastes from liquid systems.

Indian Point 2 01.1-1 Revision 11

Liquid Effluent Concentrations B D 3.1.1 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.1 Liquid Effluent Concentrations BASES It is expected that the release of radioactive materials in liquid and gaseous effluents to UNRESTRICTED AREAS will not exceed the concentration limits specified in 10 CFR Part 20 and should be as low as reasonably achievable (A LARA) in accordance with the requirement of 10 CFR 50.36a. While providing reasonable assurance that the design objectives will be met, these Specifications permit the flexibility of operation, compatible with considerations of health and safety, to ensure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the concentration limits specified in 10 CFR Part 20. It is expected that using this operational flexibility under unusual operation conditions, and exerting every effort to keep levels of radioactive materials in liquid and gaseous wastes as low as reasonably achievable, releases will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20.

The design objectives have been developed based on operating experience, taking into account a combination of variables including defective fuel, primary system leakage, primary to secondary system leakage, steam generator blowdown and the performance of the various waste treatment systems, and are consistent with 10 CFR Part 50.36a.

The Indian Point site is a multiple-unit site. There exist shared radwaste treatment systems and shared effluent release points. Where site limits must be met, the effluents of all the units will be combined to determine site compliance. For instances where unit-specific information may be required for radwaste processed or released via a shared system, the effluents shall be proportioned among the units sharing the system(s) in accordance with the methods and agreements set forth in the ODCM.

This specification 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 EFFLUENT 217 CONCENTRATIONS specified in 10 CFR Part 20. 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, 10 CFR Part 50, to a

< member of the public and (2) the limits of 10 CFR Part 20.1302 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 MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection {lCRP) Publication 2.

This specification applies to the release of liquid effluents from all units on site.

Indian Point 2 B D 3.1.1 - 1 Revision 11

r j It IPEC COMBI.NED ODCM Rev 0 Justification Package Combines Unit 2 ODCM Rev 11 and Unit 3 Rev 18 Prepared by: Steven Sandike Brief Summary of Changes December, 2007 As much as possible, technical or process changes to either ODCM were avoided for this merge, simply combining the elements of both unit ODCMs into one. Cross reference documents have been generated to identify the new location of each page or paragraph of the old ODCMs to the appropriate new location. The new station ODCM is in the format of

. Unit 2's previous ODeM (per NUREG 1431 and ITS). Several administrative changes were required to move the material from the old ODCMs to new Revision 0 of the IPEC station ODCM. Along with these unavoidable administrative wording changes, several other minor changes are included in this revision, as summarized below.

aDCM Part I Definitions Section 01.1- modified SITE BOUNDARY & UNRESTRICTED AREA to apply to the site licensee(s).

2 Updated Instrumentation sections 03.3.1 and 03.3.2 to include all IPEC effluent instrumentation by 10 nomenclature, and appended OSRs as required to ensure all station OSRs could be referenced.

3 Modified Table 03.3.1-1, part 4, RWST level instruments, to list the daily channel check, but defer the periodicity of Channel Operability Tests and Calibrations to the appropriate section of unit-specific Technical Specifications.

4 Added requirements for the Unit 2 VC Noble Gas Monitor (R-42) similar to those of Unit 3's R-12 in Section 03.3.2, including new footnote (g) from Unit 3's equivalent section. This footnote helps explain the use of the monitor for VCPR quantification.

S Modified Table 03.3.2-1, part 3, VC Noble Gas Monitors, to list the monthly source check, but defer the periodicity of the other surveillances (Channel Check, Operability Tests, and Calibrations) to the appropriate section of the Technical Specifications.

6 Modified Table 03.3.2-1, parts 4 and 6, to stipulate a 24-month calibration for the sample flow rate monitors (totalizers).

7 Clarified REMP section 03.S.1 4c(broad leaf sample locations) and 03.S.2 (Land Use) to explain the use of the Site Boundary locations (highest 0/0) in lieu of a garden census.

8 Modified Section OS.6 to rename the GWMP the "Radiological Ground Water Monitoring Program" (RGWMP), clarify the bullets, and add requirements specifying what kind of information goes into which annual report.

aDCM Part II 9 The S-mile cow milk pathway description and dose equations were removed from the OOCM in 2003 due to the absence of a documented pathway. This information was returned to the OOCM in this revision, with an opening discussion in Section 3.3.4.1 explaining that the USE of this pathway is turned on and off according to the current land use census. Other sections effected include 3.3.4.2, 3. 3.4.S.d, 3.S.4, 3.S.6, and Appendix I, each of which shows the return of applicable guidance for determining doses from the Cow-Milk pathway.

Returning the Cow's Milk Pathway equations and guidance to the OOCM does NOT infer that this pathway was activated. This information was returned to the OOCM, as a result of discussions during a recent in-house audit, to simplify administrative requirements, should the land use census ever identify the need to activate the pathway, in mid-year, for example. When required, this pathway can simply be turned on and documented, without the rigor of re-establishing the modeling and equations in the OOCM at that time, when details of this pathway's calculations may be more difficult to recollect. The change would be documented in the land use census and incorporated in the 10CFRSO effluent tracking software. It would also be documented in the annual effluent report (Reg Guide 1.21), and in station procedures governed under the 10CFRSO.S9 review process, but the OOCM should not require a change. At the present time, this pathway remains inactivated at IPEC.

Each of the above changes is discussed in detail on the following pages. This information is to be included in the OSRC presentation, the 50.59 package, and the next Annual Effluent Release Report sent to the Commission per Reg Guide 1.21

IPEC COMBINED ODCM Rev 0 Justification Package Combines Unit 2 aDCM Rev 11 and Unit 3 ReV 18 item # 1 of 9 Dec, 2007 OBJECTIVE:

Modified SITE BOUNDARY & UNRESTRICTED AREA in Definitions Section 01.1, to apply to the site licensee(s) rather than one unit or the other.

DESCRIPTION OF CHANGES:

Changed references to a specific unit to "the licensee(s)".

IMPACT:

None JUSTIFICATION:

Typographical improvement to ensure applicability across the entire Entergy site. The application of SITE BOUNDARY and UNRESTRICTED AREA in NUREG 0133 and NUREG 1301 are for purposes of applicability to 10CFR20 and releases from the entire SITE.

IPEC COMBINED ODCM Rev 0 Justification Package Combines Unit 2 aDCM Rev 11 and . Unit 3 Rev 18 item # 2 of 9 Dec,2007 OBJECTIVE:

Update Instrumentation sections D3.3.1 and D3.3 .. 2 to include all IPEC effluent instrumentation by ID nomenclature, and append DSRs as required to ensure all station DSRs could be referenced.

DESCRIPTION OF CHANGES:

ODCM Surveillance Requirements (DSRs) were added to be inclusive while combining ODCMs.

Additionally, while RMS already involved specific instrument ID nomenclature, the appropriate identification for other plant (effluent) instrumentation was added to these tables, rather than to simply refer to them by name or description. For example, "R-18" was already identified for the Unit 3 liquid waste radiation monitor, but "U-181" was added to specifically identify 31 Monitor Tank level instrument.

IMPACT:

None JUSTIFICATION:

The enhanced tables more clearly demonstrate the specific instrument, while still adopting the necessary format changes for the combined aDCM in NUREG 1431 format. Specific instrument identification was added to clarify compliance with necessary surveillance requirements.

IPEC COMBINED ODCM Rev 0 Justification Package Combines Unit 2 aDCM Rev 11 and Unit 3 Rev 18 item # 3 of 9 Dec,2007 OBJECTIVE:

Modify Table D3.3.1, part 4, RWST level instruments, to list the daily channel check, but defer the periodicity of Channel Operability Tests and Calibrations to the appropriate section of unit-specific Technical Specifications DESCRIPTION OF CHANGES:

Listed the tank level instruments by ID number, and required only the daily channel check in the ODCM.

The other requirements for the RWST level instruments, such as channel calibrations, are listed in Technical Specifications 3.5.4 for both units, and Section 3.3.3 (PAM) for unit 2.

IMPACT:

None.

JUSTIFICATION:

NUREG 1301 does NOT require tank level instruments in the ODCM. Typically, however, these instruments are included nonetheless, because they may be used to quantify effluent and to help demonstrate compliance with the ten curie rule from old NUREG 0472 (prior to NUREG 1301).

For the RWST, previous versions of the ODCM(s) listed requirements that were echoed from the Technical Specifications Section 3.5.4 for both units, and Section 3.3.3 for unit 2. In this revision to the ODCM, only the daily channel checks remain in the ODCM. A footnote is added to this revision of the ODCM to reference the specific requirements of Technical Specifications for the Channel Operability Tests and Calibrations. (These tests are actually performed MORE frequently than the periodicity established in Tech Specs, per the site's PM schedule).

The applicable sections of Technical Specifications also list a requirement for Channel Check:

Unit 2 . Tech Spec 3.3.3 once per 31 days (actually performed DAILY)

Unit 3 Tech Spec 3.5.4 once per 7 days (actually performed DAILY)

A 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> frequency requirement for the Channel Check will stay in the ODCM. This conservativism is partly due to the inconsistent approach between units (per above TS reference). Another reason to maintain this conservativism is the fact that ALL tank level instruments were originally identified in Radiological Environmental Technical Specifications (NUREG 0472) for purposes'of assurance of compliance with the 10 curie rule. This rule ensured compliance with 10CFR20 release rate limitations in the event of a tank rupture and subsequent effluent concerns.

For these reasons, as well as the fact that the site PM schedule and CCR watch logs continue to apply this periodicity, the new revision of the station ODCM will maintain the daily channel check as a conservative measure to ensure compliance with somewhat divergent Technical Specification requirements for both units.

Other requirements are deferred to Technical Specifications and existing PM schedules.

IPEC COMBINED ODCM Rev 0 Justification Package Combines Unit 2 aDCM Rev 11* and Unit 3 Rev 18 item # 4 of 9 Dec, 2007 OBJECTIVE:

Add requirements for the Unit 2 VC Noble Gas Monitor (R-42) similar to those of Unit 3's R-12 in Section 03.3.2, including new footnote (g) from Unit 3's equivalent section.

DESCRIPTION OF CHANGES:

Added R-42 requirements to Section 03.3.2 (3a) and footnote (g).

IMPACT:

None.

JUSTIFICATION:

Channel checks, Operability Tests, and Calibrations for these monitors are required per Technical Specifications 3.3.6 and have been ongoing since initial licensing. However, Unit 2's initial license (NUREG 0472) did NOT require listing the VC Noble Gas monitor in this section of the Environmental Technical Specifications, and subsequently, it did not get transferred to the OOCM during ITS.

Years later, older versions of NUREG 0472 and NUREG 1301 did, in fact, include this monitor in the applicable section, and it was applied for Unit 3. Also required in this section of the NUREGs was a Source Check, which to this day, is NOT listed in the Technical Specifications.

Since an operable VC Noble Gas monitor is valuable to ensure accurate quantific.ation of VC Pressure Reliefs, the new combined OOCM uses this latter methodology of inclusion. The details of quantification technique are prescribed in footnote (g).

Application and testing of the VC Noble Gas monitor in this fashion is in keeping with NUREG 1301 and existing Technical Specification requirements.

IPEC COMBINED ODCM Rev 0 Justification Package Combines Unit 2 aDCM Rev 11 and Unit 3 Rev 18 item # 5 of 9 Dec, 2007 OBJECTIVE:

Modify Table D3.3.2, part 3, VC Noble Gas Monitors, to list th~ monthly source check, but defer the periodicity of the other surveillances (Channel Check, Operability Tests, and Calibrations) to the appropriate section of the Technical Specifications.

DESCRIPTION OF CHANGES:

f Section D3.3.2 now includes the monthly source check requirements for both unit's VC Noble Gas Monitor. While Unit 3's previous revision ALSO echoed the Channel Operability Test and Calibration periodicities, these requirements originate from the Technical Specifications and the appropriate section is referenced in new footnote (g) in this revision of the ODCM. Also included in this footnote is an explanation of the use of the noble gas monitor for VCPR quantification.

IMPACT:

None.

JUSTIFICATION:

Operability Tests and Calibrations for these monitors are required per Technical. Specifications 3.3.6.

New footnote (g) references this section.

Because the Tech Specs do NOT require a source check, and this check is valuable to ensure accurate quantification of VC Pressure Reliefs, the 31-day source check requirement is maintained in this revision to the ODCM. Footnote (g) ensures connectivity to Technical Specifications and explains the use of the noble gas monitor for VCPR quantification.

It also clarifies that the VC Noble Gas monitor is NOT required in Modes 5 or 6 during VC Ventilation when there is a continuous monitor on the plant vent. This caveat had previously only been explained in Unit 3's ODCM. It was relocated into this footnote for the merging process.

Application and testing of the VC Noble Gas monitor in this fashion is in keeping with NUREG 1301 and existing Technical Specification requirements.

IPEC COMBINED ODCM Rev 0 Justification Package Combines Unit 2 aDCM Rev 11 and Unit 3 Rev 18 item # 6 of 9 Oec,2007 OBJECTIVE:

Modify Table 03.3.2-1, parts 4 and 6, to stipulate a 24-month calibration for the sample flow rate monitors (totalizers), instead of the older reference of 18-months DESCRIPTION OF CHANGES:

Table 03.3.2-1 parts 4 and 6, for Unit 2's Plant Vent and Stack Vent sampling stations, were updated to reference a required 24-month calibration on the installed sampler flow meter (totalizer), in lieu of the older requirement for a calibration every 18 months.

IMPACT:

None.

JUSTIFICATION:

Updating this calibration requirement from 18 to 24 months was expected during ITS (Unit 2 ODCM Rev 6), but was inadvertently missed.

This requirement in previous revisions was identified with the "R" notation, which at the time, was thought to be 18-months. Since the adoption of the 2-yr fuel cycle, these type of periodicities have been re-evaluated, with most going to 24 months. Only those surveillance requirements with a track record of required added attention failed to be updated to a 24-month periodicity. These particular instrument are in fact, totalizer, not flow meters, and are used on a daily basis to track integrated flow through the vents.

Both units 2 and 3 have used these instruments for over 25 years, with calibrations performed offsite, or more recently, new meters purchased every two years, with no record of degradation or failure.

During the 80's and 90's, both units performed calibrations at an offsite vendor every 18 months. Per industry experience and vendor suggestion, it was decided that new meters were more economical than continuing to "calibrate" the old ones. Therefore, for over 6 years (longer at unit 2), we have been replacing these totalizers and applying the manufacturers certification at our design flowrate as the compliance with'this two year calibration. Performance of these totalizers continues to be excellent.

Summarizing, the bases for establishing a 2-yr calibration for these instruments across the site is:

1) the performance record of these instruments to date,

2) the fact that Unit 3's OOCM moved to 2-yr requirements in 2000,

3) the continued compliance with NUREG1301, and

4) the desire for a more consolidated site program.

IPEC COMBINED ODCM Rev 0 Justification Package Combines Unit 2 aDeM Rev 11 and Unit 3 Rev 18 item # 7 of 9 Oec,2007 OBJECTIVE:

Clarify REMP section 03.5.1 4c (broad leaf sample locations) and 03.5.2 (Land Use) to explain the application of sampling at the Site Boundary locations (highest D/O) in lieu of a garden census.

DESCRIPTION OF CHANGES:

Adopted the Unit 3 verbiage in these sections, including the use of footnotes (i) and G) on Table 3.5.1-1, and the words directly from NUREG 1301 for Section 03.5.2, Land Use Census.

IMPACT:

None.

JUSTIFICATION:

The Unit 3 aOCM was modified during implementation of GL 89-01 (per NUREG 1301) to use more precise wording, directly from the NUREG, allowing this method of collection for determining % values.

The unit 3 wording has been in service for over 6 years. However, it was not properly applied to Unit 2's ODCM during the ITS project at Unit 2, in 2003. The Unit 3 upgraded wording better connects the bases and justification for broad leaf vegetation sampling and its connection to the land use census. The applicable footnote (j) is discussed in Section 03.5.2, Land Use Census, so there is a documented connection with the bases document (directly from NUREG 1301) for the decisions regarding sampling at the site boundary in lieu of a garden census. Therefore, in this instance, the Unit 3 verbiage, as well as the footnote, were applied to the IPEC OOCM.

IPEC COMBINED ODCM Rev 0 Justification Package Combines Unit 2 aDeM Rev 11 and Unit 3 Rev 18 item # 8 of 9 Dec,2007 OBJECTIVE:

Better document the ground water monitoring program in the ODCM.

DESCRIPTION OF CHANGES:

• Modified Section 05.6 to rename the GWMP the "Radiological Ground Water Monitoring Program" (RGWMP).

• Clarified the bullets under 05.6, according to the objectives of the program.

• Added requirements for what kind of information goes into which annual report (05.6)

• Added specific detail to ODCM Part II, Sec 2.1.16, discussing quantification requirements, including a reference to Attachment J, which includes the details for calculating offsite dose.

IMPACT:

None. The RGWMP implementing documents are already in place (IP-SMM-CY-110 and NEM procedures).

JUSTIFICATION:

The refinements to the RGWMP in 2006 were added to station procedures and needed to be included in this revision of the ODCM. The direction for reporting GW data in annual reports was a direct result of the NEllndustry Groundwater Protection Initiative final guidance document (NEI 07-07). The discussion in ODeM Part II, Section 2.1.16 includes the requirements for quantifying grqundwater effluent, but details of this assessment are unique and the staff felt they would be better qaptured in an Attachment.

Therefore, Section 2.1.16 now references new Attachment J. This attachment explains the hydrological and environmental approaches to acquiring the parameters needed to perform standard dose calculations from previous sections of the ODCM. While the equations for calculating dose are the same, this attachment was felt necessary due to the unique nature of data acquisition for ground water flow rate, dilution flow, and source term data.

Once these parameters are accumulated, dose calculations proceed per approved guidance in the ODCM and its bases documents, NU REG 0133 and 1301.

IPEC COMBINED ODCM Rev 0 Justification Package Combines Unit 2 ODCM Rev 11 and Unit 3 Rev 18 item # 9 of 9 Dec,2007 OBJECTIVE:

The 5-mile cow milk pathway description and dose equations need to be returned to the ODCM, with an opening discussion in Section 3.3.4.1 to explain that the USE of this pathway is turned on and off according to the current land use census. Update other sections effected: (3.3.4.2, 3.3.4.5.d, 3.5.4, 3.5.6, and Appendix I) to show the return of applicable guidance for determining doses from the Cow-Milk pathway.

DESCRIPTION OF CHANGES:

Replaced the methodology for determining 5-mile-cow-milk pathway doses, should this pathway be initiated by the Land Use Census. Therefore, Section 3.3.4.1 opens with the explanation that doses from this pathway only apply when it is activated. Section 3.3.4.2 now shows this potential pathway again. Details of the calculation for the dose factor ( Ric) were returned to Section 3.3.4.5.d.

Discussion of interface with MET data also needed to have the pathway re-established. The MET constants were reapplied to Sections 3.5.4 and 3.5.6, for routine and short-term applications.

The last page of Appendix I was returned, showing the dose limits for this pathway in terms of uCi/sec.

I The only additions to this material over what was in earlier ODCMs are the updated MET constants and an additional note to clarify that these parameters are only to be included in dose calculations when activated by the Land Use Census.

IMPACT:

None.

JUSTIFICATION:

The cow-milk pathway in the ODCM continues to be defined per NUREG Q133, Reg Guide 1.109, and NUREG 1301. No technical changes were performed from the earlier revision of the ODCMs, which had included this pathway description, other than updating the MET data with the latest information (applied from 1992-2002), and notes describing how it is turned off or on per the land use census.

I I

The intent of this upgrade to return this information to the ODCM (despite this pathway being inactive) was to preclude an ODCM revision, should this pathway ever be enabled by a change to the Land Use Census. Identification of this pathway within the ODCM (whether or not it i~ activated), and specifically, the detailed calculation for Ric, also provides better confidence that this detail will not be lost, should the pathway come in to play in the future. Documentation of the parameters and NUREG 0133 calculation would not have to be created from scratch. Calculation of potential doses via this pathway continue to be a simple option to turn on or off in the 10CFR50 effluent tracking software (RETDAS) and therefore should remain an option and defined in the ODCM. All equations and parameters follow the prescription from NUREG 0133 and Reg Guide 1.109, as they had in Revision 13 and before.

I

Entergy Nuclear Northeast Indian Point Energy Center Units 1, 2, and 3 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Rev. 0 WRITIEN BY:

REVIEWED BY:

OSRC REVIEW:

APPROVED BY: I L-15 -o=+-

date EFFECTIVE DATE:

T able of Contents ii List of Tables and Figures vi Introduction viii PART 1- RADIOLOGICAL EFFLUENT CONTROLS D 1.0 USE AND APPLICATION D 1.1 Definitions D1.1-1 D1.2 Logical Connectors D 1.2-1 D 1.3 Completion Times D 1.2-1 D1.4 Frequency D 1.2-1 D 2.0 SAFETY LIMITS (Not Used)

D 3.0 APPLICABILITY D 3.0 ODCM Limiting Condition for Operation (DLCO) D 3.0-1 D 3.0 ODCM Surveillance Requirement (DSR) D 3.0-2 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.1 Liquid Effluents Concentration D 3.1.1-1 D 3.1.2 Liquid Effluents Dose D 3.1.2-1 D 3.1.3 Liquid Radwaste Treatment System D 3.1.3-1 D 3.1.4 Liquid Holdup Tanks D 3.1.4-1

. D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.1 Gaseous Effluents Dose Rate D 3.2.1-1 D 3.2.2 Gaseous Effluents Dose - Noble Gas D 3.2.2-1 D 3.2.3 Gaseous Effluents Dose - Iodine and Particulate D 3.2.3-1 D 3.2.4 Gaseous Radwaste Treatment System D 3.2.4-1 D 3.2.5 Ventilation Exhaust Treatment System D 3.2.5-1 D 3.2.6 Gas Storage Tanks D 3.2.6-1 D 3.3* INSTRUMENTATION D 3.3.1 Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1-1 D 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2-1 D 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE D 3.4.1 Radioactive Effluents Total Dose D3.4.1-1 IPEC ODCM ii Revision 0

PAGE D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.1 Monitoring Program D 3.5.1-1 D 3.5.2 Land Use Census D 3.5.2-1 D 3.5.3 Interlaboratory Comparison Program D 3.5.3-1 D 3.6 SOLID RADIOACTIVE WASTE D 3.6.1 Solid Radwaste Treatment System D 3.6.1-1 D4.0 DESIGN FEATURES D 4.1 UNRESTRICTED AREA D4.1-1 D 5.0 ADMINISTRATIVE CONTROLS D 5.1 Annual Radiological Environmental Operating Report D 5.1-1 D 5.2 Radioactive Effluent Release Report D 5.2-1 D 5.3 Special Reports D 5.3-1 D 5.4 Major Changes to Radwaste Treatment Systems D 5.4-1 D 5.5 Process Control Program (PCP) D 5.5-1 D 5.6 Ground Water Monitoring Program (GWMP) D 5.6-1 IPECODCM 111 Revision 0

BASES PAGE BD3.0 APPLICABILITY B 0 3.0 OOCM Limiting Condition for Operation (OLCO) B 0 3.0-1 B 0 3.0 OOCM Surveillance Requirement (OSR) B 03.0-1 B 0 3.1 RADIOACTIVE LIQUID EFFLUENTS B 03.1.1 Liquid Effluents Concentration B03.1.1-1 B 03.1.2 Liquid Effluents Dose B 03.1.2-1 B 0 3.1.3 Liquid Radwaste Treatment System B 0 3.1.3-1 B 03.1.4 Liquid Holdup Tanks B 0 3.1.4-1 B 03.2 RADIOACTIVE GASEOUS EFFLUENTS B 03.2.1 Gaseous Effluents Dose Rate B 0 3.2.1-1 B 03.2.2 Gaseous Effluents Dose - Noble Gas B 03.2.2-1 B 0 3.2.3 Gaseous Effluents Dose - Iodine and Particulate B 0 3.2.3-1 B 0 3.2.4 Gaseous Radwaste Treatment System B 03.2.4-1 B 03.2.5 Ventilation Exhaust Treatment System B 0 3.2.5-1 B 0 3.2.6 Gas Storage Tanks B 0 3.2.6-1 B 03.3 INSTRUMENTATION B 03.3.1 Radioactive Liquid Effluent Monitoring Instrumentation B 0 3.3.1-1 B 03.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation B 0 3.3.2-1 B 0 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE B 0 3.4.1 Radioactive Effluents Total Dose B03.4.1-1 B 03.5 RADIOLOGICAL ENVIRONMENTAL MONITORING B 03.5.1 Radiological Environmental Monitoring Program B03.5.1-1 B 03.5.2 Land Use Census B 03.5.2-1 B 03.5.3 Interlaboratory Comparison Program B 0 3.5.3-1 B 03.6 SOLID RADIOACTIVE WASTE B 03.6.1 Solid Radwaste Treatm,ent System B 0 3.6.1-1 IPEC OOCM IV Revision 0

PART II CALCULATIONAL METHODOLOGIES PAGE 1.0 RADIATION MONITORS AND SETPOINTS 1.1 Effluent Monitoring System Description 1 1.2 Setpoints for Airborne Effluent Monitors 1 1.3 Setpoints for Liquid Effluent Monitors 2 2.0 LIQUID EFFLUENT METHODOLOGY 2.1 Liquid Effluent Releases - General Information 6 2.2 Liquid Effluent Concentrations 9 2.3 Liquid Effluent Dose Calculation Requirements 12 2.4 Dose Methodology (Computer Calculation) 13 2.5 Backup Simplified Dose Methodology 16 2.6 Site-Specific Bio-Accumulation and Dose Factors 16 3.0 GASEOUS EFFLUENT METHODOLOGY 3.1 Gaseous Effluent Releases - General Information 25 3.2 Gaseous Effluent Dose Calculation Requirements 30 3.3 Dose Methodology (Computer Calculation) 31 3.4 Backup Simplified Dose Methodology 43 3.5 Calculation of Meteorological Dispersion Factors 46 3.6 Justification and Use of Finite Cloud Assumptions for Assessing SB Dose 51 4.0 TOTAL DOSE DETERMINATIONS 4.1 10CFR190 Dose Evaluation 100 4.2 Doses from Liquid Releases 100 4.3 Doses from Atmospheric Releases 100 4.4 Doses to MEMBERS OF THE PUBLIC Visiting the Site 101 5.0 LOWER LIMIT OF DETECTION 102 REFERENCES 104 APPENDICES Appendix A: Summary of Radiological Effluent Controls 107 Appendix B: Liquid Effluent Simplified Flow Diagram 108 Appendix C: Gaseous Effluent Simplified Flow Diagram 110 Appendix 0: Steam Partition Factor Calculation (f ) 112 Appendix E: Allowed Diluted Concentration (ADC) 113 Appendix F: Conversion Factors for Liquid Effluent Monitors 114 Appendix G: Environmental Sampling Points 115 Appendix H: Interlaboratory Comparison Program 122 Appendix I: Calculation of Allowable Release Rates for'lndian Point Units 2 and 3 123 Appendix J: Hydrological Verification of Groundwater Flow Rates 130 IPEC ODCM v Revision 0

LIST OF TABLES AND FIGURES PART 1- RADIOLOGICAL EFFLUENT CONTROLS Tables:

03.1.1-1 Radioactive Liquid Waste Sampling and Analysis 03.1.1-2 03.2.1-1 Radioactive Gaseous Waste Sampling and Analysis 03.2.1-2 o 3.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation 03.3.1-6 03.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation 03.3.2-5 03.5.1-1 Radiological Environmental Monitoring Program 03.5.1-6 o 3.5.1-2 Reporting Levels for Radioactivity Concentrations In Environmental Samples 03.5.1-9 o 3.5.1-3 Detection Capabilities for Environmental Sample Analysis 03.5.1-10 Figures:

4.1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE 04.1-2 GASEOUS AND LIQUID EFFLUENTS 4.1-2 MAP DEFINING RELEASE POINTS 04.1-3 IPEC OOCM VI Revision 0

LIST OF TABLES AND FIGURES PART 11- CALCULATIONAL METHODOLOGIES 1-1 Unit 2 Effluent Radiation Monitor System Data 4 1-2 Unit 3 Effluent Radiation Monitor System Data 5 2-1 Site Related Adult Ingestion Dose Commitment Factors 18 2-2 Site Related Teen Ingestion Dose Commitment Factors 20 2-3 Site Related Child Ingestion Dose Commitment Factors 22 2-4 Bio-Accumulation Factors for Liquid Effluent Isotopes 24 3-1a Adult Inhalation Dose Factors 52 3-1 b Teen Inhalation Dose Factors 54 3-1c Child Inhalation Dose Factors 56 3-1d Infant Inhalation Dose Factors 58 3-2 TB/Skin GP Dose Factors, w/ Half Life & Stable Element Transfer Data 60 3-3a Adult Ingestion Dose Factors 62 3-3b Teen Ingestion Dose Factors 64 3-3c Child Ingestion Dose Factors 66 3-3d Infant Ingestion Dose Factors 68 3-4 Total Body Dose Factors, Ki, from Noble Gas (Gamma) 70 3-5 Skin Dose Factors, Li, from Noble Gas (Beta) 71 3-6 Air Dose Factors, Mi, from Noble Gas (Gamma) 72 3-7 Air Dose Factors, Ni, from Noble Gas (Beta) 73 3-8 NG Dose Factors for Instantaneous and Time Average Mixtures at the SB 74 3-9 Locations of Site Boundary and Nearest Residence 75 3-10a Adult Inhalation Ri(l) 76 3-10b Teen Inhalation Ri(l) 78 3-10c Child Inhalation Ri(1) 80 3-10d Infant Inhalation Ri(l) 82 3-11a . Adult Ingestion (Leafy Vegetable) Ri(V) 84 3-11b Teen Ingestion (Leafy Vegetable) Ri(V) *86 3-11c Child Ingestion (Leafy Vegetable) Ri(V) 88 3-12a Adult Grass-Cow-Milk Pathway Ri(C) 90 3-12b Teen Grass-Cow-Milk Pathway Ri(C) 92 3-12c Child Grass-Cow-Milk Pathway Ri(C) 94 3-12d Infant Grass-Cow-Milk Pathway Ri(C) 96 3-13 Total Body and Skin Ground Plane Dose Factors Ri(G) and Ri(S) . 98 IPEC ODCM Vll Revision 0

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is established and maintained pursuant to Technical Specifications Section 5.5. for both IPEC units 2 and 3. Previous revisions of each unit's ODCM have been combined to form a station ODCM. The IPEC ODCM consists of two parts:

1) Part I, Radiological Effluent Controls, (RECS) - previously, often referred to as the Radiological Effluent Technical Specifications, or RETS (Section 3.9 of original Unit 2 Technical Specifications, and Appendix B or original Unit 3 Technical Specifications).

2) Part II, Calculational Methodologies (previously often referred to as simply the "ODCM")

Part I, Radiological Effluent Controls, includes the Radiological Effluent Control Specifications (RECS) and Radiological Environmental Monitoring Programs (REMP) required by Technical Specification 5.5. It also includes descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by each unit's Technical Specifications.

Part II, Calculational Methodologies, provides the methodology to manually calculate radiation dose rates and doses to individual persons in UNRESTRICTED AREAS in the vicinity of Indian Point due to the routine release of gaseous and liquid effluents. Long term cumulative effects are usually calculated through computer programs employing approved methodology. At IPEC, this method includes the use of ten-year averaged meteorology in the case of gaseous effluents.

Other computer programs are utilized to routinely estimate the doses due to radioactivity in liquid effluents. Manual dose calculations are performed when computerized calculations are not available. The ODCM also provides setpoint methodology that is applied to effluent monitors and optionally to other process monitors.

The sources for criteria found in the ODCM and the Radiological Effluent Control Specifications include the following:

• Liquid Effluent Release Rate: Diluted concentrations in the discharge canal are limited to ten times the EFFLUENT CONCENTRATIONS identified in 10CFR20 Appendix B.

• Airborne Effluent Release Rate: Release rates are limited to corresponding dose rate limits from NUREG 0133 and 0472.

• Integrated Radiological Effluent Dose: The design objectives of 10CFR50 Appendix I.

The ODCM and associated tracking software implements the methodology of

1) Reg. Guide 1.109 "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50 Appendix I", and

2) NUREG-0133 "Guidance Manual for Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants."

Other references may be cited to permit reasonable handling of a situation not covered by either of the two cited references. In some cases, site-specific data or reasonable simplifying assumptions are used and justified to permit formulation of more workable methodologies for implementing RECS dose calculation requirements.

IPEC ODCM viii Revision 0

Indian Point Energy Center Offsite Dose Calculation Manual PART I - RADIOACTIVE EFFLUENT CONTROLS

Definitions

'D 1.1 D 1.0 USE AND APPLICATION D 1.1 Definitions

---

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

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

Definition GASEOUS A GASEOUS RADWASTE TREATMENT SYSTEM is any system RADWASTE designed and installed to reduce radioactive gaseous effluents by TREATMENT collecting primary coolant system offgases from the primary system and SYSTEM providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

MEMBER(S) OF MEMBER(S) OF THE PUBLIC includes all persons who are not THE PUBLIC occupationally associated with the site. This category does not include employees of the utility, their contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

MAXIMUM MPCW is that concentration of a radionuclide equal to ten times the PERMISSIBLE EFFLUENT CONCENTRATIONSspecified in 10CFR20, Appendix B, CONCENTRATION Table 2, Column 2.

WATER (MPCW)

OFFSITE DOSE The OFFSITE DOSE CALCULATION MANUAL shall contain the CALCULATION current methodology and parameters used in the calculation of offsite MANUAL doses due to 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.

PRIMARY TO A PRIMARY TO SECONDARY LEAK is defined by a quantifiable leak SECONDARY rate equal to or greater than 0.5 gpd, AND LEAK a) The presence of fission or activation products in the secondary fluid, verified as Steam Generator U-tube leaks* (and not from other known contamination, such as IVSWS leaks), OR b) Tritium activity in the secondary fluid indicating an increase above historical baseline (normal diffusion) of 5.00E-6 uCi/ml or greater.

PROCESS The PROCESS CONTROL PROGRAM is a manual containing and/or CONTROL referencing selected operational information concerning the PROGRAM solidification of radioactive wastes from liquid systems.

IPECODCM D1.1-1 Revision 0

Definitions 01.1 o 1.1 Definitions PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

SITE BOUNDARY The SITE BOUNDARY is that line beyond which the land is neither owned, leased, nor otherwise controlled by the licensee(s).

SOLIDIFICATION SOLIDIFICATION is the conversion of wet wastes into a form that meets shipping and burial ground requirements.

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

UNRESTRICTED An UNRESTRICTED AREA is any area at or beyond the SITE AREA BOUNDARY, access to which is not controlled by the licensee(s) for purposes of protection of individuals from exposure to radiation and radioactive materials. (See Figure 0 4.1-1)

VENTILATION A VENTILATION EXHAUST TREATMENT SYSTEM is any system EXHAUST 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 Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required.

IPEC ODCM 01.1-2 Revision 0

Logical Connectors D 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors Logical Connectors are discussed in Section 1.2 of the Technical Specifications and are applicable throughout the Offsite Dose Calculation Manual and Bases.

1.3 Completion Times Completion Times are discussed in Section 1.3 of the Technical Specifications and are applicable throughout the Offsite Dose Calculation Manual and Bases.

1.4 Frequency Frequency is discussed in Section 1.4 of the Technical Specifications and is applicable throughout the Offsite Dose Calculation Manual and Bases IPEC ODCM D 1.2-1 Revision 0

APPLICABILITY 03.0 o 3.0 OOCM Limiting Condition for Operation (OLCO) Applicability OLCO 3.0.1 OLCOs shall be met during the MODES or other specified condition in the Applicability, except as provided in OLCO 3.0.2.

OLCO 3.0.2 Upon discovery of a failure to meet a OLCO, the Required Actions of the associated Conditions shall be met, except as provided in OLCO 3.0.5.

If the OLCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required unless otherwise stated.

OLCO 3.0.3 When a OLCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to:

a. Restore compliance with the OLCO or associated ACTIONS, and

b. Enter the Circumstances into the Corrective Action Program.

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

OLCO 3.0.3.b shall be completed if OLCO 3.0.3 is entered.

Exceptions to this Specification are stated in the individual Specifications.

OLCO 3.0.4 Not Applicable to OOCM Specifications.

OLCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to TRO 3.0.B for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

IPEC OOCM 03.0-1 Revision 0

APPLICABILITY o 3.0 o 3.0 ODCM Surveillance Requirement (OSR) Applicability OSR 3.0.1 OSRs shall be met during the MODES or other specified conditions in the Applicability for individual OLCOs, unless otherwise stated in the OSR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the OLCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the OLCO except as provided in OSR 3.0.3.

Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

OSR 3.0.2 The specified Frequency for each OSR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply.

If a Completion Time requires periodic performance on a "once per ... " basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

OSR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the OLCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the OLCO must immediately be declared not met, and the applicable Condition(s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the OLCO must immediately be declared not met, and the applicable Condition(s) must be entered.

IPEC OOCM o 3.0-2 Revision 0

Liquid Effluents Concentration 03.1.1 o 3.1 RADIOACTIVE LIQUID EFFLUENTS 03.1.1 Liquid Effluents Concentration DLCO 3.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (Figure 04.1-1) shall be limited to:

a. The MPCW concentrations as defined in 01.1 for radionuclides other than dissolved or entrained noble gases; and

b. 2 x 10.4 IJCi/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 03.1.1-1 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 03.1.1-1 are maintained within the limits of DLCO 3.1.1.

IPEC ODCM Page 3.1.1 - 1 Revision 0

Liquid Effluents Concentration D 3.1.1 Table D 3.1.1-1 (Page 1 of2)

Radioactive Liquid Waste Sampling and Analysis LOWER LIMIT LIQUID MINIMUM OF DETECTION RELEASE SAMPLE SAMPLE ANALYSIS SAMPLE ANALYSIS (LLD) in uCi/ml, TYPE TYPE FREQUENCY FREQUENCY (a),(g),(c)

1. Batch Waste Principal Release Tanks Gamma Emitters 5E-7 (b) Grab Sample Each Batch (h) Each Batch (h)

Mo-99, Ce-144 5E-6 eg, Waste Tanks, 1-131 1E-6 SG Dissolved and One batch per Draindowns, Grab Sample 31 days Entrained Gases 1E-5 31 days (h) etc (gamma emitters)

H-3 1E-5 Composite (d) Each batch (h) 31 days Gross Alpha 1E-7 Sr-89, Sr-90 5E-8 Composite (d) Each batch (h) 92 days Fe-55 1E-6

2. Continuous Releases (e)

Composite (d) Composite Principal Gamma eg, SG 7 days Emitters (c) 5E-7 Blowdown, U1 NCO, Mo-99, Ce-144 5E-6 U1 SFDS, 1-131 1E-6 etc Dissolved and Grab Sample 31 days 31 days Entrained Gases 1E-5 (gamma emitters)

H-3 1E-5 31 days Gross Alpha 1E-7 Composite (d) Composite Sr-89, Sr-90 5E-8 92 days Fe-55 1E-6

3. Service Water Gamma and Beta Per liquid batch Grab Sample 31 days 31 days (in Radiologically emitters U) releases, above.

Controlled Areas)

4. Turbine Hall Drains, SG Composite (d) Gamma and Beta Per liquid batch Composite 7 days emitters U) releases, above.

Feedwater (i)

IPEC aDCM Page 3.1.1 - 2 Revision 0

Liquid Effluents Concentration D 3.1.1 Table D 3.1.1-1 (Page 2 of2)

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. The LLD shall be determined in accordance with the methodology and parameters in the ODCM. It should be recognized that the LLD is defined as an a priori (before-the-fact) limit representing the capability of a measurement system and not as an a posterior (after-the-fact) limit for a particular measurement.

(b) A batch 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-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with an LLD of 5 x 1Q.Qf.lCi/ml. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identified, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Specification D 5.2.

(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) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(f) When operational or other limitations preclude speCific gamma radionuclide analysis in batch releases, the provisions of Regulatory Guide 1.21 (Revision 1), Appendix A Section C.4 and Appendix A, Section B shall be followed.

(g) For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentration near the LLD. Under these circumstances, the LLD may be increased in inverse proportion to the magnitude of the gamma yield (i.e., 5 x 10.7 11 where I is the photon .

abundance expressed as a decimal fraction).

(h) Complete prior to each release.

(i) Steam Generator Feedwater and Turbine Hall Drains are adequately monitored from Steam Generator Blowdown Composites. Increased monitoring need only be performed when a Primary to Secondary leak exists, as defined in RECS Section D.1.1.

0) Beta emitters need only be analyzed if gamma emitters have been positively identified.

IPEC ODCM Page 3.1.1 - 3 Revision 0

Liquid Effluents Dose D 3.1.2 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 4.1-1) shall be limited to:

a. :s: 1.5 mrem to the whole body and :s: 5 mrem to any organ during any calendar quarter; and .

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

APPLICABILITY: At all times.

ACTIONS 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 5.3, a PUBLIC from the release Special Report that of radioactive materials in (1) Identifies the cause(s) liquid effluents to for exceeding the limit(s)

UNRESTRICTED AREAS and exceeds limits. (2) Defines the corrective actions that have been taken to redl!ce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with DLCO 3.1.2.

IPECODCM D 3.1.2 -1 Revision 0

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 Immediately MEMBER OF THE a MEMBER OF THE PUBLIC from the release PUBLIC which includes of radioactive materials in contributions from direct liquid effluents exceeds 2 radiation from the units times the limits. (including outside storage tanks, etc.).

AND Immediately B.2 Verify that the limits of DLCO 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 5.3, a ~

time not met. Special Report, as defined in 10 CFR 20.2203 (a)(4), of 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.

IPEC ODCM D 3.1.2 - 2 Revision 0

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.

IPEC ODCM D 3.1.2 - 3 Revision 0

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 in operation when projected liquid effluent doses, from each unit, to UNRESTRICTED AREAS (Figure D 4.1-1) would be:

a. > 0.06 mrem to the total body in a 31 day period; or

b. >0.2 mrem to any organ in a 31 day period.

APPLICABILITY: Prior to each release.

ACTIONS 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 5.3, a treatment. Special Report that includes:

(1) An explanation of why liquid radwaste was being discharged without Projected doses due to the treatment, identification liquid effluent, from the of any inoperable unit, to UNRESTRICTED equipment or AREAS would exceed subsystems, and the limits. 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.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.1.3.1 Project the doses due to liquid effluents from each unit 31 days to UNRESTRICTED AREAS.

IPEC ODCM D 3.1.3 - 1 Revision 0

Liquid Holdup Tanks D 3.1.4 D 3.1 LIQUID EFFLUENTS D 3.1.4 Liquid Holdup Tanks DLCO 3.1.4 Radioactive liquid contained in unprotected outdoor liquid storage tanks shall be limited to ::::; 10 Curies, excluding tritium and dissolved or entrained gases.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Level of radioactivity A.1 Suspend addition of Immediately exceeds the limits in any radioactive material.

listed tank:

AND U2& U3 PWSTs A.2 Initiate measures to reduce 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> U2& U3 RWSTs content to within the limits.

U1 Waste Dist Storage Tanks AND U3 Monitor Tanks A.3 Describe the events leading to Prior to submittal of U3 CPF High/Low TDS Tanks the condition in the next Radioactive Outdoor Temporary Tanks Radioactive Effluent Release Effluent Release Report. Report SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.1.4.1 Determine that the quantity of radioactivity in 31 days, during periods outdoor liquid unprotected tanks (listed above) where radioactive liquid does not exceed the limit. is being added to the tanks, in accordance with the methodology and parameters of the ODCM IPEC ODCM D 3.1.4 - 1 Revision 0

Gaseous Effluents Dose Rate 03.2.1 o 3.2 RADIOACTIVE GASEOUS EFFLUENTS o 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 04.1-1) shall be limited to:

a. For noble gases, S 500 mrem/yr to the whole body and S 3000 mrem/yr to the skin and

b. For 1-131, tritium (H-3) and all radionuclides in particulate form with half-lives> 8 days, S 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 SITE within the limit.

BOUNDARY due to radioactive gaseous effluents exceeds limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.1.1 The dose rate from noble gases in gaseous In accordance with effluents shall be determined to be within the limits Table 0 3.2.1-1 of DLCO 3.2.1.a.

DSR 3.2.1.2 The dose rate from 1-131, H-3 and all In accordance with Table 0 3.2.1-1 radionuclides in particulate form with half-lives

> 8 days in gaseous effluents shall be determined to be within the limits of DLCO 3.2.1.b.

IPEC ODCM 03.2.1 -1 Revision 0

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 GASEOUS SAMPLE SAMPLE ANALYSIS SAMPLE LIMIT OF RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS DETECTION TYPE (LLD) Ca)

Principal Grab Noble 1E-4

1. Waste Gas Each Tank (h) Each Tank (h) Gas (NG)

Storage Tank Sample JlCi/cc Gamma Emitters (b)

Principal NG Grab Purge Each Purge (h) Each Purge (h) Gamma 1E-4 Sample

2. Emitters (b) JlCi/cc Vapor Containment PrincipalNG Press Grab 1E-4 31 days (i) 31 days (i) Gamma Relief Sample JlCi/cc Emitters (b)

3. Condenser Air Grab Principal NG 1E-4 31 days 31 days Gamma Ejector Sample JlCi/cc Emitters (b)

Principal NG 1E-4

4. Continuous Grab 31 days (c) 31 days (c) Gamma Ventilation: Sample JlCi/cc Emitters (b)

a. Main Plant H-3 1E-6 Continuous 31 days (e) H-3 Vent (unit 2) Specific JlCi/cc

b. Stack Vent Charcoal 1E-12 (unit 1) Continuous (f) 7 days (c), (g) 1-131 Sample JlCi/cc

c. Main Plant Principal Vent (unit 3) Gamma Particulate 1E-11 Continuous (f) 7 days (c), (g) Emitters (b)

d. Radioactive Sample JlCi/cc (1-131, Machine Shop Others)

Vent (unit 3)

Composite 1E-11

e. Admin Bldg Particulate Continuous (f) 31 days Gross Alpha Sample JlCi/cc Vent (unit 3)

Composite 1E-11 Particulate Continuous (f) 92 days Sr-89 / Sr-90 Sample JlCi/cc Noble Gases 1E-6 Noble Gas Continuous (f) Continuous (f) Gross Beta Monitor JlCi/cc (d) or Gamma IPEC aDCM D 3.2.1 - 2 Revision 0

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, for purposes of these Specifications, 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.

The LLD shall be determined in accordance with the methodology and parameters in the ODCM.

It should be recognized that the LLD is defined as an 9 priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular .

measurement.

(b) The principal gamma emitters for which the LLD Control applies exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. Other identifiable gamma peaks (1-131 in particulate form, for example), together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Section D 5.2.

(c) IF following a shutdown, startup, or a thermal power change (within one hour) exceeding 15 percent of RATED THERMAL POWER, analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has increased by a factor of 3 or more, AND the noble gas monitor shows that effluent activity has increased by a factor of 3 or more THEN:

1) Sample the main Plant Vent for Noble Gases within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, AND

2) Sample the main Plant Vent for Iodine and Particulate once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days with analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of sample changeout. The LLDs of these samples may be increased by a factor of 10.

(d) This value is the established Radiation Monitor sensitivity (minimum).

(e) Grab samples can be used as alternative to continuous sampling, provided the periodicity of these grab samples is increased from monthly to once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded, or at least once per 7 days when spent fuel is in the Spent Fuel Pool.

(f) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications D 3.2.1, D 3.2.2 and D 3.2.3.

(g) Continuous samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.

Additionally, !E routine Iodine sampling indicates 1-131 in any of the listed continuous streams, THEN collect a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> sample from the applicable vent (within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) for short-lived Iodine isotope quantification, on a periodicity not to exceed once per 31 days. The LLDs of these samples may be increased by a factor of 10.

(h) Complete prior to each release.

(i) Vapor Containment noble gas shall be sampled at least monthly to ensure Pressure Reliefs are quantified with an accurate isotopic mixture. Containment noble gas radiation monitor readings can be used for quantification of Pressure Reliefs, provided the monitor readings are consistent with those observed during recent (at least monthly) grab samples. Sample data is adjusted by the noble gas radiation monitor reading for purposes of quantification of each release. Should the monitor be inoperable, a containment noble gas grab sample is required within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the Pressure Relief. Should BOTH the containment noble gas and particulate monitors be inoperable, two independent samples of the VC are required prior to a Pressure Relief.

IPECODCM D 3.2.1 - 3 Revision 0

Gaseous Effluent Dose - Noble Gas D 3.2.2 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.2 Gaseous Effluent Dose - Noble Gas 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 4.1-1) shall be limited to:

a. ~ 5 mrad to the whole body from gamma radiation and

~ 10 mrad to the skin from beta radiation during any calendar quarter, and

b. ~ 10 mrad to the whole body from gamma radiation and

~ 20 mrad to the skin from beta radiation during any calendar year.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The calculated air dose at A.1 Prepare and submit to the 30 days or beyond the SITE NRC, pursuant to D 5.3, a BOUNDARY due to noble Special Report that gases released in gaseous (1) Identifies the cause(s) effluents exceeds limits. for exceeding the limit(s) and (2) Defines the corrective 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 3.2.2.

IPECODCM D 3.2.2-1 Revision 0

Gaseous Effluent Dose - Noble Gas 03.2.2 ACTIONS (continued)

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

AND Immediately B.2 Verify that the limits of DLCO 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 0 5.3, a time not met. Special Report, as defined in 10 CFR 20.2203 (a)(4), of 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.

IPEC ODCM 03.2.2 - 2 Revision O.

Gaseous Effluent Dose - Noble Gas 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.

IPEC ODCM D 3.2.2 - 3 Revision 0

Gaseous Effluent Dose - Iodine and Particulate o 3.2.3 o 3.2 RADIOACTIVE GASEOUS EFFLUENTS 03.2.3 Gaseous Effluent Dose -Iodine and Particulate DLCO 3.2.3 The dose to a MEMBER OF THE PUBLIC from 1-131, tritium, and all radionuclides in particulate form with half-lives> 8 days, in gaseous effluents, released from each unit to areas at or beyond the SITE BOUNDARY (Figure 04.1-1) shall be limited to:

a.  ::; 7.5 mrem to any organ during any calendar quarter, and

b. ~ 15 mrem to any organ during any calendar year.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The dose from 1-131, A.1 Prepare and submit to the 30 days tritium, and radioactive NRC, pursuant to 0 5.3, a material in particulate form Special Report that with half-lives> 8 days (1) Identifies the cause(s) released in gaseous for exceeding the limit(s) effluents at or beyond the SITE BOUNDARY and exceeds limits.

(2) Defines the corrective 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 3.2.3.

IPECODCM 03.2.3 -1 Revision 0

Gaseous Effluent Dose - Iodine and Particulate D 3.2.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Calculated dose to a B.1 Calculate the annual dose to Immediately MEMBER OF THE a MEMBER OF THE PUBLIC from the release PUBLIC which includes of radioactive materials in contributions from direct liquid effluents exceeds 2 radiation from the units 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 Prepare and submit to the 30 days Associated Completion NRC, pursuant to D 5.3, a time not met. Special Report, as defined in 10 CFR 20.2203 (a}(4), of 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.

IPECODCM D 3.2.3-2 Revision 0

Gaseous Effluent Dose - Iodine and Particulate 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 1-131, tritium, and radioactive material in particulate form with half-lives> 8 days.

IPEC aDCM D 3.2.3 - 3 Revision 0

Gaseous Radwaste Treatment System 03.2.4 o 3.2 RADIOACTIVE GASEOUS EFFLUENTS 03.2.4 Gaseous Radwaste Treatment System DLCO 3.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation when projected gaseous effluent doses, from each unit, at and beyond the SITE BOUNDARY (Figure 04.1-1) would be:

a. > 0.2 mrad for gamma radiation; and

b. > 0.4 mrad for beta radiation in a 31 day period.

APPLICABILITY: Prior to each release.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive gaseous A.1 Prepare and submit to the 30 days waste is being discharged NRC, pursuant to 0 5.3, a without treatment. Special Report that includes the following: ,

AND (1) Identification of any Projected doses due to the inoperable equipment or gaseous effluent, from the subsystems and the unit, at and beyond the reason for the SITE BOUNDARY would inoperability, exceed limits.

(2) Action(s) taken to restore the inoperable equipment to OPERABLE status, and (3) Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.4.1 Project the doses due to gaseous effluents from each 31 days unit at and beyond the SITE BOUNDARY.

IPEC ODCM 03.2.4 -1 Revision 0

Ventilation Exhaust Treatment System D 3.2.5 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.5 Ventilation Exhaust Treatment System OLCO 3.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM shall be in operation when projected gaseous effluent doses, from each unit, at and beyond the SITE BOUNDARY (Figure D 4.1-1) would be:

a. > 0.2 mrad air dose from gamma radiation; and

b. > 0.4 mrad air dose from beta radiation in a 31 day period; or

c. > 0.3 mrem to any organ in a 31 day period.

APPLICABILITY: Prior to each release.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive gaseous A.1 Prepare and submit to the 30 days waste is being discharged NRC, pursuant to D 5.3, a without treatment. Special Report that includes the following:

(1) Identification of any inoperable equipment or Projected doses due to subsystems and the gaseous effluent, from reason for the each unit, to areas at or inoperability, beyond the SITE BOUNDARY would (2) Action(s) taken to restore exceed limits. the inoperable equipment to OPERABLE status, and (3) Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.5.1 Project the doses from gaseous releases from each 31 days unit to areas at and beyond the SITE BOUNDARY when the GASEOUS RADWASTE TREATMENT SYSTEMS are not being fully utilized.

IPEC ODCM D 3.2.5-1 Revision 0

Gas Storage Tanks 03.2.6 o 3.2 GASEOUS EFFLUENTS o 3.2.6 Gas Storage Tanks DLCO 3.2.6 The radioactivity contained in each gas storage tank shall be limited to the following unit-specific curie levels of noble gas (considered as Xe-133):

Unit 2: ~ 29,761 Curies Unit 3: ~50,OOO Curies APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Level of radioactivity A.1 Suspend addition of Immediately exceeds the limits. radioactive material.

A.2 Reduce content to within the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.2.6.1 The quantity of radioactive material contained in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during each gas storage tank shall be determined to be addition of within the limits above, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> radioactive when radioactive materials are being added to the material to the tank in accordance with the methodology and tank parameters in the ODCM.

IPEC ODCM 03.2.6 -1 Revision a

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 D 3.3 INSTRUMENTATION D 3.3.1 Radioactive Liquid Effluent Monitoring Instrumentation DLCO 3.3.1 The unit-specific 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 for the applicable unit.

ACTIONS

---

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

Separate condition entry is allowed for each channel.

IPECODCM D 3.3.1 -1 Revision 0

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 Immediately channels inoperable. referenced in Table D 3.3.1-1 for the channel.

AND B.2 Restore inoperable 30 days channel(s) to OPERABLE status.

C. As required by Required C.1 Analyze at least 2 Prior to initiating a Action B.1 and referenced independent samples in release in Table D 3.3.1-1. accordance with Table D

(

3.1.1-1.

AND C.2 -----------N 0 TE ----------------

Verification Action will be performed by at least 2 separate technically qualified members of the facility staff.

Independently verify the Prior to initiating a release rate calculations and release discharge line valving.

D. As required by Required D.1 Collect and analyze grab 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 IlCilml.

Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter IPEC ODCM D 3.3.1 - 2 Revision 0

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Collect and analyze grab 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Action B.1 and samples for radioactivity at referenced in a limit of detection of at AND Table D 3.3.1-1. least 5 x 10.7 !-lCi/ml, when specific activity is Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

> 0.01 !-lCi/gm DOSE thereafter EQUIVALENT 1-131.

OR I

E.2 Collect and analyze grab 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> samples for radioactivity at a limit of detection of at AND least 5 x 10.7 !-lCi/ml, when specific activity is Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

s; 0.01 !-lCi/gm DOSE thereafter EQUIVALENT 1-131.

F. As required by Required F.1 ---------------NO TE ------------

Action B.1 and Pump performance curves 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> referenced in generated in place may be Table D 3.3.1-1. used to estimate flow. AND Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Estimate the flow rate during thereafter actual releases.

G. As required by Required G.1 Estimate tank liquid level. Immediately Action B.1 and referenced in AND Table D 3.3.1-1.

During liquid additions to the tank H. Required Action B.2 and H.1 Explain in the next In accordance with associated Completion Radioactive Effluent Radioactive Effluent Time not met. Release Report why the Release Report inoperability was not corrected in a timely manner.

IPEC ODCM D 3.3.1 - 3 Revision 0

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. Required Action and 1.1 Suspend liquid effluent Immediately associated Completion releases monitored by the Time for Condition C, D, E, inoperable channel(s).

or F not met.

J. Required Action and J.1 Suspend liquid additions to Immediately associated Completion the tank monitored by the Time for Condition G not inoperable channel(s).

met"-

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DSR 3.3.1.2 Perform CHANNEL CHECK by verifying indication of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on any 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 OPERATIONAL TEST 92 days IPEC ODCM D 3.3.1 - 4 Revision 0

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY DSR 3.3.1.6 Perform CHANNEL OPERATIONAL TEST. The 92 days CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation (or control panel indications/display) occurs if the instrument indicates measured levels above the alarm/trip setpoint DSR 3.3.1.7 Perform CHANNEL OPERATIONAL TEST. The 92 days CHANNEL OPERATIONAL TEST shall also demonstrate control room alarm annunciation (or control panel indications/display) occurs if any of the following conditions exist, instrument indicates measured levels above the alarm setpoint, instrument controls not set in operate mode.

DSR 3.3.1.8 Perform CHANNEL OPERATIONAL TEST 24 months DSR 3.3.1.9 Perform CHANNEL CALIBRATION 24 months IPECODCM D 3.3.1 - 5 Revision 0

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 Table D 3.3.1-1 (page 1 of 3)

Radioactive Liquid Effluent Monitoring Instrumentation - Units 1, 2, and 3 CONDITIONS APPLICABILITY REQUIRED REFERENCED OR OTHER CHANNELS SURVEILLANCE INSTRUMENT FROM SPECIFIED PER REQUIREMENTS REQUIRED CONDITIONS INSTRUMENT ACTION B.1

1. Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release DSR 3.3.1.1

a. Unit 2 Liquid Radioactive (a) C DSR 3.3.1.3 Waste Effluent Line (R-54) DSR 3.3.1.6 (e)

DSR 3.3.1.9 (d)

DSR 3.3.1.1

b. Unit 2 Steam Generator Effluent (a) (i) E DSR 3.3.1.4 Blowdown Line (R-49) DSR 3.3.1.6 (e)

DSR 3.3.1.9 (d)

DSR 3.3.1.1

c. Unit 3 Liquid Radioactive (a) C DSR 3.3.1.3 Waste Effluent Line (R-18) DSR 3.3.1.6 (e)

DSR 3.3.1.9 (d)

DSR 3.3.1.1 (h)

d. Unit 3 Condensate Polisher Facility (a) C DSR 3.3.1.4 (h)

(CPF) Waste Line (R-61) DSR 3.3.1.6 (e)

DSR3.3.1.9 (d)

DSR 3.3.1.1

e. Unit 3 Steam Generator Effluent (a) (i) E DSR 3.3.1.4 Blowdown Line (R-19) DSR 3.3.1.6 (e)

DSR 3.3.1.9 (d)

2. Gross Beta or Gamma Radioactivity Monitors Providing Alarm but NOT Providing Automatic Termination of Release

a. Unit 1 or 2 Service Water or River Water Effluent Lines

- VC FCU (R-46 or R-53) DSR3.3.1.1 (a) 1 (g) D DSR 3.3.1.4

- 21 CCW HX (R-39) DSR 3.3.1.7 (e)

- 22 CCW HX (R-40) DSR 3.3.1.9 (d)

- SBBPS HX (R-52)

DSR 3.3.1.1

b. Unit 1 Secondary Boiler (a) D DSR 3.3.1.4 Blowdown Effluent Line (R-51) DSR 3.3.1.7 (e)

DSR 3.3.1.9 (d)

c. Unit 1 Sphere Foundation DSR 3.3.1.1 Drain Sump Effluent Line (R-62) (a) D DSR 3.3.1.4 DSR 3.3.1.7 (e)

DSR 3.3.1.9 (d)

d. Unit 3 Service Water Effluent Lines DSR 3.3.1.1

- SW for VC FCU return (a) 1 (g) D DSR 3.3.1.4 (R-16A or R-16B) DSR 3.3.1.7 (e)

DSR 3.3.1.9 (d)

- SW for CCW Heat DSR 3.3.1.1 Exchanger (R-23) (a) D DSR 3.3.1.4 DSR 3.3.1.7 (e)

DSR 3.3.1.9 (d)

IPEC aDCM D 3.3.1 - 6 Revision 0

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 Table D 3.3.1-1 (page 2 of 3)

Radioactive Liquid Effluent Monitoring Instrumentation - Units 1,2, and 3 APPLICABILITY REQUIRED CONDITIONS OR OTHER CHANNELS REFERENCED SURVEILLANCE INSTRUMENT SPECIFIED PER FROM REQUIRED REQUIREMENTS CONDITIONS INSTRUMENT ACTION B.1

3. Flow Rate Measurement Devices DSR 3.3.1.2

a. Unit 2 Liquid Radwaste (a) F DSR 3.3.1.5 Effluent Line DSR 3.3.1.9 (CT971-FRE, CT971-FIE)

b. Unit 2 Steam Generator DSR 3.3.1.2 Blowdown Effluent Line (a) (i) F DSR3.3.1.5 (FI-1241 to FI-1244, and DSR 3.3.1.9 FT-1241 to FT-1244)

e. Unit 1 North Curtain Drain (a) F DSR 3.3.1.2 Effluent Line (f) DSR 3.3.1.9 (LW-FE-12)

d. Unit 1 Sphere Foundation (a) F DSR 3.3.1.2 Drain Sump (f) DSR 3.3.1.9 (LW-FZ-100)

DSR 3.3.1.2

e. Unit 3 Liquid Radwaste (a) F DSR 3.3.1.5 Effluent Line DSR 3.3.1.9 (FE-1064, FI-1064)

DSR 3.3.1.2

f. Unit 3 Cond Polisher (CPF) (a) F DSR 3.3.1.5 Effluent Line (3LG-FIT-41, DSR 3.3.1.9 (3LG-FM-41,3LG-FR-41)

g. Unit 3 Steam Generator (a) (i) F DSR 3.3.1.2 Blowdown Effluent Line DSR 3.3.1.5 (FT-545 to 548, FIR-543,544) DSR 3.3.1.9

4. Tank Level Indicating Devices (e)

DSR 3.3.1.1 (b)

a. Unit 1 Waste Distillate (a) G DSR 3.3.1.5 Storage Tank #13 DSR 3.3.1.9 (CT967-LlE-1, LlE-2)

b. Unit 1 Waste Distillate DSR 3.3.1.1 (b)

Storage Tank #14 (a) G DSR 3.3.1.5 (CT974-LlE-1, LlE-2) DSR 3.3.1.9

e. Unit 2 Primary Water DSR 3.3.1.1 (b)

Storage Tank (a) G DSR 3.3.1.5 (LT-1131, LI-1131) DSR 3.3.1.9

d. Unit 2 Refueling Water (a)

Storage Tank G DSR 3.3.1.1 (b)

(LI-920, L T-920, L T-5751) 0)

e. Unit 3 Refueling Water (a)

Storage Tank G DSR 3.3.1.1 (b)

(LI-920A, LI-920B) (j)

IPEC aDCM D 3.3.1 -7 Revision 0

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 Table D 3.3.1-1 (page 3 of 3)

Radioactive Liquid Effluent Monitoring Instrumentation - Units 1, 2, and 3 APPLICABILITY REQUIRED CONDITIONS OR OTHER CHANNELS REFERENCED SURVEILLANCE INSTRUMENT SPECIFIED PER FROM REQUIRED REQUIREMENTS CONDITIONS INSTRUMENT ACTION B.1

4. Tank Level Indicating Devices (c) (continued)

DSR 3.3.1.1 (b)

f. Unit 3 Primary Water Storage (a) G DSR 3.3.1.8 Tank (LT-1131, L1-1131) DSR 3.3.1.9 DSR 3.3.1.1 (b)

g. Unit 3 Monitor Tank #31 (a) G DSR 3.3.1.8 (L1-181) DSR 3.3.1.9 DSR 3.3.1.1 (b)

h. Unit 3 Monitor Tank #32 (a) G DSR 3.3.1.8 (L1-180) DSR 3.3.1.9 DSR 3.3.1.1 (b)

i. Unit 3 CPF High Total (a) G DSR 3.3.1.8 Dissolved Solids Tank DSR 3.3.1.9 (h)

(3-LG-L1-12)

DSR 3.3.1.1 (b)

j. Unit 3 CPF Low Total (a) G DSR 3.3.1.8 Dissolved Solids Tank DSR 3.3.1.9 (h)

(3-LG-L1-22)

NOTES (a) Applicability is defined as anytime releases are being performed via this pathway. During periods of release, channels shall be OPERABLE and in service on a continuous basis, except that outages are permitted, within the time frame of the specified action, for the purpose of maintenance and performance of required CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, or CHANNEL OPERATIONAL TEST.

(b) During liquid addition to the associated tank.

(c) Tanks included in this Specification 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, as specified in RECS Section D 3.1.4.

(d) Radioactive calibration standards used for CHANNEL CALIBRATIONS shall be analyzed with instrumentation which is calibrated NIST traceable standards. Standards from suppliers who participate in approved measurement assurance activities with NIST are acceptable.

(e) Test will include: Low sample flow, no counts per minute failure, and alarm setpoint reached. The CHANNEL OPERATIONAL TEST does not include testing or trouble shooting, nor the performance of any equipment diagnostic capabilities provided with the monitor installation.

(f) Flow rate for these continuous intermittent release pathways is normally obtained from a flow totalizer on the system outlet.

(g) One instrument per operating Service Water system is required. For example, unit-specific VC FCU monitors are redundant and compensatory actions are only required when BOTH monitors are OOS for anyone unit. However, for Unit 2's CCW HX's (R-39 and R-40), the appropriate SW monitor is required to be in service anytime the effected loop is in service.

r (h) Channel and Source Checks for R-61 in Unit 3's Condensate Polisher Facility (CPF) are required only during or after a primary to secondary leak, as defined in RECS Section 1. Surveillances on the flow meter and level instruments are performed to be prepared for this type of leak. The level instrument calibration is also required by the SPDES permit.

(i) Applicable for Continuous Steam Generator Blowdown to the environment only. These requirements are not applicable for Batch Steam Generator Draindowns.

U) Surveillance requirements for the RWST level instruments (CHECKS and CALIBRATIONS) are prescribed in Technical Specifications (Sections 3.3.3 and 3.5.4 for Unit 2 and Section 3.5.4 for Unit 3). However, the requirement for a daily channel check (when making additions to the tank, per earlier footnote b) is maintained in the ODCM per the original licensing bases (NUREG 0472) and the 10 curie rule.

IPEC aDCM D 3.3.1 - 8 Revision 0

Radioactive Gaseous Effluent Monitoring Instrumentation o 3.3.2 o 3.3 INSTRUMENTATION o 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation DLCO 3.3.2 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 0 J.3.2-1 shall be OPERABLE with:

a. The minimum OPERABLE channel(s) in servipe.

h. The alarm/trip setpoints set to ensure that the limits of DLCO 3.2.1 are not exceeded. .

APPLICABILITY: According to Table 0 3.3.2-1.

ACTIONS

---

NOT E-------------------------------------------------------

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 channel alarm/trip setpoint effluents monitored by the less conservative than affected channel.

required.

OR A.2 Declare the channel Immediately inoperable.

OR A.3 Change the setpoint so it is Immediately acceptably conservative.

B. One or more channels B.1 Enter the Condition Immediately inoperable. referenced in Table 0 3.3.2-1 for the channel.

AND B.2 Restore inoperable 30 days channel(s) to OPERABLE status.

IPEC ODCM 03.3.2 -1 Revision 0

Radioactive Gaseous Effluent Monitoring Instrumentation 03.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. As required by Required Action B.1 and referenced C.1 Take grab samples. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in Table 03.3.2-1.

Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND C.2 Analyze samples for gross 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from time of activity. sampling completion

(\

D. As required by Required 0.1 Estimate the flow rate for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Action B.1 and referenced the inoperable channel(s).

in Table 0 3.3.2-1. AND Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter E. As required by Required E.1 Continuously collect 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Action B.1 and referenced samples using auxiliary in Table 0 3.3.2-1. sampling equipment as required in Table 03.2.1-1.

F. As required by Required F.1 Determine the radioactive 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Action B.1 and referenced content of the receiving in Table 0 3.3.2-1. gas decay tank is in AND compliance with DLCO 3.2.1. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter IPEC ODCM 03.3.2 - 2 Revision 0

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required G.1 Analyze at least 2 Prior to initiating a Action B.1 and referenced independent samples in gas decay tank in Table D 3.3.2-1, for gas accordance with release decay tank releases. Table D 3.2.1-1.

AND G.2 -----------N 0 TE ----------------

Verification Action will be performed by at least 2 separate technically qualified members of the facility staff.

Independently verify the Prior to initiating a

, gas decay tank release rate calculations and discharge line valving. release H. Required Action B.2 and H.1 Explain in the next In accordance with associated Completion Radioactive Effluent Radioactive Effluent Time !,,)ot met. Release Report why the Release Report inoperability was not frequency corrected in a timely manner.

I. Required Action and 1.1 Suspend gaseous effluent Immediately associated Completion releases monitored by the Time for Condition C, D, E inoperable channel(s).

or F not met.

J. Required Action and J.1 Suspend gaseous effluent Immediately associated Completion releases from Waste Gas Time for Condition G not Holdup System.

met.

K. As required by Required K.1 Take Noble Gas grab Prior to venting Action B.1 and referenced* samples and analyze for Vapor Containment in Table D 3.3.2-1 (in gross activity. (VC)

MODES 1-4 only).

K.2 Immediately suspend

\ PURGING the VC.

IPEC ODCM D 3.3.2 - 3 Revision 0

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DSR 3.3.2.2 Perform CHANNEL CHECK. 7 days DSR 3.3.2.3 Perform SOURCE CHECK. Prior to release DSR 3.3.2.4 Perform SOURCE CHECK. 31 days DSR 3.3.2.5 Perform CHANNEL OPERATIONAL TEST. 92 days The test shall include 1) low sample flow, 2) no counts ~er minute failure, 3) a demonstration 0 the automa ic isolation capability of this fcathwar, and that control room alarm annunciation or con rol panel indications/disPla Y occurs if the instrument indicates b

measured levels a ove the alarm/trip setpoint.

This test does NOT include testin~ of troubleshootin~

and equipment diagnostic capabl ities provided wit the monitor installation.

DSR 3.3.2.6 Perform CHANNEL OPERATIONAL TEST. 92 days The test shall include 1) low sample flow (except for Condenser Air Ejector monitors), 2~ no counts per minute failure, 3) a demonstration t at control room I alarm annunciation (or control panel indications or display) occurs if the instrument indicates measured levels above the alarm setpoint, or the instrument controls are not set in operate mode.

This test does NOT include testin~ of troubleshootin~

and equipment diagnostic capabl ities provided wit the monitor installation.

DSR 3.3.2.7 Perform CHANNEL CALIBRATION. 24 months IPEC ODCM D 3.3.2-4 Revision 0

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 1 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation - Units 1,2, and 3 CONDITIONS INSTRUMENT APPLICABILITY REQUIRED REFERENCED SURVEILLANCE and OR OTHER CHANNELS FROM REQUIREMENTS APPLICABLE UNIT SPECIFIED PER (1,2, or 3) REQUIRED CONDITIONS INSTRUMENT ACTION B.1

1. Waste Gas Holdup System

a. Unit 2 Noble Gas DSR 3.3.2.1 Monitor, providing (b) 1 F DSR 3.3.2.4 Alarm, (R-SO) DSR 3.3.2.6 DSR 3.3.2.7 (c)

b. Unit 3 Noble Gas DSR 3.3.2.1 (b) 1 F DSR 3.3.2.4 Monitor, providing DSR 3.3.2.6 Alarm, (R-20) DSR 3.3.2.7 (c)

2. Condenser Air Evacuation .System DSR 3.3.2.1

a. Unit 2 Noble Gas Activity, (R-4S) (a) 1 C DSR 3.3.2.4 DSR 3.3.2.6 (d)

DSR 3.3.2.7 (c)

b. Unit 3 Noble Gas Activity, (R-1S) DSR 3.3.2.1 (a) 1 C DSR 3.3.2.4 DSR 3.3.2.6 (d)

DSR 3.3.2.7 (c)

3. Vapor Containment Atmosphere

a. Unit 2 Noble Gas Activity Monitor, providing ALARM and automatic (a) 1 K DSR 3.3.2.4 termination of release (g)

(R-42)

b. Unit 3 Noble Gas Activity (a) 1 K DSR 3.3.2.4 Monitor, providing (g)

ALARM and automatic termination of release (R-12)

IPEC aDCM D 3.3.2 - 5 Revision 0

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 2 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation - Units 1, 2, and 3 CONDITIONS INSTRUMENT APPLICABILITY REQUIRED REFERENCED SURVEILLANCE and OR OTHER CHANNELS FROM REQU IREMENTS APPLICABLE UNIT SPECIFIED PER REQUIRED (1.2. or 3) CONDITIONS INSTRUMENT ACTION B.1

4. Unit 2 Main Plant Vent Radiation Monitor:

DSR 3.3.2.1

a. Noble Gas Monitor (R-44) (a) & (b) 1 C&G DSR 3.3.2.4 DSR 3.3.2.5 DSR 3.3.2.7 (c)

Other Monitoring Equipment:

b. Iodine Sampler (a) 1 E DSR 3.3.2.2

c. Particulate Sampler (a) 1 E DSR 3.3.2.2

d. Process Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (SV2-DPT, SV2-1-DPT, SV2-DPI) DSR 3.3.2.7

e. Sample Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (Chem Totalizer) DSR 3.3.2.7

5. Unit 3 Main Plant Vent Radiation Monitor:

DSR 3.3.2.1

a. Noble Gas Monitor(s) (a) & (b) 1 C&G (R-14 or R-27) DSR 3.3.2.4 DSR 3.3.2.5 DSR 3.3.2.7 (c)

Other Monitoring Equipment:

b. Iodine Sampler (a) 1 E DSR 3.3.2.2

c. Particulate Sampler (a) 1 E DSR 3.3.2.2

d. Process Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (from R-27's Kurz probes and DSR 3.3.2.7 RMBO processing computer)

(a) 1 D DSR 3.3.2.1

e. Sample Flow-Rate Monitor DSR 3.3.2.7 (Chem Totalizer)

IPEC aDCM D 3.3.2 - 6 Revision 0

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 3 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation - Units 1, 2, and 3 CONDITIONS INSTRUMENT APPLICABILITY REQUIRED REFERENCED SURVEILLANCE and OR OTHER CHANNELS APPLICABLE UNIT SPECIFIED FROM REQU IREMENTS PER (1,2, or 3) CONDITIONS REQUIRED INSTRUMENT ACTION B.1

6. Unit 1 Stack Vent Radiation Monitor:

DSR 3.3.2.1

a. Noble Gas Monitor (R-60) (a) 1 C DSR 3.3.2.4 DSR 3.3.2.6 DSR 3.3.2.7 (c)

Other Monitoring Equipment:

b. Iodine Sampler (a) 1 E DSR 3.3.2.2

c. Particulate Sampler (a) 1 E DSR 3.3.2.2

d. Process Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (SV1-DPT, SV1-FR) DSR 3.3.2.7

e. Sample Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (Chern Totalizer) DSR 3.3.2.7

7. Unit 3 Radioactive Machine Shop (RAMS) Vent Radiation Monitor: DSR 3.3.2.1 DSR 3.3.2.4

a. Noble Gas Monitor (R-59) (a) 1 C DSR 3.3.2.6 DSR 3.3.2.7 (c)

Other Monitoring Equipment:

b. Iodine Sampler (a) 1 E DSR 3.3.2.2

c. Particulate Sampler (a) 1 E DSR 3.3.2.2

d. Process Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (from R-59's RM80 processor) DSR 3.3.2.7

e. Sample Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (Chern Totalizer) DSR 3.3.2.7 IPECODCM D 3.3.2-7 Revision 0

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 4 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation - Units 1, 2, and 3 INSTRUMENT APPLICABILITY CONDITIONS REQUIRED REFERENCED SURVEILLANCE and OR OTHER CHANNELS APPLICABLE UNIT FROM REQUIREMENTS SPECIFIED PER (1,2, or 3) CONDITIONS REQUIRED INSTRUMENT ACTION B.1

8. Unit 3 Admin Bldg Vent (f)

Radiation Monitor: DSR 3.3.2.1 DSR 3.3.2.4

a. Noble Gas Monitor (R-46) (a) 1 C DSR 3.3.2.6 DSR 3.3.2.7 (c)

Other Monitoring Equipment:

b. Iodine Sampler (a) 1 E DSR 3.3.2.2

c. Particulate Sampler (a) 1 E DSR 3.3.2.2

d. Sample Flow-Rate Monitor (a) 1 D DSR 3.3.2.1 (Chern Totalizer) DSR 3.3.2.7 NOTES (a) During release via this pathway. Channels shall be OPERABLE and in service on a continuous basis, except that outages are permitted, within the time frame of the specified action for the purpose of maintenance and performance of required CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, or CHANNEL OPERATIONAL*TEST.

(b) During waste gas holdup system operation (treatment for primary system off-gases).

(c) Radioactive Calibration Standards used for channel calibrations shall be traceable to the National Institute of Standards and Technology (NIST) or an aliquot of calibration gas shall be analyzed with instrumentation which is calibrated with NIST traceable standards. Standards from suppliers who participate in measurement assurance activities with NIST are acceptable.

(d) The CHANNEL OPERATIONAL TEST for the Condenser Air Ejector monitors does NOT require a loss of sample flow test. .

(e) The main Plant Vents for Units 2 and 3 monitors the Fuel Storage Building vents, in addition to ventilation from the Primary Auxiliary Buildings.

(f) The Unit 3 Admin Bldg Controlled Area ventilation system does NOT have an installed process flow meter.

Default fan flow is used in lieu of a measurement, per ODCM Part II, Section 3.1.11.

(g) Most surveillance requirements for Vapor Containment monitors are located in Technical Specifications, Section 3.3.6. Source checks, however, are NOT required per Technical Specifications. Since these checks are valuable to ensure accurate quantification of VC Pressure Reliefs (as described below), a monthly source check requirement is listed here, in addition to the requirements of Technical Specifications.

Grab samples of the Vapor Containment atmosphere are routinely collected at least monthly and compared to the gas monitor for use in quantification of VC Pressure Reliefs (by scaling the monitor reading for each release to the reading obtained at time of grab sample). If the noble gas monitor is inoperable, a grab samples shall be taken and analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to performing a Pressure Relief. During containment building ventilation in Modes 5 or 6, continuous monitoring and automatic termination of release is not required. In this condition, one continuous monitor at the Plant Vent is sufficient.

IPEC ODCM D 3.3.2 - 8 Revision 0

Radioactive Effluents Total Dose D 3.4.1 D 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE D 3.4.1 Radioactive Effluents Total Dose DLCO 3.4.1 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 CONDITION REQUIRED ACTION COMPLETION TIME A. Estimated dose or dose A.1 Verify the condition resulting Immediately commitment due to direct in doses exceeding these radiation and the release limits has been corrected.

of radioactive materials in liquid or gaseous effluents exceeds the limits.

B. Required Action and B.1 --------------N OTE -------------

associated Completion This is the Special Report Time not met. required by D 3.1.2, D 3.2.2, or D 3.2.3 supplemented with the following.

Submit a Special Report, 30 days pursuant to D 5.3, including a request for a variance in accordance with the provisions of 40 CFR 190.

This submission is considered a timely request, and a variance is granted until staff action on the request is complete.

IPEC ODCM D3.4.1-1 Revision 0

Radioactive Effluents Total Dose D 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.4.1.1 Perform a cumulative dose calculation due to 12 months radioactive material in gaseous and liquid effluents to determine compliance with DLCa 3.4.1.

IPEC aDCM D 3.4.1 - 2 Revision 0

Radiological Environmental Monitoring Program D 3.5.1 D 3.5 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 CONDITION REQUIRED ACTION COMPLETION TIME A. Radiological A.1 Prepare and submit to the In accordance with Environmental Monitoring NRC in the Annual the Annual Program not conducted as Radiological Environmental Radiological specified in Operating Report, a Environmental Table D 3.5.1-1. description of the reasons Operating Report for not conducting the frequency program as required and the plans for preventing a recurrence.

B. Level of radioactivitY in an B.1 ------------N 0 TES-------------

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

Table D 3.5.1-2 when averaged over any 2. For radionuclides other calendar quarter. than those in Table D 3.5.1-2, this report shall OR indicate the methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC.

IPEC ODCM D 3.5.1 -1 Revision 0

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 30 days radionuclides in Table NRC, pursuant to D 5.3, a D 3.5.1-2 are detected in Special Report that the environmental (1) Identifies the cause(s) for sampling medium and exceeding the limit(s) and Concentration 1 + (2) Defines the corrective reporting level 1 actions to be taken to reduce radioactive concentration 2 + ... ~ 1.0. effluents so that the reporting level 2 potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Radionuclides other than SpeCifications D 3.1.2, those in Table D 3.5.1-2 D 3.2.2, or D 3.2.3.

are detected in an environmental sampling OR

- medium at a specified location which are the B.2 ------------NOTE S-------------

result of plant effluents and 1.0nly applicable if the the potential annual dose radioactivity/radionuclides to a MEMBER OF THE are not the result of plant PUBLIC from all effluents.

radionuclides is ~ the calendar year limits of 2. For radionuclides other Specifications D 3.1.2, than those in Table D 3.2.2 or D 3.2.3. D 3.5.1-2, this report shall indicate the methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC.

In accordance with Report and describe the the Annual condition in the Annual Radiological Radiological Environmental Environmental Operating Report. Operating Report frequency IPEC ODCM D 3.5.1 - 2 Revision 0

Radiological Environmental Monitoring Program D 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Milk or fresh lea~ C.1 Identify specific locations 30 days vegetation samp es for obtaining replacement unavailable from one or sam~les ana add them to more of the sample the adiological locations required by Environmental Monitoring Table D 3.5.1-1. Program.

AND C.2 Delete the specific 30 days locations from which samples were unavailable from the Radiol~ical Environmental onitoring Program.

AND C.3 Pursuant to D 5.2, submit In accordance with in the next Radioactive the Radioactive Effluent Release Report Effluent Release documentation for a Report change in the ODCM reflectin~ the new location s) with supporting information identifyinilithe cause of the unavaila ility of samples and justifying the selection of the new location(s) for obtaining samples.

D. Environmental samples D.1 Ensure all efforts are made Prior to the end of required in Table D 3.5.1-1 to complete corrective the next sampling are unobtainable due to action(s). period samplin equipment /

n malfunc Ions. AND D.2 Report all deviations from In accordance with the sam~ling schedule in the the Annual Annual adlological Radiological Environmental perating Environmental Report. Operating Report IPEC ODCM D 3.5.1 - 3 Revision 0

Radiological Environmental Monitoring Program D 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Samples required by Table E.1 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.

E.2 Make appropriate 30 days substitutions in the Radiological Environmental Monitoring Program.

AND E.3 Submit in the next In accordance with Radioactive Effluent the Radioactive Release Report Effluent Release documentation for a Report change in the ODCM 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 .

. IPEC ODCM D 3.5.1 - 4 Revision 0

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.

IPEC aDCM D 3.5.1 - 5 Revision 0

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

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

1. Direct 41 routine (1) An inner ring of stations Quarterly Gamma dose quarterly Radiation monitoring (DR1-DR16), one in each stations (b) meteorological sector in (DR1-DR41) the general area of the SITE BOUNDARY (2) An outer ring of stations (DR17-DR32), one in each meteorological sector in the 6 to 8 km range from the site (3) The balance of the stations (DR33-DR41), should be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations

2. Airborne Siocations (1 ) 3 samples (A1-A3) from Continuous sampler Radioiodine canister:

Radioiodine (A1-AS) offsite locations close to operation with sample Analyze weekly for 1-131 and the site boundary in collection weekly or Particulates different sectors, of the more frequently if Particulate sampler:

highest calculated annual (1 ) Analyze for gross beta average ground level D/Q required by dust loading radioactivity ~ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change (2) 1 sample (A4) from the (d).

vicinity of an established (2) Perform gamma isotopic year-round community analysis on each sample having the highest (e) in which gross beta calculated annual average activity is > 10 times the ground level D/Q previous yearly mean of control samples.

(3) 1 sample (AS) from a control location, 1S-30 km (3) Gamma isotopic analysis of composite distant and in the least sample (e) (by location) prevalent wind direction (c) once per 3 months.

3. Waterborne

a. Surface (f) 1 sample Upstream (Wa 1) Composite sample (1 ) Gamma isotopic over a one month analysis of each sample period (g) (e) once per month.

1 sample Downstream (Wa2) (2) Composite and analyze for H-3 quarterly.

b. Drinking 1 sample Nearest water supply (Wb1) Grab sample: Monthly (1 ) Gross beta and gamma isotopic analyses(e) of each sample monthly.

(2) Composite and analyze for H-3 quarterly.

IPEC aDCM D 3.5.1 - 6 Revision 0

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

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

3. Waterborne (continued)

c. Sediment 2 samples Downstream area (Wc1) Twice per year at least 90 Gamma isotopic analysis (e),

from with existing or potential days apart H-3, and Sr-90, of each Shoreline recreational value sample semiannually.

Upstream area (Wc2) control sample

d. Ground 2 samples Site Boundary Monitoring Quarterly Gamma isotopic analysis (e),

Water Wells, drilled near the SW H-3, and Sr-90, of each site boundary sample quarterly.

4. Ingestion

a. Milk (i) (1) 3 samples from In 3 locations (la1-la3) Twice per month when (1) Gamma isotopic (e) and 1-MILK within 5 km having the animals are on pasture; 131 analysis of each SAMPLING highest dose potential monthly at other times sample twice per month LOCATIONS April through December (2) Gamma isotopic (g) and 1-(2) If there are none, In each of 3 areas (la1-la3) 131 analysis of each then 1 sample 5 to 8 km distance, if sample once per month from MILK available, where doses are January through March if SAMPLING calculated to be > 1mrem required LOCATIONS per year (h)

(3) 1 sample from a At a control location (la4), Concurrently with indicator MILK 15 to 30 km distant and in locations SAMPLING the least prevalent wind LOCATION direction

b. Fish and (1) 1 sample each In the vicinity of a plant Sample in season, Invertebrates from edible discharge area (lb1) or Gamma isotopic analysis of portions of Semiannually if sample is each sample (e) , and Sr-90.

commercially or not seasonal recreationally important species (2) 1 sample of the If available in areas not same species influenced by plant discharge (lb2)

IPECODCM D 3.5.1 -7 Revision 0

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

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

4. Ingestion (continued) Grown nearest to each (1) Samples of 3 of 2 different offsite

c. Food different kinds locations of highest Products of broad leaf predicted annual vegetation (edible average ground level Monthly when Gamma isotopic (e) and 1-131 or inedible) U) D/Q if milk sampling is available analysis not performed (lc1-lc2)

(2) 1 sample of each of the Grown 15 to 30 km similar broad distant in the least leaf vegetation. prevalent wind direction if milk sampling is not performed (lc3)

(a) The code letters in parenthesis, e.g., DR1, A1 refer to sample locations specified in ODCM, Part II. 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.S.1-1. Refer to NUREG-0133, "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 permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to DS.1.

(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 40 routine monitoring stations shall be equipped with 2 or more dosimeters or with 1 instrument 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 measuring direct radiation.

(c) 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.

(d) Airborne particulate sample filters shall be analyzed for gross beta activity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay.

(e) Gamma isotopic analysis means the identification and quantification of gamma -emitting radionuclides that may be attributable to the effluents from the facility.

(f) The "upstream" samples shall be taken near the intake structures as described in the aDeM. The

""downstream" sample shall be taken from the mixing zone at the diffuser of the discharge canal.

(g) In this program, a composite sample is one in which the quantity (aliquot) 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.

(h) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

(i) The requirement to obtain and analyze samples from milch animals within 8 km of the site is intended to ensure monitoring of the "cow-milk" and vegetation pathways. Thus, only milch animals whose milk is used for human consumption are considered in the pathway and sample evaluation.

(j) Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different sectors with the highest predicted D/Q in lieu of the garden census.

IPECODCM D 3.5.1 - 8 Revision 0

Radiological Environmental Monitoring Program D 3.5.1 Table D 3.5.1-2 (pa~e 1 of 1)

Reporting Levels for Radioactivity In nvironmental Samples **

AIRBORNE FOOD RADIONUCLIDE PARTIUCLATE 9,R FISH MILK PRODUCTS ANALYSIS WATER GASES (pCi/m ) (pCi/kg, wet) (pCi/L) (pCi/kg, wet)

(pCi/L)

H-3 20,000

• 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 Sr-90 *** 8* 40 Zr-95 400 Nb-95 400 1-131 2* 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 Values provided are for drinking water pathways. If no drinking water pathway exists, higher values are allowed, as follows:

H-3 30,000 pCi/L (This is a 40 CFR 141 value)

Sr-90 12 pCi/L 1-131 20 pCi/L These reporting levels are associated only with the REMP requirements. The Ground Water Monitoring Program may involve unique reporting level criteria, independent of the REMP, and defined in station procedures.

• • • Sr-90 is added to this table due to its potential pathway via ground water.

IPEC aDCM D 3.5.1 - 9 Revision 0

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

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

LOWER LIMIT OF DETECTION (LLD) (b) (c)

AIRBORNE PARTIUCLATE FOOD RADIONUCLIDE WATER OR GASES FISH MILK PRODUCTS SEDIMENT ANALYSIS (pCi/L) (pC ilm 3) (pCilkg, wet) (pCilL) (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 H-3 2,000 (d)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Sr-90 (f) 5 5000 Zr-95 15 Nb-95 15 1-131 1 (d) 0.07 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 15 15 La-140 15 15 IPECODCM D 3.5.1 -10 Revision 0

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

Detection Capabilities for Environmental Sample Analysis Table Notation (a) This list does 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 in the Annual Radiological Environmental Operating Report pursuant to Specification 0 5.1.

(b) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

(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% probability of falsely concluding that a blank observation represents a "real" signal.

It should be recognized that the LLD is defined as an g priori (before the fact) limit representing the capability of a measurement system and not as an g posteriori (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 interfering nuclides, or other uncontrollable circumstances may render these LLDs .

unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to RECS 0 5.1.

(d) These LLDs are for drinking water samples. If no drinking water pathway exists, the LLDs may be increased to 3,000 for H-3 and 15 for 1-131.

(e) These required lower limits of detection are associated only with the REMP requirements. The Ground Water Monitoring Program may involve unique reporting level criteria, independent of the REMP, and defined in station procedures.

(f) Sr-90 is added to this table due to its potential pathway via ground water.

IPEC aDCM D 3.5.1 - 11 Revision 0

Land Use Census 03.5.2 03.5 RADIOLOGICAL ENVIRONMENTAL MONITORING o 3.5.2 Land Use Census DLCO 3.5.2 A land use census shall:

a. Be conducted.

b. Identify within a distance of 8 km (5 miles) the location, in each of the 16 meteorological sectors, of the nearest milk animal, the nearest residence, and the nearest garden of> 50 m2 (500 fe) producing broad leaf vegetation. Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of a garden census, per Table 0 3.5.1-1, part 4.c.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Land use census identifies A.1 Identify the new location(s) In accordance with location(s) that yields a in the next Radioactive the Radioactive calculated dose, dose Effluent Release Report. Effluent Release commitment, or D/Q value Report greater than the values currently being calculated in DSR 3.2.3.1.

IPEC ODCM 03.5.2 -1 Revision a

Land Use Census D 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Land use census identifies B.1 Add the new location(s) to 30 days location(s) that yields a the Radiological calculated dose, or dose Environmental Monitoring commitment (via the same Program.

exposure pathway) a factor greater than 2 than at a AND location from which samples are currently B.2 Delete the sampling After October 31 of being obtained in location(s), excluding the the year in which the accordance with control station location, land use census was Table D 3.5.1-1. having the lowest conducted calculated dose, dose commitment(s) or D/Q value, via the same exposure pathway, from the Radiological Environmental Monitoring Program.

AND B.3 Submit in the next In accordance with Radioactive Effluent the Radioactive Release Report Effluent Release documentation for a change Report in the ODCM including revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

IPEC ODCM D 3.5.2 - 2 Revision 0

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 In accordance with Annual Radiological Environmental Operating Report. the Annual Radiological Environmental Operating Report IPEC ODCM D 3.5.2 - 3 Revision 0

Interlaboratory Comparison Program 03.5.3 03.5 RADIOLOGICAL ENVIRONMENTAL MONITORING o 3.5.3 Interlaboratory Comparison Program DLCO 3.5.3 The Interlaboratory Comparison Program shall be described in the ODCM.

Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Analyses not performed as A.1 Report the corrective In accordance with required. actions taken to prevent a the Annual recurrence to the NRC in Radiological the Annual Radiological Environmental Environmental Operating Operating Report Report.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.5.3.1 Report a summary of the results obtained as part of In accordance with the Interlaboratory Comparison Program in the the Annual Annual Radiological Environmental Operating Report. Radiological Environmental Operating Report IPEC ODCM 03.5.3 -1 Revision 0

Solid Radwaste Treatment System D 3.6.1 D 3.6 SOLID RADIOACTIVE WASTE D 3.6.1 Solid Radwaste Treatment System DLCO 3.6.1 The appropriate equipment of the Solid Radwaste Treatment System shall be in operation process wet radioactive wastes in accordance with the Process Control Program.

APPLICABILITY: During solid radwaste processing ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive solid waste A.1 Suspend shipments of Immediately does not comply with solid radioactive waste.

Process Control Program requirements.

IPEC ODCM D 3.6.1 -1 Revision 0

Solid Radwaste Treatment System D3.6.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY DSR 3.6.1.1 Verify solidification of specimens in accordance with Prior to each the Processing Control Program. . shipment DSR 3.6.1.2 Record the following information for each class of Prior to each solid waste (as defined by 10 CFR Part 61) shipment shipped offsite during the Radioactive Effluent Release Report period:

a. Container volume,

b. total curie quantity (specify determined by measurement or estimate),

c. principal radionuclides (specify determined by measurement or estimate),

d. source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

e. type of container (e.g., LSA Type A, Type B, Large Quantity), and

f. solidification agent or absorbent (e.g., cement, urea formaldehyde).

IPEC aDCM D 3.6.1 - 2 Revision 0

UNRESTRICTED AREA D4.1 D 4.0 DESIGN FEATURES D 4.1 UNRESTRICTED AREA D 4.1.1 The definition of UNRESTRICED AREA used in implementing the Radiological Effluent Controls (RECS or ODCM Part I) has been expanded over that in 10 CFR 20.1003. For calculations performed pursuant to 10 CFR 50.36a, the concept of UNRESTRICTED AREAS refers to areas "at or beyond the SITE BOUNDARY" and does not include areas over water bodies.

A map representing the UNRESTRICTED AREA is shown in Figure D 4.1-1 Information which will allow identification of structures and release points for radioactive gaseous and liquid effluents is shown in Figure D 4.1-2.

D4.1.2 For the purpose of satisfying 10 CFR Part 20, the "Restricted Area" is the same as the "Exclusion Area" defined in the FSARs.

IPEC ODCM D 4.1 - 1 Revision 0

UNRESTRICTED AREA D 4.1 Figure D 4.1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS R~T' TRUE' NORTH NORTH' .,

,BROADWAY EXCLUSION AREA .

BOUNDARY ISf"SI~-c-f---",,-~J I ELECTRI.~

5WITCHYARD UNIT.2 It-HAKE

~"::c .* ..~" 'J

>.0:: +

UNIT 1 U",UT3

.UNIT ;3 DISC~RGE

~

GAS PIPELINE '. ":345KV

'TRANSMISSION lINEBROAQWAY PRopERTY LINE; ..

EASEMENT E}i(CLUSION ~AR.EA BOUNDARY ..

IPEC ODCM D 4.1 - 2 Revision 0

UNRESTRICTED AREA 04.1 Figure D 4.1-2 MAP DEFINING RELEASE POINTS

• G~SEo.lJS EFFLUENT RELEASE Po.lNT ~

RiivsT 0 N

i

,i DISCHARGE, CANAL U'1TURBI,NEBLDG,

! U-3*TURBINE BLDG, U-2 TURBINE BLDG, I

SFr.lJRrTYh "

~H~~

IPEC ODCM D 4.1 - 3 Revision 0

Annual Radiological Environmental Operating Report D 5.1 D 5.0 ADMINISTRATIVE CONTROLS D 5.1 Annual Radiological Environmental Operating Report An annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 15th of each year. Per the Technical Specification Reporting Requirements, a single submittal may be made for a multiple unit station.

The Annual Radiological Environmental Operating Report shall include:

• Summaries, interpretations, and an analysis of trends of the results of the Radiological Environmental Monitoring Program for the report period, including a comparison, as appropriate, with preoperational studies, with operational controls, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

• At least two legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor. One map shall cover stations near the site boundary and the second shall include the more distant stations.

• The results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

• A summary description of the Radiological Environmental Monitoring Program.

• A discussion of the reasons for not conducting the Radiological Environmental Monitoring Program as specified by D 3.5.1 and the plans for preventing recurrence.

• A discussion of environmental sample measurements that exceed the reporting levels of Table D 3.5.1-2 but are not the result of plant effluents.

• A discussion of all deviations from the sampling schedule of Table D 3.5.1-1.

• A discussion of the contributing factors for cases in which the LLD required by Table D 3.5.1-3 was not achievable.

• A discussion of identifiable nuclide peaks, including those of nuclides specified in Table D 3.5.1-3.

• The results of the land use census.

• The corrective actions taken to prevent a recurrence if the Interlaboratory Comparison Program is not being performed as required.

• The results of licensee participation in the Interlaboratory Comparison Program.

IPEC ODCM D 5.1 - 1 Revision 0

Radioactive Effluent Release Report D 5.2 D 5.0 ADMINISTRATIVE CONTROLS D 5.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report to be submitted by May 1 of each year shall include:

a. A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

b. 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 Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data onsite in a file that shall be provided to the NRC upon request

c. An assessment of the offsite radiation doses due to the radioactive liquid and gaseous effluent releases from the unit or station during the previous calendar year. This assessment shall include potential offsite dose determined with data collected from the Radiological Ground Water Monitoring Program (RGWMP).

d. An assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the SITE BOUNDARY (Figure D 4.1-1) 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.

Gaseous pathway doses are determined from sampling and measurements at the exhaust points, coupled with the use of annual-averaged meteorological data collected from a period of live data to verify its validity. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM).

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

~'

IPEC ODCM D 5.2 - 1 Revision 0

Radioactive Effluent Release Report D 5.2 D 5.2 Radioactive Effluent Release Report (continued)

e. The following information for each class of solid waste (in compliance with 10 CFR Part 61) shipped offsite during the report period:

1. Container volume,

2. total curie quantity (specify whether determined by measurement or estimate),

3. principal radionuclides (specify whether determined by measurement or estimate),

4. source of waste and processing employed (e.g., dewatered spent resin, compacted dry-waste, evaporator bottoms),

5. type of container (e.g., LSA, Type A, Type B, Large Quantity), and

6. solidification agent or absorbent (e.g., cement, urea formaldehyde).

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

g. A summary of data collected for the RGWMP, per D5.6 and NE107 Industry Ground Water Protection Initiative.

h. Any changes made during the reporting period to the Process Control Program (PCP) and to the Offsite Dose Calculation Manual (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification D 3.5.2.

IPEC ODCM Revision 0

Special Reports D 5.3 D 5.0 ADMINISTRATIVE CONTROLS D 5.3 Special Reports Special reports shall be submitted to the NRC Regional Administrator of the Region I Office

. within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the applicable Specification:

a. Radioactive Effluents (Specifications D 3.1, D 3.2 and D 3.4)

b. Radiological Environmental Monitoring (Specification D 3.5)

IPEC ODCM D 5.3 - 1 Revision 0

Major Changes to Radioactive Waste Systems D5.4 D 5.0 ADMINISTRATIVE CONTROLS D 5.4 Major Changes to Radioactive Waste Systems Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid) shall be reported to the Commission in the Radioactive'Effluent Release Report for the period in which the change was made. The discussion of each change shall contain:

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

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

c. a detailed description of the equipment, components and processes involved and the interfaces with other plant systems, d 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, .

e. an evaluation of the change, which shows the expected maximum exposures to individuals in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto,

f. 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 in which the changes are to be made;

g. an estimate of the exposure to plant operating personnel as a result of the change,and

h. documentation of the fact that the change was reviewed and found acceptable by the OSRC.

IPECODCM D 5.4 - 1 Revision 0

Process Control Program D 5.5 D 5.0 ADMINISTRATIVE CONTROLS D 5.5 Process Control Program Licensee initiated changes to the Process Control Program (PCP):

a. Shall be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:

1. sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information,

2. a determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes, and

3. documentation of the fact that the change has been reviewed and found acceptable by the OSRC.

b. Shall become effective upon review and acceptance by the OSRC.

D 5.6 Radiological Ground Water Monitoring Program (RGWMP)

The RGWMP shall be defined in station procedures and shall include detailed information regarding the following:

• Purpose and scope of the program

• Location and periodicities of samples

• Required radionuclides for analysis, including limits of detection

• Guidance for communication of abnormal results

• An annual report summarizing the radiological condition of ground water.

Elements of the RGWMP program that intersect the REMP shall be included in the Annual Radiological Environmental Operating Report, per D 5.1.

An evaluation of the EFFLUENT impact, and a summary of the sample data from the RGWMP shall be included in the annual Radiological Effluent Release Report, per D 5.2.

IPEC ODCM D 5.5 - 1 Revision 0

Indian Point Energy Center Offsite Dose Calculation Manual Part I (RECS)

BASES

Applicability B 0 3.0 3.0 APPLICABILITY BASES DLCOs 3.0.1, 3.0.2, and 3.0.5, and DSRs 3.0.1, 3.0.2, and 3.0.3 reflect para"el requirements in the Technical Specifications. Refer to Technical Specification Bases for appropriate discussions.

ODCM Specification DLCO 3.0.3, in lieu of imposing a plant shutdown as para"eled in Technical Specifications, requires: . (a) an Action to initiate efforts to restore compliance with the ODCM or associated Actions; and (b) an Action that requires entering the circumstances into the Corrective Action Program (CAP). These requirements ensure that the appropriate actions continue to be focused on and that the circumstances concerning failure to comply with the ODCM Actions would be reviewed. This review wi" be conducted in accordance with the procedural guidance for CAP Notifications.

There are no ODCM 3.0 Specifications that para"el Technical Specification LCO 3.0.4 or SR 3.0.4. Restrictions in entering MODES or other specified conditions in the Applicability have historically not been applied to ODCM Specifications. There are also no ODCM 3.0 Specifications that para"el Technical Specification LCO 3.0.6 and LCO 3.0.7, which allow for exceptions and revisions of other Technical Specifications. They are not applicable to the ODCM since it is not permitted to allow the ODCM to revise a Technical Specification.

(Note, currently no identified ODCM DLCOs support Technical Specification systems; however, this discussion is presented to address the philosophy that would be applied.) An allowance similar to Technical Specification LCO 3.0.6 does not apply to the ODCM. When a Technical Specification supported system LCO is discovered to be not met solely due to a ODCM support system DLCO not met, appropriate Technical Specification ACTIONS are required to be entered immediately. This applies even in instances where the ODCM contains a delay prior to declaring a Technical Specification supported system inoperable. In this case, certain ODCM inoperabilities may not directly impact the OPERABILITY of the Technical Specification supported system and delayed declaration of inoperability of the supported system is acceptable. In other cases, discovered support system inoperabilities that directly result in supported system inability to perform the safety function, should result in immediate declaration of inoperability of the supported system.

Technical Specification LCO 3.0.7 has no para"el in the ODCM since it provides for explicit changes to specified Technical Specifications by the Section 3,.1.8 Specifications. However, in the event that LCO 3.0.7 provides for changes to the Technical Specification MODE definitions by the Section 3.1.8 Specifications, the revised MODE definitions apply to a" plant references, including ODCM references.

IPECODCM B 03.0-1 Revision 0

Liquid Effluent Concentrations B D 3.1.1 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.1 Liquid Effluent Concentrations BASES It is expected that the release of radioactive materials in liquid and gaseous effluents to

.~ UNRESTRICTED AREAS will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20 and should be as low as reasonably achievable* (ALARA) in accordance with the requirement of 10 CFR 50.36a. While providing reasonable assurance that the design objectives will be met, these Specifications permit the flexibility of operation, compatible with considerations of health and safety, to ensure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels, but still less than ten times the effluent concentration limits (EC's) specified in 10 CFR Part 20. It is expected that using this operational flexibility under unusual operation conditions, and exerting every effort to keep levels of radioactive materials in liquid and gaseous wastes as low as reasonably achievable, releases will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20.

The design objectives have been developed based on operating experience, taking into account a combination of variables including defective fuel, primary system leakage, primary to secondary system leakage, steam generator blowdown and the performance of the various waste treatment systems, and are consistent with 10 CFR Part 50.36a.

The Indian Point site is a multiple-unit site. There ~xist shared radwaste treatment systems and shared effluent release points. Where site limits must be met, the effluents of all the units will be combined to determine site compliance. For instances where unit-specific information may be required for radwaste processed or released via a shared system, the effluents shall be proportioned among the units sharing the system(s) in accordance with the methods and agreements set forth in the ODCM.

This specification 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 EFFLUENT CONCENTRATIONS specified in 10 CFR Part 20. 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 1,10 CFR Part 50, to a member of the public and (2) the limits of 10 CFR Part 20.1302 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 MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (lCRP) Publication 2.

This specification applies to the release of liquid effluents from all units on site.

IPECODCM B D 3.1.1 - 1 Revision 0

Liquid Effluents Dose D 3.1.2 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.2 Liquid Effluents Dose BASES This Specification is provided to implement the requirements of Sections II.A, liLA and IV.A of Appendix 1,10 CFR Part 50. The DLCO implements the guides set forth in Section II.A of Appendix I. The actic;>n 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 material in liquid effluents will be kept "as low as reasonably achievable".

Also, for fresh water sites to UNRESTRICTED AREA 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 concentration in the finished drinking water that are in excess of the requirements of 40 CFR Part 141.

The dose calculation methodology and parameters in the ODCM implement the requirements in Section liLA of Appendix I; that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 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 Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", April 1977.

In addition'to the limiting conditions for operation, the reporting requirements specify that the licensee shall identify the cause whenever the dose from the release of radioactive materials in liquid waste effluent exceeds the above limits and describe the proposed program of action to reduce such releases to design objective levels on a timely basis.

IPEC ODCM B D 3.1.2 - 1 Revision 0

Liquid Radwaste Treatment System D 3.1.3 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.3 Liquid Radwaste Treatment System BASES This Specification requires that the licensee maintain and operate appropriate equipment installed in the liquid waste systems, when necessary, to provide assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonably achievable". This Specification implerDents the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objective given in Section II.D of Appendix I to 10 CFR Part 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 ILA of Appendix I to 10 CFR Part 50 for liquid effluents.

IPECODCM B D 3.1.3 - 1 Revision 0

Liquid Holdup Tanks D 3.1.4 D 3.1 RADIOACTIVE LIQUID EFFLUENTS D 3.1.4 Liquid Holdup Tanks BASES The tanks listed in this Specification include outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. These tanks include the following:

a. Refueling Water Storage Tanks

b. Primary Water Storage Tanks

c. 13 Waste Distillate Storage Tank

d. 14 Waste Distillate Storage Tank

e. 31 Monitor Tank

f. 32 Monitor Tank

g. Unit 3 CPF High Total Dissolved Solids Tank

h. Unit 3 CPF Low Total Dissolved Solids Tank

i. Any Outside Temporary Tank Restricting the quantity of radioactive material contained in the specified tanks provides assurance that, in the event of an uncontrolled release of any such tank's contents, the resulting concentration would be less than the limits of 10 CFR 20 at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

IPEC ODCM B D 3.1.4 - 1 Revision 0

Gaseous Effluents Dose Rate D 3.2.1 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.1 Gaseous Effluents Dose Rate BASES This Control provides 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 at or beyond the SITE BOUNDARY in excess of the design objectives of Appendix I to 10 CFR Part 50. This Control is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.A and II.C design objectives of Appendix I to 10 CFR Part 50.

For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for the reduced atmospheric dispersion of gaseous effluents relative to that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total 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 mremiyear. This Control does not affect the requirement to comply with the annual limitations of 10 ~FR 20.

This Control applies to the release of gaseous effluents from all units at the site.

IPEC ODCM B D 3.2.1 - 1 Revision 0

Gaseous Effluents Dose - Noble Gas D 3.2.2 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.2 Gaseous Effluents Dose - Noble Gas BASES This Specification is provided to implement the requirements of Sections II.B, liLA, and IV.A of Appendix I to 10 CFR Part 50. The DLCO implements the guides set forth in Section II.B 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 material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable." The Surveillance Requirements implement the requirements in Section liLA of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 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 Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases form Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

This Control applies to the release of gaseous effluents from each unit on site.

IPEC ODCM B D 3.2.2 - 1 Revision 0

Gaseous Effluents Dose - Iodine and Particulate D 3.2.3 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.3 Gaseous Effluents Dose - Iodine and Particulate BASES This Specification is provided to implement the requirements of Section II.C, liLA and IV.A of Appendix I to 10 CFR Part 50. The DLCOs are the guides set forth in Section II.C 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 gaseous effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable."

The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section liLA of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 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 1,"

Revision 1, October 1977 and Regulatory Guide 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 specifications for iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY.

The pathways that were examined in the development of these calculations were (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man (applied where applicable), and (4) deposition on the ground with subsequent exposure of man.

This Control applies to the release of gaseous effluents from each reactor on site.

IPEC ODCM B D 3.2.3 - 1 Revision 0

Gaseous Radwaste Treatment System D 3.2.4 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.4 Gaseous Radwaste Treatment System BASES This Specification requires that the appropriate portions of the Gaseous Radwaste Treatment System be used, when specified, to provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This Specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix 1,10 CFR Part 50, for gaseous effluents.

This Specification applies to the release of gaseous effluents from each reactor on site.

IPEC ODCM B D 3.2.4 - 1 Revision 0

Ventilation Exhaust Treatment System D 3.2.5 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.5 Ventilation Exhaust Treatment System BASES This Specification requires that the appropriate portions of the Ventilation Exhaust Treatment System be used, when speCified, to provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This Specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

This Specification applies to the release of gaseous effluents from each reactor on site.

IPEC ODCM B D 3.2.5 - 1 Revision 0

Gas Storage Tanks D 3.2.6 D 3.2 RADIOACTIVE GASEOUS EFFLUENTS D 3.2.6 Gas Storage Tanks BASES The tanks included in this Specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by other specifications to a quantity that is less than the quantity that provides assurance that, in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 Rem in an event of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurances that, in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 Rem. This is consistent with Branch Technical Position ETSB 11-5 in NUREG-0800, July 1981, and NUREG 0133.

IPEC ODCM B D 3.2.6-1 Revision 0

Radioactive Liquid Effluent Monitoring Instrumentation D 3.3.1 D 3.3 INSTRUMENTATION D 3.3.1 Radioactive Liquid Effluent Monitoring Instrumentation BASES The radioactive liquid effluent instrumentation, required OPERABLE by this Specification, is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with methods set forth in the ODCM to ensure that the alarm/trip will occur prior to exceeding ten times the EFFLUENT CONCENTRATION values specified in 10 CFR Part 20.

The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 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.

IPEC ODCM B D 3.3.1 - 1 Revision 0

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 D 3.3 INSTRUMENTATION D 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation BASES The radioactive gaseous effluent instrumentation, required OPERABLE by this Specification, is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding release rates corresponding to effluent dose rates of 0.5 Rem/yr whole body, and 3.0 Rem/yr to the skin.

This instrumentation also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design criteria 60, 63 and 64 in Appendix A to 10 CFR Part 50.

IPEC ODCM B D 3.3.2 - 1 Revision 0

Radioactive Effluents Total Dose D 3.4.1 D 3.4 RADIOACTIVE EFFLUENTS TOTAL DOSE D 3.4.1 Radioactive Effluents Total Dose BASES This Specification is provided to meet the dose limitation of 40 CFR Part 190 that has been incorporated into 10 CFR Part 20 by 46 FR 18525. The Specification requires the preparation and submittal of a special report whenever the calculated doses from plant-generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER

. OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks 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 Part 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 contribution from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. .

If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the special report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(a)(4), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed.

The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10CFR Part 20, as addressed in Specifications D 3.1.1 and D 3.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

IPECODCM B D 3.4.1 - 1 Revision 0

Radiological Environmental Monitoring Program D 3.5.1 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.1 Radiological Environmental Monitoring Program BASES The radiological environmental monitoring program required by this specification provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of members of the public resulting from the station operation.

This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 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. 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 an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

IPEC ODCM B D 3.5.1 -1 Revision 0

Land Use Census D 3.5.2 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 3.5.2 Land Use Census BASES This specification is provided to ensure that changes in the use of areas at and 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 from the door-to-door survey, from aerial surveyor from consulting with local agricultural authorities shall be used.

This census satisfies the requirements of SectionIV.B.3 of Appendix I to 10 CFR Part 50.

Restricting the census to gardens of greater than 50 m2 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 Regulatory Guide 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 (Le., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m 2

• IPEC ODCM B D 3.5.2-1 Revision 0

Interlaboratory Comparison Program D 3.5.3 D 3.5 RADIOLOGICAL ENVIRONMENTAL MONITORING D 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 material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring (developed using the guidance in Regulatory Guide 1.21, Revision 1, April 1974 and Regulatory Guide 4.1, Revision 1, April 1975) in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

IPEC ODCM B D 3.5.3 - 1 Revision 0

Solid Radwaste Treatment System D 3.6.1 D 3.6 SOLID RADWASTE TREATMENT SYSTEM D 3.6.1 Solid Radwaste Treatment System BASES This Specification implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the process control program may include, but are not limited to, waste type, waste pH, waste/liquid/solidification agent/catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times.

IPEC ODCM B D 3.6.1 -1 Revision 0

INDIAN POINT ENERGY CENTER OFFSITE DOSE CALCULATION MANUAL ODCM PART 11- CALCULATIONAL METHODOLOGIES Revision 0

aDCM Part II - Calculational Methodologies 1.0 RADIATION MONITORS AND SETPOINTS 1.1 Effluent Monitoring System Description Information regarding effluent radiation monitor function and setpoint bases is provided in Tables 1-1 and 1-2. Additionally, Appendices Band C show a schematic of release pathways, including the relative position and application of these monitors.

1.2 Setpoints for Airborne Effluent Monitors Setpoints for airborne (gaseous) monitors are based on the permissible discharge rate as calculated in Section 3 of the aDCM, Part II, and shown in Appendix I. These setpoints are inherently conservative due to the assumed mixture (Table 3-8). They are tiered in such a way as to ensure proper (higher) authentication is obtained as the selected limit (and expected release rate) increases.

The Annual Limit is used to conservatively establish initial setpoints for routine operation.

For releases associated with unit shutdown, etc, additional permission may be obtained to apply the quarterly or instantaneous values, per Section 3.1.8. This method ensures operational control of releases, while precluding approaching the limits of D3.2.1.

The methodology identified in Section 3 and Appendix I is used to generate the following release rate limits (radiation monitor setpoint calculations only use the noble gas rates):

Conservative Permissible Discharge Rates (J,lCi/sec) lodine/Particulate* Noble Gases TYQe of Limit Basis Unit 2 Unit 3 Unit 2 Unit 3 Annual Average . ODCM, Part II, App I 4.01E-2 4.0SE-2 7.20E+3 3.S7E+3 Quarterly Average ODCM, Part II, App I S.02E-2 S.10E-2 1.44E+4 7.14E+3 Instantaneous RECS 03.2.1 and App I 1.38E+1 1.38E+1 7.00E+4 7.00E+4

• Half-lives greater than 8 days 1.2.1 The Plant Vent Wide Range Gas Monitor (R-27) reads in J,lCi/sec. Therefore, at unit 3, the alarm setpoints are set directly in J,lCi/sec. (Unit 2 does not apply alarm setpoints to R-27).

1.2.2 If the monitor reads and alarms in )lei/cc, the maximum alarm set point is calculated as follows:

S = D / [(F) * (4.72E+2)] where; S =Maximum alarm setpoint in )lCi/cc D = Permissible discharge rate in )lCi/sec F = Vent duct flow in fe/min 4.72E+2 =unit conversion factor (28317 ccemin/fee60sec)

IPEC aDCM Page 1 of 130 Revision 0

ODCM Part II - Calculational Methodologies 1.2.3 If the monitor reads and alarms in cpm, then the maximum alarm setpoint is calculated as follows:

S = D / [(F) * (4.72E+2) * (CF)]

where:

S, D, F, and 4.72E+2 are defined in the previous step CF = Rad Monitor Conversion Factor (~Ci/cc per net cpm) 1.2.4 Normally, maximum allowable limits are calculated using a standard nuclide mix. However, setpoints may be determined based on the actual mix, on a case by case basis. This method is usually performed when the instantaneous release rate is applied. Should this method be applied, extra care should be applied to setpoint partitioning (for all release points) to ensure site dose rate limits are not approached.

1.2.5 During normal operation, the main plant vent is the only significant release point at either unit. Hence, monitors on the plant vent are routinely set at the annual limit, which is approximately 10% of the conservative instantaneous limit.

Monitor setpoints on other pathways are routinely set to 1% of the instantaneous limit. If multiple pathways become significant, each pathway's permissible release rate is apportioned with the Plant Vent's to ensure the total discharg~ rate for all release points remains less than the maximum permissible discharge rate.

If necessary, release rates may be apportioned (per 10CFR20 applicability to a site, rather than anyone unit) for maximum operational flexibility such that one unit "borrows" routine apportionment from the other unit. This evolution is controlled by station procedures, which require direct communication with the Shift Managers and the Chemistry Department.

1.3 Setpoints for Liquid Effluent Monitors 1.3.1 Liquid Effluent Monitors have setpoints based on limiting the concentrations in the discharge canal to ten times the concentration values in Appendix B, Table 2, Column 2 to 10CFR20 in accordance with 10CFR20.1302(2)(i).

1.3.2 Monitor setpoints are inherently conservative due to the routine use of determining dilution from Circulating Water Pumps at the applicable unit only.

In actuality, both Circulating and Service Water systems for the entire site contribute to site dilution.

IPEC ODCM Page 2 of 130 Revision 0

ODCM Part II - Calculational Methodologies 1.3.3 For monitors that read and alarm in ~Ci/ml, setpoints are calculated as follows:

S = [(ADC) (F)] / [f] =Maximum alarm setpoint in ~Ci/ml where:

F = Available discharge canal dilution flow for this release, in gpm f = calculated allowable release rate in gpm (Section 2.2.6)

ADC = The Allowed Diluted Concentration is the equivalent MPCW for gamma emitting isotopes weighted for total specific activity (both gamma and beta emitters). This term is necessary to correct the MPCW due to the relatively insignificant effect of beta emitters on the radiation monitor, as described in Section 2.2.6.

1.3.4 Alert or Warn setpoints should be used on batch liquid release monitors to ensure the contents of the batch tank have not changed since sampling. The alert setpoint is calculated as follows:

AS = (C) * (M) where:

AS = Alert or Warn setpoint in ~Ci/ml C = Average monitor reading at time of sample M = A conservative factor based upon the mixing ratio of two tank volumes and an expected monitor response error term (typically 1.25, coinciding with 25%).

NOTE: Liquid Monitor alert setpoints do not control any auto functions but simply provide indication to the operators.

Alert or Warn setpoints for other monitors are typically initially established at approximately 75% of the Alarm value.

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ODCM Part II - Calculational Methodologies TABLE 1 -1 Unit 2 Effluent Radiation Monitor System Data CHANNEL MONITOR DESCRIPTION SAMPLING LOCATIONS RANGE EFFLUENT CONTROL FUNCTIONS 1E-7 to 1E-2 R-42 Containment Gas Monitor 72' Fan Bldg Containment Ventilation Isolation

}.lCi/cc 1E-7 to 1E-2 Shuts RCV-014 (isolating gas tanks), stops VC R-44 Plant Vent Radiogas Monitor 88' Fan Bldg llCi/cc release fans and shuts VC vent/purge valves.

In-line detector on the air ejector 1E-6 to 1E-1 Alarm diverts air ejector exhaust to VC and R-45 Condenser Air Ejector Monitor exhaust header llCi/cc secures steam to priming air ejector re-heaters.

Waste Gas Disposal System None. RECS D3.2.6 is assured by setpoint R-50 98' PAB 0.1 to 1E5 Ci Monitor basis per aDCM Part II, Sec 3.1.12.

Plant Vent Wide-Range Drawn from inside Plant Vent, 1E-7 to1E+5 None. PV Concentration and release rate R-27 Monitor to 85' BAB }.lCi/cc information only, for accident applications.

Unit 1 Stack Vent Unit 1 Nuclear Services Bldg 1E-7to1E-2 R-60 None Radiogas Monitor 100' Elevation llCi/cc Adjacent to service water return 1E-7 to 1E-2 Fan Cooler Unit Service R-46 / 53 line from V.C. fan cooler units and None Water Return llCi/cc motor coolers Component Cooling System Adjacent to line monitors on each 1E-6 to 1E-2 None. Setpoints are not based on effluent.

R-47 pump outlet pump outlet llCi/ml They are for ALARA and information only.

Component Cooling Heat 1E-7to1E-2 R-39 / 40 Exchanger Service Water 80' PAB None

-- llCilcc Monitors Waste Disposal Liquid Effluent 1E-7 to 1E-2 R-54 In-line monitor on 70' CSB Terminates Distillate Tank releases on alarm Monitor llCi/cc 1E-6 to 1E+2 R-49 SG Blowdown Monitor 15' Transformer Yard Housing Closes blowdown isolation valves llCi/cc Sec Boiler Blowdown 1E-7 to 1E-2 R-51 43' Superheater Bldg None Purification llCilcc Sec Boiler Blowdown 1E-7 to 1E-2 R-52 33' Superheater Bldg None Purification Sys SW llCilcc IPECODCM Page 4 of 130 Revision 0

ODCM Part II - Calculational Methodologies TABLE 1 - 2 Unit 3 Effluent Radiation Monitor System Data CHANNEL MONITOR DESCRIPTION SAMPLING LOCATIONS RANGE EFFLUENT CONTROL FUNCTIONS Samples drawn from 32 and 35 R-12 Containment Gas Monitor Containment Fan Coolers 1E-7 to 1E-1 !lCi/cc Containment Ventilation Isolation In Plant Vent at approximately Secures waste gas tank release and R-14 Plant Vent Radiogas Monitor 1E-6 to 1E-1 !lCi/cc Containment Ventilation Isolation 105' elevation On alarm, diverts air ejector exhaust to In-line detector on the air ejector VC and secures steam to priming air R-15 Condenser Air Ejector Monitor 1E-6 to 1E+O !lCi/cc exhaust header ejectors re-heaters Waste Gas Disposal System Adjacent to line, on suction to None. This setpoint is based on limiting R-20 Monitor waste gas compressors 1E-2 to 1E+3 !lCi/cc 50,000 Ci per tank, per RECS D3.2.6.

Plant Vent Wide-Range Secure waste gas tank release and R-27 Drawn from inside Plant Vent 1E-7 to 1E+5 !lCi/cc Containment Ventilation Isolation Monitor 4th Floor Administration Building 1E+1 to 1E+6 cpm Administration Building Vent Monitor Exhaust Plenum for (typically 5.0E-8 to R-46 Radiogas Monitor None Controlled Areas 5.0E-2 !lCi/cc)

RAMS Building Vent Radiogas 55' RAMS Building Monitor R-59 Monitor Exhaust Plenum 1E-6 to 1E+2 !lCi/cc None Adjacent to service water return Fan Cooler and Motor Cooler line from V.C. fan cooler units and 1E-7 to 1E-1 !lCi/cc None R-16 AlB Service Water Return motor coolers Component Cooling System Adjacent to line monitors on each None. These setpoints are not based on R-17 AlB 1E-6 to 1E-1 !lCi/ml pump outlet pump outlet effluent and are for information only.

Component Cooling Heat Adjacent to line, mounted on SW Exchanger Service Water return from Component Cooling 1E-7 to 1E-1 !lCi/cc R-23 None Monitor Heat Exchanger Waste Disposal Liquid Effluent In-line monitor on monitor tank Terminates monitor tank release on alarm 1E-7 to 1E-1 !lCi/cc R-18 Monitor recirc pump discharge PAB blowdown room monitors Closes blowdown isolation valves and SG SG Blowdown Monitor 1E-6 to 1E+2 !lCi/cc sample valves R-19 steam generator blown Recirc line of HTDS/LTDS tanks Terminates HTDS or LTDS tank release.

CPF Regen Waste Release in CPF (used when primary to Applicable only in a primary to secondary 1E-7 to 1E-1 !lCi/cc R-61 Monitor secondary leakage exists). leak, as defined in RECS D1.1.

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ODCM Part II - Calculational Methodologies 2.0 LIQUID EFFLUENTS 2.1 Liquid Effluent Releases - General Information 2.1.1 A completed and properly authorized Liquid Radioactive Waste Permit is required prior to performing any BACTH release (a release of known volume and activity from an isolated source).

2.1.2 All activity determinations for liquid radioactive effluents are performed in such a manner as to be representative of the activity released to the river.

2.1.3 The radioactivity in liquid waste tanks shall be continuously monitored during release except as allowed by RECS 03.3.1. If the flowmeter is inoperable, the flow shall be estimated every four hours by difference in tank level or by discharge pump curves.

2.1.4 Prior to discharge, the radioactive waste tank contents shall be recirculated for at least two tank volumes. After this recirculation, and prior to discharge, a sample shall be taken and analyzed for activity with a portion of the sample set aside for composite analysis. The measured activity shall be used for calculating allowable discharge rate and the alarm setpoint for the liquid waste discharge monitor.

2.1.5 Steam Generators or other CONTINUOUS releases shall be quantified and included in effluent reports, but do not require a pre-release permit. Continuous releases are typically quantified from periodic sampling and the use of radiation monitoring. In Modes 4-6, however, SG Draindowns are typically quantified in BATCH mode.

2.1.6 Assurance that the combined liquid releases from Units 2 and 3 maintain compliance with 10CFR20 is provided by administrative controls which include an administrative minimum dilution of 100,000 gpm for any batch release, and routine use of unit-specific dilution flow for each permitted release.

Upon agreement between both Shift Managers, however, one unit can reduce or eliminate radioactive liquid waste discharges for a period of time to allow the other unit to use the full site dilution flow, or a specified portion thereof. When applying this shared policy, the Shift Managers require the details and duration of this evolution in writing at both CRSwork stations.

2.1.7 Steam Generator Blowdown activity is determined by composite samples collected in a manner to be proportional to the rate of flow of individual steam generator to total steam generator blowdown. These samples are then analyzed for the various radionuclides at frequencies specified in the RECS. Due to appropriate compositing, total blowdown flow is then routinely multiplied by average concentrations to determine the actual effluent contribution from Steam Generator Blowdown.

2.1.8 Time average dose calculations (10CFR50) may use total site dilution flow for both units, with the determined dose contributions additive for a site report over any specified period.

2.1.9 The discharge canal flow rate is determined by the use of pump flow characteristics curves. Actual monthly average flow rates and total gallons of dilution are determined by Programs and Components and delivered to Chemistry on a monthly basis. Unit 2 circulator pumps are operated at either low or high speed (approximately 88,000 to 140,000 gpm). Unit 3 circulator pumps have a variable speed capacity, and can produce a range from 65,000 to 140,000 gpm.

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ODCM Part II - Calculational Methodologies 2.1.10 Radioactivity content in outdoor tanks is to be limited to less than 10 curies, excluding tritium and noble gas, as per RECS D3.1.4.. Compliance with this requirement is demonstrated by limiting the radioactive concentration in these tanks to the value which results in 10 curies when the tank is at full liquid capacity, except as modified below. The radioactive concentration limits for these tanks are:

6 RWST: 10 curies x 10 j.1Ci / curie = 7.3 x 10-3 j.1Ci / ml 358,500gal x 3785ml / gal 6

PWST: 10 curies xl 0 j.1Ci / curie = 1.6 x 10-2 j.1Ci / ml 165,000gals x 3785ml / gal 31 & 32 Monitor Tanks (Unit 3):

10 curies x 106 j.1Ci / curie 1

- - - - - - - - - = 2.2 x 10- j.1CiI ml 11,750gals x 3785ml / gal 13 & 14 Waste Distillate Storage Tanks (Units 1/2):

10 curies x lO\lCi / curie 1

- - - - - - - - = 1.1 x 10- /lCi! ml 23,577gals x 3785mll gal Unit 3's Condensate Polisher High and Low Total Dissolved Solids Tanks:

6 10 curies x 10 j.1Ci / curie 2

- - - - - - - - - = 4.4 x 10- j.1CiI ml 60,000gals x 3785ml / gal Outside Temporarv Tanks:

10 curies x 10-6 j.1Ci / curie

---

= j.1Ci / ml Volume (gal) x 3785ml / gal Integrated curies in a tank can similarly be detElrmined by calculating the curies added from known inlet concentrations and volumes, which would then be combined with previously determined tank curie levels.

The refueling water storage tank has the potential to be filled from the reactor cavity with liquid which exceeds the limits stated. Therefore, prior to filling the RWST from the reactor cavity after refueling operations, the reactor cavity (or residual heat removal system) must be sampled for radioactivity and action taken to ensure that the total activity in the tank does not exceed 10 curies.

Outside temporary tanks should not be filled with liquid which could exceed the concentration limit calculated. Therefore, prior to transfer to outside temporary tanks, the source of liquid shall be sampled for radioactivity. If it exceeds the concentration limit calculated, action shall be taken to ensure that the total activity in the tank does not exceed 10 curies.

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aDCM Part II - Calculational Methodologies 2.1.11 Turbine hall drains (from sumps in the five foot elevation for units 2 and 3) receive drains from areas containing secondary plant components at sub-atmospheric pressures. These sumps do not meet the intent of a turbine hall drain system as defined in NUREG 0472, however their effluent contribution should be evaluated.

Quantification of effluents is performed on this pathway during a Primary to Secondary Leak, as defined by RECS D1.1. In these cases, releases from this pathway would be quantified by periodic sampling multiplying the source term by a determination of the release rate to the river, generally bounded by secondary system loss or make-up rate. .

At elevated Steam Generator activity levels (approximately 1.0E-4 or above), turbine hall drains may require temporary processing, should effluents via this pathway approach the 31-day dose projection limits per RECS D3.1.3. In this case, water at Unit 3 can be directed to the Condensate Polishing Facility prior to release. At Unit 2, a temporary processing skid will need to be applied, or water directed to the Secondary Boiler Blowdown Purification System, or other installed cleanup system.

Activity released via this pathway is determined as follows:

Turbine Hall J (FeedwaterJ (steam Plant SG BlowdownJ Drain

( Effluent Activity

= Specific

• Makeup - Rate to the Activity Rate River 2.1.12 Carbon 14 is released at a rate of .07 curies per GW(e)/yr with an average make up rate of 0.5 gal/min based upon studies performed by the New York State Department of Health. The estimate of Carbon 14 releases are included in the Radiological Impact on Man section of the Annual Radioactive Effluent Release Report. These estimates are not included in dose calculations for routine releases.

2.1.13 Several normally non-radioactive systems are periodically analyzed for radioactivity.

Examples include Unit 3's Condensate Polisher regenerant waste tank, the Spent Fuel Pool Auxiliary Heat Exchanger Secondary Cooling Systems (when in use), and Site Storm Drains, etc. The monitoring program for these type of release points is consistent with the direction set forth in NRC IE Bulletin 80-10 "Contamination of Non-radioactive Systems and Resulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to Environment". Should a system become contaminated, releases will be evaluated and quantified (as either batch or continuous) in accordance with the requirements listed in the RECS and the IPEC 80-10 program.

2.1.14 The Unit 3 liquid waste monitor tanks have an airborne release pathway. The original plant design limited the gases through this pathway by reducing the entrained gases to less than 2E-3 /lCilml. When the entrained gas concentration in the monitor tank inlet exceeds 2E-3 /lCi/ml, the noble gas release will be quantified by calculating the difference (in /lCi's) between the gaseous activity added to the tank and the gaseous activity present in the effluent release sample. This difference will be the activity released through the tank vents and is quantified as an airborne release.

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aDCM Part II - Calculational Methodologies 2.1.15 Due to the addition of Hafnium control rods at Unit 3, an offsite dose may need to be calculated for Hafnium isotopes in waste pathways. In the absence of site-specific bioaccumulation and dose factors for Hafnium, factors for Zirconium are used, as suggested in ICRP 30. Should these calculations become necessary, they will be performed per the following sections, and manually added to other totals.

2.1.16 Investigations from the Ground Water Monitoring Program (GWMP) may result in a determination of liquid effluent. A quantification and dose assessment of radioactive groundwater or storm water leaving the site shall be performed at least annually.

This quantification shall include, as a minimum, the source term from samples obtained near the effluent points of each applicable pathway (eg, ground water wells nearest the site boundary), and a determination of release rate and dilution flow.

Release rates to the river from both the bedrock pathways and collective storm drain pathways are provided from modeling by hydrologists. A precipitation mass balance was initially applied (Reference 32), and later verified by an application of the Darcy's Law model. Future determinations will continue to use a combination of these models at various depths, over effected zones, as discussed in Attachment J, Hydrological Verification of Grounwater Flow Rates.

Dilution flow is directly measured in the Discharge Canal for the Storm Drain component. For groundwater reaching the Hudson via a direct path under the canal, a dilution factor equivalent to a 6-hour half-tidal surge in the effected area of the Hudson applies, as discussed in Reference 33.

Dose calculations are otherwise then completed per the following sections.

2.2 Liquid Effluent Concentrations 2.2.1 This section provides a description of the means that will be used to demonstrate compliance with the RECS 03.1.1.

2.2.2 Compliance with the instantaneous limits of 10CFR20 is achieved by allocating dilution flow on a per unit basis, as described in Section 2.1.6. Compliance with 10CFR50 (quarterly and annual limitations) is assured by completing a monthly report which summarizes the time-average releases from the site.

2.2.3 Each isolated liquid waste tank must be recirculated for at least two tank volumes prior to sampling in order to ensure a representative sample is obtained. At Unit 2, this duration is determined from station procedures with every batch release. At Unit 3, a default minimum recirculation time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> may be used for 31 and 32 monitor tanks in lieu of the actual calculation:

11750 gals

• 2 Tank Volumes 39 lJ

- - - - = - - - - - - - - - . nours~ 4 11lJours 100 gal/min Note: Nominal monitor tank pump flow rate is approximately 135 gpm. For conservativism however, 100 gpm is used for the recirculation flow rate, while 150 gpm is used for the discharge flow rate in all release calculations.

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aDCM Part II - Calculational Methodologies 2.2.4 For batch releases, the concentration in liquid effluents prior to dilution in the discharge canal is determined by sampling prior to release. For continuous releases, the concentrations can be determined by either grab sampling, or by direct reading radiation monitor. If the process radiation monitor is utilized, the conversion factor should be verified as appropriate for the mixture being released.

For non-direct reading monitors, the following calculation is used:

C = CF*CR C= Concentration of liquid effluent (uCi/ml) prior to dilution CF = Conversion factor of monitor (uCi/ml per net cpm)

CR = Count rate of monitor (in net cpm) 2.2.5 The final diluted concentration in the canal is determined as follows:

CD = (C) * (f)/(F)

Where: CD = Diluted concentration in the discharge canal in uCi/ml C = Pre-dilution liquid concentration in uCi/ml F = Dilution flow in the discharge canal in gal/min f = Release rate of liquid effluent in gal/min 2.2.6 Calculation of Maximum Permissible Concentration in liquid Effluents

a. This section describes the methodology used to ensure compliance with RECS D3.1.1. The discharge canal concentration of radionuclides must be maintained less than those identified as limits (10 times the EC's of 10CFR20). The noble gas limit has been specified as 2E-4 uCi/ml.

These criteria are normally assured by using an Allowed Dilution Concentration (ADC) on each discrete release. This differs from the ECs given in 10CFR20 Appendix B in that, for radioisotopes that do not have gammas greater than 60 kev emitted during decay, default values are included to estimate their contribution.

The Allowed Diluted Concentration is derived and calculated as follows:

ADC= MPCwt*CG or ADC= MPCwt *CG or Totalactivity CG+CB where:

ADC = Allowed diluted concentration in uCi/ml IPEC aDCM Page 10 of 130 Revision 0

aDCM Part II - Calculational Methodologies MPCWt = Maximum permissible concentration in water for all isotopes (beta & gamma), in uCi/ml, as defined in RECS, 01.1, as follows:

MPCWt L (CYMPCWi

.1

)

Ci and MPCWi = Concentration and MPCW for each isotope CB = The concentration of the non gamma emitters, in uCi/ml CG = The concentration of the gamma emitters, in uCi/ml

b. A representative sample must be obtained. For batch releases, at least two tank volumes are recirculated after the tank has been isolated to meet these requirements. The minimum recirculation time is determined as follows:

T = 2 (V) / (G) where; T = Minimum recirculation time in min V = Volumes in the tank to be discharged, in gal G = Recirculation rate in gal/min

c. After the tank has been sampled, the Allowed Diluted Concentration is determined, per the equations above.

d. A determination of other liquid radioactive discharges is evaluated. If other releases are in progress at an affected unit, the radioactive concentrations and discharge rates are included to determine a potentially new required dilution factor.

e. Available dilution flow may be adjusted by physically using more pumps or altering an allocation fraction. Additionally, if required, release rate can be adjusted to comply with diluted concentration limits with existing dilution flow. Typically, however, these measures are not required.

f. The required dilution flow is calculated as follows:

E = Dr*CG where; ADC Dr = Current release discharge rate, gpm E = Required dilution for current existing release(s), gpm CG and ADC are defined in Section 2.2.6~a IPEC aDCM Page 11 of 130 Revision 0

ODCM Part II - Calculational Methodologies

g. The permissible discharge rate is calculated as follows:

ADC*B D Where:

CG D = Permissible discharge rate in gal/min ADC = Calculated and described in Step 2.2.6.a CG = Gamma emitter concentration in IlCi/ml B = Adjusted dilution flow from the unit, in gpm, from Step 2.2.6.d, above, as follows:

B=

(~low

}'ailable) - (Required

~lutlOn DIllltlOufrom E otherreleases,

)

Note: With no "other" releases, B simply becomes the A vailable Dilution Flow.

2.3 Liquid Effluent Dose Calculation Requirements 2.3.1 RECS D3.1.2 requires that the dose or dose commitment above background to an individual in an unrestricted area from radioactive materials in liquid effluents released from each reactor unit shall be limited:

a) During any calendar quarter: Less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.

b) During any calendar year: Less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

c) If either of the above limits is exceeded by a factor of two or more, then cumulative dose contributions from direct radiation would be determined by evaluation of existing perimeter and environmental TLDs per RECS D3.4.1.

2.3.2 RECS D3.1.3 requires that appropriate portions of the radwaste treatment system be used to reduce the radioactive material in liquid waste prior to their discharge when the projected dose due to liquid effluent from each reactor unit when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ. Doses due to liquid release shall be projected at least once per 31 days. These doses are projected based on the dose methodology in Section 2.4. or 2.5. The average of previous months' doses is used to project future dose, as follows:

Dose ]

=

Current Month Dose + Previous months' Dose

+/-

major I

p anne d 1

[ Projection . number of months used [

evolutions The term for planned evolutions is routinely determined from previous similar evolutions, such as releases associated with plant shutdown.

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ODCM Part II - Calculational Methodologies 2.4 Dose Methodology (Computer Calculation) 2.4.1 NUREG 0133 (Ref. 1, Section 4.3, Pg. 14) states that cumulative dose contributions should consider the dose contribution from the maximum exposed individual's consumption of fish, invertebrates, and potable water as appropriate. The river near IPEC is considered to be fresh water when in reality it is a tidal estuary and never completely fresh. Observed average chlorosity at IPEC has ranged as high as 2.5 gm/liter or about 13% sea water and 87% fresh water.

Hence, use of the Hudson River for fresh water supply purposes is precluded south of Chelsea (mile point 65) which is the nearest point of potable water supply (approximately 15 miles upstream of IPEC). Radionuclide concentrations in the nearest water supply have been calculated (Ref. 2) to be a factor of at least 500 lower than the river water in the Indian Point area.

Due to the absence of a potable water pathway, RECS D3.1.2 reporting regulations for a 3 mile downstream limit do not apply. There is no exposures from ingestion of drinking water.

Thus, at IPEC, the cumulative dose considers only the dose contributions from the maximum exposed individuals consumption of fish and invertebrates. Tables of dose factors for three age groups were developed as per Section 2.4.3 and are included as Tables 2-1, 2-2, and 2-3. (Infant dose factors are 0 and are not included).

2.4.2 The relationships and methods that form the calculational base for dose accounting for the liquid effluent pathway are described in this section. These relationships can be used to meet the calculational requirements of Section 2.3.1. The cumulative dose factors (Ait) are calculated in Section 2.4.3. The following equation is generally applicable and can be used for any number of isotopes released over a time period:

m n D (T) = L [A

• L (dt i=!

iT k=!

k )( C ik )( Fk ) ]

Where:

m = The total number of isotopes released.

D(T) = The liquid effluent cumulative dose commitment from nuclides to the total body or any organ, T, for the time period k, in mrem.

dtk = The length of the time period, k over which C ik and Fk are averaged for all liquid releases, in hours. (This can be individual release durations summed, or an entire period duration, defined with each application of this equation.)

Cik = The undiluted liquid effluent average concentration of nuclide, i, in uCi/ml, during time period dtk from any liquid release.

n = The total number of releases considered.

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aDCM Part II - Calculational Methodologies AiT = The site related ingestion dose commitment factor to the total body or any organ for each identified principal gamma and beta emitter listed in Table 2-1, 2-2, and 2-3, in mrem-ml per hr-uCi.

Fk = The total dilution factor for Cik during any liquid effluent releases; defined as the ratio of the maximum undiluted liquid waste flow during release to the average flow from the site discharge structure to unrestricted receiving waters, times an applicable factor.

The term C ik represents the total undiluted concentration of radioactive material in liquid waste at the release point as determined by the radioactive liquid waste sampling and analysis program as contained in the RECS. All dilution factors beyond the sample point are included in the Fk and AiT terms.

The term Fk is a total dilution factor and is determined as follows:

F = Liquid Radioact ive Waste Flow k [Discharge Structure Exit Flow

• Applicable Facto r]

The liquid radioactive waste flow is the flow from all continuous and batch radioactive effluent releases specified in the RECS from all liquid radioactive waste management systems. The discharge structure exit flow is the average flow during disposal from the discharge structure release point into the receiving body of water. Based on studies by New York University Medical Center (ref. 14 page 7), the appropriate "Applicable Factor" (a mixing factor in the near field), is 5.0.

For permitting and initial assessment of liquid effluent releases, Fk is first determined with dilution flow concurrent with applicable releases (see Section 2.2). Doses are later recalculated (for the entire site) on a quarterly basis to determine actual doses from quarterly total site dilution volume. This method allows both an immediate and accurate long-term assessment of radiation dose resulting from liquid effluent releases at Indian Point.

2.4.3 Dose Factor for Liquid Effluent Calculations The equation for dose from liquid effluents requires the use of a dose factor AiT for each nuclide, i, which embodies the dose factors, pathway transfer factor, pathway usage factors, and dilution factors for the points of pathway origin.

IPEC follows the guidance of NUREG 0133 and has calculated AiT for the total body and critical organ of the maximum exposed individual for Adult, Teen and Child doses.

Most factors needed in the equation were obtained from Regulatory Guide 1.109 with the following exceptions (see Section 2.6 and Ref 2, 12, 13, 14, and 25):

The fish and invertebrate bioaccumulation factors (BFi and Bl i) for Cesium, Niobium, Silver, and Antimony, were determined locally.

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ODCM Part II - Calculational Methodologies For Cesium, a site specific factor of 224 was used instead of the 2,000 presented in Table A-1 of the Regulatory Guide for fish. Similarly, a factor of .

224was used for invertebrates instead of the Regulatory Guide value of 1000.

For Silver, the fish and invertebrate factors are 2.3 and 3300, respectively.

For Niobium, the fish and invertebrate factors are 300 and 100 respectively.

For Antimony, the fish and invertebrate factors are 1 and 300 respectively.

The summary dose factor is as follows:

A;T = K[(UF)BF; + (UI)BI;lDJ Where:

AiT = Composite dose parameter for the total body or critical organ for nuclide, i, for all appropriate pathways, mrem/hr per IlCilml.

K = Units conversion factor, 114155 = (1E6pCi/uCi) * (1E3ml/kg) 8760 hr/yr UF = kg/yr fish consumption from Table E-5 of Reg Guide 1.109:

21 Adult 6.9 Child 16 Teen 0 Infant BFi = Fresh Water Fish Bioaccumulationfactor for nuclide, i, in pCi/kg per pCi/1 from Table A-1 of Regulatory Guide 1.109.

UI = kg/yr invertebrate consumption from Table E-5 of Regulatory Guide 1.109:

5.0 Adult 1.7 Child 3.8 Teen o Infant

. Bli = Salt Water Invertebrates Bioaccumulation factor for nuclide, i, in pCi/kg per pC ill from Table A-1 of Regulatory Guide 1.109.

DFi = Dose conversion factor for nuclide i, for age groups in pre-selected organs, T, in mrem/pCi, from Tables E-11, 12 & 13 of Regulatory Guide 1.109.

IPEC has compiled AiT factors for 3 age groups and various organs for the maximum exposed individual. These are included as Table 2-1,2-2, and 2-3. For completeness, this table includes all isotopes found in Reg Guide 1.1 09, however, several isotopes listed are not routinely identified at IPEC. In addition, the values for Antimony, Silver, Cesium, and Niobium are site specific as previously discussed.

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ODCM Part II - Calculational Methodologies 2.5 Backup Simplified Dose Methodology 2.5.1 An alternate computer method which completely complies with Section 2.4 is available should the primary computer system be inoperable.

2.5.2 Hand Calculations which completely comply with Section 2.4 can be employed if the primary and secondary computer codes are inoperable. Because they are time .

consuming and subject to calculational errors, procedural guidance in the actual flow of calculations should be used to maintain a standard format. These procedures are also used for benchmark tests of the computer codes.

2.6 Site Specific Bio-Accumulation & Dose Factors 2.6.1 As stated in Section 2.4.3 the bioaccumulation factor (BFi) for Cesium in fish is assumed to be 224 instead*of the 2000 listed in Regulatory Guide 1.109 (Ref. 3).

Similarly, the bioaccumulation factor for invertebrates is 224. This is based on three facts; 1) the Hudson River at IPEC is not completely fresh, 2) the Bioaccumulation Factor for salt water is 40 (Ref. 2), and 3) the behavior of Cesium in the Hudson is a complex phenomenon, as discussed below.

The NYU Study (Ref. 2) shows that Cesium concentrations in fish are regulated at a relatively constant value independent of the concentration of Cesium in water, and the bioaccumulation factors are thus inversely proportional to the water concentration of Cesium. This explains the lower bioaccumulation factor for Cesium reported by numerous investigators for salt water fish as opposed to fresh water fish because of the higher stable Cesium content of sea water. The NYU Report states that water at Indian Point has a dissolved Cesium concentration which is much higher than would be expected from simple mixing between sea water and fresh water and postulates that these higher concentrations result from leaching of Cesium from bottom sediment by saline water.

Use of the bioaccumulation factors of Regulatory Guide 1.109 for a fresh water site will thus substantially overestimate fish ingestion doses because no account is taken of the phenomena just discussed. However, radio-cesium concentrations in fish may still be estimated through the use of a bioaccumulation factor, provided that this factor is determined from the body of water of interest. This factor has been estimated (Ref.

12, page 33) to be about 224 for the flesh of indigenous fish caught in the Indian Point area. In contrast, the Cesium fresh water bioaccumulation factor presented by Regulatory Guide 1.109 for fish is 2000.

Fish ingestion doses would therefore be overestimated by a factor of 13 if the Regulatory Guide values were used.

Similarly for invertebrates, the site specific bioaccumulation factor of 224 is used. This is larger than the value of 25 given in Reg Guide 1.109 for salt water invertebrates.

A second conservatism in the NRC model concerns the location at which the concentrations in the river of the discharged Cesium are evaluated. Use of this model implies that these fish have grown directly in such a location prior to being caught, which is unrealistic and adds about a factor of five in conservation. This conservatism remains in the calculation, thus the use of the NYU (Ref. 12) bioaccumulation factor is justifiable.

IPEC ODCM Page 16 of 130 Revision 0

ODCM Part II - Calculational Methodologies 2.6.2 No bioaccumulation factor for Silver is listed in Rev. 1 of Regulatory Guide 1.109, Table A-1. The values of 2.3 and 5000 for fish and invertebrates were obtained from ORNL-4992 (sponsored by ERDA 660, Ref. 25) and are included in the ODCM in the interests of increased accuracy since Ag-11 Om is a potential component of IPEC liquid releases.

2.6.3 International Atomic Energy Agency Report No. 57 provides data more recent than that presented in Regulatory Guide 1.109 for niobium bioaccumulation factors. The factor in the Regulatory Guide appears to be substantially over-conservative and, therefore, the more recent IAEA information is incorporated into the dose calculation methodology for liquid releases of radio-niobium. The values from Table XVII of IAEA No. 57 are 300 and 100 for freshwater fish and marine invertebrates respectively and are incorporated into this ODCM.

2.6.4 Antimony isotopes are not listed in Reg. Guide 1.109. As for Niobium above, IAEA Report No. 57 was used to provide bioaccumulation factors for the Antimony isotopes in Table 2-1. Dose factors were calculated for Antimony as per Reference 13.

2.6.5 Te-123m dose factors are not listed in Reg. Guide 1.109. Since this isotope is

. identified from potentially faBed secondary startup sources and previously identified at IPEC, ingestion dose factors were derived from ICRP 30 and calculated per Ref 34.

2.6.6 In summary, with the exception of the bioaccumulation and dose factors discussed above, all remaining factors applied at IPEC are defined in Reg Guide 1.109 for a combination of fresh water fish and salt water invertebrates.

IPEC ODCM Page 17 of 130 Revision 0

ODCM Part II - Calculational Methodologies Table 2 - 1 Site Related Adult Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 2.S2E-Ol 2.S2E-Ol 2.S2E-Ol 2.S2E-Ol 2.S2E-Ol 2.S2E-Ol BE-7 3.29E-Ol 7.45E-Ol 3.69E-Ol O.OOE+OO 7.S3E-Ol O.OOE+OO 1.2SE+02 NA-24 4.0SE+02 4.0SE+02 4.0SE+02 4.0SE+02 4.0SE+02 4.0SE+02 4.0SE+02 P-32 4.96E+07 3.0SE+06 1.92E+06 O.OOE+OO O.OOE+OO O.OOE+OO 5.57E+06 CR-51 O.OOE+OO O.OOE+OO 4.31E+00 2.5SE+00 9.50E-Ol 5.72E+OO 1. OSE+03 MN-54 O.OOE+OO 5.43E+03 1.04E+03 O.OOE+OO 1.61E+03 O.OOE+OO 1.66E+04 MN-56 O.OOE+OO 1.37E+02 2.42E+Ol O.OOE+OO 1.73E+02 O.OOE+OO 4.36E+03 FE-55 3.21E+04 2.21E+04 5.16E+03 O.OOE+OO O.OOE+OO 1. 24E+04 1. 27E+04 FE-59 5.06E+04 1.19E+05 4.56E+04 O.OOE+OO O.OOE+OO 3.32E+04 3.96E+05 CO-5S O.OOE+OO 5.15E+02 1.15E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E+04 CO-60 O.OOE+OO 1.4SE+03 3.26E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.7SE+04 NI-63 4.97E+04 3.45E+03 1.67E+03 O.OOE+OO O.OOE+OO O.OOE+OO 7.19E+02 NI-65 2.02E+02 2.62E+Ol 1.20E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 6.65E+02 CU-64 O.OOE+OO 9.0SE+Ol 4.26E+Ol O.OOE+OO 2.29E+02 O.OOE+OO 7.74E+03 ZN-65 1.61E+05 5.13E+05 2.32E+05 O.OOE+OO 3.43E+05 O.OOE+OO 3.23E+05 ZN-69 3.43E+02 6.57E+02 4.57E+Ol O.OOE+OO 4.27E+02 O.OOE+OO 9.S7E+Ol BR-S3 O.OOE+OO O.OOE+OO 4.05E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 5.S4E+Ol BR-S4 O.OOE+OO O.OOE+OO 5.25E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 4.13E-04 BR-S5 O.OOE+OO O.OOE+OO 2.16E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-S6 O.OOE+OO 1.01E+05 4.72E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.00E+04 RB-SS O.OOE+OO 2.91E+02 1.54E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.02E-09 RB-S9 O.OOE+OO 1.93E+02 1.35E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.12E-ll SR-S9 2.57E+04 O.OOE+OO 7.37E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.12E+03 SR-90 6.32E+05 O.OOE+OO 1.55E+05 O.OOE+OO O.OOE+OO O.OOE+OO 1.S2E+04 SR-91 4.72E+02 O.OOE+OO 1.91E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 2.25E+03 SR-92 1.79E+02 O.OOE+OO 7.75E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+03 Y-90 6.07E+00 O.OOE+OO 1.63E-Ol O.OOE+OO O.OOE+OO O.OOE+OO 6.43E+04 Y-91M 5.73E-02 O.OOE+OO 2.22E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.6SE-Ol Y-91 S.S9E+Ol O.OOE+OO 2.3SE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.S9E+04 Y-92 5.33E-Ol O.OOE+OO 1.56E-02 O.OOE+OO O.OOE+OO O.OOE+OO 9.33E+03 Y-93 1.69E+00 O.OOE+OO 4.67E-02 O.OOE+OO O.OOE+OO O.OOE+OO 5.36E+04 ZR-95 1.63E+00 5.22E-Ol 3.54E-Ol O.OOE+OO S.20E-Ol O.OOE+OO 1.66E+03 ZR-97 9. 00K--02 1.S2E-02 S.30E-03 O.OOE+OO 2.74E-02 O.OOE+OO 5.63E+03 NB-95 4.S3E+00 2.69E+OO 1.44E+OO O.OOE+OO 2.65E+OO O.OOE+OO 1.63E+04 MO-99 O.OOE+OO 1.2SE+02 2.43E+Ol O.OOE+OO 2.90E+02 O.OOE+OO 2.97E+02 TC-99M 1. 59E-02 4".50E-02 5.73E-Ol O.OOE+OO 6.S4E-Ol 2.21E-02 2.66E+Ol TC-IOI 1.64E-02 2.36E-02 2.32E-Ol O.OOE+OO 4.25E-Ol 1. 21E-02 7.09E-14 RU-I03 1.10E+02 O.OOE+OO 4.74E+Ol O.OOE+OO 4.20E+02 O.OOE+OO 1.2SE+04 RU-I05 9.16E+00 O.OOE+OO 3.62E+OO O.OOE+OO 1.lSE+02 O.OOE+OO 5.60E+03 RU-I06 1.64E+03 O.OOE+OO 2.07E+02 O.OOE+OO 3.16E+03 O.OOE+OO 1.06E+05 AG-IIOM 4.5SE+02 4.23E+02 2.51E+02 O.OOE+OO S.32E+02 O.OOE+OO 1.73E+05 SB-122 3.47E+Ol 7.99E-Ol 1.20E+Ol 5.3SE-Ol O.OOE+OO 2.0SE+Ol 1.32E+04 SB-124 4.S6E+02 9.20E+OO 1.91E+02 1.lSE+OO O.OOE+OO 3.79E+02 1. 3SE+04 SB-125 3.11E+02 3.47E+OO 7.40E+Ol 3.16E-Ol O.OOE+OO 2.40E+02 3.42E+03 IPECODCM Page 18 of 130 Revision 0

ODCM Part II - Calculational Methodologies Table 2 - 1 Site Related Adult Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI TE-125M 2.72E+03 9.87E+02 3.65E+02 8.l9E+02 1.llE+04 O.OOE+OO 1.09E+04 TE-l27M 6.88E+03 2.46E+03 8.38E+02 1.76E+03 2.79E+04 O.OOE+OO 2.3lE+04 TE-l27 1.12E+02 4.0lE+Ol 2.42E+Ol 8.28E+Ol 4.55E+02 O.OOE+OO 8.82E+03 TE-129M 1.17E+04 4.36E+03 1.85E+03 4.01E+03 4.88E+04 O.OOE+OO 5.88E+04 TE-129 3.l9E+Ol 1.20E+Ol 7.77E+00 2.45E+Ol 1. 34E+02 O.OOE+OO 2.4lE+Ol TE-13lM 1.76E+03 8.60E+02 7.l6E+02 1.36E+03 8.71E+03 O.OOE+OO 8.53E+04 TE-13l 2.00E+Ol 8.36E+00 6.32E+00 1.65E+Ol 8.77E+Ol O.OOE+OO 2.83E+00 TE-132 2.56E+03 1. 66E+03 1. 55E+03 1. 83E+03 1.60E+04 O.OOE+OO 7.83E+04 I-130 4.88E+Ol 1.44E+02 5.68E+Ol 1.22E+04 2.24E+02 O.OOE+OO 1.24E+02 1-131 2.68E+02 3.84E+02 2.20E+02 1.26E+05 6.58E+02 O.OOE+OO 1.0lE+02 1-132 1.3lE+Ol 3.50E+Ol 1.23E+Ol 1.23E+03 5.58E+Ol O.OOE+OO 6.58E+00 I-133 9.l6E+Ol 1. 59E+02 4.86E+Ol 2.34E+04 2.78E+02 O.OOE+OO 1.43E+02 1-134 6.84E+00 1. 86E+Ol 6.64E+00 3.22E+02 2.95E+Ol O.OOE+OO 1.62E-02 I-US 2.86E+Ol 7.48E+Ol 2.76E+Ol 4.93E+03 1.20E+02 O.OOE+OO 8.45E+Ol CS-134 4.14E+04 9.84E+04 8.04E+04 O.OOE+OO 3.l8E+04 1.06E+04 1.72E+03 CS-136 4.33E+03 1. 7lE+04 1.23E+04 O.OOE+OO 9.5lE+03 1.30E+03 1.94E+03 CS-137 5.30E+04 7.25E+04 4.75E+04 O.OOE+OO 2.46E+04 8.l8E+03 1.40E+03 CS-138 3.67E+Ol 7.25E+Ol 3.59E+Ol O.OOE+OO 5.33E+Ol 5.26E+00 3.09E-04 BA-139 6.47E+00 4.6lE-03 1.89E-Ol O.OOE+OO 4.3lE-03 2.6lE-03 1.l5E+Ol BA-140 1.35E+03 1.70E+00 8.87E+01 O.OOE+OO 5.78E-01 9.73E-01 2.79E+03 BA-l41 3.14E+00 2.37E-03 1. 06E-Ol O.OOE+OO 2.2lE-03 1.35E-03 1.48E-09 BA-142 1.42E+00 1.46E-03 8.93E-02 O.OOE+OO 1.23E-03 8.27E-04 2.00E-18 LA-l40 1.58E+00 7.95E-Ol 2.l0E-Ol O.OOE+OO O.OOE+OO O.OOE+OO 5.83E+04 LA-142 8.07E-02 3.67E-02 9.l5E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.68E+02 CE-14l 3.23E+00 2.l8E+00 2.48E-Ol O.OOE+OO 1.01E+00 O.OOE+OO 8.35E+03 CE-143 5.69E-Ol 4.2lE+02 4.66E-02 O.OOE+OO 1.85E-Ol O.OOE+OO 1.57E+04 CE-144 1.68E+02 7.04E+Ol 9.04E+00 O.OOE+OO 4.l7E+Ol O.OOE+OO 5.69E+04 PR-143 5.80E+00 2.33E+00 2.88E-Ol O.OOE+OO 1.34E+00 O.OOE+OO 2.54E+04 PR-144 1.90E-02 7.88E-03 9.65E-04 O.OOE+OO 4.45E-03 O.OOE+OO 2.73E-09 ND-l47 3.97E+00 4.59E+00 2.74E-Ol O.OOE+OO 2.68E+00 O.OOE+OO 2.20E+04 W-187 2.98E+02 2.49E+02 8.71E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 8.l6E+04 NP-239 3.53E-02 3.47E-03 1.9lE-03 O.OOE+OO 1. 08E-02 O.OOE+OO 7.l2E+02 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-57 O.OOE+OO 1.21E+02 2.0lE+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.07E+03 SR-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-97 4.05E-02 1.02E-02 3.74E-03 O.OOE+OO 1.20E-02 O.OOE+OO 3.78E+Ol CD-l09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SN-1l3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-134 3.29E+Ol 2.l5E+Ol 1.32E+Ol 2.88E+Ol 2.08E+02 O.OOE+OO 3.65E-02 CE-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO HG-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO IPECODCM Page 19 of 130 Revision 0

ODCM Part II - Calculational Methodologies Table 2 - 2 Site Related Teen Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 2.17E-01 2.17E-01 2.17E-01 2.17E-01 2.17E-01 2.17E-01 BE-7 3.58E-01 8.02E-01 4.01E-01 O.OOE+OO 8.50E-01 O.OOE+OO 9.76E+01 NA-24 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 P-32 5.40E+07 3.35E+06 2.09E+06 O.OOE+OO O.OOE+OO O.OOE+OO 4.54E+06 CR-51 O.OOE+OO O.OOE+OO 4.44E+00 2.47E+00 9.73E-01 6.34E+00 7.46E-t02 MN-54 O.OOE+OO 5.33E+03 1.06E+03 O.OOE+OO 1.59E+03 O.OOE+OO 1.09E+04 MN-56 O.OOE+OO 1.43E+02 2.54E+01 O.OOE+OO 1.81E+02 O.OOE+OO 9.40E+03 FE-55 3.35E+04 2.37E+04 5.54E+03 O.OOE+OO O.OOE+OO 1.51E+04 1.03E-t04 FE-59 5.20E+04 1.21E+05 4.69E+04 O.OOE+OO O.OOE+OO 3.83E+04 2.87E-t05 CO-58 O.OOE+OO 5.10E+02 1.18E+03 O.OOE+OO O.OOE+OO O.OOE+OO 7.04E-t03 CO-60 O.OOE+OO 1.48E+03 3.32E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.92E-t04 NI-63 5.15E+04 3.64E+03 1.75E+03 O.OOE+OO O.OOE+OO O.OOE+OO 5.79E-t02 NI-65 2.18E+02 2.79E+01 1. 27E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.51E+03 CU-64 O.OOE+OO 9.53E+01 4.48E+01 O.OOE+OO 2.41E+02 O.OOE+OO 7.39E-t03 ZN-65 1.46E+05 5.07E+05 2.36E+05 O.OOE+OO 3.24E+05 O.OOE+OO 2.15E-t05 ZN-69 3.73E+02 7.10E+02 4.97E+01 O.OOE+OO 4.64E+02 O.OOE+OO 1.31E-t03 BR-83 O.OOE+OO O.OOE+OO 4.41E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE-tOO BR-84 O.OOE+OO O.OOE+OO 5.55E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE-tOO BR-85 O.OOE+OO O.OOE+OO 2.34E+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 1.09E+05 5.12E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.61E+04 RB-88 O.OOE+OO 3.12E+02 1.66E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.67E-05 RB~89 O.OOE+OO 2.01E+02 1.42E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.09E-07 SR-89 2.79E+04 O.OOE+OO 8.00E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.33E+03 SR-90 5.27E+05 O.OOE+OO 1. 30E+05 O.OOE+OO O.OOE+OO O.OOE+OO 1.48E-t04 SR-91 5.12E+02 O.OOE+OO 2.04E+01 O.OOE+OO O.OOE+OO O.OOE+OO 2.32E+03 SR-92 1.94E+02 O.OOE+OO 8.25E+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.93E+03 Y-90 6.57E+00 O.OOE+OO 1.77E-01 O.OOE+OO O.OOE+OO O.OOE+OO 5.42E+04 Y-91M 6.18E-02 O.OOE+OO 2.36E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.92E+00 Y-91 9.64E+01 O.OOE+OO 2.58E+00 O.OOE+OO O.OOE+OO O.OOE+OO 3.95E+04 Y-92 5.80E-01 O.OOE+OO 1.68E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.59E+04 Y-93 1.84E+00 O.OOE+OO 5.03E-02 O.OOE+OO O.OOE+OO O.OOE+OO 5.61E+04 ZR-95 1.68E+00 5.29E-01 3.64E-01 O.OOE+OO 7.78E-01 O.OOE+OO 1. 22E+03 ZR-97 9.65E-02 1.91E-02 8.80E-03 O.OOE+OO 2.90E-02 O.OOE+OO 5.17E+03 NB-95 4.86E+00 2.70E+00 1.48E+00 O.OOE+OO 2.61E+00 O.OOE+OO 1.15E+04 MO-99 O.OOE+OO 1.36E+02 2.60E+01 O.OOE+OO 3.12E+02 O.OOE+OO 2.44E+02 TC-99M 1.63E-02 4.55E-02 5.89E-01 O.OOE+OO 6.77E-01 2.52E-02 2.98E+01 TC-101 1.77E-02 2.51E-02 2.47E-01 O.OOE+OO 4.55E-01 1. 53E-02 4.30E-09 RU-103 1.15E+02 O.OOE+OO 4.93E+01. O.OOE+OO 4.06E+02 O.OOE+OO 9.63E+03 RU-105 9. 85E+00 . O.OOE+OO 3.82E+00 O.OOE+OO 1.24E+02 O.OOE+OO 7.96E+03 RU-106 1.77E+03 O.OOE+OO 2.23E+02 O.OOE+OO 3.42E+03 O.OOE+OO 8.50E+04 AG-110M 4.45E+02 4.22E+02 2.56E+02 O.OOE+OO 8.04E+02 O.OOE+OO 1.18E+05 SB-122 4.35E+01 8.47E-01 1.27E+01 5.53E-01 O.OOE+OO 2.72E+01 9.13E+03 SB-124 5.09E+02 9.40E+00 1.99E+02 1.16E+00 O.OOE+OO 4.45E+02 1.03E+04 SB-125 3.27E+02 3.58E+00 7.64E+01 3.11E-01 O.OOE+OO 2.85E+02 *2.53E+03 r

IPECODCM Page 20 of 130 Revision 0

aDCM Part II - Calculational Methodologies Table 2 - 2 Site Related Teen Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI TE-125M 2.96E+03 1. 07E+03 3.96E+02 8.28E+02 O.OOE+OO O.OOE+OO 8.75E+03 TE-127M 7.48E+03 2.65E+03 8.90E+02 1.78E+03 3.03E+04 O.OOE+OO 1.87E+04 TE-127 1.22E+02 4.33E+01 2.63E+01 8.44E+01 4.95E+02 O.OOE+OO 9.44E+03 TE-129M 1.26E+04 4.68E+03 2.00E+03 4.07E+03 5.28E+04 O.OOE+OO 4.74E+04 TE-129 3.47E+01 1.29E+01 8.44E+00 2.48E+01 1.46E+02 O.OOE+OO 1.90E+02 TE-131M 1.89E+03 9.06E+02 7.55E+02 1.36E+03 9.44E+03 O.OOE+OO 7.27E+04 TE-131 2.16E+01 8.90E+00 6.75E+00 1.66E+01 9.44E+01 O.OOE+OO 1.77E+00 TE-132 2.70E+03 1.71E+03 1.61E+03 1.80E+03 1.64E+04 O.OOE+OO 5.42E+04 1-130 5.06E+01 1.46E+02 5.84E+01 1.19E+04 2.25E+02 O.OOE+OO 1.12E+02 1-131 2.87E+02 4.02E+02 2.16E+02 1.17E+05 6.92E+02 O.OOE+OO 7.95E+01 1-132 1.37E+01 3.58E+01 1.29E+01 1.21E+03 5.64E+01 O.OOE+OO 1.56E+01 1-133 9.87E+01 1.67E+02 5.11E+01 2.34E+04 2.94E+02 O.OOE+OO 1.27E+02 1-134 7.17E+00 1.90E+01 6.82E+00 3.17E+02 2.99E+01 O.OOE+OO 2.50E-01 1-135 2.99E+01 7.71E+01 2.86E+01 4.96E+03 1. 22E+02 O.OOE+OO 8.54E+01 CS-134 4.24E+04 9.97E+04 4.63E+04 O.OOE+OO 3.17E+04 1.21E+04 1.24E+03 CS-136 4.35E+03 1.71E+04 1.15E+04 O.OOE+OO 9.32E+03 1.47E+03 1. 38E+03 CS-137 5.67E+04 7.54E+04 2.63E+04 O.OOE+OO 2.57E+04 9.97E+03 1.07E+03 CS-138 3.93E+01 7.54E+01 3.77E+01 O.OOE+OO 5.57E+01 6.48E+00 3.42E-02 BA-139 7.05E+00 4.96E-03 2.05E-01 O.OOE+OO 4.67E-03 3.42E-03 6.28E+01 BA-140 1.44E+03 1.76E+00 9.28E+01 O.OOE+OO 5.98E-01 1.19E+00 2.22E+03 BA-141 3.40E+00 2.54E-03 1.14E-01 O.OOE+OO 2.36E-03 1.74E-03 7.25E-06 BA-142 1.52E+00 1. 52E-03 9.33E-02 O.OOE+OO 1. 28E-03 1.01E-03 4.65E-12 LA-140 1.67E+00 8.20E-01 2.18E-01 O.OOE+OO O.OOE+OO O.OOE+OO 4.71E+04 LA-142 8.58E-02 3.81E-02 9.49E-03 O.OOE+OO .O.OOE+OO O.OOE+OO 1.16E+03 CE-141 3.49E+00 2.33E+00 2.67E-01 O.OOE+OO 1.10E+00 O.OOE+OO 6.66E+03 CE-143 6.16E-01 4.48E+02 5.01E-02 O.OOE+OO 2.01E-01 O.OOE+OO 1.35E+04 CE~144 1. 82E+02 7.55E+01 9.80E+00 O.OOE+OO 4.51E+01 O.OOE+OO 4.59E+04 PR-143 6.28E+00 2.51E+00 3.13E-01 O.OOE+OO 1.46E+00 O.OOE+OO 2.07E+04 PR-144 2.06E-02 8.44E-03 1.05E-03 O.OOE+OO 4.84E-03 O.OOE+OO 2.27E-05 ND-147 4.50E+00 4.89E+00 2.93E-01 O.OOE+OO 2.87E+00 O.OOE+OO 1. 76E+04 W-187 3.22E+02 2.62E+02 9.19E+01 O.OOE+OO O.OOE+OO O.OOE+OO 7.10E+04 NP-239 3.98E-02 3.75E-03 2.08E-03 O.OOE+OO 1.18E-02 O.OOE+OO 6.03E+02 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-57 O.OOE+OO 1.25E+02 2.10E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E+03 SR-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-97 4.36E-02 1.08E-02 3.95E-03 O.OOE+OO 1. 27E-02 O.OOE+OO 2.58E+02 CD-109 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SN-113 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-134 3.46E+01 2.22E+01 2.32E+01 2.84E+01 2.12E+02 O.OOE+OO 1.28E+00 CE-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO HG-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO. O.OOE+OO O.OOE+OO IPEC aDCM Page 21 of 130 Revision 0

ODCM Part II - Calculational Methodologies Table 2 - 3 Site Related Child Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 1.81E-01 1. 81E-01 1. 81E-01 1. 81E-01 1.81E-01 1.81E-01 BE-7 4.77E-01 8.08E-01 5.33E-01 O.OOE+OO 7.96E-01 O.OOE+OO 4.52E+01 NA-24 4 .. 57E+02 4.57E+02 4.57E+02 4.57E+02 4.57E+02 4.57E+02 4.57E+02 P-32 6.98E+07 3.27E+06 2.69E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1. 93E+06 CR-51 O.OOE+OO O.OOE+OO 4.86E+00 2.70E+00 7.37E-01 4.92E+00 2.58E+02 MN-54 O.OOE+OO 4.20E+03 1.12E+03 O.OOE+OO 1.18E+03 O.OOE+OO 3.53E+03 MN-56 O.OOE+OO 1.31E+02 2.96E+01 O.OOE+OO 1.59E+02 O.OOE+OO 1.90E+04 FE-55 4.55E+04 2.42E+04 7.48E+03 O.OOE+OO O.OOE+OO 1.37E+04 4.47E+03 FE-59 6.53E+04 1.06E+05 5.27E+04 O.OOE+OO O.OOE+OO 3.07E+04 1.10E+05 CO-58 O.OOE+OO 4.20E+02 1.29E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.45E+03 CO-60 O.OOE+OO 1. 23E+03 3.64E+03 O.OOE+OO O.OOE+OO O.OOE+OO 6.84E+03 NI-63 6.85E+04 3.67E+03 2.33E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.47E+02 NI-65 2.83E+02 2.66E+01 1.55E+01 O.OOE+OO O.OOE+OO O.OOE+OO 3.26E+03 CU-64 O.OOE+OO 9.05E+01 5.47E+01 O.OOE+OO 2.19E+02 O.OOE+OO 4.25E+03 ZN-65 1. 55E+05 4.12E+05 2.56E+05 O.OOE+OO 2.59E+05 O.OOE+OO 7.23E+04 ZN-69 4.94E+02 7.14E+02 6.60E+01 O.OOE+OO 4.33E+02 O.OOE+OO 4.50E+04 BR-83 O.OOE+OO O.OOE+OO 5.67E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-84 O.OOE+OO O.OOE+OO 6.56E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-85 O.OOE+OO O.OOE+OO 3.02E+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 1.06E+05 6.50E+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.80E+03 RB-88 O.OOE+OO 3.00E+02 2.08E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.47E+01 RB-89 O.OOE+OO 1. 85E+02 1.64E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.61E+00 SR-89 3.63E+04 O.OOE+OO 1. 04E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.41E+03 SR-90 4.68E+05 O.OOE+OO 1.19E+05 O.OOE+OO O.OOE+OO O.OOE+OO 6.30E+03 SR-91 6.60E+02 O.OOE+OO 2.49E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.46E+03 SR-92 2.48E+02 O.OOE+OO 9.96E+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.70E+03 Y-90 8.79E+00 O.OOE+OO 2.35E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.50E+04 Y-91M 8.17E-02 O.OOE+OO 2.97E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.60E+02 Y-91 1.29E+02 O.OOE+OO 3.44E+00 O.OOE+OO O.OOE+OO O.OOE+OO 1.71E+04 Y-92 7.70E-01 O.OOE+OO 2.20E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.22E+04 Y-93 2.44E+00 O.OOE+OO 6.69E-02 O.OOE+OO O.OOE+OO O.OOE+OO 3.63E+04 ZR-95 2.10E+00 4.62E-01 4.11E-01 O.OOE+OO 6.62E-01 O.OOE+OO 4.82E+02 ZR-97 1.27E-01 1.83E-02 1.08E-02 O.OOE+OO 2.63E-02 O.OOE+OO 2.77E+03 NB-95 5.75E+00 2.24E+00 1.60E+00 O.OOE+OO 2.10E+00 O.OOE+OO 4.14E+03 MO-99 O.OOE+OO 1.31E+02 3.23E+01 O.OOE+OO 2.79E+02 O.OOE+OO 1.08E+02 TC-99M 1. 99E-02 3.89E-02 6.46E-01 O.OOE+OO 5.66E-01 1.98E-02 2.22E+01 TC-101 2.30E-02 2.41E-02 3.06E-01 O.OOE+OO 4.11E-01 1. 27E-02 7.66E-02 RU-103 1.48E+02 O.OOE+OO 5.67E+01 O.OOE+OO 3.72E+02 O.OOE+OO 3.82E+03 RU-105 1.30E+01 O.OOE+OO 4.73E+00 O.OOE+OO 1.15E+02 O.OOE+OO 8.50E+03 RU-106 2.36E+03 O.OOE+OO 2.95E+02 O.OOE+OO 3.19E+03 O.OOE+OO 3.68E+04 AG-110M 5.24E+02 3.54E+02 2.83E+02 O.OOE+OO 6.59E+02 O.OOE+OO 4.21E+04 SB-122 5.80E+01 8.56E-01 1.70E+01 7.43E-01 O.OOE+OO 2.36E+01 4.46E+03 SB-124 6.55E+02 8.50E+00 2.29E+02 1.44E+00 O.OOE+OO 3.63E+02 4.09E+03 SB-125 4.22E+02 3.25E+00 8.85E+01 3.91E-01 O.OOE+OO 2.35E+02 1.01E+03 IPEC ODCM Page 22 of 130 Revision 0

aDCM Part II - Calculational Methodologies Table 2 - 3 Site Related Child Ingestion Dose Commitment Factors (Freshwater Fish and Saltwater Invertebrate Consumption)

(AiT) mR/hr per uCi/ml ISOTOPE BONE LIVER TOT BODY THYROID KIDNEY LUNG GI-LLI TE-125M 3.81E+03 1.03E+03 5.08E+02 1.07E+03 O.OOE+OO O.OOE+OO 3.68E+03 TE-127M 9.67E+03 2.60E+03 1.15E+03 2.31E+03 2.76E+04 O.OOE+OO 7.83E+03 TE-127 1. 58E+02 4.25E+01 3.38E+01 1.09E+02 4.48E+02 O.OOE+OO 6.15E+03 TE-129M 1. 63E+04 4.55E+03 2.53E+03 5.25E+03 4.78E+04 O.OOE+OO 1. 99E+04 TE-129 4.48E+01 1.25E+01 1.06E+01 3.20E+01 1. 31E+02 O.OOE+OO 2.79E+03 TE-131M 2.41E+03 8.33E+02 8.86E+02 1.71E+03 8.06E+03 O.OOE+OO 3.38E+04 TE-131 2.78E+01 8.46E+00 8.26E+00 2.12E+01 8.40E+01 O.OOE+OO 1.46E+02 TE-132 3.38E+03 1.50E+03 1.81E+03 2.18E+03 1.39E+04 O.OOE+OO 1.51E+04 I-130 6.28E+01 1.27E+02 6.54E+01 1.40E+04 1.90E+02 O.OOE+OO 5.94E+01 I-131 3.70E+02 3.72E+02 2.12E+02 1.23E+05 6.11E+02 O.OOE+OO 3.31E+01 I-132 1.72E+01 3.16E+01 1.45E+01 i.47E+03 4.84E+01 O.OOE+OO 3.72E+01 I-133 1.27E+02 1. 58E+02 5.96E+01 2.93E+04 2.63E+02 O.OOE+OO 6.35E+Ol I-134 9.02E+00 i.67E+01 7.70E+00 3.85E+02 2.56E+01 O.OOE+OO 1. 11E+01 I-135 3.77E+01 6.78E+01 3.21E+01 6.00E+03 1.04E+02 O.OOE+OO 5.16E+01 CS-134 5.15E+04 8.44E+04 1.78E+04 O.OOE+OO 2.62E+04 9.39E+03 4.55E+02 CS-136 5.17E+03 1.42E+04 9.19E+03 O.OOE+OO 7.56E+03 1.13E+03 4.99E+02 CS-137 7.19E+04 6.88E+04 1.02E+04 O.OOE+OO 2.24E+04 8.07E+03 4.31E+02 CS-138 5.01E+01 6.97E+01 4.42E+01 O.OOE+OO 4.90E+01 5.28E+00 3.21E+01 BA-139 9.34E+00 4.99E-03 2.71E-01 O.OOE+OO 4.35E-03 2.93E-03 5.39E+02 BA-140 '1.87E+03 1.64E+00 1.09E+02 O.OOE+OO 5.35E-01 9.79E-01 9.50E+02 BA-141 4.51E+00 2.53E-03 1 . .4 7E-01 O.OOE+OO 2.19E-03 1.48E-02 2.57E+00 BA-142 1.97E+00 1.42E-03 1.10E-01 O.OOE+OO 1.15E-03 8.35E-04 2.57E-02 LA-'l40 2.16E+00 7.55E-01 2.54E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+04 LA-142 1.12E-01 3.57E-02 1.12E-02 O.OOE+OO O.OOE+OO O.OOE+OO 7.08E+03 CE-141 4.65E+00 2.32E+00 3.45E-01 O.OOE+OO 1. 02E+00 O.OOE+OO 2.90E+03 CE-143 8.19E-01 4.44E+02 6.44E-02 O.OOE+OO 1.86E-01 O.OOE+OO 6.51E+03 CE-144 2.44E+02 7.64E+01 1.30E+01 O.OOE+OO 4.23E+01 O.OOE+OO 1.99E+04 PR-143 8.40E+00 2.52E+00 4.17E-01 O.OOE+OO 1.37E+00 O.OOE+OO 9.06E+03 PR-144 2.76E-02 8.53E-03 1.39E-03 O.OOE+OO 4.51E-03 O.OOE+OO 1.84E+01 ND-147 5.96E+00 4.83E+00 3.74E-01 O.OOE+OO 2 .. 65E+00 O.OOE+OO 7.65E+03 W-187 4.08E+02 2.42E+02 1. 08E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.40E+04 NP-239 5.15E-02 3.70E-03 2.60E-03 O.OOE+OO 1.07E-02 O.OOE+OO 2.74E+02 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-57 O.OOE+OO 1.15E+02 2.33E+02 O.OOE+OO O.OOE+OO O.OOE+OO 9.43E+02 SR-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-97 5.55E-02 1.00E-02 4.68E-03 O.OOE+OO 1. 11E-02 O.OOE+OO 3.09E+03 CD-109 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SN-113 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-134 4.31E+01 1.94E+01 2.59E+01 3.41E+01 1.80E+02 O.OOE+OO 1.97E+02 CE-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO HG-203 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO IPEC aDCM Page 23 of 130 Revision 0

aDCM Part II - Calculational Methodologies Table 2-4 Bio-Accumulation Factors for Liquid Effluent Isotopes (pCi/kg per pCi/liter)

Freshwater Saltwater Freshwater Saltwater ISOTOPE Fish Invertebrates ISOTOPE Fish Invertebrates BFi BIi BFi BIi H-3 9.000E-01 9.300E-01 TE-125M 4.000E+02 1.000E+02 BE-7 2.000E+00 2.000E+02 TE-127M 4.000E+02 1.000E+02 NA-24 1.000E+02 1.900E-01 TE-l27 4.000E+02 1.000E+02 P-32 1.000E+05 3.000E+04 TE-129M 4.000E+02 1.000E+02 CR-51 2.000E+02 2.000E+03 TE-129 4.000E+02 1.000E+02 MN-54 4.000E+02 4.000E+02 TE-131M 4.000E+02 1.000E+02 MN-56 4.000E+02 4.000E+02 TE-131 4.000E+02 1.000E+02 FE-55 1.000E+02 2.000E+04 TE-132 4.000E+02 1.000E+02 FE-59 1.000E+02 2.000E+04 1-130 1.500E+01 5.000E+01 CO-58 5.000E+01 1.000E+03 1-131 1.500E+01 5.000E+01 CO-60 5.000E+01 1.000E+03 1-132 1.500E+01 5.000E+01 NI-63 1.000E+02 2.500E+02 1-133 1.500E+01 5.000E+01 NI-65 1.000E+02 2.500E+02 1-134 1.500E+01 5.000E+01 CU-64 5.000E+01 1.700E+03 1-135 1.500E+01 5.000E+01 ZN-65 2.000E+03 5.000E+04 CS-134 2.240E+02 2.240E+02 ZN-69 2.000E+03 5.000E+04 CS-136 2.240E+02 2.240E+02 BR-83 4.200E+02 3.100E+00 CS-137 2.240E+02 2.240E+02 BR-84 4.200E+02 3.100E+00 CS-138 2.240E+02 2.240E+02 BR-85 4.200E+02 3.100E+00 BA-139 4.000E+00 1.000E+02 RB-86 2.000E+03 1.700E+01 BA-140 4.000E+00 1.000E+02 RB-88 2.000E+03 1.700E+01 BA-141 4.000E+00 1.000E+02 RB-89 2.000E+03 1.700E+01 BA-142 4.000E+00 1.000E+02 SR-89 3.000E+01 2.000E+01 LA-140 2.500E+01 1.000E+03 SR-90 3.000E+01 2.000E+01 LA-142 2.500E+01 1.000E+03 SR-91 3.000E+01 2.000E+01 CE-141 1.000E+00 6.000E+02 SR-92 3.000E+01 2.000E+01 CE-143 1.000E+00 6.000E+02 Y-90 2.500E+01 1.000E+03 CE-144 1.000E+00 6.000E+02 Y-91M 2.500E+01 1.000E+03 PR-143 2.500E+01 1.000E+03 Y-91 2.500E+01 1.000E+03 PR-144 2.500E+01 1.000E+03 Y-92 2.500E+01 1.000E+03 NO-147 2.500E+01 1.000E+03 Y-93 2.500E+01 1.000E+03 W-187 1.200E+03 3.000E+oi ZR-95 3.300E+00 8.000E+01 NP-239 1.000E+01 1.000E+01 ZR-97 3.300E+00 8.000E+01 K-40 O.OOOE+OO O.OOOE+OO NB-95 3.000E+02 1.000E+02 CO-57 5.000E+01 1.000E+03 MO-99 1.000E+01 1.000E+01 SR-85 O.OOOE+OO O.OOOE+OO TC-99M 1.500E+01 5.000E+01 Y-88 O.OOOE+OO O.OOOE+OO TC-101 1.500E+01 5.000E+01 NB-94 3.000E+02 1.000E+02 RU-103 1.000E+01 1.000E+03 NB-97 3.000E+02 1.000E+02 RU-105 1.000E+01 1.000E+03 CO-109 O.OOOE+OO O.OOOE+OO RU-106 1.000E+01 1.000E+03 SN-1l3 O.OOOE+OO O.OOOE+OO AG-llOM 2.300E+00 5.000E+03 BA-133 O.OOOE+OO O.OOOE+OO SB-122 1.000E+00 3.000E+02 TE-134 4.000E+02 1.000E+02 SB-124 1.000E+00 3.000E+02 CE-139 O.OOOE+OO O.OOOE+OO SB-125 1.000E+00 3.000E+02 HG-203 O.OOOE+OO O.OOOE+OO Bio-Accumulation Factors and OFi'sfor Noble Gases 0 IPEC aDCM Page 24 of 130 Revision 0

ODCM Part II - Calculational Methodologies 3.0 GASEOUS EFFLUENTS 3.1 Gaseous Effluent Releases - General Information 3.1.1 A completed and properly authorized Airborne Radioactive Waste Release Permit shall be issued prior to the release of airborne activity from the waste gas holding system, containment purge, or any other batch release.

3.1.2 Since Indian Point is a two unit site, the derived instantaneous ~Ci/sec limits for each unit, (Section 3.2) were derived from an actual site limit (Appendix I). The time-average limits are "per reactor", and applicable to each unit.

3.1.3 During Modes 4 through 6, there is no flowpath for a release from the Condenser Air Ejector. During these intervals, when there is no actual release pathway, the monthly grab sample described in RECS D3.2.1 is not required.

3.1.4 During normal plant operation (without a primary to secondary leak), almost all gaseous releases are through the main Plant Vent. A negligible amount may be identified in other pathways (see Appendix C).

In the event of extended operation with a primary to secondary leak, low level releases are expected from both the blowdown flash tank vent and condenser air ejector. However, the limits on steam generator leakage are much more restrictive than those for effluent releases. Therefore, allocation of portions of the allowable release rate to these various release points during routine operation is not warranted.

If, on the other hand, the instantaneous release rate is being considered for the Plant Vent, then ALL release points should be considered when establishing alarm setpoints, per ODCM Part II, Section 1.

3.1.5 For releases that are expected to continue for periods over two days, a new release permit will normally be issued each day.

A containment purge permit may be closed, with the release reclassified as continuous building ventilation, when activity in containment is sufficiently reduced to that level which, if released for 31-days, would remain BELOW the dose projection limits.

However, when plant conditions change, such that releases to containment are likely, a new permit should be evaluated.

3.1.6 Assurance that the combined gaseous releases from Units 2 and 3 do not exceed limits of Section 3.2.1 is provided by administrative controls for both units. These controls include apportionment of the 10CFR20 limitations and back-calculating radiation monitor setpoints accordingly. These calculations are discussed in Appendix I.

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ODCM Part II - Calculational Methodologies 3.1.7 By mutual agreement with units 2 and 3 Shift Supervisors, one unit can reduce or eliminate discharges for a period of time to allow the other unit to use the full site permissible discharge rate, or a specific portion thereof, for unique releases that may require the site limit for release rate. To better control these evolutions, written agreement to the apportionment is generally kept with each unit's CRS and included on applicable permits for the duration.

3.1.8 Conservative release rate limitations have been established to ensure compliance with 10CFR20, and to aid in controlling time average dose limits. The annual average release rate limit (Appendix I) shall normally be used for calculating limitations on discharge. If this limitation is unduly restrictive, other release rates may be allowed, per Appendix I, and summarized below:

As described in Appendix I, the ODCM instantaneous limit provides a maximum release rate with an actual or suspected isotopic mixture, back-calculated from the actual 10CFR20 limit (500 mrem/yr for the site). The calculations for the use of this limit should be verified within the Chemistry department. The default interval in which to determine the proximity to this limit (uCi/sec or mrem/yr) is one hour or less.

3.1.9 Containment Pressure Reliefs Containment pressure reliefs occur frequently enough to be considered continuous releases. Grab samples of containment atmosphere are obtained periodically to ensure the use of accurate mixtures in effluent calculations. The containment noble gas monitors (R-42 for Unit 2 and R-12 for Unit 3) are used in conjuction with expected flow rates to determine a release rate. The effluent noble gas monitor in the plant vent is also used to verify total unit release rate remains below the current authorized limit.

3.1.10 Composite Particulate Samples Continuous building ventilation exhaust points are sampled continuously for Iodine and Particulate. Media is replaced weekly, with composite filters prepared for vendor lab analyses monthly.

3.1.11 Flow rate measurement for the Continuous Building Ventilation systems is typically obtained from the installed process monitor or nearby instrument. When the process flow rate instrument is OOS, estimates are performed every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per the RECS, to allow appropriate quantification of continuous airborne effluent. The estimates are typically performed by summing the exhaust flow rates (or design flow rate) from any operable fans. Unit 3's PV flow may be estimated from a backup instrument.

Unit 3's Admin Bldg does NOT have a flow rate instrument (design flow of 12500 cfm is used). The process flow rate monitor surveillance requirements specified in the RECS are not applicable for the Unit 3 Admin Building.

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aDCM Part II - Calculational Methodologies 3.1.12 Gas Storage Tank Activity Limits The quantity of radioactivity in each gas storage tank is limited to 50,000 Ci of noble gas, Xenon-133 equivalent, per RECS 03.2.6. The source of this requirement is NUREG 0133 (Section 5.6.1) for both units. However, the parameters used in the given equation are applied differently at each unit, as defined in the FSARs and summarized in the following discussion:

Unit 2:

(500mrem)

• 3.15E + 7 sec/ yr Q133= 3 = 29,761 Ci (lE6J1Ci/ Ci)(294mrem - m 3 / JLCi - yr)(1.81E - 3 sec/ m )

Where; 294 mrem-m 3"-lCi-yr = the Xe-133 WB dose factor, RG 1.109, table B-1 (K).

1.81 E-3 sec/m 3 =Design Basis Accident XlQ from Indian Point 2 FSAR An actual curie limit is calculated by substituting the actual mixture Keff into the equation above. For example, the Keff for the accident mix computed using Table 14.2-5 of the FSAR is 476 mrem-m 3hlCi-yr. Thus, the actual activity limit (for an expected mixture of radionuclides, not just Xe-133) is:

(500mrem)

• 3.15E + 7 sec/ yr Q133= 3 = 18,300 Ci (lE6JLCi/Ci)(476mrem-m 3 /JLCi-yr)(l.81E-3 sec/m)

Similar calculations could be performed with actual Keff and XlQ data.

As demonstrated above, the setpoints calculated from NUREG 0133 modeling assume Xe-133 equivalent and no tank interconnections (29,761 Ci of Xe-133 equivalent or 18,300 Ci for an expected accident mixture).

However, the tanks are, in fact, generally interconnected, requiring a more conservative approach. The unit 2 FSAR (14.2.3) has established a specific gas decay tank limit of 6,000 Ci each. This value is based on the original RECS required 29,761 curies of Xe-133 equivalent, divided into 4 large and all 6 small gas decay tanks. Given the actual atmospheric volume of the tanks (525 fe for each large and 40 fe for each small), the total volume is approximately 4.5 tanks:

29,761 = 6,000 Ci Xe-133 Equivalent 4.5 The RECS required gas storage tank radiation monitor (R-50), is therefore set to alarm at 6,000 curies. Warn setpoints are established by procedure, usually with consideration for measured tank contents and anticipated release rate.

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