Text

Annual Radioactive Effluent Release Rept Jan-Dec 1993. W/940331 Ltr
	ML18059A916
Person / Time
Site:	Palisades
Issue date:	12/31/1993
From:	Rogers D; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9404040195
	Download: ML18059A916 (220)
	v • d • e

l\o-, .- -- J"W'""!!

consumers Power David W. Rogers Plant Safety and Licensing Director POWERIN&

MICHlliAN'S PRDliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 March 31, 1994 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - 1993 ANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT Enclosed is the 1993 Annual Radioactive Effluent Release and Waste Disposal report for the Palisades plant.

10 CFR 50.36a has been changed to require the Radioactive Effluent Release and Waste Disposal Report be submitted to the NRC once every twelve months instead of semi-annually. This is the first annual report submitted.

David W. Rogers Safety and Licensing Director CC: Administrator Region III, USNRC Resident Inspector, Palisades -

Enclosure 9404040195 931231

~DR ADOCK 05000255 PDR A OHS ENERGY COMPANY

Enclosure 1 Consumers Power Company Pali sades Pl ant Docket 50-255 1993 ANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT March 31, 1994

PALISADES NUCLEAR PLANT ANNUAL

RADIOACTIVE EFFLUENT RELEASE REPORT January - December 1993 This report provides information relating to radioactive effluent releases and solid radioactive waste processing at the Palisades Nuclear Plant during the period of January 1, 1993 through December 31, 1993. Palisades was off-line various times during this reporting period. The following is a summary of the plant operating status between January 1, 1993 and December 31, 1993:

January through March 1993 The plant operated at full power during these three (3) months.

April 1993 The plant began the month at full power until April 28, when an orderly shutdown commenced, due to a unidentified PCS leakage requiring us to take the unit off-line. An Unusual Event was declared and the plant went off-line at 2158 hrs on April 28, 1993.

May 1993 The plant remained off-line through May 16, 1993. During this forced outage,

six control rod drive seal housings were replaced, one (1) primary coolant pump seal was replaced and various other maintenance and surveillance activities were performed. The plant went back on-line on May 16, 1993 and operated at full power the rest of the month.

June 1993 The plant began the month at full power .. On June 4, 1993, the plant de-escalated in power to start the scheduled Refueling Outage. The plant was taken off-line at 2301 hrs and remained there through the end of June.

July through October 1993 The plant was off-line during this time period for the plants refueling outage.

November 1993 The plant was off-line until November 5, 1993. On November 5, 1993, the plant was placed on-line at 0432 hrs, but went off-line at 0731 hrs to r~pair a trubine electrohydraulic control system leak. The plant returned to power at 0944 hrs on November 6, 1993, but was taken off-line again at 2105 hrs on the same day for a "turbine overs peed trip test. 11 The test failed, so repairs were made and the plant went back on-line at 0534 hrs on November 8, 1993. On November 8, 1993 at 1419 hours0.0164 days 0.394 hours 0.00235 weeks 5.399295e-4 months , the "turbine overspeed trip test" was repeated satisfactorily and the plant was placed back on-line at 1705 hours0.0197 days 0.474 hours 0.00282 weeks 6.487525e-4 months . The plant remained on-line the remainder of the month.

1 I

I December 1993

The plant remained at full power for the entire month.

1. Supplemental Information A. Batch Releases Information relating to batch release of gaseous and liquid effluents is provided in Table HP 10.5-1 (Attachment 1).

B. Abnormal Releases

1. Failure of the Emergency Escape Airlock Equalizing Valve On March 6, 1993, at 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months , it was determined that containment integrity , as defined in Technical Specification 1.4 and 3.6.la, was violated due to an equalizing valve of the emergency escape airlock sticking open. This discovery was made at the time that the plant staff was performing Technical Specification S0-48, "Escape Air Lock Penetration Leak Test." As a result of this discovery, an Event Report, E-PAL-93-007, was written. The root cause of this event was determined to be a sticking equalizing valve due to the lubricant drying out and becoming tacky due to heat and lack of usage of this airlock. The

corrective action was the purchase of a new type of lubricant that was used in REFOUT 93.

A determination of the quantity of radioactivity released was calculated and documented in a Licensee Event Report 93-002. The isotopes and activity released via this pathway were:

Rb-88: l.675E-Ol µCi; Cs-138: 5.168E-03 µCi; Ar-41: 2.09E+OO µCi; Xe-133: 5.912E+Ol µCi; Xe-135: 3.28E+OO µCi and I-131: 6.785E-04

µCi. (Note: Y-88 was previous reported, however upon further review of the data, it was determined that this isotope was not present, but was actually Rb-88 as is being reported in the effluent report.)

The activity reported above is reflected in the activity totals of the report.

2. SIRW Tank Activity Limit Exceeded.

(NOTE: No actual release took place)

The Effluent Concentration (EC) activity limit (100,000%) for the SIRW tank was exceeded on August 30, 1993 due to the transfer of reactor cavity water. This evolution resulted in an EC value of 116,800%. Upon discovery of this_situation, per the ODCM, Appendix A,Section III.K(2) all additions of radioactive material to the tank is to be immediately suspended and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within limits. The tank was

immediately placed on recirculation through the demineralizer and

the EC activity was reduced from 116,800% to 84,900% within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The evaluation of this event revealed that historically the reactor cavity water is run through a demineralizer to reduce activity when transferring it to the SIRW tank. However, Operations did not want to send the water through the demineralizer until the activity level in the tank was known due to the fuel problems encountered during REFOUT 93. This decision was thought to be a conservative measure in order to avoid the creation of localized hot spots in the clean-up demineralizer.

The specific details of this event is recorded in D-PAL-93-208.

C. Lower Limits of Detection (LLD's) for gaseous and liquid effluents is provided in Attachment 5.

D. Radioactive Effluent Monitoring Instrumentation:

1

.1. Waste Gas Decay Tank Vent Flow Indicator (Fl-1121)

The Offsite Dose Calculation Manual (ODCM), Appendix A, Table A-1 requires that when a radioactive gaseous effluent monitoring instrument channel becomes inoperable, best efforts m~st be made to return the instrument to operable status within 30-days and if

unsuccessful, report the incident in the next Radioactive Effluent Report. The Offsite Dose Calculation Manual, Appendix A, Table A-1 further stipulates that radioactive effluent releases may continue to be made with less than the required amount of operable channels providing that the flow rate is estimated at least once per 24-hours for continuous releases or at least every four hours for batch releases.

On July 7, 1993, it was determined that the flow indicator, FI-1121 was inoperable. As required per Health Physics Procedure HP 6.6, if FI-1121 is inoperable during Waste Gas Decay Tank batch releases, releases may continue provided the flow rate is estimated by the Primary Side Auxiliary Operator at least every four hours during batch releases. These calculations were performed, as necessary, for batch releases during the period of July 7, 1993 through December 31, 1993.

The root cause of the problem continues to be the fact that when a flow is applied to the rotameter the "float pin" oscillates violently which resulted in the "float pin" bending. The float pin has previously been straightened and an adjustment made to PCV-1123 was made.

The corrective solution to this reliability problem is to replace the instrument with a new flow indicator with a wider flow range.

This corrective action has been turned over to the Instrument and Control System Engineering Group per work order 24204932.

During the period of inoperability, all of the Offsite Dose

Calculation Manual (ODCM) sampling requirements as stated in Table A-1 were met.

A detailed report of the work performed on FI-1121 is documented in work order 24202520.

2) Failed Fuel Monitor (RIA-0202A)

(NOTE: This is not a process monitor)

This monitor was declared inoperable on March 21, 1993 due to a questionable flow going through the monitor. This monitor remained on the LCO Board most of the year. During this time period, the boronometer was removed (per a Facility Change) and a new flow indicator was installed. During plant start-up from REFOUT 93, the RMC Group started the calibration of this monitor.

The monitor calibration was completed and approved December 30, 1993.

The Chemistry Department sampled and analyzed the primary coolant as required per Technical Specification Table 4.2.1, Footnote (1) during the period that RIA-0202A was declared inoperable.

2* Gaseous Effluents

Table HP 10.5-2 (Attachment 2) lists and summarizes all gaseous radioactive effluents released during the ~eporting period. The unidentified beta was 1.44E-04% of the total release.

The June 1993 stack gas filter Sr-89/Sr-90 values were calculated by performing a ratio of the previous and post two (2) months analysis results of Sr-89/Sr-90 versus unidentified beta to determine the June values. This calculation was performed due to the June 1993 stack filters being lost. A Deviation Report, D-Pal-93-180, was generated to identify and evaluate this violation of the ODCM, Appendix A, Table B-1.

3. Liquid Effluents Table HP 10.5-3 (Attachment 3) lists and summarizes all liquid radioactive effluents released during the reporting period. The unidentified beta was 1.96E-04% of the total release.

4. Solid Waste There were no solid waste shipments from January 1 to December 31, 1993 (Table HP 10.5-4, Attachment 4).

5. Summary of Radiological Impact on Man Potential doses to individuals and populations were calculated using GASPAR and LADTAP computer program codes. The quarterly values for curies released were input for each nuclide and summarized as follows:

A. The offsite air doses at the site boundary (0.48 SSE) due to noble

gases were 2.SIE-06 millirad beta and 4.28E-07 millirad gamma for the first quarter; l.73E-03 millirad beta and 4.82E-04 millirad gamma for the second quarter; l.16E-04 millirad beta and l.IIE-06 millirad gamma for the third quarter; and 2.75E-03 millirad beta and 9.25E-04 millirad gamma for the fourth quarter. The maximum noble gas offsite air dose to the nearest residence (0.50 mi S) for beta occurred during the fourth quarter, being l.96E-03 millirads beta and for gamma during the fourth quarter being 6.60E-04 millirads gamma.

B. The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluent releases (tritium, particulate, and iodine) was the child bone for all four (4) quarters. Doses were 4.94E-03 millirem for the first quarter; l.23E-02 millirem for the second quarter; 2.IBE-02 millirem for the third quarter; and l.58E-02 millirem for the fourth quarter.

C. Integrated total body doses to the general population and average doses to individuals within the population from gaseous effluent release pathways to a distance of 50-miles from the site boundary were: 5.96E-03 person-Rem and 5.14E-06 millirem for the first quarter; l.IOE-02 person-Rem and 9.48E-06 millirem for the second quarter; l.69E-02 person-Rem and l.46E-05 millirem for the third quarter; and l.16E-02 person-Rem and l.OOE-05 millirem for the fourth quarter.

D. The maximum total body dose to an individual in unrestricted water-rel ated exposure pathways was l.31E-03 millirem (adult) for the first quarter; 2.09E-03 millirem (adult) for the second quarter; 5.43E-03 millirem (adult) for the third quarter; and 5.54E-03 millirem (adult) for the fourth quarter. The maximum organ doses were 2.17E-03 millirem (teenage liver) for the first quarter; 3.28E-03 millirem (teenage liver) for the second quarter; 8.41E-03 millirem (teenage liver) for the third quarter; and 9.20E-03 millirem (teenage liver) for the fourth quarter.

E. Integrated total body doses to the general population and average doses to individuals within the population from liquid effluent release pathways to a distance of 50-miles from the site boundary were: 5.24E-03 person-Rem and 4.52E-06 millirem for the first quarter; 9.30E-03 person-Rem and 8.02E-06 millirem for the second quarter; 2.09E-02 person-Rem and I.BOE-OS millirem for the third quarter; and l.95E-02 person-Rem and l.68E-05 millirem for the fourth quarter.

6. Process Control Program (PCP)

The Process Control Program was revised, effective January I, 1993, which relocated the Technical Specification requirements pertaining to solid radwaste to Appendix C of the Process Control Program (PCP). The programmatic controls were retained in the Administrative Controls section of Technical Specifications. These changes were implemented per the guidance outlined in the NRC Generic Letter 89-01.

A copy of the revised PCP is enclosed (Attachment 7) along with the supporting documentation as per the requirements of Technical Specification 6.19 .

7. Offsite Dose Calculation Manual (ODCM)

There were several changes to the Palisades Offsite Dose Calculation Manual, Revision 7, during this reporting period, which include:

A. Update of Table 1.4, 1992 Palisades Land Use Census; B. Update of Table 1.4a; 1992 Palisades Land Use Census - Critical Receptor Items; C. Update of Table 1.9; 1993 Palisades Gaseous Design - Objective Annual Quantities; D. Reflect the changes of relocating procedural requirements related to gaseous and liquid effluents, total dose, environmental monitoring program and associated procedural reporting requirements from the Technical Specifications, as allowed per NRC Generic Letter 89-01. This changed included the creation of a new section, "Appendix A".

E. Reflects the new terminology used in the new 10CFR20; F. Addition of a new "Action 5" to Appendix A, Table A-1; G. Addition of a new section, ODCM, Appendix A, Section 111.K, which provides the requirements that specifies the concentration limits

H.

I.

allowed in the SIRW tank.

Clarification of the ODCM, Appendix A, Section 11.K(l) by adding a formula.

Add an allowance to bypass the Vacuum Degassifier for greater than 7 days when the reactor is in cold shutdown and depressurized.

The revised ODCM is enclosed with this report (Attachment 6) along with supporting documentation as per the requirements of Technical Specification 6.18. Attachment B to the ODCM, "Request to Retain Soil in Accordance with 10CFR20.302," has not been included with this submittal as no revisions to Appendix B have been made .

ATTACHMENT 1

Consumers Power Company Palisades Plant RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES January - December 1993 March 31, 1994

1 Page

TABLE HP 10.5-1

PALISADES PLANT RADIOACTIVE EFFLUENT REPORT BATCH RELEASES January l, 1993 to December 31, 1993 A. GASEOUS Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Number of Releases 3 10 14 1 Total Release Time Minutes 626 2874 4150 417 Maximum Release Time Minutes 345 501 605 417 Average Release Time Minutes 209 287 296 417 Minimum Release Time Minutes 105 155 120 417

B. LIQUID Number of Releases Total Release Time Units Minutes 1st Qtr 1

595 2nd Qtr 1254 3

3rd Qtr 2

1156 4th Qtr 1

1528 Maximum Release Time Minutes 595 554 626 1528 Average Release Time Minutes 595 418 578 -1528 Minimum Release Time Minutes 595 230 530 1528

ATTACHMENT 2

Consumers Power Company Palisades Plant RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES January - December 1993 March 31, 1994

' ~*-

3 Pages

TABLE HP 10.5-2

PALISADES PLANT RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES January l, 1993 to December 31, 1993 Est Total A. FISSION AND ACTIVATION GASES Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Error %

1. Total release Ci 4.0SE-02 3.24E+01 1.35E+OO 5.90E+01

2. Average release rate for S.20E-03 4.13E+OO 1. 70E-01 7.42E+OO 5.66E+OO period µCi/sec

3. Percent of annual avg EC % 1.39E-06 1.26E-03 3.47E-05 2.12E-03 B. IODINES

1. Total Iodine Ci 1.10E-04 9.09E-04 8.65E-05 1.46E-04 *

2. Average release rate for 1.42E-05 1.16E-04 1.09E-05 1.84E-05 1.54E+01 period µCi/sec

3. Percent of annual avg EC % 4.31E-06 7.24E-05 7.79E-06 4.52E-06

c. PARTICULATES

1. Particulates with half-life 1.52E-05 7.64E-05 6.54E-05 4.62E-05

> 8 days Ci

2. Average release rate for 1.96E-06 9.73E-06 8.23E-06 5.81E-06 period µCi/sec

3. Percent of annual avg EC % 2.73E-05 1.13E-04 1.81E-04 1.35E-04 N/A

4. Gross alpha radioactivity Ci 7.65E-06 1.97E-05 2.29E-05 1.77E-05 D. TRITIUM

1. Total Release Ci 1.SSE+OO 2.0SE+OO 3.26E+OO 1 .63E+OO

2. Average release rate for 1. 99E-01 2.61E-01 4.10E-01 2.0SE-01 period µCi/sec

3. Percent of annual avg EC % 2.84E-04 3.73E-04 5.86E-04 2.93E-04 E.

1. Beta Airdose at Site 2.51E-06 1. 73E-03 1.16E-04 2.75E-03 Boundary Due to Noble Gases (ODCM App A 111.C) mrads

2. Percent limit % 2.51E-05 1. 73E-02 1.16E-03 2.75E-02

3. Ga111Tia Airdose at Site 4.28E-07 4.82E-04 1.11E-06 9.25E-04 Boundary Due to Noble Gases (ODCM App A 111.C) mrads

4. Percent limit % 8.56E-06 9.64E-03 2.22E-05 1.85E-02 F.

1. Maximum Organ Dose to 4.94E-03 1.23E-02 2.18E-02 1.SBE-02 Public Based on Critical Receptors (ODCM App A 111.D) mrem

2. Percent of limit % 6.59E-02 1.64E-01 2.91E-01 2.11E-01 Data is reported for I-131 and 1-1~~ only.

TABLE HP 10.5-2

PALISADES PLANT RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS January l, 1993 to December 31, 1993

1. FISSION GASES Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Argon-41 Ci 2.09E-06 <LLD <LLD <LLD Krypton-85 Ci l.52E-02 4.37E+OO 1. 34E+OO l.26E-02 Krypton-85m Ci <LLD <LLD <LLD <LLD Krypton-87 Ci <LLD <LLD <LLD 2.87E-04 Krypton-88 Ci <LLD <LLD <LLD <LLD Xenon-13lm Ci <LLD 2.16E-Ol 2.92E-03 <LLD Xenon-133 Ci 2.50E-02 2.70E+Ol 4.19E-03 5.90E+Ol Xenon-133m Ci <LLD 2.78E-Ol <LLD <LLD

Xenon-135 Xenon-135m Xenon-138 Ci Ci Ci 2.84E-04

<LLD

<LLD 5.84E-Ol 2.lOE-04

<LLD

<LLD 5.45E-04

1. 74E-03

<LLD Total for Period Ci 4.05E-02 3.24E+Ol l.35E+OO 5.90E+Ol

2. IODINES Iodine-131 Ci 3.12E-05 7.68E-04 8.65E-05 2.62E-05 Iodine-132 Ci <LLD 4.42E-04 <LLD <LLD Iodi ne-133 Ci 7.92E-05 l.41E-04 <LLD l.20E-04 Iodine-134 Ci <LLD <LLD <LLD <LLD Iodi ne-135 Ci <LLD <LLD <LLD <LLD Total for.Period Ci l.lOE-04 l.35E-03 8.65E-05 1.46E-04

TABLE HP 10.5-2

3. PARTICULATES*

PALISADES PLANT RADIOACTIVE EFFLUENT REPORT Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Manganese-54 Ci <LLD <LLD <LLD <LLD Cobalt-58 Ci <LLD l.71E-05 1. 05E-06 <LLD Iron-59 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci <LLD 1.36E-05 8.51E-07 <LLD Zinc-65 Ci <LLD <LLD <LLD <LLD Strontium-89 Ci 5.65E-06 5.05E-07 3.51E-06 l.19E-06 Strontium-90 Ci . 2.0lE-06 l.53E-06 3.50E-07 3.20E-07 Molybdenum-99 Ci <LLD <LLD <LLD <LLD Cesium-134 Ci <LLD <LLD <LLD <LLD Cesium-137 Ci 8.40E-07 9.97E-06 <LLD <LLD

Cerium-141 Cerium-144 Chromium-51 Ci Ci Ci I

<LLD

<LLD 7.98E-09

<LLD

- Cesium-138 Ci 5.17E-09 <LLD <LLD <LLD

- Rubidium-88 Ci l.68E-07 <LLD <LLD <LLD Net unidentified beta Ci 6.74E-06 3.37E-05 5.96E-05 4.47E-05 Total l.52E-05 7.64E-05 6.54E-05 4.62E-05

Particulates with half-lives > 8 days.

- Particulates with half-lives< 8 days; not reflected in overall isotopic totals.

ATTACHMENT 3

Consumers Power Company Pa 1i sades Pl ant RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS - SUMMATION OF RELEASES January - December 1993 March 31, 1994

2 Pages

TABLE HP 10.5-3

PALISADES PLANT RADIOACTIVE EFFLUENT REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES January l, 1993 to December 31, 1993 A. FISSION AND ACTIVATION Est Total PRODUCTS Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Error %

1. Total release (not 9.39E-04 1.12E-03 6.0SE-03 5.93E-03 including tritium, gases, alpha) Ci

2. Average release rate for 3.83E-11 5. 14E-11 4.55E*10 2.91E*10 1.08E+01 period µCi/ml.

3. Percent of EC % 3.06E-03 4.27E-03 1.56E-02 1.21E-02 B. TRITIUM

1. Total Release Ci 4.07E+01 1.06E+02 5.26E+01 1.12E+01

2. Average diluted 1.66E-06 4.86E*06 3.95E-06 5.49E-07 4.00E+OO concentration during period µcitml.

3. Percent of EC % 1.66E-01 4.86E-01 3.95E-01 5.49E-02

c. DISSOLVED AND ENTRAINED GASES

1. Total Release Ci <LLD 4.39E-04 <LLD <LLD

2. Average di luted - 2.01E-11 - - 1.22E+01 concentration during period µCi/ml.

3. Percent of EC % - 1.01E-05 - -

D. GROSS ALPHA RADIOACTIVITY 2.19E-07 6.69E-07 3.20E-06 6.18E-07 (Total Release) Ci E. VOLUME OF \IASTE RELEASED 1.99E+05 5.45E+OS 3.52E+05 1.93E+05 (Prior to Dilution) Liters F. VOLUME OF DILUTION YATER 2.45E+10 2. 18E+10 1.33E+10 2.04E+10 USED DURING PERIOD Liters G. MAXIMUM DOSE COMMITMENT - 1.31E-03 2.09E-03 5.43E-03 5.54E-03

\IHOLEBODY mrem Percent of ODCM App A 111.H 8. 73E-02 1.39E-01 3.62E-01 3.69E-01 limit %

H. MAXIMUM DOSE COMMITMENT - 2.17E-03 3.28E-03 8.41E-03 9.20E-03 ORGAN mrem Percent of ODCM App A 111.H % 4.34E-02 6.56E-02 1.68E-01 1.84E-01 limit

TABLE HP 10.5-3

PALISADES PLANT RADIOACTIVE EFFLUENT REPORT LIQUID EFFLUENTS January l, 1993 to December 31, 1993

1. NUCLIDES RELEASED Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Manganese-54 Ci <LLD <LLD <LLD <LLD Cobalt-58 Ci 6. lSE-05 <LLD 4.22E-03 3.40E-03 Iron-59 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci 2.66E-04 2.51E-04 3.80E-04 4.59E-04 Zinc-65 Ci <LLD <LLD <LLD <LLD Strontium-89 Ci 3.98E-07 l.18E-06 8.61E-07 3.86E-07 Strontium-90 Ci 3.38E-06 5.89E-06 2.03E-06 2.32E-07

Molybdenum-99 Iodi ne-131 Cesium-134 Ci Ci Ci

<LLD

<LLD l.92E-05 6.20E-05

<LLD

<LLD l.57E-04 Cesium-137 Ci 5.62E-04 7.20E-04 l. llE-03 l.87E-03 Ceri um-141 Ci <LLD <LLD <LLD <LLD Cerium-144 Ci <LLD <LLD <LLD <LLD Antimony-125 Ci <LLD 7.89E-05 <LLD <LLD Xenon-133 Ci <LLD 4.39E-04 <LLD <LLD Ci Ci Net unidentified beta Ci 4.54E-05 4.62E-05 2.76E-04 4.64E-05 Fission &Activation Product Total Ci 9.39E-04 l.12E-03 6.05E-03 5.93E-03 Tritium Ci 4.07E+Ol 1. 06E+02 5.26E+Ol l.12E+Ol Grand Total Ci 4.07E+Ol 1. 06E+02 5.26E+Ol l. l 2E+Ol

ATTACHMENT 4

Consumers Power Company Palisades Plant RADIOACTIVE EFFLUENT RELEASE REPORT SOLID WASTE January - December 1993 March 31, 1994

1 Page

TABLE HP 10.5-4

PALISADES PLANT RADIOACTIVE EFFLUENT REPORT SOLID WASTE January l, 1993 to December 31, 1993 Waste Source of Solidification Container Volume *Total *Principal Cl ass --=Wa=s"'"""'t""'e_ _ Agent Type (cu ft) Curies Radionuclides Note: No solid radwaste shipments from January l, 1993 to December 31, 1993 .

*NOTE: Gamma isotopes are measured quantities; all other isotopes are estimated.

ATTACHMENT 5

Consumers Power Company Palisades Plant RADIOACTIVE EFFLUENT RELEASE REPORT LOWER LIMITS OF DETECTION FOR PALISADES EFFLUENTS January ~ December 1993 March 31, 1994

1 Page

LOWER LIMITS OF DETECTION (LLDs) FOR PALISADES EFFLUENTS Gaseous Effluents Nuclide LLD (µCi/cc)*

Cr-51 l.62E-09 Mn-54 3.72E-10 Co-58 6.29E-10 Waste Gas Decay Tank Co-60 7.03E-10 Batch 93-039-G Fe-59 8.73E-10 and 93-040-G. Zn-65 7.04E-10 Se-75 2.64E-10 Cs-134 3.0lE-10 Cs-137 3.30E-10 Zr-95 5.97E-10 Sb-125 6.97E-10 Nb-95 6.62E-10

Liquid Effluents Nuclide LLD (µCi/cc)**

Co-58 l.47E-07 Mn-54 9.48E-08 Fe-59 l.31E-07 Zn-65 l.45E-07 Liquid Batch Release Co-60 l.62E-07 Number: 93-008-R, Cs-134 l.90E-07 93-017-R and Cs-137 l.55E-07 93-021-R. I-131 l.18E-07

From typical stack and/or Waste Gas Decay Tank release analysis.

- From typical liquid release analysi~

ATTACHMENT 6

Consumers Power Company Palisades Plant RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT OFFSITE DOSE CALCULATION MANUAL March 31, 1994

~i fj; .1 :Q PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 7 January l, 1993 RECa\le)

FEB 161993 ffiC - PAI.

Approved MRN IJ/~n~

RMC Administrator Date

~' *: . . '

/;2.-.J0-92..

9:J.-l lS 7 PRC Reviewed Date "

I\ I * * '\ ' ~ ' .! .

/ 1, \

P.AL12AQES NUCLEAFLEbAtll OFFSJTE DOSE CALCULATION MANUAL TITLE: OFFSITE DOSE CALCULATION MANUAL *..

i...

~~;'

-?*

~-M~!lo~ ~--11~3 Procedure Sponsor Date

Technical Reviewer Date User Reviewer Date Rev#

~./.k:...L_; /;{/, /r.:r Plant General Manager Date

.1::...

Rev1s1on 7 Table of Contents I. GASEOUS EFFLUEHJS . . .

A. ALARM/TRIP SETPOINT METHOD

1. Allowable Concentration 1

2. Monitor Resoonse . . . . 2 B. DOSE RATE CALCULATION . . . . . . , . . 3 C. DESl&N OBJECTiVt QUANTITY (DBQ) L!"ITS OH BATCH AND CONTINUOUS RELEASES . . . . . 16

l. Qatch Rel eases . . . . 16

2. Continuous Releases . 17

3. Exceeding DBQ L1m1ts . . . 17

4. Releasing Rad1onucl1des Not L1sted 1n Table 1.9 17 D. OPTIONAL QUARTERLY DOSE CALCULATIONS . 18

1. Methodology for Optional Quarterly QQ.se Calculations 18 E. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION . 20

1. System Description . . . . . . . . 20

2. Determination of Satisfactory Operation 21 F. RELEASE RATE FOR OFFSITE EC (50 mrem/yr) 21 G. PARTICULATE AND IODINE SAMPLING 22 H. NOBLE GAS SAMPLING . 22 I. TRITIUM SAMPLING . * . * . 22 \

J. FIGURES AND TABLES . . . . 22 l!

l I I. LIQUID EFFLUENJS

55 l,,

A. CONCENTRATION 55 t I

1. Requirements . . . * . * . . . .. . 55 2.

3.

Prerelease Analysis . . . . . . . . . . . . . .

Effluent Concentration CEC) - Sum of the Ratios 55 56 I

B. INSTRUMENT SETPOINTS . . . . 57 I

1. Setpo1nt Determination . . 57

2. Composite Samplers *

57

3. Post-Release Analysis 58 C. DOSE 58

' 1. REIS Requirement *

58

2. Release Ana1Ys1s 58

aovlslon 7 Table of Contents D. OPERABILITY OF LIQUID RAOWASTE EQUIPMENT 62 E. RELEASE RATE FOR OFFSITE EC (50 mRem/yr) s;:

F. FIGURES AND TABLES . 63 III. UBAHJUM FUEL CY~LE DOSE 84 A. SPECIFICATION . 84 B. ASSUMPTIONS 84 C. DOSE CALCULATIUH 84 IV. BADWASTE SYSTEM MODIFICATIONS GS A. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION 85

1. Puroou . . . . . . . . . . . . 85

2. Definition . . . . . . . . . . . 85

- Appendix A, "Relocated Technical Specification" Appendix B, "Request to Retain Soil in Accordance with 10CFR20.302"

., .* . ... . I

f'Al.UAtH.~ 1,11\:l.f f\I\ PLf\JH lJff ~I H QO~I Ci\Lf;VLM l Qi~ MMl\JAL

Huvision /

I. ~illQ!l~ __ tHJ..V.JJtl~

A. ALARM/TRIP SETPOINT METHOD Appendix A, Section 111.B.1 requires that the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

For noble gases: less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and For iodine-131, for iodine-133, for tritium, and for al I rad*tonuclides in part1c11late form with half lives greater than 8 days: Less than or equa I to 1500 mrems/yr to any organ.

Appendix A, Section 111.A.l requires gaseous effluent monitors to have alarm/trip setpoints to ensure that offsite concentrations, when averaged over l hour, will not be greater than Appendix A, Section Iil.B.l. This section of the ODCM describes the methodology that will be used to determine these setpoints.

The methodology for determining alarm/trip setpoints is dividEd into two major parts. The first consists of c~lculating an allowable concentration for the nuclide mixture to be released. The second consists of determining monitor response to th~s mixture in order to establish the physical settings on the moniturs.

1. Allowable Concentration The total EC-fraction (Rk) for each release point will be calculated by the relationship defined by Note 4 of Appendix B, 10 CFR 20:

Rlkl = ( ~) (F) }f

( 1.1) where:

Actual or measured concentration, at ambient temperature and pressure of nuclide i (µCi/cc)

The EC of nuclide i from 10 CFR 20, Appendix B, Table 2

50 mrem/yr - total body.

The total EC-fraction for release point k X/Q "' Most conservati¥e sector site boundary dispersion (l.40E-J6 sec/m)

F

Release flow rate (83,000 cfm

39.2 m3/sec) for stack monitor considerations; variable for other monitors .

1 Rev 7 01/01/93

HQ.I.E:

Ru v I s l on I If a batch release Is made wh\le a continuous release or another batch release is in progress, the surn of al I values of R* must be less than 10.0.

2. Hon1tor Respon~e Normal rad1oact1v1ty releases consist ma1nly of well-decayed fission gases. Therefore, monitor response calibrations are performed to fission gas typical of normal releases (mainly Xe-133). Response of monitors used to define fission product release rates under accident conditions may vary from that of Xe-133, however. Monitor response for the two categories of monitor 1s determined as follows:

a. Normal Release {aged fission gasses)

Total gas concentration (µCi/cc) at the monitor is calculated.

The calibration curve or constant for cpm/µCi/cc) is applied to determine cpm expected. The setting for monitor ~larms is established at some factor (b) greater than 1 but less than l/Rk (Equation 1.1) times the measured concentration (c):

s Cl b x c ( 1. 2)

b. Accident Releases Monitors are preset to alarm at or before precalculated offsite dose rates would be achieved under hypothetical accident conditions. These setpoints are established in accordance with Emergency Plan requirements for defining Emergency Act1~n Levels and associated actions. Emergency Implementing I Procedures contain monitor-specific curves or calibration [

constants for conversion between cpm and µCi/cc (or R/hr and

µCi/cc), depending on monitor typ~, for fission product mixtures as a function of mixture decay time.

I r

When these monitors are utilized for other than accident f i;

conditions, either an appropriately decayed "accident" t

conversion curve may be used, or a decayed fission gas 1*

I calibration factor may be applied. In these cases, setpoints t are established as in I.A above.

r Setpoints of accident monitors {if set to monitor normal releases) are reset to the accident alarm settings at the end t of normal release. Setpoints of other release monitors are rI maintained at the level used at the latest release (well below !

the level which would allow 10 times EC to be exceeded at the site btiund~y), or are reset to approximately three. tim9s

background in order to detect leakage or inadvertent releases of low level gases.

2 Rev 7 01/01/93

Rovls1on 7 B. DOSE RATE CALCULATION

l. Dose rates are calculated for (1) noble gases and (2) iodines and particulates. Dose rates as defined In this section are bas~d on 10 CFR 50 Appendix I llm1ts of mrem per quarter and mill ire~ per year. All dose pathways of major importance in the Palisades anvirons are considered.

a. Equations and assumptions for calculating doses f;om noble gases are as follows:

1) Assumptionli a) Doses to be calculated are the maximum offsite point in air, total body and skin.

b) Exposure pathway is submersion within a cloud of nobie gases.

c) Noble gas radionuclide mix is based on the histor*lcally observed source term given in Table 1.1, plus additional nuclides .

d) e)

f)

Basic radionuclide data are given in Table 1.2.

All releases are treated as ground-level.

Meteorological data expressed as joint-frequency distribution of wind speed, wind direction, ~nd atmospheric stability for the period resulting in X/Q's and D/Q's shown in Table 1.3.

g) Raw meteorological data consists of wind speed and direction measurements at lOm and temperature measurements at lOm and 60m.

h) Dose is to be evaluated at the offsite exposure points where maximum concentrations are expected to exist (overland sector site boundaries), and nearest residents.

i) Potential maximum population (resident) exposure points are identified in Table 1.4.

j) A semi-infinite cloud model is used.

k) fJr person exposures;* credit is taken for shielding by residence (factor of 0.7).

1) Radioactive decay is considered for the plume.

. 3".

Rev 7 01/01/93

,' */.,,.: .-~:

' . . ' :~'~. " ' .. .~ *. :)*?~ ~* .'*~

m)

Rev1slon 7 Building wake effects on effluent dispersion are cons1dered.

n) A sector-1vorage dispersion equation Is used.

o) The wind speed classes that are used are as foi~~~J:

Wind Speed Class Number Range (m/sl Midpoint (mis) l 0.0-0.4 0.2 2 0.4-1.5 0.95

,,,~ l.S-3.0 2.25 4 3.0~5.0 4.0 5 5.0-7.5 6.25 6 7.5-10.0 8.75 7 > 10.0 p) The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A"'l, 8=2, ... , G*7.

q) Terrain effects are not considered .

2) Eqyatio[Js To calculate the dose for any one of the exposure points, the following equations are used.

For determining the air concentration of any radionuclide:

x1 f:

)=1 t ( )l/'1. E k:::l 2

1t f j k 01 p zku j (2nx/n)

[ - (".1 exp .

x )]

uj (1.3) where:

.. Air concentration of radionuclide i, µCi/m 3 *

.. Joint relative frequency of occurrence of winds in wind speed class j, stability class k, blowing toward this exposure point, expressed as a fraction.

-... Average release rate of radionuclide i, µCi/s.

Fraction of radionuclide remaining in plume *

~

- Vertical dispersion coefficient for stab.11 ity cl ass k (m) .

4 Rev* 7.

.' '::.., ~--- . :. . . :. 01/01/93

l } ,.

PAUil:\t!.LS NIJ\; LUlli .PLf\Jff Qf.f_~Ut:.J29)£ .~ALCV.UHJQH_ MAliVJ\L

fh~vlslon l MI d po I n t v <1 1u e o f w i n d speed c I a ~ s i n t 1~ i-v ii 1 j ,

m/s.

x Downwind distance, m.

n

Number of sectors, 16.

.XI

Radioactive decay coefficient of radionuclide i, s.'.

2'1'X/n Sector width at point of interest, m.

.. L.- .. _ ... _,

1.llC 1.Ut.d I body dose rate:

( 1. 4) where:

Total body dose ratet mrem/y.

Air concentration of radionuclide i, µCi/m 3 *

0 11 c ~

Total body dose factor due to gamma radiation, mrem/y per µCi/m ("fable 1.5).

For determining the skin dose rate:

X1 (DFS 1 + 1.11 DFY 1 )

( 1. 5) where:

Skin dose rate, mre ."!l/Y.

Air concentration of radionuclide i, µCi/m 3 Skin dose factor due to beta radiation, mrem/y ;:

per µCi/m 3 (Table 1.5). r The average ratio of tissue to air energy

[

1.11

I r

absorption coefficients, mrem/mrad. ?*

l.

i DFY 1

GalTITia-to-air dosr factor for radionuclide i, I L.

mrad/y per µCi/m (Table 1.-5) .

(:

t i

1I I

5 Rev 7. I,.

01/01/93 I I

.~ ...

l i*

lf llovls1on J For determining dose rate to a µoint in Clir:

i D. "' ~ X 1 (DFY 1 or DFB!)

I where:

( 1 . 6)

I Air dose rate, mrad/yr I Air dose factor for beta radiation (Table 1.5}.

l b. Equations and assumptions for calculating doses from radioiodines and partic~late$ ~r~ as fo11cw$:

I} Assumot 1on~

a) Dose is to be calculated for the critical organ, thyroid, and the critical age groups (adult, teen, child, infant), infant (milk} and child (green, leafy vegetables).

b) Exposure pathways from iodines and particulates are milk ingestion, ground contamir.ation, green leafy vegetables from home gardens, and inhalation.

c) The radioiodine and particu~ate mix is based on the historically observed source term given in Table 1.1.

d) Basic radionuclide data are given in Table 1.2.

l e) All releases are treated as ground-level.

f) Mean annual average X/Q's are given in Table 1.3.

g) Raw meteorological data for ground-level releases consist of wind speed and direction measurements at 1.:! . .. lOm and temperature measurements at lOm and 60m .

h) Dose is to be evaluated at the potential offsite exposure points where maximum doses to man are expected to exist.

i) Real cow, goat and garden locations are considered.

j) Potential maximum exposure points (Table 1.4) considered are the nearest cow, goat and home garden locations in each sector.

k) Terrain effects and open terrain recirculation factors are not considered.

6 Rev 7

. 01/01/93

t ~ .t Rovislon 7 l) Building wake effects on effluent dispersion are cons ldered.

m) Plume depletion and radioactive decay are considered for air-concentration calculations.

n) . Radioactive decay is considered for ground-concentration calculations.

o) Deposition is calculated based on the curves given in Figure 1. 2.

p} ~~1k co"s and goats obiain 10~ of their food from pasture grass May through October of each year. Use default values of 0.58 for cows and 0.67 for goats for fraction of year on pasture.

q) Credit is taken for shielding by res~dence (factor of O. 7).

2) Eqyat 1ons To calculate the dose for any one of the potential maximum-expo~ure points, the following equations in Section 1.2.2 are used.

a) Inhalation Equation for calculating air concentration, X1 is the same as in the Noble Gas Section (Equation 1.3).

For determining the organ dose rate:

{l. 7) where:

= Organ dose rate due to inhalation, mrem/y.

= Air cincentration of radionuclide i,

µCi/m .

Inhalation dose factor, mrem/pCi (Table 1. 7).

.BR*

Breathing rate 1~00 m3/y infant; 3700 rn3/y child; or 8000 m/y teen and adult.

lxl06 .. pCi/µCi conversion factor.

7 Rev 7 01/01/93

t J Rev1s1on 7 b) .W:.Q.\l nd Con t am irfiliQD For datermlntng the ground concentration of any nuclide; 7

Gi "' 3. 15 x 10 7 L

k:::il

( 1. 8) where:

- Ground concentration of radionuclide t,

µCi/m.:.

k Stability class.

Joint relative frequency of occurrence of winds in stability class ~blowing toward this exposure point, expressed as a fraction.

- Average release rate of radionuclide i,

µCi/s.

DR Relative deposition rate, m* 1 (Fig 1.2~.

x n

- Downwind distance, m.

Number of sectors, 16.

Sector width at point of interest, m.

Radioacti~a decay coefficient of radionuclide i, y* 1 *

- Time for buildup of radionuclides on the ground, 15 y.

3.15xl07 .. s/y conversion factor .

8 Rev 7 01/01/93

P!~Ll ~A.Q(j HIJCLlAH J>t!'.N r WT:'ilH I.l<2$( (:_AL(.'.llU\J jl)ij ~11\HUAl Rcvi$lon 1 Co1 roCHl(j J*nu,.ry 1 'n I

.*1 I ' ,/ 1--

,--1

) 1--

~---,

. j

1 I I

' : ' ' '1 I' '

l '

I I'I f

~

U. !:I

-a:

UJ 1o-4 I I 11 T -~

i

~

LW

j "- '

I a: ... '

w 2:

UJ

~

c(

a:

"" 1',.

~

~,,__

I '

I

~~

! 1o-6 I t:: ~

~

I ...... I

~

Q UJ

~,

i I I

c(

...J ' ~hi.. l

~ill.

i LU cc I 1<>-8 I

I I

I !:

1I 1 I: I ii I' 10-7 I 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

Figure 7. Aelltiwe Deposltloft for Ground Level Rel.... (AJI Atmo1J>Mric:

SnbUity CS.-I n- ** r 9 Rev 7 01/01/93

p_~JJ 5ADf5. NlJGUJ\Jl. !'Ll\NT QfUlJI .P05f~ ~.\L.t;VU\f lOH MNNAL Ruvis1or; I For determining the total body or* or<Jdll dw.t~ 1*,1te from ground contamlnat1on:

D0 "' ( 8, 7 6 0) ( 1 X 10 6 ) ( 0 .7)

( '.. 9) where:

Dose rate due to ground contamination, mrem/y.

Grounrl concentration of radionuclide i,

,,r"I /,_1 P"' Ill

Dose factor for standing on contaminated ground, mrem/h per pCi/m2 (Table l.Sj.

8,760 .. Occupation time, h/y.

lxl0 6 pCi/µCi conversion factor.

o. 7 ::l Shielding factor accounting for a distance of 1.0 meter above o~dinary ground, dimensionless.

c) Milk and V~gctat1on Ingestion For determining the concentration of any nuclide (except C-14 and H-3) in and on vegetation:

CV ~

3,600 .l.J ft 0 1 DR (r[l-exp (->. 111 t.ll + B1,,[ 1-exp p}. (-.\1tb)J ) (Cexp-(.\1tbll) 1 k*l (2*x/n) 'iv x.1 1 (1.10) where:

cv, Cl Concentration of radionuclide in and on vegetat1Dn, µCi/kg.

1~1 J~

.;~

k .. Stability class w

)

',\i

, fk .. Frequency of this stability class and wind direction combination, expressed as a

.'ft

&,, fraction.

}~ ..

QI

Average release rate of radionuclide i,

µCi/s.

DR

Relative deposition rate, m* 1 (Figure 1.2).

x . Downwind distance, m.

10 Rev 7 01/01/93

rAU)AQfS_ WKlEAR J~LP..lff Qff~lH: DQ5L C1\LCVLATlQl"UiAJtl.1AL Revision l n Number of sectors, 16.

2u/n Sector width at point of interest, m.

r Q Fraction of deposited activity re:~lned r;n vegetation (l.0 for iodines, 0.2 for particulates) .

.XEi Effective removal rate constant,

.XEi ~ A1 + ).w' where ).1 1 is the radioactive decay coefficient, h' , and ).~ is a measure of physical loss by weathering

(.Xw ... 0021 h").

te Period over which deposition occurs, 720 h.

Yv Agricultural yield, 0.7 kg/m 2

B;v Transfer factor from soil to vegetation of radionuclide i (Table 1.6).

.x, Radioactive decay coefficient of radionuclide i, h" 1 tb .. Time for ~uildu~ of radionuc1ides on the ground, l.3lxl0 h (15Y).

p

Effectivr surface density of soil, 240 kg/m .

3,600 "' s/h conversion factor.

th "' Holdup time Jetween harvest and consumption of food (2,160 hours0.00185 days 0.0444 hours 2.645503e-4 weeks 6.088e-5 months for stored food)

For determining the concentration of C-14 in vegetation:

CV14 = 1X10 3 X 14 (0.11/0.16)

{l.11) where:

cv,, "' Concentration of C-14 in vegetation,

µCi/kg.

,;',* Air concentration of C-14, µCi/m 3

0.11

Fraction of total plant mass that is natural carbon.

'* '~* :.. ; . ' : - Rev 7 01/01/93

-.:i..: .* * .';": .

. '. ~~}. :. '

f i¥¥ * *** AA fiWW;_

0 .16 r~ev Is I on 7 Concentration of natural atmosphere, g/m .

Cl rtrnn i fl lhe lxl0 3 . g/kg convers1on factor .

For determ1ning the concentration of H-3 in vegetation:

CVT = 1 x 10 x-r (0.75) (0.5/H) 3 (l.12) where:

ru

..,.T ;;;; Concsntr-at1mi of H-3 in vegetation, µCi/mJ.

3 Xy Air concentration of H-3, µCi/m .

0.75 Fraction of total plant mass that is water.

0.5 Ratio of tritium concentration in plant water to tritium concentration in atmospheric water.

3 H* Absolute humidity of the atmosphere, g/m

g/kg conversion factor.

For determining the concentration of any nuclide in cow's or goat's milk:

(1.13) where:

Concentration of radionuclide i (including C-14 and H-3} in milk, µCi/2.

Concentration of radionuclide i in and on vegetation, µCi/kg.

Transfer factor from feed to milk for radionuclide i, d/l (Table 1.6}.

Amount of feed consumed by the milk animal per day, kg/d (cow, 50 kg/d or goat 6 kg/d}.

Radioactive decay 1coefficient of

., ' ' >" radionuclide i, d"

Transport time of activity from feed to milk.to receptor, 2 days .

12 Rev 7

1

.1* '. .*, '.

1'**

01/01/93

} . * .. \ *. .

" ~

l{e v 1 s l on l For determining the orgar. dose rate fr-om ingestion of green leafy vegetables and milk:

D "' l x 10 6 ~1 CM 1 DF' 1 UM

~I . 14 j where:

D "' Organ dose rate due to ingestion, mrem/y.

Concentration of radionuclide i in vegetables or milk, µCi/kg (or liters).

OF t :~ Ingestion dose factor, mrem/pCi (Table 2.1).

UM Ingestion rate for milk, 330 l/y; for vegetables 26 kg/yr (child), no ingestion by infant.

6 lxl0 pCi/µCi conversion factor.

d) Meat Ingestion (Beefl

To calculate the concentration of a nuclide in animal flesh:

cf, "'

where:

Fft CV, Qn exp (.X 1ts) (1.15)

Concentration of nuclide i in the animal flesh, pC ij:~g.

Fraction of animal's daily intake which appears in each kg of flesh, days/kg (Table 1.6}.

Concentration of radionuclide i in the animal's feed (Equation I.IO}.

Amount of feed consumed by the cow per day, 50 kg/d.

Average time from slaughter to consumption, 20 days.

.13 Rev 7

'.)_ . 01/01/93 '

..* - ~. .'

lJ

!hivlslon 7 To l1etermine thl!

D t =- [

or~ian do~;e Cn Dr1 Ur from ingestion of beef:

l (1.16) where:

Ingestion dose factor for age group, mrem/pC1 (Table 2.1) for nuclide i.

u, Ingestion rate of meat for age group, kg/y (child-41, teen-65, adult-110).

e) Organ Duse Rates For determining the total body and organ dose rate from iodines and particulates:

D .. o, + DG + DH + Dv + of (1.17) where:

D Total organ dose rate, mrem/y.

o.

DG OM Dose rat~ due to inhalation, mrem/y.

Dose rate due to ground contamination, mrem/y.

Dose rate due to milk ingestion, mrem/y.

Dv Dose rate due to vegetable ingestion, mrem/y.

DF = Dose rate due to beef ingestion, mrem/y.

3) The maximum organ dose rate, maximum total body dose rate, and maximum skin dose rate calculated in the previous section (Sec I.B) are used to calculate design basis quantities as described in Section I.B.1.3.

14

Rev 7 01/01/93

Pl1U~.ADIS. HVt:LLf\R \'LAH!

Off ~!J[ QQ){_CA.lt;lJlM ! OH Ht'\NUA1.

lhwi s ion J c.

The design basis quantity of a radionucl id1~ emitted to the atmosphere is the amount of that nuclide, when released in on1~

year, which would result in a dose not exceedJng any of the following:

1) 15 millirem to any organ of an individual from iodines and particulates wtth half-life greater than 8 days (Appendix A, Section 111.D.l}.

2). 15 milltrem to skin of an individual from noble gas (Appendix A.Section III.C.l.b).

3) 5 mtllirem to the total body of~~ ~~dividual from noble gas (Appendix A, Section 111.C.l.a).

Design basis quantity (Ci) is the smallest value for each nuclide, calculated by dividing the dose limits (a through c above) by the appropriate dose calculated from the amount of radionuclide (Ci) used to conservatively estimate the doses of Section D, as listed in Table 1.1 (or a hypothetical 1 Ct/year); the result is then multiplied by the amount of

radionuclide used.

DBQ =

where:

DAI DC (Cc)

(1.18)

Appendix I dose limit (mrem or mrad).

Calculated dose (mrem Jr mrad).

Quantity of nuclide resulting in dose Dc (Ci).

DBQ

Design Basis Quantity (Ci).

1.

The limiting values for Design Basis Quantities for radionuclides released to the atmosphere are given in I Table 1.9.

r:

The inverse of the ratio C../Dc in the above equation (ie, DclCc) I I

is a useful value, since it represents the most limiting dose ~*

per unit quantity of each nuclide released. Use of the D/Cc ratio in Quarterly evaluation of offsite dose is discusse~ in f

[.

Section 0. Values of De/Cc are given.in Table 1.9. I*

I r:

iI 15 Rev 7 01/01/93 I[

J.

Aµp1!ndix A, Sections J.3.b and J.3.c ciescr*itJe the n!qu1n~rrn~nts

~ fur an annua 1 1and use census and revision of the ODC~; for use in the following calendar year. Areas of the ODCM 1-1n di will be reviewed, and changed if appropriate, are Table l.t1 ~L;l:,d Use Census data by Sector), Table l.4a (Critical Receptors),

and Table 1.9 (Gaseous Design Basis Objective Annual Quantities). Changes will be effective on January l of the year following the year of tho survey.

e. Gaseous Releases From the Stqam -~rator B1owdowo Vent and Atmosphere Re)r:~1e vaives Releases from the steam generator blowdown vent and atmospheric relief valves are difficult to quantify as there are no sampling capabilities on these steam release systems. however, neither system is a normal release path. The ~team generator blowdown vent is normally routed to the main condenser and recirculated. Radioactive releases will be calculated by analyzing steam geherator blowdown liquid and assuming that 100

..*.,< percent of Noble Gases, 10 percent of the Iodines and 1 percent of the Pnrticulates will be released to the environment in the steam phase. Volumes will be 1*cleased to the environment 1n the steam phase. Volumes will be calculated using water balances or alternate means as available.

C. DESIGN OBJECTIVE QUANTITY {DBQ) LIMITS ON BATCH AND CONTINUOUS RELEASES

1. Batch Releases Prior to each batch release (waste decay tank release or Containment purge), the quantity of each nuclid~ identified is summed with the quantity of that nuclide released since the first of the current calendar year. The cumulative total for each nuclide then is divided by the design objective quantity for each nuclide (from Table 1.9), and the resultant fractions are summed in order to assure that the sum fraction of all nuclides does not exceed 1.0:

Ai < 1. 0 (DBQ) 1 (1.19}

The amount in any calendar quarter should not exceed 0.5. This is checked by subtracting the value obtained at the end of the previous quarter from the value obtained from the cumulative total to date, including the batch to be released.

16 Rev 7 01/01/93

~ I

!' f\.11 ~AQ L'i.. mK LEAR J' LANI QfDH.LQQH.. G.AlP.JLAf tQN M/\J1\JAt Rovhlon 7 2.

Low level continuous releases from the vent gas collection header and other low level sources are totaled on a weekly basis and sumned with any batch releases for the week In order to esti\bl ish '.he cumulative DBQ fraction from batch plus continuous releasec.1 '.or the year-to-date. Calculations are performed tn the same manner as for batch releases described in C.l.

3. Exceeding DBO L1m1ts As discussed under B.l.3, the DBQ is a very conservative estimate of activity which ccu1d give doses at A~pendix I limits. Because different organs are :;ummed together and doses to different people are summed, the DBQ typically overestimates dose by about a factor of five. Thus, if calculations of DBQ fraction exceed 1.0 for year-to-date or 0.5 for the quarter, technical specifications probably still would not be exceeded. However, further discretionary releases should be deferred until an a~curate assessment of dose is made by use of GASPAR computer code or by analysis of appropriate release data via the segment gaussian dose model used in emergency planning (inhalation dose, total body external dose, and boundary dose in air). See also Section D.1.2 .

It should be noted that Palisades PlJnt to date (based on review of semiannual effluent data) has never exceeded the annual or quarterly DBQ fraction, despite its conservati~m. 1*hus, it is not expected that an alternate to the DBQ method will be required unless the plant is in a significantly off-normal condition.

4. Releasing Radionucl1des Not listed in Table 1.9 Table 1.9 contains all nuclides identified to date as routine constituents of gaseous releases at Palisades Plant, plus those common to PWRs in general, even if not previously detected at Palisades. From time to time, however, other nuclides may be detected.

If the unlisted nuclide constitutes less than 10% of the EC-fraction for the release, and all unlisted nuclides total less than 25% of the EC-fraction, the nuclide may be considered not present.

If the unlisted nuclide constitutes greater than 10% of the EC-fraction, or all unlisted nuclides together constitute greater than 25%, then each nuclide should be assigned a DBQ equal to the most conservative value listed for the physical form of the nuclide involved (noble gas, halogen or particulate).

Should a nuclide not listed in Table 1.9 begin to appear in significant quantities on a routine basis, revision to this ODCM should be made in order to include a design basis quantity specific to that nuclide .

17 Rev 7 01/01/93

l I ) ' :.

Revision I

--'"'-----~*----

0. OPTIONAL QUARTERLY DOSE CALCULATIONS I. tl!'t.tll..QQQl.Qgy for Opt1onal Quarterly Pose Ca]culatiom.

This option may be used in place of, or in addition to, th~ Design Basis Quantity (DBQ) fraction calculation described by Equation 1.19. This optional conservative calculation relates the DBQ fraction to the doses from which it was originally derived. Use of this method may assist in identification of the critical dose pathway or characteristics of the assumed critical individual (infant, child, teen and adult), since Table l.S indicates these parameters.

a. Simplified Conservative Approach This method utilizes a limiting dose concept such that the limiting dose for each nuclide is summed with the limiting dose for each other nuclide, regardless if such sum is physically possible. It also assumes critical pathways, such as milk and vegetables, are in effect even in winter when the pathway is absent.

As such, the method is highly conservative and significantly

over-estimates dos~. If limits appear to be exceeded by this method, Section D.1.2 (a concise method, but requiring comp~ter support) will be utilized.

I. Assumptions a) All assumptions of Section I.I are utilized.

b) Limiting doses for each gaseous nuclide are summed, regardless of limitin~ decay mode {gamma or beta}.

c} Limiting doses for each particulate and iodine nuclide are summed, regardless of dose point location, exposure pathway or organ affected.

d) Doses are summed for detected nuclides such that all nucl1des which contribute greater than 10%

individually or 253 in aggregate, to the EC of released radioactivity, are included in the dose calculation.

*!':1.

(1 __

]--

' 18 *Rev* 7 01/01/93

r'_l\U:i0ll£5 W1CLIAR P!N~!

Qff SllI QQ$C __ ~A!.Sl1U\TJQ!'l MN~lJAL Hov1slon I For determining gaseous effluent dose:

i D0 "" L AiG(Dc/Cc) 10

< 5 millirad/qua.rter, l 1 mrad/

0 (I. 20) where:

'1.,.

DG

Dose from gaseous effluents (mrad).

011ant1ty cf gaseous nucl1de i reieased (Ci).

..i Cl

' Dose per Ci factor for gaseous nuclide (mrad/Ci).

The limit for this mixture is conservatively taken as that for gamma exposure (5 mrem/quarter, 10 mrem/year) although as indicated in Table 1.9, a majority of the gaseous effluents are beta-limiting and on an individual basis have the higher limit of 10 millirem/quarter and 20 millirem/year.

For determining tritium, particulate and iodine dose to organs:

i DTPI =L ATPii (Dc/Cc)TPii < 7. 5 mrem/q, 15 mrem/y (1.21) where:

Dose from particulates and iodines (mrem).

Quantity of particulate or iodine nuclide i released (Ci).

Dose per Ci factor for particulate or iodine nuclide i (mrad/Ci).

19 Rev 7 01/01/93

Revls\011 7 This methodology is to be used if the highly conservative calculations described in C.l or D.l yield values that appear to exceed applicable limits.

Doses for released particulates, iodines and noble gases wtll be determined by use of the NRC GASPAR computer code. fhe co~puter run will utilize the annual average joint frequency meteorological data based on not less than 3 years of meteorological measurement, and will reflect dew.ographic and land use information from the land ijSe survey generated in the most recent prior year. Where appropriate, seasonal adjustments wil I be applied to obtain realistic dose estimates since both recreational and agricultural activities can vary greatly in relation to season of the year.

An alternative to GASPAR for offsite dose calculation is the use of the Palisades Segmented Gaussian Plume Emergency offsite dose calculation program. This dose model allows evaluation of dose under the actual meteorological conditions present at the time of release. It is anticipated that the system may be used .

in major short-term releases such as Containment purges are to be made under conditions which depart sign*ificantly from mean annual conditions.

E. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION The gaseous radwaste treatment system (GRTS) described below shall be maintained and operated to keep releases ALARA.

1. System Description A flow diagram for the GRTS is given in Figure 1-1. The system consists of three waste-gas compressor packages, six gas decay tanks, and the associated piping, valves, and instrumentation.

Gaseous wastes are received from the following: degassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown, displacing of cover gases caused by liquid accumulation in the tanks connected to the vent header, and boron recycle process operation.

Design of the system precludes hydrogen explosion by means of ignition source elimination (diaphragm valves, low flow diaphragm cnmpressors and system electrical grounding), and minimization of leakage outside the system. Explosive mixtures of hydrogen and oxygen have been demonstrated compatible with the system by' operational experience over the past 13 years.

20 Rev 7 01/01/93

PAU ~AOVi Nll~U.Afl PLAN r Q!TS l rt PQS[ ~AL,Cl.JLAT l QN H_l\Nt.J/1L 2.

Design basis quantity fraction wil 1 be calcu:ated for batch and continuous releases as described in Section J.C. lhese calct1lations will be used to ensure that the GRTS is operating as designe.f.

Because the plant was designed to collect and hold for decay ~ va~t majority of the high level gases generated within the primary system, and because the 13-year operating history (to date of writing the initial OOCM) of the plant has demonstrated the system's consistent performance well below Appendix I limits, no additional operability requirements are specified.

F. RELEASE RATE FOR OFFSITE EC (50 mremiyrj 10 CFR 20.1302 requires radioactive effluent releases to unrestricted areas be in concentrations less than the limits specified in Appendix B, Table 2 when averaged over a period not to exceed one year. (Note:

there are no unrestricted areas anywhere within the site houndary as defined by Figure 1-1.) Concentrations at this level if present for one year will result in a dose of 50 mrem wholebody. 10 CFR 50.36a requires that the release of radioactive materials be kept as low as reasonably achievable. However, the section further states that the licensee is permitted the flexibility of operation, lo assure a dependable source of power even under unusual operating condit:ons, to release quantities of material higher than a small percentage of 10 CFR 20.I302 limits but still within those limits. Appendix I to 10 C~R 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as reasonably achievable requirement.

The GASPAR code has been run to determine the dose due to external radiation and inhalation. The source term used is listed in Table I.I.

The meteorology data is given in Table 1.3. Dose using annual average meteorology, to the most limiting organ cf the person assume to be residing at the site boundary with highest X/Q, is 2.lSE-02 mrem (for one year). The release rate which would result in a dose rate equivalent to 50 mrem/year (using the more conservative total body limit) is the curies/year given in Table 1.1 multiplied by 50/2.lSE-02 or 0.11 Ci/sec .

21 Rev 7 01/01/93

!'A.U?.AJ)[) W.JUEM~ P~J\!H Qff~JT[ DQ2L ~!\L~ULAHQN M/\f-:t.J1\L Hevlslon 7 G. PARTICULATE AND IODINE SAMPLING Particulate an 1od1ne samples .u-e obtalned from the continuous sample stream pulled from the plant stack. Samples typically are obtai~ed to represent an Integrated release from a gas batch (waste gas deca.* tank or Containment purge, for example), or a series of samples are obtai~ed to follow the course of a release. In any event, sample intervals are weekly, at a minimum.

Because HEPA filters are present between most source inputs to the stack and the sample point, releases of particulates normally are signlficantly less than pre-release calculations indicate. This provides for conser~atism in estabiishing setpoints and in estimation of pre-reiease design basis quantity fr~ction. However, for the sake of maintaining accurate release totals, monitor results (for gases) and sample results (for particulates and iodines) utilized rather than the pre-release estimates, for cumulative records.

Gamma analytical results for particulate and halogen filters are combined for determination of total activity of particulates and halogens released. Beta and alpha counting also is performed on the particulate filters. Beta yields of the gamma isotopes detected on particulate filters are applied to determine "identHied" beta, an the "identified" count rate is subtracted from the observed count rate to give

~,.

"unidentified" beta. The "unidentified" beta is assumed to be Sr-90 until results on actual Sr-90 (chemically separat~d from a quarterly composite of filters) are obtained. Sampling and analysis will be performed per Appendix A, Table B-1 requiremants.

H. NOBLE GAS SAMPLING Noble gases will be sampled from Waste Gas Decay Tanks prior to release and the Containment prior to purging. A~alysis of these samples will be

.:.! used for accountability of noble gases. Off gas will be sampled at least i* weekly and used to calculate monthly noble gas releases. Nonroutine releases will be quantified from the stack noble gas monitor (RE 2326) which has a LLD of IE-06 µCi/cc. Sampling and analysis will be performed per Appendix A, Table B-1 requirements.

- 1*. ; '

I. TRITIUM SAMPLING Tritium has a* low dose consequence to the public because of low

! production rates. The major contributors to tritium effluents are evaporation from the fuel pool and reactor cavity (when flooded).

Because of the low dose impact, gaseous tritium sampling will not be required. Tritium effluents will be estimated using conservative evaporation rate calculations from the fuel pool and r*eactor cavity.

J. FIGURES AND TABLES 22 Rev 7 01/01/93

.j *.

WASnGM SUltGFTANk ME 1113 AE1320

,i::r----.,......--1Du..-* A~AE

~~

.~

f;.,s'J

<--C

~~):.>

STEAM G£NERATOft 1mr ,_

81.DWDOWN TANk VENT ' 0 IV'I tC'.>

0 ~\..nfO

<:> Jr""lll"!"l

<: . ~v.

in:

t>:Z N

w ....

v, 0

Ir iC

ni!""">

ct~

!~tr.-;

1-t?

z,-

O "I

~>

~

'"31: :z

~ ~--;

FUEL SlJPPl y HANO LG \=

.> ~

t; AREA r---------.,

r--------*---,

RAO- :

I FUR

.ME.A WASTT Sl. .LY ARFI\ RE 6117' *OO ADOH t.1 A£ 5711'

'lllE 10. 5711 AND "7U Tii,. SUN'\. V AND {)llft' Of r .. I) C~M 0

o:a

- CD

........ < GASEOUS FLOW IS NOT TFRMlt:ATEO PALISADES EFFLUENT FLOW PATHS

'° w"""'

.J ',; . - '*

PAUJ.AJ)f5 NlJGLit\R PLf\!ff Qf f HilJJ.Qa GA1.G~1LAJ J9H M!\K')At l~ev 1 ~*ion J Nye] Ide Ugfilillfil ( 2 ) umu.s.!{2)

H-3 5.5 159 Kr-85 4. l NA Kr-85m 0.12 NA Kr-87 8.4E-02 NA Kr-88 2.IE-01 NA Ar-41 3.lE*-02 NA Xe-13lm 2.2 NA Xe-133 1493 NA Xe-lj3m "u. 't.>

~ ...

Xe-135 1.11 NA Xe-135m 0.3 NA 1-131 0.025 3.21E-03 1-132 2.91E-03 NA

!-133 6.5£-03 4.7E-05 1-134 4.8E-04 NA I-135 l.84E-02 NA Ha-24 1. SE-06 NA

] Cr-51 2.SE-04 3.9E-03

.~

i Mn-54 4 .1 E-04 7.SE-03 Co-57 2.lE-06 3.2E-05 Co-58 8.6E-04 2.9E-02 Fe-59 6.6E-06 4.lE-04 i Co-60 1. lE-03 1. 24E-02

! Se-75 3.7E-06 NA j Nb-95 2.4E-05 4.53E-04 j

I Zr-95 4.7E-06 l.79E-04 J

j Mo-99 1. SE-07 NA 1 Ru-103 .3E-07 .lE-05 l) Sb-127 NA 3.SE-05 Cs-134 4.5E-05 0.7 l

l Cs-136 NA l.SE-06 J Cs-137 2.6E-04 1.36E-02 ll Ba-140 2.SE-07 NA la-140 7.SE-07 1. lE-04 I Unidentified beta 3.9E-04 3.3E-03 l.1

.j {l) Data derived from taking the effluents released during July-December 1978 through January-June 1982 and dividing by 4.

I Nuclide values listed as NA have not been observed at detectable levels

1. (2) l *. . in these waste streams.

j*

l

'j *, *.

1***-- *.

L ; 24 Rev 7

re**}:. :"*

01/01/93

i. :*. ;, .:*.

l >; - . *" ~ .. ' ..

PALI ~AUL~ WJGLLMl PLANJ QffS1ILQ9~E ~!~LPJLl\Ll()n MAmMl Revision I TAaLLL2.

! I

!!8.ilLRAfllfil.4!.!~LlOE DATA I

l I

I NUCUDE HAl.f-Ll FE LAMllDA .J}f.l£1~______y l\lllill...~----*

Il (days) ilLtl .IBE'li1U_$_l LM1Y/J2ill l

l Tr it 1um 4.49E 03 l.79E-09 5.68E-03 0.0 l*l!.

2 3

4 5

C-14 N-13 0-19 F-18 2.09E 06 6.94E-03 3.36E-04 7.62E-02 3.84E-12 1.16£-03 2.39E-02

1. 05E-04 4.95£-02 4.91E-Ol 1.02£ 00 2.50£-01 0.0

1. 02£ 1.05£ l.02E 00 00 00 l 6 NA-24 6.33E-Ol 1. 27£-05 5.55E-Ol n, 4.12E 00 7 P-~2 l. 43£ Oi 5.6iE-Oi ' ("'J.r-'t"""

o. :1:::11:-v1 0.0 8 AR-41 7.63£-02 l.OSE-04 4.64E-Ol l.28E 00 9 CR-51 2.78E 01 2.89£-07 3.86E-03 3.28£-02 10 MN-54 3.03E 02 2.65E-08 3.80£-03 8.36£-01 11 MN-56 1.07£-01 7.50£-05 8.29E-01 1.69£ 00 I 12 13 14 FE-59 C0-58 C0-60 4.SOE 01 7.13E 01

1. 92E 03

l. 78£-07 1.12£-07 4 .18E-09 1.18E-01 3.41£-02 9.68£-02 1.19E 00 9.78£-01 2.50E 00 1 15 ZN-69m 5.75£-01 1. 39£-05 2.21£-02 4.16£-01

~

16 ZN-69 3.96£-02 2.03£-04 3.19E-Ol 0.0 17 BR-84 2.21E-02 3.63E-04 1. 28E 00 1. 77E 00 18 BR-85 2.08£-03 3.86£-0'3 1. 04E 00 6.60£-02 19 KR-85m l.83E-Ol 4.38E-05 2.53£-01 1. 59£-01 20 KR-85 3.93E 03 2.04£-09 2.SlE-01 2.21E-03 21 KR-87 5.28E-02 l.52E-04 1. 32E 00 7.93£-01 22 KR-88 1.17£-01 6.86£-05 3.61£-01 1. 96E 00

'.f 23 KR-89 2.21E-03 3.63£-03 1. 36E 00 l .83E 00 24 RB-88 l.24E-02 6.47E-04 2.06E 00 6.26E-01 25 RB-89 1. 07E-02 7.50£-04 l.OlE 00 2.05E-OO 26 SR-89 5.20E 01 1. 54E-07 5.83E-Ol 8.45£-05 27 SR-90 1.03E 04 7.79E- 1 0 1.96£-01 0.0 28 SR-91 4.03E-Ol 1. 99E-05 6.50E-Ol 6.95£-01 29 SR-92 l.13E-Ol 7.lOE-05 1. 95E-Ol 1. 34E 00 30 SR-93 5.56E-03 1. 44E-03 9.20E-01

2.24E 00 31 Y-90 2.67E 00 3.00E-06 9.36E-Ol 0.0 32 Y-9lm 3.47E-02 2.31E-04 2.73E-02 5.30E-Ol 33 Y-91 5.88E 01 l.36E-07 6.06£-01 3.61E-03 34 Y-92 l.47E-Ol 5.46E-05 1. 44E 00 2.50E-Ol 35 Y-93 4.29E-Ol l.87E-05 1.17E 00 8.94E-02 36 ZR-95 -6.SOE 01 1.23£-07 1.16£-01 7.35E-Ol 37 NB-95m 3.75E 00 2 .14E-06 l.81E-Ol 6.06E-02 38 NB-95 3.50E 01 2.29E-07 4.44E-02 7.64£-01 39 M0-99 2.79E 00 2.87E-06 3.96E-Ol l.50E-Ol 40 TC-99m 2.SOE-01 3.21E-05 1. 56E-02 l.26E-Ol 41 TC-99 7.74E 07 1. 04E-13 8. 46E-02

0.0 42 TC-104 1. 25E-02 6.42E-04 l.60E 00 1.95E 00

Rev 7 01/01/93

f

~

(

_______ Revision 7 TABLE 1.2 {continufilil DASIC RAOIONU(;l.IDE DATA NUCLIDE HALF-LIFE _1Af1BDA BEIA 1 (days) ilill !MEV/Dl S}

43 RU-106 3.67E 02 2.19E-08 1.0lE-02 0.0 44 TE-132 3.24E 00 2.48[-06 1. OOE-01 2.33E-Ol 45 1-129 6.21E 09 1.29E-15 5.43E-02 2.46E-02 46 1-131 8.0SE 00 9.96[-07 l.94E-01 3.81£-01 47 I-132 9.58E-02 8.37E-05 4.89E-Ol 2.24E 00 48 I-133 8.75E-01 9.17E-06 4.0SE-01 6.02[-01

"' "'"'r ,,..

49 1-134 3.61E-OZ C..LC.C.-U't t:: 1t::~ .n1

u. 1ui:.-u1 2.59£ 00 50 I-135 2.79E-Ol 2.87E-05 3.68E-Ol 1. SSE 00 51 XE-13lm l.18E 01 6.BOE-07 l.43E-01 2.0lE-02 52 XE-133m 2.26E 00 3.SSE-06 l. 90E-Ol 4.lSE-02 53 XE-133 5.27E 00 1. 52E-06 l.35E-Ol 4.60E-02 54 XE-135m 1. OSE-02 7.43E-04 9.58E-02 4.32E-Ol 55 XE-135 3.83E-Ol 2.09E-OS 3 .17E-Ol 2.47E-Ol 56 XE-137 2. 71E 03 2.96E-03 l. 77E 00 1.88E-Ol 57 XE-138 9.84E-03 8.lSE-04 6.6SE-01 l. lOE 00 58 CS-134 7.48E 02 1.07E-08 l.63E-Ol 1. SSE 00 59 CS-135 l. IOE 09 7.29E-15 S.63E-02 0.0 60 CS-136 I.JOE 01 6.l7E-07 l.37E-Ol 2.lSE 00 61 CS-137 l. lOE 04 7.29f-10 1. 71E-01 S.97E-Ol 62 CS-138 2.24E-02 3.S8E-04 1. 20E 00 2.30E 00 63 BA-139 S.76E-02 1.39E-04 8.96E-01 3.S3E-02 64 BA-140 1. 28E 01 6.27E-07 3.lSE-01 l.71E-Ol 65 LA-140 1.68E 00 4. 77E-06 S.33E-Ol 2.31E 00 66 CE-144 2.84E 02 2.82E-08 9.13E-02 1. 93E-02 67 PR-143 1.36E 01 S.90E-07 3.14E-Ol O.Q 68 PR-144 l.20E-02 6.68[-04 l.21E 00 3.18E 00 1

Average energy per disintegration values were obtained from ICRP Publication No 38, Radionyc]ide Transformations; Energy and Intensity of Emissions 1983 and.* NUREG/CR-1413 (ORNL/NUREG-70), a Radionuclide Decay Datil Base - Index and Syrnmarv Table, DC Kocher, May 1980.

- ~ ~ . ., . . 26 ..*.. . . Rev 7 *.

".i*

'- .. *:., ., .."/' '01/01/93

,'1. *

" .~- .',

£6/IO/IO l ~a~r LZ' i

J to-lt.fl'Z 66* ' t'Z 60* 1cr*e Hl'Z.

iO* H1"f l>O* tot*r

~o-IO*

HI'S 010'1 60* 81iL't 11- m**

--1r' n: ¥~***

I!:

n* ir1 t&*

t'1 li*2'1 lll1't

r* *r**

HS'Z 1h't tO* ttt'Z h*., *z eo- *oh It*

tt-no*s

tt**

... oa*;

It- £16'*

,.., nz**

... orr..

tO* UO'l It* LU' oo- '

,,_ *t*r LO* '1 lt*

ft 11

11

"-ro**

ff'I!

Lt- t!

'2 1* ~

~r.n*'

1 ,Lt-

.. lff"'.,

u-

- 1 lte UC'6

,... "°" ,._

to- '~

u- ,., .*

~*Ht' Ul't

"t

'f . Mlll

);."

"T"

t t'Z LO* '20'1 H* 6 f't NII

,. I',_,"'

... 02D'l t*- .... , 10* Ht't

-- to*r ns** '"*ro***

H*r ,.,

tl04 iO*il"1'5 tO*l!JM*'"

60*ilZDl *s ... 'ff' to- uc*z 10- lf t.'

tO- 5Dt'

ll- " ' ' "

lt* fU'Z ll*lilfU'I LO*JlOZl'f IC HSM u-uu *z tu- oco*z 10-rzo*

eo- zu* ..s ll* ISH't t0*il*8Z'S 10- *o**t 60-ilZH 'Z H*IO"' 'Z u-u oe- tn* t

... uo**

IZ*llt UH llU.

tll*UU' l to-aon*z lt*S wai... nuw IO*ilUZ'"

, .-r 1n nrna1tno1 .l.lllMQIC

~' ltJr.I

,Lt-

.. ff'"'

n*z

'°'

to-:UOt'S tO*ilLtl'S t*C

MSC IO IJ.lYra" 1101 WIQ

<Otn:> D.lJWi':>H > *1111:>

a;aina11n '>.Y:>JG 011 .

JGUM ~IY.ll!O:> 1110 40.l - :unia* 'UI~, GlltlOalO

..... nYll !BW lllUIZt - t1n1111 *Jen ..... HOOODOX aannf4 8Hllll

cacva1a1 ial\ii a11nowo ,,,

e' D C:>Hl1Y:>> UYll ltOIUllrlil .lQH o*~~9Z CCld.LIW'&S> Yl*Y':>ilC'Clr.>'NIW'OG1G t'I' CCVil.1.3~> .LllOlilH OHIG1InG O'Ot Cc.il.LIWl .LHOlaH GWJH *~a~

ooo*,~ ooo*et OOC'(f IOD'Of DOOZ OOO'Ol OOOt D.lIC IHl ..,., CJtlW ~I a:mwlC11

'i10-i1',0.'

vo-nev '

IO*il~U llO-littl' l tO-ilrOt'6 tO*l!Ut' I iO-~lOV 110-ilHO' L 10-lll>ft'I LO*I0,1' l l0-ill'9. t tO-hl t to-nz,*z t*-izz**~ LO*JGtt't *~*=ttr*t 'o-~*r tO*VGl*'Z LO* 6tG't tl*JlL6 fO* P~l'l "tD-~6l**s an

is

~0-~fH ' DO-HOO.' 10-a*H * ' 10-ilHt'l lO-!l*OO't lO*llUf' t lO-attt'Z lO-JOf6't L0-1t*o** fO-,tll't tO*il~l~'t ICJ e~-iCoH 80-:HDO' 9 PO-H6l' l f0-Ht1'6 LD*1'6t 't £0*ll0 '9. t £0-POtf'f to-*&*t** to- Oit'L PO- Zlf't tO-VOL6'f I ro-i! nr *' 00-?'H

9 CC-ii Ht. ( eo-nn** lD*il*U* t to-rn* ,,_ ,,,., .. ,,,,., - ,,. :*-**1****1 **-1*****

LO*ilt9 t to-a*r to-atr*** t*- rt" *o- tLt'T *o-15oz** 1111;

¥0-ilOCl 9 wo-~~H't to-n tt *

L0-29Dl't lO-il~ H' t LO*illtt'l LO*~-Zf'f LO*DltD'f to- Q"Z'6 *o- ,.,., 90-~Ztt >>N t to-1flt'Z lD-?i~&** ~-1i***1 ZOt't PO*#*e**~

fO*HU.' 20-ilPU' f 80-illOt'I LD-~*ro*1 LO*UH' l Jllll lo-n*~ 1 a-a19~* 1 LO-~\"H' 1 ,~*r&t*:i £0*!.IPO I' (

to- en*l'1 '"t II l.~-llf??. 1 1.0*l!!>G l LO* !ltl'I l?- 'P *; lO*iLlL '! tll- Lt*lltt~*~ t&-~il.ii'~ *- !!~'.*~*tu* PO* \'ft'6

.i

~.

H-;;n*v H-iltli'9 i iii-iiii* i. i L~*jjl>io;* i ll*-~ Lil "'i n-i::ze:*t

£0-H*o*t 1.0-;m;z

t LO- 11*(' l £0*iUl!6'l 80-ii6U t tO*il1£0'6 tO-JOll'l LO*atO('I lO*llOO' Z tt>-~m*r to-its)*~ to-gtit**

LO* *Ot'l LO* ~tO't tO* 6tt't ft* Ztt* ti*it5?'1 ;o- tot*t ***100'*'

D* rfl'l 99- S6,'9 WP4 IClal H-ill 1'. f 90-~'19"' t0--(1.!'9 t0-~0,C't OO*Pth' I LO- f(O't tc-attS'l 40* (ft't ,,. LO,'l *o- tro*,

~O-<l>U

~v-H10 go-il6Z t' ~ to- $U'£ eo*~z9o*i eo-~ftt** tO*i!,H' l lO- to-;1tt'l to- Cf&'t ,,_

OfO'l to- ** ,., lO-tr**1 G90' O* ttT'I f0-~!01 te- l*~** to-~,~**

~

";ti ti$

RC.-~<SI 10-;ou * ~ l;lO-ilZH to-~~*1*9 90- ,,,., LQ-~IOl' 1 10-!roc*t te*i*"l't ,o.,tj**: ,:- *01** to-11of**

Ou-Utl GO- "fD'C eo-.11ue

t IO-lt6C'L tO*ltfl'4 to- in* t tO- LU. z LO- LOt.' tit* L * . - tu. t H* or "t "" ..

b Ot ~ ooo*~ QO,.[ OCO'f 001*r lllC ;H! I'll*' HO. r

'°'

sai1H Ml ll:lllUctO 1 HC'l Hl 'I IK'~ tn*e '

urno:i n.&..a111?Jc1 *11N:i IORJA'llllpu YNPI*

aDu 'no1m * ....,., 011 O!C!GiJnt lllJlllllWlNO:l IC oltl!

acr.iia* 11"11i i*~*o

orn* ¥!\'ti .Lllt< llltC/tl - U1to/l~ c:c!Un n = ~MIJ ~119' ~

u-o-ra *lU "c i<n~

lVflNWH I U'Jl<*!""H fffJi j\('lfl:)lV] ~istEr JlHHo l t~\fid HV:(i:"li'itl qfflis lli.fil

...c:

ft Iii 0

0 r-c:

..:: !;:zl

..,........... la' &..,:: ...

&2*Zzzy

.. 1 nic:

n ..

0

. j fit1 .. ;1* I..... i c:

.. .. j...

r-z c

~

a -...

r-

~ i .

i ... !.

~

.' . I ~

.... ~,

n D

g .*

. . . . . . . . - ..... . .....g ................. g h~~N~*oNo~..,.**~*

~NY~*~* **--*~*D NUtD.,.N****

.. ..N**N.....

~~~~*Y.,_.*~*~--~M

- w*H-~o~*****......,.

-~*ouo*~~*~**..,_

c .. =-~

*-.~. 1: I I.

oa -~*~-*o******N*~

e I I I I oooeo***o*aoo*oo I I I I I I I I I I I

~

I G

-~ --.....-------*--A~

I I I I I I I I I I I I I I It a ********~--*-***

. . . . . ... . . ... .. . ~ I

...-. . . . . .=.......

NN .....

~~:~===~Q~==:=

N¥M~

........... N

~;

2

~-----~-~N...--**-

~N-ww**~-~~*-*-*

-*NH~*o****O-~*w

~*-o-~*Y*MH***Ne

*,._,......AaaRA**~

=

~!

Q *...

~ fi c...

n I

c I I I I I I I It I I I I I I I I I I I I I I I I I I I I I I I ti c <

~:::::::: ::~:~:::::::::~ i:

I

........c I- *.. i I

i -=

N

- -:::* '.* I:: 0 c

. __ r-

~ ~

- - - - ~iiss!i

r.t...,,,,,,, !; -** .. ! ~

~~===== I ...... '

c

.... ............--..iwaa........ -.... c ... t .....

~ .................... . .,._"" ...............

ii

...E .

~ :::::::~*=::::: 0 ..

Y*-~ .. __

NNHNNt....hl .. , * *

w . .- -..

w*--~*-.uo_.,~o.......... .

~

... ll ~

0 e

-4

~

- w*geeaeo****** ....

-4

-~~M~ ...N~AM.11~.~~* *M**-NUl*t**...o****

c 0

-.qaA**ftlA~-~----

1 I I I I I I I I I I I I I I I

=~ ***oo***t*oooe*o*

I I I I I I I It I I I I I I I ~

., v.

.-... E . t N .. :s ~*~~*~~~~******* 0 Q)

I

~Y**w..-.~

t:===*~:~::~::~:

.....**www D

.... .. N ii I

I

~

UJI

!""~

a * ~~~-~i.....~~-~-

I I I I I I I I I I ! I I I I ' !6

!i eo*oo~*oo**~****

- - - - ~*-******** ~I

.. ii ................

.... --*~--***

................... .....* i

1 ........ ._ ...... .._......,..., ....

..;! *a._.,.,._,..,_,.

......... -~"' 0 0 * ....

-*.. ...~w**

I I

.. . .'119**-*** **

I

~*

- - - oo****et**** .. *

I I I I I I I I I I I I II

-4

-cl N

I N

o .. -

~'-O'-

~~~,~~~====

__ .,. .......... -o**u Wt_.,.N..., .. *Wtc.-"111'** . . .

.........u .........,.............. .

.,.,.,...,..,..n~*ARftl I It I I I I I I I I I I I I I -..

D ... CI

~*~~N**~~N*~N-~*

N~*w* ~ ~

. . . . D ...... \ia . . . ...., *N~Wt ...... CI t:~::~~~~~~~t:~

I I 1 1 f I I I f I 1 1 I I I I!

oooooeooooe*oooo 0

0 e

~=~=~::~~~~=~~:~

. . . . . llSJa. . . . . . RA,.,_flt,.Al'lll I I I I' If t I I I I I I I I eoooooooagoo.:.>ooo Q

~~~~~NN*w*MN~--- . . . . ... .

Yu4t>~ ...,. ..... _ _ _

......... ....,~***

-~ ~~*~*~**~~~~*~ :0 *-oCloQ.NC.***-Q.._. .........

~~-~o*~N~*****M~ _.,...,Nm'--c*""~.,.o--'-*'--

~~*~MY****M*~*~* ....,..,.N....,.a

..I ,.,.,.,.,.,.fll *cN* ......t:e,.-*..........

'-"'-'..., "'0 0 -~ ......-~~......--*AN o I I I I I I I I I I I I I I I I

I I I I I I I I I I I I I I I oocoaonooooooooo

........ ooooaeoooooeoooo o:o ___ _ *--~---~ .... ~ ....

~---~NNW*MMN

- m

........ < ~*M**o~*-*N~*WN~ 0 ~--.QN . . C. * ._,O ........... _ _

_ _ ..,_e>>.o-*ONO*ONUt**

'°w....,

~~~-N~a~*~N~~~~~

u o...,,..,._..,.0.,....,1* ..,...,oY*- ...

,.,."'"""',.tlt,.RlllaAN,.,..sa,.

~~oM*aoN***a**~M

. . . . . . . . . . . . . .amaRNRN O 0 I~ I I I I I I I I I I I I I I D I I It I I I I I I I I I I I I OOOOOOOODOOOQOOO ooaoooooooocooco "'

aaa********ooaoa

---00000000-~~ ......

0 I I t t I I I I I I I t I t*t I

- - - - oa-******* oaae*******aoaoa ~ *w.1u~M~~u...,uwu...n1

0000000-----.

~ =:~:=:~~~~:~=:~

000 00 0*000 000 0000 0 I I I I I I I I I I I I I I I I O I I I I I I I I I I I* I I It

~~~~~~~~~~~~M~~~

_..,..,...,, __.* ...,.a ... ,.... ,,..~~ .. oo 0 umwwMWUU~UU~M*W

~ ~~~*~*~a~~*~**~

~~~~~~~~~~~~~~~~

_ _.,~~* ..

~~--""NN~--~-~-*

O<<tN--..,..""~*-,... ~ "4 o .. _.,o .,,...~o*aN-0><41

...... ff')

~~'"':~~~O:~":~~~~~--:~

N~o~o~~~o~oo~-~-

0\

W'\N~-9'\"0 .... *-*""'~---.-.

~***---NN--- *~~ > .........

o******~~******* ooa*******~ooaaa ************~***

o.ooooeoeeooooee* QJr-4 T .,.,..,...,.,.,.......,.,.,.,.,.,

OOOCIOOOOCIOC>OOOOO ---oaaooooo .. --~- G t I I I I I I I I I I I I I I I IX 0 o

.. ......-..... "- =:~~==:=~=~===::::

a I It I I I I I It I I I Ir I I It It I I I I I I I I I I I 0 * .,.,~w*u~U~MW~~M~ a ~U~M.,..MmMu*ww*~u a *a~**-~ ... -**--o~* ... . .

. . . . . . . .. .. oo*************o o a~*N~ ........... ~ft-P..N-*

. . . . . . . . '9--.......

.. ...,._Na*--N. ~~~~~~~~~~~~~~~~

~-- ,._,.....~ O~~ON . . . . . . . . . . . . . . . . 0 0

..-.ic: . . . . . . . . . , ft . .............. .

- oa**N*"HN**N*~

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 91'

~~~~~~**~"~ ........... 0 0000000000000000

".._ ... . . . . . . . . 00000000-~o e t I I I I I I I I I I I I I I I e I I I I I I I I I I I I I I I I G WWU'WWUt....,..,_,.,.,.,.,. o u.......,.u.,....,w~tiw~

o~ft . . .*MO .... G . . . "~

==~~:=~~=~~~::::::~

Q

., ............... o ........ N~N

-~*-"~"~~~~o*-** . . . ..,..... . .. .. .,a ...............

O*N~"P..90ft*Na*a ...

a ... oe oe**

* * *-:ti ........................ .

oooooo<<****aaoaoe

- - - - o**o***ooe I I I I I I I t I I I I I I I I *...

I I I I I I' I I I It I I It

_,.,..,.,_,Wtlrwww.-~11M1-.WW ~

o ... ...,_,...,-"'.,.,.'""*.,*a"" .... N4' o a*~o****ftW"*~ .......

-*-~*NC*~~~n**N o~**NU***N*WNOaN

. . . ..,-.................... -~"......

N-N~

~~**** ... P..NNO

-*N**-~ ..... ~.

.~ "' ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -4'1 ~

~

ft **o&oe~***o*o***

- e ................,uwv*.,. ***

~"' ........ ~ ....

I I I I I I I I I I I I I I I I

~~ =~:=:::==~~;=~= l:~

~

t-N-~~~~~~~~~~~~~~~~

~ ................~"..--**** ~= :::: :::::::::: !.

I

... ~ .............I..._ ..,.. ...... .._ ...... ~

... .... .. ........ . , I~

... ~********ooo****

I I I I I I I I I I I If I I I ~

.* .N-* .....,......................

-....o.....,.aitt.......,...,.o..,,.._. -~-

..a...

~

. iI I ....a

. ~--*==~:;:;~:::::;

I

~=--~=:,:::::.~~

__...,.. m::: ....::= ..................... I*

~

v: **ooeo****uo***** ........,. -*Ill*-***

II .-.;........,;.-:9.;..;,_;....:..;..-

- ~: *aeeeeo*o*e*o***

I

...a**.

c

.- ..... ...a**.............................. .. .

0 I I I I I I I U fJ I t I I I I I I I I t I t I I I I *I I I I I I c .. .......... ~. . -.4 .............ft.......

i i

'"1*

""*o* ..**** ... ff9'-.N**

,...._..,,,.._,.., . . . , . . . . . . N _ _ o ...

""~ *--*~

tI"

~ .. .. . . * ..H*H*~-*-*-~-

..._ _ _ N . . _..'4,.f'iJN ... N-ftN

~

T4:'T,.~TTi*TTT~T~~T

. . . . .w ..........,... . . . *ea

- - - --eeoeeeoooo I I t I I I I I I I I I I I I I

................. w.w

~ i o ........... ,..N#llr....

..~=~=~~.~==: :::

q* ... * ..........

~==~==~i~~~;

...,.~,... .. ,...~*

. . . . . . . . . . . . . . . . . . ,. . . . 114 ........... . .

""4 .,;...;..;.;..;, ;..;..; :.. * ,.:...;.;...;.;...;

=~::::::::::::::

N._,.flll...........

_., N**atflo

- f t. . . . . . . . . . . . . . . .. - - 0 . . 0 . .

tf\...........

a-. ...............,,,, .

3 ...........a*oa I

~: :::::::::::: {;

- - ft~*~**-~*~~~H

~- **-..;.;.;#.-...;...;..:..;*..:..:

====~====~====

~= --*****-~---M~ ....

...... i., >

....... - * * * ~ . . . . . ~ON**

...H t..: :~=:~=:~=~~:~:

i* *~*o**--~-N~~Na ..... .....

c...,.**aoN****~

i3 II:

.:e.i..;..;..:..N-t~~~~~~~ .;...;...;_;..;.; ~..;..;..;..;..;

.. ....... ............ . . . -*.........* ---...... .~ ....

J Cl

~==:::::: **--**********~*

Gooeooeoo*ooeooo I I I I I I I I I I I I I I I I

~

I I I I I I I I I I I t I I I I

\ "

~~ ....... .....

"-*~~~NO~~**~*N

~ ~~~~*a*

~ft~***~***~N* -. ~ ., *aa

~~~~~Nee-**~-~~

""........ **~-~**~~~~~ ~

~*~a~~~G--N*N*~~

~.;.-;.;.;.;~.;.;...;~..;..;N...;...;

~

u a

=

~

> a u

"'~~1~~~1~--- 0

..,.. m~ z::z .,,., ..

""' ll .......

... I 4

. *' .>-;*~.,~ ... * . . . : :r~** <-'. 'f---

... a s I i*aI la.ml

==**-=*a g

..... II i

..... =

~ ~

- n

a * ...c.,.

I *p: ~..! i"" ~ ~ ..: !R

******~ ~~&~&&~~

if I ......... 0....,. =

.,.~*.,.*****0*1.-

t:::=~~=:::~

...~ ~.

c ..

.. D ... n

..a

,,,,,,,,,,,,,,, 'r.. != I!. r: a

0

===~::::::

- - - - ca*****eooo

Eg n

................. **-*.,.°'NY..........- ....--

N N

M

~

N H

N N

N

>c 0 ~-W~MOY~~*a--o-~

oo*~Y*N~o**~~O~Y

... i : I

- DH+-. .**""1D\a......... Cll .....

I ,.,..~-NO

>c t I I I I I I I I I ' I I I ' I liit

09********oeogu

~ ~

a c

~ *8 ............... - .................

~I

............... 9"""" ... --~

I -

I

~

i MM

~

N*W*>>N*

~

- - - - -*~~-

..................y .........,..

- - - - ~

~~~*M~

._.~.a

==~~===::~:t::~

000000***~0****-

-*~.,

. . . . . . . . . .l . . . . . . .

...._~.,_.._.D

................ c..*

i

. . . . . ~ ...............'-M. .

- o...

=:==~:=::::~

t::==:=::::::=.

u*oo**~~N~*~

- M*N .....1...._ ................. ..* 10

--***---**~~~NNNN

. ......"°..........

~

- - - - 111111u*

~ ....... , ......-

................................................ *o****---*****-- n ..... A****e=**~

~

1vi

~~

,.: .a.a;.;..a.:.;.;,.;.~:..:.

Nae

~"""' ~r-I 0<<'-

~-

i *

...' i :;:;

tO'?

>v.lo

~f

...N_M..,.-w,..._.-..... o* r1}r-ri

~

~~~~~~~~~~~~ ~ ........................

~N

< iVI

............._. . . . . .._.. .N ............

! **-~-~~~~~ ... a*o-~Y

~===:~~~j~===-~c ...

& ~-

- ..
  
  ..e.:.:.o;.;.-.;.a.;.--.1.

a*-.

..-*-**o*"":

"f t::==~~===:~~~~

--~ ...................

=====i-:::r:::.=:::::

...........N.......

'r':-~'~:"M"'rTT?,,.,:~;

a :::::::::::::::::

Cf

_. 1~....--~

C>

0 Ek::

,nin

,-~

1;= r""\

i ..*

--*********--*"'"- l*

. . . . . . . . . * * . . . . . a .

...**:*00.............,._ . .. . . .

~...............................

.. .. ~

) -...: ;> ;;p I ~

R~NaGr

. . . . . . . . . . . . . . . . . . . . . 1. . . . . . . . . . .....

==~~:~==~=:~~! **o**UtH.-..,_..... .,....._.

--*****~-*~~r

........................................ ::::::;::!:::=

~t..!~~:.~:..!*c~

f llliJN ...... UiWceN*................... 2 ..

I I 1 I.JI I I I ,f I I I I*-~

M-t I

- t.....-i;.:=:

~01-0

Zii

~l;:..

~

- .... **~~*~.,............,. :z

................................. w * * *

...... 0........................ ..

G

~*~

i~==~==~=:=~==~ **NN..,._...,_,,....

~~---~ * .-.~ ...--w..-M M

G

= ...:

~=

~

~~.........................

!.!.!!!:.~~:,,~..,!.,!~. ..

~---~

ct~UI***

~

-c r

~i

~ ~~ ........ -.~--~~.............

I..

~

--~*~*:..;...~~~*~~~~ .. o .............."',_.............

.:c

~--~ .. ~N***N~*~*~

- - N I

... ~~-*-**-*~...,..

-~..,.

I I I I

.......................................-~~

..,...,.~,...,.**~o I I I I I I I I I I I*

=~!:~:~:~:~~~:=~~~

~~AaAM~---IUUiRG I I I I I oaoeu**ou**ooe..>-eo I I I I I I I I I I le K

r~

....MNN~N...... NNNNN .. N

. . . . . . . . . . . . . . . ~~~M . . N* YY.****w***w.Y. ...NH...,..

~*~-~~M~~***~~~~. ~~~::::=:==~~:=~~ ~

"::=:~=~=~~===~

I

. . . . . . . . . . . . . 0 0 ...... *

N * . .~* ....

I I I NNNNNNMN*fllltNNNNNN I ........__

. . . . . . . . . . . . . . . . . ., . , . , . , . . .. . .0 I t t I I t I I I I I I e

~RRAANallla*AA . . . . . . U I I I I I I

~-----------~~.........

OOOODODQODQCOOee I I I I I I I I It*

0 a

~ '

- ~-- ... w ..... **-~MWU --*Y**M~~**~NNN~ **~~~*N*Y~*N--~N

=====:~=====~=~= .. .

0 ***~~-~~~~o**~~~.

N**~**o~~*N*N~*Y

--~*YU~*D~~-.._.~

.......... ~-***~6-*D*w.,.***

........... ~-*~* ...... ONG*

,.,':'ff'M'~':-':::":':'

G J.

.... N~*Y*N*CDN..,.0~*

N....,.......**R*R*~O

. U l ..... 0 ............ 01. . . . 0 M~~-~~ ......N-RQ...... O

~~~~~~~~!~!!!~~!-

~

I I I I I I I I I I I I I I I I 0 0::0 _0-........................ - ....... ---

-m

.... NNN ..N..,.. NNNNNMN . . . . . . . . . . . . . . .N ......... NNNN ooaoooo**O~GQOO*

~l~

. .............. . ~N-~~-**~~H---

'° ~, WY .. ~ .................... .,.NNN . .

w....a

-*~***;,,.~;..;...;_:o ~;_..;,..;_.

~=~~~==~=~~:~£t:

,,,,,~~~~,~~~

~~ ... ~ ......... .-~~~~-~~~

~NNNNN..,..NNNNNNNN

~

D

o**ON~~-~*N~-~*~

~~~**~*.,.NQ*o*-~-g I

......a....a*M*"'9*Nc:r*

,._,.'8R,_,.R:a,.

._~N I

NNNN~NNNNNNMNNNN I

~

I ..

I I

--~

I ............... ___ _

I I I I I 411Rflll:A0 I t I I G

~y----*--~*h*N~*

~aN**.--*oUt\190...,...,....,.

. . . . ONN*NA'-"'**oc\#O...,CI**

,_,_ftlRl'QNAP"1&RtflU9RRftllli.,.

I I I I

~----------

GOOOOODOGOOQQ~~o I I I I I I *I I I I I 10 g

~

{ l ;.

~AUiAf>L5 .t.l.!Jt;;LLl\H PLArU Qf£~JI1JlQ5L CALG.VLAL19.H. 11.A:NVAL

1922 fALIS8QES nevlslon IMLE l. 4 I

1,.AHlL!&Ulli!!~

I.ABLE lQsll-1 Distance to the nearest residence, garden, dairy/beef cattle and goat in each sector.

SECTOR RESIDENCE GARDEN BEEF CATTLE DAIRY COW fil28l H > 5 mi > 5 mi > 5 mi > 5 mi > 5 mi NNE 1.1 mi 1.6 mi > 5 mi > 5 mi > 5 rn1 NE 0.9 mi 0.9 mi > 5 mi > 5 mi > 5 mi ENE 1. 3 mi 1. 5 mi 4.0 mi 4.0 mi 2.5 mi E 1. 0 mi 1.0 mi 3.5 mi > 5 mi > 5 mi ESE 1.0 mi 1.1 mi 3.1 mi 4.0 mi > 5 mi SE 1.0 mi 1.0 mi 3.8 mi 4.3 mi > 5 mi SSE .75 mi 1. 5 mi > 5 mi > 5 mi > 5 mi s .5 mi 1.5 mi > 5 mi > 5 mi > 5 mi 1~

SSW .75 mi 1. 5 mi > 5 mi > 5 mi > 5 mi

~'!.

31" Rev 7 01/01/93

~ )

i ! i i *, ~* ;

Revision 7 TABLE 1.%

1992 PALISAPES LANO USE CENSUS TABLE 10.11-3 Cr1t1cal Receptor Items Distance Sector (M1le£1 Locat1on/Descr1ption .*X/Q {sec/m3 )

SSE 0.48 Site Boundary N/A 1.4E-06 Ie..

s 0.50 Residence, Palisades Park 3/4 m1le West of 29th Residence/

Garden l.OE-06 Ier Avenue and Blue Star intersection.

ESE 3.10 Newel, 73419 30th Ave Covert, (South s1de of Beef Cattle 7.4E-08 Ie.-

road) .

ENE ENE 4.00 2.50 Cecil Hodge, 16971 72nd Street, 3.8 mile South of 16th Avenue and 72nd Stre~t intersection (west side of 72nd Street}.

24th Ave and M-140 Dairy Goat 6.4E-08 1.3£-07 intersection, west side.

NE 0.90 LSwetway, Rt 3 Box 133 Garden 7.3E-07 Blue Start Hwy, east side.

f:ilrr.E: *Based on Palisades 5-year composite meteorological data, 1983-1987 .

32 Rev 7 01/01/93

jr ".!, j *. I

>' . ~* : J r>.AL L~A.DE5. _m.H.~.LEA!L PLANT

~)ff~ITL m>.5L_CAlC!1lATlQN M.Jl.mJ.Al Rov1sion 7 IAillE l .5 DOSE FACTORS fQfL.fillQMER~lOH IH NO.fil,l_GASES*

_filE_'- _Qf_f_ OFS 1 'Ir.pi'

__..k;;_ _

Kr-85m l.17(+3) 3 1.23(+3) 1.46(+3) l.97(+3)

J~

~~

Kr-85 1.61(+1) 1.72(+1) 1. 34 ( +3) 1.95(+3)

{'_;

- *-.I * ") \

Kr-87 5.92(+3) 0, A I \ 1'.J J 9.73{+3) l.03(+4)

"~

~~.

~~

~

Kr-88 l. 47 ( +4) 1. 52 ( +4) 2.37(+3) 2.93(+3)

't* Kr-89 1. 66 ( +4) 1. 73 ( +4) 1. 01 ( +4) 1. 06 ( +4)

t"

'.~

. :\ Xe-13lm 9.15(+1) 1. 56( +2) 4.76(+2) 1.11 ( +3)

,,,w

-~i.

1 Xe-133m 2.51(+2) 3.27(+2) 9.94(+2) 1. 48 ( +3)

Xe-133 2.94(+2) 3.53(+2) 3.06(+2) 1.05(+3)

Xe-135m 3.12(+3) 3.36(+3) 7.11 ( +2) 7.39(+3}

Xe-135 1.81(+3} 1. 92 ( +3} 1. 86 (+3) 2.46(+3)

Xe-137 1.42(+3} 1. 51 ( +3) 1.22(+4) 1.27(+4)

Xe-138 8.83(+3) 9.21(+3) 4.13(+3) 4.75(+3)

. Ar-41 8.84(+3) 9.30(+3) 2.69(+3) 3.28(+3}

1. mrem/y per µCi/m:

2. mrad/y per µC1/m

3. 1.17(+3)

l.17x 03

Dose factors for exposure to a semi-infinite cloud of nobi'e gases. Values were obtained from USNRC Regulatory Guide 1~109, Revision 1 (October 1977) *

I. ' '

33 Rev 7 01/01/93

~ ** ~ :J , "i _,

!'All~r\Ot.5 _NV!;tf.A!'LP_LAJH QJ01IL QQ~L.CAL.GlJHHlQN MAWJ/1.L

Revision 7 IAf!!..Lli.§_

STAPLE ELEMENT TRANSFER DA))

F - MILK (COW) 111 Fm - MILK (GOAT) F - MEAT B~v ELEMENT COAYS/Ll (DAYS/L) (bAYS/KG) l.YEG/ .,,Oil.l H 1. OE-02 l.7E-Ol l.2E-02 4.8E-OO c }. 2f 002 l.OE-01 3.lE-02 5.SE-00 Na 4.0E-02 4.0E-02 3.0E-02 5.2E-02 p 2.SE-02 2.SE-01 4.6E-02 l. 1E-00 Cr 2.2E-03 2.2E-03 2.4[-03 2,5E-04 Mn 2.SE-04 2.5E-04 8.0E-04 2.9E-02 Fe 1. 2E-03 l.3E-04 4.0E-02 6.6E-04 Co l.OE-1)3 l. OE-03 1. 3E-02 9.4£-03 Nl 6.7E-03 6.7E-03 5.3[-02 l. 9E-02 Cu 1. 4E-02 l.3E-02 8.0E-03 l. 2E-Ol Zn 3.9E-02 3.9E-02 3.0E-Oi 4.0E-01 Rb 3.0E-02 3.0E-02 3.lE-02 l. 3E-Ol Sr 8.0E-04 l.4E-02 6.0E-04 l.7E-02 y l.OE-05 l.OE-05 4.GE-03 2.6E-03 Zr 5.0E-06 5.0E-06 3.4E-02 l. 7E-04 Nb 2.SE-03 2.5E-03 2.BE-01 9.4E-03 Mo 7.SE-03 i'.SE-03 8.0E-03 l.2E-Ol Tc 2.SE-02 2.5E-02 4.0E-01 2.5E*Ol Ru l.OE-06 l.OE-06 4.0E-01 5.0E-02 Rh l.OE-02 l.OE-02 l.5E-03 l.3E+Ol Ag 5.0E-02 5.0E-02 1. 7E-02 l. SE-01 Te l.OE-03 l.OE-03 7.7E-02 1. 3E-OO I 6.0E-03 6.0E-02 2.9E-03 2.0E-02 Cs 1. 2E-02 3.0E-01 4.0E-03 l.OE-02 Ba 4.0E-04 4.0E-04 3.2E-03 5.0E-03 La 5.0E-06 5.0E-06 2.0E-04 2.SE-03 Ce 1.0E-04 1. OE-04 l.2E-03 2.5E-03 Pr 5.0E-06 5.0E-06 4.7E-03 2.SE-03 Nd 5.0E-06 5.0E-06 3.3E-03 2.4E-03

~' '

w 5.0E-04 5.0E-04 l.3E-03 l.BE-02 Np 5.0E-06 5.0E-06 2.0E-04 2.5E-03 34 Rev 7

, 01/01/93

' \'*

PJ\t 15_AJ)[j__ liV~.LJj\~ Pl.ANT liff~l fLQ05L~AtC!JLATl01'! MAN!Jt1L

Rovlslon 7 TABLE l. 7 INFANT INtlALATlON DOSE COMMITMENT FACTORS (HREH,50Y PER PCI INHALED IN FinST YH)

ISOTOPE . BONE LIVER TOTAL BODY THY 010 KIDNEY LUNG GI-LLI H3* 0. 4.62£-07 4.62[-07 4.62[-07 4.62E-07 4.62£-07 4.62E-07 BElO 9.49£-04 l.25[-04 2.65£-05 0. 0. 1.49£-03 l.73[-05 Cl4 1. 89£-05 3.79£-06 3.79£-06 3.79£-06 3.79£-06 3.79£-06 3.79£-06 Nl3 4.39£-08 4.39£-08 4.39£-08 4.39E-08 4.39£-08 4.39£-08 4.39£-08 Fl8 3.92£-06 0. 3.33£-07 0. 0. o. 6. lOE-07 NA22 7.37£-05 7.37E-05 7.37£-05 7.37£-05 7.37£-05 7.37£-05 7.37[-05 NA24 7.54E-06 7.54£-06 7.54£-06 7.54£-06 7.54[-06 7.54E-06 7.54£-06 P32 1.45£-03 8.03£-05 5.53£-05 0. 0. 0. 1.15£-05 n 1. OOE-08 0.

AR39 AR41 0.

o; 0.

0.

v.

0.

v.

0. 3.14£-08 0.

CA41 7.48£-05 0. 8.16£-06. 0. 0. 6.94£-02 2.96£-07 SC46 3.75£-04 5.41£-04 l. 69£-04 0. 3.56£-04 0. 2.19£-05 CR51 0. 0. 6.39£-08 4 .11£-08 9.45£-09 9.17£-06 2.55E-07 MN54 0. 1.81£-05 3.56£-06 0. 3.56E-06 7.14£-04 5.04£-06 MN56 0. l.lOE-09 l.58E-l0 0. 7.86E-10 8.95E-06 5.l2E-05 FE55 1.41£-05 8.39£-06 2.38£-06 0. 0. 6.21£-05 7.82£-07 FE59 9.69£-06 l.68E-05 6.77£-06 0. 0. 7.25£-04 1.77£-05 C057 0. 4.65£-07 4.58E-07 0. 0. 2.71£-04 3.47£-06 C058 0. 8.71£-07 1. 30[-06 0. 0. 5.55£-04 7.95£-06 C060 0. 5.73E-06 8.41£-06 0. o. 3.22£-03 2.28£-05 Nl59 1.0IE-05 5.44£-06 3. lOE-06 0 . 0. 5.48£-05 6.34£-07 Nl63 2.42£-04 l.46£-05 8.29£-06 0. 0. 1.49£-04 1.73£-06 NI65 1.71£-09 2.03£-10 8.79E-ll 0. l). 5.80£-06 3.58£-05 CU64 o. 1.34£-09 5.53£-10 0. 2.84£-09 6.64£-06 1.07£-05 ZN65 1. 38£-05 4.47£-05 2.22E-05 0. 2.32£-05 4.62£-04 3.67£-05 ZN69M+D 8.98£-09 1.84£-08 1.67£-09 o. 7.45£-09 1. 91£-05 2.92E-05 ZN69 3.85£-11 6.91£-11 5.13E-12 0. 2 .87£-11 l.05E-06 9.44E-06 SE79 0. 2.25£-06 4.20E-07 0. 2.47£-06 2.99£-04 3.46£-06 BR82 0. 0. 9.49£-06 0. 0. 0. 0.

BR83+0 0. 0. 2.72E-07 0. 0. 0. 0.

BR84 0. 0. 2.86£-07 0. 0. 0. 0.

BR85 0. 0. 1. 46E-08 0. 0. 0. 0.

KR83M 0. 0. 0. 0. 0. 2.50£-09 0.

KR85M 0. 0. 0. 0. 0. l.31E-08 0.

KR85 0. 0. 0. o. 0. 1.16E-08 0.

KR87 0. 0. 0. 0. 0. 6.59E-08 o.

KR88+0 0. 0. 0. o. 0. 1.38E-07 0.

KR89 0. 0. o. 0. 0. 8.67E-08 0.

RB86 0. 1. 36E-04 6.30E-05 o. 0. 0. 2.17£-06 RB87 o. 7.llE-05 2.64E-05 o. 0. o. 2.99E-07 RB88 0. 3.98£-07 2.05£-07 0. 0. 0. 2.42E-07 RB89+0 o. 2.29£-07 1.47£-07 0. 0. 0. 4.87£-08 SR89+0 2.84E-04 0. 8.15E-06 o. 0. 1.45E-03 4.57£-05 SR90+D 2.92E-02 0. l .85E-03 0. 0. 8.03E-03 9.36E-05 SR9l+D 6.83E-08 0. 2.47£-09 0. 0. 3.76£-05 5.24£-05 SR92+D 7.50E-09 0. 2.79£-10 0. 0. 1. 70£-05 l.OOE-04 Includes a 50% increase to account for percutaneous transpiration .

35 Rev 7 01/01/93

; .J

~ ~~ i : ~~

,l.I llil~[~J!llia.E..AB._fLAll..I QEf~llLQfil__ru,_cuLl\llQtt_f1.At!!Jt'J, Rov1s1on 7 IADLE l1Z (~oat1nu~d)

INFANT INHALATION DOSE COHHITHENT FACTORS (HREH,SOY PER PC! INHALED IN FIRST YR(

ISOTOPE BONE LIVER TOTAL BODY THY OID KIDNEY LUNG Gl-L I Y90 2.35E-06 0. 6.30E-08 0. 0. 1.92£-04 7.43E-05 Y91M+O 2.91E-10 0. 9.90E-l2 o. 0. 1.99£-06 l.68E-06 Y91 4.20E-04 0. l.12E-05 0. 0. 1.75£-03 5.02£-05 Y92 1.17E-08 0. 3.29E-10 0. 0. 1.75£-05 9.04£-05 Y93 l.07E-07 0. 2.91E-09 . o. 0. 5.46£-05 1.19£-04 ZR93t0 2.24E-04 9.51E-05 6.18E-05 o. 3.19E-04 1.37£-03 1.48£-05 ZR95t0 8.24E-05 1.99[-05 1. 45E-05 0. 2.22£-05 1.25£-03 1. SSE-OS ZR97t0 1. 07E-07 1.83£-08 8.36E-09 0. l.8SE-08 7.88E-05 1. 00£-04 NB93M 1.38E-04 :L 59E-05 l.15E-05 0. 3.68E~OS 2.09£~04 2.47£-06 NB95 l.12E-05 4.59£-06 2.70E-06 o. 3.37E-06 3.42E-04 9.0SE-06 NB97 2.44E-10 S.21E-11 1.88£-11 0. 4.07E-ll 2.37E-06 1. 92£-05 M093 0. 6.46[-06 2.22E-07 0. 1. 54£-06 3.40£-04 3.76£-06 M099+0 o. 1.18£-07 2.31£-08 0. 1.89£-07 9.63£-0S 3.48E-05 TC99M 9.98£-13 2.06E-12 2.66£-11 0. 2.22E-~l 5.79£-07 1.45£-06 TC99 2.09E-07 2.68[-07 8.85[-08 0. 2.49E J6 i:L 77£-04 7.82£-06 TClOl 4.6SE-14 S.88£-14 5.80E-13 0. 6.99£-13 4.17£-07 6.03£-07 RU103t0 1. 44E-06 0. 4.85E-07 0. 3.03E-06 3.94£-04 1.15£-0S RU105tD 8.74£-10 0. 2.93E-10 0. 6.42£-10 l.12E-05 3.46£-0S RU106tD 6.20E-05 o. 7.77£-06 o. 7.61£-0S 8.26E-03 l. l 7E-04 RHlOS 8.26E-09 5.41£-09 3.63E-09 0. 1.50£-08 2.0BE-OS 1. 37E-05 PD107 0. 4.92E-07 4. llE-08 0. 2.75£-06 6.34E-05 7.33£-07 P0109 0. 3.92£-09 1.05£-09 0. 1.28E-08 l.68E-OS 2.8SE-OS AGllOMtD 7.13E-06 s .16£-06 3.S7E-06 0. 7.80£-06 2.62£-03 2.:i6E-05 AGlll 3.75£-07 1. 45£-07 7.75£-08 0. 3.0SE-07 2.06£-04 3.02£-05 CD113M 0. 6.67E-04 2.64E-05 0. 5.SOE-04 1.40E-03 1. 65£-05 CD115M 0. l.73E-04 6.19E-06 0. 9.41£-05 l.47E-03 5.02£-05 SN123 2.09E-04 4.21£-06 7.28E-06 4.27E-06 0. 2.22£-03 4.0SE-05 SN125tD l.OlE-05 2.SlE-07 6.00E-07 2.47E-07 0. 6.43£-04 7.26£-05 SN126+D 8.30E-04 1.44£-05 3.52E-OS 3.84E-06 0. 4.93£-03 1. 6SE-05 SB124 2.71£-05 3.97E-07 8.56E-06 7. lSE-08 0. l.89E-03 4.22E-05 SB125+D 3.69E-05 3.41£-07 7.78E-06 4.4~E-08 0. l. l 7E-03 1. OSE-05 SB126 3.08£-06 6.0lE-08 l. llE-06 2.3SE-08 0. 6.88E-04 5.33E-OS SB127 2.82E-07 5.04£-09 8.76E-08 3.60£-09 0. 1. S4E-04 3.78£-0S TE125M 3.40£-06 l.42E-06 4;70E-07 1.16£-06 o: 3.19£-04 9.22E-06 TE127M+D l.19E-05 4.93E-06 1.48E-06 3.48£-06 2.68E-OS 9.37E-04 1. 95£-05 TE127 1. 59E-09 6.81E-10 3.49£-10 1.32£-09 3.47E-09 7.39£-06 1. 74£-05 TE129M+D 1.0lE-05 4.3SE-06 1. 59£-06 3.91£-06 2.27E-OS 1. 20£-03 4.93£-05 TE129 5. 63E-11 2.48E-ll 1.34E-11 4 .82£-11 l.25E-10 2 .14£:-06 1.88£-0S TE131M+D 7.62E-08 3.93£-08 2.S9E-08 6.38£-08 1.89F.-07 1.42E-04 8.SlE-05 TE13l+D 1.24E-11 5.87E-12 3.57E-12 l.13E-ll 2.85E-11 1.47E-06 5.87E-06 TE132+D 2.66E-07 1.69£-07 1. 26E-07 1. 99E-07 7.39E-07 2.43E-04 3.15£-05 TE133M+D 6.13E-11 3.59E-ll 2. 74E-ll S.52E-ll I. 72£-10 3.92E-06 1. S9E-05 TE134tD 3.18E-ll 2.04E-11 1.68E-ll 2.91£-11 9. 59E-ll 2.93£-06 2.S3E-06

'- 1129 2.loE-05 1. 59E-05 l.16E-05 l.04E-02 l.88E-05 o. 2.12E-07 t' -::'( ,, 1130 4.54E-06 9.9~E-06 3.98E-06 l.14E-03 1.09E-05 0. 1. 42E-06

. :-;1 1131+0 2.71E-05 3.17E-05. I.40E-05 1.06£-02 3.70E-05 0. 7.56E-07

\

~ '.~* *.

rf

~*

,,\'.\

36 Rev 7 01/01/93

MWpm!JlitM Rev1s ion 7 TABLE 1.7 (continued)

INFANT INHALATION DOSE COHHITHENT FACTORS (HREH/50Y PER PCI INHALED IN FIRSl YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI I 132 l.21E-06 2.53E-06 8.99E-07 l.21E-04 2.82E-06 0. l.36f-06 1133+0 9.46E-06 l.37E-05 4.00E-06 2.54E-03 l.60E-05 0. l.54E-06 1134 6.58£-07 l.34E-06 4.75E-07 3.18E-05 l.49E-06 0. 9.21E-07 1135+0 2.76E-06 5.43E-06 l.98E-06 4.97E-04 6.05E-06 0. l.31E-06 XE131M 0. o. 0. 0. 0. 6.77E-09 0.

XE133M 0. 0. 0. 0. 0. 8.89[-09 0.

XE133 o. o. 0. 0. 0. 7.41E-09 0.

XE135M o. o. o. 0. 0. 8.05E-09 0.

XE135 0. 0. 0. 0, 0. 1.80E-08 0.

XE137 o. 0. 0. O. 0. 8.30E-08 0.

XE138t0 0. 0. 0. 0. o. 9.78£-08 0.

CS134M+D l.32E-07 2.lOE-07 l.llE-07 0. 8.SOE-08 2.00E-08 1.16E-07 CS134 2.83£-04 5.02E-04 5.32E-05 O. 1.36E-04 5.69E-05 9.53E-07 CS135 l.OOE-04 8.66£-05 4.73E-06 0. 2.58E-05 1.0lE-05 2.18£-07 CS136 3.45E-05 9.61E-05 3.7BE-05 O. 4.03E-05 ~.40E-06 l.02E-06 CS137tD 3.92E-04 4.37E-04 3.25E-05 O. l.23E-04 5.09E-05 9.53E-07 CS138 3.61E-07 5.58E-07 2.84E-07 0. 2.93E-07 4.67E-08 6.26E-07 CS139+0 2.32E-07 3.03E-07 l.22E-07 O. l.65E-07 2.53E-08 l.33E-08 BA139 l.06E-09 7.03E-13 3.07E-ll 0. 4.23E-13 4.25E-06 3.64E-05 BA140+D 4.00E-05 4.00E-08 2.07E-06 O. 9.59E-09 l.14E-03 2.74E-05 BA14ltD l.12E-10 7.70E-14 3.55E-12 0. 4.64E-14 2.12E-06 3.39E-06 BA142+0 2.84E-ll 2.36E-14 l.40E-12 0. l.36E-14 l.llE-06 4.95E-07 LA140 3.61E-07 l.43E-07 3.68E-08 O. 0. l.20E-04 6.06E-05 LA141 4.85E-09 l.40E-09 2.45E-10 0. 0. l.22E-05 5.96E-05 LA142 7.36E-10 2.69E-10 6.46E-ll 0. 0. 5.87E-06 4.25E-05 CE141 l.98E-05 l.19E-05 l.42E-06 0. 3.75E-06 3.69E-04 l.54E-05 CE143+D 2.09E-07 1~38E-07 l.58E-08 0. 4.03E-08 8.30E-05 3.55E-05 CE144+D 2.28E-03 8.65E-04 l.26E-04 0. 3.84E-04 7.03E-03 l.06E-04 PR143 l.OOE-05 3.74E-06 4.99E-07 0. l.41E-06 3.09E-04 2.66E-05

, . PR144 3.42E-ll l.32E-11 l.72E-12 0. 4.80E-12 l.15E-06 3.06E-06 ND147+D 5.67E-06 5.81E-06 .3~57E-07 0. 2.25E-06 2.30E-04 2.23E-05 PM147 3.91E-04 3.07E-05 l.56E-05 0. 4.93E-05 4.55E-04 5.75E-06 PM148MtD 5.00E-05 l.24E-05 9.94E-06 0. l.45E-05 l.22E-03 3.37E-05 PM148 3.34E-06 4.82E-07 2.44E-07 O. 5.76E-07 3.20E-04 6.04E-05 PM149 3.lOE-07 4.08E-08 l.78E-08 O. 4.96E-08 6.50E-05 3.0lE-05 PM151 7.52E-08 l.lOE-08 5.55E-09 O. l.30E-08 3.25E-05 2.58E-05 SM151 3.38E-04 6.45E-05 l.63E-05 0. 5.24E-05 2.98E-04 3.46E-06 SM153 l.53E-07 l.18E-07 9.06E-09 0. 2.47E-08 3.70E-05 l.93E-05 EU152 7.83E-04 l.77E-04 l.72E-04 O. 5.94E-04 l.48E-03 9.88E-06 EU154 2.96E-03 3.46E-04 2.45E-04 0. l.14E-03 3.05E-03 2.84E-05 EU155 5.97E-04 5.72E-05 3.46E-05 0. l.58E-04 5.20E-04 5.19E-05 EU156 l.56E-05 9.59E-06 l.54E-06 O. 4.48E-06 6.12E-04 4.14E-05 TB160 l.12E-04 O. l.40E-05 O. 3.20E-05 l.llE-03 2.14E-05 H0166M l.45E-03 3.07E-04 2.SIE-04 0. 4.22E-04 2.0SE-03 l.65E-05 Wl81 4.86E~08 l.46E-08 l.67E-09 o. 0. 1.33E-05 2.63E-07 Wl85 *. l.57E-06 4.83E-07 5.58E-08 O. 0. 4.48E-04 l.12E-05 Wl87 9.26E-09 6.44E-09 2.23E-09 0. 0. 2.83E-05 2.54E-05 37 Rev 7

. - . '.~ *.

01/01/93

~.~.: *~ ;

j *~ . ?. '*. ,.

"""J

&?'¥Ila& DPT fN1-~k>§$141Wlifibli&Ut£Wbi.$Wi'iililliWi?IDikw.R~:';

~tw t

}

'1 .* f'

,\ *.i :~ I e..>lli~Mlf.~_JHJ~UA!L.P_L.AJH Qff.s.JilJlQ S.L CAl CU!J\I1Qtl.J1AHUA.L

Rcvis1on 7 IAD1.E__lLL_L~t1nuedl INFANT INHALATION DOSE COHHITHENT FACTORS (HREH,50Y PER PCJ INHALED IN FIRS1* YRl ISOTOPE BONE LIVER TOTAL BODY THY OID KIDNEY LUNG GJ-L I

" PB210+0 8.62E-02 2.02[-02 3.43£-03 0. 6.85[-02 l.76E-Ol 3.79(-05 81210+0 o. 1.33[-05 1. lSE-06 0. l.03E-04 9.96(-03 3.27£-05

" P0210 2.98E-OJ S.63E-03 7.12E-04 0. 1.30E-02 2.40[-0l 4.36£-05 RN222+0 0. 0. 0. o. 0. 9.88£-06 o.

RA223+D 1. 56E-03 2.26E-06 3.12E-04 0. 4.16£-05 2.25£-01 3.04E-04

~.~ RA224+D 1. 77E-0-1 4.00E-07 3.54E-OS 0. 7.30£-06 7.91£-02 3.42£-04 RA225+0 2.57E-03 2.88E-06 5.13£-04 0. 5.31E-OS 2.57£-01 2.87E-04 RA226+0 2.48E-01 l.46E-OS 2.05E-Ol 0. 2.94E-04 7.83E-Ol 3.05£-04 J

!* - RA228+D 1.60£-01 7.61E-06 l .BOE-01 0. 1.53£-04 1.09£-00 5.19£-05 AC225 3.69£-03 4.72E-03 2.48E-04 0. 3.49£-04 l.96E-Ol 2.71E-04 AC227+0 5.29E+OO 8.76E-Ol 3.28£-01 0. l. B6E-01 l.62E+OO 5.27E-05

_, TH227+0 1. 82£-03 3.C3E-05 5.24£-05 0. l.13£-04 3.27£-01 3.53£-04

{

TH228+0 8.46£-01 l. lOE-02 2.86£-02 0. 5.61£-02 4.65E+OO 3.62£-04

- TH229 1. 34E+Ol 1.82£-01 6.62£-01 o. 8.99E-Ol l.22E+Ol 3.29£-04 TH230 3.46E+OO 1.79£-01 9.65£-02 0. 8.82£-01 2.18£+00 3.87£-05 TH232+0 3.86E+OO 1. 53£-01 2.29£-01 0. 7.54£-01 2.09E+OO 3.29£-05 THl34 1. 33£-05 7 .17£-07 3.84£-07 0. 2.70£-06 1. 62£-03 7.40£-05 PA23l+D 9. lOE+OO 3.00E-01 3.62E-Ol 0. l.62E+OO 3.85£-01 4.61£-05 PA233 6.84£-06 1.32£-06 1.19£-06 o. 3.68£-06 2.19E-04 9.04£-06 U232+D 2.57£-01 o. 2.13E-02 o. 2 AOE-02 l.49E+OO 4.36E-05 U233+D 5.44£-02 o. 3.83£-03 0. 1. 09£-02 3.56£-01 4.03E-05 U234 5.22E-02 0. 3.75£-03 0. 1.07£-02 3.49E-Ol 3.95E-05 U235+D 5.0lE-02 o. 3.52£-03 0. l.OlE-02 3.28E-Ol 5.02E-05 U236 5.0lE-02 0. 3.60£-03 0. 1.03£-02 3.35£-01 3. 71E-05

' U237 3.25£-07 o. B.65£-08 0. 8.08£-07 9.13E-05 1.31£-05 U238+D 4.79£-02 0. 3.29£-03 o. 9.40£-03 3.06£-01 3.54£-05 NP237+0 3.03£+00 2.32£-01 1.26£-01 0. 7.69£-01 3.49E*Ol 5.lOE-05 2.67£-06 6.73£-08 4 .16£-08 o.

='<,

~;.*

NP238 1.47£-07 9.19£-05 2.58£-05 NP239 2.65£-07 2.37£-08 l.34E-08 0. 4.73E-08 4.25E-05 1. 78£-05 PU238 5.02E+OO 6.33E-Ol l.27E-Ol 0. 4.64E-Ol 9.03E-Ol 4.69£-05 PU239 5.50E+OO 6.72E-Ol l .34E-Ol 0. 4.95E-Ol 8.47E-Ol 4.28E-05 PU240 6.49E+OO 6. 71£-01 1.34£-01 o. 4.94E-Ol 8.47£-01 4.36E-05 PU24l+D 1. SSE-01 6.69E-03 3. l lE-03 0. 1. lSE-02 7.62£-04 8.97E-07 PU242 5~09E+OO 6.47£-01 l.29E-Ol 0. 4.77£-01 8.15£-01 4.20£-05 PU244 5.95E+OO 7.40£-01 l.48E-Ol 0. 5.46E-Ol 9.33E-Ol 6.26£-05 AM241 1. 84E+OO 8.44£-01 1.31£-01 0. 7.94E-Ol 4.06E-Ol 4.78£-05 AM242M 1. 90E+OO 8.24£-01 1.35£-01 0. 8.03E-Ol l.64E-Ol 6.0lE-05 AM243 l.82E+OO 8. lOE-01 1. 27E-Ol 0. 7. 72£-01 3.85£-01 5.60E-05 CM242 8.58£-02 7.44£-02 5.70E-03 0. l.69E-02 2.97£-01 5.lOE-05

-ji CM243 l.73E+OO 7.94£-01 l.06E-Ol 0. 3.91E-Ol 4.24E-Ol 5.02£-05 CM244 l.43E+OO 7.04E-Ol 8.89E-02 o. 3. 21£-01 4.08E-Ol 4.86E-05 CM245 2.26E+OO 8.SOE-01 l.36E-Ol o. 5.23E-Ol 3.92£-01 4.53£-05 CM246 2.24E+OO 8.79£-01 1.36£-01 0. 5.23£-01 3.99£-01 4.45E-05 CM247+D 2.J8E+OO 8.64£-01 1.33£-01 0. 5.15E-Ol 3.92E-Ol 5.85E-05 CM248 l .82E+Ol 7.12E+OO l.lOE+OO o. 4.24E+OO 3.23E+OO 9.43E-04 CF252 4.26E+OO o. 1. OlE-01 0. 0. 1.37E+OO l.SSE-04 38 Rev 7

-**1; 01/01/93

'~.' .

.::*-- ~* ' '

'* ~ ' (', ."'

I '1 l..* .1 Rov1s1on 7 TABLE 1.7 (~Qllt~l CHILD INHALATION DOSE COMMITMENT FACTORS (HREM/50Y PER P~I INHALED IN FIRST i~)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-lll H3* 0. 3.04E-07 3.04E-07 3.04E-07 3.04(-07 3.04E-07 3.04E-07 BElO 8.43E-04 9.83E-OS 2.12E-05 0. 0. 7.41E-04 l.72E-05 Cl4 9.70E-06 1.82£-06 1.82£-06 1.82£-06 l.82E-06 1.82£-06 l.82E-06 N13 2.33E-08 2.33£-08 2.33E-08 2.33£-08 2.33E-08 2.33£-08 2.33E-08 FIB l.88E-06 0. l.85E-07 0. 0. 0. 3.37E-07 NA22 4.41E-05 4.41£-05 4.41E-05 4.41E-05 4.41E-05 4.41E-05 4.41E-05 NA24 4.35£-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P32 7.04E-04 3.09E-05 2.67E-05 0. 0. 0. l.14E-05 AR39 0. 0. 0. 0. 0. 4.89E-09 0.

AR41 0. O. 0. 0. 0. l.68E-OB 0.

CA41 7.06E-05 0. /.ZOE-06 0. 0. 7.21E-02 2.94E-07 SC46 l.97E-04 2.ZOE-04 l.04E-04 0. 2.39E-04 0. 2.45£-05 CRSl 0. O. 4.lZE-08 2.JlE-08 6.57E-09 4.59£-06 2.93E-07 MN54 0. l.16E-05 2.57E-06 0. 2.71£-06 4.26£-04 6.19E-06 MN56 0. 4.48E-10 8.43E-11 0. 4.52E-10 3.SSE-06 3.33E-05 FESS l.28E-05 6.80E-06 2.lOE-06 0. 0. 3.00E-05 7.75E-07 FES9 5.59E-06 9.04E-06 4.SlE-06 0. 0. 3.43E-04 l.91E-05 C057 O. 2.44E-07 2.88E-07 0. 0. l.37E-04 3.58E-06 COSS 0. 4.79E-07 8.SSE-07 0. 0. 2.99E-04 9.29E-06 C060 0. 3.55E-06 6.12E-06 0. 0. l.91E-03 2.60E-05 NI59 l.66E-05 4.67E-06 2.83£-06 0. 0. 2.73E-05 6.29E-07 NI63 2.22E-04 l.25E-0S 7.56E-06 0. 0. 7.43E-05 l.71E-06 NI65 8.0BE-10 7.99E-ll 4.44E-ll 0. 0. 2.21E-06 2.2?E-05 CU64 0. 5.39E-10 2.90E-10 0. 1.63E-09 2.59E-06 9.92E-06 ZN65 l.15E-05 3.06£-05 1.90£-05 0. 1.93£-05 2.69E-04 4.41E-06 ZN69M+D 4.26E-09 7.28£-09 8.59E-10 0. 4.22E-09 7.36E-06 2.71E-05 ZN69 l.81E-ll 2.61E-11 2.41E-12 0. l.58E-ll 3.84E-07 2.75E-06 SE79 0. l.23E-06 2.60E-07 0. 1.71E-06 l.49E-04 3.43E-06 BR82 0. 0. 5.66E-06 0. 0. 0. O.

BR83+D 0. 0. l.28E-07 0. 0. 0. 0.

BR84 0. 0. l.48E-07 0. 0. 0. 0.

BR85 0. 0. 6.84E-09 0. 0. 0. 0.

KR83M 0. 0. 0. 0. 0. l.22E-09 0.

KRBSM 0. 0. 0. 0. 0. 6.58E-09 0.

KR85 O. 0. 0. 0. 0. 5.66E-09 0.

KR87 0. 0. 0. 0. 0. 3.38E-08 0.

KR88+D 0. 0. 0. 0. 0. 6.99E-08 0.

kR89 0. 0. 0. 0. 0. 4.55E-08 0.

RB86 0. 5.36E-05 3.09E-05 0. 0. 0. 2.16E-06 RB87 0. 3.16E-05 1.37E-05 0. 0. 0. 2.96E-07 RB88 O. 1.52E-07 9.90E-08 0. 0. 0. 4.66E-09 RB89+0 0. 9.33E-08 7.BJE-08 0. 0. 0. 5.llE-10 SR89+D l.62E-04 0. 4.66E-06 0. 0. 5.83E-04 4.52E-05 SR90+D 2.7~E-02 0. l.74E-03 0. 0. 3.99E-03 9.28E-05 SR91+0 3.28E-08 0. l.24E-09 0. 0. l.44E-05 4.70E-05 SR92+D 3.54E-09 0. l.42E-10 0. 0. 6.49E-06 6;55E-05

Includes a 50% increase to account for percutaneous transpiration.

39 Rev 7 01/01/93

,~{X;(_-.:*-*

PA!...iSt'JJE.S_.liU~itAfLPLAJU 9£D1I.l_Q9~.LCA.LC.IJll\IlQ1Li1A_NJJA!.

Rev1s1on 7 IABLE L.Lfc;ontdl CHILO INHALATION DOSE COHHITHENT FACTORS ~HREH~50Y PER PCI INHALED IN FIRST YKL

~"' - ISOTOPE BONE LIVER TOTAL BOO TH ROJO KIDNEY LUNG GI- LI Y90 l.llE-06 0. 2.99E-08 0. 0. 7.07E-05 7.24E-05 Y91M+D l.37E-10 0. 4.98E-12 0. 0. 7.GOE-07 4.64E-07

f.

Y91 2.47E-04 0. 6.59E-06 0. 0. 7. lOE-04 4.97E-05

~ Y92 5.50E-09 o. l. 57E-10 0. o. 6.46E-06 6.46E-05

~_' Y93 5.04E-08 0. l.38E-09 0. 0. 2.0lE-05 l.05E-04 ZR93+D 2.07[-04 7.BOE-05 5.55E-05 0. 3.00E-04 7. lOE-04 l.47E-05 ZR95+0 5.13E-05 l.13E-05 l.OOE-05 0. l.61E-05 6.03E-04 l. 65E-05 ZR97+0 5.07[-08 7.34E-09 4.32[-09 0. l.OSE-08 3.06E-05 9.49[-05 NB93M 1. 27E-04 3.17E-05 l.04E-05 0. 3.44E-05 l.04E-04 2A5E-06 NB95 6.35E-06 2.48[-06 l . 77E-06 0. 2.JJE-06 1. 65£-04 1. OOE-05 NB97 l.16E-10 2.08£-11 9.74E-12 0. 2.31£-11 9.23£-07 7.52E-06 M093 0. 3.76E-06 1.35£-07 0. l.06E-06 l.70E-04 3.78E-06 M099+D 0. 4.66E-08 l.15E-08 0. 1.06E-07 3.66E-05 3.42£-05 TC99M* 4.81E-13 9.41E-13 l.56E-ll 0. l.37E-11 2.57£-07 1.30£-06 TC99 1.34£-07 1. 49£-07 5.35E-08 0. 1.75£-06 3.37£-04 7.75E-06 TClOl 2.19£-14 2.30£-14 2.91£-13 0. 3.92£-13 1. 58£-07 4.41£-09 RU103+0 7.55E-07 0. 2.90[-07 0. 1. 90£-06 1. 79£-04 l.21E-05 RU105+0 4.13E-10 0. l.50E-10 0. 3.63E-10 4.30E-06 2.69£-05 RU106+0 3.68E-05 o. 4.57E-06 0. 4.97E-05 3.87£-03 1.16£-04 RH105 3.91[-09 2.IOE-09 l.79E-09 0. 8.39E-09 7.82E-06 l .33E-05 PD107 0. 2.65E-07 2.51E-08 0. 1. 97E-06 3.16E-05 7.26E-07 PD109 o. l.48E-09 4.95E-10 0. 7.06E-09 6.16E-06 2.59E-05 AGllOM+D 4.56E-06 3.08E-06 2.47E-06 0. 5.74£-06 l.48E-03 2.71E-05 AGlll 1.81£-07 5.68[-08 3.75E-08 0. 1. 71E-07 7.73E-05 2.98E-05 CD113M 0. 4.93£-04 2 .12£-05 o. 5.13E-04 6.94E-04 1.63E-05 CD115M 0. 7.88E-05 3.39E-06 0. 5.93E-05 5.86E-04 4.97E-05 SN123 1. 29E-04 2.14E-06 4. l9E-06 2.27E-06 0. 9.59E-\l4 4.05E-05 SN125+0 4.95E-06 9.94E-08 2.95E-07 1. 03E-07 0. 2.43E-04 7.17E-05 SN126+0 6.23E-04 1. 04E-05 2.36E-05 2.84E-06 0. 3.02E-03 1. 63E-05

$8124 1. 55E-05 2.00E-07 5.41E-06 3.41E-08 o. 8.76E-04 4.43E-05

~~ SB125+0 2.66E-05 2.0SE-07 5.59E-06 2.46':-08 0. 6.27E-04 1.09E-05 1 SB126 1. 72E-06 2.62[-08 6.16E-07 l.OOE-08 0. 2.86E-04 5.67E-05

~~ $8127 1.36£-07 2.09E-09 4.70E-08 l.SIE-09 0. 6.17E-05 3.82E-05

' TE125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0. 1.29E-04 9.13E-06 TE127M+D 6.72E-06 2.31E-06 8.16E-07 l.64E-06 1. 72E-05 4.00E-04 1. 93E-05 TE127 7.49E-10 2.57E-10 1.65£-10 5.30E-10 1. 91E-09 2.71E-06 1.52£-05 TE129M+O 5.19E-06 1.85E-06 8.22E-07 l.71E-06 1.36E-05 4.76E-04 4.91E-05 TE129 2.64E-ll 9.45E-12 6.44E-12 l.93E-11 6.94E-11 7.93E-07 6.89E-06 TE131M+D 3.63E-08 1.60E-08 l.37E-08 2.64E-08 1. 08E-07 5.56E-05 8.32E-05 TE13l+D 5.87E-12 2.28E-12 l.78E-12 4.59E-12 1.59E-ll 5.55E-07 3.60E-07 TE132+0 l .30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 l.02E-04 3. 72E-05 TE133M+O 2.93E-11 1.51E-11 l.50E-ll 2.32E-ll 1.0lE-10 1.60E-06 4.77E-06 TE134+0 1.53E-ll 8.81E-12 9.40E-12 l.24E-ll 5. 71E-11 1. 23E-06 4.87E-07 1129 1. O~E-05 6.40E-06 5. 71E-06 4.28E-03 1. 08E-05 o. 2.15E-07 1130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0. l.38E-06 1131+0 l.30E-05 l.30i-05 7.37E-06 4.39E-03 2.13E-05 0. 7.68E-07 40 Rev 7 01/01/93

i I ;. (~ l ; ~ ' *~* 1 . ' . .

) U!.llAUE.S_JiU~L.EAR ..J~l"tU QffS ITE POSE CALCU1AilQtLM.A_N.!J1'J.

le J;

l Rov1s1on 7 1

J TABLE 1.7 (contd)

-l CHILD INHALATION DOSE COMHITHENT FACTORS ~HREH~50Y PER PCI INHALED IN FIRST Yk}

] ISOTOPE 1132 BONE LIVER TOTAL BOD TH ROJO 5.72E-07 1.10£-06 5.07£-07 5.23£-05 1.69£-06 0.

KIDNEY LUNG Gl-LLI 8.65E-07 1133+0 4.48£-06 5.49£-06 2.08£-06 1.04£-03 9.13£-06 0. l.48£-06

1. 37E-05 8.92£-07 o.

'.I 1134 3.17£-07 5.84£-07 2.69E-07 2.SSE-07 ll iI 1135+0 XE131M XE133M XE133 XE135M

1. 33£-06 2.36E-06 0.

0.

o.

0.

o.

0.

o.

1.12£-06 2.14£-04 3.62£-06 0.

o.

0.

o.

0.

o.

0.

o.

l. 20E-06 3.30E-09 0.

4.36E-09 0.

3.66E-09 0.

4.48E-09 0.

'l j XE135 0. 0. 0. o. o. 9.09E-09 0.

.i

\

XE137 o. 0. 0. 0. o. 4.07E-08 0.

j XE138+0 0. 0. 0. 0. 0. 5. IZE-08 0.

t l

CS134M+D 6.33E-08 8.92E-08 6.12E-08 0. 4.94E-08 8.35E-09 7.92E-08 CS134 1. 76E-04 2.74£-04 6.07E-05 o. 8.93£-05 3.27£-05 l.04£-06 CS135 6.23E-05 4.13£-05 4.45£-06 o. 1. 53£-05 5.22£-06 2.17£-07 CS136 l.76E-05 4.62E-05 3.14£-05 0. 2.58E-05 3,93E-06 l.13£-06 CS137+0 2.45£-04 2.23E-04 3.47E-05 0. 7.63E-05 2.81£-05 9.78£-07 CS138 l.71E-07 2.27£-07 l.SOE-07 0. 1.68E-07 1.84£-08 7.29E-08 CS139+0 1.09E-07 1.15£-07 5.80E-08 0. 9.08£-08 9.36E-09 7.23E-12 1*

BA139 4.98£-10 2.66£-13 1.45£-11 0. 2.33£-13 1. 56£-06 1. 56£-05 BA140+0 2.00E-05 1.75£-08 1.17E-06 0. 5. 71E-09 4. 71£-04 2.75E-05 BA141+D 5.29£-11 2.95£-14 1.72£-12 0. 2.56£-14 7.89£-07 7.44£-08 BA142+0 1. 35£-11 9.73£-15 7.54£-13 o. 7.87£-15 4.44£-07 7.41£-10 LA140 1. 74£-07 6.08£-08 2.04£-08 0. 0. 4.94£-05 6 .10~-05 LA141 2.28£-09 5.31£-10 1.15£-10 0. 0. 4.48£-06 4.37E-05 LA142 3.50£-10 l. llE-10 3.49E-ll 0. 0. 2.35£-06 2.05E-05 CE141 1. 06£-05 5.28£-06 7.83E-07 0. 2.31£-06 1.47£-04 1.53£-05 CE143+0 9.89£-08 5.37£-08 7.77£-09 0. 2.26£-08 3.12E-O~ 3.44£-05 CE144+0 1.83£-03 5.72£-04 9.77£-05 0. 3 .17£-04 3.23£-03 1.05£-04 PRl43 4.99£-06 1.50£-06 2.47£-07 o. 8. llE-07 1.17£-04 2.63£-05 PR144 l.61E-ll 4.99£-12 8. lOE-13 0. 2.64£-12 4.23£-07 5.32£-08 ND147+0 2.92£-06 2.36£-06 1.84£-07 0. 1.30£-06 8.87£-05 2.22£-05 PM147 3.52£-04 2.52E-05 1.36£-05 0. 4.45£-05 2.20£-04 5.70£-06 PM148M+D 3.31£-05 6.55£-06 6.55£-06 o. 9.74£-06 5.72£-04 3.58£-05 PM148 1.61£-06 1.94£-07 1. 25E-07 o. 3.30£-07 1.24£-04 6.0lE-05 PM149 l.47E-07 1.56E-08 8.45E-09 0. 2.75E-08 2.40E-05 2.92E-05 PM151 3.57E-08 4.33E-09 2.82E-09 0. 7.35E-09 l.24E-05 2.50E-05 SM151 3.14E-04 4.75E-05 l.49E-05 0. 4.89E-05 1.48£-04 3.43£-06 SMi53 7.24E-08 4.51E-08 4.35E-09 0. 1.37E-08 l.37E-05 1.87£-05 EU152. 7.42E-04 l.37E-04 l.61E-04 o. 5.73E-04 9.00E-04 l.14E-05 EU154 2.74E-03 2.49E-04 2.27E-04 0. l.09E-03 l.66E-03 2.98E-05 EU155 5.60E-04 4.0SE-05 3.18E-05 0. l.51E-04 2.79E-04 5.39£-05 EU156 7.89£-06 4.23£-06 8.75E-07 o. 2.72E-06 2.54E-04 4.24£-05 TB160 7.79E-05 o. 9.67E-06 0. 2.32£-05 5.34£-04 2.28E-05 H0166M l.34E-03 2.81E-04 2.37E-04 o. 4.0lE-04 l.lJE-03 1.63£-05 W181 2.66E-08 6.52E-09 8.99E-10 0. 0. 5. 71E~06 2.61£-07 Wl85 8.31E-07 2.08E-07 2.91E-08 o. o. l.86E-04 1. llE-05 Wl87 4.41E-09 2.61E-09 1.17E-09 o. 0. l. llE-05 2.46£-05

- L* .. *..- 41 Rev 7

.... 01/01/93

't;c

~- ..* ' .. ,

. \.

1

~ . . .; 1. \. *,

eAUSAilE~!!UCillR.J.LtWJ:

le Q£B J TE DO SE -'AL.~JJhAIJJHLl't~!lAl Rev1s1on 7 IADLE l1Z (~Qot!ll CHILD INHALATION DOSE COMMITMENT FACTORS ~MREH~50Y PER PCI INHALED IH FIRST i~L ISOTOPE BONE LIVER TOTAL BOD TH ROID KIDNEY LUNG GI- LI PB210+0 8.03E-02 l.85E-02 3.lBE-03 0. 6.31E-02 8.74E-02 3.75E-05 81210+0 0. 5.llE-06 5.65E~07 0. 5.76E-05 3.70E-03 3.21E-05 P0210 l.70E-03 2.76E-03 4.09E-04 0. 8.85E-03 l .OSE-01 4.32E-05 RN222+D o. 0. 0. 0. 0. 4.82E-06 0.

RA223+0 7.69E-04 8.89E-07 1. 54E-04 0. 2.36E-05 8.48E-02 3.00E-04 RA224+0 8.44E-05 I. 53E-07 1.69E-05 o. 4.06E-06 2.92E-02 3.34£-04 RA225+D 1.28E-03 l.14E-06 2.56E-04 o. 3.02E-05 9.74E-02 2.84E-04 RA226+0 2.34E-Ol 7.66E-06 1. 92E-Ol o. 2.03E-04 3.90£-01 3.02E-04 RA228+D 1.49E-Ol 3.94£-06 1.68E-Ol o. l.04E-04 5.37£-01 5.14E-05 AC225 1.81£-03 i.87E-03 i. 2i E-04 0. l.99E-04 7.37E-02 2.67E-04 AC227+D 4.96E+OO 8.05E-Ol 3.07E-Ol 0. 1. 77E-Ol 8.04E-Ol 5.22E-05 TH227+0 9.24E-04 1. 26E-05 2.67E-05 0. 6.67E-05 l.26E-Ol 3.49E-04 TH228+D 8.06E-Ol 1.04[-02 2.72E-02 0. 5.41E-02 3.34E+OO 3.59E-04 TH229 l. 28£+01 l.76E-Ol 6.JlE-01 0. 8.68E-Ol l.04E+Ol 3.27E-04 TH230 3.30E+OO l.73E-Ol 9.20E-02 0. 8.52E-Ol 1. 85E+OO 3.84E-05 TH232+0 3.68E+OO l.47E-Ol l.28E-Ol 0. 7.28E-Ol l. 77E+OO 3.27E-05 TH234 6.94E-06 3.07E-07 2.00E-07 0. 1.62E-06 6.31E-04 7.32E-05 PA231+D 8.62E+OO 2.86[-01 3.43E-01 o. l. 56E+OO 1. 92E-Ol 4.57E-05 PA233 4.14E-06 6.48E-07 7.25E-07 o. 2.38E-06 9. 77E-05 8.95E-06 U232+D 2.19E-Ol o. 1. 56E-02 0. 1.67E-02 7.42E-01 4.33E-05 U233+D 4.64E-02 o. 2.82E-03 0. 7.62E-03 1. 77E-Ol 4.00E-05 U234 4.46E-02 o. 2.76E-03 0. 7.47E-03 1. 74E-Ol 3.92E-05 U235+0 4.27E-02 o. 2.59E-03 0. 7.0lE-03 l.63E-Ol 4.98E-05 U236 4.27£-02 0. 2.65E-03 0. 7.16E-03 1.67E-Ol 3.67E-05 U237 1.57£-07 o. 4.17E-08 0. 4.53E-07 3.40E-05 1. 29£-05 U238+D 4.09£-02 0. 2.42E-03 0. 6.SSE-03 l.53E-Ol 3.SlE-05 NP237+0 2.88E+OO 2.21E-01 1.19E-01 0. 7.41E-Ol 1. 74[-(ll 5.06£-05 NP238 1.26£-06 2.56£-08 1. 97E-08 o. 8.16E-08 3.39£-05 2.50E-05 NP239 1. 26£-07 9.04E-09 6.35E-09 0. 2.63E-08 1. 57E-05 1. 73E-05 PU238 4. 77E+OO 6.05E-Ol 1.21E-Ol 0. 4.47E-Ol 6.0BE-01 4.65E-05 PU239 5.24E+OO 6.44E-Ol 1. 28E-Ol 0. 4.78E-Ol 5. 72E-Ol 4.24E-05 PU240 5.23E+OO 6.43E-Ol l.27E-Ol 0. 4. J7E.,.Ol 5.71E-Ol 4.33E-05 PU24l+D l.46E-Ol 6.33E-03 2.93E-03 0. l.lOE-02 5.06E-04 8.90E-07 PU242 4.85E+OO 6.20E-Ol 1. 23E-Ol 0. 4.60E-Ol 5.50E-Ol 4.16E-05 PU244 5.67E+OO 7. lOE-01 1.41E-01 0. 5.27E-Ol 6.30E-Ol 6.20E-05 AM241 1. 74E+OO 7.85E-Ol 1. 24E-Ol o. 7.63E-Ol 2.02E-01 4.73E-05 AM242M 1.79E+OO 7.65E-01 I.27E-Ol o. 7. 71E-01 8.14£-02 5.96E-05 AM243 I. 72E+OO 7.53E-Ol I. 20E-Ol 0. 7.42E-Ol I. 92E-Ol 5.55E-05 CM242 6.33E-02 4.84E-02 4.20E-03 o. l.34E-02 l.31E-Ol 5.06E-05 CM243 1. 61E+OO 7.33E-Ol 9.95E-02 o. 3.74E-Ol 2.lOE-01 4.98E-05 CM244 l.33E+OO 6.48E-Ol 8.31E-02 0. 3.06E-Ol 2.02E-Ol 4.82E-05 CM245 2.14E+OO 8.16E-Ol 1. 28E-Ol o. 5.03E-Ol I. 95E-Ol 4.49E-05 CM246 2.13E+OO 8.lSE-01 1.28E-Ol o. 5.03E-Ol I. 99E-Ol 4.41E-05 CM247+0 2.07E+OO 8.02E-Ol l.26E-Ol o. 4.95E-Ol l.95E-Ol 5.SOE-05 CM248 l.72E+Ol 6.61E+OO l.04E+OO 0. 4.08E+OO l.61E+OO 9.35E-04 Cf 252 3.92E+OO o. 9.33E-02 0. 0. 6.62E-Ol l.84E-04

.. 1.*

. 42 Rev 7 01/01/93

,i '.*r*' ,

. \, "", '

,*r "

PAU~/\QO_ HlJUft\I\ !~LA.NJ QffHIL _QQ)l .CAlCIJLM l Ort rtANVAL Rovislon 7 IM.LE l. 7 {tQn!Ql TEEN INHALATION DOSE COHHITHENT FACTORS (HREH/50V PER PCJ INHALED IN FIRST ~n)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-lll HJ* 0. l.59E-07 l.59E~07 l.59E-07 l.59E-07 l.59E-07 1.59£-07 BElO 2.78E-04 4.JJE-05 7.09E-06 0. 0. 3.84E-04 l.77E-05 Cl4 3.25E-06 6.09E-07 6.09E-07. 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Nl3 B.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 FlB 6.52E-07 0. 7.lOE-08 O. 0. 0. 3.89E-08 NA22 l.76E-05 l.76E-OS l.76E-05 l.76E-05 l.76E-05 l.76E-05 l.76E-05 NA24 l.72E-06 l.72E-06 l.72E-06 l.72E-06 l.72E-06 l.72E-06 l.72E-06 P32 2.36E-04 1.37E-05 8.95E-06 0. 0. 0. l.16E-05 AR39 0. 0. 0. 0. 0. 4.00E-09 0.

AR41 0. 0. 0. 0, 0. l.44E-08 0.

CA41 4.05E-05 0. 4.38E-06 0. 0. 1.0lE-01 3.0JE-07 SC46 7.24E-05 l.41E-04 4.18E-05 0. l.35E-04 0. 2.98E-05 CRSl 0. 0. l.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 MN54 0. 6.39E-06 l.OSE-06 O. 1.59E-06 2.48E-04 8.35E-06 MN56 0. 2.12E-10 3.lSE-11 0. 2.24F-10 l.90E-06 7.18E-06 FESS 4.18E-06 2.98E-06 6.93E-07 0. 0. l.55E-05 7.99E-07 FE59 1.99E-06 4.62E-06 1.79E-06 -o. 0. 1.91E-04 2.23E-05 C057 0. l.18E-07 l.15E-07 0. 0. 7.33E-05 3.93E-06 COSS 0. 2.59E-07 3.47E-07 0. 0. l.68E-04 1.19E-05 C060 0. l.89E-06 2.48E-06 0. 0. l.09E-03 3.24E-05 NIS9 5.44E-06 2.02E-06 9.24E-07 0. 0. l.41E-OS 6.48E-07 NI63 7.25E-05 5.43E~06 2.47E-06 0. 0. 3.84E-05 l.77E-06 NI65 2.73E-10 3.66E-ll 1.59E-ll 0. 0. l.17E-06 4.59E-06 CU64 0. 2.54E-10 l.06E-10 0. 8.0lE-10 l.39E-06 7.68E-06 ZN65 4.82E-06 l.67E-05 7.BOE-06 0. l.OBE-05 l.SSE-04 5.83E-06 ZN69M+D l.44E-09 3.39E-09 3.llE-10 0. 2.06E-09 3.92E-OG 2.14E-05 ZN69 6.04E-12 l.lSE-11 8.07E-13 0. 7.53E-12 1.98E-07 3.56E-08 SE79 0. 5.43E-07 8.71E-08 0. 8.13E-07 7.71E-05 3.53E-06 BR82 0. 0. 2.28E-06 0. 0. 0. 0.

BR83+D 0. 0. 4.JOE-08 0. 0. 0. 0.

BR84 0. O. 5. 41 E-08 0. 0. 0. 0.

BR85 0. O. 2.29E-09 0. 0. 0. 0.

KR83M 0. 0. 0. 0. 0. 9.97E-10 0.

KR85M 0. 0. 0. 0. 0. 5.46E-09 0.

KRBS O. 0. 0. 0. 0. 4.63E-09 0.

KR87 0. 0. 0. 0. 0. 2.82E-08 0.

KR88+D 0. 0. 0. 0. 0. 5.81E-08 0.

KR89 0. 0. 0. 0. 0. 3.85E-08 0.

RB86 0. 2.38E-05 1.0SE-05 0. 0. 0. 2.21E-06 RB87 0. l.40E-05 4.SBE-06 0. 0. 0. 3.0SE-07 RB88 0. 6.82E-08 3.40E-08 0. 0. 0. 3.65E-15 RB89+D 0. 4.40E-08 2.91E-08 0. 0. 0. 4.22E-17

't:*

SR89+0 5.43E-05 0. l.56E-06 0. 0. 3.02E-04 4.64E-05 SR90+0 l.~SE-02 0. 8.3SE-04 0. 0. 2.06E-03 9.56E-05

~ .(*,:._ SR9l+D l.IOE-08 0. 4.39E-10 0. 0. 7.59E-06 3.24E-OS SR92+0 l.19E-09 0. 5.0SE-11 0., 0. 3.43E-06 1.49E-05

Includes a 50% increase to account for percutaneous transpiration.

43 Rev 7 01/01/93

\ .

-l Revision 7 i TABLE 1.7 {contQl TEEN INHALATION DOSE COMMITMENT FACTORS (HREM/50Y PER PCI INHALED IN FIRST YRJ ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 3.73E-07 0. 1. OOE-08 0. 0. 3.66[-05 6.99£-05 Y91M+O 4.63E-ll 0. 1.77E-12 0. 0. 4.00E-07 3.77[-09 Y91 8.26£-05 0. 2. 21E-06 o. 0. 3.67E-04 5.llE-05 V92 l .84E-09 0. 5.36E-ll 0. o. 3.35E-06 2.06E-05 V93 1.69£-08 0. 4.65E-10 0. 0. 1. 04E-05 7.24E-05 ZR93+0 6.83£-05 3.38E-05 l.84E-05 0. l.16E-04 3.67E-04 1. 60E-05 ZR95+0 l.82E-05 5.73E-06 3.94E-06 0. 8.42E-06 3.36E-04 l.86E-05 ZR97+0 1. 72E-08 3.40E-09 l.57E-09 0. 5.ISE-09 1. 62E-05 7. 88E-05 NB93M 4.14E-05 1.36E-05 3.41E-06 0. 1.59E-05 5.36£-05 2.52E-06 NB95 2.12£-06 i.29E-06 7.0BE-07 0. 1. 25E-06 9.39E-05 1.21E-05 NB97 3.92E-ll 9.72E-12 3.55E-12 0. l.14E-ll 4.9IE-07 2.71E-07 M093 0. l.66E-06 4.52E-OB 0. 5.06E-07 8.81E-05 3.99E-06 M099+D 0. 2.llE-08 4.03E-09 0. 5.14E-08 l.92E-05 3.36E-05 TC99M 1. 73E-13 4.83E-13 6.24E-12 0. 7.20£-12 l.44E-07 7.66£-07 TC99 4.48E-08 6.SSE-08 1. 79E-OB 0. 8.35E-07 l.74E-04 7.99E-06 TClOl 7.40E-15 1.0SE-14 1. 03E-13 0. 1.90£-13 8.34E-08 l.09E-16 RU103+D 2.63£-07 0. 1.12E-07 0. 9.29E-07 9.79E-05 l.36E-05 RUlOS+D l.40E-10 0. 5.42E-ll 0. l.76E-10 2.27E-06 l.13E-05 RU106+D l.23E-05 0. 1.55E-06 0. 2.38E-05 2.0lE-03 1. 20£-04 RH105 l.32E-09 9.48E-10 6.24E-10 0. 4.04£-09 4.09E-06 1. 23E-05 PD107 0. l.17E-07 8.39E-09 o. 9.39E-07 l.63E-05 7.49E-07 PD109 0. 6.56E-10 1.66E-10 0. 3.36E-09 3.19E-06 1. 96E-05 AGllOM+D 1. 73E-06 l.64E-06 9.99E-07 0. ~.13E-06 8.44E-04 3.4!E**05 AGlll 6.07E-08 2.52E-08 1. 26E-08 0. 8.17E-08 4.00E-05 3.00E-05 C0113M 0. 2 .17E-04 7.IOE-06 0. 2.43E-04 3.59E-04 1. 68E-05 CD115M 0. 3.48E-05 l.14E-06 0. 2.82E-05 3.03E-04 5.IOE-05 SN123 4.31E-05 9.44E-07 1.40E-06 7.55E-07 0. 4.96E-C4 4.16E-05 SN125+D 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0. l.26E-04 7.29E-05 SN126+D 2.18E-04 5.39E-06 8.24E-06 1.42E-06 0. I. 72E-03 1. 68E-05 SB124 5.38E-06 9.92E-08 2. lOE-06 1. 22E-08 0. 4.BlE-04 4.98E-05 SB125+D 9.23E-06 l.OlE-07 2 .15E-06 8.BOF-09 0. 3.42E-04 1. 24E-05 SB126 6.19£-07 1. 27E-08 2.23E-07 3.50E-09 o. 1.55E-04 6.0IE-05 SB127 4.64£-08 9.92E-10 l.75E-08 5.21E-10 o. 3.31E-05 3.94E-05 TE125M 6.lOE-07 2.SOE-07 8.34E-08 1. 75E-07 o. 6.70E-05 9.38E-06 TE127M+D 2.25E-06 l.02E-06 2.73E-07 5.4BE-07 8.17E-06 2.07E-04 1. 99E-05 TE127 2.51E-10 1.14E-10 5.52E-11 l.77E-10 9.IOE-10 l.40E-06 1. OlE-05 j TE129M+D TU29 1.74E-06 8.87E-12 8.23E-07 4.22E-12 2.BIE-07 2.20E-12

5. 72E-07 6.4BE-12 6.49E-06 2.47£-04 3.32E-ll 4.12E-07 5.0GE-05 2.02E-07 l TE131M+D TE13l+D TE132+D

1. 23E-08 1.97E-12 4.50E-08 7.SlE-09 l.04E-12 3.63E-08 5.03E-09 6.30E-13 2.74E-08 9.06E-09 l.55E-12 3.07E-08 5.49E-08 2.97E-05 7.72E-12 2.92E-07 2.44E-07 5.61E-05 7.76E-05 1.89E-09 5.79E-05 TE133M+O 1.0lE-11 7.33E-12 5.71E-12 8. lBE-12 5.07E*ll 8. 71E-07 1. 23E-07 TE134+D 5.31E-12 4.35E-12 3.64E-12 4.46E-12 2.91E-ll 6.75E-07 l.37E-09 1129 3.53E-06 2.94E-06 4.90E-06 3.66E-03 5.26E-06 0. 2.29E-07 1130 7.BOE-07 2.24E-06 8.96E-07 l.86E-04 3.44E-06 0. 1.14E-06 1131+0 4.43E-06 6.14t.-06 3.30E-06 1.83E-03 1. 05E-05 0. 8.llE-07 44 Rev 7 01/01/93 l'

J 8 W6ff .... a a * ****I NM ¥4 #PRfu.:~

- ~ .

- - ~

-71 ~* *. ~

J.

I

~ ~-- ~ 1 ;I ) ;

.:i PAl.1:5.AQ.E..LJi~WB PLAHI Qf.D..11.L!J osL~t\L CIJ LAii OH 11/iliUAL Revision 7

J). -

}

IAJl.LE l1Z {~QDt~)

f, TEEN INHALATION DOSE COMMITMENT FACTORS ~MREM~50Y PER PCI INHALED IN FIRST Ykj ISOTOPE BONE LIVER TOTAL BO Y T YROID KIDNEY LUNG GI-Lll 1132 1.99[-07 5.47E-07 l.97E-07 1. 89[-05 8.65E-07 0. l.59E-07 1133+0 I. 52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0. l. 29E-06 1134 l. llE-07 2.90E-07 l.OSE-07 4.94E-06 4.SBE-07 0. 2.55E-09

\. 1135+0 4.62E-07 l. lSE-06 4.36E-07 7.76E-05 l.86E-06 o. 8.69[-07 XE131H 0. 0. o. 0. 0. 2.70E-09 0.

,' XE133M 0. o. 0. o. 0. 3.59E-09 0.

XE133 0. o. 0. 0. 0. 2.99E-09 0.

XE135M 0. 0. o. 0. 0. 3.88E-09 o.

XE135 o. 0. 0. 0. 0. 7.SSE-09 0.

XE137 0. 0. 0. o. 0. .J.33E-08 o.

-~.

XE138+0 0. 0. o. 0. 0. 4.38E-08 0.

'.s CS134M+D 2.20E-08 4.35E-08 2.35E-08 o. 2.54E-08 4.56E-09 2.02E-08

."if CS134 6.28E-05 1.41£-04 6.86E-05 o. 4.69E-05 l.83E-05 1. 22E-06

> CS135 2.08E-05 l.82E-05 4.47E-06 0. 7.30E-06 2.70E-06 2.23E-07 CS136 6.44E-06 2.42E-05 1.71~-05 0. 1. 38E-05 2.22E-06 l.36E-06 CS137+D 8.38E-05 1.06E-04 3.89E-05 o. 3.80E-05 l.51E-05 l.06E-06 CS138 5.82E-08 1.07E-07 5.58E-08 0. 8.28E-08 9.84E-09 3.38E-11 CS139+D 3.65E-08 5.12E-08 1. 97E-08 0. 4.34E-08 4.86E-09 1.66E-23 BA139 1.67E-10 1.18E-13 4.87E-12 0. l.llE-13 8.08E-07 8.06E-07 BA140+0 6.84E-06 8.38E-09 4.40E-07 o. 2.8~E-09 2.54E-04 2.86E-05 BA141+0 1. 78E-ll l.32E-14 5.93E-13 0. l.23E-14 4.llE-07 9.33E-14 BA142+0 4.62E-12 4.63E-15 2.84E-13 0. 3.92E-15 2.39E-07 5.99E-20 LA140 5.99E-08 2.95E-08 7.82E-09 0. 0. 2.68E-05 6.C9E-05 LA141 7.63E-10 2.35E-10 3.87E-ll 0. 0. 2.31E-06 1. 54E-05 LA142 l.20E-10 5.31E-ll l.32E-ll o. o. 1. 27E-05 l.SOE-06 CE141 3.55E-06 2.37E-06 2.71E-07 0. 1. llE-06 7.67E-05 l.58E-05 CE143+D 3.32E-08 2.42E-08 2.70E-09 0. l.08E-08 l.63E-i>5 3.19E-05

.J CE144+D 6. llE-04 2.53E-04 3.28E-05 0. 1. SlE-04 1.67E-03 l.OSE-04 PR143 1.67E-06 6.64E-07 8.28E-o8 0. 3.86E-07 6.04E-05 2.67E-05 PR144 5.37E-12 2.20E-12 2.72E-13 o. 1. 26E-12 2.19E-07 2.94E-14

)

ND147+D 9.83E-07 1.07E-06 6.41E-08 0. 6.28E-07 4.65E-05 2.28E-05

~ ... PM147 l.15E-04 1. IOE-05 4.SOE-06 o. 2.lOE-05 1.14E-04 5.87E-06 PM148M+D l.32E-05 3.35E-06 2.62E-06 0. 5.07E-06 3.20E-04 4. lOE-05

>. : PM148 5.44E-07 8.SSE-08 4.48E-08 0. l.60E-07 6.52E-05 6.14E-05

-" PM149 4.91E-08 6.89E-09 2.84E-09 o. l.31E-08 l.24E-05 2.79E-05 PM151 1. 20E-08 1. 99E-09 l.OlE-09 o. 3.57E-09 6.56E-06 2.27E-05 SM151 1.07E-04 2.IOE-05 4.86E-06 0. 2.27E-05 7.68E-05 3.53E-06 SM153 2.43E-08 2.0IE-08 1.47E-09. 0. 6.56E-09 7. llE-06 l.77E-05 EU152 2.96E-04 7.19E-05 6.30E-05 o. 3.34E-04 5.0lE-04 l.35E-05 EU154 9.43E-04 l.23E-04 8.60E-05 0. 5.44E-04 9.12E-04 3.34E-05 EU155 2.00E-04 1.96E-05 1. 21E-05 0. 7.65E-05 I. SlE-03 5.97E-05 EU156 2.70E-06 2.03E-06 3.30E-07 0. l.36E-06 l.37E-04 4.56E-05 J TB160 3.04E-05 o. 3.79E-06 0. l.20E-05 2.97E-04 2.60E-05 H0166M 4.40E-04 l.36E-04 9.87E-05 0. 2.00E-04 6.24E-04 l.68E-05 Wl81 8.90E-09 2.88E-09 3.0lEulO 0. 0. 2.95E-06 2.69E-07 WISS 2.78E-07 9.17E-08 9.73E-09 0. 0. 9.60E-05 l.14E-05 Wl87 l.SOE-09 l.-22E-09 4.29E-10 o. o. 5.92E-06 2.21E-05 45

Rev 7 01/01/93

1.' '

.- ' . :.. ~-

t ~ - ~. .' ~- a . 9 '.i P.AU~P...9 f5_!'!.U CL ll\IL PlllNJ Qff-5 lIL!HlS L ~Al CW..t\ UO!LMJ\lillA1.

Revision I IABLE L_L_i.£Qntdl TEEN INHALATION DOSE COMMITMENT FACTORS (HREH~50Y PER PCI INHALED JN FIRST YR}

ISOTOPE BONE LIVER TOTAL BODY T YROJD KIONEY LUNG Gl-Lll PB210+0 3.09£-02 8.20£-03 1.07£-03 0. 2.95£-02 4.52£-02 3.87£-05 81210+0 0. 2.26£-06 1.89£-07 0. 2.74£-05 1.91£-03 3.19£-05 P0210 5.68E-04 1.22£-03 1. 37E-04 0. 4.21£-03 5.41E-02 4.45£-05 RN222+D 0. 0. 0. 0. 0. 3.94E-06 0.

RA223+D 2.57E-04 3.93E-07 5.14E-05 0. l.12E-05 4.39£-02 3.04£-04 RA224+0 2.83£-05 6.77E-08 5.65E-06 0. 1.93£-06 1. SlE-02 3.29E-04 1.l RA225+0 4.28£-04 5.04£-07 8.56£-05 0. 1. 44£-05 5.04E-02 2.89E-04 RA226+0 1.33£-01 3.38E-06 9.87E-02 o. 9.67£-05 2.02E-Ol 3.llE-04 I

l RA228+0 5.34E-02 1. 74E-O~ 5.88E-02 o. 4.97E-05 2.78E-Ol S.30E-OS AC225 6.04E-04 8.25E-04 4.06E-05 o. 9.47E-05 3.81E-02 2.70E-04 I AC227+0 TH227+D TH228+D TH229 2.49E+OO 3.09E-04 2.60E-Ol 9.06E+OO 3.69E-Ol 5.56£-06 4.37E-03 l.36E-Ol l.48£-01 B.93£-06 8.78E-03 4.45E-Ol 0.

0.

l .07E-Ol 4 .16E-Ol 5.38E-05 3.IBE-05 6.50E-02 3.57E-04 2.45£-02 1. 69E+OO 3.70E-04 6.67£-01 5.05E+OO 3.36E-04 TH230 2.34E+OO 1.34£-01 6.49E*02 0. 6.55E-Ol 8.98E-Ol 3.95E-05 TH232+0 2.61E+OO 1.14£-01 9.21E-02 0. 5.60E-Ol 8.60E-Ol 3.36E-05 TH234 2.32E-06 1.35E-07 6. 71E-08 0. 7.73£-07 3.26E-04 7.49E-05 PA23l+D 5.32E+OO 2.00E-01 2.07E-Ol 0. l.12E+OO 9.91E-02 4.71E-05 PA233 1. 68E-06 3.24E-07 2.89E-07 0. 1. 22E-06 5.39E-05 l.OOE-05

- U232+0 U233+0 U234 U235+D U236 U237 U238+D 7.31E-02

1. SSE-02 1.48E-02 1.42E-02 l.42E-02 5.25E-08 1.36E-02 0.

o.

0.

5.23E-03 9.42E-04 9.23E-04 B.67E-04 8.86E-04

1. 40E-08

8. lOE-04 o.

o.

0.

7.94E-03 3.84E-01 4.46E-05 3.63E-03 9.lSE-02 4 .12E-05 3.SSE-03 8.99E-02 4.04E-05 3.34E-03 8.44E-02 5.13E-05 3.41E-03 8.62E-02 3.79E-05 2.16E-07 1. 76E-05 1. 29E-05 3.12E-03 7.89E-02 3.62E-05 NP237+D 1. 77E+OO l.54E-Ol 7.21E-02 0. 5.35E-Ol 8.99E-Ol 5.22E-05 NP238 4.23E-07 l.13E-08 6.59E-09 0. 3.88E-08 l.75E-05 2.38E-05 NP239 4.23E-08 3.99E-09 2.21E-09 0. 1. 25E-08 8. llE-06 1.65E-05 PU238 2.86E+OO 4.06E-Ol 7.22E-02 0. 3.lOE-01 3.12E-Ol 4.79E-05 PU239 3.31E+OO 4.SOE-01 8.0SE-02 0. 3.44E-Ol 2.93E-Ol 4.37E-05 PU240 3.31E+OO 4.49E-Ol 8.04E-02 0. 3.43E-Ol 2.93E-Ol 4.46E-05 PU24l+D 6.97E-02 3.57E-03 l.40E-03 0. 6.47E-03 2.60E-04 9 .17E-07 PU242 3.07E+OO 4.33E-Ol 7.75E-02 0. 3.31E-Ol 2.82E-Ol 4.29E-05 PU244 3.59E+OO 4.96E-Ol 8.88E-02 o. 3.79E-Ol 3.23E-Ol 6.39E-05 AM241 1.06E+OO 4.07E-Ol 7. lOE-02 0. 5.32E-Ol 1.0SE-01 4.88E-05 AM242M I. 07E+OO 3.93E-Ol 7.lSE-02 0. 5.30E-Ol 4.21E-02 6.14E-05 AM243 l.06E+OO 3.92E-Ol 6.95E-02 0. 5.21E-Ol 9.91E-02 5.72E-05 CM242 2.12E-02 2.14E-02 l.41E-03 o. 6.40E-03 6.76E-02 5.21E-05 CM243 8.45E-Ol 3.SOE-01 5.00E-02 0. 2.34E-Ol l.09E-Ol 5.13E-05 CM244 6.46E-Ol 3.03E-Ol 3.88E-02 0. l.81E-Ol l.OSE-01 4.96E-05 CM245 l.32E+OO 4.llE-01 7.53E-02 0. 3.52E-Ol l.OlE-01 4.63E-05 CM246 l.31E+OO 4. llE-01 7.52E-02 0. 3.SlE-01 1.03E-Ol 4.54E-05 CM247+D 1.28,+00 4.04E-Ol 7.41E-02 o. 3.46E-Ol 1.0lE-01 5.97E-05 CM248

1.06E+Ol 3.33F+OO 6. llE-01 0. 2.85E+OO 8.32E-Ol 9.63E-04 Cf 252 l.29E+OO 0. 3.07E-02 0. 0. 3.43E-Ol l.89E-04 I

- ,1 '* :

.;~ .~; :* :. > * : . . --. '

46

Rev 7

)

-~'. :::.. *:* -'~ *: .

'/*

.. 01/01/93

... .;r>:.:r:* '. , *,*.-* ' - .

~! ~-; .-~:/.;* ;. ' ,,

- V., -. ...... ,~ *

I 1

1 *:

P."'ll~Qf.~_ !HJUf..MLP.LANI

QffHTC.1195.L. G.l\.!~CVLATJiltL11AHllAL.

Revl~lon IAB6E 1,7 7

{~ootd)

ADULT INHALATION DOSE COHHITHENT FACTORS (HREM~50Y PER PC! INHALED IN FIRST YRl ISOTOPE BONE LIVER TOTAL BODY TH ROID KIDNEY LUNG GI- LI tlJ* 0. l.58E-07 1.58E-07 l.58E-07 l.58[-07 l.58[-07 l.58E-07

! BElO 1.98£-04 3.06£-05 4.96£-06 o. 0. 2.22E-04 1.67E-05 1l Cl4 2.27E-06 4.26E-07 4.26£-07 4.26£-07 4.26E-07 4.26E-07 4.26£-07 Nl3 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 I

Fl8 4.71E-07 o. 5.19E-08 0. 0. 0. 9.24E-09 l j NA22 l.30[-05 l.30E-05 1.30£-05 l.JOE-05 1. 30E-05 1.30£-05 1.30£-05 NA24 1. 28E-06 1. 28[-06 1.28E-06 1. 28E-06 I. 28E-06 l.2BE-06 l. 28£-06 l P32 1. 65E-04 9.64£-06 6.26E-06 0. 0. 0. l. OBE-05

!l AR39 0. 0, 0. 0. !.l. 2.08E-C9 n....

AR41 o. 0. 0. 0. 0. 8.06E-09 Q.

j CA41 3.83E-05 0. 4.13E-06 0. 0. 3.83E-06 2.86£-07 l SC46 CR51 5.51E-05 0.

l.07E-04 3.llE-05 0.

0. l.25E-08 9.99E-05 0. 3.23£-05 7.44£-09 2.BSE-09 1.80£-06 4. lSE-07 1l MN54 0. 4.95E-06 7.87£-07 0. 1.23£-06 l.75E-04 9.67£-06 l MN56 FESS 0.

3.07£-06 1.47£-06 l.55E-10 2.29E-11 2 .12E-06 4.93E-07 0.

3.47E-06 l.32E-06 0.

0. 1. 63E-10 l. lBE-06 2.53E-06 0.

0.

9.0lE-06 7.54£-07 l.27E-04 2.35£-05 l FE59 C057 COSS o.

0.

8.65E-08 8.39£-08 0.

1. 98£-07 2.59E-07 0.

0.

4.62E-05 3.93E-06 1.16E-04 l.33E-05

- - C060 NI59 Nl63 Nl65 CU64 ZN65 0.

4.06[-06 5.40£-05 l.92E-10 0.

4.05E-06 l.4-lE-06 1.46£-06 6.77E-07 0.

2.62E-ll l.83F.-10 7 .69E-ll l.85E-06 0.

3.93E-Oti l.81E-06 0.

1.14E-11

1. 29E-05 5.82E-06 0.

0.

c.

7.46E-04 3.56E-05 8.20E-06 6.llE-07 2.23E-05 1.67£-06 7.00E-07 1. 54£-06 5.78E-10 8.48E-07 6.12£-06 8.62E-06 l.OBE-04 6.68E-06 ZN69M+D 1.02£-09 2.45E-09 2.24E-10 0. 1. 48E-09 2.38E-06 1. 71E-05 ZN69 4.23E-12 8.14E-12 5.6SE-13 0. 5.27E-12 l.15E-O/ 2.04E-09 SE79 0. 3.83£-07 6.09E-08 0. 5.69E-07 4.47E-05 3.33E-06 BR82 0. 0. 1.69E-06 0. 0. 0. 1.30E-06 BR83+0 0. o. 3.0IE-08 0. o. 0. 2.90E-08 BR84 0. 0. 3.91E-08 0. 0. 0. 2.0SE-13 BR85 0. 0. l. 60E-09 0. 0. 0. o.

KR83M 0. o. o. 0. 0. 5.19E-10 0.

KR85M 0. 0. 0. 0. 0. 2.91E-09 0.

KR85 0. 0. o. 0. 0. 2.41E-09 0.

KR87 0. 0. o. 0. 0. l.53E-08 0.

KR88+0 0. 0. 0. 0. 0. 3 .13E-08 0.

KR89 0. 0. o. 0. o. 2 .13E-08 0.

RB86 0. 1. 69E-05 7.37E-06 0. 0. . 0. 2.08E-06 RB87 o. 9.86£-06 3.21E-06 0. o. 0. 2.88E-07 RB88 0. 4.84E-08 2.41E-08 0. 0. 0. 4.18E-19 RB89+0 0. 3.20E-08 2.12E-08 0. 0. o. 1.16E-21 SR89+0 3.SOE-05 o. l.09E-06 0. o. l.75E-04 4.37E-05 SR90+D 1. 24E-02 0. 7.62E-04 0. 0. 1. 20E-03 9.02E-05 SR9l+D 7.74E-09 0. 3.13E-10 o. 0. 4.56E-06 2.39E-05 SR92+D 8.43E-10 o. 3.64E-11 0. o. 2.06E-06 5.38£-06

Includes a 50% increase to account for percutaneous transpiration.

47 Rev 7 01/01/93

j . ,I PAL! S.A!2f~-~\l~1.(>\JL ~Ll'JiI

!!tU llLQ_Q~[__~Al~!JlAil_Qli_l'1-ANLlAl Revision 7 Il\Jl1E l.Z (~oatdl ADULT INHALATION DOSE COHHITHEHT FACTORS (HREH,50Y PER PCl INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY TH ROID KIDNEY LUNG GJ-lll Y90 2.61E-07 0. 7.0lf-09 0. 0. 2.12E-05 6.32E-05 Y91M+D 3.26E-ll o. l.27E-12 0. 0. 2.40E-07 l.66E-10 Y91 5.78E-05 0. l.SSE-06 0. 0. 2 .13E-04 4.81E-05 V92 1. 29E-09 o. 3.77E-ll 0. 0. l.96E-06 9.19E-06 Y93 1.lBE-08 0. 3.26E-10 0. 0. 6.06E-06 5.27E-05 ZR93t0 5.22E-05 2.92E-06 1. 37E-06 0. l.llE-05 2.13E-05 1. 51E-06 ZR95+D 1. 34E-05 4.30E-06 2.91E-06 0. 6. 77E-06 2.21E-04 1. 88E-05 ZR97tD 1. 21 E-08 2.45E-09 l.13E-09 0. 3.71E-09 9.84E-06 6.54E-05

? AOC' _n&. n l.15E-05 3. llE-05 2.38£-06 NS93M 3. lOE-05 l.OlE-05 '-. ""T.;,-~-vv v.

NB95 l.76E-06 9. 77E-07 5.26E-07 0. 9.67E-07 6.31E-05 l.30E-05 NB97 2.78E-ll 7.03E-12 2.56E-12 0. 8.18E-12 3.00E-07 3.02E-08 M093 0. l.17E-06 3.17E-08 0. 3.SSE-07 5.llE-05 3.79E-06 M099+D 0. l.S!E-08 2.87E-09 0. 3.64E-08 l.14E-05 3. lOE-05 TC99M l.29E-13 3.64E-13 4.63E-12 0. S.52E-12 9.SSE-08 S.20E-07 TC99 3.13E-08 4.64E-08 1. 2SE-08 0. S.85E-07 l .vlE-04 7.54E-06 TClOl 5.22E-15 7.52E-15 7.38E-14 0. l.35E-13 4.99E-08 l.36E-21 RU103+0 1.91E-07 0. 8.23E-08 o. 7.29E-07 6.JlE-05 l.38E-05 RU105+D 9. 88E- ll 0. 3.89E-ll 0. 1. 27E-10 l.37E-06 6.02E-06

RU106+D RH105 PD107 PD109 AGllOM+D AGlll CD113M 8.64E-06 9.24E-10 0.

0.

1.35E-06 4.25E-08 0.

0. 1. 09E-06 6.73E-10 4.43E-10 0.

8.27E-08 5.87E-09 0.

4.63E-10 1.16E-10 0.

1.25E-06 7.43E-07 0.

1. 78E-08

1. 54E-04 8.87E-09 0.

4.97E-06 o.

0. l.67E-OS 1.17E-03 l.14E-04 2.86E-09 2.41E-06 1. 09E-05 6.57E-07 9.47E-06 7.06E-07 2.3SE-09 l.85E-06 l.52E-05 2.46(-06 5.79E-04 3.781:-05 5.74E-08 2.33E-05 2.79E-05

1. 71E-04 2.08E-04 1. 59E-05 CD115M 0. 2.46E-05 7.95E-07 0. 1. 98E-05 1. 76E-04 4.SOE-05 SN123 3.02E-OS 6.67E-07 9.82E-07 5.67E-07 0. 2.88E-04 3.92E-05 SN125+D l.16E-06 3.12E-08 7.03E-08 2.59E-08 0. 7.37E-05 6.81E-05 SN126+D 1. 58E-04 4.18E-06 6.00E-06 1. 23E-06 0. 1. l 7E-03 l.59E-05 SB124 3.90E-06 7.36E-08 1. SSE-06 9.44E-09 o. 3.lOE-04 5.08E-05 SB125+D 6.67E-06 7.44E-08 1. 58E-06 6.75E-09 0. 2.18E-04 l.26E-05 SB126 4.50E-07 9 .13E-09 1.62E*07 2.75E-09 0. 9.57E-05 6.0lE-05 SB127 3.30E-08 7.22E-10 1. 27E-08 3.97E-10 0. 2.05E-05 3.77E-05 TE125M 4.27E-07 1. 98E-07 5.84E-08 l.31E-07 1. 55E-06 3.92E-05 8.83E-06 TE127M+D 1. 58E-06 7.21E-07 1. 96E-07 4.llE-07 5.72£-06 1.20£-04 l.87E-05 TE127 1.75£-10 8.03E-ll 3.87E-ll l.32E-10 6.37E-10 8.14E-07 7.17E-06 TE129M+D l.22E-06 5.84E-07 1. 98E-07 4.30£-07 4.57E-06 1.45E-04 4.79E-05 TE129 6.22E-12 2.99E-12 1.SSE-12 4.87E-12 2.34E-11 2.42E-07 1. 96E-08 TE131M+D 8.74E-09 5.45E-09 3.63E-09 6.88£-09 3.86E-08 1. 82E-05 6.95E-05 TE131+0 l .39E-12 7.44E-13 4.49E-13 1.17£-12 5.46E-12 1. 74E-07 2.30E-09 TE132+D 3.25E-08 2.69E-08 2.02£-08 2.37E-08 l.82E-07 3.60£-05 6.37£-05 TE133M+D 7.24E-12 5.40E-12 4.17£-12 6.27E-12 3.74E-ll 5.51£-07 5.49E-08 TE134+0 3.84E-12 3.22E-12 1.57E-12 3.44E-12 2.lSE-11 4.343-07 2.97E-ll 1129 2.48E-06 2. llE-06 6.91E-06 5.54E-03 4.53E-06 0. 2.22E-07 1130 5.72E-07 1. 68E ~06 6.60E-07 l.42E-04. 2.61E-06 0. 9.61E-07 1131+0 3.lSE-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0. 7.SSE-07

48 Rev 7 01/01/93

.) *~ ~h.~ **

~ "

~li~AQI ~- WLt;. LIAR P.kl\JU QfJ~lILQ_Q S_LJALC_Ll LAf ! QtlJlAl{IJA!,

Rev1s1on 7 I.AI!kLL1__W>ntd.l

~

ADULT INHALATION DOSE COMMITMENT FACTORS {MREH~50Y PER PC! INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY TH ROJO KIDNEY LUNG GI-LLI 1132 1. 45E-07 4.07E-07 l.45E-07 l.43E-05 6.48E-07 0. 5.0BE-08 1133+0 1.0BE-06 1.85E-06 5.65£-07 2.69E-04 3.23E-06 0. 1. 11 E-06 1134 8.05E-08 2.16£-07 7.69E-08 3.73E-06 3.44E-07 0. l.26E-10 1135+0 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1. 39E-06 0. 6.56E-07 XE131M 0. o. 0. 0. o. l.40E-09 0.

XE133M 0. 0. 0. 0. o. l.89E-09 0.

XE133 0. o. 0. 0. 0. l. 57£-09 0.

XE135M 0. 0. 0. 0. 0. 2.22£-09 0.

n..,, 4.0SE-09 0.

XE135 XE137 0.

0.

0. 0. 0.

0. l. 74E-08 0.

XE138+D 0. 0. 0. 0. 0. 2.44E-08 0.

., CS134M+D l.59E-08 3.20E-08 1. 72E-08 0 . l.83E-08 2.93E-09 7.92E-09

,J

~" CS134 4.66E-05 l.06E-04 9.lOE-05 0. 3.59E-05 l.22E-05 l.30E-06

j CS135 l.46E-05 l.29E-05 5.99£-06 0. 5.llE-06 l.57E-06 2.llE-07 CS136 4.88E-06 l. 83E-05 l. 38E-05 0. l.07E-05 l.SOE-06 1.46E-06 CS137+D 5.98E-05 7.76E-05 5.35£-05 0. 2.78£-05 9.40£-06 1.05£-06 CS138 4 .14E-08 7.76£-08 4.05£-08 o. 6.00E-08 6.07E-09 2.33£-13 CS139+0 2.56E-08 3.63E-08 1. 39E-08 0. 3.05E-08 2.84E-09 5.49E-31 BA139 l.17E-10 8.32E-14 3.42E-12 0. 7.78£-14 4.70E-07 1.12E-07 BA140+D 4.88E-06 6.13E-09 3.21[-07 0. 2.09£-09 1. 59E-04 2.73E-05 BA14l+D l.25E-ll 9.41E-15 4.20E-13 0. 8.75£-15 2.42E-07 l.45E-17 BA142+D 3.29E-12 3.38E-15 2.07E-13 0. 2.86E-15 1. 49E-07 1. 96E-26 LA140 4.30E-08 2 .17£-08 5.73£-09 0. u. 1. 70£-05 5.73E-05 LA141 5.34E-10 1.66E-10 2.71E-ll 0. 0. 1.35[-06 7.31E-06 LA142 8.54E-ll 3.88E-11 9.65E-12 0. 0. 7.91E-07 2.64E-07 CE141 2.49E-06 1. 69E-06 1.91E-07 0. 7.83£-07 4.52E-05 1. SOE-05 CE143+D 2.33E-08 1. 72E-08 l.SlE-09 0. 7.60£-09 9.97E-06 2.83E-05 CE144+D 4.29E-04 1. 79E-04 2.30E-05 0. 1.06£-04 9.72E-04 1.02£-04 PR143 1.17E-06 4.69E-07 5.80E-08 0. 2.70E-07 3.51E-05 2.50E-05 PR144 3.76E-12 1.56E-12 l.91E-13 0. 8.81£-13 l.27E-07 2.69E-18 ND147+D 6.59£-07 7.62E-07 4.56E-08 0. 4.45E-07 2.76E-05 2 .16E-05 PM147 8.37E-05 7.87E-06 3.19E-06 0. l.49E-05 6.60E-05 5.54E-06 PM148M+D 9.82E-06 2.54E-06 1.94E-06 0. 3.85E-06 2 .14E-04 4.18E-05 PM148 3.84E-07 6.37E-08 3.20E-08 0. 1. 20E-07 3.91E-05 5.SOE-05 PM149 3.44E-08 4.87E-09 1. 99E-09 0. 9.19E-09 7.21E-06 2.50E-05 PM151 8.50E-09 l.42E-09 7.21E-10 0. 2.55E-09 3.94E-06 2.00E-05 SM151 8.59E-05 1. 48E-05 3.55E-06 0. 1.66E-05 4.45E-05 3.25E-06 SM153 1. 70E-08 1.42E-08 1. 04E-09 0. 4.59E-09 4.14E-06 1. 58E-05 EU152 2.38E-04 5.41E-05 4.76E-05 0. 3.35E-04 3.43E-04 1.59E-05 EU154 7.40E-04 9. IOE-05 6.48E-05 0. 4.36E-04 5.84E-04 3.40E-05

~l EU155 1.0lE-04 1.43£-05 9.21£-06 0. 6.59E-05 9.46E-05 5.95E-06

~~

EU156 I. 93E-06 1.48E-06 2.40E-07 0. 9.95E-07 8.56£-05 4.SOE-05 ii TB160 2.21£-05 0. 2.75E-06 0. 9.IOE-06 1. 92E-04 2.68E-05

{;

6\'. . H0166M 3.37E-04 1.0SE-04 8.00E-05 0. l.57E-04 3.94E-04 1. 59E-05 Wl81 6.23E-09 2.0~~-09 2.17E-10 0. 0. 1.71E-06 2.53E-07 WISS l.95E-07 6.47E-08 6.SlE-09 o. 0. 5.57E-05 l.07E-05 Wl87 1. 06E-09 8.85E-10 3.IOE-10 0. 0. 3.63E-06 1. 94E-05 49 Rev 7 01/01/93

' ,. ' fAU~J)l~_ J1V~ LfJ\JLP1AtH Qf£.~lI£ DOSf:__!;_AJ.J~llLAT JQN_J'l!\_NUl\_l Revision 7 L

[.

F TABLE l~.I_Lcont!U.

1:

ADULT INHALATION DOSE COHHITHENT FACTORS (HREH~50Y PER PCI INHALED IN FIRST YRl t" ISOTOPE BONE LIVER TOTAL BODY TH ROID KIDNEY LUNG GI- LI PB210+D 2.64E-02 6.73E-03 8.37E-04 0. 2.12E-02 2.62E-02 3.65E-05 t Bl210+D 0. 1. 59E-06 l.32E-07 0. 1.92E-05 l.llE-03 2.95E-05 t P0210 3.97E-04 8.60E-04 9.58[-05 0. 2.95E-03 3,14E-02 4. 19£-05 r~..

RN222+D o. 0. 0. 0. o. 2.05E-06 0.

RA223+D 1. 80E-04 2.77E-07 3.60E-05 0. 7.85E-06 2.55E-02 2.84E-04 RA224+0 1. 98E-05 4.78E-08 3.96E-06 0. 1. 35E-06 8. 77E-03 3.0lE-04 RA225+0 3.00E-04 3.56E-07 5.99E-05 0. 1.0lE-05 2.92f-02 2.71E-04 2.39E-06 9.14E-02 0. 6.77E-05 l.17E-Ol 2.94E-04 j~

RA226+D 1.25E-01 RA228+0 AC225 4.41E-02 4.23E-04 1.23E-06 4.78E-02 0.

5.82E-04 2.84E-05 0.

3.48£-05 L61E-Ol 5.00E-05 6.63E-05 2. 21E-02 2.52E-04 r AC227+0 TH227+D 2.30E+OO 2.17E-04 3.0SE-01 l.36E-Ol 0.

3.92E-06 6.25E-06 0.

9.82E-02 2.41E-Ol 5.08E-05 2.22E-05 3.77E-02 3.34E-04 r~

TH226+0 2.00E-01 3.39E-03 6. 77E-03 0. 1.89E-02 l. 01 E+OO 3.49E-04 ~:

TH229 8.88E+OO l.33E-Ol 4.36E-Ol 0. 6.52E-01 3.49E+OO 3.17E-04 t**

TH230 2.29E+OO 1.31E-Ol 6.36E-02 o. 6.40E-Ol 6.21E-Ol 3.73E-05 TH232+D 2.56E+OO l.12E-Ol 9.04E-02 0. 5.47E-Ol 5.96[.:.0l 3.17E-05 TH234 l.63E-06 9.SGE-08 4.70E-08 0. 5.41E-07 1. 89E-04 7.03E-05 ~:*

PA231+0 S.08E+OO l.91E-Ol 1. 98E-Ol 0. l.07E+OO 5.75E-02 4.44E-05 PA233 l.21E-06 2.42E-07 2.09E-07 0. 9.lSE-07 3.52E-05 l.02E-OS U232+0 5.14E-02 o. 3.66E-03 o. 5.56E-03 2.22E-Ol 4.21E-05 U233+0 l.09E-02 0. 6.60E-04 0. 2.54E-03 5.32E-02 3.89E-05 U234 l.04E-02 0. 6.46E-04 0. 2.49E-03 5.22E-02 3.BlE-05 f' U235+0 l.OOE-02 0. 6.07E-04 0. 2.34E-03 4.90E-02 4.84E-il5 1~~.

U236 l.OOE-02 o. 6.20E-04 0. 2.39E-03 5.00E-02 3.57E-05 ;*'

J U237 3.67E-08 o. 9.77E-09 0. 1.SlE-07 l.02E-05 1. 20E-05 ~

U238+0 9.58E-03 0. 5.67E-04 0. 2.lSE-03 4.58E-02 3.41E-05 *;;:

NP237+D l.69E+OO l.47E-Ol 6.87E-02 0. 5.lOE-01 5.22E-02 4.92E-05 }

NP238 2.96E-07 8.00E-09 4.61E-09 0. 2. 72E-08 l.02E-05 2 .13E-05 *:

NP239 2.87E-08 2.82E-09 1. 55E-09 0. 8.75E-09 4.70E-06 l.49E-05 /.

PU238 2.74E+OO 3.87E-Ol 6.90E-02 0. 2.96E-Ol l.82E-Ol 4.52E-05 rt PU239 3.19E+OO 4.31E-Ol 7.75E-02 0. 3.30E-01 1. 72E-Ol 4.13E-05 ~

PU240 3. l8E+OO 4.30E-Ol 7.73E-02 0. 3.29E-Ol 1. 72E-Ol 4.21E-05 .f*

~.

PU24l+D 6.41£-02 3.28£-03 1. 29E-03 o. 5.93E-03 1. 52E-04 8.65E-07 7.46E-02 o.

PU242 2.95E+OO 4.lSE-01 3.17E-Ol l.65E-Ol 4.0SE-05 -'.'

-:r*

PU244 3.45E+OO 4.76E-Ol 8.54E-02 0. 3.64E-Ol l.89E-Ol 6.03E-05 \

AM241 l.OlE+OO 3.59E-01 6. 71E-02 o. 5.04E-01 6.06E-02 4.60E-05 AM242M l.02E+OO 3.46E-Ol 6.73E-02 0. 5.0lE-01 2.44E-02 5.79E-05 *,. ~

AM243 1. 01 E+OO 3.47E-Ol 6.57E-02 0. 4.95E-01 5.75E-02 5.40E-05 :*'

CM242 l.48E-02 l.SlE-02 9.84E-04 0. 4.48E-03 3.92E-02 4.91E-05 CM243 7.86E-Ol 2.97E-Ol 4.61E-02 0. 2.15E-Ol 6.31E-02 4.84E-05 }

\.

CM244 5.90E-Ol 2.54E-Ol 3.51E-02 0. 1.64E-Ol 6.06E-02 4.68E-05 (:

~*;*:

CM245 l.26E+OO 3.59E-Ol 7.14E-02 o. 3.33E-Ol 5.85E-02 4.36E-05 *'-:

CM246 l.25E+OO 3.59E-Ol 7 .13E-02 0. 3.33E-Ol 5.96E-02 4.29E-05 ~t~*

CM247+D l.22E+O!l 3.53E-Ol 7.03E-02 o. 3.28E-Ol 5.85E-02 5.63E-05 ],

CM248 1.0lE+Ol 2.91E+OO 5.79E-Ol 0. 2.70E+OO 4.82E-Ol 9.09E-04 '.r' CF252 9.78E-01 0. 2.33E-02 0. o. l.99E-Ol 1. 78E-04 ,,*"

- 50 Rev 7 01/01/93

{

\':

~*

t,*.

-~ '

1

't'*

"j ~ L , _'i

,t EXI.ERHAL D~.LEACJ]RS Rev1sion 7 I.ADJ..LLl FOR STANOINLi~lAftlliAIJON filiQUND_ _(_Q£Ji 11

' (HREH/HR PEB PCl/H)

ELEMENT IOTAL BODY SKIN H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20£-10 2.60E-l0 Mn-54 5.80£-09 6.80£-09 Mn-56 i. iOE-08 l.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 l.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1. 50£-09 1. 70£-09 Zn-65 4.00E-09 4.60E-09 Zn-69 o.o 0.0 Br-83 6.40E-ll 9.30E-ll Br-84 1. 20E-08 1.40E-08 9r-85 0.0 0.0 Rb-86 6.30£-10 7.20E-10 Rb-88 3.SOE-09 4.00E-09 Rb-89 1. 50£-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr*-91 7.lOE-09 8.30£-09 S*r-92 9.00E-09 l.OOE-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.SOE-09 4.40E-09 Y-91 2. 40E-ll 2.70E-11 Y-92 1.60E-09 1.90E-09 11-93 5.70E-10 7.80E-10

~'.r-95 5.00E-09 5.BOE-09 2r-97 5.50E-09 6.40E-09 Nb-95 5. lOE-09 6.00E-09 Mo-99 1. 90£-09 2.20E-09 Tc-99m 9.60£-10 1.lOE-09 Ic-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.lOE-09 Ru-106 1. SOE-09 l.80E-09 Ag-llOm 1. SOE-08 2.lOE-08 Te-l25m 3.SOE;.11 4.SOE-11 Te-127m l.lOE-12 1.30E-12 Te-127 1. OOE-11 1. lOE-11

~*. :_ . ~...~*.

'"r ,,

' '. !~** *.

51 . Rev 7 01/01/93

' .. ~ *: : -.

EXI~RHAL DOSE TABLE Revis1on 7 EA(;IQ8~ f9R.._$T~{QIN\t l.~ (continued)

QN ~Q~8MIH8IIQH Gf!Q!JfilL.(QfJi 1l

{HR~ML fl P~.~ PG ILH l ELEMENT TOTAL BODY SKIN Te-129m 7.70E-10 9.00E-10

. Te-129 7.lOE-10 8.40E-10 Te-lllm 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1. 70£-09 2.00E-09 1-130 1.40£-08 1. 70F.-08 I~ 13! ,, onC'_no

'- * \ I V l . - V i l 3.4t>E*09 1-132 l.70E-08 2.00E-08 1-133 3.70E-09 4.SOE-09 1-134 l.60E-08 1. 90E 08 0

1-135 I. 20E-08 l.40E-08 Cs-134 1. 20E-08 l.40E-08 Cs-136 1.SOE-08 1. 70E-Ob Cs-137 4.20£-09 4.90E-09 Cs-138 2.10£-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2. lOE-09 2.40E-09 ;.

Ba-141 4.30E-09 4.90E-09 I Ba-142 7.90E-09 9.00E-09 f La-140 1. SOE-08 r l.70E-08 ir La-142 1.SOE-08 l.SOE-08 '

I Ce-141 5.SOE-10 6.20E-10 f r;

Ce-143 2.20E-09 2.SOE-09 Ce-144 3.20E-10 3.70E-10 i f

Pr-143 0.0 o.o r l

Pr-144 2.00E-10 2.30E-10 I Nd-147 1.00E-09 1. 20£-09 W-187 3.lOE-09 3.60E-09 Np-239 9.50E-10 1. lOE-09 rI' 52 Rev 7 _

01/01/93 -*:.*

~. ..

~.. ' ' . : I' . ,-,

r*~

. , ... * ....* ....... _..:. .. . *:*~- .. - .... "**. *.r, r

] 't* '. I Revision 7 TAQLE 1. 9 l~ PALISADES GASEOUS DESlGH QDJECTIYE ANNUAL QUANTITIES Design Objective Dose Factor Annual Quantity Nuclide Organ mrem/C1 (Cj)

Ag-1 lOm GI Tract-T l.OSE+OO 1. 43E+Ol Ar-41 Total Body 2.75E-04 l.82E+04 Ba-139 GI Tract-C 2.38E-03 6.30E+03 Ba-140 Lung-I 8.37E-02 1. 79E+02 Br-82 Total Body:! l.16E-03 4.31E+03 C-14 Bone-C l.07E-Ol 1.40E+02 Ce-141 GI Tract-T l.ISE-01 1. 30E+02 Ce-144 GI Tract-T 3.06E+OO 4.90E+OO Co-57 GI Tract-T 7.74E-02 l. 94E+02 Co-58 GI Tract-T 1.37£-01 1. 09E+02 Co-60 GI Tract-T 7.83£-01 1. 92[+01 Cr-51 GI Tract-A,T 2 .14E-03 7.01E+03 Cs-134 Lher-C 6.29E+OO 2.38E+OO l

Cs-136 Total Body-I l.OOE-01 5.00E+Ol Cs-137 Bone-C 6. ISE+OO 2.44E+OO Cs-138 Total Body-I l.64E-05 3.05E+05 Fe-55 Bone-C l.80E-Ol 7.98E+Ol Fe-59 GI Tract-I 2.19E-Ol 6.8SE+Ol H-3 Total Body-C l.23E-O.; 4.07E+04 1-131 Thyroid- I 9.97E+OO l. SOE+OO 1-132 Thyroid-C 8.28E-03 l .81E+03 I-133 Thyroid-C 1.65£-01 9.09E*:*Ol I-134 Thyroid-C 2.17E-03 6.91E+03 I-135 Thyroid-C 3.39E-02 4.42E+02 Kr-83m Skin 6.66E-07 2.25E+07 Kr-85 SKin 6.0lE-f'S 2.50E+05 Kr-85m Total Body *3.63E-05 1.38E+05 Kr-87 Skin 6.45E-04 2.33E+04 Kr-88 Total Body 4.57E-04 l.09E+04

,*I Kr-89 Total Body S.16E-04 9.69E+03 La-140 GI Tract-T 2.0lE-02 7.46E+02 Mn-54 GI Tract-I 2.21E-Ol 6.79E+Ol Mn-56 GI Tract-C 5.0BE-03 2.95E+03 Mo-99 GI Tract-I l. llE-02 l.35E+03 N-13 Total Body-C 3.55E-06 l.41E+06 Na-24 Total Body-C 6.63E-04 7.54E+03 Nb-95 GI Tract-A 9.83E-02 1.53E+02 Ni-65 GI Tract-C 3.46E-03 4.34E+03

. *,' Nc-239 GI Tract-T 5.44E-03 *2. 76E+03

'R -88. Total Body-C l.51E-05 3.31E+OS

-Ru-103 GI Tract-I 1. 25E-Ol l.20E+02

- Ru-105** GI Tract-C 4.lOE-03 3.66E+03

. Sb~l24;. GI Tract-T 7.04E-Ol 2.13E+Ol

Sb-125 .

GI Tract-I 53 3.97E-Ol 3.78E+Ol Rev 7 01/01/93

.. l

! ! t. ,j. . r. . . ; :.

I.AllJ...Llil {continued)

_li93 PALlSA.D..E.~ GASEOUS DESI~

QIL!ECTJVE ANNUAL OUANTIIlES Design Objective Dose Factor Annual Quantity Nuc]1de Organ mrem/Ci (Ci)

Sr-89 Bone-C 8.26E+OO l.82E+OO Sr-90 Bone-C 3.40E+02 4-.41E-02

,} Sr-91 Sr-92 Bone-I GI Tract-C l.68E+OO o -

"". oni:

8.93E+OO r Tc-99m GI Tract-T

,, ... _f\'2 2.53E-04

- ..,..,,, 1. SOE+03 5.93E+04 Tc-101 GI Tract-I 3.48E-05 4.31E+OS Te-127 GI Tract-T 3.33E-03 4.50E+03 Xe-131m Skin 2.65E-05 5.66E+05 Xe-133 Total Body 9.13f-06 5.48E+OS Xe-133m Skin S.54E-05 2.71E+OS Xe-135 Total Body 5.62E-05 8.90E+04 Xe-135m Total Body 9.69E-05 5.16E+04 Xe-137 Skin 5.94E-04 2.53E+04 Xe-138 Total Body 2.74E-04 l.82E+04 Zn-65 Total Body-C 4.16E-Ol l.20E+Ol Zr-95 GI Tract-T 2.89E-Ol 5.19E+Ol l

II_

l .**:

I,. :

j *.:.'." ..

~~....

. 54 Rev 7

.** ... . 01/01/93

.i l

j l

l

- 11. hl.QUID EFFLU~

Revision 7 A. CONCENTRATION

l. Reqy1rements Appendix A,Section III.G r~quires that the concentration of radioactive material released at any time fro~ the site to unrestricted areas shall be limited to ten times the Effluent i Concentration (EC) specified in 10 CFR 20, Appendix B, Table 2, lI Column 2 for nuclides other than dissolved or entrained noble gases.

For dissu1ved or entrained noble gases, the concentration shall be

; limited to 2E-04 µCi/ml total activity. To ensure compliance, the I

. '~: '

following approach will be used for each release.

2. Prerelease AnaJvs1s Most tanks will be recirculated through two volume clianges prior to sampling for release to the environment to ensure that a representative sample is obtained. The appropriate recirculation time for those tanks too large to provide two volume changes will be the time that the suspended particulate concentration reaches steady state. Either a one-time test, or prior sampling data, may be used to determine appropriate recirculati0n time.

Prior to release, a grab sample will ~e analyzed for each release, and the concentration of each radionuclide determined.

n C "' :E 1=1 C1 (2.1) where:

c Total concentration in the liquid effluent at the release point, µCi/ml.

Concentration of a single radionuclide i, µCi/ml.

'*.?.*::I ~'

'1;_ . .

.**;;'*~*.~{

55 Rev 7 01/01/93

3. EfflY9ilLC.9.n~~!llr~t1on Rovlslon 7

{EC) - Sum Qf t!1~_1@1-~.

The EC-Fraction (RJ) for each release point will be calculated by the relationship deftned by Note 4 of Appendix B, 10 CFR 20:

i

( 2. 2) '

where:

C1 Effluent concentration of radionuclide i, µCi/ml.

l ,.

f.

Tha EC of rad1or.uc11de 1, lu CfR 20, Appendix B, Table 2, Column 2 - µCl/ml.

RJ The Total EC-Fraction for the release point*.

The sum of the ratios at the discharge to the lake mu~t be ~ 10 due to the releases from any or all concurrent releases. The following f, relationship will assure this criterion is met:

f -1 ) + f (Ra -1 ) f s: F tf.

1 ( R1 3 ( R3 -1 )

+

2 (2.3) t where: '

I I i' The effluent flow rate (gallons/minute) for the respective releases, determined by Plant personnel. r f

.. The Total EC-Fractions for the respective releases as r determined by Equation 2.2. t' r

F Minimum required dilution flow rate. Normally, a f conservatively high dilution flow rate is used, that is, flow rate used~ (u 1)(F) where b1 is a 1*

conservative factor greater than 1.0. (

l*

I

[.

I t

I r

I Ii I

I t

(

l 56 Rev 7 01/01/93

' ."'.. . ~- .

J.*'r;,

i' l

1 PAlJ:it'JJE5 Nl.JGLLA.H !'Ll\Jfl L_~_A_L_G_W_J_1J-*J_!)_N_r_li\

1 r-*:l - - - - - - - - - - - - - -J_f_-f_?_l_H._ . __Q_.Q_$.__

Ruv I 'I on I

__t1-t1_.A_L_ _ _ _ _ __

B. INSTRUMENT SETPOINTS

1. .S.llru2.in.L.D9term1 natl2.n Appendix A, Section 111.F requires alarm setpoints for each liquid effluent monitor will be established using Plant instructions to enusre the requirements of Appendix A,Section III.Gare not exceeded. Concentration, flow rate, dilution, principal gamma emitter, geometry and detector efficiency are combined to give an equivalent setpoint in counts per minute (cpm). The identification number for each liquid effluent radiation detector i~ contained in Figure 2-2.

The respective al~rm/trip setpoints at each release point will be set such that the sum of the ratios at each point, as calculat~d by Equation 2.2, will not be exceeded. The value of R is directly related to the total concentration calculated by Equation 2.1. An increase in the concentration would indicate an increase in the value of R. A large increase would cause the limits specified in Section 2.1.l to be exceeded. The minimum alarm/trip setpoint value is equal to the release concentration, but for ease of operation it may be desired that the setpoint (S} be set above the effluent concentration (C} by the same factor (b) utilized in setting dilution flow. That is:

s =bx c (2.4)

Liquid effluent flow paths and release points are indicated in Figure 2 .1.

2. Composite Samplers Effluent pathways, Turbine Sump and Service Water, are equipped with continuous compositors to meet the requirements of Appendix A, Table D-1. These compositors are adjustable and normally set in a time mode and collect three to six samples hourly, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a day I with a total collection of approximately one gallon per day. A representative sample is collected daily from the compositor and saved for the weekly, monthly analysis requirements of Appendix A, Table D-1. In the event that a compositor is not operational, effluent releases via this pathway may continue provided that grab samples are collected and analyzed for gross beta or gamma radioactivity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per Appendix A, Table C-1, Action 3.

.* . 57 Rev 7 01/01/93

- tl '. . ;*

,. *~**

f ! '.i . ':

3.

Rev1slon 7 A post-release analysis will be done using actual release data to ensure that the li~1ts specified in Section I were not exceeded.

A composite list on concentrations (C 1 ), by isotope, will be used with the actual liquid radwaste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equation 2.3 to demonstrate compliance with the limits in Section I.

This data and setpoints will be recorded in auditable records by Plant personnel.

C. DOSE I. REIS Requirement Appendix A,Section III.H.l requires that the quantity of radionuclides released by limited such that the dose vr dose Il commitment to an individual from radioactive materials in liquid effluents release to unrestricted areas from the reactor (see Figure 2-1) will not exceed:

a. During any calendar quarter, 1.5 mrem to the total body and 5 mrem to any organ, and

b. During any calendar year, 3 mrem to the total body and 10 mrem to any organ.

To ensure compliance, quantities of activity of each radio~uclide released will be su1M1ed for each release and accumulated for each quarter as follows in Section 2.

2. Release Ana1Ys1s Calculations shall be performed for each batch release, and weekly for continuous releases according to the formula:

~ 1 AdC 1 :!> 0.5 (2.5) where:

.. Cumulative quarterly activity of nuclide i identified in liquid release cc,).

Design objective annual quantity of radionuclide i from Tablt: 2. 2 *

58 Rev 7 01/01/93

! 'r ~ . \ .!. * '

Hevislon 7 The design basis quantities are derived in such a con~ervative manner that doses may be ~1reat ly overestimated by this techn i ,~11e.

As a consequence of this conservatism, and tn l lght of historically consistent operations with releases well below annual design basis quantities, the Appendix A, effluent requirements do not require monthly dose projections. Instead, if at any time, calculations by Equation (2.5) results in values greater than 0.5 for a given quarter or 1.0 for year-to-date, the NRC LADTAP code will be run to ensure that Appendix A,Section III.H.l has been met.

Values for the design basis quantities (C 1), and the dose per Curie (Dc/Cc)i for e~ch nuclide i shown in Table 2.2, were calculated as follows in Sections 2.1 and 2.2.

a. Water Ingestion The dose to an individual from ingestion of radioactivity from any source as described by the following equa~ion:

i Dj I: (DCF) ij Y. 1 1 1"'1 (2.6) where:

Dose for the jth organ from radionuclides releases, mrem.

j The organ of interest.

(DCF)IJ Ingestion 3iose commitment factor for the jth organ from the it radionuclide mrem/pCi, see Table 2.1.

Activity ingested of the ith radionuclide, pCi.

11 is described by:

(Ai) (V) (365)

Ii = (1000) (d) (1E06)

(2. 7) where:

365 = Days per year.

A1 Annual activity released of 1th radionuclide, µCi.

V ~ Average rate of water consumption (2000 ml/d - adult, 1400 ml/d - teen and child, 900 ml/d - infant, ICRP 23, p. 358).

d = Dilution water flow for year, ml ..

':*:\ * , *

1 . ' 59 Rev 7 01/01/93

i; l

i Rtw Is I on 7 I

1 1000 ~ Dispersion factor from dlschilrye to ne;trest dri11kiriq water supply.

1E06 .. Conversion µCi to pCi.

The dose equation then becomes:

i (3.65E05)(V) '5' x A 1 mrem D:l "" d lcl (DCF) ij (2.8) b, fish Ingest]on The dose to an individual from the consumption of fish is describe~by Equation 2.10. In this case the activity ingested of the it radionuclide (1 1 ) is described by:

A 1B 1 F(1E09)

I 1 "' = pCi 15d (2.9) where:

Annual released of ith radionuclide, µCi.

.. Fish concentration factor of 1th radionuclide

µCi/gm

µCi/ml (see Table 2.0).

F Amount of fish eaten per year (21 kg adult, 16 kg teen, 6.9 kg child, none infant.)

15 Dispersion factor from discharge tc fish exposure point.

d

Dilution water flow for year, ml.

1E09 "' Conversion of µCi and Kgm to gross.

Substitution of Equation 2.9 into Equation 2.6 gives:

i (6. 7E07) F 't" Dj = d ~. A 1 x B 1 x DCF 1 mrem J.=1 (2.10) 60 Rev 7 01/01/93

,:I';:.

Rov1sion 7 A complete analysis utilizing the NRC computer code LADlAP with the total source release will be done annually in conjunctton with the annual environmental report. This analys;s will provide estimates of dose to the total body and various organs in addition to the dose limiting organs considered in the method of Section 2. The following approach is utilized on LADTAP. The dose to the jth organ from m rad1onuclides, Dj, is described by:

m

n. 't"'

-J "' f:,.J -'f'I 1. m..-.om

~ .. ___ ...

1=1 (2.11}

m

}: (DCF) ij x Ij mrem l"'l where:

. Dose to the jth organ from the ith radionuclide, mrem .

The organ of interest (bone, GI tract, thyroid, liver, kidney, lung or total body}.

(DCF)IJ Adult ingestion 3iose commitment factor for the jth organ from the ;t radionuclide, mrem/pCi (see Table 2.1).

Activity ingested of the ith radionuclide, µCi.

11 for water ingestion is dPscribed by:

A1 Vr I1 = -vcr- µCi (2.13) and for fish ingestion 11 is described by:

I A1 B1 Fr nCi 1 = vd ,..

where:

A, - Activity release of jth radionuclide during the year,

µCi. .

V. .* : -Average<rat*e cif water consumption (2000 ml/d).

... ' .*. r

Number.of days during the *yea~ (365 d).

Rev 7 01/01/93

!11\L~AQI.~- !!V~Lt:!.W PU\KJ Qff~lI_E__QQ}L~tP:JLAI !Qti MAJWAL Revision 7 v Dispersion factor from point of discharge to ~*oint of exposure.

d Dilution water volume (ml).

11Ci/gm

µCi/ml Fish concentration factor of the ;th radionuclide, F Amount of fish eaten per day (57.5 gm/d).

D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT The Palisades liquid radwaste system is designed to reduce the radioactive materials in liquid wastes prior to their discharge (by recycle or shipment for disposal) so that radioactivity in liquid effluent releases to unrestricted areas (see Figure 2-1) will not exceed

., the limits of Appendix A, llI.H.l. Maintaining the cumulative fraction if allowable release for each batch release and weekly for continuous releases assures compliance with this requirement. In addition, 13 years of operating experience (to the date this ODCM was first adopted) has shown that design basis quantities never have been exceeded.

E. RELEASE RATE FOR OFFSITE EC (50 mRem/yr) 10 CFR 20.1302 requires radioactive effluent releases to unrestricted areas be less than the limits specified in Appendix B, Table 2 when averaged over a period not to exceed one year. Concentrations at this level, if ingested for one year, will result in a dose of 50 millirem to the total body. In addition, 10 CFR 50.36a requires that the release of radioactive materials be kept as low as is reasonably achievable.

Appendix I to 10 CFR 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as is reasonably achievable requirement.

The LADTAP code has been run to determine the dose due to drinking water at plant discharge concentration (l,000 x nearest drinking water intake 1.

concentration.) The source term used is given in Table 1.1. Dose to the

,\

~

most limiting organ of the person hypothetically drinking this water is

}' 3.88E-03 mrem. The release rate which would result in a dose rate equivalent to 500 mrem/year (using the more conservative total body limit) is the curies/year given in Table 1.1 (162) times 500/3.BBE-03 or 2.1E07 Ci/yr = 0.661 Ci/sec.

F. FIGURES AND TABLES 62 Rev 7 01/01/93

~.

..... ~::.

)>

~

,...,.,,en I

' ,,.., ,:*~c;.

13,/l I

/

/" **I 1"'!.

I 0

\ / ~- ~

'.I I

\ / **. 10 I *

\

\ I

,, /

i

/ ,*

\ I /

\ /

I /

\ /

\ IJ

/ /

\

...., I I I

/

4

/

~;~l

/

' .. w ' I I HI ,,,

' \ I "' __

~!Z'. / (:

x.

\ /

o...~01 *- )' . I I. (iAS(OUS EJFLUC1t15 IV c::C

~iS

~ ......

Q

~

t

\

.i~ ' J1- /.

~....

sr*a m

- 9..

/

i:::

~~=! /.** .:. I .

~

WiU1 0 I * .* , .

i ..-'\ L*OUIO~ ~

- 1 . * .1'11*

.* '*.:.""" ..;;*- .......*-. ID

~

%1~ "'> ~AO Ill ....,. .1 ,, " \ \ , .... - - - * -

,,,/

Uj

.... I * ' - - -

<:> :'J I \

i...n~ a:

Ci~ I ' ' ' ' ts. ..

c;;ci ,,. I \ '. ._

V";1 0

' I

\

' ' ~

-4~

~:::::: ,

, I \ '

""1

~

.......; *1 l I \ \~f \ ' '

Ol

I s \ \ '

I \ \ ' &t1 .*:t ..'

I \ ' \ ' ;

. I

' \

\

,*,. 71~ METFRS I . , \ \ UIWlt:OTRIC1lD Al\(A I & 19\ Slll IOUNDARY SITE ENVIRONMENT I I \ \ 18 .. '* TLD STATIONS 42 f'ALISADH HUClfAflt Pl.ARI sin AOUNOAftY ***

FICIJRE :! -1

~*.... .-:.:. ]

...... (")

PALISADES RADWASTE EFFLUENTS - LIQUID 1r- -*.

I

°' -

cu-

~ '1" 0:: 0 I' ~ .'

-.0 wv.r~

',Y';.I! ~

PRlllllARY SYST£M S10MG£ TAN!K . ,*:

rqfAllO l'ltl')f{

TOO ... ~

...;1 I Af..ltS 171 TRIP a FLOW CONTROL

~\

~;

~<'

~x\

-JIZ; r.l..01 j_,

SERV1a WAIER _._..__

>-I

~

r-

~~ _J ~~I I Al'ffOtr.; WAST[ sYSt8*

-'! :::1 Zi IOIHTY WA.'>m

<.;I~

~<::

l.Al!'MOllY Ulll.ITY

~

!Ui

<.l')j i > ';Y5 l FM WATEA Q

...ju..D, a:: !5lcYlfAC,£ OJ'-"l *:* -.. *-;_

.:(,0 '11\ttl(

~OI

l~ , ;11 T\Jft91Mt BtDG

_~._

~H rrt 1f :l( II *.* *.;.

~;....j DRAINS -*---.

.r.\

Uo.<

WK.I~

u.~ TAH.._

0' DILUTIOll fLOW St:RVIC£WAT£R~~.,._~..L-~~~~...~lA~Kf__ 1N_LE_T~--i\-

Revl~lon 7 TABLE 2.0 B.IQACCUMUlATION FAC!ORS PC1/gm per uC1/ml FRESHWATER ELEMENT FISH H 9.0E-01 c 4.6E 03 NA l, OE 02 p 1.0E OS.

CR 2.0E 02 MN 4.0E 02 FE I.OE 02 co 5.0E 01 NI 1. OE 02 cu 5.0E 01 ZN 2.0E 03 BR 4.2E 02 RB 2.0E 03 SR 3.0E 01 v 2.SE 01 ZR 3.3E 00 NB 3.0E 04 MO l .OE 01 TC 1.SE 01 RU 1.0E 01 RH l.OE 01 TE 4.0E 02 I 1. SE 01 cs 2.0E 03 BA 4.0E 00 LA 2.SE 01

., CE 1.0E 00 PR 2.SE 01

., ND 2.SE 01

~

w 1. 2E 03

-~ . NP 1. OE 01

!ii

.'l

~*

~'

' '\,, .. . *,. '.

.*;*: ... ., - .. ,.... '**. '.** 65 *. ' ' Rev 7 01/01/93

. ' ' ' .' *~

' . ':, ..* ' i *.*

Rovision 7 TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS {MREH/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEV LUNG Gl-LLI HJ 0. 3.08E-07 3.0BE-07 3.0BE-07 3.08E-07 3.08E-07 3.083-07 BElO l.71E-05 2.49E-06 5.16E-07 0. l.64E-06 0. 2.78E-05 Cl4 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Nl3 5.SSE-08 5.85E-08 5.85E-08 5.835E-08 5.85E-OB 5.85E-08 5.BSE-08 FIS 5.19E-06 0. 4.43E.07 0.

0. 0. 1.22E-06 NA22 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83£-05 9.83E-05 NA24 l.OlE-05 l.OlE-05 l.OlE-05 l.OlE-05 l.OlE-05 1.0lE-05 l.OlE-05 P32 l.70E-03 1.00E-04 6,59E-05 0. 0. 0. 2.30£-05 AR39 0. 0. 0. 0. 0. 0. 0.

AR41 0. 0. 0. 0. 0. 0. 0.

CA41 3.74E-04 0. 4.0SE-05 0. 0. 0. l.91E-07 SC46 3.75E-08 5.41E-08 l.69E-08 0. 3.56E-08 0. 3.53E-05 CR51 0. 0. 1.41E-08 9.20E-09 2.0lE-09 l.79E-08 4.llE-07 MN54 0. l.99E-05 4.SlE-06 0. 4.41E-06 0. 7.31E-06 MN56 0. 8.lSE-07 l.41E-07 0. 7.03E-07 0. 7.43E-05 FESS l.39E-05 8.98E-06 2.40E-06 0. 0. 4.39E-06 l.14E-06 FE59 3.0SE-05 5.38E-05 2.12E-05 0. 0. l.59E-05 2.57E-05 C057 0. 1.15E-06 1.87E-06 0. 0. 0. 3.92E-06 COSS 0. 3.60E-06 8.98E-06 0. 0. 0. 8.97E-06 C060 0. l.08E-05 2.55E-05 0. 0. 0. 2.57E-05 NI59 4.78E-05 l.45E-05 8.17£-06 0. 0. 0. 7.16E-07 NI63 6.34E-04 3.92E-05 2.20E-05 0. 0. 0. l.95E-06 NI65 4.70E-06 5.32E-07 2.42E-07 0. 0. 0. 4.05E-05 CU64 0. 6.09E-07 2.82E-07 0. l.03E-06 0. l.25E-05 ZN65 l.84E-05 6.31E-05 2.91E-05 0. 3.06E-05 0. 5.33E-05 ZN69M+D l.50E-06 3.06E-06 2.79E-07 0. 1.24£-06 0. 4.24E-05 ZN69 9.33E-08 l.68E-07 l.25E-08 0. 6.98E-08 0. 1.37£-05 SE79 0. 2.lOE-05 3.90E-06 0. 2.43E-05 0. 5.58E-07 BR82 0. 0. l.27E-05 0. 0. 0. 0.

BR83+0 0. 0. 3.63E-07 0. 0. 0. 0.

BR84 0. 0. 3.82E-07 0. 0. 0. 0.

BR85 0. 0. l.94E-08 0. 0. 0. 0.

KR83M 0. O. 0. 0. 0. 0. 0.

KR85M 0. 0. 0. 0. 0. 0. 0.

KR85 0. 0. 0.

0. 0. 0. 0.

KR87 0. 0. 0. 0. 0. 0. 0.

KR88+D 0. 0. 0. 0. , . 0. 0. 0.

KR89 0. 0. 0. 0. 0. 0. 0.

RB86 0. l.70E-04 8.40E-05 0. 0. 0. 4.35E-06 RB87 0. 8.88E-05 3.52E-05 0. 0. 0. 5.98E-07 RB88 0. 4.98E-07 2.73E-07 O. 0. 0. 4.85E-07 RB89+0 0. 2.86E-C7 l.97E-07 0. 0. 0. 9.74E-08 SR89+0 2.SlE-03 0. 7.20E-05 0. 0. 0. 5.16E-05 SR90+D l.85E-02 O. 4.71E-03 0. O. 0. 2.31E-04 SR9l+D 5.00E-05 0. l.BlE-06 0. O. 0. 5.92E-05 SR92+0 l.92E-05 0. 7.13E-07 0. 0. 0. 2.07E-04 66 Rev 7 01/01/93

Ruv1s1on 7 T8BlE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 8.69E-08 O. 2.33E-09 0. 0. 0. l.20E-04 Y91M+O 8.lOE-10 0. 2.76E-l! 0. 0. 0. 2.70E-06 Y91 l.lJE-06 O. 3.0IE-08 0. 0. 0. B.lOE-05

¥92 7.65E-09 O. 2.lSE-10 0. 0. 0. l.46E-04 Y93 2.43E-08 O. 6.62£-10 0. O. 0. l.92E-04 ZR93+D 1.93E-07 9.lBE-08 5.54E-08 0. 2.71E-07 0. 2.39E-05 ZR95+D 2.06E-07 5.02E-08 3.56E-08 0. 5.41E-08 0. 2.SOE-05 ZR97+D 1.48E-08 2.54E-09 1.16£-09 0. 2.56£-09 0. 1.62£-04 NB93M l.23E-07 3.33[-03 1.G4E-06 0. 3.25E-08 0. 3.SBE-06 NB95 4.20E-08 l.73E-OB l.OOE-08 0. l.24E-08 0. 1.46E-05 NB97 4.59E-10 9.79E-11 3.53E-ll 0. 7.65E-ll 0. 3.09£-05 M093 0. 5.65E-05 1.82E-06 0. l.13E-05 0. 1.21£-06 M099+D 0. 3.40E-05 6.63E-06 0. 5.0BE-05 0. l.12E-05 TC99M 1.92E-09 3.96E-09 5.lOE-08 0. 4.26E-08 2.0?E-09 l.lSE-06 TC99 1.0BE-06 l.46E-06 4.55E-07 0, 1.23£-05 l.42E-07 6.31E-06 TClOl 2.27E-09 2.86E-09 2.83E-08 0. 3.40E-08 1.56£-09 4.86E-07 RU103+D l.48E-06 0. 4.95£-07 O. 3.08£-06 0. I.BOE-OS RUlOS+D l.36E-07 O. 4.SSE-08 0. l.OOE-06 0. 5.41E-05 RU106+D 2.41E-05 O. 3.01E~06 0. 2.85E-05 0. 1.83E-04 RH105 1.09E-06 7.13E-07 4.79E-07 0. l.98E-06 0. 1.77E-05 PD107 0. 1.19E-06 8.45E-08 0. 6.79E-06 0. 9.46E-07

PD109 0. 1.SOE-06 3.62E-07 0. 5.SlE-06 0. 3.68E-05 AGllOM+D 9.96E-07 7.27E-07 4.81E-07 0. 1.04E-06 0. 3.77E-05 AGlll 5.20E-07 2.02E-07 i.07E-07 0. 4.22E-07 0. 4.82E-05 CD113M 0. 1.77E-05 6.52E-07 0. 1.34E-05 0. 2.66E-05 CDllSM 0. 1.42E-05 4.93E-07 0. 7.41E-06 0. 8.09E-05 SN123 2.49E-04 3.89E-06 6.SOE-06 3.91E-06 0. 0. 6.58E-05 SN125+D 7.41E-05 l.38E-06 3.29E-06 l.36E-06 0. 0. 1.llE-04 SN126+D 5.53E-04 7.26E-06 l.BOE-05 l.91E-r5 0. 0. 2.52E-05 58124 2.14E-05 3.ISE-07 6.63E-06 5.68E-08 0. l.34E-05 6.60E-05 SB125+D l.23E-05 1.19E-07 2.53E-06 l.54E-08 0. 7.72E-06 l.64E-05 SB126 8.06E-06 l.58E-07 2.91E-06 6.19E-08 0. 5.07E-06 8.35E-05 SB127 2.23E-06 3.98E-08 6.90E-07 2.84E-08 0. 1.15E-06 5.91E-05 TE125M 2.33E-05 1.79E-06 3.lSE-06 7.84E-06 0. O. l.llE-05 TE127M+D 5.85E-05 l.94E-05 7.0SE-06 l.69E-05 1.44E-04 0. 2.36E-05 TE127 l.OOE-06 3.35E-07 2.lSE-07 8.14E-07 2.44E-06 0. 2.lOE-05 TE129M+D l.OOE-04 3.43E-05 l.54E-05 3.84E-05 2.SOE-04 0. 5.97E-05 TE129 - 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 O. 2.27E-05 TE131M+D l.52E-05 6.12E-06 5.0SE-06 l.24E-05 4.21E-05 0. l.03E-04 TE13l+D l.76E-07 6.SOE-08 4.94E-08 1.57E-07 4.SOE-07 0. 7.llE-06 TE132+D 2.0SE-05 l.03E-05 9.61E-06 1.52E-05 6.44E-05 0. 3.SIE-05 TE133M+O, __ ,3.91E"'.07 .1.79E-07 1.71E-07 3.45E-07 l.22E-06 0. l.93E-05 TE134+D .2*.67E-or**t~34E-li7 l.38E-07 2.39E-07 9.03E-07 0. 3.06E-06 1129 :; 2'~86E-05~'-**2:~12E-OS l.SSE~os l.36E-02 2.SlE-05 0. 4.24E-07 1130 . ,~_:. 6.00E-06 . L'32E"'.05 5.30E-06 l.48E-03 l.45E-05 0. 2.83E-06 1131+0 *. *_ .-_ 3.59E-05: _4.23E-05 1.86E-05 l.39E-02 4.94E-05 0. 1.SlE-06 Rev 7 01/01/93

l 1 fAll~AO U_li!lJ~lfAfLP LA.MI Qff} 1IL!lQ~L~Al.,UlAllQKJ1J\JilJA!.

l *

- - - - - - * - - - - - - - - - - R c _ v _ i _ s1_o_n_1_ _ _ _ _ _ _ _ _ _ - - - - -

TABLE 2.1 CHILD INGESTION DOSE COHHITHENT FACTORS (HREH/50Y PER PCI INGESTED IN FIRST Yn)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUHG GI-lll H3 0. 2.03E-07 2.03£-07 2.03E-07 2.03E-07 2.03£-07 2.03£-07 8£10 1.35£-05 1.57£-06 3.39E-07 0. l.llE-06 0. 2.75£-05 Cl4 1.21£-05 2.42£-06 2.42£-06 2.42£-06 2.42£-06 2.42£-06 2.42£-06 N13 3.lOE-08 3.lOE-08 3.lOE-08 3.lOE-08 3.10£-08 3.lOE-08 3.lOE-08 Fl8 2.49£-06 O. 2.47£-07 0. 0. 0. 6.74£-07 NA22 5.88£-05 5.88£-05 5.88£-05 5.88£-05 5.88£-05 5-88£-05 5.88£-05 NA24 5.80£-06 5.80E-06 5.80£-06 5.80£-06 5.80£-06 5.80£-06 5.80£-06 P32 8.25£-04 3.86£-05 3.18E-05 0. 0. 0. 2.28E-05 AR39 O. 0. o. 0. 0. 0. O.

AR41 0. 0. 0. 0. 0. 0. 0.

j CA41 SC46 CR51 3.47E-04 0.

1.97£-08 2,70£-08

0. 0.

3.79£-05 1.04£-08 8.90£-09 0.

0.

4.94£-09 0.

2.30£-08 1.35£-09 0.

0.

9.02£-09 1.90£-07 3.95£-05 4.72£-07 l MN54 MN56 FESS 0.

0.

1.07£-05 3.34£-07 1.15£-05 6.lOE-06 2.85[-06 7.54£-08 1.89£-06 0.

0.

3.00E-06 4.04£-07 0.

0.

3.45£-06 8.98£-06 4.84£-05 1.13£-06 l FE59 C057 1.65£-05 2.67£-05

0. 4.93£-07 1.33£-05 9.98£-07 0.

0.

7.74£-06 0.

2.78£-05 4.04£-06 C058 0. 1.80£-06 5.51E-06 0. 0. 0. 1.05£-05 i.*

C060 0. 5.29£-06 1.56£-05 0. 0. 0. 2.93E-05 NI59 4.02E-05 l.07E-05 6.82E-06 O. 0. 0. 7.10E*07 NI63 5.38E-04 2.88E-05 1.83£-05 0. 0. 0. l.94E-06 1!

NI65 2.22£-06 2.09£-07 1.22£-07 O. 0. 0. 2.56£-05

i CU64 0. 2.45£-07 l.48E-07 0. 5.92£-07 0. l.15E-05

'! ZN65 l.37E-05 3.65£-05 2.27E-05 0. 2.30£-05 0. 6.41E-06 ZN69M+D 7.IOE-07 l.21E-06 1.43£-07 0. 7.03£-07 0. 3.94E-05 ZN69 4.38E-08 6.33E-08 5.85E-09 0. 3.84£-08 0. 3.99£-06 SE79 0. 8.43£-06 1.87£-06 0. 1.37£-05 0. 5.53£-07 BR82 0. 0. 7.55£-06 0. 0. 0. 0.

BR83+D 0. 0. 1. 71£-07 0. 0. 0. 0.

BR84 0. 0. 1.98£-07 0. 0. 0. 0.

BR85 0 0. 9.12E-09 0. 0. 0. 0.

KR83M 0. 0. 0. 0. 0. 0. 0.

KR85M 0. 0. 0. 0. 0. 0. 0.

KR85 0. O. O. 0. 0. 0. O.

KR87 0. 0. O. 0. O. 0. 0.

KR88+D 0. 0. 0. 0. 0. 0. 0.

KR89 0. O~ 0. 0. 0. 0. 0.

RB86 0. 6.70E-05 4.12E-05 0. 0. 0. 4.31£-06 RB87 0. - 3.9SE-05 l.83E-OS 0. O~ 0. 5.92£-07 RB88 0. l.90E-07 l.32E-07 0. 0. 0. 9.32£-09 RB89+D 0. l.17E-07 l.04E-07 O. 0. 0. l.02E-09 SR89+0 l.32E-03 0. 3.77E-05 O. O. ~- 5.llE-05 SR90+D l.70E-02 0. 4.31E-03 0. 0. 0. 2.29£-04 SR9l+D 2.40E-05 O. 9.06E-07 0. 0. O. 5.30£-05 SR92+D 9.03£-06 0. 3.62£-07 O. 0. 0. 1.71£-04 70 Rev 7 01/01/93

';~** *..., .

PA.l l :SAD f~J11J_~ UJ\H. .. PLAHf Qff}l TI. QQ~LG~L<::Jl6AI 1Qlt .fV\NW\l Hev1slon 7 180LE 2.1 CHILD INGESTION DOSE COHHlTHENT FACTORS (HREH/50Y PER PCl INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI V90 4. llE-08 0. l. lOE-09 0. 0. 0. l.17E-04 Y91M+O 3.82E-10 0. 1.39£-11 0. 0. 0. 7.48E-07 Y91 6.02E-07 0. l.61E-08 0. 0. 0. 8.02E-05 V92 . 3.60E-09 0. 1.0JE-10 0. 0. 0. l.04E-04 Y93 l.14E-08 0. 3.13E-10 0. 0. 0. l.70E-04 ZR93+0 1.67E-07 6.25E-08 4.45E-08 0. 2.42E-07 O. 2.37E-05 ZR95+0 l.16E-07 2.SSE-08 2.27E-08 0. 3.65E-08 0. 2.66E-05 ZR97+0 6.99E-09 l.OlE-09 5.96E-10 0. l.45E-09 0. l.53E-04 NB93M l.OSE-07 2.62E-08 8.61E-09 o. 2.83E-08 0. 3.95E-06 NB95 2.25E-08 8.76E-09 6.26E-09 0. 8.23E-09 0. l.62E-05 NB97 2.17E-10 3.92E-ll l.83E-ll 0. 4.35E-ll 0. l.21E-05 M093 0. 2.41E-05 8.65E-07 0. 6.35E-06 0. l.22E-06 M099+D 0. l.33E-05 3.29E-06 0. 2.84E-05 0. l.lOE-05 TC99M 9.23E-10 l.81E-09 3.00E-08 0. 2.63E-08 9.19E-10 l.03E-06 TC99 5.35E-07 5.96E-07 2.14E-07 0. 7.02E-06 5.27E-08 6.25E-06 TC!Ol l.07E-09 l.12E-09 l.42E-08 0. l.91E-08 5.92E-10 3.56E-09 RU103+D 7.31E-07 0. 2.81E-07 0. 1.84E-06 0. l.89E-05 RUIOS+D 6.45E-08 0. 2.34E-08 0. 5.67E-07 0. 4.21E-05 RU106+D l.17E-05 0. 1.46E-06 0. I.SSE-OS 0. l.82E-04 RH105 5.14E-07 2.76E-07 7.36E-07 0. l.lOE-06 0. l.71E-05 PD107 0. 4.72£-07 4.0lE-08 0. 3.95E-06 0. 9.37E-07 PD109 0. 5.67E-07 1.70E-07 0. 3.04E-06 0. 3.35E-05 AGllOM+D 5.39E-07 3.64E-07 2.91E-07 0. 6.78E-07 0. 4.33E-05 AGlll 2.48E-07 7.76E-08 5.12E-08 0. 2.34£-07 0. 4.75E-05 CD113M 0. 1.02E-05 4.34E-07 0. l.OSE-05 0. 2.63E-05 CD115M 0. 5.89E-06 2.51E-07 0. 4.38E-06 0. 8.0IE-05 SN123 1.33E-04 l.65E-06 3.24E-06 l.75E-06 0. 0. 6.52E-05 SN125+D 3.SSE-05 5.35E-07 l.59E-06 5.55E-07 0. 0. l.lOE-04 SN126+D 3.33E-04 4.15E-06 9.46E-06 l.14E-06 0. 0. 2.50E-05 58124 1.llE-05 1.44E-07 3.89E-06 2.45E-08 0. 6.16E-06 6.94E-05 SB125+0 7.16E-06 5.52E-08 l.50E-06 6.63E-09 0. 3.99E-06 l.71E-05 SB126 4.40E-06 6.73E-08 l.58E-06 2.SBE-08 0. 2.lOE-06 8.87E-05

--~ SB127 1.06E-06 l.64E-08 3.68E-07 l.18E-08 0. 4.60E-07 5.97E-05

..:.~ TE125M l.14E-05 3.09E-06 1.52E-06 3.20E-06 0. 0. l.lOE-05 TE127M+D 2.89E-05 7.78E-06 3.43E-06 6.91E-06 B.24E-05 0. 2.34E-05

h- TE127 4.71E-07 l.27E-07 l.OlE-07 3.26E-07 l.34E-06 0. l.84E-05 TE129M+D 4.87E-05 l.36E-05 7.56E-06 l.57E-05 l.43E-04 O. 5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0. a~34E-06 TE131M+D 7.20E-06 2.49E-06 2.65E-06 5.l2E-06 2.41E-05 0. l.OlE-04 TE13l+D 8.JOE-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0. 4.36E-07 TE132+D 1.0lE-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0. 4.50E-05

-.'.!. TE133M+D 1.SJE-07 7.56E-08 9.37E-08 l.45E-07 7.ISE-07 0. 5.77E-06

-~ ::~:\' . TE134+D 1.29E-07 5.BOE-08 7.74E-08 l.02E-07 5.37E-07 O. 5.89E-07 1129 l.39E-05 8.53E-06 7.62E-06 5.58E-03 l.44E-05 0. 4.29E-07 1130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0. 2.76E-06 1131+0 1.72E-05 1~73E-05 9.83E-06 5.72E-03 2.84E-05 0. 1.54E-06

. -*: :". 71 Rev 7

,*, .*' 01/01/93

: * I

}_ ; *" ' ,',.

PJ\_JJ SAJ}U~Jl~!.l.NLPJ..J\JU Qf_illTLQQil_~lli!JLAINN__ l't}._Nllf16 Rcvts1on 7 IML~ 2.1 CHILD INGESTION DOSE COMHITHENT FACTORS (HREM/50Y PER PCI INGESTED JN FIRST tR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GJ-LLI 1132 8.00E-07 ) .47£-06 -6.76E-07 6.82E-05 2.25[-06 0. l. 73E-06 1133+0 S.92E-06 7.32E-06 2.77E-06 1.36[-03 l.22E-05 0. 2.95[-06 1134 4.19E-07 7.78E-07 3.58E-07 l.79E-05 1.19£-06 0. 5.16[-07 I 135+0 1. 75E-06 3. lSE-06 1.49E-06 2.79E-04 4.83E-06 0. 2.40E-06 XE131M o. 0. o. 0. 0. 0. 0.

XE133M o. 0. 0. o. o. o. 0.

XElll o. 0. 0. 0. 0. o. 0.

XE135M 0. 0. 0. o.

0. 0. 0.

XE135 o. n

\I.

n

v. v. "u. 0. 0.

XE137 0. 0. o. 0. 0. 0. 0.

XE138t0 o. 0. 0. 0. 0. 0. 0.

CS134M+O 8.44E-08 1.25£-07 8. 16E-08 0. 6.59£-08 I. 09E-08 I. 58E-07 CS134 2.34£-04 3.84E-04 8.lOE-05 0. 1.19£-04 4.27E-05 2.07[-06 CS135 8.30E-05 5.78E-05 5.93E-06 0. 2.04E-05 6.81E-06 4.33£-07 CS136 2.35£-05 6.46E-05 4.18[-05 o. 3.44E-05 5.13E-06 2.27E-06 CS137+0 3.27E-04 3 .13E-04 4.62[-05 0. 1. 02E-04 3.67E-05 1. 96E-06 CS138 2.28E-07 3.17E-07 2.0lE-07 o. 2.23E-07 2.40E-08 l.46E-07 CS139t0 l.45E-07 l.61E-07 7.74E-08 0. l.21E-07 l.22[-08 l.45E-ll BA139 4.14E-07 2.21E-10 1. 20E-08 0. l.93[-10 l.30[-10 2.39[-05 BA140t0 8.31E-05 7.28[-08 4.85E-06 0. 2.37[-08 4.34[-08 4.21E-05 BA14lt0 2.00E-07 l.12E-10 6.51E-09 0. 9.69E-ll 6.SBE-10 1.14£-07 BA142t0 8.74E-08 6.29£-11 4.88E-09 0. 5.09E-ll 3.70£-11 1. g[-09 LA140 1.0lE-08 3.53£-09 1.19£-09 o. 0. 0. 9.84E-05 LA141 1. 35£-09 3.17£-10 6.88E-ll 0. o. 0. 7.0SE-05 LA142 5.24E-10 1.67E-10 5.23£-11 o. o. 0. 3.31£-05 CE141 3.97E-08 1. 98E-08 Z.94E-09 o. 8.68E-09 0. 2.47E-05 CE143t0 6.99E-09 3.79E-06 5.49£-10 0. 1.59E-09 0. 5.55E-05 CE144t0 2.08£-06 6.52[-07 l. llE-07 0. 3.61E-07 o. 1. 70E-04 PR143 3.93E-08 l.18E-08 1. 95E-09 o. 6.39E-09 0. 4.24E-05 PR144 l.29E-10 3.99E-ll 6.49E-12 0. 2.llE-11 o. 8.59E-08 ND147tD 2.79[-08 2.26[-08 l.75E-09 0. 1. 24E-08 0. 3.58E-05 PM147 3.18E-07 2.27[;.08 1. 22E-08 o. 4.0lE-08 0. 9.19E-06 PM148Mt0 1.03E-07 2.0SE-08 2.0SE-08 0. 3.04E-08 0. 5.78E-05 PM148 3.02E-08 3.63E-09 2.35E-09 o. 6.17E-09 0. 9.70E-05 PM149 6.49E-09 6.90E-10 3.74E-10 o. l.22E-09 0. 4.71E-05 PM151 2.92E-09 3.SSE-10 2.31£-10 o. 6.02E-l0 0. 4.0lE-05 SM151 2.56E-07 3.BlE-08 1. 20E-08 o. 3.94E-08 0. 5.53E-06

., SM153 3.65£-09 2.27E-09 2.19E-10 0. 6.91E-10 o. 3.02E-05 EU152 6.lSE-07 l.12E-07 l.33E-07 o. 4.73E-07 o. l.84E-05

' EU154_ 2.30E-06 2.07[-07 1.89E-07 o. 9.09E-07 o. 4.81E-05 EU155 4.82E-07 3.47E-08 2.72E-08 0. 1. 30E-07 o. 8.69E-05 EU156 5.52E-08 3.0lE-08 6.23[-09 0. l.94E-08 o. 6.83E-05 TB160 l.66E-07 o.. 2.06E-08 0. 4.94E-08 o. 3.68£-05 H0166H 1.0BE-06 2.i!6E-07 1. 91E-07 0. 3.22E-07 o. 0.

W181 4.23E-06 1.04E-08 1.43£-09 0. o. o. 3.79£-07 WISS -I.73E-06 4.32E-07 6.0SE-08 o. o. o. 1.61E-05 W187 4.29E-07 2.54E-07 1.14£-07 0. o. o. 3.57E-05

,'!** 72 Rev 7 01/01/93

Rev1s1on 7 IAfil.LL.l CHILD INGESTION DOSE COMHITHENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST ~h~

ISOTOPE BONE LIVER TOTAL DODY THYROID KIDNEY LUNG GI-lll PB210+D 4.75£-02 l.22E-02 2.09E-03 0. 3.67E-02 0. 5.57£-05 81210+0 l.97E-06 l.02E-05 l.69E-07 0. l.lSE-04 0. 5.17E-05 P0210 1.52E-03 2.43E-03 3.67E-04 0. 7.56E-03 0. 6.55E-05 RN222+0 0. 0. 0. 0. 0. 0. 0.

RA223+0 2.12£-02 2.45£-05 4.24£-03 0. 6.SOE-04 0. 3.38E-04 RA224+0 6.89E-03 1.25£-05 1.38£-03 0. 3.31E-04 0. 3.78E-04 RA225+0 2.SOE-02 2.50E-05 5.59£-03 0. 6.62£-04 0. 3.21E-04 RA226+D 5.75E-Ol l.84E-05 4.72E-Ol 0. 4.88E-04 0. 3.41E-04 RA228+0 3.85£-01 9.99E-06 4.32E-Ol 0. Z.65E-04 0. 5.81E-05 AC225 1.88E-05 l.94E-05 1.26£-06 0. 2.07E-06 ~. 4.31E-04 AC227+0 4.12£-03 6.63E-04 2.SSE-04 0. l.46E-04 0. 8.43E-05 TH227+0 5.85E-05 7.96E-07 1.69£-06 0. 4.22E-06 0. 5.63E-04 TH228+D 2.07£-03 2.65E-05 7.00E-05 0. l.38E-04 0. 5.79E-04 TH229 1.38£-02 l.81E-04 6.80£-04 0. 8.84£-04 0. 5.27E-04 TH230 3.55E-03 1.78E-04 9.91E-05 0. 8.67£-04 0. 6.19E-05 TH232+0 3.96£-03 1.52E-04 3.0lE-04 0. 7.41E-04 0. 5.27E-05 TH234 3.42£-07 l.SlE-08 9.88£-09 0. 8.0lE-08 0. 1.18E-04 PA23l+D 7.07£-03 2.34E-04 2.81£-04 0. 1.28£-03 0. 7.37E-05 PA233 1.81£-08 2.82£-09 3.16£-09 0. 1.04£-08 0. 1.44E-05 U232+0 1.76£-02 0. l.26E-03 0. 1.34£-03 0. 6.98E-05 U233+0 3.72E-03 0. 2.2~£-04 O. 6.lOE-04 0. 6.45E-05 U234 3.57£-03 0. 2.21£-04 0. 5.98£-04 0. 6.32E-05 U235+0 3.42£-03 0. 2.07E-04 0. 5.61E-04 0. 8.03E-05 U236 3.42E-03 0. 2.12£-04 0. 5.73E-04 0. 5.92£-05 U237 2.36E-07 0. 6.27E-08 0. 6.81E-07 0. 2.08E-05 U238+0 3.27E-03 0. l.94E-04 0. 5.24E-04 0. 5.66E-05 NP237+D 2.36£-03 l.81E-04 9.79E-05 0. 6.05£-04 0. 8.16E-05 NP238 5.83£-08 1.18£-09 9.08E-10 0. 3.76£-09 0. 4.04£-05 NP239 5.25E-09 3.77E-10 2.65E-10 0. l.09E-09 0. 2.79E-05 PU238 l.25E-03 1.56£-04 3.16£-05 0. l.lSE-04 0. 7.50£-05 PU239 i.36E-03 1.65£-04 3.31E-05 0. l.22E-04 0. 6.85£-05 PU240 1.36£-03 1.65£-04 3.31E-05 0. l.22E-04 0. 6.98E-05 PU241+0 4.00E-05 1.72£-06 8.04E-07 0. 2.96E-06 0. l.44E-06 PU242 l.26E-03 1.59£-04 3.19E-05 0. l.17E-04 0. 6.71E-05 PU244 l.47E-03 1.82£-04 3.65E-05 0. l.35E-04 0. l.OOE-04 AM241 l.43E-03 6.40E-04 l.02E-04 0. 6.23£-04 0. 7.64E-05 AM242M 1.47£-03 6.25£-04 l.04E-04 0. 6.30E-04 0. 9.61E-05 AM243 l.41E-03 6.14E-04 9.83E-05 0. 6.06E-04 0. 8.95E-05 CM242 8.SOE-05 6.73£-05 5.84E-06 0. l.87E-05 0. 8.16E-o5*

CM243 l.33E-03 6.03£-04 8.24E-05 0. 3.08E-04 0. 8.03E-05 CM244 l.llE-03 5.36£-04 6.93£-05 0. 2.54E-04 0. 7.77E-05 CM245 1.76£-03 6.64E-04 l.05E-04 0. 4.llE-04 0. 7.24E-05 CM246 l.74E-03 6.64£-04 l.05E-04 0. 4.lOE-04 0. 7.llE-05 CM247+0 l.70E-03 6.53E*04 l.03E-04 0. 4.04£-04 0. 9.35E-05 CM248 l.41E-02 5.38E-03 8.52E-04 0. 3.33E-03 0. 1.51£-03 CF252. l.07E-03 O. 2.54E-05 0. 0. 0. 2.96£-04

-.-L

, *~

73 Rev 7 01/01/93

lAB.lLLl TEEN INGESTION DOSE COHHITMENT FACTORS (MREM~50Y PER PCI INGESTED IN FIRST Yk/

ISOTOPE DONE LIVER TOTAL BODY HYROID KIDNEY LUHG GI-LLJ H3 0. l.06E-07 l.06E-07 l.06E-07 l.06E-07 l.06E-07 l.06E-07 BElO 4.48E-06 6.94E-07 l .13E-07 0. 5.JOE-07 0. 2.84E-05 Cl4 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12£-07 Nl3 l.15E-08 1. ISE-08 l.ISE-08 1. J SE-08 1.15£-08 l.15E-08 1.ISE-08 Fl8 8.64E-07 0. 9.47E-08 o. 0. 0. 7.78E-08 NA22 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 NA24 2.30E-06 2.30E-06 2.30E-06 2.JOE-06 2.30E-06 2.30£-06 2.30E-06 P32 2.76E-04 l.71E-05 1. 07E-05 0. 0. 0. 2.32E-05 AR39 o. 0. 0. 0. 0. 0. o.

AR41 0. 0. 0. 0. 0. 0. 0.

CA41 l.97E-04 0. 2.13E-05 0. 0. 0. 1. 95E-07 SC46 7.24E-09 I. 41 (-08 4. lSE-09 0. l.35E-08 0. 4.BOE-05 CRSl 0. 0. 3.60£-09 2.00E-09 7.89E-10 5.14£-09 6.0SE-07 MN54 0. 5.90E-06 !.17E-06 0. l.76E-06 0. 1.21E-05 MN56 0. 1. 58E-07 2.BlE-08 0. 2.00E-07 0. l.04E-05 FESS 3.78E-06 2.68E-06 6.25E-07 0. 0. l. 70E-06 l.16E-06 FE59 5.87E-06 l.37E-OS 5.29E-06 0. 0. 4.32E-06 3.24E-05 C057 0. 2.38E-07 3.99£-07 o. 0. 0. 4.44E-06 COSS o. 9.72E-07 2.24E-06 0. 0. 0. l.34E-05 C060 0 2.81E-06 6.33E-06 0. 0. 0. 3.66E-05 NI59 l.32E-05 4.66E-06 2.24E-06 0. 0. 0. 7.31E-07 NI63 1. 77E-04 1. 25E-05 6.00E-06 0. 0. 0. 1. 99E-06 NI65 7.49E-07 9.57E-08 4.36£-08 0. 0. o. 5.193-06 CU64 0. l.lSE-07 S.41E-08 0. 2.91£-07 o. 8.92E-06 ZN65 5.76E-06 2.00E-05 9.33E-06 0. 1. 28E-05 0. 8.47E-06 ZN69M+D 2.40E-07 5.66E-07 5.19E-08 0. 3.44E-07 0. 3.llE-05 ZN69 1.47£-08 2.80E-08 1. 96E-09 0. l.83E-08 0. 5 .16E-08 SE79 0. 3.73E-06 6.27E-07 0. 6.SOE-06 0. 5.70E-07 BR82 0. o. 3.04E-06 0. 0. 0. 0.

BR83+D 0. 0. 5.74E-08 0. 0. 0. 0.

BR84 0. 0. 7.22E-08 0. 0. 0. o.

BRSS. 0. 0. 3.0SE-09 o. 0. 0. 0.

KR83M 0. 0. o. 0. 0. o. o.

KR85M 0. 0. 0. o. o. 0. o.

KR85 0. 0. 0. o. 0. 0. 0.

KR87 0. 0. 0. 0. 0. o. 0.

KR88+0 0. 0. 0. 0. 0. 0. 0.

KR89 0. 0. o. 0. 0. o. o.

RB86 0. 2.98E-05 l.40E-05 0. 0. o. 4.41E-06 RB87 0. l.75E-05 6. llE-06 o. 0. 0. 6. llE-07 RB88 o. 8.52E-08 4.54E-08 0. 0. 0. 7.30E-15 RB89+D 0. 5.SOE-08 3.89E-08 o. 0. 0. 8. 43E-17 SR89+D 4.40E-04 o. 1. 26E-05 o. 0. o. 5.24E-05 SR90+0 8.30E-03 o. 2.0SE-03 0. o. o. 2.33E-04 SR9l+D 8.07E-06 0. 3.21E-07 0. 0. o. 3.66E-05 SR92+0 3.0SE-06 0. l.30E-07 0. o. o. 7.77E-05

l.

74 Rev 7 01/01/93

PAUiN2L) fil.JClfAR J>J.l\NT QJnlTI QQ~(_C8lCULAf10N MANl)l\l_

LIVER Revls1on 7 IAftlLl.~l TEEN INGESTION DOSE COMMITMENT FACTORS {MREH/50Y PER PCl INGESTED JN FIRST YR, TOTAL BODY THYROID LUNG GI-LU ISOTOPE BONE KIDNEY Y90 1. 37£-08 0. 3.69E-10 0. 0. 0. l.13E-04 Y91M+O 1.29£-10 0. 4.93E-12 0. 0. 0. 6.09E-09 V91 2.0lE-07 0. 5.39£-09 0. 0. 0. 8.24E-05 V92 1. 21E-09 0. 3.SOE-11 0. 0. 0. 3.32E-05 V93 3.83£-09 0. l.OSE-10 0. 0. 0. 1.17£-04 ZR93+0 5.53£-08 2.73E-08 1.49£-08 o. 9.65E-08 0. 2.58£-05 ZR95+0 4. l2E-08 1. lOE-08 8.94£-09 0. 1.91£-08 0. 3.00E-05 ZR97+0 2.37E-09 4.69E-10 2.16E-10 0. 7.llE-10 0. J.27£-04 NB93M 3.44E-08 l.13E-08 2.83£-09 0. I. 32£-08 0. 4.07£-06 NB95 8.2££-09 4.56£-09 2.SlE-09 0. 4.42E-09 0. 1. 95£-05 NB97 7.37£-11 1. 83£-11 6.68E-12 0. 2.14£-11 0. 4.37E-07 M093 0. 1. 06£-05 2.90E-07 0. 3.04E-06 0. I. 29E-06 M099+D 0. 6.03E-06 l.15E-06 0. l.38[-05 0. 1. OSE-05 TC99M 3.32£-10 9.26E-10 l.20E-08 0. l.38E-08 5.14E-10 6.08£-07 TC99 1.79£-07 2.63E-07 7.17E-08 0. 3.34£-06 2.;2E-08 6.44E-06 TC!Ol 3.60£-10 5.12E-10 5.03E-09 0. 9.26E-09 3.12E-10 8.75E-17 RU103+0 2.SSE-07 0. l.09E-07 0. 8.99E-07 0. 2.13E-05 RUlOS+D 2.18E-08 0. 8.46E-09 0. 2.75E-07 0. 1.76E-05 !

RU106+0 3.92E-06 o. 4.94E-07 0. 7.56E-06 0. 1.88£-04 t*

5.31E-07 0. i,,

RH105 1. 73E-07 l.25E-07 8.20£-08 0. 1.59E-05 PD107 0. 2.08E-07 l.34~-08 0. l.88£-06 o. 9.66E-07 I:

PD109 0. 2.51E-07 5.70£-08 0. 1.45£-06 0. 2.53E-05 ..I AGllOM+D 2.05E-07 t. 94E-07 l.18E-07 0. 3.70E-07 0. 5.45£-05 AGlll 8.29E-08 3.44E-08 0.

l.73E-08 0.

4.51E-06 1.45E-07 o.

l.12E-07 o.

4.99£-06 0.

4.SOE-05 2.71E-05 t f CD113M i CD115M 0. 2.60E-06 8.39E-08 0. 2.0SE-06 0. 8.23E-05 '

0. I SN123 4.44E-05 7.29E-07 l.08E-06 5.84£-07 0. 6.71£-05 l**

SN125+0 l.19E-05 2.37E-07 5.37E-07 1.86E-07 0. 0. 1.12£-04 'i**

SN126+0 1.16£-04 2.16£-06 3.30[-06 5.69E-07 0. 0. 2.58E-05 f-SB124 3.87E-06 7.13E-08 1.51£-06 8.78E-Q9 0. 3.38E-06 7.SOE-05 r SB125+D 2.48E-06 2. 71E-08 5.SOE-07 2.37E-09 0. 2 .18E-06 I. 93E-05 SB126 l.59E-06 3.25E-08 5.71E-07 8.99E-09 0. l.14E-06 9.41E-05 SB127 3.63E-07 7.76E-09 l.37E-07 4.08E-09 0. 2.47E-07 6.16E-05 TE125M 3.83E-06 I.38E-06 5.12E-07 l.07E-06 0. 0. l.13E-05 TE127M+D 9.67E-06 3.43E-06 l. ISE-06 2.30E-05 3.92E-05 o. 2.41E-05 ['

TE127 I. 58£-07 5.60£-08 3.40E-08 1.09E-07 6.40E-07 o. I. 22E-05 TE129M+D l.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82£-05 0. 6.12E-05 TE129 4.48E-08 l.67E-08 1.09£-08 3.20£-08 1.88E-07 0. 2.45£-07 TE131M+D 2.44E-06 1.17£-06 9.76E-07 1. 76E-06 l.22E-05 o. 9.39£-05 TE13l+D 2.79E-08 l.15E-08 8.72£-09 2.15£-08 1. 22E-07 0. 2.29E-09 TE132+D 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2 .12E-05 0. 7.00E-05 TE133M+D 6.44E-08 3.66E-08 3.56E-08 5.llE-08 3.62£-07 0. 1.48E-07 TE134+D 4.47E-08 2.87E-08 3.00E-08 3.67E-08 2.74E-07 o. l.66E-09 1129 4.66E-06 3.92E*06 6.54E-06 4. 77E-03 7.'0lE-06 o. 4.57E-07

!130 l.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59£-06 o. 2.29E-06 .'

1131+0 5.85E-06 8.19E-06 4.40E-06 2.39E-03 l.41E-05 0. I. 62E-06 '

75 Rev 7 01/01/93 i"

Revision 7 TABLE 2.1 TEEN INGESTION DOSE COHHITMENT FACTORS (HREH/50Y PER PCI INGESTED IN FlRSl Y~~

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GJ-LLI 1132 2.79E-OJ 7.JOE-07 2.62E-OJ 2.46E-05 l.15E-06 0. 3.18E-07 1133+0 2.0lE-06 3.41E-06 l.04E-06 4.76E-04 5.98E-06 0. 2.58E-06 1134 l.46E-07 3.87E-07 l.39E-07 6.45E-06 6.lOE-07 0. 5.lOE-09 1135+0 6.lOE-07 l.57E-06 5.82E-07 l.OlE-04 2.48E-06 0. l.74E-06 XE131M O. 0. O. 0. 0. O. 0.

XE133M 0. 0. O. 0. 0. 0. O.

XE133 0. O. O. O. 0. O. 0.

XE135M O. 0. 0. 0. 0. 0. O.

XE135 O. 0. O. o. O. o. o.

XE137 . 0. 0. o. 0. 0. O. 0.

XE138+0 0. 0. O. 0. 0. 0. 0.

CS134M+D 2.94E-08 6.09E-08 3.13E-08 0. 3.39E-08 5.95E-09 4.05E-08 CS134 8.37E-05 l.97E-04 9.14E-05 0. 6.26E-05 2.39E-05 2.45E-06 CS135 2.78E-05 2.SSE-05 5.96E-06 0. 9.73E-06 3.52E-06 4.46E-07 CS136 8.59E-06 3.38E-05 2.27E-05 0. l.84E-05 2.90E-06 2.72E-06 CS137+0 l.12E-04 l.49E-04 5.19E-05 0. 5.07E-05 l.97E-05 2.12E-06 CS138 7.76E-08 l.49E-07 7.45E-08 0. l.lOE-07 l.28E-08 6.76E-ll CS139+0 4.87E-08 7.17E-08 2.63E-08 O. 5.79E-08 6.34E-09 3.33E-23 BA139 l.39E-07 9.78E-ll 4.05E-09 0. 9.22E-ll 6.74E-ll l.24E-06 BA140+0 2.84E-05 3.48E-08 l.83E-06 O. l.18E-08 2.34E-08 4.38E-05 BA141+0 6.71E-08 5.0lE-11 2.24E-09 0. 4.65E-11 3.43E-ll l.43E-13 BA142+0 2.99E-08 2.99E-11 l.84E-09 O. 2.53E-ll l.99E-ll 9.IBE-20 LA140 3.48E-09 l.71E-09 4.SSE-10 0. 0. 0. 9.82E-OS LA141 4.SSE-10 l.40E-10 2.31E-ll 0. 0. 0. 2.48E-05 LA142 l.79E-10 7.95E-ll l.98E-11 0. 0. 0. 2.42E-06 CE141 l.33E-08 8.BBE-09 l.02E-09 0. 4.lBE-09 0. 2.54E-05 CE143+0 2.35E-09 l.71E-06 l.91E-10 O. 7.67E-10 0. 5.14E-05 CE144+0 6.96E-07 2.88E-07 3.74E-08 0. l.72E-07 0. l.75E-04 PR143 l.31E-08 5.23E-09 6.52E-10 O. 3.04E-09 0. 4.31E-05 PR144 4.30E-ll l.76E-ll 2.18E-12 0. l.OlE-11 0. 4.74E-14 ND147+0 9.38E-09 l.02E-08 6.llE-10 0. 5.99E-09 0. 3.68E-05 PM147 l.OSE-07 9.96E-09 4.06E-09 0. l.90E-08 O. 9.47E-06 PM148M+O 4.14E-08 l.05E-08 8.21E-09 0. l.59E-08 0. 6.61E-05 PM148 l.02E-08 1.66E-09 8.36E-10 0. 3.00E-09 0. 9.90E-05

j. PM149 2.17E-09 3.05E-10 l.25E-10 0. 5.81E-10 0. 4.49E-05 j PM151 9.87E-10 l.63E-10 8.25E-11 0. 2.93E-10

0. 3.66E-05 j SM151 8.73E-08 1.68E-08 3.94E-09 0. 1.84E-08 0. 5.70E-06 i . SM153 1.22E-09 1.0lE-09 7.43E-11 0. 3.30E-10 0. 2.BSE-05 ii EU152 2.45E-07 5.90E-08 5.20E-08 0. 2.74E-07' O. 2.17E-05

. EU154 7.91E-07 1.02E-07 7.19E-08 0. 4.56E-07 0. 5.39E-05 I EU155 1.74E-07 l.68E-08 l.04E-08 0. 6.57E-08 0. 9.63E-05

\ EU156 1.92E-08 l.44E-08 2.35E-09 0. 9.69E-09 0. 7.36E-05

~

I TB160 6.47E-08 0. 8.07E-09 O. 2.56E-08 0. 4.19E-05 j H0166M 3.57E-07 l.IC~-07 7.96E-08 0. l.61E-07 O. O.

W181 1.42E-08 4.58E-09 4.79E-10 0. O. O. 3.90E-07

, *::::*;:,:: W185 5.79E-07 1.91E-07 2.02E-08 0. O. 0. 1.65£-05 W187 1.46E-07 1.19E-07 4.17E-08 0. O. 0. 3.22E-05 76 Rev 7 01/01/93

ltevhion 7 TEEN INGESTION DOSE COHHITHENT FACTORS (HREH/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL DODY THYROID KIDNEY LUNG Gl-LLI PB210+0 l.81E-02 5.44E-03 7.0lE-04 0. 1.72£-02 0. 5.74E-05 61210+0 6.59£-07 4.SlE-06 5.66E-08 0. 5.48E-05 0. 5.lSE-05 P0210 6.09E-04 l.07E-03 l.23E-04 0. 3.60E-03 C. 6.75E-05 RN222+D 0. 0. 0. 0. 0. 0. 0.

RA223+0 7.llE-03 l.08E-05 l.42E-03 0. 3.lOE-04 0. 3.43E-04 RA224+0 2.31E-03 5.52E-06 4.61E-04 0. l.58E-04 0. 3.71E-04 RA225+0 9.37E-03 l.lOE-05 l.87E-03 0. 3.15E-04 0. 3.27E-04 RA226+0 3.22E-Ol 8.13E-06 2.39E-Ol 0. 2.32E-04 0. 3.SlE-04 _;,.

RA228+0 l.37E-Ol 4.41E-06 l.51E-Ol O. l.26E-04 0. 5.98E-05 AC225 6.29E-06 8.59E-06 4.22£-07 0. 9.85E-07 0. 4.36£-04 AC227+0 2.05E-03 3.03£-04 l.22E-04 0. 8.61E-05 0. 8.68£-05 TH227+D l.96E-05 3.52E-07 5.65£-07 0. 2.0lE-06 0. 5.75E-04 TH228+0 6.80£-04 1.14£-05 2.30E-05 0. 6.41E-05 0. 5.97(-04 TH229 8.39E-03 1.26£-04 4.llE-04 0. 6.IOE-04 0. 5.43£-04 TH230 2.16£-03 l.23E-04 6.00E-05 0. 5.99E-04 0. 6.38E-05 TH232+D 2.42E-03 l.OSE-04 l.63E-04 0. 5.llE-04 0. 5.43E-05 TH234 l.14E-07 6.68E-09 3.31E-09 0. 3.81E-08 0. 1.21E-04 PA23l+D 4.31E-03 l.62E-04 l.68E-04 0. 9.lOE-04 0. 7.60£-05 PA233 7.33E-09 l.41E-09 l.26E-09 0. 5.32£-09 0. l.61E-05 U232+0 5.89E-03 0. 4.21E-04 0. 6.38E-04 0. 7.19E-05

U233+0 U234 U235+0 U236 U237 U238+0 NP237+D l.24E-03 O.

l.19E-03 0.

l.14E-03 0.

1.14E-03 0.

7.89E-08 0.

l.09E-03 0.

l.44E-03 l.25E-04 7.543-05 0.

7.39E-05 0.

6.94E-05 0.

7.09E-05 0.

2.IOE-08 0.

6.49E-05 0.

5.BSE-05 0.

2.90E-04 0.

2.85E-04 0.

2.67E-04 0.

2.73E-04 0.

3.24E-07 0.

2.50E-04 0.

4.33E-04 0.

6.65E-05 6.51E-05 8.28E-05 6.llE-05 2.09E-05 5.83E-05 8.41E-05 NP238 l.95E-08 5.22E-10 3.04E-10 0. l.79E-09 0. 3.83E-05 NP239 l.76E-09 l.66E-10 9.22E-ll 0. 5.21E-10 0. 2.67E-05 PU238 7.21E-04 l.02E-04 l.82E-05 0. 7.BOE-05 0. 7.73E-05 PU239 8.27E-04 l.12E-04 2.0lE-05 0. 8.57E-05 0. 7.06E-05 PU240 8.26E-04 l.12E-04 2.0IE-05 0. 8.56E-05 0. 7.19E-05 PU24l+D l.84E-05 9.42E-07 3.69E-07 0. l.71E-06 0. l.48E-06 PU242 7.66E-04 l.OBE-04 l.94E-05 0. 8.25E-05 0. 6.92E-05 PU244 8.95E-04 l.23E-04 2.22E-05 0. 9.45E-05 0. l.03E-04 AM241 8.62E-04 3.29E-04 5.75E-05 0. 4.31E-04 0. 7.87E-05 AM242M 8.70E-04 3.19E-04 5.BOE-05 0. 4.30E-04 0. 9.90E-05 AM243 8.60E-04 3.17E-04 5.62E-05 0. 4.22E-04 0. 9.23E-05 CM242 2.94E-05 2.97E-05 l.95E-06 0. 8.89E-06 0. 8.40E-05 CM243 6.91E-04 2.86E-04 4.09E-05 0. l.91E-04 0. 8.28E-05 CM244 5.32E-04 2.49E-04 3.19E-05 0. l.49E-04 0. 8.00E-05 CM245 l.07E-03 3.33E-04 6.lOE-05 0. 2.85E-04 0. 7.46E-05 CM246 l.06E-03 3.32E-04 6.09E-05 0. 2.84E-04 0. 7.33E-05 CM247+D l.03E-03 3.27E-~4 6.00E-05 0. 2.BOE-04 0. 9.63E-05 CM248 8.60E-03 2.69E-03 4.95E-04 0. 2.31E-03 0. l.55E-03 CR252 3.SlE-04 0. 8.37E-06 0. 0. 0. 3.05E-04 77 Rev 7

01/01/93

t. ; _.

eALUAUf.i~LIAILP.1-.ANI Qff.S.lT.E_J)_OSL..kl!lC!ti.AllfilLJ1_AN!1Al Revision 7 IMLE Z.l ADULT INGESTION DOSE COMMITMENT FACTORS (HREH/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI HJ 0. l.OSE-07 l.OSE-07 1.0SE-07 1. 05E-07 l. 05E-07 1. 05£-07 BElO 3 .18E-06 4.91E-07 7.94E-08 o. 3.71E-07 o. 2.68£-05 Cl4 2.84E-06 5.68E-07 5.68E-07 S.68E-07 *5.68E-07 5.68E-07 5.68£-07 Nl3 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36£-09 F18 6.24E-07 o. 6.92E-08 o. 0. 0. 1.85£-08 NA22 1. 74E-05 1.74E-05 1. 74E-05 1. 74E-05 l.74E-05 1.74E-05 1.74E-05 NA24 1. 70E-06 1. 70E-06 1. 70E-06 1. 70E-06 l.70E-06 1. 70E-06 1.70[-06 P32 1. 93E-04 1. 20E-05 7.46E-06 0. ,.0. 0. 2.17E-05 AR39 o. n I\

u.

ft

u. u. o. 0.

AR41 o. 0. 0. o. 0. 0. 0.

CA41 l.83E-05 0. 2.00E-05 o. 0. 0. l.84E-07 SC46 5.51E-09 l.07E-08 3. llE-09 0. 9.99£-09 0. 5.21£-05 CR51 0. 0. 2.66E-09 1. 59E-09 5.86E-10 3.53E-09 6.69E-07 MN54 o. 4.57E-06 8.72E-07 o. l.36E-06 0. l.40E-05 MN56 0. l.lSE-07 2.04E-08 0. I. 46E-07 o. 3.67£-06 f E55 2.75E-06 1. 90E-06 4.43E-07 0. 0. l.06E-06 l.09E-06 FE59 4.34E-06 1.02E-05 3.91E-06 o. 0. 2.85E-06 3.40E-05 C057 o. 1. 75E-07 2.91E-07 o. 0. 0. 4.44E-06 COSS o. 7.45E-07 l.67E-06 0. c.. 0. 1. SlE-05 C060 0. 2.14E-06 4.72E-06 0. 0. 0. 4.02E-05 NI59 9.76E-06 ,3.35E-06 1. 63E-06 0. 0. o. 6.90E-07 NI63 l.30E-04 9.0lE-06 4.36E-06 o. 0. o. i.88E-06 NI65 5.28E-07 6.86E-08 3.13E-08 o. 0. 0. l.74E-06 CU64 0. 8.33E-08 3.91E-08 o. 2.lOE-07 0. 7. lOE-06 ZN65 4.84E-06 1. 54E-05 6.96E-06 o. 1.03E-05 0. 9.70E-06 ZN69M+D L70E-07 4.0SE-07 3.73E-08 0. 2.47E-07 0. 2.49E-05 ZN69 l.03E-08 1. 97E-08 l.37E-09 o. 1. 28E-08 0. 2.96E-09 SE79 0. 2.63E-06 4.39E-07 0. 4.SSE-06 o. 5.38E-07 BR82 0. o. 2.26E-06 0. 0. 0. 2.59E-06 BR83+0 0. 0. 4.02E-08 o. 0. o. 5.79E-08 BR84 0. 0. 5.21E-08 0. 0. 0. 4.09E-13 BR85 0. o. 2.14E-09 0. 0. 0. 0.

KR83M o. 0. 0. o. 0. o. o.

KR85H o. 0. 0. o. 0. 0. 0.

KRBS 0. 0. o. 0. 0. 0. 0.

KR87 o. o. o. o. o. 0. 0.

KR88+0 o. o. 0. 0. o. o. o.

KR89 o. o. 0., 0. 0. o. 0.

RB86 o. 2. llE-05 9.83E-06 o. 0. 0. 4.16E-06 RB87 0. 1.23E-05 4.28E-06 0. 0. o. 5.76E-07 RB88 o. 6.0SE-08 3.21E-08 0. 0. 0. 8.36E-19 RB89+0 o, 4.0lE-08 2.82E-08 o. 0. o. 2.33E-21 SR89+D

3.0SE-04 o. 8.84E-06 o. o. o. 4 .. 94E-05 SR90+D* 7.SSE-03 0. l.86E-03 o. 0. 0. 2.19E-04 SR9l+D 5.67E-06.

o. 2.29E-07 0. 0. o. 2.70E-05

SR92+0

2.lSE-06 0. 9.30E-08 o. 0. 0. 4.26E-05

. . ..:*,., '/ .

~ *~ . .: .** ,**.. '*** 78 Rev 7 01/01/93

eAl..1~.015-_Ji!!<;_LEAILflMT QfOH f._QQ SL C.~LC.IJLAJlOJL~,i\H!JAt Revision 7 TAOLE 2. l ADULT INGESTION DOSE COMMITMENT FACTORS (HREM/50V PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG G!-LLI V90 9.62£-09 0. 2.58£-10 o. 0. 0. 1.02£-04 Y91M+D 9.09£-11 0. 3.52E-12 0. 0. 0. 2.67£-10 V91 l.41£-07 o. 3.77£-09 0. 0. 0. 7.76£-05 Y92 8.4SE-10 o. 2.47£-11 0. 0. 0. 1.48£-05 V93 2.68E-09 o. 7.40£-11 0. 0. 0. 8.50£-05 ZR93+0 4 .18E*08 2.34£-09 1.09£-09 0. 8.87£-09 0. 2.43£-06 ZR95+0 3.04£-08 9.75E-09 6.60£-09 0. 1. 53E-08 0. 3.09E-05 ZR97+0 1.68E-09 .... .--- ....

1101='-1'."I ...,

1 i:cc_1n

.., * .Jt.J"- - .&*V n

" . fl...' '"'~

'1. 1,C.-LU ~ -

o. 1. 05£-04 NB93M 2.SSE-08 8.32E-09 2.0SE-09 0. 9.57£-09 0. 3.84£-06 NB95 6.22E-09 3.46£-09 l.86E-09 0. 3.42E-09 0. 2.IOE-05 NB97 5.22E-ll 1.32E-ll 4.82E-12 0. 1.54E-ll 0. 4.87£-08 M093 0. 7.SIE-06 2.03£-07 0. 2.13£-06 0. l.22E-06 M099+D 0. 4.31£-06 8.20£-07 0. 9.76E-06 0. 9.99E-06 TC99M 2.47E-10 6.98E-10 8.89E-09 0. 1. 06E-08 3.42£-10 4 .13E-07 TC99 I. 25E-07 1.86£-07 5.02E-08 0. 2.34£-06 1. 58E-08 6.08£-06 TClOl 2.54E-10 3.66~-10 3.59E-09 o. 6.59£-09 l.87E-10 l.IOE-21 RU103+D 1. 85E-07 o. ' 7.97£-08 0. 7.06E-07 0. 2.16E-05 RU105+0 1. 54E-08 0. 6.0BE-09 0. I.9gE-07 0. 9.42E-06 RU106+0 2.75E-06 0. 3.48E-07 0. 5.31£-06 0 . 1.78E-04 RH105 1. 21E-07 8.85E-08 5.83E-08 0. 3.76E-07 0. 1.41E-05 PD107 0. l.47E-07 9.40E-09 0. l. 37.£-06 0. 9.liE-07 PD109 0. 1. 77E-07 3.99E-08 o. l.Olf-06 0. 1. 96E-05

AGllOM+D 1. 60E-07 1.48E-07 8.79£-08 0. 2.91£-07 0. 6.04E-05 AGlll 5.BlE-08 2.43E-08 l. 21 E-08 0. 7.84E-08 0. 4.46E-05 CD113M 0. 3.lSE-06 l.C2E-07 o. 3.SOE-06 0. 2.56E-05 CDllSM 0. l.84E-06 5.87E-08 o. l.46E-06 0. 7.74E-05 SN123 3. llE-05 5.lSE-07 7.59E-07 4.38E-07 0. 0. 6.33E-05 SN125+0 8.33£-06 1. 68E-07 3.78E-07 l.39E-07 o. 0. 1.04£-04 SN126+D 8.45E-05 1.67E-06 2.40E-06 4.921:.-07 0. 0. 2.43E-05 SB124 2.80E~06 5.29E-08 1.11 E-06 6.79E-09 0. 2.18E-06 7.95E-05 SB125+D

I.79E-06 2.00E-08 4.26E-07 l.82E-09 0. 1.38E-06 1. 97E-05 SB126 l.15E-06 2.34E-08 4.15E-07 7.04E-09 0. 7.0SE-07 9.40E-05 58127 2.58E-07 5.65E-09 9.90E-08 3.lOE-09 o. 1.53E-07 5.90E-05 TE125M 2.68E-06 9. 71E-07 3.59E-07 8.06E-07 1.09E-05 0. 1.07E-05 TE125M+D 6.77E-06 2.42E-06 8.25E-07 1. 73E-06 2.75E-05 0. 2.27E-05 TE127 l. lOE-07 3.95E-08 2.38E-08 8.lSE-08 4.48E-07 0. 8.68E-06 TE129H+D 1. lSE-05 4.29E-06 l.82E-06 3.95E-06 4.80E-05 o. 5.79E-05 TE129 3.14E-08 l.18E-08 7.65E-09 2.41E-08 l.32E-07 0. 2.37E-08 TE131M+D l.73E-06 8.46E-07 7.05E-07 l.34E-06 8.57E-06 0. 8.40E-05 TE13l+D l.97E-08 8.23E-09 6.22E-09 l.62E-08 8.63E-08 o. 2.79E-09 TE132+D 2.52E-06 1.63E-06 1.53E-06 1.SOE-06 1.57E-05 0. 7.71E-05 TE133M+D 4.62E-OB 2.70E-08 2.60E-08 3.91E-08 2.67E-07 0. 6.64E-08

0 TE134+0 3.24E-08 2.12i-08 l.30E-OB 2.83E-08 2.0SE-07 o. 3.59E-ll

_',,:' 1129 3.27E-06 2 .SlE-06 . 9.21E-06 7.23E-03 6.04E-06 0. 4.44E-07

. ". . 1130 7.56E-07 2.23E-06 8.SOE-07 1.89E-04 3.48E-06 o. 1. 92E-06 1131+0 4.16E-06 5.95E-06 3.41E-06 1. 95E-03 1.02E-05 o. l.57E-06 I.-

:*~-* 1' ***

79 Rev 7 01/01/93

.( ~.-...

eAWAQU__fillllf.AfLf~JH Qff.filLQQ2.E.~J.AllQ1L!'tf)_ti!JA~

Rov1s 1on 7

~

~*

~ TABLE 2.1 ADULT INGESTION DOSE COMHtTHEHT FACTORS (MREM~SOY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY T YROID KIDNEY LUNG

GI-Lll 1132 2.0JE-07 5.43E-07 l.90E-07 l.90E-05 B.65E-07 0. l.02E-07 1133+0 l.42[-06 2.47E-06 7.53E-07 3.63E-04 4.JlE-06 0. 2.22E-06 1134 1.06E-07 2.88E-07 l.03E-07 4.99E-06 4.58E-07 0. 2.SlE-10 1135+0 4.43E-07 l. 16E-06 4.28E-07 7.65£-05 1.86E-06 0. 1. 3lE-06 XE131M 0. 0. 0. 0. 0. 0. 0.

.. XE133M 0. 0. 0. 0. 0. 0. 0.

XE133 0. o. 0. o. 0. 0. o.

~

XE13SM o. 0. 0. 0. 0. 0. 0.

XE135 o. 0. 0. o. 0. o. 0.

XE137 0. 0. 0. 0. 0. 0. 0.

XE138+0 0. 0. 0. 0. 0. 0. 0.

CS134M+D 2.13E-08 4.4BE-08 2.29E-08 0. 2.43[-08 3.83E-09 1. 58E-08

,f' CS134 6.22E-05 1. 48E-04 l.21E-04 o. 4.79E-05 l.59E-05 2.59E-06 CS135 1. 95E-05 1.BOE-05 7.99E-06 0. 6.SlE-06 2.04E-06 4.21E-07

(

CS136 6.SlE-06 2.57E-05 l.85E-OS o. l.43[-05 1.96E-06 2.92E-06 CS137+0 7.97E-OS 1.09£-04 7.14E-05 o. 3.70E-05 1.23E-OS 2.llE-06 CS138 6.52E-08 l.09E-07 5.40E-08 0. 8.0lE-08 7.91E-09 4.65E-13 CS139+0 3.41E-08 5.08f-08 1. 8SE-08 0. 4.07E-08 3.70E-09 1.lOE-30 BA139 9.70E-08 6.91E-ll 2.84E-09 o. 6. 46E-ll 3.92E-ll 1. 72E-07 BA140+D 2.0JE-05 2.55£-08 l.J3E-06 0. 8.67E-09 1.46E-08 4.18E-05 BA141+D 4. 71E-08 3.56E-ll 1. 59E-09 0. 3.31E-ll 2.02E-ll 2.22E-17 BA142+D 2 .13E-08 2.19E-ll 1. 34E-09 0. l.85E-l! 1. 24E- ll 3.00E-26

' LA140 2.50E-09 1.26E-09 3.33E-10 o. 0. 0. 9.25E-05 LA141 3.19E-10 9.90E-ll l.62E-11 0. 0. 0. 1.18E-OS LA142 1.28E-10 5.82E-ll 1. 45E-ll o. 0. o. 4.25E-07 CE141 9.36E-09 6.33E-09 7.18E-10 0. 2.94E-09 0. 2.42E-05 CE143+0 l.65E-09 1. 22E-06 l.35E-10 0 . 5.37E-10 o. 4.56E-05 CE144+D 4.88E-07 2.04E-07 2.62E-08 0. l.21E-07 0. 1. 65E-04

~ PR143 9.ZOE-09 3.69E-09 4.56E-10 o. 2.13E-09 0. 4:03E-05

~f PR144 3.0lE-11 l .25E-ll 1. 53E-12 0. 7.0SE-12 o. 4.33E-18 ND147+0 6.29E-09 7.27E-09 4.JSE-10 0. 4.25E-09 0. 3.49E-OS PM147 7.54E-08 7.09E-09 2.87E-09 0. 1. 34E-08 0. 8.93E-06 PH148H+D 3.07E-08 7.95E-09 6.0SE-09 0. 1. ZOE-08 0. 6.74E-05 PM148 7 .17E-09 1.19E-09 5.99E-10 0. 2.25E-09 0. 9.35E-05 PM149 1. 52E-09 2.lSE-10 8. 78E-ll o. 4.06E-10 0. 4.03E-OS

. PM151 6.97E-10 1.17E-10 5.91E-ll o. 2.09E-10 o. 3.22E-05 SM151 6.90E-08 1. 19E-08 2.85E-09 o. l.33E-08 0. 5.25E-06

1 SM153 8.57E-10 7.lSE-10 5.22E-ll 0. 2.31E-10 0. 2.SSE-05

., EU152 1. 95E-07 4.44E-08 3.90E-08 0. 2.75E-07 0. 2.56E-05 EU154 6.15E-07 7.56E-08 5.38E-08 0. 3.62E-07 0. 5.48E-05 EU155 8.60E-08 l.22E-08 7.87E-09 0. 5.63E-08 o. 9.60E-06 EU156 l.37E-08 l.06E-08 1. 71E-09 o. 7.0BE-09 0. 7.26E-05 TB160 4.70E-08 o... 5.86E-09 o. l.94E-08 o. 4.33E-0.5 H0166H 2.70E-07 8.43E-08 6.40E-08 0. 1.26E-07 o. 0.

Wl81 9.91E-09 3.23E-09 3.46E-10 o. o. 0. 3.68E-07 WISS 4.0SE-07 1.35E-07 1.42E-08 o. o. 0. 1. 56E-OS Wl87 l.OJE-07 8.61E-08 3 .OlE-08. o. 0. 0. 2.82E-05 80 Rev 7 01/01/93

.. .... ~.

--~ . . .

~-

~:

~~-

\.ti Rov1s1on 7

~

TABLE 2.1 ADULT INGESTION DOSE COHHITHENT FACTORS {MREH/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDHEY LUNG GI-LU PB210+0 1.53£-02 4.37£-03 5.44£-04 0. l.23E-02 0. 5.42E-05 81210+0 4.61£-07 3.18E-06 3.96£-08 0. 3.83£-05 0. 4.75E-05 P0210 3.56£-04 7.56E-04 8.59E-05 0. Z.52£-03 0. 6.36E-05 RN222+D 0. 0. 0. O. 0. 0. 0.

RA223+0 4.97E~03 7.65E-06 9.94£-04 0. 2.17£-04 O. 3.21E-04 RA224+0 l.61E-03 3.90E-06 3.23E-04 O. l.lOE-04 0. 3.40£-04 RA225+0 6.56E-03 7.78E-06 l.JlE-03 0. 2.21£-04 0. 3.06£-04 RA226+0 3.02E-Ol 5.74£-06 2.20E-Ol 0. l.6~E-04 O= 3.32£-04 RA228+0 l.12E-Oi 3.12E-06 l.21E-Ol 0. 8.03E-05 0. 5.64f.-05 AC225 4.40E-06 6.06E-06 2.96£-07 0. 6.90£-07 0. 4.07£-04 AC227+0 l.87E-03 2.48£-04 l.llE-04 0. 8.00E-05 0. 8.19£-05 TH227+0 1.37£-05 2.48£-07 3.95£-07 0. 1.41£-06 0. 5.40£-04 TH228+D 4.96£-04 8.40£-06 1.68£-05 O. 4.67£-05 0. 5.63E-04 TH229 7.98£-03 1.19£-04 3.91£-04 0. 5.75£-04 0. 5.12£-04 TH230 2.06£-03 l.17E-04 5.70£-05 0. 5.65£-04 0. 6.02£-05 TH232+D 2.JOE-03 l.OOE-04 l.SOE-04 0. 4.82£-04 0. 5.12E-OS TH234 8.0lE-08 4.71E-09 2.31E-09 O. 2.67£-08 0. l.13E-04 PA231+0 4.lOE-03 1.54E-04 l.59E-04 0. 8.64E-04 0. 7.17E-05 PA233 5.26E-09 1.06E-09 9.12E-10 0. 3.99E-09 0. l.64E-05 U232+0 4.13E-03 O. 2.95E-04 O. 4.47E-04 0. 6.78E-05 U233+0 8.71E-04 0. 5.28E-05 0. 2.03E-04 0. ~.?.7E-05 U234 8.36E-04 0. 5.17£-05 0. l.99E-04 0. 6.14£-05 U235+0 8.0lE-04 0. 4.86E-05 O. l.87E-04 0. 7.81£-05 U236 8.0lE-04 0. 4.96E-05 0. l.91E-04 0. 5.76E-05 U237 5.52E-8 0. 1.47E-08 0. 2.27E-07 0. 1.94E-05 U238+0 7.67£-04 0. 4.54E-05 0. l.75E-04 O. 5.50E-05 NP237+0 l.37E-03 1.19E-04 5.54E-05 0. 4.12E-04 0. 7.94E-05 NP238 l.37E-08 3.69E-10 2.13E-10 0. l.25E-09 O. 3.43E-05 NP239 l.19E-09 1.17E-10 6.45E-11 0. 3.65E-10 0. 2.40E-05 PU238 6.SOE-04 9.SSE-05 1.71E-05 0. 7.32E-05 O. 7.JOE-05 PU239 7.87E-04 1.06E-04 1.91E-05 O. 8.llE-05 0. 6.66E-05 PU240 7.85E-04 1.06E-04 1.91E-05 O. 8.lOE-05 0. 6.78E-05 PU241+0 1.65E-05 8.44E-07 3.32E-07 0. 1.53E-06 0. 1.40E-06 PU242 7.29E-04 l.02E-04 1.84£-05 O. 7.BlE-05 0. 6.53E-05 PU244 8.52E-04 1.17E-04 2.llE-05 0. 8.95E-05 0. 9.73E-05 AM241 8.19E-04 2.BBE-04 5.41E-05 0. 4.07E-04 O. 7.42E-05 AM242M 8.24E-04 2.78E-04 5.43E-05 0. 4.05E-04 0. 9.34E-05 AM243 8.ISE-04 2.78E-04 5.30E-05 0. 3.99E-04 O. 8.70E-05 CM242 2.06E-05 2.lOE-05 1.37E-06 0. 6.22E-06 O. 7.92E-05 CM243 6.39E-04 2.41E-04 3.75E-05 0. l.75E-04 0. 7.SlE-05 CM244 4.83E-04 2.07E-04 2.87E-05 O. 1.34E-04 0. 7.55E-05 CM245 1.02E-03 2.87E-04 5. 76E-OS O. 2 .69E-04 O. 7.04E-05 CM246 1.0lE-03 2.87£-04 S.75E-05 O. 2.68E-04 O. 6.91E-05 CM247+0 9.84E-04 2.83E-04 5.67E-05 0. 2.64E-04 0. 9.09E-05 CH248 8.18E-03 2.33E-03 4.67E-04 O. 2.18E-03 0. 1.47E-03 CF252 2.64E-04 0. 6.29E-06 O. O. 0. 2.SSE-04

' 81 Rev 7 01/01/93

\ J. " : 'i PAlU!\L1f}_JilJ~LLJ\!\ _PLMH QfOJ f £_ Q~)S£ CJ'\l.~lJLALlQJL_MP.JilJAl Rovlsion 7 TAB!.~

_Ml ISADE~

Liquid Effluent Design Objective Annual Quantity Design Object1vP.

Dose Conversion Annual Quant Hy Nuclide Half-life Factors (mrem/Ci) lndiy1du~l/Organ (Curies)

H-3 12.3 yr 1.75£-06 Adult/TB 1. 71 E+06 Na-24 15 h 5.44E-03 Teen/TB 551. 5 Sc-46 83.9 d 2.02E-02 Teen/TB 148.5 Cr-51 27.8 d l.56E-03 Adult/GI (LLI) 6,410.0 Mn-54 303 d 3.50E-02 Teen/TB 85.7 Fe-55 2.6 yr 4.48E-03 Child/Bone 2,232.0 Mn-56 2.576 h l .86E-03 Teen/TB 1,612.0 Co-57 270 d 4.39E-03 Teen/TB 683.4 Co-58 71.3 d l.03E-02 Teen/TB 291.3

Fe-59 Co-60 Cu-64 Ni-65 Zn-65 Br-84 45.6 d 5.26 yr 12.8 h 2.56 h 245 d 31.8 mo 4.0SE-02 4.71E-Ol l.32E-03 5.82E-04

1. 83E-Ol 2.02E-03 Adu~t/G1 Teen/TB Teen/GI (LLI)

Teen/TB Teen/TB Teen/TB (LLI) 245.1 6.37 7,575.0 5,154.0 16.4 1,485.2 Rb-86 1.02 mo 3.06E-Ol Child/TB 9.80 Rb-88 17.8 mo 6.92E-04 Tee:i/TB 4,335.3 Sr-89 52.7 d l.56E-Ol Child/Bone 64.1 Sr-90 27.7 yr 2. 71E-OO- Adult/Bone 3.69 Sr-91 9.67 h l.16E-03 Teen/TB 2,586.0 Sr-92 2. 71 h 1. SlE-03 Teen/TB 1,986.8 Y-92 3.53 h 2.69E-04 Teen/TB 11, 150. 0 Nb-95 35 d 7.24E+OO Adult/GI (LLI) 1.38 Zr-95 65.5 d 6 .17E-03 Teen/TB 486.2 Nb-97 72 mo 6.95E-04 Teen/TB 4,316.6 Zr-97 17 h 9.28E-04 Teen/TB 3,232.8 Mo-99 66.7 h l. llE-03 Teen/Kidney 9,009.0 Tc-99m . 6.05 h l.42E-04 Teen/TB 21,126.8 Ru-103--- 39.5 d 2.74E-03 Teen/TB 1,094.9 Ag-llOm . 255 d 7.75E-02 Teen/TB 38.7

'*1,Y*

.. 82 Rev 7

~ ~

O_l/01/93 11::*

Rev1s1on 7 I.AD..L.E 2.2 (continued)

PALISADES Liquid Effluent Design Objective Annual Quantity Design Objective Dose Conversion Annual Quantity Nuclide Half-Life Factors !T.re~JCil Ind l vidua*i /Organ !Curies}

Cd-113m 13.6 yr 6.02E-02 Adult/GI (LLI) 166.1 Sb-124 60 d l.51E-02 Teen/TB 198.7 Sb-125 2.7 yr 5.llE-02 Teen/TB 58.7 Te-127 9.4 h 7.38[-03 Teen/GI (LLI) 1,355.0 Te-127m 109 d l.39E-Ol Teen/Kidney 71. 9 Te-129m 34.1 d 2.66E-Ol Adult/GI (LLI) 37.6 1-130 12.3 h 1.17E-02 Child/Thyroid 854.7 1-131 8.05 d 3.27E-Ol Child/Thyroid 30.6 Te-13lm 30 h 2.27E-Ol Adult/GI (Lll) 44.0

1-132 Te-132 I-133 Cs-134 I-134 1-135 2.26 77.7 h 20.3 h 2 yr 52 mo 6.68 h h 3.lSE-05 2.93E-Ol 3.94E-02 2.86E+OO 2.43E-03 1.64[-03 Teen/TB Adult/GI (LLI)

Child/Thyroid Adult/TB Teen/TB Child/Thyroid 94,339.0 34.1 253.8 1.04 1,234.0 6,097.0 Cs-136 13.7 d 4.13E-Ol Adult/TB 7.26 Cs-137 30 yr 1. 71E+OO Adult/TB 1. 75 Cs-138 32.2 mo 2.31E-03 Teen/TB 1,298.0 Ba-139 82.9 mo 4.66E-05 Teen/TB 64,377.0 Ba-140 12.8 d 7.96E-04 Teen/TB 3,768.0 La-140 40.22 h l.85E-02 Adult/GI (LLI) 540.5 Ce-141 32.5 d 3.70E-04 Teen/TB 8,108.0 Ce-144 284 d 1. 56E-03 Teen/TB 1,923.0 Eu-152 12.7 yr 3.24E-Ol Teen/TB 9.25 W-187 23.9 h I. 98E-Ol Adu1t/GI (Lll) 50.5 Np-239 2.346 d 2.26E-03 Adult/GI (LLI) 4,424.0

' ' * .~ t

. :~;.'

~

\'.

~' .

... ,*.i

.' ~

83 Rev 7 01/01/93

l ,1 Rev1s1on 7 111. !J!Wil.UM FUEL CYCLE DOSE A. SPECIFICATION In accordance with Appendix A,Section III.I.I, if either liquid or gaseous quarterly releases exceed the quantity which would cause offslte doses more than twice the limit of Appendix A, Sections 111.C.l, 111.D.l, or III.H.l, then the cumulative dose contributions from combined release plus direct radiation sources (from the reactor unit and rQdwaste storage tanks) shall be calculated. The dose is to be determined for the member of the public protected to be the most highly exposed to these combined sources.

B. ASSUMPTIONS

1. The full time resident determined to be maximally ex~osed individual (excluding infant) is assumed also to be a fisherman. This individual is assumed to drink water and ingest local fish at the rates specified in Sections II C.2.1 and II C.2.2.

2. Amount of sh0re line fishing (at accessible shoreline adjacent to site security fence) is conservative~y assumed as 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per quarter (average of approximately 1/2 hour per day each day of the quarter) for the second and third qua~ters of the year, 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months for the fourth quarter and 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months for the first quarter.

C. DOSE CALCULATION Maximum doses to the total body and internal organs of an individual shall be determined by use of LADTAP and GASPAR computer codes, and doses to like organs and total body summed. Ad~ed to this sum will be a mean dose rate, calculated or measured for the shoreline due to plant present curing the quarter in question, times the assumed fishing time.

D40 - DG + DL + (RT) (T} (2.15) where:

40 CFR 190 dose (mrem)

Limiting dose to an individual from gaseous source term (mrem}

DL Limiting dose to an individual from liquid source term (mrem}

... ' - Mean dos~ rate calculated to be applicable to Lake Michigan shoreline adjacent to plant site (mrem/hr)

I~

T

Assumed shoreline fishing time for the quarter in questions (hours}.

1 ;I* 84 Rev 7 01/01/93 ll ..

l .*..;~- .

_.,_ ... _.* -'"------.;.__--------------------*-*--*--*~-*-*---~*-*--*******-*-~-*. *-***h~- . .

-' .t ~: \t .

Revision 7 IV. RAOWASTE SYSTEM MODIFJCATlCNS A. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION

l. Purpose The purpose of this definition is to assure that Technical Specification 6.20 will be satisfied under clearly identifiable circumstances, and with the objective that current raJwaste system capabilities are not jeopardized.

2. Def1nition A major radwaste system modification is a modification which would remove (either by bypassing or physical removal) or replace with less efficient equipment, any components of the radw~ste system:

a. letdown filters or demineralizers

b. Vacuum degasifier

c. Miscellaneous or clean waste evaporators

d. The present waste gas compressor/decay tank system

e. Fuel pool filters/demineralizers

f. Radwaste polishing demineralizers

g. Radwaste solidification system Improvements or additions to improve efficiency will not be considered major modifications unless a complete substitution of equipment or systems is made with equipment of unrelated design.

Examples would be, 1) replacement of mechanical degasifier with steam, jet degas1f1er, 2) replacement of waste gas system with cryogenic system, 3) replacement of asphalt solidification with cement system, and 4) change from deep bed resins to Powdex, etc.

. '*."' ~.;*

i ,~ I

/:'::.,..:~ ,:*~.~*- .

' ~. '

85 Rev 7 01/01/93

-- ' ~.. ;:, ~;.

NOTE:

"Appendix A" of the Offsite Dose Calculation Manual (ODCM) was a new appendix created with the relocation of the Technical Specifications. This revision was "Rev O". Since this was a complete new appendix there are no specific lines on the side of the margin. The Rev number and effective date is located in the bottom margin.

Located within Rev 0 are additional pages for "other changes" that occurred throughout the year. The changes are noted by a line in the right/left margin with the Rev number and effective date of the change in the bottom margin.

. I*'

.: ODCM : . .:

- i<

APPENDIX* A

,,1 .. -****.**

RELOCATED. TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Revision 0 January l, 19~3 RECEIVED

'..~..

'... SEP 15 19~3

_.-,~...~*

!;Mc.;; PAL: .'. 1,.-

. -*. {*

',. .....; - - ~~-...

--~MRN~:..._-*;.;..-* -*.*-

, ~: ~- -- .--~ ., .

.i. '~ ..

. *- f,.

~-* *,;.

.--.*\,, **;...

>t.r. . . ..

. 'DElINITIONS * '.

'.I. *. *. '.*.

. 1

~

A. . Channef ;C~lfb~at.1.2..i;( . 1** *.

'*1.* B. Chanr1el Check *~ .. . . . '*. , . *1-

c. Channel Functional_ Test . . 1 D. Source Che.ck 2

~.'

E *.. Offsite o~~e-Calculatiori Manual . *,

2 ~* .

F: . Gaseous *Raclwaste Tre-~tment System.

.. 2

.~**

G. 2 H. Process Control*Pr~ir~iii- (PCP) 2 I Site Boundary .. 2 J. Unrestricted Area 2 K. Ventilation Exhaust.Treatment System 3

~. *:.

III .. *, PR~CED~L Am>. SURVEILLANCE REQUIREHENTS'Afm BASES 3 0

A;** Radi.oactive Gaseous E ff~uent. Monitoring-. Instrumentation 3

- .. 1. R~quirement . .. ._

3

2. Action . , ** 3

3. Surveillanc~ Requirements 4

4. Bases . 4 B. Gaseous Efflueuts Dose Rate 9

1. Requirement' 9

. 2. Action .. '. 9

~ "~

... '.-: -~'

.. . -~ .-: 3;.

Suiv~*illa~ce Req*.:!.r~m~nt~ . . . .. 9

'4: *Bases. .. 9*

. . 10

1. Require~ent ... 10 2 .. ,

. 10

3.

Surveilta~~e *<' . .

Requir~lients

<. ~- .. . .._. *. .. *. 11 .-r,

.. : *

c *,. * * -'

4. Bases* ** **-- 11

'. .* 16

1. Requlre~ent -. 16

~- ' : .

2.

3.

Actio'n Surveillance

,7 Requirements 16

.16 i6

4. .Bases . .- *,-* ** .

1 F. Radioactive Li guid Efflue'nt Monitoring Instrumentation *. '*' 17'

1. Requirement. **11'

2. Action 17

3. SurveillRnce Requirements 17

4. Bases 17 G. Liguid Efflue~ts Concentration . - 22

1.

Requiiei:nent -* 22

2. Action ,* 22

3. Surv~lllance Requirements 22

4. Bases . '

22 H. Liquid Effluent Dose 26

1. Requirement 26

2. Action 26

3. Surveillance Requirements 26

4. Bases 26 Total Dose 27

1. Requirement .. ,* 27

2. .:Action 27

3. SurJ~i~._fonce Requirements 28

4. - Bases *- *. .. 28

'+ . .

J. Radiological Environmental Monitoring 29

.... , 1. . Require~ent:*; . * . *.* "29

..... **"-. 2. Action *..

.. .* . ' .. -"*' - ' 31

'Monitoring Pro~ram *. .*. 31

b. Land Use Census 31

c. Inter.laboratory Compal'.'ison Program .* 32 K. SIRW or Temporarv Liquid Storage Tank 43

1. Requirement 43

2. Act.:.on 43

3. Surveillance Requirements 43

4. Bases . 43 IV. REPORTING REQUIREMENTS. 4l~

. \'

A.

Radiological Effluent Release Report 44 L Supplemental Information 44

2. Gaseous Effluents .* 45

3. Liquid Effluents 46

4. Radiological Impact on Man 47

5. ODCM Changes 48 B. Radiological Environmental Operating Re'port 4g G. Nonroutine Reports 49 V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS.YASTE 52 TREATMENT SYSTEMS A. Licensee Modificatiuns 52 B. Definition of Major Radwaste System Modification 52

1. Purpose ~~

2. Definition 52 TABLES A- .L Radioactive Gaseous Effluent Mordtoring Instrumentation 5 A-2 Radioactive Gaseous Effluent Monltoring lnstrumentation 7

-Surveillance Requlrements B-1 Radioactive Gaseous Waste Sampling and Analysis Program '. *. 14 C-1 Radioactive Liquid Effluent Monitoring Instrumentation 18

<;:-2 Radioactive: Liquid Effluent Monito:..:ing Instrumentation 20 Surveillance Requirements D-1 Radio<:.ctive Liquid Waste s.ampling and Anelysis P~ogram . 24 iii Rev. o*

'~:: .

' ~.=

.':;i1:1r:j,'f,:~;!:;";:,:A;*~i:'~'i,i!'.~y:~?.,: .* '..

.. ,. 23~a-::' .. _.. *.

E-1 Radiological Env!ronmentai Monitoring Program 33 E-2 Raporting Levels for Radioactivitj Concentrations in 39 Environmental Samples E-3 Detecr:..on Capabilitie:J for Environmental Sample Analysis 40 F-1 Environmental Radiological Monitoring Program Summary . so

. ~ T;' -*:*

.~,:

i' :- -*. ~-

Rev. 0

'* \ ~ .

. .. i

1' - ** ~' * *.-:

- '~. - *..

Relocated Technical Specifications I. INTRODUCTION The NRC, through 10CFRS0.36a, requires implementation of Technical Specifications on effluents from nuclear p".>wer plants. NRC Generic Letter 89-01, dated Jan~&ry 31, 1989, allowed relocaticn of the existing procedural requirements from the. Technical Specifications* (implemented in Amendment 85, November 9, 1984).

The relocated procedural requirements related to gaseous and liquid effluents, total dose, environmental monitoring program, and associated procedural reporting requirements follow below. Programmatic controls are retained in the Aciministrative Controls section of the Technical Specification to satisfy the regulatory requirements of 10CFRSO. 36a. The Technic'll Specifications programmatic controls include requirements for the establishment, implementation, maintenance, and changes to the Offsite Dose Calculation Manual (ODCM) as well as record retention and reporting requirements.

II. DEFINITIONS A. Channel Calibration a Channel Calibration shall be the adjustment, as necessary, of the channel output such that it responds with the necessary ~ange anu accuracy to known values of the paramt.ter which the chann~'1 monitors. The Channel Calibration shall encompass the entire channel including the sensor and alarm and/or trip h:nctions, and shall include the Channel Function Test. The Gha*~nel Calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

B. Channel Check A Channel Check shall be the qualitative assessment of channel behavior during operation by ~bservation.

This determinRtion shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring

.t, the same parame~er.

rci~t:'il G. Channel Functional Te~~ -

1.

3 Channel Functional Test sh~ll be:

Analog channels - .the inj ectio.n of a simulated signe.l into the channel '.as close to the sensor as practicable to Vtirify operability inch1dirig alara and/or trip functions.

c* ~ *

2. Bistable channels : the injection of a simulated signal into the sensor to verify operability including alarm and/or trip functf ,*_1s .- * *

i '

r1~~~;~:

.='*.-

- -**l.* .* '

. Rev o ' *.. 1/1/93 *

'~'~

I~t~I:ft}

--:-. - ~** ... ~ ::*

.*., ,. . -~. '

. ~ - ***-;,.*

D.

Sourc~ Check - a source check shall be the qualitative assessmlOnt of channel response when the channel sensor is exposed to a radioactive sou:cce.

E. Offsite Dose Calculation Manual (per Plant Technical Spec:!.fication) - the Offs!.te Dose Calc~l .. ~ion Manual (ODCM) shall contain the methodology and parameters*used in the calculation of offsite doses resultlng from radioactive gaseous and liquiC:..

effluents, in the calculation of gaseous and liquid effluen\:

monitoring alarm/trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain; 1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs requiren by the Technical Specifications and, 2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Relea.3e Repoi:ts required by the Technical Specifications.

F. Gaseous Radwaste Treatment Svstem any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off gase.s from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the envircnment.

G. Mernbais ~f the Public - all persons who are not occupationally associated with the plant. This category does not include employees of the utility, it.; contractors or vendors. Also excluded froJ11 this category are persons who enter the site to service equipment or ta make deliveries.

H. Process Control Program (PCP) - shall contain the current formula, Sa.Ulpling, analy~es, tests and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated we~ solid wastes will be accomplished in such a way .'.ls t*. ~:;f:*_~r:? :::::::::F::!.z~-:~

with 10CFR Part 20, 10CFR Part 71 and Federal and State regulations and other requirements governing the disposal of the radioactive waste.

I.* Site Boundary - that line beyond which the land is neither owned nor otherwise controlled by the licensee.

J. Unrestricted A!"ea - any area at or beyond the Site *Bound.iiry access which is not ccntrolled by the licensee for purposes of protection of individuals from exposure to radiation and radioac~ive materials or, any area

within the Site Boundary used. for residential quarters or for industrial, commercial, institutional arid/or* recreational purf">i:les.

'** *-.* - . t -~ .**.

2 *.:Revp o l/1/93.

( .... ' - ;-.'

' ; ..; ~ .

-:*. :. ~

, . i,.

Ventilation Exhaust Treatment System - any system designed ar.d installed ,to reduce ga'leous radioiodine or radioactive material

, in particulate fcrin in ef.fluents by passing *:entilation or vent ,

exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing icdines or particulates from the gaseous

, e~haust stream prior t*,) the rele.ase to, the envirorunent. Such a sys tee, 'is, not considered to have any effect on noble gas effluents. Engi~eered Safety Feature (ESF) atmospheric cleanup systems are not considored to be ventilation exhaust treatmen(

sys,tem co,mponents.

III. PROCEDURAL AND SURVEILLANCE RZQUIREMENTS AND BASES A. Radioactive G~seous Effluent Monitoring Instru_IJ'entation

1. Requirement:,

The radioactive gaseous effluent monitoring instrumentation channels shown in Table P.-1 shall be operable with their alarm/trip setpoints set to ensure that the limits of requirement III.B.l are not exceeded.

The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

2. Action:

, a. With a radioactive gaseous effluent monitoring instrumentation channel glarm/trip setpoint less conservative than required by the above requirement, without delay, suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.

b. With less than the minimum m !!l'ber of radioactive 1

- - ., gaseous effluent monitoring instrumentation

_channi;.l.s ~per able, , take the action 'show in Table A-1. Exert best efforts to return the instruments

..*- to operable, *status within 30 days and, if

- r unsuccessful,

explain in the next Radioactive Effluent Relea~e Report why .the inoperability was not correc,ted in a timely manner.

. ~.. . ... f" *- * . . .*- . .,:.:

.. --~ ..

c:*

s*u~611~:~ri~Ei:

,,/.<~;:**

Reciiifr~~~~ts: ~.,

,- .'-._ ::.. *-****.':'} :' -. :',, ... ::: *:*: ' ... .,; . *.. . ....

Each. "' .. radioactine. , gaseous ~ff.~uent **monitoring ... : .

"'

instr\.!mentation channel shall. be* demonstrated operabl-a by

. performance *.of the* Channel Check, Source '::heck, Channel Calibration' anci Channel F'.J.nctional :Test. operations at the frequencies shown.In Table A-2.

4. Bases:

The **radioactive gaseous effluent instrumentation is provided *. to monitor and control, as applicable, the releases" .of radioactive materials. in gaseous .effluents

duri~g actual~ or. potential r*eleas_es of ~::iseous *effluents~

The alarm/trip . setpoints* for. these ins~truments shall be

. 'caiculated and 'adjusted.in accordance with t:h~ methodology and parameters in* :the ODCM to. ensure that the alarm/trip

will occur prior: to. exceeding the limits of 10CFR Part 20.

The operability

aud use of .this instrunient~tion is consistent with *the requirements of General Design Criteria 60, 63 and*64 of Appendix A to 10CFR Part SO .

.~.:.

. * ' * . - '-:~~***' *~: .. I

~'- ' .*_ ' ..

GASEOUS EFfLur~T MONITORING

~;

- - MINIMUM CHANNE::..S

., c" ~-*~~-'*-*~~~I~N~S~T~R=U=M=E=N~T=-~~~.~~~*~~*~o~P~E=RA,._,,,B~L=E=-~~-=-A=P~P~L=I~C:AB=-=~I~L~I~TY......._~~~~A=C~T~I'-=O~

1. 'WASTE GAS HOLDUP SYSTEM . **. ::, .

. a .. *, N~ble .*Gas Activity Monitor

(RIA .1113) Provldin3 Alarm*

. *and Automatic Termination cf

~~* '

~' ';

<_'

Re~e.~~;e '*> * * . (1) At All Times ,1

.. : .. :Sb.*., Effluent **sy~tem FlOw Rate

. : ;*:.*t'.~ \ . Measurix:ig Device (FI ll21) (1) ** At: All Times .. 2 2.* CONDENSER EVACUATION SYSTEM (RIA 0631)

a. *.*Noble Gas* Activi::y Monitor (1) Above 210°F 3

3. STACK GAS EFFLUENT SYSTEM

. a. *Noble Gas Ac~ivity Monitor (RIA .. : :2326)

~

(1) At All Times

b ~* " Iodine/Particulate/Sampler/ .

. Monitor (RIA 2325) (1) At All. Times 3

c. Sampler Flow Rate Monitor (1) At All Times 2

d. Hi Range Noble Gas (RIA 2327)** ~l) Above 210°F 4

4. STEAM GENERATOR BLOYDO~ VENT SYSTEM a . . Noble Gas Activity Monitor

.. :'(RIA 2320) (1) 3

. 5./'.'.MAIN STEAM SAFETY AND DUMP VAL'iE

- << ,.* '.'.* DISCHARGE LINE

a. -.Gross Gamma Activity Monitor ** l . Above 325°F 4

.> (RIA 2323 and 2324) per Main Steam Line

. 6 . .*ENGINEERED SAFEGUARDS ROOM VENT SYSTEM

~

'a. Noble Gas Activity Monitor 1 Above 210°F 4 and 5

~~*~.-:.,;'::;.; : . .R!j'..i'~C\;*,<:~~-)aio and. l~~'~; .. , . **. :**p~r room.* ***:* _ .. ,

~);'.!* ":;;:.* :*;.v ,-_,*~* . ::.**'i,Setpoint's*: for th~sc. instrumenti:' are exempted .. from" III .B. l limit;s.

}-.*_*.:_*~-,+*~ .. _:., -::: .. ~. ...

""1*,~~ -:,-~-- - ';': .. *, . . ;~ . . *-. *. *- ,*'*.*:.* ._*-.;*_ * - . . .......... ..-*-. ** .. _. .

?;; /'.~ *:. :> -<< "... * :: ... Se.tpo.ints for* thes*e instruments are* governed by Emergency. Implementing

" f~~t*,,;":. *F ~~".:--;-._;*._*'.~:,*i>r6c~aure*s: or 'o.Peratbg:' procedures._... .. ... * * :. ** .. * * :*: *

" . ~:

. Rev 0 * :.*'

1jl~93

FS1..7 Table A-1 RAPIOACII'VE GASEOUS EFFLUENJ MONITORING INSTRUME.NTAT!ON MINIMUM CHANNELS It!STRUMENT OPERABI.r; afPLICABI!,ITY ACTION

1. VASTE GAS HOLDUP SYSTEM

a. Noble Gas Accivit:y Monitor (RIA 1113) Providing Alarm and Automatic Te:rm.ination of :.

~

Release (1) At All Times l ~f

b. Effluent System Flov Rate r

Measuring Device (Fl 1121)

~::>

(1) At All Tines 2 r Ir

\!

2. COliDE!iSEll EVACUATION SYS'l'!ll (llA 0631)

a. Noble Gas Activity Monitor {l) Above 210"F 3 f*

l-"

3. STAa CA:> UF1.IJEY? SYS'IEX

- Noble C&s Activity l!anitor (RIA 2326) (1) At All T~s 3 J 1.

tf*

c I

b_ Iodine/Partie~te/~ler/ f; Konitor (RIA 2325) .;::; ;,:

At All Tbes 3

c. Saapler nov !Ute ~cor (i) At: All Tlmies 2 :;

d. Bi Range ~*oble Cas (RL\ 2121)* (l) Above 210.F (i.

4. STUll CIBER.UOa !LOVDOW VDT S !SIE!I f rr

~;.

,i;

'*'(

- Noble Cas Ac:clvicy Kcnitor (llA 2320) (l) Above no*F 3

~:.

.,'_: l_~-'*

~~;

5_ !!AD STU!I SAFn'! Al!ID Dmt:P VAl.U *;>*

~*

DISCBAGE LIBE f;

- Gros* Cam:ta Activicy !fcnicor *

(lillA 2323 ~ 2324) l per tt&in Above l2)*y !~

~.;

t*.

S~aa Une ~~*'

1:i

6. DCJJIU1l!'D ~ llOO!I VESt SlS!U

~r f.~

. ** Hobb C&s Ac:tivicy Mon.1.cor ** l Abo'V9 210*F 4 and s *'.1*

.(llIA 1810 and 1811) per rOOl'.I /:'.

~.:..

,'~

fr/*,

.~

rL

-~.

{,

~~:*

~~'r.

s Rev 1 9/10/93 1=~.

TABLE NOTATION - />':TION STAT:ruiEN"l'S ACTION 1 - With the number of channels operable less than required by the Minimum Channels.Operable requirements, the contents of the tank(s) may be released to the environment provided that prior t9 initiating the release:

a. at least two independent samples of the tank's contents are analyzed,' and

b. at least* two technically qualified member~ of the Facil~ty staff independently ve.rify the release rate calculations and discharge valve line up; otherwise, suspend release of radioactive effluents via this pathway.

ACTION 2 With /the number of channels operable less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once peY 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for continuous releases or four hours for batch releases.

. ACTION 3 With the number of chan..'1.els operable less than required by the Minimum Channels Ope=able requirement, effluent ~eleases via this pathway may continue provided grab sample3 are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these sample:s are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 4 With the number of operable channels less than reC!uired by the Minimum Chann8ls Operable requirements, initiate the preplanned alternate method of monitoring the appropriate parameLe:r:(s), ;.;U:.l,l_;-.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

a. either restore the inoperable channel(s) to operable status within 7 days of the event, or

b. prepare and.submit a Special Report to the NRC within 30 days follo.wing the event outlining the actions taken, the cause of the inoperability arid the plans and schedule for restoring the system to operable status.

ACTION 5 If either channel fails *low or is otherwise inoperable, the ventilation dampers asso*<ated wich that channel shall be closed immediately and acti -~ shall be taken to have the affected channel

..~ : repaired. THe .daq a-> associated with the channel shall not be opened u~til the' affected channP.l has been declared inoperabl~.

6 Rev 0 1/1/93

'~: ..... -

Table A-1 (cont'd)

TABLE NOTAT!ON - ACTION STATEMENTS ACTION 1 - \lit:h t:he number of channels operable less than required by the Minimum Channels Operable requirements, the contents of the t:ank(s) may be released t:o the environment provided that: prior t:o init:iat:ing t:he release:

a. at: least cvo independent samples of the tank's contents are analyzed, and

b. at: least: cvo technically qualified men:bers of the Facilicv staff independent:!:: '.'erify the release rate calculations and discharge valve lin~ up; othervise, suspend release of radioactive effluents via this pathway.

ACTION 2 \Jith the nu::U>er of char.ru:!.s O?erable less than required by the

~ini.l!nlB Channels Operable re~uire!!ent:. effluent releases via this pathway cay continue provic!cd the flov rate is esti.:.ated at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for cont:i~ releases or four ~ours for batch releases.

ACTION 3 ACTION 4 IJith the num.ber of d:.~..s-1.s .,~,r~l~ less ~nan required by ~

Kinitruca Chan."Wtls Oper~lt> ~~~.:'"13':>.t:, effluent: releases via tlrls pathvay nay continue provided gr~ s&mples are taken at: least: or.ce per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ~ chase s.a::1ple.s .u-e analyzed for gross act:ivity vit:hin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

\Jith ~ mm.her of operable channels less than ?:e<tuired by cile Mini:ra.i:::l Channels Ope:-ahle requirelHnts. init.ia:;e ::he preplanned alt.ernat:e a_.e~ of morniU>ring t:he appropriat.e paraGet.er(s), vit.hin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

&. eicher rostor* tiwi inoperable ch&nr-..el(s) -.o operable sueus

.vi.thin 1 days of thti event. or

b. prep*re and au!iin.it. a S?ochl Report. t:o *the NRC vir.hin 30 dAys folloving ~ eve.nt. cut.lining the act.ions taken. t:he cause of mo inoperA!>Uiq ~ che plans u..C seh~~ule for restoring c:he syste* to operable s't.atu.s.

ACTION S If either channel fuls lov or b omervise inoperable. t:he vencil*tion ~rs associated vith chat. channel shall be closed Ui:::Mdl&t*ly and .acticm shall be t~n to ha*.-e ::he .sffecud chan..'"lel repaired. th* ~rs assocla~d vith :he channel sb.11 ~ be I

openad until cha aifecc.ed channel ti.. been decl4%cd operable.

6 Rev l 9/10/93

CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL*

CHECK_ CHE.CJ< .QA.LIBRATION . TEST D( 4 )" R(3) q(l)(2) 0(4) NA R -* ... **

D M R(3) Q{2) *Above

.... - -~. ~

. ;~

-.'":.* . ' ... - ..~

D M R{3). Q{2)

w M** R(3)** NA *

-~

D .NA R NA. * *,*;*

D M R(3) . Q{2) Above 210°it :--. .

7 Rev 0 i/1/93

. ,*, Table A-2 (Cont'd)

. ' ". -; . ' . ' ~

RADIOACTIVE*GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

' ,: **: ,~

CHANNEL MODES IN.WHICH CHANNEL SOURCE CHANNEL :. FUNCTIONAL SURVEILlANCE "

'Y '* ' ,' ' * <<: . *' INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED*

?>!~.I~::~TKAM* SAFETY AND DUMP .VALVE DISCHJl.R.GE LINE

. ' i, .- .* ~

' .: */.*a.*: Gross Gamma Activity Moaltor D M R(3) Q(2) AbovL 325°F

,._ ,o ; *_;.* iNG}~i:ERE~ SAFEGUARDS ROOM VENT SYSTEM

_',~a *.

Noble; Gas Activity Monitor D M R(3) Q(l)(2) Above 210°F TABLE NOTATION

.*.: (l)* ..:'Tha *c'Channel Functional Test shall also demonstrate that automatic isolation of this pathway oc.curs if instrument:~_, ...... :*

,, * 'indicates measured levels above the alarm/trip 3etpoint.. .. C* *. *

(2)', :The:.,Cha.'~riei unctional Test sh2ll also demonstrate that cor.trol room alarm annunciation occurs if either of the

,.

following r _.1di tions ex is ts.

. a. . Instrument indicates measured levels above the alarm setpoint (not applicable for Item 3. d, Hi Range Noble Gas).-- ..

'b. i,'

'cir'cu:lt failure.

( 3) *' a . T::1e' Channel Calibration shall be performed using one or more of the reference standards traceable to the Nationat.

.. _Institute of Standards and Technology or using standards t:\at have been obtained from suppliers that participate_'.*

--.:.**: : ,- in *llleasurement assurance activities with NIST. These standards shall permit calibrating the system over. itsJ.

intended range of energy and measurement range. .

. -~ .*- ' -.'(: .* .

' ** *.D * * *' For: subsequent Channel Calibration, sources that have oeen related to the (1) calibration may be used; *

. (4) . Channel. Check shall consist of veri.L'ying indication of flow during periods of release. Channel Chack shall .be

- at le~st on.ce per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on wh Leh continuous or batch releases are made.

TABLE FRF.QUENCY NOTATION D At least once ?er 24 ho~rs Q At least once per 92 days M At least once per 31 days R At least once per 18 months p Prior to radioactive batch release w At least om;e per weP.k

' .~ . . - ,-

8 Rev 0

. ' *~ *'

B. ~a~eous ~~fl~~nts Dose Rat~

1.

r..c:quirement: .

The dose rate . due to radioactive materials released in gaseous*

effluents from the site to areas at and beyond the Site Boundary (see Figure 2-1) shall be limited to the following:

a. For noble gases: Lc3S than or equal to 500 mrems/yr to the total body a~d less than or equal to 3000 mrems/yr to the skin; and_

b. Fo*r Iodine-131, for Iodine-133, for tritiur11 and for all radionuclides in particulate form with h~lf-li*res greater than 8 da)'s: Less than or equal to 1500 mrems/yr to any organ.

2. Action:

With the dose rate(s) averaged over a period of one hour exceeding the above limits, without delay, restore the release rate to within the above limit(s).

3. Surveilla.r.::e Requirements:

a. The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of B .1.a in accordance with the methodology and parameters in the ODCM.

b. The dose ra-te due to Iodine -131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in* gaseous effluents shall be determined to be within the limits _of B.1. b in accordance with the methodology and parameters in the ODCH by obtaining :Lepresentative samples and performing . analyses in accordance with the sampling and analysis program specified in Table B-1.

4*. 'Bases:'****.: **:;'

This is pr~vided to ensure. that the dose at any time at and beyond the Site Boundary.~rom gaseous effluents from all units on the site w1ll'be within iO.times the annual dose limits of 10CFR Part.20 to*

' Uniest~icted Are.as. The annual dos3 limits are the doses associated with: 'the ~oncentrations *of 10 ti~es 10CFR Part 20, Apoendix B, Tahle:-2. Column" 1. These restrictions provide reasonable "assurance

.-~_~_-_:_.,-'.*,_.* -_L~.

_ _ that radioae:t_i:ve- material di:; charged in gaseous effluents wn1 _not* ..

--- -* "-. .

result i.n _the exposure of. a ~':"-'!llber of the Public in an Unrestricted"

_-.* ~- ~-~- -~- -~_i_: )___;:_-__*.:__;__*_.-_,'. .....* ____ Area:,_ either within or ~. 'tside the Site Boundary, to annual exposure 7

, ,::~... * . ;:_::::*:~*:. :_{*/::_>:: .glfeatex<:~t:1la~(:;desi:gn'.;;-J.,, ~ives of 10CFR_ ,50, APpendix _I, Sectio~: .-..,..:.

1-V~.::::~;~- <-,-.;<.;_:~;~~;'~--..::--:;.- . .- ;;.. II_..,B*.~*... -~o; ~Me~ers 0-~- -~he Publi~ who may 8.t times b.e within the_

pt"(::-:_.-. . ,-:*0,-*-,.*:,-_;~\' ;;.'.-.~"f': Si_fe :-Bou-adary oct:*.ipancy of the Member: of the'" !'ublic ~ill_. ..

ii*;t;,:;}~~:f~-~<~,:~~:~t~

: ,- '*:-. *"~cl'"~;~:-'<'.:'.**'*<"'.'"*':, '*: ,'.'*' *':

. 9 Rev 0 1(1/93 t~~~i~-f~~:~.~i1f1~~lf1a;~9i'..~" F ...*. .**. * ***

~sually be sufficiently lo;., to compensate for al"y.increase in the atmospoeric diffusion facto:* above that for th; Site Boundary.

rxmnples of calculations for such Members of the Public, with ~he appropriate occupancy factors, shall be given in th<! ODCM. The specified release rate limits r~strict, at all times, the corresponding dose rate above background to a Member of the Public at or beyond the Site Boundary to less than or equal to 500 mrems/yr to the total body.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLD' s). Detai_led

discussion of the LLD

and other detection limits can be' found in HASL Procedures ;:.ranual, HASL-300 (revised annually), Currie,* LA, "Limits for Quali::ative D~tection and Quantitative Determination - Application to Radiochemistry,~

Anal Chem 40, 586-93 (1968), and Hartwell, J K, "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

c. Noble Gases Dose

1. Requirement:

The air. dose due to noble &ases_ released ir:. gaseous effluents to areas at and beyond the Site Boundary (see Figure 2-1) 3hall be lilliited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radia~ion and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma *radiation and less tha~ or equal to 20 mrads for beta radiation. *

2. Action:

With the calculated air*: dose fr~m radioactive noble gas.:a in gaseous effluents'exceeding any of the above limits,. prepare and submit to the NRG *within 30 days a Special Report that identifies the cause{s) for exceeding the limit(s) and defines the cc.rrective actions . that have been taken to reduce the

'~.

releases and the proposed corrective actions to be taken to assure that subsequent relea;;es will be in compliance with the above limits. *

,* ~- .

10 Rev; 0 *1;1;93

- .~-:*. *:.**:*

Surveillance Requireaents:

Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall ~e determined in accordance with t~e methocto:ogy and pRremeters in the ODGM at least once per 31 days.

4. Bases:

This requirement is provided to implement the requirements of Sections II.B, Ill.A and IV.A of Appendix I, 10CFR Part 50.

The limiting Condition for Operation 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 is reasonably achievable". The Surveillance Require~ents 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 expo!'ure of a Member of the Public thr0ueh appropriate pathw.c.ys is u.1lik.aly to be substantially undera~timated. The d0se calculation methodology and parameters established in the ODGM for calculating the doses due to the c;.ctual release_rates of radloactive noble gases in gaseous efflaents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculatio.:1 of Annual Dos~s to Man from Routine Releases of Re:'tctor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I,"

Revision 1, October 1977 and D.egulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents

in Routi':1e Releases from LiS?;ht-'Water-Cooled Reactors", Revision l, July 1977. The ODGM equations provided for determining the air doses at and beyond the Site Boundary are based upon the hist::oricaJ. average atmos:.:!<. *cf-:: conditions.

D. l-131. I-133, Tritium an<l PaLticulates

1. Requirement:

The d~s.a to a Member of the Pubiic from Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor uni*c, to areas at and beyond the Site Boundary (see Figure '.'-l) shall be limited to the following:

a. .During:.ar.~ __ .*.endar qu.::.rttr: Less than. or equal to 7 .. 5

mrems*to any organ, and

-*.1 .:._::.

(?f;, ~-:: . :* *. :. ~- - ***. -

11 1/1/93

--.-* *. ~.~} '

~*

....~:'

.*--: ~ . - .. **

b. During any cal~ndar year: Less than or equal to 15 m~ems to any orgP~.

2. Action:

With the calculated dose from the release of Iodine-131, Iodine-133, tritium and i:adionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRG within 30 days *a Special Report that identifies the cause(s) for exceeding the limit and define(s) 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 the abov~ limits.

3. Surveillance Requirements:

Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131, Iod~ne-133, tritium and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODGM at least oncu per 31 dayP.

4. Bases:.

This r&quirement is provided to impleffient the requirements of Sections II.C, III.A and IV.A of Appendix I, 10CFR Part 50 .

. 'The requirements are the g~ides set forth in Section II.C of Appendix I. The Action statements provide the required operating flexibility and a~ the :;;ame time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radio~ctive materials in gaseous effluents to Unrestricted Areas will. be kept "as low as 1s reasonably achiev~ble". The.ODCM calculational methods specified in the Surveillanqe Require!!'ents. implement the ::-::quirements in Section II.A of Appendix I that conformance with the guides of Appendb{'tI,ibe shc.wti by* calculational procedures base:! 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* arid parameter.:; for calculating the doses due to

. the. actual, releas*e .*rates of the subject materials are

**~' . -.. -.

.consistent:with the methodology provided in Regulatory Guide.

..~: .. -- *<

" ,o ;< .,_., N ~' : *, * * '

.. L 109, , :"Calculation of:. Annual Doses to Man From Routine il~ *~. Releases'.. of Reactor E\ ':"luents for the Purpose of E.,;aluating '. ,.,

'comp Hance },.~th. 10CFR. Part. so, Appendix I", Revision 1,

,October:;~ E ": . . ~nci~ Regulatoi-y . Guide 1.111, ".Methods." for.

' Est'imati'ng Atm;}spherr'c *Transport and Dispersion of Gase~tis.

,>:~r2t'~*.*

.. 0 ~-:* . *- -*Q ; : - ,

.~*. -* ~. Efflueilt:S .. ;in -- R~~ttinP :.::_Relea~es

.- ;;."~ ', .'

From . *Light-Water'- Cooled*.>-

,:: ~~

R.0..;, o

: ..:~ .

~. '

,,*-~1.*;.I.~~~~~¥~~~~~1s~.i~.l.i_i,~ll.~~~~I~~i~~f~~~~~~~i~~Er~~Itif~J~{~l~1~!l;f~t?l

. S*

.*-.. *-*:. *,._, *\, ~:

....... **: . ~'*

/*,.< *.. **~'*' -.

'*,,**<:::./:.":.\\:'.::*.:"

. i.,..,.:_\; , ..,

,.".>:.':p ~*,*\*

~****:.*,* '1\ *,..:::.:*lj{;~'.:,***-* **,,*.~- . ." -~_ . *. *.,\ .... _ *,;-::~~:~*._..

. .~- -~: *'. :* ,;:,,.. _ ; ' . ,-~:-.?:.~.*.~ ***-:~*f' ,:*.~-;*'. :~ c *,._.,:*J . ., .....+{***, ' " _.; *.. ' j .

\:* .. Reactors~ ,*Revisi'Jn:. l; .. July.;: 1977. *. *. *The.cie *equations.* also provide *. for determi~bg .* '*t:he actual 'dosei:; based upcn the historical .average ."atmospheric conditions. . The release rate*

requirements' . for .: Iodine:..131, Iodine-133, tritium. and radionuclides in parti~ulate form with helf-lives greater than

.. 8 days are dependent 'upori. the existing radionuclide pathways

. to **.man,' .in are.as 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* s:ubsequent* consump_tion by man, *3) deposition onto grassy . areas . where 'milk . animals . and . meat producing animals* graze* with *con:suinpfion *of* the milk ~nd ,meat by man, and: 4) . deposition cm -the ~*gz.*c;und with' subsettuent exposure of man. . -- - . " .. ' , ' - ,

. . : J:-*

~

~--~-~~~~~~~~=-*~*m*~c~>~~~-~*-~***~*~1~~a~.*~~~~~.g-~,~-Q*~*w.*;~~~~~~Mz~:;~:~:~:*~~-

.. '}.,'

... l

."-~Table B-i*

0

. RADIOACTIVE GASEOUS WASTE SAffPLING AND_ANALYSIS PROGRAM

~. . , ..

... )

MINIMUM. LOWER* LIMIT '*.

SAMPLING ANALYSIS TYPE.OF DETECTION (LLD) 11 {

--"""""'"'"""-'=-====-=--='"'-"".....,_."'-~-FR---=EouENCY FREQUENCY ACTIVITY ANALYSIS*. (LJCi/mll *. *_, .

p* p Storage Each.Tank Each Tank Principal ,G~a-*Emitt~r-sb 1 x 10-4 Grab Sample '";** ... *

- ' *' :~~

p p Containment PURGb.:

Each .PURGE Each PURGE Principal Gamma Emlttersb Grab Sample biack *Gas. Effluent

Continuousc wd*c Charc'>al I-131, I~l33 1 }; '10"12 :

Sample :.

Continuousc wd*c Particulate Principal* Gammac:Emittersb. 1 x .10- 1*

Sample * .(I-131, Others)"*: ..

Continuousc Q Composite Sr-89, Sr-90 and .1 x 10"11 Particulate _Gross Alpha

. '(': Sample .., ..

Continuous 0 Noble Gas Noble Gases.

lE-06 Monitor Gross Beta or G~~

\".

\-,

14 Rev 0

. ' - ' * . * 't, ~.

* ; ., : * ~ <' ' ) '. -

.. :.:; 1,' *T~bl~ B~l .(Cont'd)

'i, TABLE NOTATION 3

The LLD is defined, in Table E-3. note C.

bThe. principal g~a emitters for which the LLD specification applies exclusivel::,*

are the*following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-13S 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. This list does not mean.

_that only these nuclides are to be considered. *Other gamma peaks that are identifiable, together with those of the above nuclides, shall .:!~so be analyzed

.and reported in the Radioactive Effluent Release Report.

(LLD lE-10 because of low gamma yields cThe ratio of the sample flow rate to the sample stream flow rate shall be known for the 'time period covered by each dose or dose rate calculation made in accordanc9 with requirements III.B.l, 111.C.l and III.D.l.

dsamp.les shall be changed at least once per 7 days and analyses shall be completed' withiri 48 ho~.lr.3 after changing or after re:moval from sampler.

CWith channels operable on iodine monitor RIA 2325 less than required per

III .A.1,* sampling shall also be performed at least once pe-= 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, start-up or Thermal Power change exceeding 15 percent of Rated Thermal Power in one hour and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of e;hanging. When samples collecte\i for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs Hay be increas~d by a factor of 10. This requirement does not apply if, 1) analysis shows that the Dose Equiv3lent I-131 concentration in the primary coolant has not increased more than a factor of 3, and 2) th~ noble gas monitor shows that effluent activity has not increased more than a factor of 3.

-,1 ..

... 15 *.Rev*a 1/1/93

. {~(

. '. .1'"

~*

. 1~. . '*

E. Gaseous Waste Treatment S~.::em

-~ ..

l Requirement:

.1 When gaseous waste exceeds a Ae-133 concentration of lF-05

' µCi/cc, the Waste GRs Decay Tank System shall be used to l reduce radioactive gaseous effluents by holding gaseous waste l colh~cted by the system for a mini!Ilum of 15 days 'up to 60 days.

I 1 2. Action:

i l

a. If. a waste gas decay* tank is required to be released with less than 60 days holdup time, the system wzste gas

. tank contents shall be evaluated and the waste gas decay i

1.;. tank with.the lowest Xe-133 content shall be released.

b. Gaseous waste may be discharged directly from the waste gcs surge tank through a high-efficiency filter oc from a waste gas decay tc:nk with less than 15 days of holdup directly to the stack for a period not to exceed 7 days if the holdup system equipment is not available and the release rates meet ~equirem~nts III.B, C and D.

3. Sur\reillance Requirements:

4.

Not Applicable.

Bases:

The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releas£s of radioactive ma~erials in gaseous effluents will be kept "as low as is reasonably achievable" by mee~ing the design objectives given in Section II.D cf Appendix I to 10CFR.50.

1.. * '

It* is **e~pected

thst reiea~~~*-' of* radioactlve material~ .in effhfrmts shali be. kept* at. small fractions of the limits specified in 20*.106 of 10CFR20'; . At the same time the licensee is permitted the flexibility of.* operation; compatible with.

considerations of health'and safety, to assure that the public.

is provided a dependable *source. of power even under unusual operating conditions whi~h :nay temporarily result in releases highE:r .than such sma'n**.fractions :. but still -.... ithin the limits specified:i~ III.B, C !0d D. * **

~*'.f~.'i: :_: ',." < ~ . .- *.*. ,'. ." *..

R~v*o lil/93.

- .~:

1'.* ..*

E. Gaseous Waste Treatment System

1. Requirement:

\Jhen gaseous waste exceeds a Xe-133 concentrlltion ':lf lE-05

µCi/cc, the Yast:e Gas Decay Tank System shall be used to reduce radioactive gaseous effluents by holding gaseous waste collected by the syste?S for a minimum of 15 days up to 60 days.

2. Action:

a. If a vaste gas decay tank is required to be released

-.-!th less ~'um 60 days holdup t:i!!.e. the syst:e.a va.ste gas tank cont:enu shall be evaluated and the waste gas decay t:G....,i.: vi.th the lovest Xe-133 content shall be released.

b. Gaseous vas~ eay 'be discharged directly fro:a tile vast:e gas surge t:.anlt chrough a high-efficiency filcer or frco a vaste ga.s ~y ~ vith less t:ha..."l 15 days of holdup directly to the si:.ack for a period not to exceed 7 days if the holdup sys~ equipment: is net: available and t:he rele.ase rates mieet requiresent:.s III.B. C, .and D.

4. B&ses:

lhe require:ent chat the qpropriate port.ions of these sys::.e:u be used. vhen speelfi.ed. provides re.a.son&ble assurance that:

'*:it.

me releases of radie&e~ive mat.rials in gaseous efflwmts

.\ vill be kept *a.s lc-v &S is rea.soDAbly ~hh-.*able* by meeting t:he design objectlvtes given 1u Section ll .D of Appendix I co locn.50.

It: u expected that: ?"eleuaa of radi.O£Ct:h-e n.ateri.als in effluencs shall be b9t at:

small fr.actions of t.ho 11.:du specined 1n 20. U-02 c *~ 100'220. At ~ s~ t!De the llcenseo b pem!it--cd th. nsstbility of op-er.ti.on. conpat.lble vi di conaiderat:ioce of healdl and s&fecy. t:.o usure chat: t:he public is prov1.died a dependable source of paver eve.s: under unusual op&r.aticg COllldlclcms vhic.b :z.ay t:e:porarily resuli:: in relea.es b.ipr ~ svcb ssall fract.10Dll. but sctll vitilin the liait.a speci!led in III.a. c. 4nd D.

_Revl .. 9/10/93

,, .r F. Radioactive Liquid F.ffl{ient Monitoring Instrumentation J. Require:nent:

The radioactive* liquid effluent monitoring instrumentation channels shown in Table C-1 shall be operable ".:lith their alarm/trip setpoints set to ensure that the limits of 111.G are not exceeded. The nlaim/trip setpoints of these channels shall be determined and adjusted i;'l. accordance with the methodology and parameters in the Offsite Dose Calculation Manual. (ODCM).

2. Action:

a. With a radioactive .liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than* required by the above specification,

i*

.. without delay suspend the release of radioactive liquid if' effluents monitored by the affected channel or dclclare the channel inoperable, or change the setpoint so it is acceptably conserva~ive.

b. With less than th~ minimum nJlllbei of radioactive liquid effluent monitoring tnstrumentation channels Operable, take the A~tiori "shown. in Table C-1. Exert best efforts to return the instruments:.to* Operable status within 30 days <ind' if.. unsuccessful; . explain in the next Radioactive Effluent .

Release Report why the inoperability was. not *corrected in a timely manner.

3. Surveillance Requirements:

~.

., . Each radiosctive liquid effluent monitoring instrumentation channel shall be demonstrated Operable by performance ot th~

Channel Check, Source Check, Channel Calibration and Channel Functional Test operations at. th.e frequenc:~:::!:: shown in Table C-2. ,. ,,*,

, '-4. Bases: *,, ...

' :;~" ~* '

The radioactive l_iquid efflliiant'instrt.imentation is provided to monitc..r and control; . :,.ar.;. applicable, the

releases .of radioactive materials in )iquid effluents during actual or

;;!,/~, * . potential_ releas~s . of lf.quid *. effluents. The alarm/trip

.-,~*1 *_,.';~:-_,**. ;_ ,.**:~-;',!*.~:_c'*.:

.v. ' *'

.f~{q~~*i;::~:;:~~~:J~~::;:£~~~10;,:r~!~~==;:f:;~;

-~**c:**.~*"\~eeding the :"Emit~ ,_of_),O(;FR).'art ;20 ._. The** Operability and L. . :~~*-':.:*/;:~?.... _-_ . .* _:-._ *. .." ::-::;~:~,~l;.ef~en~~!s<>{~;~~!f~.:~:i;;:_-:c;~~:~;;:~2ci;*e~t3

.-:.:.**-.:**, . .. . Apoendix A .to lOCFr.. Part - 50 '.: ., . *.. '> .

idth64 t: ~

"; .":,~/:

Rev r 1/1/93

<<_' **,, ,f" ,. . "*:'. ,\.

"::":'*.* . ~** ...*..

..'~: ,-.*.., .. ..,., .. ',_.'

~--

.. *.t' RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ,,

1*

' '. '."'~

',~,

. . *: . .._ ~., '

MINIMUM 1 *;\:* . ;* CHANNEL .' ..; ~

INS'!'RUMENT l , -*, :- OPERABLE ACTION

1 *. L :GROSS ~IOACTIVITY MONITO~ PROVIDING ALARM AND

j AUTOMATIC TERMINATION OF RELEASE

' ~ ,; *.

i:-..

j., . -~' .'

a. >Liq~id

' ; . Radwaste

. Effluent Line (RIA 1049) (1)

I:,

'I * ..* I*

.b.. * :S.te*am Generator Blowdown Effluent Line il :."

(RIA 0707.) (1) 2

2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALAR1'.'.BUT NOT PROVIDING AUTOMATIC TER..'frnATION OF

.RELEASE

a. . Service Water Sy£ tern Effluent Line (RIA 0833) (1) 3 b . . Turbine Building (Floor Drains) Sump~ Effluent Line (RIA 5211) (1) 3

3. * .. FLOY RATE. MEASUREMENT DEVI.-;Es

a. ,Liquid Radwaste Effluent Line (FIC 1051 or 1050) (1) 4

4. CONTINUOUS COMPOSITE SAMPLERS (Alarm/Trip S~tpoints are not applicable)

a. Turbine Building Sumps Effluent Line (1) j

."i>. *Service Water System Efflue:nt (1) 3

c. Steam Generator Blowdown Effluent . (1) 3

.* .~

.~t§':~

.. "* ***~:

.. ~; l ... J

...;*".:*)'-.. *:

- - /'
    
    *
    
    .~. ~.. ,~

18 '.

Table C-1 (Cont'd)

TABLE NuTATION AC\"ION 1 - With the number of channels operable less than required by th~

Minimum Channels Operable requirement, effluent releases may continue provided that prior to initiatin~ a release:

a. At least two independent samples are analyzed in accordance with requirements and

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend r~lease of radioactive effluents via this pathway.

ACTION 2 - With the number of channels operable less ::han i:equired by the Minimum Channels Operable requirement, effluent release£ via this pathway . continue provided c;:::-ab sam,;les are analyzed for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10-7 microcuries/ml at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 3 - With the number of channels operable less than required by the Minimum Channels Operable requirement, effluent release3 via this pathway may continue provided tP.at, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a lower limit of detection of at least lo-7 microcurie/ml.

ACTION 4 - With the number of channels operable less than required by the Minimum Channels Operable requirement, effluent relea~e~ via Lhi~

pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump p*. ".'f".lrmance curves or tank levels may be used to estimate flow.

.19 Rev J 1/1/93

\*.1*. :~ ,r ,. :*:

i c'

- 1*'.*,' . *_'.:.-*

. ._-, ::: *:-,~ l .

EFFLUENT MONITORING. INSTRUMENTATICN SURVEILLANCE REQUIREMBNTs*:.

. ~ :'

CHANNEL SOURCE : , CHANNEL

.*INSTRUMENT CHECK CHECK. CALIBRATION

~"

' }* ; ~-*

>.;.','. *_:, ,.'*';>ic: *.> :1 ;.. _: GROSS; RADIOACTIVITY: MONITORS

PROVIDING ALARM AND

- -~' :,. ~ ... " .

Kfflu~nt Line* (rUA 1049) p p R(3) Q(l)(2),

,;_ ~* : _.

Line (RIA 0707) I) M R(3) Q(lj (2)'

-~

,,_"\,

I) M R(3). . Q(2)

.* *< .;.:-_,.,,,,t:.;._;_ ~*::;0;:.~f* ~~-:~~ ,_1'1:1rhine-, B~ilding (Ffoor Drains) Sumps Effluent

.,:,* ,,,., *-,l:-'* .: ,;*;-~---:'. .. ,(.:_ ""' 1 {\;;~Line '-(RIA '-5211)" "* > . D M R(3) Q(2)*

,-.;,~~!~;~~

-l. *:}~r~E:i~.:-~:::,f;~*~:-;\_:~J'*: :;r_.* :* :, . <: : *>< :_:_ --~:*..:::*.'.;.j~:* _

~1i~,_\ ..::;~--~,~- _;*, (:'.~-~~*/',*.~7Q~..~TE. ~UREMENT_v?~V-~~E:~.:

1

~**.;~.:~~**,~::.}*,:~\*;~:::;~**,.~>~~~, : :.::!~:,*; j_::,:::.; ~ ~ , * : , : 'I~;. .: ~-~~1;,i; : ~ }>"

":*.~:"{*-:'!."' ~: ~:.:~";";-o:;**-**a*. :-.. *Liquid Radwaste *Effluent" Line (FIG 1051 or 1050) D(4) R NA

~~~~~i;~Jit:~i*;ift ~:::'E::i~*r:MPCJSITE SAHP~ *., D(4). . . NA*

NA:

0(4) NA NA ,. *NA

-~

-6.: STUM GEN'l'...RATOR . BLOWDOWN EFFLUENT C:OHPOSITER 0(4) NA NA NA -* ;., :.

ii..

~ .. i. .: -.~ - ~,~

' '~ ....

. *.:. (

.. .: ;. .* .. :1**

20* .R~v 0 *1/1/93

. : .~ ,' :

Table *c-2:.*' ccont 1 d)

TABLE. NOTATION

.:;*'>!:\f~~f~:;..':_{~*a 'Channel. Functional* Test shall also demonstrate that automatic isolation of this path~ay

>~~.'~/ . :;:*('*-'instrument indkates measured levels above th.e alti'rm/trip setpoint.

/*< ' *.::* . .-~;**~> ,' ~:. : *- 1 - ' * - * * ' *

. *** (2):.. *The Channel Functional Tes*c shall also demonstrate* ~hat *control Room alarm ahriunciatfon occurs if of the following conditicns exists:

a> Instrument indicates* measured levels above the alarm setpoint.

b .: * ."Circuit failure.

The Channel Calibration shall be performed using one* or more of the reference standards. i:raceab}e .to the National Institute of Standards and Technology or using standards that have been obtained from->

':-;* suprtiers that*. participate in measurement: assurance activities with NIST.* These standards shall **

. '.pe.ct~-'.t

cali'urating the system over its intended range of energy and measuremt'nt range .

.*, :*".:. *b;:.

~~' . . .

'For subsequent- Channel *calibration, sources that have been related to the (a) calibration

. .. .,. ,'used .

...,_.,, *l,.

Chan~el. Check shall .consist of verifying indication of. flow during periods of releases.

Channel Ch~'ck i.t shall be*;made at l.east onc.e per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on *days on which continuous* or batch releases are made .

TABLE FREQUENCY NOTATION

. '*.* D At least'on~e pe~ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Q At least once per 92 days*

M At least once per 31 days R At least once per 18 months p Prior to radioactive batch release w* -At least'once per week 21 *..--*

-~ . ,*

G.

Liquid Effluents Concentration * '" ,,

l RequirP.ment:

The concentration of radioactive materi.::>.l released in liquid effluents to Unrestricted Areas 'shall be limited to 10 times the concentrations . specified in 10CFR Part 20, Appendix B,.

Table 2, Column 2 for radionuclides other than dissolved or entrained noble gas~s. For dissob~ed or entrained noble gases, 'th~ concentration shall be limited to 2 x 104 microcuries/ml total activity.

2. Action:

With' the concentration of radioactive material released in liquid effluents to Unrestricted Areas exceeding the above limits, without delay, restore the concentration to within the above limits.

3. Surveillance Requirem~nts:

a. 'Radioactive liquid wastes shall be sampled and analyzed according to the salj}pling a1.d analysis program of Table 1.1-1.

b. The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the.

ODCM to assure that the concentrations at the point of release are maintain£d within the limits of G.l above.

4. Bases:

This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effl.. uent:s to Unrestricted Areas will be less than 10 times the concentration levels specified in 10CFR Pa:*_c '.W, Appendix B, Table.: 2,' Column 2. . , This . limitation provides additional assui::iince that. the level~ of radio~ctive materials in be dies of'water ,in'U~restricted Areas will result in exposures within the Section II.A de3ign objectives of Appendix I, 10CFR Part 50, to a. Member of *the. Public. *The concentration limit for diss~~ved. or entrained nohle gases is based upon the assumption that Xe-135 is the controlling radioisotope and lo times . the effluent concentration in air (submersion) was converted to an equiva1ent concentration in water using ,_the .

" .~ - methods described in I*.<ernational Commission on Radiological

- ~ . '.

Protection (ICRP) Publication 2.

. ~ .:'* ., , ; .

Rev o

. *. ~--' . .! .**

..... - ' . ' ~*

~: .. . ' -: . :', *~;' ._:* .

.r-*

Th'~'_r~quiied::~etb:tfon capab1ii'~ies for radioactive materials in liquid; W'ast'a'*, sa;ples are' tabulated ::.n terms of the lower lirnit:s of detecticn * (LLDs).

Detailed discussion* of the LLD and other, detection_ limits _can be found h. HASL Procedures Manual,' HASL-300Cc(revised dnnually), Currie, LA, "Limits for Qiialitative . Detection . and , Quantitati...-e Determination Appiica-tion_>tc>"-Radiochemistry", -Anal'Chem 40, 586-93 (19le),

and Hartwell, -:J - K, - "Detection Limits for Radioanalytical

-Counting Techniques", Atlantic -Richfield Hanford Company Report Af1!:!-SA-215 :(June 1975) .

' -'~

"{

. .*~-

>A,*,*

~

-- RevO

' - : -~.:, . *. -; ', '

L~IN:..:.:Go::...*~;;._*_..,AN...,,.,..M.YSIS PROGRAM

.:.:RA=-D=I*O=*A,_,_C=T,._.I"""V;..:.E"-"L::.::I.,.O""U""'I=-D-W:;;..:A:.:.:S.. ,T'""E"-*-"'s""AM.. =.P....

Lower.Limit Minillium of.Detectior.

Sampling

Analysis.* Type of Activity. :* .. (LLD)*

Gaseous Release T)rpe Frequency Frequency Analysis (uCi/mH

.: A. Batch Waste p P Principal Gamma s x ::.0-1 Release Each Batch Fach Batch Emittersc Tanksb I-131 1 x 10-6

' ' . ~,,(:

P* M Dissolved and

_ .... One Batch/M: Entraineci Gases :,* j (Gamma Emitters) p M H-3 1 x l0-5

Each* Batch Composited

. Gross Alpha. 1 x lo-7 p . Q * .sr-89, .sr-90 5. x 10-3 Each Batch .Composited*

B. Continuous w Principal~amma 5 x 10~7 .*:

Releases" Continuous 1 Gompositef

Emitt:ersc (Turbine Sump, I-131 1 x 10-6 Steam Generator Blowdown and Service Water) M M Dissolved and 1 x 10-S Grab Sample Entrainc...: G.:15~5 (Gamma* Emitters

M 1 x io-5 Contln~ousf . Conipositer

. Gross Alpha: 1 x 10-1

. .' Q Sr-89, Sr-90 5 x 10-3 Compositef

~ .... -:.

FREQ~~NCY NOTATION

. ::.* P: PriOr' to batch rele~se * **

.. ,:. . M . C~l~ndar.'.month. . ... * , *

. :._ -~ *; Calex!dar 'Ciul:rter. * - *

\** :::: * ~ 1,~~~(~~r. -*~~~k

-*..::..: *;_ ;_:* ;-;! '" - -*--~* *: * -

- - .r.

Table D-1 (Cont'd)

. ,_ :~

TABLE NOTATION 8

The LLLJ is defined, in Table E-3, Note* C .

. bA batch release is the discharge of liquid wastes.of a discrete volume. Prior to sampling for analyses, each bater. shall be isolated and then thoroughly mii:ed to assure repre_sentative sampling. .

CThe pri:lcipal.gamma emitters for which the LLD specification applies "exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99*, Cs-*

134,

Cs-137, Ce-141 and Ce-144*. This list* does not mean that* only these nuclides are."to be considered. Other gamma peaks that are identifiable, together with those of. the above nuclides, shall also be ar.alyzed and reported in the Radioactive Effluent Release Report. *

(LLD - 5ED-06 because of low gamma yields).

dA composite sample is one in ;rhich the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and iu which the method of sampling employed results in a specimen that is representative of the liquids released.

eA continuous release is the discharge of liquid wastes of a nondiscrete volume; eg, from a volume of a system that has an input flow during the continuous release.

fTo be representative of the _quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected in a series of aliquots of constant v0lume collected at regular time intervals and combined to form a single sample. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release .

. ..",. ~

::- .. ~ . '.:

25 Rev 0 '1/1/93

H. Liguid E1fluent Do;~

.l. Re~uireraent:

The dose .or dose commitment to a Me~ber of the Public from radioactive-materials in liquid effluents reletlsed from e.acb reactor unit to Unrestricted Areas shall be limited:

a. during any calendar quarter to less than or equal to 1. 5 mrems to the total body and to less than or equal to 5 mrems to any organ, and

b. during any calendar year to less than or equal to 3 mrems to the total body and to less than or ~qual to 10 mrems to any organ.

2. Action:

With the calculated dose from the release of radioactive materials in liquid affluents exceeding any of the above limits, prepare and submit to the NRG within 30 days a Special

. Rer.ort that identifies the cause ( s) for exceeding the.limit ( s)

-..nd defines the corrective actions that have been taken to reduce the releases an~ the proposed co~rective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include the results cf radiological analyses of the drinking water source.

3. Surveillan~e Requirements:

Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once every 31 days .

4. .Bases: . :.-.*-*

This requirement is provided to implement the requirements of Sections. II.A, III.A and IV .A of Appendix I, _lOCFR Part 50.

The Limiting Condition for Operation 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_ implem*ent *:**the guides set forth in Section IV .A cf Appendix I to a'ssure that the releases of radioactive material in li:quid e:t;fluent.t' ,-~ Unrestricted Areas will be "!cept "as low as* is* r~asonably ach~eva.ble". Also, for freshwater sites with

. . drinking watar<supplies .that can be potentially affected by .

~

plant**:"opcrati9ns ~- -.there: is - reasonable assuran-:e

that -the *

.. ;op~r.~{tion_

'* ~. . - ' ' - . - . f,.~c.:!.:lity.

9(:-:*tl\!'i:s; : . .- .

will - no~ result .fr. :2adionuclide Rev 0 1/1/93

.. t. --;. *. .;.,.

' I*'

! ~ : .- : '. *.:

~' ..

. ,* .~ . ' "

. co~cet1trat:ions . ::.n the finished d~lnki.ng water. that are in.

excess of the re~~uirements of 40CFR Part 141. The dos(:

c~lcul3tion methodology and parameters in the ODCM implement:

the requirements in Sect.ion III .A of Appendix I t!iat conformance witn: the guides of Appendix *I be shown by calculational procedures based on models and data, such t':lat:

the actual . exposure of a Member of the Public thr:mgh appropriate pathways is unlikely t:o be substar.t:ially 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 provlded *in : Regulatory.*. Guide 1.109, "Calculation o.f Annual Doses** to. Man Fro.ii;* Routine Releases of Reactor Effluents for the* Purpo~e of Evaluating Compliance with 10CFR 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.

I. Total Dose

1. Rquirement:

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 less th~n or equal to 25 mrems to the total body or any organ, except the thyroid, which shall. be* limited to less than* or equal to 75 mrems.

2. Action:

With the calculc.ted doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of III.C.l.a, III.C.l.b,. III.D.l.a,. III.D.l.b, III. H .1. a or. III.~ .1. b, *calculations s::** *,ld be made including direct radiation contributions from the reactor units and from;*

outside storage tankS t'~ dete~in'e whether the above, limit*s of I!I. I .1 have been exceeded.*.* If such is.* the_ case, prepare and submit to the NRC within 30 days a Special Report that defines the corrective actfon to be taken to reduce subsequent raleases to prev~nt:*recurrence** of exceeding the above .limits and includes the schedule for achieving conformance with the above limits. This_Sp2cial Rep~rt, as defined in 10CFR Part

20. 405c' shall include an analysis .that . estimat.es the

. radiation expo~tir,- _(dose) t:o a Member -of . the Public from uranium fuel* cycle sources, including all effluent pathways and direct ~adiation, ,*for the, calendar.yearthat. includes the

. -* .. *. release(s). C°ove-ief'bi'.J:hl~ *:r~po~t.*. *.:It. ~hait::*also :descrlbe-levels of radi.~t10~-:a.11d:concent:iation.S-. of-'radicJ&ctive"materrar . ' '"~.

. ' - ~,*

~sJ .. 7 concent:rat:ions in t:he finished drinking 1o1at:er t:hat are :.n excess of t:he requirements of 40CFR Part 141. The dose calculat:ion met:hodology and parameters in the ODCM implement t:ne requirements in Section III.A of Appendix I that conformance wit:h the guides of Appendix I be sho;.-n ov calculational procedures based on models 3nd data. such tha~

the act:ual exposure of a Member of t:he Public through appropriat:e pat:hways is uTJ.likely to be substantially underest:i.l:uited. The equations specified in the ODC~ for calculating the doses due t:o the actual release rates of radioactive ll.aterials in liquid effluents are consist:ent *.;i ::t-.

the methodology provided in Regulatory Guide 1. 109.

calculation of Annual Doses to ~an F:c~ Routine Releases ~:

Reactor Effluents Ior t:he Purpose of Evaluating Co:::?liance with 10CFR.. Part 50. Appendix I.* Revision l. O~t:ober 1977 and Regulatory Guide L 113. *Esti!:!.ating Aquatic Dispersion cf Effluents Fro~ Accidental and Routine Reactor Releases for the Purpose of !apleaent:ing Appendix r.* April 1977_

I. Total Dose

l. Require~~nt:

Tue ar.nual (calecda= ye.ar) dose or dose co=it.!:l~nt t:o any Mei::ber cf the P-..t.1.~~ el'-:.:.\: to ,r;;!.?:i.:.:.;es of radioact:ivi::.y a.nd to r4diacion fr03 u=;..ni~ i'-..:.4!1 -::..,.cl~ sources shall be li.!llited ::o less ct>..an or equal t~ 25 ~r~ns ~o \:he total body or any org~n.

~xcept ::he ::hyroi~. ~itlch st~ll b~ liai::.ed t:o less ::h.an o~

equal co 7:'> ~=-

2. Action:

~!di c."le c.a.lcula.~ doses froa the release of radioact:i.~

a.aterials in liquid or gaseous effluents exceeding tvice the lUtlts of Ill..C.La. IU .. C.Lb, l!I.D.l..a. ltl.D.LC>.

III.H .. l..a. or UL!!. Lb. calculations should be t:Mde .nclud!.ng dircc:e radiation con ttihutlons frou t..~e reactor units and frc.~

oucside storage t..&clt.s 'to det.ern1r.e vhf!cll.er tile ab-0.._-e linic:.s of III.I .. l have ~n ~xc~~ded .. If such is :.he case. prep~re a~d suboi:: to l:he s::ac vii:hin 30 days £ Spctcial Report t:.~t defines die corrective &ct!.on to be ta.ken to re~e subsequent releases ::o prcv~nt recurrence of excecdir..g the Above liai::.s and includes ~ schedule for Achieving c:onfontJlnce ~ith the above li.oits.. This Special Repor::. a.s defined in lOCF'R E'&r::

20 .. 2203, sh.dl ir.dude an analpb that cstizates the radiation ~c (do.so) to & Ke.nber of tho ?ubl ic f:rtl~

uraniw:a fuel cycle sources. inclw:i~ all effluen~ pathvays and d1recc rad.L!lr;ion, for th" calendar y~ that: includes :he releue(s) co~r.d by this reporc:. It shall also dascr;;be levels of radia.41cm and coccenttacions of r&dioac:f.ve i:uc:eri.al

-* *~,-

27 Rev l 9/10/93

involved and th~ cause of the exposure levels or concentrations. If t:he estimated tlose(s :i exceeds the above limits, end if the release condition resulting in violation of 40CFR Part 190 has not already been correct~d, the Special Report shall .include a requ.,,st for a variance in accordance with the provisions of 40CFR Pe.rt 190. Subreittal of the report is considered a timely request c>.nd a variance :ls eranted until staff action on the request is complete.

3 .. Surveillance Requirements:

a. Cumulative dose contributions f°rom liquid and gaseous effluents shall be determined ir. accordance ~ith III.C.l, III.D.l and III.H.l and in .?ccordance.with the methodology and parameters in the ODCM.

b. Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Action 1.2 above.

4. B:o.ses:

This requirement is provided to meet the dose limitations of 40CFR Par~ 190 that have been incorporated into 10CFR Part 20 by 46 FK 185:25. It also requires the preparation and submittal of a Special Report whenGver the calculated d0ses from plant generated ~adioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except for thyroid, which shall ~e limited to less than or equal to 75 mrems. For sites containing up to 4 reactors, it is highl~ unlikely that the resultant dose to a Member of th~

Public will exceed the dose limits of 40G1'"1{ Part 190 if tha individual reactors remain within twice* the dose design objectives of Appendix I and if direct *,:r.-:iation doses from the reactor units and o.utside storage tanks ate~.kept .small.

Th.:!* Special Report will describe a course of: actfo~ that should result in the limitation of the annua*l dose *to a Member of the Public to within the 40CFR Part 190 limits. For the

. purposes of the Special Rtport, it may be assumed that the

dose commitment to the Member of the Public* from other uranium fuel cycle sources is negligible, with the.exc~ption that dose contributions from other nuclear fuel cycle facilities at the

. s*ame site or within a radius of. 8. km must be considered. . If

the dose to any MeT~*:,r. of the* Public is es'timated to* exceed

- the requirements of 40CFR Part 190, the Special Report with a

. .request for. . 3. .. variance.. (provided the .. *release ..~. conditions.

'resultlrig fo violati0n"o'f40CFR Part 190.have *~ot already been

. : :.'.eofrected);

.~ . : *; . .

in *'iccortlance with.. the prov1sioris:~of 40CFR-Part*.*

,l/1/9 3 .* '

.*;* ... *. ~ . '

.190.11 and 10CFR Part 20.405c, is considered* to be a timely request snd fulfills the requiremen<;s of *-"*OCFR Part 190 until NRG.staff action is completed. The variance only relates to the limits *of 40GFR. Part 190 and does not app:y in any way t~

the other require~ents for dose limi~ation of 10CFR Pnrt 20.

An individual .is not considered R Member of the Public durinp; any period in which he/she is engaged in carrying out a;"ly operation that is part of the nuclear fuel cycle.

J.

Radiological F.nvironmental Monitoring

1. Requirement:

The radiological . environmental monitorin~ program shall be conducted as specified in Table E-1.

2. Action:

a. With the radiological environmental monitoring program not being conducted as specified in Table E-1, prepare and submit to the NRG, in the Annual Radiological Environmental Op*::!rating Report a descript!.on of the reasons for not r.onductiag the program as required and the plans. for prc*1enting a recurrence.

b. With the level of radioactivity as the result of plant effluents in.*. an environmental sru:ipling medium at a specified location exceeding, the reporting levels of Table E-2 when a'.Teraged over any calendar quarter, prepare and submit to the NRG within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents. When r:iore than one of the radionuclides in Table E-2 are de~ected in tile sampling m.edium, this report shall be submitted if:

Goncent~~tion* (l) * +. Concentration ( 2) + ... -~ 1. 0 Reporting ~vel (1) Reporting Level (2) 1'1hen radiomiclides other than those in Table E-2 are

detected: .and. are thi:: result of plant effluents, this report shall* ba submitted if the potential annual dose.

to a*. Meriibe'r of the Public is equal to or greater than

the calendar year limits of III.C.l, III.D.l and III.H. l. This report is not required if the measured

. lev.el. of ra~~ ._)activity W8.S not the result of plant

. **effluents; . however' . in such an event' the condition

. shall * .. be ,, repo:rted . and .described in . the Annual

'Radlol~gical 0

Y**

... *,-,.. Eriv ir.6nmer1tal Operating. Report:.

Rev 0 1/1/93 '

F~-~t 7*

40CFR Part 190.11 and 10CFR Part 20.2203, is considered to be a timely request and fulfills the requirements of 40CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40CFR Part 190 and does .-..

not apply in any vay t::o the ot::her requirements for dose limitation of 10CFR Part: 20. An individWll is not considered a Member of the Public during any period in which he/she is engaged in carrying out any operation that is pa:-t of -che .(

r:*

nuclear fuel cycle.

J. Radiological Environpental ~oni;orini

1. Require~ent:

The radiological enviror.;c,ental i:::onitoring progra=i shall be conducted as specified in Table E-1.

2. Action:

a. Uith the r~diologic.l e:1viror.=:ental .:r,onitoring ?rogra:z not bi!ting conmxted as s~cified in Table E-1. prepare and suboi.t t.o the SAC, in the Annual Radiological E..T..rirorurenul Op.er.atL"l.g Report a description of the reasons for r..ot c~~t::ing the progrlil:2 as required and the pla..'l.S fo~ r;::eoo;.;:li.*~~'b ~ l.~~u=-:i:c:u:e.

b. 'liich tll-e level of radio~.c~:*d<.y a__::i; the result of ?lant::

efiluencs in ao e-nviron~~n::.31 ~ling .i:tedi~ at a spec!.fi~ lcc.aciooi exceecUng the r~;>ort::ing 1.e..-el.s of

!'Able E-2 when ~ra&ed over any calendar quarter.

prepare and subaU.t:: to the S'RC witi\in 30 ~ys a Sp.ecia.!.

Report chat ic!.ea:ifies the cause(s) fer exce~ding ~he lin!t(5) .;md <!'..efin.e5 th~ corrective 3Ct:ions to be ;:.ak.en to rcduc* radi1:i~t:h~ efflu.ent:s - io"h.en 2i0re th.an or.a of die radionui::Udes !n T.ahle £-2 are det::ecte-d *n clle S4!rpl1ng t::ed!am. t.hu report sh&U be sub3.lccea .f:

Conson;ttdw n y + Cs;tpeenrn;!cn (2_) + ___ -~ l..O Reporting Ln<tl (l) Repor~ic,g Level (2)

~"hen r&dio::r.=Udc.5 other 'Ch.n those ln Yablc £-2 a.re detected and ue the result of ?l&0c effluents. 'this reporc sh&ll be su.b:Jict:cd if rhO ;x>tent!4l an.'1Ual dose to a Kes:ber of ::.~e Public !s ~ to or gre~ter th.an the calcndu )'u.r l U1 u cf Ill .. C. l

II L D .. l , .-r.d It I . H. 1.. This re pore b not re~r~ 1 f t:ho in.e*sured lc'-"Ol of r*d.ic.ace.h'it;y v.ss noc d\e re.sul: of ?lane e.ffluents; htrlll'Sver. in suc..'i .an ar\*a:o:n:. the. condition shall be upo~d &nd d.scribed in the Amm&l iladlologtcal E:Ntrc:m.ental epcr.at1ng Reporc .

. -~. *.-

_..... - 29 llev l 9/10/93

c. With milk or ~resh leafy vegetable samples unavailable from one or mor~ of the sample loc.:1tions required by Table E-1, identify locations for obtaining replace@ent samples and add them to the radiological environmental monitoring pLogram within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring progrs.m. Identify th~

cause of the unavailability of samples and identify ~he new locaticn(s) for obtaining replacement samples in the next Annual Radiological Environmental Report:

3. Surveillance Requirements:

a. The radiological environmental monito::-ing samples shall be collected pursuant to Table E-1 and shall be analyzed pursuant to the requirements of Table. E-1 and the detection capabilities.required by Table*E-3.

b. A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 9 overland meteorological sectors of the nearest milk animal, the ne.arest residence and the .nearest garden of greater ~han Sv fil2. (500 ft 2 ) producing broad leaf vegetation. Proad leaf veget~tion sampling of at least three different kinds of vegetation may be perfoill1ed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. For broad leaf veg~tation sampling, Table E-1, item 4c, shall be followed, including analysis of control samples.

c. The land use census shall be conducted during the gro~ing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting loc;:>.l agriculture authcr.'<*-:a.s. ThP- results of the land use census shall be included in the Annual Radiological Envirorunental Operating Report and s!iall be included in a revision of the ODCM for use in the following calendar year.

d. Analyses shall be performed on radioactive materials supplied as part of an* Interlaboratory Comparison i ..

Program that has been approved by the NRG.

e. A summary of t:,'-,,.._ results* obtained as part of the above required Interloboratory Comparison Program shell be incluqed in .. the. Am1ual Radiological .. Envirprime~tal op~.~;iting Report*. '.,**,

30 . . Rev 0 ** '. :. . l/1/93 *

. ~-

. . .~ ~ ,.__ .. .::**;*.

f.

The environme.nta.l air s*amplers sha1.l be operationally checked mont~ly 3nd airflow verifiec annually.

4. Bases:

a. Monitoring Program The radiological environmental monitoring program provides r~p;:-osentative measu:::<:?ments of radiation and of radioactive materials in chose 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 !li\)nitoring program implementsSection IV.B.2 of Appendix I to 10CFR. Part 50 and thereby supplements the radiological* effluent monitoring program by verifying that the measurable concentrations of radioactiv*e materials and *levels of radiation are not higher than expected on the basis of the effluent measurements and the model~_ng of the environmental exposure pat:hways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first three years of commercial operatio.n. . Following this period, program ch&nges may be initiated based on operational experience.

The required detect.~on capabilities for environmental sample analyses are tabulated in terms of t:he lower limits of detection (LLDs). The LI..Ds required by Table E-3 are considered optimum for routine environmental mea£urements in industrial laboratorjes.

Detailed discussion of .the LLD, and other detection limits, can be :!:ou.'ld in P-~L Procedui:-::-- nanu2.l, HASL-300 (revised annually)*, C~rrie, LA, "Limits for Qualitative Detection and Quantitati_ve Determination -* Appi:ication to Radiochemistry," Anal' Chem 40, 586-92 (1968), and Hartwell, J K, "Detection Limits for Radioarialytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June* 1975).

b_ Land Use Census:

This requireme1*. is provided .to ensure that ch~nges in .

the use of areau at and, beyond the site boundary are

.... -. ..... . identified and that.. codifications., to the radiological ..

. ehvi ronmental moni tori ;g program .ire made' if raguire~{ by re_sults of ~his :~ensu.;;: :~: The.".bes~ *,inform'ati6;.1from-_.,.._- 'the'

~ . *: .

- 3f *::i)l/93

';.* .- _.. . :--.:;.. ~* . ;;. : ...

door-to-deer survey, from aeri~l sur'Vey or from consulting wit!. local agricultural c.uthorities shall be used. This census satisfies th~ requirements of Section IV.B.3 of Appendix I to 10CFR P~rt 50. *a~stricting the census to gardens of greater than 40 m2 provides assurance that significant exposure pathways via leafy vegetables wj 11 be identified and monitored since '*

garden of this size is the minimW11 required to produce the quantity (16 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden *size, thA following assumptions were mad~: ( 1) 20%. of the garden was *-~sed for growing broad . leaf vegetation '(ie, similar to lettuce and cabbage), and (2) a vegetation yield*of 2 kg/m2 *

c. Interlaboratory Comparison Program:

The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that: indapendent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality ass*Jrance program for* * * ~nvironmental monitoring in order to demonstrate that the results are valid for the purposes of Sec~lon !V.B.2 of Appendix I to 10CFR Part 50.

. ~.~~:/':')::\:::. ' . . ,. . *' )(', . ;..-* . - .

. . /'~-~; .:~ *>:)~-"H**::'._:;:~f:~f:i{A~,: :*- ,... *-*_-:-*

- .*1l~'t::*o

.1/1/93'

. £*-*-:-. *_~;'j*~.1-.f.c~.*

- ~*

i, *.

Table E-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

~;..,;;,-.: ~~;;,*r<< 1 r~-\'""\*liExpos~~re **Pathway* Number of Represent.'ltive Sampling a~1d Type. cf* Fre~.iency Sample$ and Sample Locationsa Collection Frequency of Analysis '. ~. +

,\,:. _*. ,;": :" *.:;<;:. ,!.

21' r~ut:lne monitoring stations Quarterly Gamma dose quarterly

,. .... ~

-'*. eithe~~:with two or more dooim.-:

.:.* *eters /iJr. with one instrwnent for .*,*.:.,

- \*irie'asuring .and recording dose. rate . :/'. *.;.:. ~-*

'.continuously' placed as follows:

- , .. 'I.*,;.. * .....

'An: i~ri.~~" ring of .stations, one in

. ,.*, .* .. *. e'ach oveihnd me teoroiogical sector

(9)' ~n'/the.:general area of the Site

B~undary: : -! *

.An*out~r l'ing.of stations, one in

- '.each .o.verland* meteorological: soc:t.or

'. (.9): Withfn the 12 km raPge fr.om the

., site'; * *

..*1:

The:.balance ~f the statioris:(3) to

be placed to serve ~s control stations.

\"***

33 Rev*o 1/1/93:'* ,,.

..... l

. .~ .. '

11. *1_'._.:_.__.:_:

- ~_;:-.

<_-.. ~ - -.:*,*:;.,t.........,.:. *~-_ .... /*;:.;,/:/. ;;*-

.* ':}t§J :; < .

.:-* *i,

..('.1.~~~2:1*

Table E-1 (cont'd)

.~;:,' .:-*, "';"; ,. .,~.:

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

.)~:,:'1

'Number of Representative .

Sampling and , .

Samples and Sample Lor.ations 8 *

Collection Freguer:c*y

-- '* ' " ~;)' .* ,::: .. 2 ~- j AIRhORNE Radioiodine and* Samplei from 5 locations Pai:.ticulates Continuous sampler Radio'\.odin~ - Canist~r:

3 samples from within 6 km of oparation with sample. I-131 analysis weekly for* ru collection weekly or each filter change.

the Site lloundary in different more frequently if sectors (2.4 km-SSW, 5.6 km-ESE required by dust and 1.6 km-N). Particulate Sampler; loading. Gross beta radioactivity _

1 sample from the vicinity of a analysis following filter-

community having the highest . changed. Gamma isotopic * -_

calculated annual average ~round analysise if gross beta r/ m3 .

.,,,~1 .u' pt*l level D/Q (Covert-5.6 km-SE).

1 sample from a control location in the least prevalent wind directionc (Grand Rapids 89 km-NNE).

34 Rev 0 1/1/93

. *~ ..; ., -

Table E-1 (cont'd)

..... .., RADIOLOGICAL ENVIRONMENTALMONITORING PROGRAM ':_._

. '.:; '. ~

Path~ay Number of Representative Sampling and Type of Ft~que11cy _

..,._...,.......-... .,......,.__s""*a;m.,.p=l.:;e'------S"'"*=iun=p-=l.,.e'""'s'"-"a::.:n.:.;d:......;:S amp 1 e Lo cat i onsa Collection Frequency of Analysis*

.:*,.i,.;_~_.-,.... !'/..

. *-:**. * . .-.'.'.!, (;(~ATERBORNE

~- . *-~ -.. *rJ*

' '.;:;f.~'.,;;,;rt~~7h *.**c s,urf.c.). .. Plant Jake water inlet. *compositc*sample.over.

1-inonth periodf.c *: **. * *. ,.

.. *... /: '".

. \ *' :** ~

Samples from plant, State Monthly grab: sample. * *, Gross* beta' '(>10 ,:pci)l :_

.*.*-- *Park; and Covert Township **requires gamma) *and**/*:*

." .. :. ~- *, '

park wells .. *:.tritium monthly. - ** * *

- \ '. - : ., ' .

' ~ ... :-~ ~ .-

. Lak~ (drinking) 1 sample of South Haven Composite sample-over drinking water supply. 1-month periodf. * * .* .

tritium mcnthly. *

'. s-~diment from 1 sample from between north *Semiannually. *Gamma.isotopic

... shoreline ..boun~ary and Van Buren State semiannually.

Park* beach.

't***

. " .... .!,: ,*: *.:.:*:,.-:J .):*:~~'

' - . -~" 35 Rev o '1/1)93':'_,

..;{/ ...

.1 ' . ,,*

. . -~ ,. ....

\"

.*-.---.,----.':'"""_"--.:'...-;**............ :--*------.*~-.--~7 - ......

r-

.:* . ' .. ~***

'*'.-;_,**_,)

-:.. ~

':*~*"*

Table E-1 (cont'd) ..

.. ,. *::';~=:-:-

..** ;.".m"

.' 'i. . .-~:0~~1 RADlOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

- !.~ .. *.,.*.'

, Numb~r of Representative Sampiing';~ncl 1; __ : . Type of ~'~equency .. * .. ;-.'~":,__ .M;":\

Samples and Sample Locations 8 *. Collection Frequency ~~ ~*;~._:"*' -~-'l:;i-~~*

'*, >~: :/;'-(;<'.

c - * .; .. '

of Analysis *

. ~~;., . '.<

. :. f.~* a:{;' Milk, Samj'1les from milking animals

~:~.-* '*<*. ~ ,,\:.~ . . ,, lfonthly .'. *.. : . Gamma isotopicc_ and i.n 3 locations between 5-13 km distance . analysis monthly ..

.*, . :*~ ' .

1. sample fro1n milking anirnals at c& c'ontrol locatlon, 15-30 km*

.*distance.

... ~

and .Sainp'ie 2 species of commer- Sample in season or Invertebrates ci~llf and/or recreationally semiannually if they

. :important species in vicinity 'are not seasonal; .

.of plant discharge area ..

1 sampfe of same species in areas"

.:*. not<influenced by plant.discharge

)\:;~~£~~\~

36 Rev 0 l/l/93 .

. */.

., .~, " ...

- -,* .--*: ... ,*{'.. ~*- ,'

. Table E-( (cont'.d)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.

".-'}"

. '.:. ~* :

Pathway.** *.*Number of Representative.* Sampling and '.fype c:*:* Frequency *,-:..:

.,.....~*~

.. .,.....~~='->'-..,_~S=a~rn~p~l~e'--~~~~=S=a~rn~p~l~e,.s<-.!a~n~d"'--~S=a~m~p~l~e'--"L~o~c~a~t~i~o~n~s=a~~~-"'C~o~l~l.~e~c~t~i~o~n~Fo...::.r=e~q~u~*e~n~c~y'--~~~~~of Ana~ysis

".r:*.*: *-.

1 .sample each of t\.'O principal At tlrne of harvestg. Gamma isotopic .;_nalysese'.

frufr*crops (blueberries and on edibie.portion, *

. <tppl'e.s) .

Samples of 3 different kinds of Monthly when avail- Gamma isotopice and . I~ Di°/'~-/~

broad -leaf vegetation grown *

. rie'ar~s t each of two diffe:i:e11t able. analysis ..

. *vg~l~(

offsite locations cf highest

.*.- . predi9 ted annual average ,ground

..:,*, level D/Q if milk sample is not

,:, per.formed. (SE or SSE sP.ctors

!**, near site).

1 sample of each of the similar* Monthly when avail- Gamma isotopice broad::ieaf veg1atati*)n grown 15- able . analysis.

. 30 ~.:distance in the *least

~prevalent'wind direction if

~,, ._'

milk*isampling is not performed. *

" 'Cs.sw.* 6r s sectors). *

~ '. .'

~-*:...:>" ~ *.

~-, ;, ._I: 'Ir

"::'i." 37 Rev 0 1/1/93

.- - . . ..:~~;*: ::*: ~-.' .' '

'.\' *.,-

. ,*; :;;* .;<f:~_:t .

';f.P.>r!!>'t.~- ....*\\*><;1'"L""--:"'Je<'","'~""'**"'!\:"*~'"

'",~ "'*~*'"'**~"'t,~ ,,.i,*'* *:~**,

.'.~*-*1;~--~~~-~~'!1:-;:f&?~~~-::~~*?--?i~~:)';*y.~, :*:,,.:'.*~-~**5-:*~,: ~ >."':? *:-'!**.- .. ,' ** ***;" '**,.,,*;. ~,; '.:i.'r * ~--: ':' ~ * '

.* '."*~.** *: ~~:r:~- .T'""""**";')";""~"':-~-:r--*~!=_.?'"!!:*-T*-:--~;-*:*~.-.~~*-r.:"*~ c-

. .. , ~ . :

Table E-1 (c0nt'd)

Table Notatioq

ii

.,i;

'*/,.':{- *~,

- an~viations are permitted from the. required sampling schedule if specimens are unobtainable due to hazardous

. *. conditio~lS, seasonal unavailability, malfunction of automatic sampling equipment and other legit:.rnate reasons.

le~*

n specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to co11*_)lete correctivG.:

. a'ction prior to the end or' the next sampling period. All deviations from the sampling *schedule shall be documented

~.n\the Al)_nual Radiological Environmental Opereting Report. It is recognized that, at times, it may not be possiblfl.J

.or.'practice.ble to continue to obtain samples of the media of choice at the most desired location or time. In thest~:

_ *.: .nstances, suitable alternative media and locations may le chosen for the particular pathway in question. anfij appropriate. substitutions made within 30 days in the radioloeical envirorunental monitoring program.

QI.-:~

.-2.-: .

bo~e. Or**: ID~re instruments 1 . SUCh as a preBSUrized ion Chamber 1 for measuring and recording dose rite COntiOUOUsly may<-:~*

.*., he**used in place, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent ..

dosimeter_(TLD) is considered to be one phosphor; two or more phosphors or phosphor readout ~ones in a packet are*

considered as two or more dosimeter.s.

*" .*cThe purpose of this sample is to obtain background information. If it is not practical to estabUsh control'.*

lo*c*ati.ons .in ;:ncordance with the distance and wind direction criteria, other sites that provide valid background data*

may be-,..substlt..ited .

.. ; . dAlrbo'rne'.*:particulate sample filters shall bP. 1malyzed for groas beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling.;

to allow for: radon and thoron daughter decay. If gross beta activity f.n air particulate samples is greater than ten .

timei:: the. yearly mean of control samples, ga'.Illlla isotopic an.'i::..Jsis shall be performed on the individual so.mples .

. '. eGamma' .:ls~topic analysis rueans the identification and quantification of gamma-emitting radionuclides that may be

. *, attributable to the effluents from the facility .

. fA: composite sample is one in which the quantity (aliquot) 0£ liquid samples is proportional to the quant;_ty of liquid

.discharged '.md_ in which the methor' of s ID1pling employed results in a. epecimen th!lt is representative cf the. liquid*

, ,'released, (continuous composites or daily grab composites which meet this criteria are acceptable).

1 gif ha4'Vest occurs more than once a yea:7, sampling shall be performed during each discrete harvest.

38 Rev 0 1/1/93

' ~ ** * ........... _ .. _~- - ----~-~ ~~~t*-z--* '~-*rts* ..;:. ..:...f.,..t:'>ifsi!:z1§st.a\pf"iff..:;.15*;..;~<J~~jfutttj\glrfiti:)" ;;!fi:. .i.Jstr&.

1 *** ...: **,~ J'" ...... di. --,.. ~l: .. /*..,~*:.. :(~-- -~;"...;

-~ .. * '-.;. ,;*'..\;

table.* E-2* .....

REPORTING~LEVELS*FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPL7~

.-. RP.porting Levels

~- ' * ...:* .. ,

.Water Airborne Particulates** Fish Milk Food * .i:'roduc ts .

CpCi/1) or GasAs (pCi/m3) (pCi/kg, Wet) (pCi/l) cpcifkg. wet>:~::*

20,000* *"1'*

1;000 30;000

>>:*400* 10,GOO i*ooo 30,000 .:-* ::.

300 10,000 300 20,000 400 2 0.9 ' 3 *. ~--~:,_-;_ :~ .. ,,._'~\

30 10 1,000 60 1,000 .'. . . .- ";~~:_ ~:: --~ :>.:,,~ -~::

.~

so 200 20 2,000 300 70 2,000-

. )!'.:I;~~

J **~ ., .:"y ...;:: .

1.ocFR Part 14T value.

...~ .: *~

1***

39 Rev 0 1/1/9.3>

. -:.,:.'1

~;.

~* I

~-: ' .

~ .. '*' ,* ,.'r ........

i~ble'E-3 -.: .

CAPABILITIES FOR. ENVIIfoNMENTAl; SAMPLE ANALYSIS 8 : 1 LOWER LIMIT OF DETECTION (LLD)bc j,'

Watar Ai.rborne Particulates Fish *Milk Food Products CpCi/U *":<<:or Gases (i;!CiLm 3 } (RC!Lki; ,* Wet} (i;!CiLll (pl;i/kg' .. Wet)

..... , 0.01

-:~ ,*

'I~ 2,000*

15 130 30 260 "

15 130 '"

30 .:' . *. 260 ., :.

15.

' .~

ld:. 0.07 1 60 .. ,

is*:!* 0.05 BJ 15 80 18 ., ,*,_,.

., *0.06 150 18 80 15 15

(~\:';1".If

.no,: drlnking water pathway exists, a value of 3,000 pCi/l may be used .

. ;*~* ~- ,:

'*.~ ..

J 40 '1/1/93 ..

. . . '.*.t

Fn:::*..ir"7.

..:ll "".lt.* .

Table E-3 jCont'd) a This lis:. does not:. mean that only t:-:ese nuclides are to be considered. Other peaks that arc identifiable, together with those of the above nuclides, shall als._ be analyzed and reported in the Annual Radiological Environmental Operating Report.

bRequired detP.ction capabilities for tilermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

cThe LLD is defined as the smallest concentration of radioactive material ia a sample that will yield a net count, above system background, that will be det:ected with 95% probability with only 5% probability of falsely conclud.!~g !:hat a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD E

V

2 . 22

Y

Exp ( - >.~ t)

Where:

LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume.

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute.

E is the counting efficiency, as counts per disintegration.

V is the sample size in units of mass or volume.

2.22 is the number of disintegrations per minute per pi:-:-::~urie.

Y is the fractional radiochemical yield, when applicable.

>. is the radioactive decay constant for the particular radionuclide.

~t for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting.

Typical values of E, V, Y and~~ sh0uld be used in the calculation.

41 Rev 0 1/1/93.

- ~ .., .. ~

.°l'ABLE NQ:i}.TION It . sho~ld: be * *r~ *::o:gni~ed that the LLD is defined a~. an "8... priori." (before the

. fact) limit' ;.:;'-,resenting the capability of a ineasi:ire~ent system arid riot as an "a

-po-stetiorl" (aftE;r the fact) limit for a parti~ular measurement . .tillalyses shall

. be pel:formed in such a manner that the state.d LLDs will be achieved under routine

conditions~ Occasionally background fluctuations; unavoidable *small sample sizes. *.,the pres~nce of interfering. nuclides. or . *othtr uncontrollable

circiunstances *- m~y r~:-.cier* these LI.Ds *unachievable.

In .*such: cases, **the contributing facto;-s shall _be identified and described iri the Annual Radiolcgical Environinental_Opera~ing *Report.* '

dLI.ri for* drinking' .water samples. *If no drinking water p~thway exists, the LLD of gainma~ 'i.sotopic" analysis may be used ..

~~:~;--.-

-~~ '* '

-~*:

, '.l '

.*,. *:~;;::- />~~- *::~ .

K. SIRIJ or Temporary 1"1.Quid Storage T:i°nk 1.* Requh:ement:

The concentration of radioactive material contained iu the SIRW tank or a~y unfrotected outside temporary tank* shall t~

limited such that the mixture radionuclides do not exce.:d 1,000 times the effluent concentration (EC) as listed in 10CFR Part 20, Appendix B, Table 2, Column 2.

2. Actio;.1:

Wit~, the. quantity of radioact:ive material in any of the abo-...~e listed tanks .exceeding the above concentration, immediately suspe~d all additions of radioact!ve material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents tc within the-li~it, and describe the events leading to this conditior. -..:1 the next Radiological Effluent Release Report.

3. Surveillance Requirement:

The concentration of radioactivr. material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a_ representative sample of the tank's contents at least once per 7 days wnen radioactive materials

.are being added to the .tank.

4. Bases:

This requirament will provide reasonable assurance that in the event of an uncontrolled release uf the tanks' contents, the resulting concentrations would be less than the limits of 10CFR Part 20, Appendix B, Table 2, Column~, 8t thA n°~rP.~t pota~le water supply and the nearest surface water supply in an Unrestricted Area. (The dilution between Palisades and the South Haven drinking water supply has '..."'en established as

1ooor.

Tanks included in this specification are those outdoor tanks that are no~ surrounded* by liners. dikes. or walls capable of holding the tank co;tents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

~~ *. :?*: ..

$: ?.~:::

- -~.

... *~ **~. J

-/.. --*. . : .:- .-~ -

Rev o 1/1/93

'il :,)t;~F:.<:,.: -~.

K. SIRW or Temporary Liquid Storage Tank

1. Requirement:

The concentration of radioactive material contained in the SIRW tank or any unprotected outside temporary tank* shall be limited such that the mixture radionuclides do not exceed 1,000 times the effluent concentration (EC) as listed in 10CFR Part 20, Appendix B, Table 2, Column 2.

.Qb ... + .Qi <1000 ECb ECi

2. Action:

With the quantity.of radioactive material in any of the above listed tanks exceeding the above concentration, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Radiological Effluent Release Report.

3. Surveillance Requirement:

The concentration of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

4. Bases:

This requirement will provide reasonable assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be *less than the limits of 10CFR Part.20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an Unrestricted Area. (The dilution between Palisades and the South Haven drinking* water supply has been established as

. 1000).

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 that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

43 Rev 2 01/05/94

-'." .. -.. :.'. ...-. ~.* . ~. . ._; .... ;

2392 IV. REPOR'rING REQUIREMENTS A. Radiological Effluent Raleas~ Report

.i.he Radioactive Effluent Release Report shall be submitted in accordance with 10CFR 50.3Ga. The report chall include a summary oi the quantities of radioac~ive liquid and gaseous effluents and solid waste reh*ased from the unit. The material prc-vided shall be (1) consistent with the objeccivP.s outlined in the ODCM and Process Control Program ~nd (2) in ~onfonnance with 10CFR 50.36s and Section IV.B.l of Appendix I ~o lOGFR .50.

The report shall include an estimate of the uncertainty associate~

with the measurement of radioactive effluents. l'his error terrn is included to provide an estimate of the uncertainty and is ~ot to be considered the absolute error assoc.iated with the ceasurement'c: or to be used in determining compliance with these requiremer.~.-.

These estimdtes will be bas~d on a statistical ana~ysis of a series of sample r~sults (~eighed appropriately fer ccunting statistics) taken once a year frcm a minimum of one typical gase~us waste tank and from a minimwu of one typical 11.:i.uid waste tank. For noble gases reh.~sed to the a:cmosphere from other than the waste gels system the error term will be estimated (and weight-averaged with the waste gas tank error) based on a statistical analysis of a series of sample results taken once a year (or the stack gas monitor counting statistics taker. over one release per year) from each source contributing more than 10% of the total annual release.

The error cerm for iodine and particulates released to the atmosphere will be based on the countin5 statis~ics for one stack gas sample taken during the year.

The report 3hall include an estimate of the lower level of detection (in µ.Ci/ml) if the unidentified portion of the release exceeds 10%

of the total annual releases. This estimate oi ~ne lower level of detection will be made for those gfilIIIDa emitting isotopes listed in Appendix B of Regulato~y Guide 1.21 (June 1974) and will be provided based on a typical background gamma spectrum.

The report ~h~ll provide the following specific terms:

1. Supplemental Information

a. Batch Releases~

The report should provide information rGlating to batch releases of liqu!.d c.nd gaseous effluents which are discharged to the environment. This information shc*.:.ld include the .1u.mber *of relf'ases, total time period for 44 Rev 0 1/1/93

"* '~*

...:. \:-.-'

I,,.*

batch relesses, and the maximum, mean, and minimWll time period of relea~e.

b. Abnormal Releases The nw:iber of abnormal releases of radioactive material to the environment should be reported. The total curi. 9S of radioactive materials releas~d as a result of abnormal rel~ases should be included.

2. Gaseous Effluents

a. Gases

1) Total curies of fission and activation gases releases.

2) Average release rates (µCi/s) of fissio;.1 and activation gases for the r,uartcrly periods covered by the report.

3) Percent of limit for releases of fission and activation gases.

4) Quarterly sums of total curies for each of the radionuclides determin~d to be released, based on analyse8 of fission and activation gases.

b. Iodines

1) Total curies of each of the isotopes, Iodine-131, Iodine-133 and Iodine-135 determined to be released.

2) Average release rate (µCi/s) of Iodine-131/133.

3) Percent of limit for:Iodine-131/133.

c. Particulates

1) Total curies of *radioactive material in particuJ.ate form with half-lives greater than 8 days' determined to be released.

2) . Average release rate (µCi/s) of radioactive

inaterL.:. in particulate* form with llalf-lives greater thrtn 8 days.

' ,. *. -~ ..*

- ..~

Rev 0 1/1/9.3

.: : .~.

i.1.1.f.IIt~1~~~m%}Jr1~t~!~~~[)'~~~~"'

' ......,. '.; *:*:.'*:/"';

3)' '.Perce:1t ** c;;f. limit . for radioactive material

in .

, "*part:f.cuiat-e 'form' wit.h half- !ives greater ~han 8' days.

4) Total curies for each of the radionuclidns in partic.ulate form determined to be released basf'd on analyses performed.

5) Total curies of gro.:;s alpha radioactivity

determined to be released.

d. Tritium

1) .Total curies of tritium dete~.ined to be released.

'in.gaseous effluents.

2) Average release rate (µCi/s) of triti:'.:.:.

3) Percent of applicable limits fo~ tritium.

3. Liquid Effluents

a. Mixed 'Fission *a.1d Activa\.:ion Products

1) Total curies of radioactive material determined t.o be released in liquf-i effluents (not including tritium, - dissolved and/or entrained gases, and alpha-emitting material).

2) Average conc:mtrations (µCi/ml) of n-~_xed fission

.and activation products released to unrestricted areas, averaged over the quarterly periods covered by the report.

3) .Percent of applicable limit of average concentretions released to .,_,~,;, i!strict~d areas. *

. *- . ! - .* -~* ..

4) : QlJ~teriy- ~~s of. *t:~tal c~ries _for ea~h c.*f the radionuclitles determin6d to be released in liquid e:f:fiuents based on ana~yses performed .

...' . -' *.' ~-

.- . ~

'Tritit'mi'

1) Total curies of critium determined to be released in liquld effluents .

~f -:

2) ,Ayerage _ * -co'ncentrati.ons (µCi/ml) of tritium

., .:_rE:leased - in . - liquid .. effluents to ... unrestricted

_::.)~~~l~i.d'.~;;i~tf:~:~~:;;:\}~~~ .: .~~-~~~~ly . perio~ *.. ~* -

-. '* :*... :~.. .::. *.-. - .~: -. *'

~-- * . ,_.. R.ev o 1/1/9_3'

_, J ... _:;~ * ,.: F *.

'~ :'\Y>}_~:r.::'.~ f . .::.~~'.;::.':'

- .:23*nr5*'

~. - **?; .. , _ ,......*.*_,,_ .

3) Percent of applicable limit. of average concentrat~ons released to u~~estricted ar&~s.

c. Dissolved and/or Entrained Gases

.1) Total curies of gaseous radioactive material.

determined to be released in liquid effluents.

2) Average concentrations (µCi/ml) of dissolved

and/or entrained gaseous radioactive material*

released to unrestricted areas, averaged over the quarterly periods covered by the report.

3) Percent of applicable limit of average concentrations released to unrestricted areas.

4) Total curies for each of the rac.i *:-nuc}.ides determined to be released as dissoJ.ve.d. and/or entrained gases in liquid efflue~ts.

d. Alpha Radioactivity Total curies of gross alphc1.-emitting material determined to be released in liquid effluents.

e. Volumes

1) Total measured volUI:Je (liters), prior to dilution, of liquid effluent released.

2) Total determined volume, in liters, of dilution water used during the period of the report.

4. Radiological Impact on Man:

The Radioactive Effluent Release Re/'::t shall include potential doses to* individuals and populations calculated

using *measured effluent and averaged meteorological dli~a in accordance with the methodologies in the ODCM.

a. Total body and significant organ doses (greater than 1

. .:*, millirem to individuals .in unrestricted areas from

'l(~:' receiving water-re_lated exposure pathways.

t .- :*;_.

b. The maximum of~site air doses (greater than 1 millirad)

.. ~ -~.

due to beta ar.." gamma radiation at locations near ground level from gaseous effluents .

.1ti . .-*._

~1-~.;.

,.**I 47 . Rev 0 1/1/93 .. **

)

I '\'

""!, ._~. '1 *

,*(

1",*

. c .. .Organ doses (greater than 1 millirem) to indi"vidu~ls in unre.stricted arn.as from raclioart;ive iodine and radioactive material in particulate form from the major pathways of exposure.

d. Total body doses (greater. than 1 manrem) to the population and average doses (greater than 1 millirei:')

1 to individuals in the population from receiving water-ralated pathw.?>ys to a distance of 50 miles from the site .

. e. rotal body doses (greater than 1 'manrem) to the population and average doses (greater 'than 1 millirem) to individuals in the population from gaseous effluents

-*~1:

to a distance of 50 miles from the site.

,: l

.. 5. ODCM Changes:

.1 :j The Radiological Effluent Release Report shall inclu<le sny changes made during tne reporting period to the Offsite Dose i

Calculation Manual (ODCM), as well as a listing of new locations for dose calculations and/or environmental monj t:oring identified by the .;.and use census pursuant to

~L III...,.3.c.

B. Radiological Environmental Operating Repor_t The Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submi t:ted . before May 1 of eac~ year. The report sh!'.ll include summaries, interpretations, and a:i.al~rsis of trends of the results of j the Radiological Environmental Monitoring Program for the reporting j period. The material provided shall be consistent with th~

I 1 objectives outlined in; (1) the ODCM, and (2) ::>ect:ions lV . .b.:i.,

I IV.B.3 and IV.C of Appendix i to 10CFR50.

i l :*.*

1 .....* .

The Annual Radiological Environmental Operating Reports shall include summaries, interpretation and statistical evaluation cf the J results of the radiological environmental surveillance activities

! /:. for the report period, including a comparison with preoperational l-1 studies, operational controls (as appropriate) and previous i environment.il surveillance reports and r:, '1 assessment of the observed

~ impacts of the plant operation on the environment. The reports shall also include the results of lan::'i use census pursuant to III.J.3.c~

i .** .>.

.~' .*,,

Rev o 48 1/1/93 ..

.),*,

The Annual Radiol0gi~al Environmental Operating Repn~ts shall include summarized an::l tab*.~lated results in ... he format o::'. Table F-1 of all radiological environmental samples taken during the report

-period. In the event that some results are _,ot available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missin6 results. Tbs missing dsta shall be submitted as soon as possible in a sup?lementary rep~rt.

Tha reports shall also ~~elude the follow~ng; a summary description of the radiological ei.1virorunental monitoring program including sampling methods for each sample type, a map of all sampling locatiom; keyed to a table giving distances and directions from the reactor and the results of land use census re qui:: ed by III. J. 3. c and result.; of the Interlaboratory Comparison Program required by III.J .3.e.

C. Nonroutine Reports A report shall be submitted t0 the NRC in the event that; 1) the Radiological Environmental Monitoring Programs are not substantially conducted as described in Sectior.. III .J, or 2) an unusual or important event occurs from plant operation that causes a signif!~ant environmentdl impact or affects a potential environmental impact. Rep.:-rts shall be s\.*.~mitted within 30 days .

. .... . -~* - . ..

R~v o 1/1/93

Table F-1 ENVIRONMENTAL RADIOLOGICAL MJNITORING PROGRAM SU!-t1ARY Name o! F a c i l i t y - - - - - - - - - - - - - - - Docket No - - - - - - - - - -

Location o! F a c i l i t y - - - - - - - - - - - - - - - Ropllrting Period - - - - - ' - - - - - -

(County, State)

Typo/Totol Lowor Limit All Indicator Medlu..:* or Pathway Nwnber of of Locations Control Locations Number ?! , ... ,.*.

, Samiil.od Analyses Detection* Mo em cob llame Mean (!)~ Mean(!)b REPORTABLE* .1 ~.:.

Cui1i t of Measure. ) Performed CLLD) Rangeb Distance & Dirsction Rangeb. Rang ab OCCURRENCES.

Air Pa~ticulat.os Gross fl 416 0.003 0.08 (200/312) Middlotown 0.10(5/52) 0.08 (8/104)- *..*\O )~~~;~

(pC.i./m3). CC.05-2.0) 5 miles 340" (0.08-2.0). (0.05-1.40)

*~ .~ .. '.

rSpec 32 Cs-137 0.003 0.05 (4/24) Smithvillo 0.08 (2/4). <LLD

... *. 1 (0.03-0.13) 2.5 miles 160" (0.03-0.13)

"'.'1-ltO 0.003. 0.03 (2/24) Podunk 0.05 (2/4) 0. 02 (1~8). l (0.01-0.08) 4 miles 270" (0.0l-0,08) i-:r-89 40 0.002 <LLD <LL!'

Sr *;-* 40 0,0003 <LLD <LLD 0

-< * ~.

50 R8V 0 l/1/S3

*t.

. :-.-.* ..*' .:r.= .

,;*. :t._ ",*

-.... *,:**. I.able .F-i. (Cont'd)

.\,",><'."*'t

'.L'ype/Iotal . Lower Limit All Indicator

"Number o! : o! "' Locations Number o! ::*.*: ..

Control Locations

Analyses

Detllcti'on* Hean (()b Name H~~* (t:)b Hean(f)b 'REPORTABLE Performed* (LLD) Rangeb DiNtancu & Direction R1mg0b Rims ob OCCURRENCES * *

~eight) .,-Spec 8'.

.. *,~* :~~. . *.

Cs-ln 80 <LLD <LLD 90 (1/~) 0

_;I '* ; , *.

t . -~,

80 <LLD <LLD <LLD 0" f~~~i~i~l~','t~t,~l *'.

80 120 (3/4) River Mile 35

Seo Column 4 <I.LO 0 (90-200) eodunlc River l' CoOO

,~,~~~:.;.1;;c::.~Noaiirii1:1/"Lower Limit.'.o! .Detlction.(LLDJ as* definer\ in table not.Gt.ion c of Table E-3.

'.Y'.~;*:~*~:~~?-~ ~~~.~.- .~.:-.rr~~:~*!-~':i~:/, ~r;*. * .~* . *:*~.-- .. ~ :.:. * *

'~/?/~;-'*'. bMeM'::*kd"::~~g11:'based upon d1t.1ctabh munurcaient.1 . .,nly, Freet.ion of detectable moaaur8tllont.a at spocific locations

\~~~f;;~t:~};J}~~;~:':~~ i~'.~~~.~~*thc~~a (!) ,'

,!1:';"::;*, *., ~:.dNot.e;:*~.,The'7examph data are provided !or illuat.rat.ive purpoBe11 only.

. *:U~:::*

.*:A;f~>::~ .

. "; -~.

.**t,.=:.::.,:*\: ~; *:;*

. ~ *> ' *.~ *;

~-~:f.'.:~.-~:~. ('.>:"* ;. ,,_ .

,":) ....

51 Rav*o 1/1/93

.:* .~'-.

" '* v *: . .~:/~.J'oa, ~onrFrcA'i'ioNs. T6 --RADro'Aci.r1~ LIQUID AND GASEOUS !IASTE TREATMENT .

..... * . , :. :*'SYSTEMS,: . --

Lic~n~~e Modifications 0

A;,

-Licensee iI-i:iti~ted major .m6difications to the radioactive liquid and gaseous waste syste~s.

1. Shall be reported to the NRC pursu<int to 10CFR 50. 59. The:

discussion of each ruodlfication shall contain:

. : .... a~ . A summary of the evaluation that led. to th2 determination that the modification could be made in

- - ' accordance with 10CFR Part 50.59.

b. A description of. the equipment, components and processes irivolved and the interfaces with other plant: :;y.:tems.

c. *Documentation cf the fact that the modificati<in was reviewed and found acceptable by the PRC.

2 .. ' Shall become effective upon review and acceptance by the Plant .

General Manager.

B. Definition of Major Radwaste System Modification 1.

Purpose:

The purpose of this definition is to assure that this requirement will be SRtisfied under clearly identifiable circumstances, and with the objective that current radwaste system capabilities are not jeopardizE:d.

2. Definition:

'A major radwaste system* modification i~: ~ modification ~hich

would remove. (either by bypassing or "physical removal) or

replace with". less efffoient equipment, any components of the radwaste sy_s telD : _

a. *Letdown. fifters or demineralizers.

Vacuum d.;ga~_s:i.fier.

c: -. Mi_~ce.llaaeou.s or clean waste evaporators.

\ ~ .

.. <*:.**:' _;-!)*- -.- -* . .- . '

-a. _.. The *p':-._..>ent . ~

W"lste gas compressor/decay tank system.

, *: R~~_:O {_;::"))~'/~3 ,.

- - ,, { :.

_. ~ ~; c ; * ,~:

~***_

V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE TREATMENT SYSTEMS A. Licensee Modifications Licensee initiated major modifications to the radioactive liquid and gaseous waste systems.

1. Shall be reported to the ~'RC pursuant to 10CFR 50.59. The discussion of each modification shall contain:

a. A su=ary of the evaluation that led to the determination that the modification could be made in accordance *ith 10CFR Part 50.59.

b. A description of the equipment, components and processes involved, and the interfaces *ith other Plant syst:e~.

c. Docll!l2entat:ion of the fact that: the modification ;:as reviewed and found acceptable by the PRC.

2. Shall become effective upon review and acceptance by the Plant General Man.ager.

B. Definition of Mejor Rad-.r?~5:t:e Svst:P..!!L Modificat:ion 1.

Purpose:

The purposf' of ::!l.!.s ~efinii:ion is ::o assure t:hat: dlis rcquire:ent *1,:ill be satisfied under clearly identifiable circUI:!.Stancas, and vi.th cite objective that current radwaste systP.m capabilities are not jeopardized.

2. Definition:

A major rachlaste systen i::wdification is a modification which would remove (eithe: by bypassing for greater than 7 days or physical re~oval) or replace ~ith less efficient equip~ent, any cocponents of tile radwaste systeQ:

a. Letdo....-n filters or deciineralizers.

b. VacuUI!! degassifier (not applicable b"hen the reactor is in cold shut:do~-n and depressuri=ed).

c. Miscellaneous or clean waste evaporators.

d. The present vaste gas coc:pressor/decay tank system.

~ Fuel Pool filters/demineralizers.

52 Rev l 9/10/93

~-...

f. Radwaste polishing demineralize*:s.

~- Radwaste Solidification system.

Improvements or additions to imp:CQVe effic.:iency will not be considered major modifications unle.ss a *complete substitt<tion of equipment or systems is made witi1 equipment of unrelated design. Examples would be; 1) replacement of mechanical degassif~er with steam, jet degassifier, 2) ::::eplacement of waste gas system with cryogenic system, 3) replacement of asphalt solidification with cement system, and 4) ch~nge from deep bead resins to Powdex, etc.

SJ Rev 0 1/1/93'

.:;,_ T

. .' ~ -

Relocated Technical Specifications Introduction The NRG, through 10CFR 50.36a, requires implementation of Technical Specifications on effluents from nuclear power plants. NRC Generic Letter 89-01, dated January 31, 1989, allowed the relocation of the existing procedural requirements from the Technical Specifications (implemented in Amendment 85, November 9, 1984). The relocated procedural requirements pertaining to solid radwaste follow below. Programmatic controls are retained in the Administrative Controls section of the Technical Specifications to satisfy the regulatory requirements of 10CFR 50. 36a. The Technical Specifications programmatic controls include requirements for the establishment, implementation, maintenance and changes to the Process Control Program (PCP), as well as record retention and reporting requirements.

Definitions The Technical Specification's definition of the PCP is:

The Process Control Program (PCP) shall contain the current formulas, sampling, analyses test and determinations, to be ,made to ensure that processing and I I packaging of solid radioactive wastes based on demonstrated processing of actuai or simulated wet solid wa~tes will be accomplished in such a way as to assure compliance with 10CFR Parts 20, 61, and 71, State regulations, burial ground requirements-, and other requirements governing the disposal of solid radioactive waste.

Solidification shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).

Requirements The solid radwaste system shall be used in accordance with the PCP to process wet radioactive wastes to meet shipping and burial ground requirements.

Action With the provisions of the PCP not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site.

Surveillance Requirements The Process Control Program shall be used to verify the solidification of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (eg, filter sludges, spent resins, evaporator bottoms and boric acid solutions) .

1 Rev 4 1/1/93

a. If any test specimen fails to verify solidification, the solidification of the batch under test shall be suspended until such time as additional test specimens ca~ be obtained,- alternative solidification parameters can be determined in accordance with the Process Control Program and a subsequent test verifies solidification. Solidification of the batch may then be resumed using the alternative solidification -parameters determined by the Process Control Program.

b. If the initial test specimen_ from -a batch of waste fails to verify solidification, the Process Control Program shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least:* J __ _

consecutive initial test specimens demonstrate solidification. The -

Process Control Program shall be modified as required, as provided in the Technical Specifications, 6.19, to assure solidification of subsequent batches of waste.

Solid Radioactive Yaste The Process Control Program implements the requirements of 10CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10CFR Part 50. - The proces~

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.

Reporting Requirements The Radiological Effluent Release Report, pursuant to the Plant Technical Specifications, shall include the following information for each class of solid waste (as defined by 10CFR Part 61) shipped offsite during the report period.

(Additional details of the report are contained in the Offsite Dose Calculation Manual).

a. Container burial volume.

b. Total curie quantity (specify whether determined by measurement or estimate).

_ c. Principal radionuclides (specify - whether determined by measurement or estimate).

d. Source of waste and processing employed (eg, dewatered spent resin, compacted dry waste, evaporator bottoms).

e. Type of container (eg, LSA, Type A, Type B, Large Quantity).

f. Solidification agent or absorbent (eg, cement, asphalt).

Rev 4 2 1/1/93

g. Any changes made during the reporting period to the PCP pursuant to the

Plant Technical Specifications.

Malor Modifications to Radioactive Solid Waste Treatment System Licensee initiated major modifications to the radioactive solid waste systems:

1. Shall be reported to the NRC pursuant to 10CFR 50.59. The discussion of each modification shall contain:

a. A summary of the evaluation that led to the determination that the modification coul4 be made in accordance with 10CFR Part 50.59.

b. *A description of the equipment, components and processes involved and the interface with other plant systems.

c. Documentation of the fact that the modification was reviewed and found acceptable by the PRC.

2. Shall become effective upon review and acceptance by the Plant Manager.

~.

I I

3 Rev 4 1/1/93

Proc No 3.07 PALISADES NUCLEAR PLANT Attachment l SAFETY REVIEW Revision 2

Item To Be Evaluated:

Tech Spec Change (RETS)

ODCM & PCP Changes Page l of l Item Identification: TS 3.24, Table 4.1.3, 4.11, 4.24, 6.8.4, 6.9.3, 6.10.2 & 6.20.,

No ODCM, PCP Rev _:___

Yes No

l. Does the item involve a change to procedures as described in the x FSAR?

List FSAR Section(s) affected and reviewed

2. Does the item involve a change to the facility as described in x the FSAB.?

List FSAB. Section(s) affected and reviewed

3. Does the item involve a test or experiment not described in the x FSAR? List Section(s) reviewed

4. Does the item require a change to the Technical Specification? x List affected and reviewed section(s) TS 3.24, Table 4.1.3.

4.11, 4.24, 6.8.4, 6.9.3, 6.10.2, and 6.20 If any Safety Review question listed above is answered Yes, perform a written Safety Evaluation according to Section 5.3.

If all Safety Review questions listed above are answered No, a written Safety Evaluation is not required. However, this Attachment shall accompany other documentation for the item being evaluated in order to provide documentation that a Safety Evaluation was not required.

ad0586-0006b-93-l54

Proc No 3.07 PALISADES NUCLEAR Pt.ANT Attachment 2 NRC NOTIFICATION DETERMINATIOH Revision 2 Page l of l Item To Be Evaluated: Item Identification: TS 3.24, Table 4.1.3, Tech Spec Change (RETS) 4.11, 4.24, 6.8.4, 6,9,3, 6,10.2 & 6.20 ODCM & PCP Changes No opcM & Pep Rev -

SECTIOll I Yes No

l. Will the probability of an accident previously evaluated in the x FSAR be increased?

2. Will the consequences of an accident previously evaluated in the x FSAR be increased?

3. Will the probability of malfunctions of equipment important to x safety be increased?

4. Will the consequences of a malfunction o~ equipment important to x safety be increased?

5. Will the possibility of an accident of a different type than any x previously evaluated in the FSAB. be created?

6. Will the possibility of a malfunction of a different type than x any previously evaluated in the FSAll be created?

7. Will the margin of safety as defined in the basis for any x Technical Specification be reduced?

If any of the above questions are answered Yes, an unreviewed safety question is involved. A written Safety Analysis shall be prepared and the item shall not be implemented without prior NRC concurrence.

If all of the above questions are answered No, a written Safety Analysis shall be prepared to provide the documented basis for concluding the proposed item does not constitute an unreviewed safety question.

SECTIOV II Yes No x

1. Should this be included in an FSAR update?

2. Is prior NB.C approval and/or an application for amendment to the x Palisades Operating License required?

SECTIOM III

,C}~-=~'~

t:::;/ pep&red By ~t ad0586-0006c-93-154

Pree ~o 3.07 PALISADES NUCLEAR. PLAHT Attachment 3 SAFETY ANALYSIS Revision 2 Page l of 2 Item to be Evaluated: Item Identification: TS 3.24, Table 4.1.J, Tech Spec Change (RETS) 4.11, 4.24, 6.8.4, 6.9.3, 6,10,2 & 6,20, ODCM & PCP Changes No ODCM & PCP Rev -

DESCKIPTIOB or ITEM Page Proposed changes to Palisades Technical S12ecifications to relocate radiological effluent procedural requirements to the Offsite Dose Calculation Manual (ODCM) or Process Control Program (PCP) 12er NRC Generic Letter 89-01.

JUSTIFICATIOM NRC Generic Letter 89-01 provides for retention of the 12rogrammatic controls for Radiological Effluent Technical Specifications (RETS) in the Administrative Control Section of the Technical seecif ications and the relocation of procedural details of RETS to the ODCM or to the PCP. Minor changes consistent with those described in the Generic Letter are also included in the proposed changes in the TS, ODCM, and PCP. Procedural requirements related to gaseous and liquid effluents, total dose 2 environmental monitoring program, and associated reeorting reguirements were relocated to the ODCM. Procedural requirements related to solid radwaste were relocated' to the PCP. Programmatic controls.revised and retained in the TS include requirements for establishment, i!Elementation 1 maintenance and changes to the ODCM and PCP as well as r~cJrd retention and reEorting requirements.

I ad0586-0006d-93-l54 SA0689-0146-NL04

Page 2 of 2

Two changes outside the scope of the present TS are also requested.

proposed' change is the 60-day reporting requirement for the semiannual The first effluent release report to 90-days. A contractor laboratory presently does not have adequate time to obtain samples and calculate the release quantities of Sr-89 and Sr-90 during the 60-day reporting period*. The change to 90-days will allow adequate time to include the results in the report and achieves the purpose of the report to provide complete effluent releases.

The second change would modify the requirement, relocated to the administra-tively controlled ODCM & PCP, to report major modifications of the radioactive waste treatment systems in a*special report to the NRC. The proposed change will require modifications be reported in the annual report pursuant to 10CFR50.59. Such a change is consistent with the present Big Rock Point Technical Specifications where it was argued that the special report requirement is not required by 10CFR50.36a or 10CFRS0.59*.

Since the changes are administrative in nature which do not lessen the radiological effluent monitoring program at Palisades, and only minor changes being made to the reporting requirements, the proposed changes to the Technical Specifications, ODCM, and PCP described above do not affect the probability or consequences of an accident or malfunction of equipment impor-tant to safety. There is also no possibility of an accident or malfunction of a different type dlan previously evaluated in the FSAR having been created due to these administrative changes. Finally, there is no affect on the Margin of Safety as defined in the basis for any Technical. Specifications due to these administrative program changes to the radiological effluent monitoring program.

SA0689-0146-Ni.04

Relocated Technical Specifications Introduction The NRG, through 10CFR SO. 36a, requires implementation of Technical Specifications on effluents from nuclear power plants. NRG Generic Letter 89-01, dated January 31, 1989, allowed the relocation of the existing procedural requirements from the Technical Specifications (implemented in Amendment 8S, November 9, 1984). The relocated procedural requirements pertaining to solid radwaste follow below. Programmatic controls are retained in the Administrative Controls section of the Technical Specifications to satisfy the regulatory requirements of 10CFR SO. 36a. The Technical Specifications programmatic controls include requirements for the establishment, implementation, maintenance and changes to the Process Control Program (PCP), as well as record retention and reporting requirements.

Definitions The Technical Specification's definition of the PCP is:

The Process Control Program (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes bas_ed on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure*

compliance with 10CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

Solidification shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).

Requirements The solid radwaste system shall be used in accordance with the PCP to process wet radioactive wastes to meet shipping and burial ground requirements.

Action With the provisions of the PCP not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site.

Surveillance Requirements The Process Control Program shall be used to verify the solidification of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (eg, filter sludges, spent resins, evaporator bottoms and boric acid solutions).

1 1/1/93

a. If any test specimen fails to verify solidification, the solidification of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative solidification parameters can be determined in accordance with the Process Control Program and a subsequent test verifies solidification. Solidification of the batch may then be resumed using the alternative solidification parameters determined by the Process Control Program.

b. If the initial test specimen from a batch of waste fails to verify solidification, the Process Control Program shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate solidification. The Process Control Program shall be modified as required, as provided in the Technical Specifications, 6.19, to assure solidification of subsequent batches of waste.

BASES Solid Radioactive Waste The Process Control Program implements the requirements of 10CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10CFR 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.

Reporting Requirements The Radiological Effluent Release Report, pursuant to the Plant Technical Specifications, shall include the following information for each class of solid waste (as defined by 10CFR Part 61) shipped offsite during the report period.

(Additional details of the report are contained in the Offsite Dose Calculation Manual).

a. Container burial volume.

b. Total curie quantity (specify whether determined by measurement or estimate).

c. Principal radionuclides (specify whether determined by measurement or estimate) ..

d. Source of waste and processing employed (eg, dewatered spent resin, compacted dry waste, evaporator bottoms).

e. Type of container (eg, LSA, Type A, Type B, Large Quantity).

f. Solidification agent or absorbent (eg, cement, asphalt).

2 1/1/93

g. Any changes made during the reporting period to the PCP pursuant to the Plant Technical Specifications.

Ma1or Modifications to Radioactive Solid Waste Treatment System Licensee initiated major modifications to the radioactive solid waste systems:

1. Shall be reported to the NRG pursuant to 10CFR. 50.59. The discussion of each modification shall contain:

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

b. A description of the equipment, components and processes involved and the. interface with other plant systems.

c. Documentation of the fact that the modification was reviewed and found acceptable by the PRC.

2. Shall become effective upon review and acceptance by the Plant Manager.

3 1/1/93

PALISAPES NUCLEAR Pl.Afil: *. Pree No 3.07 SAfEn REVIEW AtUlcbment 1

Revision o; Page l of 1 PS&L Log No 9)-(oyc(

No OIXJIY] Rev 0 Title afFstTE l?<<tf' SE Rev es o

1. Does the item involve a change to procedures as described in the i;*

FSAR? i FSAR Se~eions. affected ~~,1/,~~;,.;..;.;;....~~~~~~~~~~~~-'-~ ~t FSAR Sections reviewed \/"

2. Does the item involve a change to l:he facility as described in the FSAR?

FSAR Sections affected )!',_....- -

FSAR Sections reviewed

'f:

3. !>oes the item involve a test or experiment not described in the FSAR? <

Al~

FSAR Sections affected FSAR Sections reviewed

4. Does the item involve a change to the Technical Specification?

TS Sections affected O/XAZ &~;, A TS Sections reviewed Justify No Answers below if logic is not ~bvious:

f.*

/)dJul ,,~

'~ . ""~'~*..)

If any Safety Review question listed above is answered "YES",

Evaluation according to Section 5.3.

If all Safety Review questions listed above are answered NO, written USQ Evaluation is not required. However, this Attachment shall accompany other review materials fo the item to document that a Safety Evaluation was not required .

Q~r~/ 0-~"-c;3 Reviewed By Date

r'i*IL * .:ir1uc..:i 11u1...1...:./"\f\ ,- ._,.,,.,

SAFETY REVIEW Page l of 1 PS&L Log No _____9.__~----_1_._0.......;:10~----

Item Identification: No ;_-1A Title oPfi/T£ Pt:'$~

.. SE REV

/1.IHJ.-.Jtt.IJJ::.{;(.Q.~ #/~ f_ 0 OC(J?,l JM.i.zv. IJ.

Describe Issue/Change: (!/..ti;( f;'e.. ' III.~. t. -

Reason for Issue/Change: e.11. ,,L £!l:l I >" I o..-f::S4;.t!/'efdt I

~ D- ///h_ ~8.. E3

1. Does the item involve a change to procedures as described in Yes No the FSAR?

FSAR Sections affected None FSAR Sections reviewed /I

,_,/

2. Does the item involve a change to the facility as described in the FSAR?

FSAR Sections affected 111,.()\L FSAR Sections reviewed 11

3. Does the item involve a test or experiment not described in the FSAR?

FSAR Sections affected ..v'.:ny..

FSAR Sections reviewed /1 v--

4. Should the Technical Specifications or any of their Bases be changed in coniunction with this item?

TS Sections af ected ..Vnc.a- _.,/

TS Sections reviewed ~

Justify No Answets below if logic is not obvious:

4-dJd ~l. ~ir-1-1~ t:~u It. +/) re... t .... * .(.l"'C <...

~-"-/A....e /, ;.,,..~f -H..oe. -4~ of 11Jiv1°c:l.J 1SPfu~

~*+- ~

I~

~i- v; lu ._j *

--..~- .

If a~ Safety Review question listed above is answered "YES", perform a written USQ valuation a=cord1n~ to Section 5.3.

If all Safety Review questions listed above are answered* NG, written USQ Evaluation is not required. Howeverh this Attachment shal: accompany other review*

materials for the item to document t at a Safety Evaluation was not required.

@~F~

~ I :l.-:J.."J..- 11 I Z-'J,:Z.-f}

L Cate . Reviewe-y-- Date

... P:::cc No l.Oi A~'t:.ichment: ;

Revision S P&:1.gB l of l

It:em Identification:

ll't<.,.(A.fJ._A,r"/IN No 1'14/Vlll<<_.

DDcrn PS&L Log No _

Rev _.:J__ Title

,/. /JJ?t;ce"S.t C.#,1"'~'-

Describe Issue/Change: ~*~~~r;,,;...~~io~~~~---~~~---~~--~-~---~~------~

_.Cf:-11:~-..-_;..../7__...5_7______

oi=Psll? Gt:J$c

/.)~L"A--. ;3a?F1 &'~vZ_ /-!-'!':?

SE Re Reason for Issue/Change:

1--------------------:~.--*-----------------~-* i:es No

1. Does the item involve a change to procedures as described in the FSAR?

FSAR Se~tions. affected FSAR Sections reviewed ./

2. Does the item involve a. change to'"the facility as described in the FSAB.7 FSAR Sections affected FSAR Sections reviewed II

3. Does 1:he item involve a test or experiment not described in the FSAR?

FSAB. Sections affected FSAR Sections reviewed II /

4. Does the item involve a change to the Technical Spsc1ficat1on?

TS Sections affected ~*tff-~.;..---------------~-~-~- /

TS Sections reviewed --:;!i;C=:iilil::.....:i>fi,:.:11111a'~*----------_,,-------

Justify No Answers below if logic is nae obvioua:

0~1#At.

Ji,Sf 6clt.:...> tcJI$ '91w"1 { 91-osr) llooll.dset> rJ.11r 11t1H1e.. c."'"-"' ttJF 3.~ I ~I( I 'f.2{ ._;_,, .udf. ~HI* t.f -! ,,18 .,,,/,.If #11,-c..,_. , 4, ~ ~ /'~~4.

f' st .- ~~ .,.,,.,,.,; ~~/.J-J- r41"'rl7 /or .9* ./~c ,.flu ~I -I~' ~/cJ.rjl, I jl:a, -~. 'llt:,, ...,._ r...(..scO. ~ ~ ~ ~o&C.4 **u7 ';- *...... /O e./!'~Si:J, 3,

~ ~ l/~fc./.tl $.,....,* ~,, .;.,( r41.,~ m.I.

If any Safety Review question listed above is answered *YES", perform a written use Evaluation according to Section 5.3.

If all. Safecy Review questions listed above are answered NO, written USQ Evaluat: *.,

is not required. However, this At:t:achment shall accompany other review materials the item t:a document: that a Safety Evaluation wu nae required. 1

PALISADES NUCLEAR PLANT Pree No 3 .(

SAFETY ANALYSIS Attachment Revision 6 Pa~e 1 of : '

Item Identification: No opqri Rev __...7_

DBSCllIPi101 or I;EJI Page _ __

JUSTilIWIQR

~@, .J.e ~Y /o u=µ:p ~ , A s=,~

ft,4 ;#.- ka pu.11 S11J,,,,tf;/ L,,?..-/<, 11)

Proc ~o 3.

PALISADES NUCLEAR PLANT Attachment SAFETY REVIEW Revision :

Page 1 of Item To Be Evaluated: Item Identification: TS 3.24, Table 4.1.3, Tech Spec Change (RETS) 4.11, 4.24, 6.8.4, 6.9.3, 6.10.2 & 6.20.,

ODCM & PCP Changes No ODCM~ PCP Rev -

Yes No

1. Does the item involve a change to procedures as described in the x FSAB.?

List FSAB. Section(s) affected and reviewed

2. Does the item involve a change to the facility as described in x the FSAB.?

List FSAB. Section(s) affected and reviewed

3. Does the item involve a test or experiment. not described in the x FSAB.? List Section(s) reviewed

4. Does the item require a change to the Technical Specification? x List affected and reviewed section(s) TS 3.24~ Ta~l~ 4 1 1 1 3 1 4.11, 4.24z 6.8.4 2 6.2.3 2 6.10.2~ and 6.20*

If any Safety Revi*v question listed above is answered 'ies, perform a written Safety Evaluation accordin1 to Section 5.J.

If all Safety Review questions listed above are answered No, a written Safety Evaluation is not required. However, this Attachment shall accompany other documentation for the item being evaluated in order to provide documentation that a Safety Evaluation was not*required.

~-L-LJN./P.-~~I tJj V!t'/ J/JtU t/;Jfr I I!

/,,.,;r P:jpared By Date' 'taviewed By Date I* ./

!?roe No 3.

PALISADES NUCLEAR PLANT Attachment NRC NOTIFICATION DETERMINATION Revision 2 Page l of Item To Be Evaluated: Item Identification: TS 3,24, Table 4.l.3, Tech Spec Change (RETS) 4.11, 4.24, 6.8.4, 6.9.3, 6,10.2 & 6.20 ODCM & PCP Changes No opcM & Pl"'P Rev ----

SECTIOH I Yes No

l. Will the probability of an accident previously evaluated in the x FSAR be increased?

2. Will the consequences of an accident previously evaluated in the x FSAR be increased?

3. Will the probability of malfunctions of equipment important to x safety be increased?

4. Will the consequences of a malfunction o~ equipment important to x safety be increased?

5. Will the possibility of an accident of a different type than any x previously evaluated in the FSAB. be created?

6. Will the possibility of a malfunction of a different type *than x any previously evaluated in the FSAB. be created?

7. Will the margin of safety as defined in the basis for any x Technical Specification be reduced?

If any of the above questions are answered Yes, an unreviewed safety question is involved. A Wl:'itten Safety Analysis shall be prepared and the item shall not be implemented without prior NRC concurrence.

If all of the above questions are answered No, a written Safety Analysis shall be prepared to provide the documented basis for concluding the proposed item does not constitute an unreviewed safety question.

SECTIOll II Yes No x

1. Should this be included in an FSAR update?

2. Is prior NB.C approval and/or an application for amendment to the x Palisades Operating License required?

SECTIOV III

!?roe ~o 3. 07 PALISADES NUCLEAll PLANT Attachment 3 SAFETY ANALYSIS Revision 2 Page-l of 2 Item to be !valuated: Item Identification: TS 3.24, Table 4.1."3, Tech Spec Change (RETS) 4.11, 4.24, 6.8.4, 6.9.3, 6.10,2 & 6,20, ODCM & PCP Changes No ODCM & PCP Rev _ _

DESCKIPTIOB or ITEM Page -----

Proposed changes to Palisades Technical Specifications to relocate radiological effluent procedural requirements to the Off site Dose Calculation Manual (ODCM) or Process Control Program (PCP) per NRC Generic Letter 89-01.

JUSTIFICATIOll NRC Generic Letter 89-01 provides for retention of the programmatic controls for Radiological Effluent Technical Specifications (RETS) in the Administrative Control Section of the Technical Specifications and the relocation of procedural details of RETS to the ODCM or to the PCP. Minor changes consistent with those described in the Generic Letter are also included in the proposed changes in the TS, ODCM, and PCP. Procedural requirements related to gaseous and liquid effluents, total dose, environmental monitoring program, and associated reporting reguirements were relocated to the ODCM. Procedural requirements related to solid radwaste were relocatff: to the PCP. Programmatic controls revised and retained in the TS include requirements for establishment, implementation, maintenance and changes to the ODCM and PCP as well as r~clrd retention and reporting requirements.

ad0586-0006d-93-l54 SA0689-0146-NL04

Page 2 of 2

Two changes outside the scope of the present TS are also requested.

proposed change is the 60-day reporting requirement for the semiannual The first effluent release report to 90-days. A contractor laboratory presently does not have adequate time to obtain samples and calculate the release quantities of Sr-89 and Sr-90 during the 60-day reporting period*. The change to 90-days will allow adequate time to include the results in the report and achieves the purpose of the report to provide complete effluent. releases.

The second change would modify the requirement, relocated to the administra-tively controlled ODCM & PCP, to report major modifications of the radioactive waste treatment systems in a*special report to the NRC. -The proposed change will require modifications be reported in the annual report pursuant to 10CFR50.59. Such a change is consistent with the present Big Rock Point Technical Specifications where it was argued that the special report requirement is not required by 10CFR50.36a or 10CFRS0.59.

Since the changes are administrative in nature which do not lessen the radiological effluent monitoring program at Palisades, and only minor changes being made to *the reporting requirements, the proposed changes to the Technical Specifications, ODCM, and PCP described above do not affect the probability or consequences of an accident or malfunction of equipment impor-tant to safety. There is also no possibility of an accident or malfunction of a different type ehan previously evaluated in the FSAR having been created due to these administrative changes. Finally, there is no affect on the Margin of Safety as defined in the basis for any Technical Specifications due to these administrative program changes to the radiological effluent monitoring program.

SA0689-0146-NL04

Relocated Technical Specifications Introduction The NRG, through 10CFR SO. 36a, requires implementation of Technical Specifications on effluents from nuclear power plants. NRG Generic Letter 89-01, dated January 31, 1989, allowed the relocation of the existing procedural requirements from the Technical Specifications (implemented in Amendment 8S, November 9, 1984). The relocated procedural requirements pertaining to solid radwaste follow below. Programmatic controls are retained in the Administrative Controls section of the Technical Specifications to satisfy the regulatory requirements of 10CFR SO. 36a. The Technical Specifications programmatic controls include requirements for the estab.lishment, implementation, maintenance and changes to the Process Control Program (PCP), as well as record retention and reporting requirements.

Definitions The Technical Specification's *definition of the PCP is:

The Process Control Program (PCP) shall contain the. current formulas, sampling, analyses, *test, and determinations to be .made to ensure that processing and packaging of solid radioactive wastes bas_ed on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Parts 20, 61, and 71, State regula'tions, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

Solidification shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface. of distinct outline on all sides (free-standing).

Requirements The solid radwaste system shall be used in accordance with the PCP to process wet radioactive wastes to meet.shipping and burial ground requirements.

Action With the provisions of the PCP not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site.

Surveillance Requirements The Process Control Program shall be used to verify the solidification of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (eg, filter sludges, spent resins, evaporator bottoms and boric acid solutions).

1 1/1/93

a. If any test specimen fails to verify solidification, the solidification of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative solidification parameters can be determined in accordance with the Process Control Program and a subsequent test verifies solidification. Solidification of the batch may then be resumed using the alternative solidification parameters determined by the Process Control Program.

b. If the initial test specimen from a batch of waste fails to verify solidification, the Process Control Program shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate solidification. The Process Control Program shall be modified as required, as provided in the Technical Specifications, 6.19, to assure solidification of subsequent batches of waste.

BASES Solid Radioactive Waste The Process Control Program implements the requirements of 10CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10CFR Part 50. The process parameters included in establishing the Process Control Pro.gram 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.

Reporting Requirements The Radiological Effluent Release Report, pursuant to the Plant Technical Specifications, shall include the following information for each class of solid

'waste (as defined by 10CFR Part 61) shipped offsite during the report period.

(Additional details of the report are contained in the Offsite Dose Calculation Manual).

a. Container burial volume.

b. Total curie quantity (specify whether determined by measurement or estimate)*.

c. Principal radionuclides (specify whether determined by measurement or estimate).

d. Source of waste and processing employed (eg, dewatered spent resin, compacted dry waste, evaporator bottoms).

e. Type of container (eg, LSA, Type A, Type B, Large Quantity).

f. Solidification agent. or absorbent (eg, cement, asphalt).

2 1/1/93

g. Any changes made during the reporting period to the PCP pursuant to the Plant Technical Specifications.*

Ma1or Modifications to Radioactive Solid Waste Treatment System Licensee initiated major modifications to the radioactive solid waste systems:

1. Shall be reported to the NRG pursuant to 10CFR 50.59. The discussion of each modification shall contain:

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

b. A description of the equipment, components and processes involved and the interface with other plant systems.

c. Documentation of the fact that .the modification was reviewed and found acceptable by the PRC ..

2. Shall become effective upon review and acceptance by the Plant Manager.

3 1/1/93

"'I PAt.i~AQ&:~ tm:CLEAR fUNI ... Pree No :l.07

~AF£!Y REV'l'1i

Attachment:

l Revision 5 Page l of l PS&L Log No '1~- / 7 57 Item Identification: No ODCIY\ Rev 7 Title ot=Ps117!' Ek'se SE Re*.

lA-<...U<.1 *T?'N M4ttilllk- ./. /}J't;c~<:. er,,.~'- /)14J,,.. d.A-wJ ,"3o7JI Filion~- 1-1 *n Describe Issue/Change: .<n J.,,.~

Reason for Issue/Change: LP eFfl.ZIJ k!&tSI~ ~ l!aocAll,.o.J Yes No

1. Does the item involve a change to procedures as described in the FSAR?

FSAR Sections. affected ~ ./

FSAR Sections reviewed /I +n,..~

2. Does the item involve a change to ""the facility as described in the FSAR? -

FSAR Sections affected Al~

FSAR Sections reviewed II /

3. Does the item involve a test or eXiJeriment not described in the FSAR?

FSAR Sections affected !£.M-1 /

FSAR Sections reviewed II I

4. Does the item involve a change to the Technical Specification?

TS Sections affected J!t?u- /

TS Sections reviewed ~ £t1.ad1 Justify No AnsWers below if logic is not obvious: l!)F rfl~ ~IC- t..11~'

Ofll61/I~ . £;,Sf 61A~ ,(,cJf .s '1/w~ ( 8'1-~s-S") /!I DD14f!;tt'I>

3.v/ I 4(,1/, J/,2-'{ t!if,,,, wdtt fl>lfl* t.f ~ ,,18 ~ '* ..4~r;-- . L ~ ~ 1'1"4.<f~

/

- ,,.~ """"~ e,.~/.J...f r~'*" /or 'i~ .1.,,, ~!Iv JWt -/~I :...;:;~,I 7

I 81 j1~*~. Tl,~

....,.. ,..~eJ2. a,J_ ....,.. ~ ~ .4-'

/0 4!'£. ~. 3i.

~ ~ t~fc/.tl 5.,,,..,.,* ~,, .Joef r41,,~ m..J.

If any Safety Review question listed above is answered MYES", perform a written use Evaluation according to Sect:ion 5 .* 3.

I If all Safety Review questions list:ed above are answered NO, written USQ Eval~C *.c is not required. However, this Attachment shall accompany other review m.acerials the item to document that a. Safety Evaluation was not required.

1f1Lud l oj_vt/tu GaidF~ /;J- 8CJ-Cj1, Dace Prepared By Date Reviewed By

PALISADES NUCLEAR PLANT Pree No 3.07 SAFETY ANALYSIS Attachment 3 Revision 6 Page 1 of l Item Identification: No ~ Rev ~ Title DESCRIPTION or ITEM Page----

JUSTIPic:ATIQB C~U f* ~ "-n... .......Je, k f'4/q /o U:ft.Zi> ~ t ,4 5 =f~

AIM ~ ..4 .y:/4~ ft,& ,f~ 441 pa11 s"J,,,dl:J l ~z-1~ 11)

....-.--- .. r

11w I l4'°D 4tr14.;,;:_./ ,:/e-s "'1!@-- 44/e.4 .j OfXl!1

1-111 4 .4 4:,./1!., .j IAJ'LJ Jj,,d_ le tie. ~ tx:.fr1 / /)ppe.J~ I! I -f:L/, k_ A--/ C!:ff11;h~ di!- C~ ~p;rj;c-rndJl/Jt.;,. ~ J, vl.~ed ; £ f6~ 4/lf- v~~~.J -4,-(s ~w or '-!. 1.:.oe_~le. , (/,;~ ~:!;,~f~ w?-1( r/<.c. ~{-",:..,, ~

of ~~ ~'11).. &,....~ . fe-u..d,,- ~ n~ se.~f~ ~~ -tdLe-L

!_) fJpuYI ,. llp,prewhlo IJ ze.c-/i.,,v I rrr OK. 0 fltj 11nril~1 ~

'1<<;~ &I +'.~ uw~l..4. +,,;.,. ~f. aJ,.~f,,;., ~,:J tnk:.J n: t4 $/IJ.d fA<<..i, '(" A--7 w.tf?,,/-~..J_ od-s~J. 1-e.nc.eHWI'/

/+.vf._, j 6...,1( 6t: J,;,;fe../ j-.h ~ & mi;.!~ '1~cfr~e..s tk ~f ~ /Opo /,,,,~ fl~ ef.f/p,,.f ,,.,,,cyJ-v-J-,, (£c.)

~ /,~1eJ ,.. 1~c~~ ZO ~ Jl 1 f',Jfe 2/ l,~2.. 1J,e I'~~~,

7 J-~ -,, ~ bue~ 'ue* /;.""" 1:/11/le-~ 4 J ~ fso,

~

$vtVt-e/f..__.- Olf1Z 1l ji*r :/fe!?e. i/gns tan Ot; ~vd J;.,wt ~~ orr/eyS-t/

UIJrm f!>Jrl~v- * . -rf?t-rt.. t.5 n~ ~,.,_//,d-/- "' ;~ AM .fro,.. -If,,~ ODctn .

ATTACHMENT 7 Consumers Power Company Palisades Plant PROCESS CONTROL PROGRAM March 31, 1994

NOTE:

I~ "Appendix C" of the Process Control Program is a new appendix.

Therefore no specfic lines at the right/left margin are shown .

Rev. 4 Consumers Power Company Palisades Nuclear Plant

PROC~SS CONTROL PROGRAM (PCP)

Approved I~

Radiological Services Mgr,.

/.l-3'-9:2.-

Technical Review Date G~ fi ~ 1~-30 -z'Z._

Plant Review Committee9J-/l57 Date 7~~

J:). - 3o- 9..:>-

Date

- - 11/.10/~

Plant General Manager Date

Table of Contents 1.0 Asphalt Volume Reduction System . . . . . . 1 1.1 Variables Influencing Solidification 1 1.2 Asphalt Type . . . . 2 1.3 Waste Chemical Species 2 1.4 Waste-to-Asphalt Ratio 3 1.5 Process Temperatures 3 2.0 Dewatering Solids in High Integrity Containers (HIC) 5 3.0 Delaware Custom Materiel (DCM) - Silicate Cement 5 3.1 Testing . 6 3.2 Solidification and Free Water Determination 6 4.0 10 CFR 61 Requirements 7 5.0 Radwaste System q 6.0 Technical Specification Requirements 7 Appendix A - Asphalt Technical Data Summary

Appendix B - System Diagrams Appendix C - Relocated Technical Specifications

i Rev. 4

PALISADES PROCESS CONTROL PROGRAM (PCP) 1.0 ASPHALT VOLUME REDUCTION SYSTEM The Palisades Plant utilizes a Waste Chem volume reduction and solidification system (VRS) to process various radioactive liquid waste*

streams.

The process utilizes thermal energy (heat) to evaporate water from the radioactive waste, thus reducing waste volume to anhydrous waste residue, The end product is a monolithic, freestanding solid with no free liquid.

Fifty-five gallon drums are used to contain the encapsulated waste for temporary storage, transport and burial.

The asphalt volume reduction system is detailed in Appendix B. B-1 shows inplace shielding and equipment locations, anc;l B-2 is a flow system diagram for resins and concentrates.

To maintain operator exposure AI.ARA the entire processing area is enclosed within 1-2 foot thick concrete walls with access through lead doors. The system process is directed from a remote control room equipped with TV cameras, radiation level readouts and drum level indicators. Each drum is filled, indexed and capped remotely. Drums are removed by use of a shielded forktruck and are stored in a shielded area of the East Radwaste Building until shipped offsite: After each tank is processed the system is flushed with asphalt to reduce buildup and allow preventive maintenance or system repair with minimum exposure.

1.1 VARIABLES INFLUENCING SOLIDIFICATION The purpose of this section is to identify and define those process variables which have a direct effect on the ability of the final product to form a freestanding monolith with no free liquid.

The following variables influence the properties and consistency of the final product:

a. Asphalt type

b. Waste chemical species used as feed

c. Ratio of waste-to-asphalt

d. Process temperature

e. pH

1 Rev 4 1/1/93

1. 2 ASPHALT TYPE Asphalt utilized in the system shall conform to ASTM-D-312-71, Type III.

This is an oxidized petroleum-based asphalt, such as Witco Chemical Company's Pioneer 221. The specifications for this asphalt are provided in Appendix A.

This grade of asphalt .has a low residual volatile content and a high molecular weight. At room temperature, and at all normal ambient temperature conditions, this material is a freestanding, monolithic, solid.

Utilization of an asphalt complying with ASTM-D-312- 71, Type III, is the means by which process control of this variable is achieved.

1.3 WASTE CHEMICAL SPECIES The type and relative quantity (waste-to-asphalt ratio) of waste chemicals being incorporated into the asphalt matrix *has a direct influence on the properties of the final product. Encapsulation of inorganic salts and solids typically "stiffen" and harden the end product, whereas organic liquids have the opposite tendency. When *the specified ratio of waste-to-asphalt is maintained, final product properties for typical power plant wastes are independent of the waste type.

However, *certain chemical specifications are required as an outer bounds to limit end product tendencies to soften at lower temperatures.

A maximtim limit of 1% oil by weight will be applied to the waste feed streams. Most oils found in power plants are low viscosity fluids, which are liquid at room temperature. Based on* calculations for a typical waste stream with 20% solids by weight and 1% oil by weight, Waste Chem has found t.he total concentration of oil in the end product would be approximately 2.5%. This would then lower the end product softening point by approximately 5°F lower per percent of oil. This is within an acceptable range and, therefore, is the basis for the limit of 1% oil in the feed stream. pH should be in the range of 7.5 to 8.5 for the 'best product.

Other chemical specifications on feed streams are specified below. These are required primarily for calculating waste-to-asphalt ratio which is important to end product, and equipment protection (which will have no discernable effect on the end product).

Rev4

2 1/1/93

REQUIRED ANALYSIS Concentrates Resin/Powdex pH (equip limit) pH (equip limit)

X solids X slurry Sp Gravity Oil X 1.4 WASTE-TO-ASPHALT RATIO The ratio of waste-to-asphalt contained in the end product has the most significant effect on the viscosity and physical consistency of the product. Process control is achieved by placing limitations on the range of waste-to-asphalt ratios allowable for each waste type.

Waste-to-asphalt ratios (mass) and evaporative rates should not exceed the verification test values specified for the waste feeds as follows:

Ratio, of ..

Waste to Asphalt In the End Product **J:

1. Boric Acid Concentrates at 120 L/hr Evaporative Rate s 1.0/1.0

2.

3.

Spent Resins at 80 L/hr Evaporative Rate Powdex at 80 L/hr Evaporative Rate s . 67/1.0 s .67/1.0 Should the ratio of waste-to-asphalt be increased above the range Specified in the foregoing table I the end product viscosity Will increase and may exhibit a grainy texture. This could lead to "pyramiding" in the

steam domes. In all cases, the produc.t will cool to form a freestanding monolith. If lower than specified waste loadings are realized, the end product properties will approach that of pure asphalt. Again, solidification is assured, however, toward this end of the spectrum, economical volume redu~tion may not be realized.

Maximum concentrate feed rate can be determin,ed by the following formula:

Cone Feed Rate - 0.528 GPM (1.0 - Solids Fraction)(Sp Gravity)

NOTE"~* 0.528 gpa - 120 L/hr evaporative rate.

The corresponding asphalt feed is calculated by:

Asphalt Fe~d (GPM) - (Cone Feed Rate GPM)(Solids Fraction)(Sp Gravity)

(Waste-to-Asphalt Ratio) where the recommended waste-to-asphalt ratio is 1.0 .

3 Rev 4 1/1/93

NOTE 1: The density of Type III asphalt is 1.0 so a density correction~

is not needed. -

NOTE 2: The minimum asphalt flow is 0.065 gpm because of lubrication requirements of the twin screws.

NOTE 3: If either the concentrate or asphalt flows cannot be met, the calculated flows can be ratioed to new values to maintain the 1.0/l.O waste-to-asphalt ratio as long as the maximum concentrate flow or the minimum asphalt flows are not exceeded.

Maximum bead resin or Powdex can be determined by the following formula:

Resin Feed = 0.35 GPM (1.0 - Solid Fraction) - -I NOTE 1: Solid fraction= slurry fraction 2. Example is a 50%

slurry= 25 weight %.

NOTE 2: 0.35 gpm = 80 L/hr evaporative rate.

The corresponding asphalt feed is calculated by:

Asphalt Feed (GPM) = (Resin Feed) (Solid Fraction)

(Waste-to-Asphalt Ratio)

Where the recommended waste-to-asphalt ratio is 0.67, the notes on the proceeding asphalt calculation apply.

The operator can also visually confirm that the quality of the end product is approximately being maintained. A CCTV camera "views" the discharge from the extruder-evaporator, and a TC monitor located in the Solid Radwaste Building Control Room allows the operator t_o observe the physical consistency of the product as it is discharged into the container. At evaporative rates higher than specified, there will be excessive steaming at discharge nozzle. At higher waste-to-asphalt loading the discharge will appear grainy and stringy.

1.5 PROCESS TEMPERATURES A proper temperature profile along the length of the extruder-evaporator is required to provide adequate evaporative (process) capacity, and to assure that free water is not discharged from the machine.*

Process temper_ature profiles for waste feeds should be maintained as recommended below:

Rev4

4 1/1/93

Waste Type Process Temperature (°F)

Zones: :_i_ _2_ _ 3_ _4_ _7_

Boric Acid Concentrates WS Concentrates 380° 280° 280° 300° 300° Chemical/Laundry Waste

Spent Resins/Powdex 300° ** ** ** **

NOTE: No zone shall be maintained below 240°

Cooling Zone - no specified temperature

- Steam supply control valves are fully open Low temperature alarms are provided to alert the operator to a low temp*erature out-of-specification condition which could potentially lead to the discharge of free water. If the out-of-specification conditions persist for two (2) minutes, the extruder-evaporator is automatically tripped to prevent free water from being discharged into the container.

Free water cannot be discharged in the interim, since the residual heat of the extruder-evaporator itself is sufficient to effect evaporation .

Verification of the absence of free water and product solidification will be made on every drum produced. Container shall be examined through a removable lid bung or equivalent means for solidification by checking penetration with a solid tool and inverted for a minimum of eight hours to check for free water. Evidence of free water other than a few drops of condensation shall be cause for rejection and evaluation system product.

2.0 DEYATER,ING SOLIDS IN HIGH INTEGIITI CONTAINERS CHIC>

2.1 Solids such as bead* resin, filter cartridges and powdered resin (Powdex) may be dewatered and shipped in H!Cs per approved vendor procedures and the HIC certificate of compliance.

2.2 High integrity containers are *approved by the individual burial ground agreemant states as meeting 10CFR.61 waste form stability requirements.

2.3 Free water determination shall be verified by the successful completion and documentation of the vendor's approved dewatering procedure.

3.0 DELAWARE CUSTOM KATDIEL CDGH> - SILICATE CIMERT Liquid wastes can be solidified by the DCM method. The silicate solidifies and the cement gives structural strength .

5 Rev 4 1/1/93

3.1 For solidification, acquire a representative sample of waste. Befo~.

following the guidelines outlined below, determine the type of waste to be solidified, ie, lab waste, laundry waste, decon solutions, boric acid, oil, 'etc. Sample for R!:L boric acid, visible organics and radioactivity.

Use analysis to determine the proper laboratory procedure to test.

All batches shall be lab tested prior to solidification in a larger container unless sample analysis (pH+/- 0.2 and Boron+/- 20%) matches the analysis of a waste type which has previously passed lab test criteria.

For all oil waste, do not exceed 50% by volume. Oil must be emulsified

. to less than 50% by volume with a detergent or boric acid in some' type of neutral aqueous waste or tap water.

NOTE: Oil cannot be shipped to Barnwell, South Carolina*.

For spent resins, liquid absorbent, or other earthen-like material, dilute with an equal volume of concentrate or tap water to solidify.

All results must be recorded initially, at approximately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and approximately 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after testing. Grade observations to eva~uate sample mixes. The 48-hour test can be omitted if the 24-hour test is good.

3.2 SOLIDIFICATION AND FREE WATER DETERMINATION Solidification shall be considered successful if, 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after completion of solidification, there is not standing water on the waste surface and the surface is not penetrated more than 2" with a l" diameter rod. If deeper penetration is possible, then the drum can still be considered solid if the penetration hole remains open after the rod is withdrawn.

Silicate cement shall cure for a minimum of 28 days prior to shipment for disposal. For silicate cement drums, the following shall be done:

With the drum lid installed, *invert each drum for presence of liquid.

Drums which failed the 48-hour solidification evaluation should be capable of passing at this point. If no detectable freestanding liquid is present, the drum can be prepared for shipment. RMC Supervisor and QC Inspector shall document when no detectable freestanding liquid is present.

6 Rev 4 1/1/93

In the event liquid is observed, those drums with liquid shall be drained of all liquid. When no further liquid can be drained from the drum in a 24-hour period, the drurii shall be core-bored or overpacked with two bags of approved absorbent and inspected by QC and RMC to verify that the drum is dry. After this verification (and documentation) the drum may be prepared for shipment.

Inspect the drum lid and gasket for defects prior to lid installation.

Install lid. Use a different lid if defects are found which preven~ a tight seal between drum and lid.

4.0 10 CFR 61 REQUIREMENTS

4. l 10 CFR 61. classification requirements will be met using Wastetrak computer software program using the scaling factor methodology of AIF /NESP-027, "Methodologies for Classification of Low-Level Radioactive Waste From Nuclear Power.Plants", 1983.

The scaling factors will be updated by an ongoing analysis program of actual waste streams. The program will initiate with semi-annual. samples of available waste streams and may be modified to longer intervals if the data base warrants. Waste streams should include, if available; bead resin, concentrates, reactor coolant, clean waste, filter crud and compacted trash .

4.2 4*. 3 10 CFR 61 waste form stability requirements will be met by generic testing of the asphalt/waste stream product. The generic waste streams will be*boric acid, bead resin and chemical regenerative wastes.

Documentation of the waste stream analysis, waste form stability and computer software scaling factor security *shall be maintained by the Radiological Services Department.

5.0 RADWASTE SYSTEM 5.1 A radwaste system flow diagram is included in Ap.pendix B, B-3.

6.0 TECHNICAL SPECIFICATION RIOUIR.EMENTS The PCP is implemented* per the requirements of the Administrative Controls section of the Plant Technical Specifications, 6 .19. Procedural requirements included in Appendix C have been relocated from the Technic;al Specifications in accordance with NRC Generic Letter 89-01, dated January 31, 1989 .

7 Rev 4 1/1/93

Rev. 4 APPENDIX A Consumers Power Company Palisades Nuclear Plant

PROCESS CONTROL PROGRAM (PCP)

Asphalt Technical Data Summary

ASPHALT TECHNICAL DATA

SUMMARY

WITCO CHEMICAL - PIONEER 221

1. Basic Constituent Pioneer 221 is an oxidized petroleum base asphalt. Oxidation is accomplished by air blowing at temperatures ranging from 200°C (392°F) to 300°C (572°F). Air blowing results in a product with minimum volatile content (0.1%), greater inertness and higher molecular weight.

2. Flash Point The Flash Point of Pioneer 221 is in excess of 288°C (549°F). The Flash Point is determined by the Cleveland Open Cup (ASTM 092-71) method. It is the lowest temperature at which surface vapors will momentarily ignite when a test flame is passed over the surface.

3. Fire Point The Fire Point of Pioneer 221 is in excess of 300°C (572°F). The Fir.e Point, like the Flash Point, is determined by the Cleveland Open Cup (ASTI:l 092-72) method. It is the lowest temperature at which the surface vapors will burn for at least 5 seconds before going out, the vapors being ignited as in the test for Flash Point .

4. Ignition Point The Ignition Point of Pioneer 221 is approximately 400°C (752°F).

The Ignition Point is the lowest temperature at which the heat loss from the combustible mixture is exceeded by the heat produced in the chemical reaction. It is thus the lowest temperature at which combustion begins and continues in an air environment.

5. Softening Poin~

The Softening Point of Pioneer 221 is in the temperature range of 88-94°C (190-201°F).

The Softening Point is determined by the Ring and Ball method (ASTM D 70).

6. Viscosity The Viscosity of Pioneer 221 in the temperature range from 250°F to 400°F is presented in attached graph .

A-1 Rev 4 1/1/93

'.}.

The graph is based on the following data from Witco Chemical:

Saybolt Furol Viscosity at 205"C 54 sec at 177"C 161 sec

7. Penetration The Penetration of Pioneer 221 by ASTM Method D-5-73 for various* ... ,

temperatures is given below:

25"C (77"F) 22-30 dmm 46"C (115"F) 40-60 dmm o*c (32"F) 13-18 dmm The abbreviation "dmm" means one-tenth of a millimeter. The number of dmm's represents needle penetration under standard conditions loading and time for a given temperature.

8. Specific Gravity The Specific Gravity of Pioneer 221 is approximately 1.0 gram per cc.

Specific Gravity is determined by ASTM Method D-70-72, which employs a

pyenometer. A pyenometer is a container of known volume which is weighed empty and fHled with sample.

9. Solubility Pioneer 221 may be considered to be entirely waterproof and insoluble in water. Pioneer 221 is soluble in petroleum solvents such as naphtha, mineral spirits and kerosene, in addition to carbon tetrachloride, carbon disulfide and trichlorethylene.

A-2 Rev4

1/1/93 .

PIONEER 221 LAMINATING AND INDUSTRIAL ASPHALT PIONEER E-7465 FOR SALT CARTON MANUFACTURERS Pioneer 221 is an all-purpose, tough, medium softening point asphalt for use in laminating paper, foil-to-paper, as a base pigment for paints and varnishes, or in the manufacture.of sealers and adhesives.

Pioneer 221 complies with Federal specifications set forth by the Food and Drug Administration for use in packaging and sealing food products and will not stain, or impart an odor or taste when used properly in connection with packaging products.

PHYSICAL CHARACTERISTICS Softening Point 190-210°F Penetration @ 77°F 20-30 dmm Doctility @ 77°F 2.5 ems +

Solubility CCL 99.0% +

Flash Point (C.O.C.) SS0°F +

Weight per Gallon 8.3 lbs.

Use. Temperature 400°F +/- 25° Viscosity @ 400°F .94 secs Viscosity @ 375°F .174 secs Viscosity @ 350°F .360 secs Packaging: Bulk - Tankwagon (5000 gal), tank car (10,000 gal).

Packages - 100 lb cartons

A-3 Rev 4 1/1/93

Rev. 4 APPENDIX B Consumers Power Company Palisades Nuclear Plant

PROCESS CONTROL PROGRAM (PCP)

System Diagrams

b.

llAW c- lfJllOl N#Cl c....

AfltAfCfMll z::L..I.Z:z:.LZTTTTI I 7 7 7 I l ? 7777/l/l? t I I B-1 EQUIPMENT LOCATION

..

Rev. 4

S.11* A***"' T-~

"'unr X..o."t.T ti_..

APPENDIX B FLOW SYSTEM DIAGRAMS FOR RESINS rr--1

~

,.Tll-"

I ll0'1~T*R r

II 00

. ,.... .... d ..... ,

P.P<!ll **. . -**

. o*Al'r11a"r&I 111, ..".,... , , __ ,

...,,~*"

Rev. 4

APr'ENDIX B* *

B-3 RADWASTE SYSTEM FLOW DIAGRAM

=~-nn

---tan*

aa _ _ _ _

'Ti:'

=.=---

=~tsn<f-

_... '"" - ;:=====:J---,

Q.IM'IM:IAlilMDI

='~~: :;a.:~~:~:~~

= ..

. -=-=---...

UGI . . . . . . . . IUI GICIY'l'D ~Ull

~

_ _ _.aw11.n

____ ------.. ... ~*

t-----..

,_.... .*~ ,,.

01!.J ............

- ....- ,_as.>

~-

a:n.::a.. T -*-

- llc9" , _ ......{_ ....u-.1111

===-~ ...... *- l]!l

. . - .... c.- ............ an.r.a.. ... .................."....,

.uc.ocu--

RSl'llLil"'""'

C*.~ ~IB ~ID l~'WI nl&l8 -.n1 !ail,_ IA.11.1 IUPI n*

Rev. 4

Rev. 4 APPENDIX C Consumers Power Company Palisades Plant

PROCESS CONTROL PROGRAM (PCP)

Relocated Technical Specifications (per NRC Generic Letter 89-01)

(dated January 31, 1989)

ML18059A916

Text

******~ ~~&~&&~~

Purpose:

Purpose:

Attachment:

SUMMARY

Navigation menu

Search