Text

1994 Annual Radioactive Effluent Release & Waste Disposal Rept.
	ML18064A675
Person / Time
Site:	Palisades
Issue date:	12/31/1994
From:	Grogan M, Domonique Malone, Neal T; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	;
Shared Package
ML18064A674	List: ML18064A673; ML18064A675;
References
	NUDOCS 9504060064
	Download: ML18064A675 (286)
	v • d • e

ENCLOSURE Consumers Power Company Palisades Plant Docket 50-255

,. 1994 ANNUAL RADIOACTIVE EFFLUENT RELEASE AND WATE DISPOSAL REPORT March 22, 1995

- - . - .-------*-*-- -----------\

9504060064 950330 I PDR ADDCK 05000255 i R PDR

To DJMalone, Palisades

\k; From '~,y MLGrogan, Palisades CONSUMERS POWER Date March 22, 1995 COMPANY Subject PALISADES PLANT - Internal ANNUAL RADIOACTIVE EFFLUENT Correspondence RELEASE REPORT - JANUARY - DECEMBER 1994 CC JLKuemin, Palisades MLG95*005 KMHaas, Palisades DCC: 950/24*03*10/LP 950/22*07*01*01/LP Attached please find the subject report prepared and reviewed in accordance with Palisades Procedure HP 10.5. This report is believed accurate, pertinent and complete to the best of our ability in meeting the requirements of

10CFR50.36a and Technical specification Section 6.9.3.1.A.

The Palisades Radioactive Effluent Release Report was prepared by MLGrogan, RETS/REMP Supervisor with technical review assigned to TPNeal, HP Support Superintendent. Administrative review and report approval was performed by DJMalone, Radiological Services Manager .

Report prepared by:

Technical Review performed by:

TPNe~ Superintendent

~fo-:z-,/qs-Date Adminis~~ort approval by:

DJMalone, Radio ogical Services Manager

PALISADES NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January - December 1994 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, 1994 through December 31, 1994. The report format is detailed. in Plant Technical specification 6.9.3.1.A. Palisades was off-line during only one period in 1994. From February 17, 1994 till June 18, 1994 the Plant was off-line for boric acid pinhole leak on containment outlet suction line and various valve work. Palisades was on-line during ~ll other time frames in 1994.

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. T-91 {Primary Make-up Water Storage Tank) Leak On August 9, 1994 a flange leak from T-91 overflowed the tank valve pit and released approximately 2790 gallons onto the surrounding soil. T-91 is a hold tank used to store processed water from the dirty liquid radioactive waste system and is routinely discharged to Lake Michigan. T-91 is an outside storage tank, located West of the Turbine Building near the West boundary of the site.

Total Curies released from the flange leak are 8.31 E-1 Ci's of tritium and 6.44 E-04 Ci's of mixed beta/gamma isotopes. The dose consequence assuming direct release to Lake Michigan was maximum wholebody dose to an individual of 3.91 E-04 mrem, and maximum organ dose to an individual of 7.33 E-04 mrem.

The specific details of this event are documented in C-Pal 0653, the radiological evaluation of this release is detailed in TPN 94*020.

2. T-927 Condensate Receiver Tank Tritium Release On November 15, 1994 T-927, the condensate receiver tank for heating boiler M-901, was being discharged to Catch Basin #1.

Sample results indicated that T-927 water contained a detectable amount of tritium, of approximately 6E-6 uci/ml. A review of the T-927 discharge path determined that Catch Basin

1 was an un-monitored release pathway. Thi~ release was

terminated and re-routed to the Turbine Sump, a monitored pathway. Procedures were revised to prevent recurrence, any condensate receiver tank, or related tank with tritium detected will be released to the Turbine Sump.

In a subsequent review of the T-927 sample analysis logbook indicated that tritium had been present occasionally (4 of 16 samples) since March 1994 and consistently (every sample) since August 1994.

This change in the frequency of tritium detection (August) corresponds to the date the Beckman tritium analyzer was replaced with a new Packard tritium analyzer. A comparison of the two tritium analyzers shows the Packard to be more efficient/sensitive, with MDA values of approximately 6E-7 uci/ml, compared to the Beckman analyzer MDA value of approximately lE-6 uci/ml. This difference in sensitivity explains the increased detection of tritium in T-927 samples analyzed after August of 1994.

A batch card (94-029-R) was initiated to quantify the tritium released via T-927 (750 gallon capacity) through the Catch Basin #1 Pathway for all of 1994.

The specific details of this event are documented in C-Pal 1023.

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

D. Radioactive Effluent Monitoring Instrumentation:

1 Waste Gas Decay Tank Vent Flow Indicator (FI-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 must 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for continuous releases or fours 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, Evaluation and Release of Waste Gas Decay Tank, 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 a11 gas batch rel eases in 1994.

The root cause of the flow indicator problem is the system design and not the flow indicator itself. Both the valving sequence and the setpoint of PCV-1123 impacts FIT-1121 operation .

Actions being taken to improve performance are the changing of the valving sequence in SOP 18A, Radioactive Waste System-Gaseous, and also changing SOP 18A and HP 6.6 to alert Ops to install a gauge to verify the setting of PCV-1123. These two

.actions should help to reduce the initial surge on FIT-1121 that is blamed for repeatingly damaging it. Actions to restore FIT-1121 to operability are being followed in C-Pal-94-0839F.

During the period of inoperability, all of the Offsite Dose Calculation Manual (ODCM) sampling requirements as stated in Table A-1 were met.

2. Stack Gas Effluent system (RGEM)

On December 1, 1994, the Palisades Radiological Gaseous Effluent Monitor (RGEM) w~s declared inoperable. RGEM is the monitor for the Plant's stack gas effluent. This monitor became inoperable when the sampler flow rate monitor, FE-2346 failed its 18 month calibration test as required by the Offsite Dose Calculation Manual (ODCM) Appendix A, Table A-2. This report is being submitted because the RGEM system was not restored to operable status within the seven day requirement per the ODCM Appendix A, Table A-1 item 3.d Action statement.

The Palisades Stack Gas Effluent System (RGEM), consists of the following channels: Noble Gas Activity Monitor, RIA-2326; Iodine/Particulate/Sampler/Monitor RIA-2325; Sampler Flow Rate Monitor FE-2346; and Hi Range Noble Gas Monitor RIA-2327.

On December 1, 1994, Technical specification Surveillance Procedure RR-84D, "Radiological Gaseous Effluent Sampler Flow Rate Calibration" was performed. During this test, the RGEM sample flow rate monitor, FE-2340 did not respond to input changes per test requirements. Troubleshooting revealed that the sample flow valve control gears for FE-2346 were badly worn and disengaged. The set screw that holds the large gear on the shaft had loosened, which caused excessive gear deflection and wear. With these gears disengaged, FE-2346 could not respond to input changes per RR-84D test conditions. A condition report (C-Pal-94-1099) was initiated and the entire RGEM sampling system was declared inoperable.

Replacement sample flow valve control gears are not stocked onsite and were not immediately available from the Vendor.

Replacement gears were not received in time to restore the system to operation within the seven day time requirement.

Palisades ODCM Appendix A, Table A-1, item 3(a-d) details the sampling/analysis actions required when the RGEM system is inoperable. Each channel has specific required actions, and although only FE-2346 was not functioning properly, the entire system was declared inoperable. During this period of inoperability, all the required sampling/analysis, flow estimations, and alternate method of monitoring were implemented and completed in a timely manner. *

Also during this period, the RGEM unit (although declared inoperable) continued to provide its design function to sample/analyze Noble Gas, Iodine, and Particulate on a continuous basis. With the sample flow rate monitor .(FE-2346)

gears removed this unit still maintained a near isokenetic sample collection rate of approximately 1.60 cfm .

The RGEM unit was restored to service on December 22, 1994.

Replacement sample flow gears were ordered and installed, and the RGEM Sample Flow Rate calibration (RR-840) was successfully completed.

All the sampling/analysis requirements of ODCM Appendix A, Table A-1 action statements were completed in the time periods specifi.ed.

2. Gaseous Effluents Table HP 10.5-2 (Attachment 2), Palisades Radioactive Effluent Report, lists and summarizes all gaseous radioactive effluents released during the reporting period. The unidentified beta was 3.23 E-04% of the total release.

3. Liquid Effluents Table HP 10.5-3 (Attachment 3) lists and summarizes all liquid radioactive effluents released during the reporting period. All beta activity was accounted for during the releases. There was no "unidentified beta".

4. Solid Waste There were no solid radwaste shipments to disposal sites in 1994 .

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 1.31 E-04 millirad beta and 4.29 E-05 millirad gamma for the first quarter; 3.84 E-04 millirad beta and 9.34 E-05 millirad gamma for the second quarter; 3.00 E-04 millirad beta and 1.01 E-04 millirad gamma for the third quarter; and 2.94 E-04 millirad beta and 9.88 E-05 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 second quarter, being 2.57 E-04 millirads beta and for gam.ma during the third quarter being 6.77 E-05

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 8.12 E-03 millirem for the first quarter; 4.30 E-03 millirem for the second quarter; 5.58 E-03 millirem for the third quarter; and 4.78 E-03 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: 7.50 E-03 person-Rem and 6.47 E-06 millirem for the first quarter; 6.44 E-03 person-Rem and 5.55 E-06 millirem for the second

quarter; 7.12 E-03 person-rem and 6.14 E-06 millirem for the third quarter; and 6.68 E-03 person-Rem and 5.76 E-06 millirem for the fourth quarter .

D. The maximum total body dose to an individual in unrestricted water-related exposure pathways was 1.69 E-8 millirem (adult) for the second quarter; 1.03 E-2 millirem (adult) for the third quarter; and 3.48 E-8 millirem (adult) for the fourth quarter. There was no Radioactivity released in Liquid Effluents from Palisades in the first quarter of 1994. The maximum organ doses were 1.69 E-8 millirem (adult) for the second quarter; 1.93 E-2 millirem (teenage liver) for the third quarter; and 3.48 E-8 millirem (adult) for the fourth quarter. The calculated organ dose for the second and fourth quarters was the same value as whole body for all organs, since the only isotope released in these two quarters was tritium.

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: 1.94 E-07 person-rem and 1.67 E-10 millirem for the second quarter; 3.46 E-02 person-Rem and 2.98 E-05 millirem for the third quarter; and 3.99 E-07 person-Rem and 3.44 E-10 millirem for the fourth quarter. There was no Radiological release in liquid effluents from Palisades during the first quarter of 1994.

6. Process Control Program (PCP The Process Control Program was revised, effective December 30, 1994.

The changes made during Revision 5 include:

1. Eliminating references to the silicate cement solidification process which is no long used;

2. Changed free water determination to the current Quality Verification Program standards;

3. Removed reference to specific vendor program for 10CFR61 classification requirements; A copy of the revised PCP is enclosed (Attachment 6) 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 8 during this reporting period as a result of use of the new 5 year met data (1988-1992), and the 1993 Land Use Survey.

1) Update of Table 1.4, 1993 Palisades Land Use Census;

2) Update of Table l.4a; 1993 Palisades Land Use Census - Critical Receptor Items;

3) 4)

Update of Table 1.9; 1994 Palisades Gaseous Design - Objective Annual Quantities; Added a sum of the fractions example to clarify storage tank requirements in Section III.k.l of Appendix A of the ODCM.

The revised ODCM enclosed with this report (Attachment 7) along with supporting documentation as per the requirements of Technical Specification 6.18 .

ATTACHMENT I Consumers Power Company Palisades Plant RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES January - December 1994 I Page

TABLE HP 10.5-1

PALISADES PLANT RADIOACTIVE EFFLUENT REPORT BATCH RELEASES January 1, 1994 to December 31, 1994 A. GASEOUS Units 1st Qtr 2nd Qtr

3rd Qtr 4th Qtr Number of Releases 1 7 0 0 Total Release Time Minutes 417 2496 N/A N/A Maximum Release Time Minutes 417 615 N/A N/A Average Release Time Minutes 417 357 N/A N/A Minimum Release Time Minutes 417 233 N/A N/A

B. LIQUID Number of Releases Total Release Time Units Minutes 1st Qtr 0

N/A 2nd Qtr 635 1

3rd Qtr 1

658 4th Qtr 0

N/A Maximum Release Time Minutes N/A 635 658 N/A Average Release Time Minutes N/A 635 658 N/A Minimum Release Time Minutes N/A 635 658 N/A

ATTACHMENT 2 Consumers Power Company Pa 1i sades Pl ant RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES January - December 1994 3 Pages

TABLE HP 10.5-2

PALISADES PLANT RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES Januarv 1. 1994 to December 31. 1994 Est Total A. FISSION AND ACTIVATION Units 1st Otr 2nd Otr 3rd Otr 4th Otr Error%

GASES

1. Total release Ci 2.17E+OO 5.60E+OO 5.04E+OO 4.93E+OO

2. Average release rate for period µCi/sec 2.79E-01 7.13E-01 6.34E-01 6.20E+01 7.63E+OO

3. Percent of annual avg EC % 1.01 E-04 2.46E-04 2.31 E-04 2.25E-04 B. IODINES

1. Total Iodine Ci 3.02E-04 2.79E-04 9.15E-04 6.84E-04 *

2. Average release rate for period µCi/sec 3.88E-05 3.55E-05 1.15E-04 8.60E-05 6.15E+OO

3. Percent of annual avg EC % 2.73E-05 1.03E-05 3.86E-05 3.02E-05 C. PARTICULATES 1 . Particulates with half-life

> 8 days Ci 2.45E-05 1.82E-05 2.01 E-05 1.47E-05

2. Average release rate for eriod µCi/sec 3.16E-06 2.31 E-06 2.53E-06 1.85E-06

3. Percent of annual avg EC % 9.07E-05 4.93E-05 6.29E-05 5.26E-07 2.7E+01

4. Gross alpha radioactivity Ci 8.22E-06 1.25E-06 1.28E-06 1.35E-06 D. TRITIUM

1. Total Release Ci 1.45E+OO 1.59E+OO 1.64E+OO 1.61E+OO

2. Average release rate for period µCi/sec 1.86E-01 2.02E-01 2.06E-01 2.03E-01

3. Percent of annual avg EC % 3.38E-04 3.67E-04 3.75E-04 3.69E-04 E.

1. Beta Airdose at Site Boundary Due to Noble Gases (ODCM App A Ill.Cl mrads 1.31 E-04 3.84E-04 3.00E-04 2.94E-04

2. Percent limit % 1.31 E-03 3.84E-03 3.00E-03 2.94E-03

3. Gamma Airdose at Site Boundary Due to Noble Gases (ODCM App A Ill.Cl mrads 4.29E-05 9.34E-05 1.01 E-04 9.88E-05

4. Percent limit % 8.58E-04 1.87E-03 2.02E-03 1.98E-03 F.

1 . Maximum Organ Dose to*

~;ublic Based on Critical eceptors (ODCM App A l.Dl mrem 8.12E-03 4.30E-03 5.58E-03 4.78E-03

2. Percent of limit % 1.08E-01 5.73E-02 7.44E-02 6.37E-02

NOTE: Data is reported for I-131 and I-133 only.

TABLE HP 10.5-2

PALISADES PLANT RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS January 1. 1994 to December 31. 1994

1. FISSION GASES Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Argon-41 Ci <LLD <LLD <LLD <LLD Krypton-SS Ci 3.02E-02 9.SSE-01 <LLD <LLD Krypton-85m Ci <LLD <LLD <LLD <LLD Krypton-87 Ci <LLD <LLD <LLD <LLD Krypton-88 Ci <LLD <LLD <LLD <LLD Xenon-131m Ci <LLD 3.89E-03 <LLD <LLD Xenon-133 Ci 2.14E+OO 4.61E+OO 5.04E+OO 4.93E+OO Xenon-133m Ci <LLD <LLD <LLD 3.14E-04 Xenon-135 Xenon-135m Xenon-138 Ci Ci Ci 2.28E-04 1.02E-04 4.36E-04 2.07E-04

<LLD

1. 71E-04

<LLD

<LLD Total for Period Ci 2.17E+OO 5.60E+OO 5.04E+OO 4.93E+OO

2. IODINES lodine-131 Ci 2.16E-04 4.lOE-05 1.93E-04 1. 59E-04 Iodine-132 Ci <LLD <LLD 1. SSE-04 <LLD Iodine-133 Ci 8.59E-05 2.38E-04 7.22E-04 5.25E-04 Iodine-134 Ci <LLD <LLD <LLD <LLD Iodine-135 Ci <LLD <LLD 1. 60E-04 <LLD Total for Period Ci 3.02E-04 2.79E-04 1.23E-03 6.84E-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 <LLD <LLD <LLD Iron-59 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci <LLD 3.67E-06 3.50E-06 <LLD Zinc-65 Ci <LLD <LLD <LLD <LLD Strontium-89 Ci 1.30E-06 2.21E-06 5.45E-07 9.90E-07 Strontium-90 Ci 1. 25E-06 9.50E-07 2.30E-07 7.25E-07 Molybdenum-99 Ci <LLD <LLD <LLD <LLD Cesium-134 Ci <LLD <LLD <LLD <LLD Cesium-137 Ci <LLD <LLD <LLD <LLD

Cerium-141 Cerium-144 Ci Ci

<LLD

<LLD Net unidentified beta Ci 2.20E-05 1.13E-05 1. 58E-05 1.30E-05 Total 2.45E-05 1.82E-05 2.0IE-05 1. 47E-05

*Particulates with half-lives> 8 days.

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

ATTACHMENT 3 Consumers Power Company Palisades Plant RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS - SUMMATION OF RELEASES January - December 1994 2 Pages

TABLE HP 10.5-3 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Januarv 1. 1994 to December 31. 1994 A. FISSION AND ACTIVATION Est Total PRODUCTS Units 1st Otr 2nd Otr 3rd Otr 4th Otr Error%

1. Total release (not including tritium, gases, alpha) Ci <LLD <LLD 1.41 E-02 <LLD

2. Average release rate for 5.19E+OO period µCi/mi N/A N/A 5.62E-10 N/A

. 3. Percent of EC % N/A N/A 2.71 E-02 N/A B. TRITIUM

1. Total Release Ci N/A 5.13E-03 1.82E+01 1.66E-02

2. Average diluted 4.00E+OO concentration during period µCi/mi N/A 3.25E-10 7.25E-07 6.61E-10

3. Percent of EC % N/A 3.25E-05 7.25E-02 6.61 E-05

. C . DISSOLVED AND ENTRAINED

' GASES

1. Total Release Ci <LLD <LLD <LLD <LLD

2. Average diluted N/A N/A N/A N/A N/A concentration during period µCi/mi

3. Percent of EC % N/A N/A N/A N/A D. GROSS ALPHA RADIOACTIVITY Ci (Total Release) <LLD <LLD 9.50E-06 <LLD E. VOLUME OF WASTE RELEASED Liters (Prior to Dilution) 0.00 4.81 E+05 2.21E+05 0.00 F. VOLUME OF DILUTION WATER USED DURING Liters PERIOD 1.99E-f- 10 1.58E+10 2.51E+10 2.51E+10 G. MAXIMUM DOSE COMMITMENT - mrem WHOLEBODY . 0.00 1.69E-08 1.03E-02 3.48E-08 Percent of ODCM App A 111.H limit % N/A 1.13E-06 6.87E-01 2.32E-06

. MAXIMUM DOSE COMMITMENT - ORGAN mrem 0.00 1.69E-08 1.93E-02 3.48E-08 Percent of ODCM App A 111.H % N/A 3.38E-07 3.86E-01 6.96E-07 limit

TABLE HP 10.5-3 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT LIQUID EFFLUENTS January l, 1994 to December 31, 1994

1. NUCLIDES RELEASED Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Manganese-54 Ci <LLD <LLD 2.09E-04 <LLD Cobalt-58 Ci <LLD <LLD 2.58E-03 <LLD Iron-59 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci <LLD <LLD 6.42E-03 <LLD Zinc-65 Ci <LLD <LLD <LLD <LLD Strontium-89 Ci <LLD <LLD 4.86E-07 <LLD Strontium-90 Ci <LLD <LLD 6.19E-06 <LLD Molybdenum-99 Ci <LLD <LLD <LLD <LLD Iodine-131 Ci <LLD <LLD <LLD <LLD Cesium-134 Ci <LLD <LLD 3.95E-04 <LLD Cesium-137 Ci <LLD <LLD 3.99E-03 <LLD Cerium-141 Ci <LLD <LLD <LLD <LLD Cerium-144 Ci <LLD* <LLD <LLD <LLD Coball -57 Ci <LLD <LLD 9.07E-05 <LLD Sil ver-llO Ci <LLD <LLD 3.92E-04 <LLD Net unidentified beta Ci <LLD <LLD <LLD <LLD Fission &Activation Product Total Ci 0.00 0.00 1.41E-02 0.00

Tr it i uni Grand Total Ci Ci

<LLD 0.00 5.13E-03 5.13E-03

1. 82E+Ol l.82E+Ol l.66E-02 l.66E-02

ATTACHMENT 4

Consumers Power Company Palisades Plant RADIOACTIVE EFFLUENT RELEASE REPORT SOLID WASTE January - December 1994 I Page

TABLE HP 10.5-4 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT SOLID WASTE January l, 1994 to December 31, 1994 Waste Source of Solidification Container Volume *Total *Principal Class ~~=W=as~t=e'---~ Agent Type (cu ft) Curies Radionuclides Note: No solid radwaste shipments from January l, 1994 to December 31, 1994 .

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

ATTACHMENT 5

Consumers Power Company Pali sades Pl ant RADIOACTIVE EFFLUENT RELEASE REPORT LOWER LIMITS OF DETECTION FOR PALISADES EFFLUENTS January - December 1994 1 Page

., LOWER LIMITS OF DETECTION (LLDsl FOR PALISADES EFFLUENTS Gaseous Effluents Nuclide LLD (µCi/eel*

Cr-51 2.32E-09 Mn-54 2.63E-10 Co-58 3.25E-10 Waste Gas Decay Tank Co-60 8.54E-10 Batch #'s: 94-014-G Zn-65 7.04E-10 and 94-018-G Se-75 2.69E-10 Cs-134 2.22E-10 Cs-137 5.42E-10 Zr-95 1.61E-10 Sb-125 4.59E-10 Nb-95 3.41E-10 Liquid Effluents Nuclide LLD (uCi/ccl**

Co-58 9.35E-08 Mn-54 2.62E-07 Fe-59 4.22E-07 Zn-65 3.43E-07 Liquid Batch Release Co-60 1.40E-07

's: 94-017-R Cs-134 1.0lE-07 and 94-011-R Cs-137 1.46E-07 I-131 2. 71E-07

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

- From typical liquid release analysis.

ATTACHMENT 6

' Consumers Power Company Palisades Plant PROCESS CONTROL PROGRAM March 31, 1995

PALISADES NUCLEAR PLANT ?!."OC No .3.:-:

SAFETY REVIEW Attachmen:. ~

Revision 7 Page l of l PS&L Log No _ _tf.....__,_V-_-...;.:15'--.LZ.....:.Y Rev '-/A Title SE Rev Reason for Issue/Change:

Yes No

l. Does the item involve a change to procedures as described in the FSAR?

FSAR Sections affected ~~__,~--,..~~~~---~~~~~~~~~~~~

FSAR Sections reviewed

2. Does the item involve a change to the facility as described in the FSAR?

FSAR Sections affected ~~~~~-~~~....,....~~~~~~~~~~~~~~~

FSAR Sections reviewed II

~~~~....;....'--~~~~~~~~~~~~~~~

.I

3. Does the item involve a test or experiment not described in the FSAR?

FSAR Sections affected FSAR Sections reviewed j)nc-t-II

4. Should the Technical Specifications or any of their Bases be changed in conjunction with this item?

TS Sections affected ~~~At~'IH=r.~~=-~~~~~~~~~~~~~~~~ /

TS Sections reviewed Justify No Answers below if logic is not obvious:

Kemov-~/ r<-fv~e~ (f~1f11.J h 1,i,u,fa. c~ -11° /ffllj~ use,c/.

~/,~1--d lf.e~ ~ d~~m,-nd-,~ fo C..vr-;,...J ~ti// .s~/.,

°'ttd r....-..v ....! ,...~ ~ ~~ it"l'fl{J.._vf.,,. * (f9"'fe.t,.J

'f~~l,t:. .fl' V'~ ~~°""". /JAJV

/.J-12.

If any Safety Review question listed above is answered "YES," perform a written USQ 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 for the item to document that* a Saf_ety _Evaluation was not required.

'1 p(I>

I / ~ */l- -'f'j' 'r;*

I~

c* _p1.1ct-f':i1/r'1 fT 'Q OV i Of.JO,., Q ,_,

ATTACHMENT 7

Consumers Power Company Pa 1 i sades Pl ant RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT OFFSITE DOSE CALCULATION MANUAL March 31, 1995

-i

J*- ,... * *r--

Rev 5 Consumers Power Company Palisades Nuclear.Plant PROCESS CONTROL PROGRAM CPCP) gr ML GROGAN 12-15-94 Technical Review Date PS&L 94-1578 12-21-94 Plant Review Committee Date Periodic Review Date

-P~ger /~/54 Date

I 'l Table of Contents

1. 0 Asphalt Volume Reduction System . 1 1.1 Variables Influencing Solidification 1

1. 2 Aspha 1t Type 2

1. 3 Waste Chemical Species 2

1. 4 Waste-to-Asphalt Ratio 4

1. 5 Process Temperatures 5

1. 6 Solidification and Free Water Determination 5 2.0 Dewatering Solids in High Integrity Containers CHIC) 6 3.0 10 CFR 61 Requirements 6 4.0 Radwaste System 6 5.0 Technical Specification Requirements 6 Appendix A - Asphalt Technical Data Summary 4 Appendix B - System Diagrams Appendix C - Relocated Technical Specifications

PALISADES NUCLEAR PLANT Proc No J.J/

SAFETY REVIEW . Att.:.c~rnen~ :

{ e ~ s ; .:; n S Page 1 of 1

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PS&L Log No Item Identification:

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Title o~fi/Tt /)()ft:-

SE REV Describe Issue/Change: (!/..ti;.( {;'r:-1 ,'i1£. . ~. I.

Reason for Issue/Change: ~,,L !!!:l ,...,- I ~t-e..r

--,l!!!/'e:fJr~ D- /?lh_ ~8.1!3

1. Does the item involve a change to procedures as described in Yes No the FSAR?

.FSAR Sections affected None FSAR Sections reviewed //

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2. Does the item. involve a change ta the facility as described in the FSAR?

FSAR Sections affected ~.rx.t...

FSAR Sections reviewed -~--;/~

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3. Does the item involve a test or experiment not described in the FSAR?

FSAR Sections affected ,<,/tM.A-FSAR Sections reviewed II v-

4. Should the Technical Specifications or any of their Bases be changed in coniunction with this item?

TS Sections af ected ..Vnc- . ..,,/"'

TS Sections reviewed t.

Justify No Answers below if logic is not obvious:

4dti~ ~'-e.,,lr-/-1~ ,:;l"'t'K"' It. +D re.. (""'. .{!, r"e <..

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If a~ Safety Review guestion listed above is answered "YES", perform a written USQ valuation a=cord1ng to Section 5.3.

If all Safety Review questions listed above are answered N0, 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.

~ t. I z-i2-f}

Date ~cuif,~ IDate J...-:J.J..- 'tJ

I

PALISADES PROCESS CONTROL PROGRAM CPCP)

1. 0 ASPHALT VOLUME REDUCTION SYSTEM The Palisades Plant utilizes a Waste Chem volume reduction and solidification system CVRS) 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. and B-2 is a flow system diagram for resins and concentrates~

To maintain operator exposure ALARA. 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 fs 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.

Tlie following variables influence the properties and con'sistency 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 Rev* 5 1 1/1/95

ASPHALT TYPE

1. 2 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-0-312-71. 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 maximum 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 the 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 llmit 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).

REQUIRED ANALYSIS Concentrates Resin/Powdex pH (equip limit) pH (equip limit)

% solids % slurry Sp Gravity Oil %

Rev 5 2 111/95

I *I

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

1. Boric Acid Concentrates at 120 L/hr Evaporative Rate < 1.0/1.0

2. Spent Resins at 80 L/hr Evaporative Rate < 0. 67 /1. 0

3. Powdex at 80 L/hr Evaporative Rate ~ 0.67/1.0 Should the ratio of waste-to-asphalt be increased above the range specified in the foregoing table. 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 product 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 reduction may not be realized.

Maximum concentrate feed rate can be determined by the following formula:

Cone Feed Rate = 0.528 GPM Cl.O - Solids Fraction)(Sp Gravity)

NOTE: 0.528 gpm = 120 L/hr evaporative rate.

The corresponding asph~lt feed is calculated by:

Asphalt Feed CGPM) = (Cone Feed Rate GPM)(Solids Fraction)(Sp Gravity)

. (Waste-to-Asphalt Ratio) where the recommended waste-to-asphalt ratio is 1.0.

Rev 5 3 111/95

I' l 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 NOTE 3:

requirements of the twin screws.

If either the concentrate or asphalt flows cannot be met. the calculated flows can be ratioed to new values to maintain the 1.0/1.0 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 Cl.O - Solid Fraction)

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 CGPM) = CResin 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 to 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.

Rev 5 4 1/1/95

I i::se C/H-t:.tfuPflo~ m/t~tlAt..

Rev _2a._ Title (oocmj SE REV Describe Issue/Change:

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1. Does the item involve a change to procedures as described in Yes No the FSAR?
FSAR Sections affected A)d!lLc FSAR Sect i ans reviewed -"""""*.a.1,~--2-. ,
~_,,....---------
2. Does the item involve a change to the facility as described in the FSAR?
FSAR Sections affected i/lhUe FSAR Sect i ans reviewed --~,aos.::: ,:..,.._-~-.-.s-----------
3. Does the item involve a test or experiment not described in the FSAR?
FSAR Sections affected Al~
FSAR Sections reviewed _.....;..;/...;..,=-,.,-<-----------
4. Should the Technical Specifications or any of their Bases be changed in conjunction with this item?
TS Sections affected A/111~
TS Sections reviewed -*...:...;...,";;..;.;...;~-------------
Justify No Answers below if logic is not obvious:
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haj ?1-18 414 l"e-R-e.J.,,:,j .f;r$f yea~ of ltle..f 11,,uv- ~~~ -
If any Safety Review question listed above is answered "YES", perform~ written USQ Evaluation accord1ng to Section 5.3.
If all Safety Review questi~ns listed above are* answered NO, written USQ Evaluation is not required, However~ this Attachment shall accompany other review materials for the item to document tnat a Safety Evaluation was not required.
p~
Procedure No ODCM Revision 8 Issued Date 1/5/94
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TITLE: OFFSITE DOSE CALCULATION MANUAL a~ l s;:t;,.,
P~dure Sponsor
//Z-23-93 Date
.... Technical Reviewer I
Date I
User Reviewer Date Rev#
\((~~/ 1/Y'/1y Plant General Manager Date
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
. ~*---------- Table of Contents I. GASEOUS EFFLUENTS 1 A. ALARM/TRIP SETPOINT METHOD 1
1. Allowable Concentration 1
2. Monitor Response . 2
s. DOSE RATE CALCULATION 3 C. DESIGN OBJECTIVE QUANTITY (DBQ) LIMITS ON BATCH AND CONTINUOUS RELEASES . 16 1.. Batch Releases . 16
2. Continuous Releases 17
3. Exceeding DBQ Limits . 17
4. Releasing Radionuclides Not Listed in Table 1.9
11,
0. OPTIONAL QUARTERLY DOSE CALCULATIONS . 18
1.
1.
2.
Methodology for OQtional Quarterly Dose Calculations E. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION System DescriQtion .
.Determination of Satisfactory Operation 18 20 20 21 J_'
F. RELEASE RATE FOR OFFSITE EC (50 mrem/yr) 21 G.. PARTICULATE AND IODINE SAMPLING 22 H. NOBLE GAS SAMPLING 22 L *TRITIUM SAMPLING . 22 J. FIGURES AND TABLES 22 I I. LIQUID EFFLUENTS . 55 A. CONCENTRATION 55
1. Requirements . . . 55
2. Prerelease Analysis 55
3. Effluent Concentration CEC)
Sum of the Ratios 56 B. INSTRUMENT SETPOINTS . 57
1. Setpoint Determination 57
2. ComQosite Samplers .. 57
3. Post-Release Analysis 58 C. DOSE 58
1. RETS Reguirement 58
I I
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL

R_e_v,_*s-io_n__ s ___________________________*

Table of Contents
2. Rel ease Analysis . . . . . . . . . 58
0. OPERABILITY OF LIQUID RADWASTE EQUIPMENT 62 E. RELEASE RATE FOR OFFSITE EC (50 mRem/yr) 62 F. FIGURES AND TABLES . 62 III. URANIUM FUEL CYCLE DOSE 84 A. SPECIFICATION . 84 B. ASSUMPTIONS .. 84 C. DOSE CALCULATION 84 Appendix A. "Relocated Technical Specification" Appendix B. "Request to Retain Soil in Accordance with 10CFR20.302"
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL .
Revision 8 I. GASEOUS EFFLUENTS A. ALARM/TRIP SETPOINT METHOD Appendix A.Section III.B.l 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 all radionuclides in particulate form with half lives greater than 8
days: Less than or equal to 1500 mrems/yr to any organ.
Appendix A.Section III.A.l requires gaseous effluent monitors to have alarm/trip setpoints to ensure that offsite concentrations. when averaged over 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . will not be greater than Appendix A.Section III.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 calculating an allowable
concentration for the nuclide mixture to be released. The second consists of determining monitor response to this mixture in order to establish the physical settings on the monitors.
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:
c.1 R(kl = (~) (F) ~ -
ECi
= s; *10.0 (1.1) where:
Ci = Actual or measured concentration. at ambient temperature and pressure of nuclide i (µCi/cc)
ECi The EC of nuclide i from 10 CFR 20. Appendix B.
Table 2 = 50 mrem/yr - total body.
Rck> = The total EC-fraction for release point k X/Q Most conservative sector site boundary dispersion Cl.79E-06 sec/m3 )
F Rel ease .fl ow rate (83. 000 cfm = 39. 2 m3 /sec) for stack monitor considerations; variable for other monitors.
1
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
- Revision 8 NOTE: If a batch release is made while a contin.uous release or another batch release is in progress. the sum of all values of Rk must be less than 10.0.
2. Monitor Response Normal radioactivity releases consist mainly 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 is 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 alarms is established at some factor (b) greater than 1 but less than l/Rk (Equation 1.1) times the measured concentration (c):
s = b xc (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 Action Levels and associated actions. Emergency Implementing Procedures contain monitor-specific curves or calibration constants for conversion between cpm and µCi/cc (or R/hr and
µCi/cc). depending on monitor type. for fission product mixtures as a function of mixture decay time:
When these monitors are utilized for other than accident conditions. either an appropriately decayed "accident" conversion curve may be used. or a decayed fission gas calibration factor may be applied. In these cases. setpoints are established as in l.A above.
Setpoints of accident monitors (if set to monitor normal releases) are reset to the accident alarm settings at the end of normal release. Setpoints of other release monitors are 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 boundary). or are reset to approximately three times background in order to detect leakage or inadvertent releases B.
of low level gases.
DOSE RATE CALCULATION 2
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
1. Dose rates are calculated for (1) noble gases and (2) iodines and particulates. Dose rates as defined in this section are based on 10 CFR 50 Appendix I limits of mrem per quarter and millirem per year. All dose pathways of major importance in the Palisades environs are considered.
a. Equations and assumption~ for calculating doses from noble gases are as follows:
1) Assumptions a) Doses to be calculated are the maximum of~site point in air. total *body and skin.
b) Exposure pathway is submersion within a cloud of noble gases.
c)
Noble gas radionuclide mix is based on the historically observed source term given in Table 1.1\
plus additional nuclides.
d) Basic radionuclide data are given in Table 1.2 .
e) f)
All releases are treated as ground-level.
Meteorological data expressed as joint-frequency distribution of wind speed. wind direction. and 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) For person exposures. credit is taken for shielding by residence (factor of 0.7).
l) Radioactive decay is considered for the plume .
m) Building wake effects on effluent dispersion are considered.
3
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL n) o)
Revision 8 A sector-average dispersion equation is used.
The wind speed classes that are used are as follows:
Wind Speed Class Number Range Cm/s) Midpoint (m/s) 1 0.0-0.4 0.2 2 0.4-1.5 0.95 3 1.5-3.0 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) Equations To calculate the dose for any one of the exposure points.
the following equations are used.
For determining the air concentration of any radionuclide:
x. =
i t t J =1 k=l
(~)
1t 1 2 1 L zkU fjk j
Qi p (21tx/n)
[
exp-(A.
i x )]
. uj Cl. 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.
p Fraction of radionuclide remaining in plume.
Vertical dispersio~ coefficient for stability class k Cm).
. u*J Midpoint value of wind speed class interval j.
mis.
4 J
PALISADES NUCLEAR PLANT QFr:SITE DOSE CALCULATION MANUAL Revision 8 x
n Downwind distance. m.
Number of sectors. 16.
Radioactive decay coefficient of radionuclide i.
s-1 . .
2rrx/n Sector width at point of interest. m.
For determining the*total body dose rate:
o. 4) where:
Total body dose rate. mrem/y.
Air concentration of radionuclide i. µCi/m 3 .
Total body dose 3factor due to gamma radiation.
mrem/y per µCi/m (Table 1.5).
For determining the skin dose rate:
D5 = ~ Xi (DFSi + 1.11 DFYi)
O. 5) where:
Os Skin dose rate. mrem/y.
X; Air concentration of radionuclide i. µCi/m 3 DFS; - Skin dose3 factor due to beta radiation. mrem/y per µCi/m (Table 1.5).
1.11 = The average ratio of tissue to air energy absorption coefficients. mrem/mrad.
DFY.1 = Gamma-to-air dos! factor for radionuclide i.
mrad/y per µCi/m (Table 1.5).
For determining dose rate to a point in air:
Da =~ X.1 (DFY-
. 1 or DFB-)
1 1
o. 6) where:
DFB; Air dose rate. mrad/yr Air dose factor for beta radiation (Table 1.5) .
. 5
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
b. Equations and assumptions for calculating doses from radioiodines and particulates are as follows:
1) Assumptions 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 contamination. green leafy vegetables from home gardens. and inhalation.
c) The radioiodine and particulate mix is based on the historically observed source term given in Table 1.1.
d) Basic radionuclide data are given in Table 1.2.
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 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.
l) Building wake effects on effluent dispersion are considered.
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.
6
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 p) Milk cows and goats obtain 100% 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 residence (factor of 0. 7).
2) Eguat ions To calculate the dose for any one of the potential maximum-exposure points. the following equations in Section 1.2.2 are used.
a) Inhalation Equation for calculating air concentration. X~ is the same as in the Noble Gas Section (Equation 1.J).
For determining the organ dose rate:
D.l. =1 x 10 6 ~ Xi DFI i BR 1
O. 7) where:
D; Organ dose rate due to inhalation. mrem/y.
x.
1 Air c~ncentration of radionuclide i.
µCi Im .
DFI; Inhalation dose factor. mrem/pCi (Table 1.7).
BR = Breathing rate 14003 m3 /y infant: 3700 m3 /y child; or 8000 m/y teen and adult.
lxl0 6 = pCi/µCi conversion factor.
b) Ground Contamination For determining the ground concentration of any nuclide:
7 Gi = 3. 15 x 10 7 E k=l (1. 8) where: .
7
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL G.1 Revision 8 Ground2 concentration of radionuclide i.
µCi /m .
k Stability class.
Joint relative frequency of occurrence of winds in stability class k blowing toward this exposure point. expressed as a fraction.
Qi Average release rate of radionuclide i.
µCi/s. .
DR Relative deposition rate. m- 1 (Fig 1.2).
x Downwind distance. m.
n Number of sectors. 16.
2rrx/n
Sector width at point of interest. m.
A; = *Radioactive decay coefficient of tb 3 .15x10 7
=
=
radionuclide i . y- 1 .
Time for buildup of radionuclides on the ground. 15 y.
sly conversion factor.
8
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
~----------------------------------R-ev_,_*s_i_on__s_________________________________
Corrected ia-3 January 1977 I I T
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I 10""7 111 : , ! i O.l 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMET!RSt Fi gun 7. A.mM OIPOlltion for Ground Lft91 Rll..., (AU Atmosphwic Subility ciauest n - -- ,-
9
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 For determining the total body or organ dose rate from ground contamination:
DG = (8 7 6 0 ) ( 1 I x 10 6 ) ( 0 .7 ) .E l
G i DFG i O. 9) where:
Dose rate due to ground contamination.
mrem/y.
Ground concentration of radionuclide i.
µCi /m 2 .
DFG.1 = Dose factor for standing on contaminated ground. mrem/h per pCi/m 2 (Table 1.8).
8.760 = Occupation time. h/y.
lx10 6 pCi/µCi conversion factor.
0.7 Shielding factor accounting. for a distance of 1.0 meter above ordinary ground.
dimensionless.
c) Milk and Vegetation Ingestion For determining the concentration of any nuclide (except C-14 and H-3) in and on vegetation:
CVi =),GOO~ f1: Qi DR (r[l-exp (-A,Eit 9 ) ] + B [1-exp (-A. t )]) ([e _(A. t )Jj
-#i (21tX/n) Yv A!!i - iv PA.1 . i b xp i h O. 10) where:
CV; = Concentration of radionuclide i in and on vegetation. µCi/kg.
k Stability class fk = Frequency of this stability class and wind direction combination. expressed as a fraction.
O; = Average release rate of radionuclide i.
µCi/s.
DR Relative deposition rate. m-1 (Figure 1.2).
x = Downwind distance. m.
10
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
- - - - - Number n
-of- ----
sectors. 16.
2rrx/n Sector width at point of interest. m.
r Fraction of deposited activity retained on vegetation (1.0 for iodines. 0.2 for particulates).
AEi Effective removal rate constant.
AEi = Ai + Aw. where A;1 is the radioactive decay coefficient. h- . and A is a measure of physical loss by weathering *
(Aw= .0021 h-).
te Period over which deposition occurs. 720 h.
Yv Agricultural yield. 0.7 kg/m 2 .
Biv = Transfer factor from soil to vegetation of' radionuclide i (Table 1.6).
Ai = Radioactive decay 1 coefficient of
tb p
radionuclide i. h-Time for buildu~ of radionuclides on the ground. l.31x10 h (15Y).
Effective surface density of soil.
240 kg/m2 .
3,600 = s/h conversion factor.
th Holdup time between 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 = 1 x 10 3 X14 ( 0 . 11 I 0 . 16 )
(1.11) where:
Concentration Df C-14 in vegetation.
µCi/kg.
Air concentration of C-14. µCi/m 3 .
0.11 Fraction of total plant mass that is
0 .16 =
natural carbon .
Concentration of3 natural carbon in the atmosphere. g/m .
11
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 lxl0 3 = g/kg conversion factor.
For determining the concentration of H-3 in vegetation:
CVT = 1x10 3 XT (0.75) (0.5/H)
(1 . 12) where:
Concentration of H-3 in vegetation. µCi/m 3 .
Air concentration of H-3. µCi/m 3 .
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.
H= Absolute humidity of the atmosphere. g/m3 )
lxl0 3 = g/kg conversion factor.
For determining the concentration of any nuclide in cow's or goat's milk:
CM; =CV; FM; Qf exp (-.A; tf) 0 .13) where:
Concentration of radionuclide i (including C-14 and H-3) in milk. µCi/£.
= Concentration of radionuclide in and on vegetation. µCi/kg.
Transfer factor from feed to milk for radionuclide i. die (Table 1.6).
= Amount of feed consumed by the milk animal per day. kg/d (cow. 50 kg/d or goat 6 kg/d).
.Ai = Radioactive decay 1coefficient of radionuclide i. d" .
Transport time of activity from feed to milk to receptor. 2 days.
For determining the organ dose rate from ingestion of ~
green leafy vegetables and milk:
12
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 D = 1 x 10 6 ~
l (1. 14) where:
0 Organ dose rate due to ingestion. mrem/y.
CM., Concentration of.radionuclide i in vegetables or milk. µCi/kg (or liters).
Ingestion dose factor. mrem/pCi (Table2.1).
UM Ingestion rate for milk. 330 fly; for vegetables 26 kg/yr (child). no ingestion by infant.
lx10 6 = pCi/µCi conversion factor.
d) Meat Ingestion (Beef)
To calculate the concentration of a nuclide in animal
flesh:
C1 ;
where:
= Ft; CV; 01; exp CA/s) 0 .15)
= Concentration of nuclide i in the animal flesh. pCi/kg.
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 1.10).
= Amount of feed consumed by the cow per day.
50 kg/d.
Average time from slaughter to consumption.
20 days .
13
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 To determine the organ dose from ingestion of beef:
Df = ~1 Cfi Dfi U f (1.16) where:
Ingestion dose factor for age group.
mrem/pCi (Table 2.1) for nuclide i.
Ingestion rate of meat for age group. kg/y (child-41. teen-65. adult-110).
e) Organ Dose Rates For.determining the total body and organ dose rate from iodines and particulates~
D = 01 + DG + OM + Dv + OF 0.17) where:
D = Total organ dose rate. mrem/y.
Dose rate due to inhalation. mrem/y.
Dose rate due to ground contamination.
mrem/y.
Dose rate due to milk ingestion. mrem/y.
Dose rate due to vegetable ingestion.
mrem/y.
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
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 C. Design Basis Quantities The design basis quantity of a radionuclide emitted to the atmosphere is the amount of that nuclide. when released in one year. which would result in a dose not exceeding any of the following:
1) 15 millirem to any organ of an individual from iodines and particulates with half-life greater than 8 days (Appendix A. Sectio~ III.D.l).
2) 15 millirem to skin of an individual from noble gas (Appendix A.Section III.C.l.b).
3) 5 millirem to the total body of an individual from noble gas (Appendix A.Section III.C.l.a).
Design basis quantity (Ci) is the smallest value for each nuclide. calculated by dividing the dose limits Ca 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 Ci/year): the result is then multiplied by the amount of
radionuclide used.
DBQ where:
=
D DAI (Cc) c 0.18)
DA 1 Appendix I dose limit Cmrem or mrad).
Dc Calculated dose (mrem or mrad).
= Quantity of nuclide resulting in dose Dc (Ci).
DBQ = Design Basis Quantity (Ci).
The limiting values for Design Basis Quantities for radionuclides released to the atmosphere are given in Table 1.9.
The inverse of the ratio C£/Dc in the above equation Cie. Dc/Cc) is a useful value. since i~ represents the most limiting dose per unit quantity of each nuclide released. Use of the Dc/Cc ratio in quarterly evaluation of offsite dose is discussea in Section D.. Values of Dc/Cc are given in Table 1.9 .
15
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
d. Land Use Census and DBO Changes Appendix A. Sections J.3.b and J.3.c describe the requirements for an annual land use census and revision of the ODCM for use in the following calendar year. Areas of the ODCM which will be reviewed. and changed if appropriate. are Table 1.4 (Land Use Census data by Sector). Table 1.4a (Critical Receptors).
and Table 1.9 (Gaseous Design Basis Objective Annual Quantities). Changes will be effective on January 1 of the year following the year ef the survey.
e. Gaseous Releases From the Steam Generator Blowdown Vent and Atmosphere Release Valves 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 steam generator
blowdown vent is normally routed to the main condenser and recirculated. Radioactive releases will be calculated by .
analyzing steam generator blowdown liquid and assuming that 100 percent of Noble Gases. 10 percent of the Iodines and 1 percent of the Particulates will be released to the environment ih the steam phase. Volumes will be released to the environment in
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 nuclide 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 (DBQ ) i < 1.0 (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
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
2. Continuous Releases Low level continuous releases from the vent gas collection header and other low level sources are totaled on a weekly basis and summed with any batch releases for the week in order to establish the cumulative DBQ fraction from batch plus continuous released for the year-to-date. Calculations are performed in the same manner as for batch releases described in C.1.
3. Exceeding DBQ Limits As discussed under B.1.3. the DBQ is a very conservative estimate of activity which could give doses at Appendix I limits. Because different organs are summed 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 accurate
~ssessment 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 al so Section D. 1. 2.
It should be noted that Palisades Plant to date {based on review of semiannual effluent data) has never exceeded the annual or quarterly DBQ fraction. despite its conservatism. Thus. 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 Radionuclides 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
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL D.
Revision 8 OPTIONAL QUARTERLY DOSE CALCULATIONS
1. Methodology for Optional Quarterly Dose Calculations This option may be used in place of. or in addition to. the 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 1.9 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 dose. If limits appear to be exceeded by this method. Section D.1.2 (a concise method. but requiring computer support) will be utilized.
1. Assumpti ans a) All assumptions of Section 1.1 are utilized.
b) Limiting doses for each gaseous nuclide are summed.
regardless of limiting decay mode (gamma or beta).
c) Limiting doses for each particulate and iodine nuclide ari summed. regardless of dose point location. exposure pathway or organ affected.
d) Doses are summed for detected nuclides such that all nuclides which contribute greater than 10%
individually or 25% in aggregate. *to the EC of released radioactivity. are included in the dose calculation.
18 J
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
2. Equations For determining gaseous effluent dose:
i DG "' L AiG(Dc/Cc)iG < 5 millirad/quarter, 10 mrad/
0 (1. 20) where:
DG Dose from gaseous effluents (mrad).
Quantity of gaseous nuclide i released (Ci).
Dose per Ci factor for gaseous nuclide (mrad/Ci).
The limit for this mixture is conservatively taken ~s 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 mi 11 i rem/ yea.r .
For determining tritium. particulate and iodine dose to organs:
DTPI =L i
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
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
b. Realistic Calculation This methodology is to be used if the highly conservative calculations described in C.1 or D.l yield values that appear to exceed applicabfa limits.
Doses for released particulates. iodines and noble gases will be determined by use of the NRC GASPAR computer code. The computer run will utilize the annual average joint frequency meteorological data based on not less than 3 years of meteorological measurement. and will reflect demographic and land use information from the land use survey generated in the most recent prior year. Where appropriate. seasonal adjustments will 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 significantly from mean annual conditions.
E.
GASEOUS RADWASTE TREATMENT SYSTEM OPERATION The gaseous radwaste treatment system CGRTS) 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 CODtrol 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 compressors 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
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
----------- 2. Determination of Satisfactory Operation Design basis quantity fraction will be calculated for batch and continuous releases as described in Section I.C. These calculations will be used to ensure that the GRTS is operating as designed.
Because the plant was designed to collect and hold for decay a vast majority of the high level gases generated within the primary system. and because the 13-year operating history (to date of writing the initial ODCM) 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 mrem/yr) 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 boundary as defined by Figure 1-1.) Concentrations at this level if present for on~
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. to assure a dependable source of
power even under unusual operating conditions. to release quantities of material higher than a small percentage of 10 CFR 20.1302 limits but still within those limits. Appendix I to 10 CFR 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 1.1.
The meteorology data is given in Table 1.3. Dose using annual average meteorology, to the most limiting organ of the person assume to be residing at the site boundary with highest X/Q. is 2.15E-02 mrem (for ohe 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 50/2.15E-02 or 0.11 Ci/sec .
21
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 G. PARTICULATE AND IODINE SAMPLING Particulate an iodine samples are obtained from the continuous sample stream pulled from the plant stack. Samples typically are obtained to represent an integrated release from a gas batch (waste gas decay tank or Containment purge. for ~xample). or a series of samples are obtained 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 significantly less than pre-release calculations indicate. This provides for conservatism in establishing setpoints and in estimation of pre-release design basis quantity fraction. 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 estim~tes. 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 "identified" 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 separated from a quarterly composite of filters) are obtained. Sampling and analysis will be performed per Appendix A. Table B-1 requirements.
H. NOBLE GAS SAMPLING Noble gases will be sampled from Waste Gas Decay Tanks prior to release and the Containment prior to purging. Analysis of these samples will be used for accountability of noble gases. Off gas will be.sampled at least weekly and used j:o calculate monthly noble gas releases. Nonroutine releases will be quantified from the stack noble gas monitor CRE 2326) which has a LLD of lE-06 µCi/cc. Sampling and analysis will be performed per Appendix A. Table 8-1 requirements.
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 reactor cavity.
J. FIGURES AND TABLES 22
PALISAD~S GASEOUS EFFLUENTS STA.Ck 1I
--e . .
WA..<;T£ GAS I SURGf TANk --' t.OBLE RE 11'3 RE 2320 GAS e T29 STEAM GENFRATOR BlOWOOWN T ANk VENT
. . . _.~ ATMOSPHERE
---.Jn LOWLEYEl HEPA GAS OOLLECTION-------"' . - - - - " " '
HE AO ER HEPA RE 0831 0
(/)
1-1 \ J
-I )>
rn r 0
0 1-1
(/)
)>
COft'DfNSf .. ;:o (/) 0 m rn rn OFF GAS (/)
< n
~--------, --'* )> :z Ul N
w I AUX '
1 HEPAIQtARC'OAL r c Bl DO 0 n n c r WF.ST SJ\f E SUPPLV L......111~J ~..._--------~
RAO-WA5TE AR RE 18C'9*
HEPA
l 00 s 1-1 0
rn
)>
o
\J GUARD RE 1811 :z s;:
3: :z HEPA (NOR¥All OONTAIN* )> -I FUf.l "E UJ17 :z SlJf'Pl Y HANDlG MENT c
)>
BLDG r AREA HEPA/CHARCOAL (RF,rUHINGI r---------,
HEPA. 1 FUEL ¢,
AREA lh--- SUi .*t V RE S7t 2 " AODIT "RE 11109. 5711 AN051t?TRIPSUl'f'l VANOONF Of r .. I) C:XHAUSTUS FLOW IS NOT TFRMINATEO PALISADES EFFLUENT FLOW PATHS GASEOUS
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 *

TABLE 1.1 PALISADES GASEOUS AND LIQUID SOURCE TERMS. CURIES/YEAR Cl)

Nuclide Gaseous(2) Liquid(2)
H-3 5.5 159 Kr-85 4.1 NA Kr-85m 0.12 NA Kr-87 8.4E-02 NA Kr-88 2. lE-:-01 NA Ar-41 3.lE-02 NA Xe-131m 2.2 NA Xe-133 1493 NA Xe-133m 0.43 NA Xe-135 1.11 NA Xe-135m 0.3 NA I-131 0.025 3.21E-03 I-132 2.91E-03 NA I-133 6.5E-03 4.7E-05 I-134 4.8E-04 NA I-135 1.84E-02 NA Na-24 1.5E-06 NA Cr-51 2.5E-04 3.9E-03 Mn-54 Co-57 Co-58 Fe-59 Co-60 Se-75
4. lE-04 2.lE-06 8.6E-04 6.6E-06 1.lE-03 3.7E-06 7.8E-03 3.2E-05 2.9E-02
4. lE-04 1.24E-02 NA Nb-95 2.4E-05 4.53E-04 Zr-95 4.7E-06 . 1. 79E-04 Mo-99 1.5E-07 NA Ru-103 .3E-07 .lE-05 Sb-127 NA 3.5E-05 Cs-134 4.SE-05 0.7 Cs-136 NA 1.8E-06 Cs-137 2.6E-04 1. 36E-02 Ba-140 2.8E-07 NA La-140 7.SE-07 1. lE-04 Unidentified beta . 3.9E-04 3.3E-03 Cl) Data derived from taking the effluents released during July-December 1978 through January-June 1982 and dividing by 4.
(2) Nuclide values listed as NA have not been observed at detectable levels in these waste streams.
24
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
Revision 8 TABLE 1.2 BASIC RADIONUCLIDE DATA NUCLIDE HALF-LIFE LAMBDA BETA 1 GAMMA 1 (days) 1ill.l (MEV/DIS) (MEV/DIS) 1 Tritium 4.49E 03 l.79E-09 5.68E-03 0.0 2 C-14 2.09E 06 3.84E-12 4.95E-02 0.0 3 N-13 6.94E-03 l.16E-03 4.91E-Ol 1. 02E 00 4 0-19 3.36E-04 2.39E-02 1. 02E 00 1. 05E 00 5 F-18 7.62E-02 l.05E-04 2 .50E-Ol 1. 02E 00 6 NA-24 6.33E-Ol 1. 27E-05 5.55E-Ol 4.12E 00 7 P-32 l.43E 01 5.61E-07 6.95E-Ol 0.0 8 AR-41 7.63E-02 l.05E-04 4.64E-01 1.28E 00 9 CR-51 2.78E 01 2.89E-07 3.86E-03 3.28E-02 10 MN-54 3.03E 02 2.65E-08 3.80E-03 8.36E-Ol 11 MN-56 l.07E-Ol 7.50E-05 8.29E-01 1. 69E 00 12 FE-59 4.50E 01 l.78E-07 l. lBE-01 1.19E 00 13 C0-58 7.13E 01 l.12E-07 3.41E-02 9.78E-01 14 C0-60 1. 92E 03 4.18E-09 9.68E-02 2.50E 00 '
15 ZN-69m 5.75E-Ol l.39E-05 2.21E-02 4.16E-Ol 16 ZN-69 3.96E-02 2.03E-04 3.19E-Ol 0.0 17 BR-84 2.21E-02 3.63E-04 1. 28E 00 1. 77E 00 18 BR-85 2.08E-03 3.86E-03 1. 04E 00 6.60E-02 19 KR-85m l.83E-01 4.38E-05 2.53E-Ol l.59E-Ol 20 KR-85 3.93E 03 2.04E-09 2.51E-Ol 2.21E-03 21 KR-87 5.28E-02 l.52E-04 1. 32E 00 7.93E-01 22 KR-88 l.17E-Ol 6.86E-05 3.61E-Ol 1. 96E 00 23 KR-89 2.21E-03 3.63E-03 1. 36E 00 1. 83E 00 24 RB-88 l.24E-02 6.47E-04 2.06E 00 6.26E-01 25 RB-89 l.07E-02 7.50E-04 1. OlE 00 2.05E-OO 26 SR-89 5;20E 01 1. 54E-07 5.83E-Ol 8.45E-05 27 SR-90 1. 03E 04 7. 79E-10 1. 96E-01 0.0 28 SR-91 4.03E-Ol 1.99E-05 6.50E-Ol 6.95E-01 29 SR-92 l.13E-Ol 7.lOE-05 1. 95E-Ol 1. 34E 00 30 SR-93 5.56E-03 l.44E-03 9.20E-Ol 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-01 33 Y-91 5.88E 01 l.36E-07 6.06E-Ol 3.61E-03 34 Y-92 l.47E-Ol 5.46E-05 1. 44E 00 2.50E-01 35 Y-93 4.29E-Ol l.87E-05 l.17E 00 8.94E-02 36 ZR-95 6.50E 01 l.23E-07 l.16E-Ol 7.35E-01 37 NB-95m 3.75E 00 2.14E-06 1.81E-Ol 6.06E-02 38 NB-95 3.50E 01 2.29E-07 4.44E-02 7.64E-Ol 39 M0-99 2.79E 00 2.87E-06 3.96E-Ol l.50E-Ol 40 TC-99m 2.50E-Ol 3.21E-05 l.56E-02 l.26E-Ol 41 TC-99 7.74E 07 1. 04E-13 8.46E-02 0.0 42 TC-104 l.25E-02 6.42E-04 l.60E 00 1. 95E 00 25
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 1.2 (continued}
BASIC RADIONUCLIDE DATA NUCLIDE HALF-LIFE LAMBDA BETA 1 GAMMA 1 (days) ilhl (MEV/DIS) (MEV/DIS) 43 RU-106 3.67E 02 2.19E-08 1. OlE-02 0.0 44 TE-132 3.24E 00 2.48E-06 l.OOE-01 2.33E-Ol 45 I-129 6.21E 09 1. 29E-15 5.43E-02 2.46E-02 46 I-131 8. 05E 00 9.96E-07 1.94E-01 3.81E-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 4.08E-01 6.02E-Ol 49 I-134 3.61E-02 2.22E-04 6.16E-Ol 2.59E 00 50 I-135 2.79E-01 2.87E-05 3.68E-01 1. 55E 00 51 XE-131m 1.18E 01 6.80E-07 1. 43E-01 2.0lE-02 52 XE-133m 2.26E 00 3.55E-06 1. 90E-01 4.15E-02 53 XE-133 5.27E 00 1.52E-06 1.35E-01 4.60E-02 54 XE-135m 1. 08E-02 7.43E-04 9.58E-02 4.32E-Ol 55 XE-135 3.83E-01 2.09E-05 3.17E-01 2.47E-01 56 XE-137 2. 71E 03 2.96E-03 1. 77E 00 1. 88E-01
57 XE-138 9.84E-03 8.15E-04 6.65E-01 1. lOE 00 58 CS-134 7.48E 02 1. 07E-08 1. 63E-01 1. 55E 00 59 60 61 62 63 64 CS-135 CS-136 CS-137 CS-138 BA-139 BA-140
1. lOE 09
1. 30E 01
1. lOE 04 2.24E-02 5.76E-02
1. 28E 01 7.29E-15 6.17E-07
7. 29E-10 3.58E-04
1. 39E-04 6.27E-07 5.63E-02 1.37E-01 L71E-01
1. 20E 00 8.96E-01 3.15E-01 0.0 2.15E 00 5.97E-01 2.30E 00 3.53E-02
1. 71E-01 65 LA-140 1. 68E 00 4. 77E-06 5.33E-01 2.31E 00 66 CE-144 2.84E 02 2.82E-08 9.13E-02 1.93E-02 67 PR-143 1. 36E 01 5.90E-07 3.14E-01 0.0 68 PR-144 1.20E-02 6.68E-04 1. 21E 00 3.lBE 00 1
Average energy per disintegration values were obtained from ICRP Publication No 38. Radionuclide Transformations: Energy and Intensity of Emissions 1983 and NUREG/CR-1413 CORNL/NUREG-70). a Radionuclide Decay Data Base - Index and Summary Table. DC Kocher. May 1980.
26
USNRC COMPUTER CODE - XOQ!>OQ, VERSION 2.0 RUN DATE: 93lll6
" .. PALISADES XOQDOQ82 ***h USING 01/01/88 - 12/31/92 MET DATA ...... .
'GROUND LEVEL RELEASE - TOP OF CONTAINMENT *BUILDING NO DECAY, UNDEPLETED ANNUAL AVERAGE CHl/0 (SEC/METER CUBED) DISTANCE IN HILES FROH THE SI d SECTOR D.250 D.500 0.750 1.000 1.500 2.000 2.500 3.00D 3. 500 4.000 4.!>00 s 3.673E-06 l.205E-06 6.540E-C7 4.310£-07 2.395E-07 1.586£-07 1.153£-07 8.895E-08 7.145E-08 5.913E-UB 5.00uf-08 SSW 3.0D6E-06 9.699E-07 5.193E-07 3.431£-07 l.919E-07 1.278£-07 9.340E-OB 7.233[-08 5.B30E-08 4.839E-D8 4.107E-08 SW 3.948E-06 l.259E-06 6.682E-07 4.392£-07 2.445E-07 l.634E-07 l.199E-D7 9.3D8E-08 7.522E-08 6.257f-08 5.321E-08 WSW 4.031E-06 l.259E-06 6.556[-07 4.287E-07 2.364E-07 l.606E-07 l.IB7E-07 9.277E-08 7.537E-08 6.298E-08 S.3/Bt-DB w 4.756E-06 J.492E-06 7.. 747E-07 5.051E-07 2.798E-07 1.880[-07 I.J87f-07 l.083£-07 6.786£-08 7.336E-08 6.259E-08 WNW NW 6.204E-06 8.165E-06 J.951E-06 Z.SZSE-06 1.016£-06 l.308E-06 6.622£-07 8.529E-07 3.665E-07 4.737E-07 2.462£-07 3.203[-07 l.816E-07 2.375E-07 1.417£-07 l.861E-07 l.ISOE-07 l.515f-07 9.601£-08 l.269E-07 8 192E-08 l.085E-07 .,,
0 NNW l.071E-05 3.285E-06 l.695E-06 1.103£-06 6.121E-07 4.150£-07 3.0BSE-07 2.423E-07 1.976£-07 l.657E-07 1.419£-07 N 1.093[-05 3.365E-06 1.747£-06 l.140E-06 6.340£-07 4.292E-07 3.186£-07 2.496£-07 2.035[-07 l.705E-07 1.459£-07 .....
_, ""O
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NKE 5.439[-06 1.724[-06 9.191E-07 6.049E-07 3.376£-07 2.262£-07 1.662£-07 l.293E-07 1.047[-07 8.716E-08 7.420£-06 rn I KE 5.177E-06 l.720E-06 9.375£-07 6.138£-07 3.376E-07 2.214E-07 l.598E-07 l.Z25E-07 9.786E-08 8.063E-08 6.799£-08 Cl
(/)
EKE 3.743E-06 l.218E-06 6.574£-07 4.293E-07 2.363£-07 l.551E-07 1.lZOE-07 8.590E-08 6.870£-08 5.664E-08 4.780E-06 0 )>
E 3.799E-06 l.264E-06 6.866£-07 4.471£-07 2.447£-07 1.597£-07 l.148E-07 8.770E-08 6.990E-08 5.746E-OB 4.836£-08 :;o (/) Cl ESE SE 3.960E-06 4.526[-06 1.323£-06 1.502£-06 7.133E-07 8.075E-07 4.626£-07 5.223£-07 2.519[-07 2.839£-07 1.640£-07 l.847E-07 l.177E-07 l.3Z5E-07 8.983E-08 l.OllE-07 7.152E-08 8.046£-08 5.814E-08 6.607£-08 4.940E-08 5.556E-08
)>
CD rn (/)
n rn SSE 5.087E-06 1.682£-06 9.073£-07 5.906E-07 3.ZJ3E-07 2.115£-07 J.5Z3E-07 l.166f-07 9.308£-08 7.663[-08 6.457E-OB OJ en )> :z I --'* I c:
rn 0 n n ANNUAL AVERAGE CHl/Q (SEC/METER CUBED) DISTANCE IN HILES FROM THE SITE ::I c: I
...... rn SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.DOO 40.000 45 000 5U,UOG w
CX> ~~
S 4.315E-08 Z.445[-08 l.639f-OB 9.379E-09 6.336E*09 4.682E-09 3.661£-09 2.976£-09 Z.48BE-09 2.126£-09 l.848E-09 0 ""O SSW 3.54BE-08 2.027E-08 l.367E-08 7.884E-09 S.355E-09 3.975E-09 3.119£-09 2.543E-09 2.132£-09 I.82SE-09 1.569£-09 :z s;:
SW WSW 4.606E-OB 4.671£-08 2.652E*08 2.726£-08 l.798E-08 1.045E-08 1.866E-08 l.099E-08 7.140(-09 5.323E-09 7.574£-09 5.686[*09 4.19ZE-09 4.503E-09 3.429[-09 3.701£-09 2.882£-09 3.124f-09 2.474£-092.159[-09 2.691E-09 2.356E-G9 3:' :z
)>
z W 5.434E-08 3.165E-08 2.164£.-08 l.27JE-08 8.170£-09 6.582£-09 5.ZlZE-09 4.283E-09 3.615£-09 3.114E-09 2.726E-09 c:
WNW 7.llOE-08 4.139E-D8 2.829E-OB 1.663£-08 1.145£-08 8.594£-09 6.604E-09 5.S89E-09 4.717E-09 4.063E-09 3.556E-09 )>
I NW 9.440£-08 5.540E-08 3.807£-08 Z.254£-08 1.560£-08 1.174£-0B 9.321E-09 7.674E-09 6.488[-09 5.598E~09 4.907£~09 NNW l.236E-07 1.285£-08 5.021£-08. 2.985E-08 2.071E-08 l.562E-08 l.242E-08 l.024E-08 8.668E-09 7.486E-09 6.568l-09 H l.270E-07 7.462E-08 5.132£-08 3.042E-08 2.106£-08 l.586E-OB l.259E-08 1.037[-08 8.770£*09 7.567f-09 6.634E-09 NNE 6.428£-08 3.712£-08 2.522E-06 l.470E-08 l.OOSE-06 7.~03[-09 5.914E-09 4.840E-09 4.07lE-09 3.496E-09 3.052E-09 NE 5.842E-08 3.272£-08 2.176£-08 l.232E-08 8.275£-09 6.088£-09 4.743E-09 3.844E-09 3.206f-09 2.734E*09 2.371f-09 ENE 4.l!OE-08 2.310E-08 1.540£-08 8.756E-09 5.900£-09 4.351£-09 3.396E-09 Z.759E-09 2.305£-09 1.968E*09 l.7l0E-09 E 4.148£-08 2.308E-08 1.526£-08 8.597E-OS 5.751E-09.4.218E-09 3.279£-09 2.653E-09 Z.209E-09 1.881£-09 l.630£-09 ESE 4.234E-08 2.351E-08 1.554£-08 B.734£-09 5.639£-09 4.281E-09 3.326E-09 Z.692£-09 2.242E-09 1.909f-09 l.654E-09 SE 4.763£-06 2.646E-08 1.750£-06 9.846[-09 6.589[-09 4.836£-09 3.76ZE-09 3.045£-09 2.538£*09 2.162t*09 1.875£-09 SSE 5.546£-08 3.102£-08 2.061£-08 1.166£-08 ].833£-09 5.764E-09 4.493E-09 3.643£-09 3.040E 09 2.592£*09 2.250f-09 VENT AND BUILDING PARAM[ TLRS:
RELlASE HEIGHT lHElfRS) 56. l 0 RtP. WIND HEIGHT (METER$) 10.0 DIAMETER (H(l[RS) 0.00 BUILDING HEIGHT (METERS) ~ll.l EXIT VELOCITY (METERS) 0.00 BLDG.HIN. CRS. SEC .ARfA . (SQ .ME HRS) 2000 0 HEAT EMISSION RATE * *.(CAL/SEC) 0.0 ALL GROUNU LEVEL RELEASES.
USNRC COMPUTER CODE - XOQOOQ, VERSION 2.0 RUN DATE: 931116
t* 1 ' PALISADES XOQIDQ82 '**** USING 01/01/88 ~ 12/31/92 MET OAf A*****
GROUND LEVEL RELEASE - TOP OF CUHJAINMENT BUILOING NO DECAY, UNDEPLETED 0
CHl/Q (SEC/METER CUllO) FOR EACH SEGMENT "'Tl
"'Tl SEGMENT BOUNDARl£S [N NILES FROM THE SITE (/)
1-4 ""'C
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-i DIRECTION .5-l 1-2 2-3 3-4 4-5 5-10 10*20 20-30 30-40 40-50 rn r 1-4 Cl (/)
FROM SITE ;:o 0 )>
(/) Cl s 6.773f-07 *2.461£-07 1.163£-07 7.l76E-08 5.019£*08 2.503E*08 9.585E-09 4.714£-09 2.986[-09 2.130£-09 -i
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...... ("")
rn rn (/)
N co SSW 5.4UE-07 l.970f-07 9.415E-08 5.853E~oa 4.117£-08 2.072E-08 8.046E~09 4.000E-09. 2.551E-09 l. 829[-09 CD r
(/)
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rn SW 6.978E-07 Z.517£-07 1.208£-07 7.550E-08 5.334E-08 2.707£-08 l.065E-08 5.355£-09 3.439[-09 lo 478[ *09 0
J c r rn
~~
t-'
WSW 6.889E-07 Z.461E-07 1.195E-07 7.562E-08 5.389E-08 2.776E-08 l. ll7E-08 5. 716[ *09 3. 710E-09 2. 695£-09 w CD 1-4 w 8.142E-07 2.891E-07 l.397E-07 8.817E-08 6.273E-08 3.224E-08 l .295E-08 6.618E*09 4.294E-09 3.119[-09 0
z

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WHW l.067E*06
3.787E-07 1.829E-07 1.154E*07 8.209E-08 4.217E-08 1.692£-08 B.640E.;09 5.604E-09 4.069E-09 3:
)>
z

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z

NW l .376E-06 4.898£-07 Z.390£-07 . 1. 52DE*07 l.087E-07 5.636E-08 2.291£-08 1.180£-08. 7.693E-09 ~.606[-09 c
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1.510[-08 r NNW l.785E-06 6.336£-07 3.104E-07 1.982£-07 l.422f*07 7.407E-08 3.031£-08 1.026[*08 7.496£-09 N 1.837£-06 6.554£-07 J.206E*07 2.042E-07 l.462E*07 7.590E*08 3.090£-08 1. 594[-08 1. 040£ *OB 7.578£-09 NNE 9.584E-07 3.47SE*07 l.675E*07 l.OSOE-07 7.437£-08 3.787E-08 1.497£-08 7.548£-09 4.854£-09 3.502£-09 NE 9. 675E-07 3.473£-07 1.613[*07 9.632£-08 6.819£-08 3.356E-08 LZ62E-08 6.133E-09 3.BSBE-09 2.739£-09 ENE 6.805E-07 2.431£-07 1.130[-07 6.902[-08 4.794E-08 2.368f-08 . 8. 965£ -09 4.383£-09 . 2.769E-09 1. 972E-09 E 1. 085£-07 2.519E-07 1.159[-07 7.025£-08 4.BSOE-08 2.370[-08 8.817[*09 4.251E-09 2. fi63E-09 l. 885[-09 ESE 7.373E-07 2.597E-07 l.169E-07 7' 188£-06 4.955E-08 l.415E-08 8.960£-09 4.315£-09 2. 70(f-09 1.913[-09 SE 8.350E-07 2.928E-07 1. 338£-07 8.087E-06 5.574£-08 2.718E-08
l.OlOE-08 4.874£-09 3.057E-09 2' 167[-09 SSE 9.387E-07 3.330E-07 1. 53BE-07 9.353E-08 6.477£-08 3.182E-08 1)95~-08 5.807E-09 .3.656E-09 2.598[-09
USNRC COMPUTER CODE - XOQDOQ, VERSION 2.0 RUN DATE: 931116
PAL1SAD£s*xoQOOQ82 **a** USING 01/01/86 - 12/31/92 MET DATA *****
GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDlNG 2.260 DAY DECAY, UNDEPLETED ANNUAL AVERA6E CHl/Q (SEC/METER CUBED) DISTANCE IN HILES FROM THE; SITE SECTOR 0.250 0.500 0.750 1.000 1.500 2.000 Z.500 3.000 3.500 4 000 4.!>00 s 3.67DE-D6 1.203f-06 6.522E-07 4.294E-07 2.382£-07 l.574E-07 l.143[-07 8.798[-06 7 .055E-08 5 828E-08 4 9Z5f-O!!
SSW 3.003£-06 9.680f-07 S.177E-07 3.418E-07 1.907£-07 l.268E-07 9.249£-08 7.148£-06 5.750E-08 4.763E-08 4 035E-0!!
SW 3.943E-06 1.256£-06 6.658E-07 4.371E-07 2.428£-07 l-61BE-07 l.184E-07 9.174E-OB 7.396E-08 6.137£-08 5.207£-08 WSW 4.D27E-06 1.256[-06 6.536E-07 4.269E-07 2.368[-07 l.592E-07 1 .174E-07 9.160£-08 7.426E-OB 6.J92E-08 5.277£-08 w 4.752E-06 1.489£-06 7.7Z4E-07 5.03lf-07 2.781£-07 1.865£-07 1.373E-07 l.OJOE-07 B.663E-08 7.218E-08 6.J47E-08 6.l99E-06 1.948£-06 l.013E-06 6.S99E-07 3.646E-07 2.445E-07 l.801E-07 l.403E-07 l.136E-07 9.469E-08 8.065[-08 WNW NW 8.l58E-06 Z.52lf-D6 1.304E-06 8.500E-07 4.71ZE-07 3.180£-07 2.354E-07 1.842[-07 1.497E-0/ l.251E-0/ l.068E-07 .,
0 NNW l.070E-05 3.Z80E-D6 1.690E-06 l.099E-06 6.090E-07 4.1Z2E-07 3.060E-07 Z.399[-07 1954E-07 l.636E-07 l.399E-07 (/)
N l.092E-o5* 3.359£-06 1.742E-06 1.136£-06 6.307[-07 4.262E-07 3.158E-07 2.473[-07 2.0llE-07 l.682E-07 l.437E-07 ~ "'tJ
MNE 5.,34E-06 1.721£-06 9.167[-07 6.028[-07 3.358E-07 2.246E-07 1.648[-07 l.280E-07 l.034E-07 8.597E-OB 7.307E-OB - j )>
IT1 r NE 5.l73E-06 l.717f-06 9.353E-07 6.119£-07 3.360£-07 2.20DE-07 l.585E-07 l.213E-07 9 677[-08 7.960E-08 6.102f-08 ~
ENE 3.740[-06 1.215£-06 6.557E-07 4.278E-07 2.350£-07 l.540E-07 l.llOE-07 8.498E-08 6.784E-08 5.583(-08 4.703E-08 Cl (/)
0 )>
E 3.796£-06 1.262£-06 6.848£-07 4.456[-07 2.434£-07 1.586£-07 l.138E-07 8.679E-08 6.905E-08 5.666[-0B 4.760(-08 ;:o (/) Cl ESE 3.957£-06 1.321E-06 7.JIBE-07 4.613E-07 2.509[-07 l.631£-07 1.169£-07 8.905E-08 7.080E-08 5.806E-OB 4.875E-Oll <D IT1 IT1
(/)
. SE 4.523£-06 l.499E-06 8.056£-07 5.207[-07 2.826E-07 l.835E-07 l.31SE-07 l.OOlE-07 7.958E-08 6.525f*08 5 478[-08 <
SSE 5.082[-06 1.679E-06 9_05lf-07 5.887E-07 3.217E-07 2.lOOE-07 1.510£-07 1.154E-07 9.198[-08 7.559£-0B 6 359E-OB ~
OJ en 0
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l..O r -'*
0 0 IT1 0 c: r .
A~NUAL
SECTIR S
AVERAGE CHI/Q (SEC/HETER CUBED) 5.000 4.ZJllE-08 7.500 2.380E-08 10.000 L582E-08 15.000 8.891i£-09 DISTANCE IN MILES FRON Tli£ SITE 20.000 5.911E-09 25.000 4.299E-09 30.000 3.310[-09 35.000 Z.650E-09 40.000 Z.183E-09 45.000 l.838E-09 50.000 l.575E-09 w
I 00 s
~
0 IT1
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o
"'tJ SSW SW 3.419E-08 4.496E-08 1.969E-08 Z.558E-08 l.315E-08 1.71SE-08 7.447E-09 9.751E-09 4.969E-09 6.SZlE-09 3.625E-09 4.763E-09 2.797E-09 3.679E-09 2.243£-09 2.952E-09 l.850E-09 2.436E-09 l.560E-09 2.055E-09 l.337E-09 l.762E-09 z s;:
3: z WSW 4.574E-08 Z.641E-08 1.789[-08 l.033E-06 6.9116E-09 5.l47E-09 4.004[-09 3.Z33E-09 2.68ZE-09 2.272E-09 1.95/t-09 )> - j W S.325E-08 3.071E-08 2.080£-08 1.201E-08 8.125£-09 5.992E-09 4.666E*09 3.771E-09 3.132E-09 2.656E-09 2.289£-09 z c:
WNW 6.98BE-08 4.033[-08 2.733E-08 1.581E-08 l.07ZE-08 7.915E-09 6.172E-09 4.996£-09 4.155E-09 3.526£-09 3.045£-09 )>
11\1 9.278E-08 5.399£-08 3.679[-08 2.143£-08 1.459[-08 1.082[-08 B.459E-09 6.862E-09 5.71BE-09 4.863E-09 4.204[-09 r NNW . l.216E-07 7.lllE-08 4.863[-DB 2.848E-08 l.947E-08 1.448E-08 1.135E-08 9.233E-09 7.lllE-09 6.S72E-09 5.69ZE-09 H 1.248[-07 7.274£-08 4.963£-08 2.895[-08 1.973£-08 l.464E-08 l.14SE-08 9.294£-09 7.74BE-09 6.593£-09 5.700E-09 NHE 6.319E-08 3.619E-08 2.439E-08 1.400£-08 9.430E-09 6.934E-09 5.388E-09 4.347£-09 3.606£-09 3.055E-09 2.632E-09 NE 5.749E-08 3.195£-08 2.108[-08 l.175E-08 7.778E-09 5.641E-09 4.334E-09 3.465E-09 2.852£-09 2.400[-09 2.05SE-09 ENE. 4.D36E-08 2.249£-08 l.486E-OB 8.30BE-09 5.505E-09 3.996E-09 3.073[-09 2 458£-09 2.023£-09 l.703(-09 1.459£-09 E 4.076E-08 2.248E-08 1.476E-OB 8.lGBE-09 5.376E-09 3.8B2E-09 2.972E-09 2.369E*09 1.944£-09 1.631[-09 1.394£-09 ESE 4.173E-08 Z.JOOE-08 LSlOE-08 8.361E-09 5.510E-09 3.9B5E-09 3.055E-O!I 2.438£-09 2.00JE-09 l.6113[ 09 1.440[-09 SE 4.688E-08 2.584E-08 1.697[-08 9.401E-09 6.ZOOE-09 4.486E-09 3.442E-09 2.749E-09 2.261£-09 1.901£-09 l.627f-09 SSE 5.452E-08 3.023E-08 1.992[-08 l.l09E-OB 7.331E-09 5.313E-09 4.079E-09 3.259E-09 2.661E-09 2.255£-09 1.930[-09 VENT AND BUILDING PARAMETERS:
RELEASE.HEIGHT (METERS) 56 10 REP. WIND HEIGHT (METERS) 10.0 DIAMETER (HETfRS) 0.00 BUILDING HEIGHT* (METERS) 58. 1 EXll VHOCl IY (H.C llRS) 0 00 BLOG.MIN CAS SEC.AREA (SQ.METERS) 2000 .0 lt[AT EMISSION RATf .. (CAL/Sft:) 0.0 AIL GHUUKO.LEVEL RELEASES.
USNRC COMPUTER CODE - XOQDOQ, VERSION 2.0 RUN DATE: 931116
~ PALISADES XOQDOQ82 ***** USING 01/01/88 - 12/31/92 MET DATA *****
GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING 2.260 DAY DECAY, UNDEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT ,,
0 SEGMENT BOUNDARIES IN MILES FROM THE SITE (/1
...... ""O DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 --i l'Tl
)>
r......
FROM SITE 0 0
(/1
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s 6.755E-07 2.448E-07 l.153E-07 7.085E-08 4.938E-08 2.438£-08 9.107E-09 4. 333£-09. 2.661E-09 1.843£-09 ;;o m
(/1 0 l'Tl l'Tl
(/1 SSW 5.396£-07 l.959E-07 9.323[-08 5.773E-08 4.045E-08 2.014[-08 7.613£-09 3.652£-09 2251E-09 1. 563[-09 );! <
('")
)> :z w
0 SW 6.954E-07 2.SOOE-07 1.193E-07 7.424£-08 5.219E-08 2.614E-08 9.960E-09 4.798E-09 2.963E-09 2.059£-09 CXJ r
l'Tl Ul 0
r c
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WSW 6.868£-07 2.446E-07 l.183E-07 7.451E-08 5.288E-08 2.692E-08 1. 053£-08*. 5.180£-09 3243£-09 . 2.277£-09 I-' :::I l'Tl w 8.118£-07 2.874E-07 1.383[*07 8.693£-08 6. lSOE-08 3.132[-08 l.224E-08 6.030£-09 3183£-09 2.661£-09 w co ~ ;;o
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0 ""O WNW l.064E-06 3.768£-07 1.813£-07 1.140£-07 8.082E-08 4. 112[-08 1.611E-08 7.965£-09 5.012E-09 3.535£-09 :z
~
l .088E-08 :z NW l.373E-06 4.873[*07 2.370[*07 1.502£-07 l .070E-07 5.496E-08 Z. lBlE-08 6B83£-09 4.872£-09 3:
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1.472£-08 r N l.832E-06 6.521E-07 *3 .178£-07 2.018£-07 1.440£-07 7.404E-08 Z.945E-08 9322E-09 6.604£-09 NNE 9.560E-07 3.457£-07 1.660[-07 1.038£-07 7.323E-08 3.695[-08 1.428£-08 6.981£-09 4J62E-09 3.062£-09 NE 9.653E-07 3.458E-07 l.600E-07 9.723E-08 6.722E-08 3.280[-08 l.206E-08 5.688E-09 3.480£-09 2.406£-09 ENE 6.788£-07 2.418E-07 1.120E-07 6.816£-08 4.717E-08 2.307E-08 8.519E-09 4.029E-09 2.468£-09 1. 707E-09 E 7.067E-07 2.507£-07 l.149E-07 6.940£-08 4.775E-08 2.311[-08 8.392E-09 3. 917£-09 2379E-09 1. 636£-09 ESE 7.358E-07 2.586E-07 l .l81E-07
7.116E-08 4.891E-08 2.365£-08 8.591E-09 4.020E-09 2.449E-09 1.688£-09 SE 8.331E-07 2.915[-07 l.328E-07 7.999£-08 5.496E-08 2.657£-08 9.659E-09 4.525E-09 2J61E-09 l. 906E-09 SSE 9.365E-07 3.314£-07 1. 525E -07 9.243£-08 6.379£-08 3.105£-08 . 1.138£-08 5.358£-09 3273E-09 2.261£-09
USNRC COMPUTER CODE - XOQDOQ. VERSION 2.0 RUN DATE: 931116*
PALISADES XOQDOQ62 ***** USING 01/01/88 - 12/31/92 MET DATA *****
GROUND LEVEL RELEASE - TOP Of CONTAINMENT BUILDING 8.000 DAY DECAY, DEPLETED ANNUAL AVERAGE CHl/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SJTE SECTOR 0.2&0 o:soo 0.750 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4 500 s . 3.476E-06 1.lOOE-0.6 5.823£-Qj 3.769£-07 2.031E-07 1.310£-07 9.318E-OB 7,043E-OB 5.555E-OB 4.521E-08 3.767l**08 SSW 2.844E-06 8.852£-07 4.623£-07 3.000£-07 1.627£-07 1.056£-07 7.545£-0B 5.726E-08 4.531E-OB 3.69Bf-083.089E-08 SW 3.735£-06 1.149£-06 5.949£-07 3.839£-07 2.073£-07 l.349E-07 9.675£-08 7.363f-M 5.841£:08 4.777E-083.998E-OB WSW 3.814£-06 1.149£-06 5.837£-07 3.748£-07 2.021£-07 l.327E-07 9.586£-08 7.342£-08 5.856£-08 4.Bllf *084.044f*08 w 4.500£-06 1.361£-06 6.898£-07 4.416£-07 2.372£-07 1.553£-07 1.120£-07 8.570E-08 6.828£-08 5.605E-084.708E-08 WllW 5.870£-06 1.781£-06 9.048£-07 S.791£-07 3.108E-07 2.035E-07 l.468E-Di l.123E-07 6.943£-08 7.341E-086.166E-08 C>
NW 7.726E-06 1.014£-05 2.305£-06 2.999£-06 1.164[-06 l.509[-06 7.459f-07 9.646£-07 4.017£-07 5.191£-07 2.647E-07 3.430£-07 l.919E-07 2.493E-D7 1.474E-07 1.919E-07 l.178E-07 1.537£-07 9.iOOE-088.168E708 l.267E-07 1.069£-07 "Tl NIN VI 1--i ""O N 1.034E-05 3.072£-06 1.555£-06 9.970£-07 5.376£-07 3.547£-07 Z.574£-07 1.979£-07 l.583E-07 l.304E-07 l.098E-07 -i )>
NNE 5.146£-06 1.574£-06 8.1B4E-07 5.290[-07 Z.863E-07 l.B69E-07 1.343£-07 1.024£-07 B.138E-08 6.665E-06 5.586£-0B rn 1--i r
NE 4.899£-08 l.570E-06 8.349E-07 5.368[-07 2.864E-D7 1.830E-07 l.291E-07 9.700E-OB 7.611E-08 6.167£-085.lZOE-08 0 VI EllE 3.542E-D6 1.lllE-06 5.854E-07 3.754£-07 2.004E-07 1.281£-07 9.048E-OB 6.802£-08 5.341£-08 4.330£-08 3.597E-08 C> )>
E 3.595£-06 l.lS4E-06 6.114E-07 3.910[-07 Z.075E-07 l.JZOE-07 9.275£-0B 6.945E-08 5.435E-OB *.393[-083.640[-0B ;;o VI 0 3.747E*06 l.ZOSE-06 6.353E-07 4.046E-07 Z.137E-07 1.356£-07 9.516E-OB 7.llBE-08 5.564E-08 4.494E-083.72LE-08 Cl> rn rn ESE < VI SE 4.283E-06 1.371£*06 7.l!llE-07 4.568£-07 2.408£-07 1.527£-07 1.071£-07 B.007£-08 6.259E-08 5.054f-084 184E-OB );! -'*
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)> :z w SSE 4.813E-06 1.535£-06 8.080£-07 5.165£-07 2.742£-07 l.748E-07 1.231£-07 9.Z35E-08 7.239£-08 5.659E-084.861E-OB OJ (/I r c:
I--' r -'* (""') (")
rn 0 c: r ANNUAL AVERAGE CHC/Q (SEC/METER CUBED) DISTANCE IN MILES FROM TttE SITE ::::I rn
~~
15.000 20,000 25.000 30.000 35.000 40.000 45.000 50 000 SECTOR 5.000. 7.500 10.000 00 w 1--i S 3.ZOOE-08 1.JlOE-08 1.090E-08 5.742E-09 3.625E-09 2.5Z5E-09 1.673£-.09 l.450E-09 l. I59E-09 9.490E-10 7 .920E-10 C> ""O SSW 2.630£-08 1.417£-08 9.082£-09 4.821£-09 3.059£-09 2.139£-09 l.591E-09 l.235E-09 9.896£-10 8.116f-10 6.766f-10 :z s;
z SW 3.410E-D8 l.850E-08 L.191E~08 6.366£-09 4.057E-09 2.847£-09 2.123E-09 l.652E-09 l.325E-09 1.086£-09 9.109£-10 3:
WSW 3.461£-08 1.904£-08 1.238[-08 6.709£-09 4.318£-09 3.053E-09 2.292E-09 l.79Zf-09 1.445£-09 l.l92f-09 l.OUl[-09
)> -i
z W 4.D27E-08 2.212£-08 1.437£-08 7.7BDE-09 5.007E-09 3.541£-09 2.658£-09 2.079£-09 1.677£-09 l.384E-09 l.163£-09 c:
)>
WNW 5.274£-08 Z.89tiE-08 l.88ZE-08 1.019£-08 6.559£-09 4.640E-09 3.484E-09 Z.727£-09 Z.ZOOE-09 l.616E-09 1.527£-09 r NW 7.00ZE-08 3.876E-OB Z.532£-08 l.381E-08 8.931E-09 6.340E-09 4.775£-09 3.745E-09 3.027£-09 Z.503E-09 2.106£-09 NNW 9.171£-08 S.lOOE-08 3.342£-08 1.831£-08 l.L8BE-08 B.451E-09 6.377£-09 5.0llE-09 4.057£-09 3.359E-09 2.832E*09 N 9.420£-08 5.22ZE-08 3.41SE-08 l.864£-08 l.Z07E-08 8.569£*09 6.456£-09 5.066E-09 4.096E-09 3.368£-09 2.854f 09 HNE 4.768E-08 Z.598E-08 1.678£-08 9.009E-09 S.76ZE-09 4.056£-09 3.033£-09 2.366E-09 l.903E-09 l.567f-09 l.314E-09 NE 4.335E-08 2.291E-08 1.449£-08 7.557£-09 4.744£-09 3.292£-09 2.434£-09 l.BBOE-09 l.499E-09 l.~25£-09 l.021E-09 ENE 3;048E-08 1.616£-08 l.024£-08 5.362£-09 3.375E-09 2.347E-09 1.738£-09 1.344£-09 l.073E-09 8.783E-10 7.327E-10 E 3.076E-08 l.615£-08 l.Ol6E-08 5.26SE-09 3.292E-09 2.27lE-09 l.679E-09 1.294[-09 1.030£-09 8.403E-LD 6.992£-10 ESE 3.143E-08 l.647E-08 L.036E-08 5.362E-09 3.352E-09 Z.319E-09 1.711£-09 l.319E-09 l.051£-09 8.58lf-10 7.145E-10 SE 3.534£-08 l.85JE-08 l.165E-08 6.040E-09 3.779E-09 2.616E-09 1.931£-09 1.490E-09 l.18BE-09 9./0Jl-10 B.083r-1D SSE 4.114E-.08 Z.171E-08 1.371E-08 7 .146E-09 4.485E-09 3.llZE-09 Z.JOlE-09 1. 777£-09 l .41BE*09 l. l59[-09 9.660E-IO VENT AND BUILDING PARAMETERS:
RELEASE HEIGHT (METERS) 56.10 REP. WINO HEIGHT (METERS) 10.0 DliUIETER (METERS) 0.00 BUILDING UEIGHT (HEHRS) Sil l
[XIT VELOCITY (METERS) 0.00 DLDG.MlN.CRS.SfC.AREA (SQ.HfTER~) 7000.0 HlAT EMlSSIDM RATE. (CAL/SEC) a.a ALL GROUND LEVEL RELEASES.
USNRC COMPUTER CODE - XOQDOQ. VERSION 2.0 RUN DATE: 931116
PALISADES XOQDOQ82 ***** USING 01/01/88
12/31/92 MET DATA 00 GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING 8.000 DAY DECAY1 DEPLETED CHl/O (SEC/HETER CUBED) FOR EACH SEGMENT .,,0 SEGMENT BOUNDARIES IN MILES FROM THE SITE (/)
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DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 IT1 r CJ (/)
FR~ SITE 0
(/)
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CJ s 6.060[*07 2.097E-07 9.418E-08 5.586E-08 3.780E-08 1.766£-08 5.947E-09 2. 557E-09 1.460E-09 9.531[-10
~
o
<D IT1 IT1
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(/)
w SSW 4.842E~07 1.678E-07 7.621E-08 4.555[-08 3.099E-08 l.46DE-08 4.985E-09 2.165[-09 l. 243E-09 8.151£-10 OJr VI
)>
r c:
z:
N (") (")
SW 6.243E-07 2.144[-07 9.769E-08 5.870f-08 4.OllE-08 l.904E-08 6.573f-09 2.880E-09 1. 662E-09 l.093E-09 IT1 0 c: r WSW N
6.165E-07 2.096E*07 7.287E-07 2.46ZE*07 9.670£*08 1.130E*07 S.883E-08 6.860E-08 4.056E-08 1.954E-08 6.907E-09 4.72ZE-08 Z.Z7lf-08 6.012E-09 3.086E-09 1.803[-09 3.578E-09 2.091E-09 1.196£-09 l.389E-09 1--'
w
l CX> s 0
IT1
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o
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z:
~
WNW 9.547E-07 3.227E-07 l.481E-07 B.985£-08 6.18~[-08 2.974f-08 1.049E-08 4.689E-09 2.743E-09 1.823£-09 ::3:
. )> ~
z:
z:
NW 1. 232E-06 4.173E-07 1.935E-07 1.183£~07 8.19DE-08 3.974[-08 l .420Ew08 6.405£-09 3.766E-09 2.512£-09 c:
)>
NIW l.596E-06 5.398[-07 2.S13E-07 l.543E-07 1.071E-07 5.223f *08 l.661E-08 8.535£-09 5.038[*09 3.371[-09 . r N l.644E-06 5.584E-07 2.595E-07
l .590E-07 1.101£-07 5.351£-08 1. 916E-08 8.656£-09 5.094E-09 3.400E-09 NNE 8. 577E-07 2.960E-07 1:356E-07 8.178E-06 5.603£-08 2.671E-08 9.293E-09 4.102E-09 2.380[-09 1. 573f-09 NE 8.657[-07 2.961E-07 l .306E-07
7.658E-OB 5.139E-08 2.371E-08 7.847E-09 3.336E-09 l.893E-09 l.23lf-09 ENE 6.089E-07 2.072E-D7 9.154£-08 5.373£-06 3.611E-08 l.671E-09 5.563E-09 2.377E-09 l.353E-09 8.822£-10 E 6.340[-07 2.147E-07 9.389E-08 5.470£-08 3.654[-08 1.673E-08 5.476E-09 2.308E-09 1.303[-09 8.442£-10 ESE 6.599E-07 2.214E-07 9.635£-08 5.600E-08 3.736[-08 l.708E-08 5.579E-09 2.351£-09 1.329£-09 B. 62DE-10 SE 7.473E-07 2.496E-07 l.084£-07 6.299£-08 4.201[-08 l.92 IE-08 6.282£-09 2.652E-09 l.501E-09 9.747E-10 SSE 8.400E-07 2.838E-D7 1. 246E-07 7.284E-08 4.8BOE-08 2.247£-08 l.423£-09 3.154E-09 . l, 790£-09 l.164E-09
USNRC COHPUTfR CODE - XOQDOQ, llERS ION 2. O RUN DAfE: 931116
PALISADES XOQDOQ62 ***** USING 01/01/88 - 12/31/92 MET DATA *****
GROUND LEVEL R£LEASE - TOP OF CONTAINMENT OUILDING 11 n* 1"'1111111 -*****"***11*-" RELATIVE DEPOSJTJON PER UNIT AREA (M 1111 -2} AT FIXED POINTS BV OOWNWINO SECTORS *uu*uu .. u"u*u*
DIRECTIOH DISTANCES IN MILES FROM SITE 0.25 0.50
0.75 1.00 1.50 2.00 2.50 3.00 3.50 4.00 4.50 S 2.434E-08 8.230E-09 4.226£-09 2.595£-09 1.294£-09 7.845E-10 5.304£-10 3.844[-10 2.923E-10 2.303E-10 I.864E-10 SSW l.655E-08 5.596E-09 2.873£-09 l.764E-09 8.795E-10 5.334E-10 3.607E-10 2.614[-10 1.987(-10 l .566E-10 l.267E-10 SW 1.921E-08 6.497E-09 3.336E-09 2.048E-09 1.021E-09 6.193E-10 4.187E*10 3.034E-10 2.307E-10 l.818E-l0 l.4/2E-1D WSW 1.BOSE-08 6.-105£-09 3.135£-09 l.925E-09 9.596£-10 5.820£-10 3.935£-10 2.851E-10 2.158E-10 1.708£-10 l.383E-10 W 2.905£~10 WNW 2.419E-08 3.615E-08 8.181£-09 1.222E-08 4.200£-09 6.277£-09 2.579E-09 3.854E-09 1.286£-09 l.921E-09 7.799£-10 l.165E-09 5.273E-10 7.879E-1D 3.821£-10 5.710E-10 4.341E-10 2.289£-10 3.420E-10 l.853E-10 2.769E-10 .,,
C>
NW 4.298E*08 1.454E-08 7.463E-09 4.583E-09 2.285E-09 l.386E-09 9.369E-10 6.789£-10 5.152E-l0 4.067E-10 3.292E-l0 (/)
1-1 -0 NNW 5.435[ *08 1.838E-08 9.436E-09 5. 794E-09 2.889E-09 1. 752E-09 1.185E-09 8. 584£-10 6. 527£-10 5. l42E-10 4.163£-10 -I )>
N 4.898[*08 1.656£-08 8.504E-09 5.222£-09 2.603E-09 1.579E-09 1.067£-09 7.735E-10 S.882E-l0 4.634E-10 3.751E-10 rn 1-1 r
CJ (/)
NNE 2.933E-08 9.919E-09 5.093E-09 3.127E-09 1.559£-09 9.456E-10 6.393E-10 4.633£-10 3.523£-10 2.775£-10 2.247E-l0 0 )>
NE 4.672£-08 1.SBOE-08 8.112E*09 4.981E-09 2.483E-09 1.506E-09 l.DlBE-09 7.379E-10 5.611E-10 4.420E-10 3.578E-l0 ;o (/) CJ rn rn (/)
CD ENE 3.456E*08 l.169E-08 6.000E-09 3.684f-09 1.837£-09 1.114£-09 7.532E-10 5.458E-l0 4.150E-10 3.270f-IO 2.647E-10 -I <
E 3. 701[ *08 l.251E-.08 6.425£-09 3.945E-09 l. 967£-09 l.193E-09 8. 065£-10 5. 844E-10 4 .444£ - ID 3. SOlE-10 2. 834£-10 )> ...... n
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...... r c w ESE 4.171£-08 l.410E-08 7.242£-09 4.447£-09 2.217E-09 1.345£-09 9.091[-10 6.588E-10 5.009E-l0 3.946(-10 3.195[*10 r n n rn 0 c r SE SSE 5.332E*08 5.156£-08 1.803£-08 1.743£-08 9.258£-09 8.951£-09 5.685£-09 5.496£-09 2.834£-09 2.740£-09 1.719£-09 1.662£-09 DISTANCES IN MILES 1.162£-09 l.124E-09 8.421£-10 6.142£-10 6.404E-10 6.191E-10 5.045£-10 4.878E-10 4.084£-10 3.949[-10 ......
w.
l
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s 1-1 0
rn
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o
-0 DIRECTION :z FROM SITE 5.00 7.50 10.00 15.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 ::3:
~
z s I.5.2E-10 7.556E-ll 4.741£-11 2.396E-ll 1.450£-11 9.725£-12 6.968E-12 5.233£-12 4.0!XIE-12 3.250E-12 2.653E-12 )>
z
-I
. SSW 1.048E-10 5.l38E-ll 3.224£-11 l.629E-ll 9.862E-12 6.613£-12 4.738f-12 3.558E-12 2.766E-12 2.210E-12 1.804£-12 c SW '1.217£-10 5.965£-11 3.743E-11 1.892£-11 l.145E-ll 7.677£-12 5.SOIE-12 4.131£-12 3.212E-12 2.566E-12 2.094E-12 ,.
)>
WSW 1.144[-10 5.605E-ll 3.517E-ll l.778E-ll 1.076£-11 7.214E-12 5.169f-12 3.882E-12 3.018E-12 2".411E-12 1.968E-l2 w l.533E-10 7.SllE-11 4.713E-11 2.38ZE-ll 1.442E-11 9.667E-1Z 6.927E-12 .5.201E-12 4.044£-12 3.231£-12 2.637E-12 WNW 2.290£-10 1.122£-10 7.043E-11 3.560£-11 2.155E-ll l.445E-11 1.035£-11 7.773E-12 6.D43E-12 4.827E-12 S.940£-12 NW 2.723E-10 1.335E-10 8.374E-11 4.233E-11 Z.562E-11 1.718E-ll 1.231£-11 9.242E-1Z 7.166[*12 5.740£-12 4.685E-12 NNW 3.443£-10 1.687£-10 1.059£-10 5.352E-11 3.239E-11 2.172E-ll l,556E-ll l.169E-ll 9.086£-12 7.258E-12 5.924£-12 N 3.103E-10 l.521E-10 9.542E-11 4.823E-ll 2.919E-ll l.957E-ll 1.402f-ll 1.053E-11 6.lB8E-12 6.540E-l2 5.338E-12 NNE 1.858£-10 9.l07E-ll 5.714E-ll 2.8B8E-ll l.748E-11 l.172E-11 8.399E.-12 6.306£-12 4.903E*l2 3 917E-12 3.197£-12 NE 2.960E-10 l.451E-10 9.102£-11 4.600E-ll 2.784E-11 1.867£-11 l.338E-ll l.004E-ll 7.8lOE-l' 6.239E-12 5.092£-12 ENE 2.l9DE-10 1.073E-10 6.733E-ll 3.403E-ll 2.06DE-ll l.JBlE-11 9.B95f-12 7.43DE-l2 5.777E-12 4.615E-12 3./6/E-12 E 2.345£-10 1.l49E-10 7.209£-11 3.644£-ll 2.205£-11 1.479£-11 l.060E-ll 7.956£-12 6.1B6E-12 4.942[-12 4.033E-12 ESE 2.643E-10 l.Z95E-10 8.1Z6E-ll 4.107E-ll 2.486E-ll l.667l-ll 1.194£-ll 8.96BE-12 6.973E-L2*5.570E-12 4.546[-12 SE 3.378E-10 l.656E-10 l.039E-10 5.251£-11 3.176E-ll 2.lJlE-11 l.527E-ll l.I46E-ll 8.914f-12 7.120E-12 5.812£-12 SSE 3.266E-10 l.601E-10 l.004E-10 5.077E-ll 3.073E-ll 2.060E-ll 1.47.GE*-ll l. JOBE-11 B.619E-12 Ji 885E-12 '>.619£-12
~ . *. : ! *,
USNRC COMPUTER CODE - XOQOOQ, VERSION 2.0 RUN DATE: 931116
t PALISADES XOODOQ82 ***** USING 01/01/88 - 12/31/92 MET DATA tiaaA GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING
~*~**********kkk aawawatwAtAatttttttttttt RELATIVE DEPOSITlON PER UNJT AREA (H**-2) BY DOWNWIND SECTORS SEGMENT BOUNDARIES IN MILES DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30**40 40-50 0
""Tl FROM SITE ""Tl s 4.391E-09 l.356E-09 5.398E-10 . 2.95DE-10 1.875[-10 8. 053E-ll Z.497E-ll 9.897E-12 5.285E-l2 3.271E-12 (/)
~ -u SSW 2.985£-09 9.223£-10 3.670E-10 2. D06E-10 1.275E-10 5.475E-ll 1. 698E-1 l o.729E-12 3.594E-12 2. 224£-12 ~ )>
rn r SW 3.466E-09 1.071£-09 4.261E*l0 2.328£-10 1.480[-10 6.357E-ll l.971E-11 7.813E-12* 4.172E-l2 2. 582£-12 0
~
(/)
0 )>
WSW 3. 257E-09 1.006[-09 4.004E-1D 2.188£-10 1. 391E-10 S.974E-ll 1.852E-ll 7.342E-12 3.921E-l2 2.427E*l2 ::0
(/)
rn rn 0
w 4.364E-09 1.348[*09 S.366E-10 Z.932E-10 1. 864£-10 8.005E-ll 2.482[-ll 9.838[-12 ' 5.254£-12 3.252E-12 ~
CD
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w WNW 6.522E-09 2.015E-09 8.0lBE-10 4.381[-10 2.785E-10 1.196[-10 3. 709E -11 l.470£-11 7.851[-12 4.859E~ 12 OJ Ul
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r c
z:
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NW 7.755£-09 2.396E-09 9.533E~lO 5.210E*l0 3.311[-10 1. 422E-10 4.410E-ll 1. 748E -11 9.335E -12 5. 778£-12 rn 0
s
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c r rn 2.210E-11 l.180[-ll 7. 305[-12
~ ?i; 4.187[-10 1. 798E-l0 5. 576E-ll .......
NNW 9.805£-09 3.029E-09 l.205E*09. 6.587E-10 <X>
3. 773£-10 I .621E-10 5.025E-11 1. 992E-ll l. 064[ -11 6. 583£-12 w 8.836E-09 2.730E-09 1.086[-09 5.936E-10
~
0 -u NNE 5.Z9ZE-09 l.635E-09 6.505£-10 3.555[-10 2.259£-10 9.705f-ll 3.0lDE-11 1.193[-ll 6.370[-12 3.943£-12 :z:
~
NE 8.428E-09 2.604E-09 1.036[-09 5.662£-10 3.599£-10 1.546£-10 4. 794E-ll l.900E-11 1.015[-l l 6.280E-12 3:
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z:
2. 662f-IO 1.143£-10 3.546E-11 1.405E-ll. 7.505£-12 4. 645£-12 :z:
ENE 6.235[-09 l.926E-09 7.665E-10 4.188E-l0 c
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E 6.676£-09 2.063[*09 8.207E*l0 4.465£-10 2.851£-10 1.224[-10 3.797E-U 1.505£-11 8.036£-12 4.974£-12 r ESE 7.525£-09 2.325£-09 9.251£-10 5.055£-10 3.213£-10 1.360E-10 4.Z80E-ll 1. 696E-11 9.058E-1Z 5.606[*12 SE 9.619E~09 2.972E-09 1.183£-09 6.462£-10 4.107(-10 1.764£-10 5.471£-11 2.168£-11 l.158E-ll 7.167E-l2 SSE 9.301[*09 2.873f-09 1.143[-09 6.l48E-ID 3.971E-10 1. 706f-10 5.Z90f-11 2. 097£-11 l. llOE-11 6.930E-12 VENT AND BUILDING PARAMETERS:
RELEASE HEIGHT (METERS) 58.10 REP .. WIND HEIGHT IMETERS) 10.0 DIAMETER (METERS). 0.00 BUILDING HEIGHT !METERS) 58. l EXIT VELOCITY . (METERS) ' 0.00 BLOG . Hlr..CRS. SEC.AREA ISQ.HETERS) 2000.0' HEAT EMISSION RATE !CAL/SEC) 0.0
.ALL GROUND LEVEL RELEASES.
-e
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 1. 4 1993 PALISADES LAND USE CENSUS TABLE 10.11*1 Distance to the nearest residence. garden. dairy/beef cattle and goat in each sector.
SECTOR RESIDENCE GARDEN
BEEF CADLE DAIRY COW GOAT N > 5 mi > 5 mi > 5 mi > 5 mi > 5 mi NNE 1.1 mi 1.6 mi > 5 mi > 5 mi > 5 mi NE 1. 2 mi 1.2 mi > 5 mi > 5 mi 3.2 mi ENE 1. 3 mi 1.5 mi 4. 0 mi 4. 0 mi > 5 mi E 1. 0 mi 3.5 mi 3. 5 mi > 5 mi > 5 mi ESE 1. O mi 2.3 mi 3 .1 mi 4. 0 mi 2 .1 mi
SE SSE s
1. 0 mi
.7 mi
. 5 mi 1.0 mi
1. 6 mi 1.5 mi
> 5 mi
5. O mi
> 5 mi 4.3 mi
> 5 mi
> 5 mi
> 5 mi 5.0 mi
> 5 mi SSW . 7 mi > 5 mi > 5 mi > 5 mi * > 5 mi
35
NOTE: *Based on Palisades 5-year composite meteorological data. 1988-1992 .
36
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 1.5 DOSE FACTORS FOR SUBMtRSION IN NOBLE GASES*
DFR 1 DFY 2 DFS 1 DFB 2 Kr-85m l.17(+J) 3 1.23(+3) 1:46.(+3) 1.97(+3)
Kr-85 1. 61( +1) "1.72(+1) 1.34(+3) 1.95(+3)
Kr-87 5.92(+3) 6.17(+3) 9.73(+3) 1.03(+4)
Kr-88 1.47(+4) 1. 52( +4) 2.37(+3) 2.93(+3)
Kr-89 1.66(+4) 1. 73( +4) 1. 01( +4) 1.06(+4)
Xe-131m 9.15(+1) 1.56(+2) 4.76(+2) 1.11(+3)
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 Xe-135 Xe-137 3.12(+3)
1. 81( +3) 1.42(+3) 3.36(+3) 1.92(+3) 1.51(+3) 7.11(+2)
1. 86( +*3)
1. 22( +4) 7.39(+3) 2.46(+3)
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 3
2. mrad/y per µCi/m3 3
3. 1.17(+3) = 1.17x 0
Dose factors for exposure to a semi-infinite cloud of noble gases. Values
were obtained from USNRC Regulatory Guide 1.109. Revision 1 (October 1977) .
37
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 1.6 STABLE ELEMENT TRANSFER DATA Fm - MILK (COW) Fm - MILK (GOAT) F - MEAT B.
ELEMENT (DAYS/U CDAYS/U . (DAYS/KG) (VEG/SDIU H 1. OE-02 1.7E-01 . 1. 2E-02 4.SE-00 c 1. 2E-02 1. 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 1.lE-00 Cr 2.2E-03 2.2E-03 2.4E-03 2.SE-04 Mn 2.SE-04 2.SE-04 8.0E-04 2.9E-02 Fe 1.2E-03 1.3E-04 4.0E-02 6.6E-04 Co 1.0E-03 1. OE-03 1.3E-02 9.4E-03 Ni 6.7E-03 6.7E-03 5.3E-02 1.9E-02 Cu 1.4E-02 1.3E-02 8.0E-03 1. 2E-01 Zn 3.9E-02 3.9E-02 3.0E-02 4.0E-01 Rb
3.0E-02 3.0E-02 3.lE-02 1.3E-01
Sr 8.0E-04 1.4E-02 6.0E-04 1. 7E-02 ,
y 1. OE-05 1.0E-05 4.6E-03 2.6E-03 Zr 5.0E-06 5.0E-06 3.4E-02 1. 7E-04 Nb 2.5E-03 2.5E-03 2.8E-01 9.4E-03 Mo 7.5E-03 7.5E-03 8.0E-03 1.2E-01 Tc 2.5E-02 2.5E-02 4.0E-01 2.5E-01 Ru 1.0E-06 1. OE-06 4.0E-01 5.0E-02 Rh 1.0E-02 1.0E-02 1.5E-03 1. 3E+Ol Ag 5.0E-02 5.0E-02 1.7E-02 1.5E-01 Te 1.0E-03 1.0E-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 1.0E-02 Ba 4.0E-04 4.0E-04 3.2E-03 5.0E-03 La 5.0E-06 5.0E-06 2.0E-04 2.5E-03 Ce 1.0E-04 1. OE-04 1.2E-03 2.5E-03 Pr 5.0E-06 5.0E-06 4.7E-03
2.5E-03 Nd 5.0E-06 5.0E-06 3.3E-03 2.4E-03 w 5.0E-04 5.0E-04 1.3E-03 1.8E-02 Np 5.0E-06 5.0E-06 2.0E-04 2.5E-03 38
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
. ------ TABLE 7 1.
INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3* 0. 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 BElO 9.49E-04 l.25E-04 2.65E-05 0. 0. l.49E-03 l.73E-05 Cl4 l.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Nl3
4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 FlB 3.92E-06 0. 3.33E-07 0. 0. 0. 6.lOE-07 NA22 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 NA24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P32 l.45E-03 8.03E-05 5.53E-05 0. 0. 0. l.15E-05 AR39 0. 0. 0. 0. 0. l.OOE-08 0. .
AR41 0. 0. 0. 0. 0. 3.14E-08 0.
CA41 7.48E-05 0. 8.16E-06. 0. D. 6.94E-02 2.96E-07 SC46 3.75E-04 5.41E-04 l.69E-04 0. 3.56E-04 0. 2.19E-05 CR51 0. 0. 6.39E-08 4.llE-08 9.45E-09 9.17E-06 2.55E-07 MN54 O~ l.BlE-05 3.56E-06 0. 3.56E-06 7.14E-04 5.04E-06 MN56 0. l.lOE-09 l.58E-10 0. 7.86E-10 8.95E-06 5.12E-05 FE55 l.41E-05 8.39E-06 2.38E-06 0. 0. 6.21E-05 7.82E;07 FE59 9.69E-06 1.68E-05 6.77E-06 0. 0. 7.25E-04 l.77E~o5 C057 0. 4.65E-07 4.58E-07 0. 0. 2.71E-04 3.47E-06 C058 0. 8.71E-07 1.30E-06 0. 0. 5.55E-04 7.95E-06 C060 0. 5.73E-06 8.41E-06 0. 0. 3.22E-03 2.28E-05
Nf59 NI63 NI65 CU64 ZN65 ZN69M+D 1.81E-05 2.42E-04 l.71E-09 0.
1.38E-05 8.98E-09 5.44E-06 3.lOE-06 0.
1.46E-05 8.29E-06 0.
2.03E-10 8.79E-11 0.
1.34E-09 5.53E-10 0.
4.47E-05 2.22E-05 0.
1.84E-08 l.67E-09 0.
0.
0.
0.
5.48E-05 6.34E-07.
1.49E-04 l.73E-06 5.BOE-06 3.58E-05.
2.84E-09 6.64E-06 l.O?E-05 2.32E-05 4.62E-04 3.67E-05 7.45E-09 1.91E-05 2.92E-05 ZN69 3.85E-ll 6.91E-ll 5.13E-12 0. 2.87E-ll l.05E-06 9.44E-06 SE79 0. 2.25E-06 4.20E-07 0. 2.47E-06 2.99E-04
3.46E-06 BR82 0. 0. 9.49E-06 0. 0. 0. 0.
BR83+0 0. 0. 2.72E-07 0. 0. 0. 0.
BR84 0. 0. . 2.86E-07 0. 0. 0. 0.
BR85 0. 0. 1.46E-08 0. 0. 0. 0.
KR83M 0. 0. 0. 0. 0. 2.50E-09 0.
KR85M 0. 0. 0. 0. 0. 1.31E-08 0.
KR85 0. 0. 0. 0. 0. l.16E-08 0.
KR87 0. 0. 0. 0. 0.. 6.59E-08 0.
KR88+0 0. 0. 0. 0. 0. 1.38E-07 0.
KR89 0. 0. 0. 0. 0. 8.67E-08 0.
RB86 0. 1.36E-04 6.30E-05 0. 0. 0. 2.17E-06 RB87 0. 7.llE-05 2.64E-05 0. 0. 0. 2.99E-07 RB88 0. 3.98E-07 2.05E-07 0. 0. 0. 2.42E-07 RB89+D 0. 2.29E-07 l.47E-07 0. 0. 0. 4.87E-08 SR89+0 2.84E-04 0. 8.15E-06 0. 0. 1.45E-03 4.57E-05 SR90+0 2.92E-02 0. 1.85E-03 0. 0. 8.03E-03 9.36E-05 SR91+0 6.83E-08 0. 2.47E-09 0. 0. 3.76E-05 5.24E-05 SR92+D 7.50E-09 0. 2.79E-10 0. 0. 1.70E-05 l.OOE-04
Includes a 50% increase to account for percutaneous transpiration.
39
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8

* TABLE 1.7 (continued)

INFANT INHALATION DOSE COMMITMENT FACTORS CMREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI -LU Y90 2.35E-06 0. 6.30E-08 0. 0. 1.92E-04 7.43E-05 Y91M+O 2.91E-10 0. 9.90E-12 0. 0. 1.99E-06 1.68E-06 Y91 4.20E-04 0.
1.12E-05 0. 0. 1.75E-03 5.02E-05 Y92 l.17E-08 0. 3.29E-10 0. 0. 1.75E-05 9.04E-05 Y93 l.07E-07 0. 2.91E-09 0. 0. 5.46E-05 1.19E-04 ZR93+0 2.24E-04 9.51E-05 6.18E-05 0. 3.19E-04 1.37E-03 1.48E-05 ZR95+0 8.24E-05 1.99E-05 1.45E-05 0. 2.22E-05 1.25E-03 l.55E-05 ZR97+D 1.07E-07 l.83E-08 8.36E-09 0. l.85E-08 7.88E-05 l.OOE-04 NB93M 1.38E-04 3.59E-05 1.15E-05 0. 3.68E-05 2.09E-04 2.47E-06 NB95 1.12E-05 4.59E-06 2.70E-06 0. 3.37E-06 3.42E-04 9.05E-06 NB97 2.44E-10 5.21E-11 1.88E-11 0. 4.07E-11 2.37E-06 1.92E-05 M093 0. 6.46E-06 2.22E-07 0. 1.54E-06 3.40E-04 3.76E-06 M099+D 0. 1.18E-07 2.31E-08 0. 1.89E-07 9.63E-05 3.48E-05 TC99M 9c98E-13 2.06E-12 2.66E-ll 0. 2.22E-11 5.79E-07 1.45E-06 TC99 2.09E-07 2.68E-07 8.85E-08 0. 2.49E-06 6.77E-04 7.82E-06 TC101 4.65E-14 5.88E-14 5.80E-13 0. 6.99E-13 4.17E-07 6.03E-07 RU103+D 1.44E-06 0. 4.85E-07 0. 3.03E-06 3.94E-04 1.15E;o5 RU105+D 8.74E-10 0. 2.93E-10 0. 6.42E-10 l.12E-05 3.46E-05 RU106+D 6.20E-05 0. , 7.77E-06 0. 7.61E-05 8.26E-03 1.17E-04 RH105 8.26E-09 5.41E-09 3.63E-09 0. 1.50E-08 2.08E-05 1.37E-05 PD107 0. 4.92E-07 4.llE-08 0. 2.75E-06 6.34E-05 7.33E-07
PD109 0. 3.92E-09 1.05E-09 0. 1.28E-08 1.68E~05 2.85E-05
AGllOM+D 7.13E-06 5.16E-06 3.57E-06 0. 7.80E-06 2.62E-03 2.36E-05 AGlll 3.75E-07 1.45E-07 7.75E-08 0. 3.05E-07 2.06E-04 3.02E-05 CD113M 0. 6.67E-04 2.64E-05 0. 5.80E-04 l.40E-03 l.65E-05 CD115M 0. l.73E-04 6.19E-06 0. 9.41E-05 l.47E-03 5.02E-05 SN12j 2.09E-04 4.21E-06 7.28E-06 4.27E-06 0. 2.22E-03 4.08E-05 SN125+0 l.OlE-05 2.51E-07 6.00E-07 2.47E-07 0. 6.43E-04 7.26E-05 SN126+0 B.30E-04 l.44E-05 3.52E-05 3.84E-06 0. 4.93E-03 l.65E-05 SB124 2.?lE-05 3.97E-07 8.56E-06 7.18E-08 0. 1.89E-03 4.22E-05 SB125+0 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0. l.l?E-03 l.05E-05 SB126 3.08E-06 6.0lE-08 l.llE-06 2.35E-08 0. 6.88E-04 5.33E-05 SB127 2.82E-07 5.04E-09 8.76E-08 3.60E-09 0. l.54E-04 3.78E-05 TE125M 3.40E-06 l.42E-06 4.?0E-07 l.16E-06 0. 3.19E-04 9.22E-06 TE127M+D l.19E-05 4.93E-06 l.48E-06 3.48E-06 2.68E-05 9.37E-04 l.95E-05 TE127 l.59E-09 6.BlE-10 3.49E-10 l.32E-09 3.47E-09 7.39E-06 l.74E-05 TE129M+D l.OlE-05 4.35E-06 l.59E-06 3.91E-06 2.27E-05 l.20E-03 4.93E-05 TE129 5.63E-ll 2.48E-ll l.34E-11 4.82E-11 l.25E-10 2.14E-06 l.88E-05 TE131M+D 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 TE131+0 l.24E-ll 5.87E-12 3.57E-12 l.13E-11 2.85E-11 1.47E-06 5.87E-06 TE132+D 2.66E-07 l.69E-07 l.26E-07 l.99E-07 7.39E-07 2.43E-04 3.15E-05 TE133M+D 6.13E-ll 3.59E-ll 2.74E-ll 5.52E-ll l.72E-10 3.92E-06 1.59E-05 TE134+0 3.18E-11 2.04E-11 l.68E-11 2.91E-ll 9.59E-11 2.93E-06 2.53E-06 1129 2.16E-05 l.59E-05 l.16E-05 l.04E-02 l.88E-05 0. 2.12E-07 1130 4.54E-06 9.91E-06 3.98E-06 l.14E-03 1.09E-05 0. l.42E-06 1131+0 2.?lE-05 3.l?E-05 l.40E-05 l.06E-02 3.?0E-05 0. 7.56E-07 40
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
---------------------- TABLE 1.7 (continued)
INFANT INHALATION DOSE COMMITMENT FACTORS CMREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 l.21E-06 2.53E-06 8.99E-07 l.21E-04 2.82E-06 0. l.36E-06 1133+0 9.46E-06 l.37E-05 4.00E-06 2.54E-03 l.60E-05 0. l.54E-06 fl34 6.58E-07 l.34E-06 4.75E-07 3.lBE-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. 0. 0. 0. O.* 6.77E-09 0.
XE133M 0. 0. 0. 0. 0. 8.89E-09 0.
XE133 0. 0. 0. 0. 0. 7.41E-09 0.
XE135M 0. 0. 0. 0. 0. 8.05E-09 0.
XE135 0. 0. 0. 0. 0. l.BOE-08 0.
XE137 0. 0. 0. 0. 0. 8.30E-08 0.
XE138+0 0. 0. 0. 0. 0. 9.78E-08 0.
CS134M+D l.32E-07 2.lOE-07 l.llE-07 0. 8.50E-08 2.00E-08 l.16E-07 CS134 2.83E-04 5.02E-04 5.32E-05 0. l.36E-04 5.69E-05 9.53E-07 CS135 l~OOE-04 8.66E-05 4.73E-06 0. 2.58E-05 l.OlE-05 2.18E-07 CS136 3.45E-05 9.61E-05 3.78E-05 0. 4.03E-05 8.40E-06 l.02E-06 CS137+0 3.92E-04 4.37E-04 3.25E-05 0. 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:o7 CS139+0 2.32E-07 3.03E-07 l.22E-07 0. l.65E-07 2.53E-08 l.33E-B8 BA139 l.06E-09 7.03E-13 3.07E-ll 0. 4.23E-13 4.25E-06 3.64E-05 BA140+0 4.00E-05 4.00E-08 2.07E-06 0. 9.59E-09 l.14E-03 2.74E-05 BA141+0 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 0. 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+0 2.09E-07 l.38E-07 l.58E-08 0. 4.03E-08 8.30E-05 3.55E-05 CE144+0 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-11 l.32E-ll l.72E-12 0. 4.BOE-12 l.15E-06 3.06E-06 ND147+0 5.67E-06 5.BlE-06 3.57E-07 0. 2.25E-06 2.30E-04 2.23E-05 PM147 3.91E-04 3.0?E-05 l.56E-05 0. 4.93E-05 4.55E-04 5.75E-06 PM148M+O 5.00E-05 l.24E-05 9.94E-06 0. 1.45E-05 1.22E-03 3.37E-05 PM148 3.34E-06 4.82E-07 2.44E-07 0. 5.76E-07 3.20E-04 6.04E-05 PM149 3.lOE-07 4.0BE-08 l.78E-08 0. 4.96E-08 6.50E-05 3.0lE-05 PM151 7.5~E-08 1.lOE-08 5.55E-09 0. 1.30E-08 3.25E-05 2.58E-05 SM151 3.38E-04 6.45E-05 1.63E-05 0. 5.24E-05 2.98E-04 3.46E-06 SM153 l.53E-07 l.lBE-07 9.06E-09 0. 2.47E-08 3.70E-05 l.93E-05 EU152 7.83E-04 l.77E-04 l.72E-04 0. 5.94E-04 l.48E-03 9.88E-06 EU154 2.96E-03 3.46E-04 2.45E-04 0. '1.14E-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 0. 4.48E-06 6.12E-04 4.14E-05 TB160 l.12E-04 0. l.40E-05 0. 3.20E-05 l.llE-03 2.14E-05 H0166M l.45E-03 3.0?E-04 2.SlE-04 0. 4.22E-04 2.05E-03 l.65E-05 Wl81 4.86E-08 l.46E-08 l.67E-09 0. 0. 1.33E-05 2.63E-07 Wl85 l.57E-06 4.83E-07 5.58E-08 0. 0. 4.48E-04 1.12E-05 Wl87 9.26E-09 6.44E-09 2.23E-09 0. 0. 2.83E-05 2.54E-05
41
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL

R_e_v_is-io_n__ s _________________________*

TABLE 1.7 (continued)
INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB210+0 8.62E-02 2.02E-02 3.43E-03 0. 6.85E-02 1.76E-01 3.79E-05 BI210+0 0. 1.33E-05 1.lSE-06 0. l.03E-04 9.96E-03 3.27E-05 P0210 2.98E-03 5.63E-03 7.12E-04 0. 1.30E-02 2.40E-01 4.36E-05 RN222+0 0. 0. 0. 0. 0. 9.BBE-06 0.
RA223+0 1.56E-03 2.26E-06 3.12E-04 0. 4.16E-05 2.25E-01 3.04E-04 RA224+0 1.77E-04 4.00E-07 3.54E-05. 0. 7.30E-06 7.91E-02 3.42E-04 RA225+0 2.57E-03 2.BBE-06 5.13E-04 0. 5.31E-05 2.57E-01 2.87E-04 RA226+0 2.48E-01 1.46E-05 2.05E-01 0. 2.94E-04 7.83E-01 3.05E-04 RA228+0
1.60E-01 7.61E-06 1.BOE-01 0. 1.53E-04 l.09E-OO 5.19E-05 AC225 3.69E-03 4.72E-03 2.48E-04 0. 3.49E-04 1.96E-01 2.71E-04 AC227+0 5.29E+OO 8.76E-01 3.28E-01 0. 1.86E-01 1.62E+OO 5.27E-05 TH227+0 1.82E-03 3.03E-05 5.24E-05 0. 1.13E-04 3.27E-01 3.53E-04 TH228+0 8.46E-01 1.lOE-02 2.86E-02 0. 5.61E-02 4.65E+OO 3.62E-04 TH229 1~34E+Ol 1.82E-01 6.62E-01 0. 8.99E-01 1.22E+Ol 3.29E-04 TH230 3.46E+OO 1.79E-01 9.65E-02 0. 8.82E-01 2.18E+OO 3.87E-05 TH232+0 3.86E+OO 1.53E-01 2.29E-01 0. 7.54E-01 2.09E+OO 3.29E~05 TH234 1.33E-05 7.17E-07 3.84E-07 0. 2.70E-06 1.62E-03 7.40E~D5 PA231+0 9.lOE+OO 3.00E-01 3.62E-01 0. 1.62E+OO 3.85E-01 4.61E-05 PA233 6.84E-06 1.32E-06 1.19E-06 0. 3.68E-06 2.19E-04 9.04E-06 U232+0 2.57E-01 0. 2.13E-02 0. 2.40E-02 1.49E+OO 4.36E-05
U233+0 5.44E-02 0. 3.83E-03 0.. 1.09E-02 3.56E-01 4.03E-05.
U234 5.22E-02 0. 3.75E-03 0. 1.07E-02 3.49E-01 3.95E-05 U235+0 5.0lE-02 0. 3.52E-03 0. 1.0lE-02 3.28E-01 5.02E-05 U236 5.0lE-02 0. 3.60E-03 0. 1.03E-02 3.35E-01 3.71E-05 U237 3.25E-07 0. 8.65E-08 0. 8.08E-07 9.13E-05 1.31E-05 U238+0 4.79E-02 0. 3.29E-03 0. 9.40E-03 3.06E-01 3.54E-05 NP237+0 3.03E+OO 2.32E-01 1.26E-01 0. 7.69E-01 3.49E-01 5.lOE-05 NP238 2.67E-06 6.73E-08 4.16E-08 0. 1.47E-07 9.19E-05 2.58E-05 NP239 2.65E-07 2.37E-08 1.34E-08 0. 4.73E-08 4.25E-05 1.78E-05 PU238 5.02E+OO 6.33E-01 1.27E-01 0. 4.64E-Ol 9.03E-01 4.69E~05 PU239 5.50E+OO 6.72E-01 1.34E-01 0. 4.95E-01 8.47E-01 4.28E-05 PU240 6.49E+OO 6.71E-01 1.34E-01 0. 4.94E-01 8.47E-01 4.36E-05 PU241+0 1.55E-01 6.69E-03 3.llE-03 0. 1.15E-02 7.62E-04 8.97E-07 PU242 5.09E+OO 6.47E-01 1.29E-01 0. 4.77E-01 8.15E-01 4.20E-05 PU244 5.95E+OO 7.40E-01 1.48E-01 0. 5.46E-01 9.33E-01 6.26E-05 AM241 1.84E+OO 8.44E-01 1.31E-01 0. 7.94E-01 4.06E-01 4.78E-05 AM242M 1.90E+OO 8.24E-01 1.35E-01 0. 8.03E-01 1.64E-01 6.0lE-05 AM243 1.82E+OO 8.lOE-01 1.27E-Ol 0. 7.72E-01 3.85E-01 5.60E-05 CM242 8.58E-02 7.44E-02 5.70E-03 0. l.69E-02 2.97E-01 5.lOE-05 CM243 1.73E+OO 7.94E-Ol 1.06E-01 0. 3.91E-01 4.24E-01 5.02E-05 CM244 1.43E+OO 7.04E-01 8.89E-02 0. 3.21E-01 4.0SE-01 4.86E-05 CM245 2.26E+OO 8.SOE-01 1.36E-01 0. 5.23E-01 3.92E-01 4.53E-05 CM246 2.24E+OO 8.79E-01 l.36E-01 0. 5.23E-01 3.99E-01 4.45E-05 CM247+0 2.18E+OO 8.64E-01 1.33E-01 0. 5.15E-01 3.92E-01 5.85E-05 CM248 1.82E+Ol 7.12E+OO 1.lOE+OO 0. 4.24E+OO 3.23E+OO 9.43E-04 CF252 4.26E+OO 0. l.OlE-01 0. 0. l.37E+OO 1.85E-04 42
. PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8

TABLE 1.7 (contd)

CHILD INHALATION DOSE COMMITMENT FACTORS CMREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3* 0. 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 BElO 8.43E-04 9.83E-OS 2.12E-OS 0. 0. 7.41E-04 1.72E-05 C14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 N13 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 F18 1.88E-06 0. l.85E-07 0. 0. 0. 3.37E-07 NA22 4.41E-05 4.41E-05 4.41E-05 4.41E-05 4.41E-05 4.41E-05 4.41E-05 NA24 4.35E-06 4.3SE-06 4.35E-06 4.3SE-06 4.35E-06 4.35E-06 4.35E-06 P32 7.04E-04 3.09E-OS 2.67E-OS 0. 0. 0. 1.14E-05 AR39 0. 0. 0. 0. 0. 4.89E-09 0.
AR41 0. 0. 0. 0. 0. 1.68E-08 0.
CA41 7.06E-05 0. 7.70E-06 0. 0. 7.21E-02 2.94E-07 SC46 1.97E-04 2.70E-04 1.04E-04 0. 2.39E-04 0. 2.4SE-05 CRSl 0. 0. 4.17E-08 2.31E-08 6.S7E-09 4.S9E-06 2.93E-07 MNS4 O: 1.16E-OS 2.S?E-06 0. 2.71E-06 4.26E-04 6.19E-06 MNS6 0. 4.48E-10 8.43E-11 0. 4.52E-10 3.SSE-06 3.33E-OS FESS 1.28E-05 6.BOE-06 2.lOE-06 0. 0. 3.00E-05 7.7SE--07 FES9 S.59E-06 9.04E-06 4.SlE-06 0. 0. 3.43E-04 1.91E~05 C057 0. 2.44E-07 2.BBE-07 0. 0. 1.37E-04 3.SBE-06 COSS 0. 4.79E-07 8.S5E-07 0. 0. 2.99E-04 9.29E-06 C060 0. 3.SSE-06 6.12E-06 0. 0. 1.91E-03 2.60E-OS
NIS9 NI63 NI65 CU64 ZN65 ZN69M+D 1.66E-OS 2.22E-04 8.0BE-10 0.
1.15E-05 4.26E-09 4.67E-06 2.83E-06 0.
1.2SE-05 7.56E-06 0.
7.99E-11 4.44E-11 0.
5.39E-10 2.90E-10 0.
3.06E-05 1.90E-05 0.
7.28E-09 8.59E-10 0.
~.
0.
0.
2.73E-OS 6.29E-07 7.43E-05 1.71E-06 2.21E-06 2.27E-05 1.63E-09 2.59E-06 9.92E-06 1.93E-05 2.69E-04 4.41E-06 4.22E-09 7.36E-06 2.71E-05 ZN69 1.BlE-11 2.61E-11 2.41E-12 0. 1.58E-11 3.84E-07 2.75E-06 SE79 0. 1.23E-06 2.60E-07 0. l.71E-06 l.49E-04 3.43E-06 BR82 0. 0. 5.66E-06 0. 0. 0. 0.
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.
KR85M 0. 0. 0. 0. 0. 6. SBE-09 0.
KR85 0. 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 l.37E-05 0. 0. 0. 2.96E-07 RB88 0. l.52E-07 9.90E-08 0. 0. 0. 4.66E-09 RB89+D 0. 9.33E-08 7.83E-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 2.73E-02 0. l.74E-03 0. 0. 3.99E-03 9.28E-05 SR9l+D 3.28E-08 0. l.24E-09 0. 0. l.44E-05 4.70E-05 SR92+0 3.54E-09 0. l.42E-10 0. 0. 6.49E-06 6.SSE-05
*Includes a 50% increase to account for percutaneous transpiration.
43
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL CHILD INHALATION DOSE Revision 8 TABLE 1.7 (contd)
COMMITMENT FACTORS CMREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 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. 7.60E-07 4.64E-07 Y91 2.47E-04 0. 6.59E-06 0. 0. 7.lOE-04 4.97E-05 Y92 5.50E-09 0. l.57E-10 0. 0.. 6.46E-06 6.46E-05 Y93 5.04E-08 0. l.38E-09 0. 0. 2.0lE-05 l.05E-04 ZR93+D 2.07E-04 7.80E-05 5.55E-05 0. 3.00E-04 7.lOE-04 l.47E-05 ZR95+D 5.13E-05 l.13E-05 l.OOE-05 0: l.61E-05 6.03E-04 l.65E-05 ZR97+D 5.07E-08 7.34E-09 4.32E-09 0. l.05E-08 3.06E-05 9.49E-05 NB93M l.27E-04 3.17E-05 l.04E-05 0. 3.44E-05 l.04E-04 2.45E-06 NB95 6.35E-06 2.48E-06 l.77E-06 0. 2.33E-06 l.66E-04 l.OOE-05 NB97 l.16E-10 2.08E-ll 9.74E-12 0. 2.31E-ll 9.23E-07 7.52E-06 M093 0. 3.76E-06 l.3.SE-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 3.42E-05 TC99M 4.81E-13 9.41E-13 1.56E-11 0. 1.37E-11 2.57E-07 l.30E-06 TC99 l.34E-07 1.49E-07 5.35E-08 0. 1.75E-06 3.37E-04 7.75E-06 TC101 2.19E-14 2.30E-14 2.91E-13 0. 3.92E-13 1.58E-07 4.41E~09 RU103+D 7.55E-07 0. 2.90E-07 0. 1.90E-06 1.79E-04 l.21E-05 RU105+D 4.13E-10 0. 1.50E-10 0. 3.63E-10 4.30E-06 2.69E-05 RU106+D 3.68E-05 0. 4.57E-06 0. 4.97E-05 3.87E-03 l.16E-04 RH105 3.91E-09 2.lOE-09 1.79E-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 0. 1.48E-09 4.95E-10 0. 7.06E-09 6.16E-06 2.59E-05 AGllOM+D 4.56E-06 3.0BE-06 2.47E-06 0. 5.74E-06 1.48E-03 2.71E-05 AGlll 1.BlE-07 5.68E-08 3.75E-08 0. 1.71E-07 7.73E-05 2.98E-05 CD113M 0. 4.93E-04 2.12E-05 0. 5.13E-04 6.94E-04 l.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 4.19E-06 2.27E-06 0. 9.59E-04 4.05E-05 SN125+D 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0. 2.43E-04 7.17E-05 SN126+D 6.23E-04 1.04E-05 2.36E-05 2.84E-06 0. 3.02E-03 l.63E-05 SB124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 0. 8.76E-04 4.43E-05 SB125+D 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0. 6.27E-04 l.09E-05 SB126 1.72E-06 2.62E-08 6.16E-07 1.00E-08 0. 2.86E-04 5.67E-05 SB127 1.36E-07 2.09E-09 4.70E-08 1.51E-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 l.65E-10 5.30E-10 l.91E-09 2.71E-06 l.52E-05 TE129M+D 5.19E-06 l.85E-06 8.22E-07 l.71E-06 l.36E-05 4.76E-04 4.91E-05 TE129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 TE131M+D 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.0BE-07 5.56E-05 8.32E-05 TE131+0 5.87E-12 2.28E-12 1.78E-12 4.59E-12 l.59E-11 5.55E-07 3.60E-07 TE132+D 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 TE133M+D 2.93E-11 1.51E-11 1.50E-11 2.32E-11 l.OlE-10 1.60E-06 4.77E-06 TE134+0 1.53E-11 8.81E-12 9.40E-12 1.24E-11 5.71E-11 1.23E-06 4.87E-07 I129 l.05E-05 6.40E-06 5.71E-06 4.28E-03 1.08E-05 0. 2.lSE-07 I130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0. 1.38E-06 I131+0 l.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0. 7.68E-07 44
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
----------------------- TABLE 1.7 (contd)
CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 5.72E-07 l.lOE-06 5.07E-07 5.23E-05 l.69E-06 0. 8.65E-07 1133+0 4.48E-06 5.49E-06 2.0BE-06 l.04E-03 9.13E-06 0. l.48E-06 1134 3.17E-07 5.84E-07 2.69E-07 l.37E-05 8.92E-07 0. 2.58E-07 1135+0 l.33E-06 2.36E-06 l.12E-06 2.14E-04 3.62E-06 0. l.20E-06 XE131M 0. 0. 0. 0. 0. 3.30E-09 0.
XE133M 0. 0. 0. 0. 0. 4.36E-09 0.
XE133 0. 0. 0. 0. 0. 3.66E-09 0.
XE135M 0. 0. 0. 0. 0. 4.48E-09 0.
XE135 0. 0. 0. 0. 0. 9.09E-09 0.
XE137 0. 0. 0. 0. 0. 4.07E-08 0.
XE138+0 0. 0. 0. 0. 0. 5.17E-08 0.
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 2.74E-04 6.07E-05 0. 8.93E-05 3.27E-05 1.04E-06 CS135 6~23E-05 4.13E-05 4.45E-06 0. 1.53E-05 5.22E-06 2.17E-07 CS136 1.76E-05 4.62E-05 3.14E-05 0. 2.58E-05 3.93E-06 1.13E-06 CS137+D 2.45E-04 2.23E-04 3.47E-05 0. 7.63E-05 2.81E-05 9.78E-D7 CS138 1.71E-07 2.27E-07 1.50E-07 0. 1.68E-07 1.84E-08 7.29E~08 CS139+D 1.09E-07 1.15E-07 5.80E-08 0. 9.08E-08 9.36E-09 7.23E-12 BA139 4.98E-10 2.66E-13 1.45E-11 0. 2.33E-13 1.56E-06 l.56E-05 BA140+D 2.00E-05 1.75E-08 1.17E-06 0. 5.71E-09 4.71E-04 2.75E-05 BA141+D 5.29E-11 2.95E-14 1.72E-12 0. 2.56E-14 7.89E-07 7.44E-08 BA142+D 1.35E-11 9.73E-15 7.54E-13 0. 7.87E-15 4.44E-07 7.41E-10
LA140 1.74E-07 6.08E-08 2.04E-08 0. 0. 4.94E-05 6.lOE-05 LA141 2.28E-09 5.31E-10 l.15E-10 0. 0. 4.48E-06 4.37E-05 LA142 3.50E-10 1.llE-10 3.49E-11 0. 0. 2.35E-06 2.05E-05 CE141 1.06E-05 5.28E-06 7.83E-07 0. 2.31E-06 1.47E-04 l.53E-05 CE143+D 9.89E-08 5.37E-08 7.77E-09 0. 2.26E-08 3.12E-05 3.44E-05 CE144+D 1.83E-03 5.72E-04 9.77E-05 0. 3.17E-04 3.23E-03 1.05E-04 PR143 4.99E-06 1.50E-06 2.47E-07 0. 8.llE-07 1.17E-04 2.63E-05 PR144 1.61E-11 4.99E-12 8.lOE-13 0. 2.64E-12 4.23E-07 5.32E-08 ND147+D 2.92E-06 2.36E-06 1.84E-07 0. 1.30E-06 8.87E-05 2.22E-05 PM147 3.52E-04 2.52E-05 1.36E-05 0. 4.45E-05 2.20E-04 5.70E-06 PM148M+D 3.31E-05 6.55E-06 6.55E-06. 0. 9.74E-06 5.72E-04 3.58E-05 PM148 1.61E-06 1.94E-07 1.25E-07 0. 3.30E-07 1.24E-04 6.0lE-05 PM149 1.47E-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 1.24E-05 2.SOE-05 SM151 3.14E-04 4.75E-05 1.49E-05 0. 4.89E-05 1.48E-04 3.43E-06 SM153 7.24E-08 4.51E-08 4.35E-09 0. 1.37E-08 1.37E-05 l.87E-05 EU152 7.42E-04 1.37E-04 l.61E-04 0. 5.73E-04 9.00E-04 l.14E-05 EU154 2.74E-03 2.49E-04 2.27E-04 0. 1.09E-03 1.66E-03 2.98E-05 EU155 5.60E-04 4.0SE-05 3.lBE-05 0. 1.51E-04 2.79E-04 5.39E-05 EU156 7.89E-06 4.23E-06 8.75E-07 0. 2.72E-06 2.54E-04 4.24E-05 TB160 7.79E-05 0. 9.67E-06 0. 2.32E-05 5.34E-04 2.28E-05 H0166M 1.34E-03 2.BlE-04 2.37E-04 0. 4.0lE-04 1.13E-03 1.63E-05 Wl81 2.66E-08 6.52E-09 8.99E-10 0. 0. 5.71E-06 2.61E-07 W185 8.31E-07 2.0BE-07 2.91E-08 0. 0. l.86E-04 1.llE-05 W187 4.41E-09 2.61E-09 l.17E-09 0. 0. l.llE-05 2.46E-05
45
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 1.7 (contd)
CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE . BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 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.05E-Ol 4.32E-05 RN222+D 0. 0. 0. 0. 0. 4.82E-06 0.
RA223+0 7.69E-04 8.89E-07 l.54E-04 0. 2.36E-05 8.48E-02 3.00E-04 RA224+0 8.44E-05 l.53E-07 l.69E-05 0. 4.06E-06 2.92E-02. 3.34E-04 RA225+0 l.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 l.92E-Ol 0. 2.03E-04 3.90E-Ol 3.02E-04 RA228+0 l.49E-Ol 3.94E-06 l.68E-Ol 0. l.04E-04 5.37E-Ol 5:14E-05 AC225 1.BlE-03 l.87E-03 l.21E-04 0. l.99E-04 7.37E-02 2.67E-04 AC227+0 4.96E+OO 8.05E-Ol 3.07E-Ol 0. l.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 l.04E-02 2.72E-02 0. -5.41E-02 3.34E+OO 3.59E-04 TH229 l.28E+Ol l.76E-Ol 6.31E-Ol 0. 8.68E-Ol l.04E+Ol 3.27E-04 TH230 3.30E+OO l.73E-Ol 9.20E-02 0. 8.52E-Ol l.85E+OO 3.84E~05 TH232+D 3.68E+OO l.47E-Ol l.28E-Ol 0. 7.28E-Ol l.77E+OO 3.27E;o5 TH234. 6.94E-06 3.07E~07 2.00E-07 0. l.62E-06 6.31E-04 7.32E-05 PA23l+D 8.62E+OO 2.86E-Ol 3.43E-Ol 0. l.56E+OO 1:92E-Ol 4.57E~05 PA233 4.14E-06 6.48E-07 7.25E-07 0. 2.38E-06 9.77E-05 8.95E-06 U232+D 2.19E-Ol 0. l.56E-02
0. l.67E-02 7.42E-Ol 4.33E-05 U233+D 4.64E-02 0. 2.82E-03 0. 7.62E-03 l.77E-Ol 4.00E-05 . .
U234 4.46E-02 0. 2.76E-03 0. 7.47E-03 l.74E-Ol 3.92E-05 U235+D 4.27E-02 0. 2.59E-03 0. 7.0lE-03 l.63E-Ol 4.98E-05 U236 4.27E-02 0. 2.65E~03 0. 7.16E-03 l.67E-Ol 3.67E-05 U237 l.57E-07 0. 4.17E-08 0. 4.53E-07 3.40E-05 l.29E-05 U238+D 4.09E-02 0. 2.42E-03 0. 6.55E-03 l.53E-Ol 3.51E-05 NP237+D 2.88E+OO 2.21E-Ol l.19E-Ol 0. 7.41E-Ol l.74E-Ol 5.06E-05 NP238 l.26E-06 2.56E-08 l.97E~08 0. 8.16E-08 3.39E-05 2.SOE-05
. NP239 l.26E-07 9.04E-09 6.35E-09 0. 2.63E-08 l.57E-05 l.73E-05 PU238 4.77E+OO 6.0SE-01 l.21E-Ol . 0. 4.47E-Ol 6.0BE-01 4.65E-05 PU239 5.24E+OO 6.44E-Ol l.28E-Ol 0. 4.78E-Ol 5.72E-Ol 4.24E-05 PU240 5.23E+OO 6.43E-Ol l.27E-Ol 0. 4:77E~Ol 5.71E-Ol 4.33E-O~
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 l.23E-01 0. 4.60E-Ol 5.SOE-01 4.16E-05 PU244 5.67E+OO 7.lOE-01 1.41E-01 0. 5.27E-Ol 6.30E-Ol 6.20E-05 AM241 l.74E+OO 7.85E-01 l.24E-Ol 0. 7.63E-Ol 2.02E-Ol 4.73E-05 AM242M l.79E+OO 7.65E-Ol l.27E-Ol 0. 7.71E-Ol 8.14E-02 5.96E-05
AM243 l.72E+OO 7.53E-Ol l.20E-Ol 0. 7.42E-Ol 1.92E-Ol 5.55E-05 CM242 6.33E-02 4.84E-02 4.20E-03 0. l.34E-02 l.31E-Ol 5.06E-05 CM243 l.61E+OO 7.33E-01 9.95E-02 0. 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-01 l.28E-Ol 0. 5.03E-Ol l.95E-Ol 4.49E-05 CM246 2.13E+OO 8.15E-Ol l.28E-Ol 0. 5.03E-Ol l.99E-Ol 4.41E-05 CM247+D 2.07E+OO 8.02E-Ol l.26E~Ol 0. 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 CF252 3.92E+OO 0. 9.33E-02 0. 0. 6.62E-Ol l.84E-04 46
PALISADES NUCLEAR PLANT*
OFFSITE DOSE CALCULATION MANUAL Revision 8
----------------------- TABLE 1.7 (contd)
TEEN INHALATION DOSE COMMITMENT FACTORS CMREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY . LUNG GI-LLI HJ* 0. l.59E-07 l.59E-07 l.59E-07 l.59E-07 l.59E-07 l.59E-07 BElO 2.78E-04 4.33E-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 8.65E-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 0. .Q. 0. 3.89E-08 NA22 l.76E-05 l.76E-05 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 l.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. D. l.44E-08 0.
CA41 4.0SE-05 0. 4.38E-06 0. 0. l.OlE-01 3.03E-07 SC46 7.24E-05 l.41E-04 4.lBE-05 0. l.35E-04 0. 2.98E-05 CR51 0. . 0. l.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 MN54 Or 6.39E-06 l.OSE-06 0. l.59E-06 2.48E-04 8.35E-06 MN56 0. 2.12E-10 3.lSE-11 0. 2.24F-10 l.90E-06 7.lBE-06 FESS 4.lBE-06 2.98E-06 6.93E-07 0. 0. l.55E-05 7.99E-07 FE59 l.99E-06 4.62E-06 l.79E-06 0. 0. l.91E-04 2.23E~05 C057 0. l.lBE-07 l.15E-07 0. 0. 7.33E-05 3.93E-06 C058 0. 2.59E-07 3.47E-07 0. 0. l.68E-04 l.19E-05 C060 0. l.89E-06 2.48E-06 0. 0. l.09E-03 3.24E-05 NI59 5.44E-06 2.02E-06 9.24E-07 0. 0. l.41E-05 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 l.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 7.80E-06 0. l.08E-05 l.55E-04 5.83E-06 ZN69M+D l.44E-09 3.39E-09 3.llE-10 0. 2.06E-09 3.92E-06 2.14E-05 ZN69 6.04E-12 l.lSE-11 8.07E-13 0. 7.53E-12 l.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. 4.30E-08 0. 0. 0. 0.
BR84 0. 0. 5.41E-08 0. 0. 0. 0.
BR85 0. 0. 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.
KR85 0. 0. 0. 0. 0. 4.63E-09 0.
KR87 0. 0. 0. 0. 0. 2.82E-08 0.
KRBB+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 l.OSE-05 0. 0. *o. 2.21E-06 RB87 0. 1.40E-05 4.SBE-06 0. 0. 0. 3.0SE-07 RBBB 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 SR89+D 5.43E-05 0. 1.56E-06 0. 0. 3.02E-04 4.64E-05 SR90+0 l.35E-02 0. 8.35E-04 0. 0. 2.06E-03 9.56E-05 SR9l+D l.lOE-08 0. 4.39E-10 0. 0. 7.59E-06 3.24E-05 SR92+D l.19E-09 0. 5.08E-11 0. 0. 3.43E-06 1.49E-05
Includes a 50% increase to account for percutaneous transpiration.
47
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 1.7 (contd)
TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 3.73E-07 0. 1.00E-08 0. 0. 3.66E-05 6.99E-05 Y91M+D 4.63E-11 0. 1.77E-12 0. 0. 4.00E-07 3.77E-09 Y91 8.26E-05 0. 2.21E-06 0. 0. 3.67E-04 5.llE-05 Y92 l.84E-09 0. 5.36E-11 0. 0. 3.35E-06 2.06E-05 Y93 l.69E-08 0. 4.65E-10 0. 0. 1.04E-05 7.24E-05 ZR93+0 6.83E-05 3.38E-05 l.84E-05 0. 1.16E-04 3.67E-04 l.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 l.72E-08 3.40E-09 1.57E-09 0. 5.15E-09 1.62E-05 7.88E-05 NB93M 4.14E-05 1.36E-05 3.41E-06 0. 1.59E-05 5.36E-05 2.52E-06 NB95 2.32E-06 l.29E-06 7.08E-07 0. l.25E-06 9.39E-05 l.21E-05 NB97 3.92E-11 9.72E-12 3.55E-12 0. 1.14E-11 4.91E-07 2.71E-07 M093 0. l.66E-06 4.52E-08 0. 5.06E-07 8.81E-05 3.99E-06 M099+0 0. 2.11E~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. 7.20E-12 l.44E-07 7.66E-07 TC99 4.48E-08 6.58E-08 1.79E-08 0. 8:35E-07 1.74E-04 7.99E-06 TC101 7.40E-15 1.05E-14 l.03E-13 0. 1.90E-13 8.34E-08 1.09E~16 RU103+0 2.63E-07 0. l.12E-07 0. 9.29E-07 9.79E-05 1.36E~Q5 RU105+0 1.40E-10 0. 5.42E-11 0. 1.76E-10 2.27E-06 1.13E-05 RU106+D 1.23E-05 0. 1.55E-06 0. 2.38E-05 2.0lE-03 l.20E-04 RH105 l.32E-09 9.48E-10 6.24E-10 0. 4.04E-09 4.09E-06 1.23E-05 PD107 0. 1.17E-07 8.39E-09 0. 9.39E-07 1.63E-05 7.49E-07 .
PD109 0. 6.56E-10 1.66E-10 0. 3.36E-09 3.19E-06 l.96E-05 AGllOM+D 1.73E-06 1.64E-06 9.99E-07 0. 3.13E-06 8.44E-04 3.41E-05 AGlll 6.07E-08 2.52E-08 l.26E-08 0. 8.17E-08 4.00E-05 3.00E-05 CD113M 0. 2.17E-04 7.lOE-06 0. 2.43E-04 3.59E-04 l.68E-05 CD115M 0. 3.48E-05 l.14E-06 0. 2.82E-05 3.03E-04 5.lOE-05 SN123 4.31E-05 9.44E-07 1.40E-06 7.55E-07 0. 4.96E-04 4.16E-05 SN125+D 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0. 1.26E-04 7.29E-05 SN126+D 2.18E-04 5.39E-06 8.24E-06 1.42E-06 0. 1.72E-03 l.68E-05 SB124 5.~8E-06 9.92E-08 2.lOE-06 1.22E~08 0. 4.81E-04 4.98E-05 SB125+D 9.23E-06 1.0lE-07 2.15E-06 8.80E-09 0. 3.42E-04 l.24E-05 SB126 6.19E-07 1.27E-08 2.23E-07 3.50E-09 0. 1.55E-04 6.0lE-05 SB127 4.64E-08 9.92E-10 1.75E-08 5.21E-10 0. 3.31E-05 3.94E-05 TE125M 6.lOE-07 2.80E-07 8.34E-08 1.75E-07 0. 6.70E-05 9.38E-06 TE127M+D 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 l.99E-05 TE127 2.51E-10 l.14E-10 5.52E-11 1.77E-10 9.lOE-10 l.40E-06 l.OlE-05 TE129M+D 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TE129 8.8YE-12 4.22E-12 2.20E-12 6.48E-12 3.32E-ll 4.12E-07 2.02E-07 TE131M+D l.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE13l+D 1.97E-12 1.04E-12 6.30E-13 l.55E-12 7.72E-12 2.92E-07 l.89E-09 TE132+D 4.50E-08 3.63E-08 2.74E-08 3.0?E-08 2.44E-07 5.61E-05 5.79E-05 TE133M+D l.OlE-11 7.33E-12 5.71E-12 8.18E-12 5.0?E-11 8.71E-07 l.23E-07 TE134+D 5.31E-12 4.35E-12 3.64E-12 4.46E-12 2.91E-ll 6.75E-07 1.37E-09 1129 3.53E-06 2.94E-06 4.90E-06 3.66E-03 5.26E-06 0. 2.29E-07 1130 7.80E-07 2.24E-06 8.96E-07 l.86E-04 3.44E-06 0. l.14E-06 1131+0 4.43E-06 6.14E-06 3.30E-06 l.83E-03 l.05E-05 0. 8.llE-07 48
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
------------------------ TABLE 1.7 (contd)
TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 l.99E-07 5.47E-07 l.97E-07 l.89E-05 8.65E-07 0. l.59E-07 1133+0 l.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.05E-07 4.94E-06 4:58E-07 0. 2.55E-09 Il35+D 4.62E-07 l.lBE-06 4.36E-07 7.76E-05 l.86E-06 0. 8.69E-07 XE131M 0. 0. 0. 0. 0. 2.70E-09 0.
XE133M 0. 0. 0. 0. 0. 3.59E-09 0.
XE133 0. 0. 0. 0. 0. 2.99E-09 0.
XE135M 0. 0. 0. 0. 0. 3.88E-09 0.
XE135 0. 0. 0. 0. 0. 7.55E-09 0.
XE137 0. 0. 0. 0. 0. 3.33E-08 0.
XE138+D 0. 0. 0. 0. 0. 4.38E-08 0.
CS134M+D 2.20E-08 4.35E-08 2.35E-08 0. 2.54E-08 4.56E-09 2.02E-08 CS134 6.28E-05 l.41E-04 6.86E-05 0. 4.69E-05 l.83E-05 l.22E-06 CS135 2.0BE-05 l.82E-05 4.47E-06 0. 7.30E-06 2.70E-06 2.23E-07 CS136 6.44E-06 2.42E-05 l.71E-05 0. l.38E-05 2.22E-06 l.36E-06 CS137+D 8.38E-05 l.06E-04 3.89E-05 0. 3.BOE-05 l.51E-05 l.06E-06 CS138 5.82E-08 l.07E-07 5.58E-08 0. 8.28E-08 9.84E-09 3.38E~ll CS139+0 3.65E-08 5.12E-08 l.97E-08 0. 4.34E-08 4.86E-09 l.66E-23 BA139 l.67E-10 l.18E-13 4.87E-12 0. l.llE-13 8.0BE-07 8.06E-07 BA140+D 6.84E-06 8.38E-09 4.40E-07 0. 2.85E-09 2.54E-04 2.86E-05 BA14l+D l.78E-ll l.32E-14 5.93E-13 0. l.23E-14 4.llE-07 9.33E-14 BA142+D 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 6.09E-05 LA141 7.63E-10 2.35E-10 3.87E-ll 0. 0. 2.31E-06 l.54E-05 LA142 l.20E-10 5.31E-ll l.32E-ll 0. 0. l.27E-06 l.50E-06 CE141 3.55E-06 2.37E-06 2.71E-07 0. l.llE-06 7.67E-05 l.58E-05 CE143+0 3.32E-08 2.42E-08 2.70E-09 0. l.OBE-08 l.63E-05 3.19E-05 CE144+D 6.llE-04 2.53E-04 3.28E-05 0. l.51E-04 l.67E-03 l.OSE-04 PR143 l.67E-06 6.64E-07 8.28E-08 0. 3.86E-07 6.04E-05 2.67E-05 PR144 5.37E-12 2.20E-12 2.72E-13 0. l.26E-12 2.19E-07 2.94E-14 ND147+0 9.83E-07 l.O?E-06 6.41E-08 0. 6.28E-07 4.65E-05 2.28E-05 PM147 l.15E-04 l.lOE-05 4.50E-06 0. '2.lOE-05 l.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 8.88E-08 4.48E-08 0. l.60E-07 6.52E-05 6.14E-05 PM149 4.91E-08 6.89E-09 2.84E-09 0. l.31E-08 l.24E-05 2.79E-05 PM151 l.20E-08 l.99E-09 l.OlE-09 0. 3.57E-09 6.56E-06 2.27E-05 SM151 l.07E-04 2.lOE-05 4.86E-06 0. 2.27E-05 7.68E-05 3.53E-06 SM153 2.43E-08 2.0lE-08 l.47E-09 0. 6.56E-09 7.llE-06 l.77E-05 EU152 2.96E-04 7.19E-05 6.30E-05 0. 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 l.96E-05 l.21E-05 0. 7.65E-05 l.51E-03 5.97E-05 EU156 2.70E-06 2.03E-06 3.30E-07 0. l.36E-06 l.37E-04 4.56E-05 TB160 3.04E-05 0. 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 3.0lE-10 0. 0. 2.95E-06 2.69E-07 Wl85 2.78E-07 9.17E-08 9.73E-09 0. O~ 9.60E-05 l.14E-05 Wl87 l.50E-09 l.22E-09 4.29E-10 0. 0. 5.92E-06 2.21E-05
49
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8

* TABLE 1.7 (contd)

TEEN INHALATION DOSE COMMITMENT FACTORS CMREM/50Y PER PC! INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB210+0 3.09E-02 8.28E-03 l.O?E-03 0. 2.95E-02 4.52E-02 3.87E-05 BI210+0 0. 2.26E-06 1.89E-07 0. 2.74E-05 1.91E-03 3.19E-05 P0210 5.68E-04 1.22E-03 1.37E-04 0. 4.21E-03 5.41E-02 4.45E-05 RN222+0 0. 0. 0. 0. 0. 3.94E-06 0.
RA223+0 2.57E-04 3.93E-07 5.14E-05 0. .1.12E-05 4.39E-02 3.04E-04 RA224+0 2.83E-05 6.77E-08 5.65E-06 0. l.93E-06 1.51E-02 3.29E-04 RA225+0 4.28E-04 5.04E-07 8.56E-05 0. 1.44E-05 5.04E-02 2.89E-04 RA226+0 1.33E-01 3.38E-06 9.87E-02 0. 9.67E-05 2.02E-01 3.llE-04 RA228+0 5.34E-02 1.74E-06 5.BBE-02 0. 4.97E-05 2.78E-01 5.30E-05 AC225 6.04E-04 8.25E-04 4.06E-05 0. 9.47E-05 3.BlE-02 2.?0E-04 AC227+0 2.49E+OO 3.69E-01 1.48E-01 0. l.O?E-01 4.16E-01 5.38E-05 TH227+0
3.09E-04 5.56E-06 8.93E-06 0. 3.lBE-05 6.50E-02 3.57E-04 TH228+0 2.60E-01 4.37E-03 8.78E-03 0. 2.45E-02 1.69E+OO 3.?0E-04 TH229 9:06E+OO 1.36E-01 4.45E-Ol 0. 6.67E-Ol 5.05E+OO 3.36E-04 TH230 2.34E+OO l.34E-Ol 6.49E-02 0. 6.55E-Ol 8.98E-Ol 3.95E-05 TH232+0 2.61E+OO 1.14E-Ol 9.21E-02 0. 5.60E-Ol 8.60E-01 3.36E-D5 TH234 2.32E-06 l.35E-07 6.71E-08 0. 7.73E-07 3.26E-04 7.49E~b5 PA231+0 5.32E+OO 2.00E-01 2.0?E-01 0. l.12E+OO 9.91E-02 4.71E-05 PA233 l.68E-06 3.24E-07 2.89E-07 0. 1.22E-06 5.39E-05 1.00E-05 U232+0 7.31E-02 0. 5.23E-03 0. 7.94E-03 3.84E-Ol 4.46E-05 U233+D 1.55E-02 0. 9.42E-04 0. 3.63E-03 9.lBE-02 4.12E-05
U234 1.48E-02 0. 9.23E-04 0. 3.55E-03 8.99E-02 4.04E-05
U235+D 1.42E-02 0. 8.67E-04 0. 3.34E-03 8.44E-02 5.13E-05 U236 l.42E-02 0. 8.86E-04 0. 3.41E-03 8.62E-02 3.79E-05 U237 5.25E-08 0. 1.40E-08 0. 2.16E-07 1.76E-05 1.29E-05 U238+D 1.36E-02 0. 8.lOE-04 0. 3.12E-03 7.89E-02 3.62E-05 NP237+0 1.77E+OO 1.54E-01 7.21E-02 0. 5.35E-01 8.99E-02 5.22E-05 NP238 4.23E-07 1:13E-08 6.59E-09 0. 3.88E-08 1.75E-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-01 7.22E-02 0. 3.lOE-01 3.12E-01 4.79E-05 PU239 3.31E+OO 4.50E-01 8.05E-02 0. 3.44E-01 2.93E-01 4.37E-05 PU240 3.31E+OO 4.49E-01 8.04E-02 0. 3.43E-01 2.93E-01 4.46E-05 PU24l+D 6.97E-02 3.57E-03 1.40E-03 0. 6.47E-03 2.60E-04 9.17E-07 PU242 3.07E+OO 4.33E-01 7.75E-02 0. 3.31E-01 2.82E-01 4.29E-05 PU244 3.59E+OO 4.96E-01 8.BBE-02 0. 3.79E-01 3.23E-01 6.39E-05 AM241 1.06E+OO 4.0?E-01 7.lOE-02 0. 5.32E-01 1.05E-01 4.88E-05 AM242M 1.07E+OO 3.93E-01 7.15E-02 0. 5.30E-01 4.21E-02 6.14E-05 AM243 l.06E+OO 3.92E-01 6.95E-02 0. 5.21E-01 9.91E-02 5.72E-05 CM242 2.12E-02 2.14E-02 1.41E-03 0. 6.40E-03 6.76E-02 5.21E-05 CM243 8.45E-Ol 3.50E-01 5.00E-02 0. 2.34E-01 1.09E-Ol 5.13E-05 CM244 6.46E-Ol 3.03E-Ol 3.88E-02 0. l.BlE-01 1.05E-Ol 4.96E-05 CM245 l.32E+OO 4.llE-01 7.53E-02 0. 3.52E-01 l.OlE-01 4.63E-05 CM246 1.31E+OO 4.llE-01 7.52E-02 0. 3.51E-01 1.03E-Ol 4.54E-05 CM247+0 l.28E+OO 4.04E-Ol 7.41E-02 0. 3.46E-01 1.0lE-01 5.97E-05 CM248 l.06E+Ol 3.33E+OO 6.llE-01 0. 2.85E+OO 8.32E-Ol 9.63E-04 CF252 l.29E+OO 0. 3.0?E-02 0. 0. 3.43E-Ol 1.89E-04 50
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
------------ TABLE 1.7 (contd)
ADULT INHALATION DOSE COMMITMENT FACTORS CMREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3* 0. l.58E-07 l.58E-07 l.58E-07 l.58E-07 l.58E-07 l.58E-07 BElO l.98E-04 3.06E-05 4.96E-06 0. 0. 2.22E-04 l.67E~05 Cl4 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Nl3 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 Fl8 4.71E-07 0. 5.19E-08 0. 0. 0. 9.24E-09 NA22 l.30E-05 l.30E-05 l.30E-05 l.30E-05 l.30E-05 l.30E:o5 l.30E-05 NA24 l.28E-06 l.28E-06 l.28E-06 l.28E-06 l.28E-06 l.28E-06 l.28E-06 P32 l.65E-04 9.64E-06 6.26E-06 0. 0. 0. l.OBE-05 AR39 0. 0. 0. 0. 0. 2.0SE-09 0.
AR41 0. 0. 0. 0. 0. 8.06E-09 0.
CA41 3.83E-05 0. 4.13E-06 0. 0. 3.83E-06 2.86E-07 SC46 5.51E-05 l.07E-04 3.llE-05 0. 9.99E-05 0. 3.23E-05 CR51 0. 0. l.25E-08 7.44E-09 2.85E-09 l.SOE-06 4.15E-07 MN54 o: 4.95E-06 7.87E-07 0. l.23E-06 l.75E-04 9.67E-06 MN56 0. l.55E-10 2.29E-ll 0. l.63E-10 l.lSE-06 2.53E-06 FE55 3.07E-06 2.12E-06 4.93E-07 0. 0. 9.0lE-06 7.54E-07 FE59 l.47E-06 3.47E-06 l.32E-06 0. 0. l.27E-04 2.35E~Q5 C057 0. 8.65E-08 8.39E-08 0. 0. 4.62E-05 3.93E-06 COSS 0. l.98E-07 2.59E-07 0. O: l.16E-04 l.33E-05 C060 0. l.44E-06 l.85E-06 0. 0. 7.46E-04 3.56E-05
NI59 NI63 NI65 CU64
. ZN65 ZN69M+D 4.06E-06 5.40E-05 l.92E-10 0.
4.0SE-06 l.02E-09 l.46E-06 6.77E-07 0.
3.93E-06 l.SlE-06 0.
2.62E-ll l.14E-ll 0.
l.83E-10 7.69E-ll 0.
l.29E-05 5.82E-06 0.
2.45E-09 2.24E-10 0.
0.
0.
0.
8.20E-06 6.llE-07 .
2.23E-05 l.67E-06 7.00E-07 l.54E-06 5.78E-10 8.48E-07 6.12E-06 8.62E-06 l.OSE-04 6.68E-06 l.48E-09 2.38E-06 l.71E-05 ZN69 4.23E-12 8.14E-12 5.65E-13 0. 5.27E-12 l.15E-07 2.04E-09 SE79 0. 3.83E-07 6.09E-08 0.
5.69E-07 4.47E-05 3.33E-06 BR82 0. 0. l.69E-06 0. 0. 0. l.30E-06 BR83+D 0. 0. 3.0lE-08 0. 0. 0. 2.90E-08 BR84 0. 0. 3.91E-08 0. 0. O.* 2.0SE-13.
BR85 0. 0. l.60E-09 0. 0. 0. 0.
KR83M 0. 0. 0. 0. 0. 5.19E-10 0.
KR85M 0. 0. 0. 0. 0. 2.91E-09 0.
KR85 0. 0.
0. 0. 0. 2.41E-09 0.
KR87 0. 0. 0. 0. 0. l.53E-08 0.
KR88+D 0. 0. 0. 0. 0. 3.13E-08 0.
KR89 0. 0. 0. 0. 0. 2.13E-08 0.
RB86 0. 1.69E-05 7.37E-06 0. 0. 0. 2.0SE-06 RB87 0. 9.86E-06 3.21E-06 0. 0. 0. 2.88E-07 RB88 0. 4.84E-08 2.41E-08 0. 0. 0. 4.lSE-19 RB89+D 0. 3.20E-08 2.12E-08 0. 0. 0. l.16E-21 SR89+D 3.BOE-05 0. 1.09E-06 0. 0. 1.75E-04 4.37E-05 SR90+D 1.24E-02 0. 7.62E-04 0. 0. 1.20E-03 9.02E-05 SR91+D 7.74E-09 0. 3.13E-10 0. 0. 4.56E-06 2.39E-05 SR92+D 8.43E-10 0. 3.64E-ll 0. 0. 2.06E-06 5.38E-06
*Includes a 50% increase to account for percutaneous transpiration.
51
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 1.7 (contd)
ADULT INHALATION DOSE COMMITMENT FACTORS CMREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 2.61E-07 0. 7.0lE-09. 0. 0. 2.12E-05 6.32E-05 Y91M+D 3.26E-ll 0. l.27E-12 0. 0. 2.40E-07 l.66E-10 Y91 5.78E-05 0. l.55E-06 0. 0. 2.13E-04 4.BlE-05 Y92 l.29E-09 0. 3.77E-ll 0. 0. l.96E-06 9.19E-06 Y93 l.18E-08 0. 3.26E-10 0. 0. 6.06E-06 5.27E-05 ZR93+D 5.22E-05 2.92E-06 l.37E-06. 0. l.llE-05 2.13E-05 l.51E-06 ZR95+D l.34E-05 4.30E-06 2.91E-06 0. 6.77E-06 2.21E-04 l.88E-05 ZR97+b l.21E-08 2.45E-09 l.13E-09 0. 3.71E-09 9.84E-06 6.54E-05 NB93M. 3.lOE-05 l.OlE-05 2.49E-06 0. l.16E-05 3.llE-05 2.38E-06 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. 3.55E-07 5.llE-05 3.79E-06 M099+D 0. l.51E-08 2.87E-09 0. 3.64E-08 l.14E-05 3.lOE-05 TC99M 1:29E-13 3.64E-13 4.63E-12 0. 5.52E-12 9.55E-08 5.20E-07 TC99 3.13E-08 4.64E-08 l.25E-08 0. 5.85E-07 l.OlE-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+D l.91E-07 0. 8.23E-08 0. 7.29E-07 6.31E-05 l.38E~Q5 RU105+D 9.88E-ll 0. 3.89E-ll 0. l.27E-10 l.37E-06 6.02E-06 RU106+D 8.64E-06 0. l.09E-06 0. l.67E-05 l.17E-03 l.14E-04 RH105 9.24E-10 6.73E-10 4.43E-10 0. 2.86E-09 2~41E-06 l.09E-05 PD107 0. 8.27E-08 5.87E-09 0. 6.57E-07 9.47E-06 7.06E-07 .
PD109 0. 4.63E-10 l.16E-10 0. 2.35E-09 l.85E-06 l.52E-05 AGllOM+O l.35E-06 1.25E-06 7.43E-07 0. 2.46E-06 5.79E-04 3.78E-05 AGlll 4.25E-08 1.78E-08 8.87E-09 0. 5.74E-08 2.33E-05 2.79E-05 CD113M 0. l.54E-04 4.97E-06 0. 1.71E-04 2.0BE-04 l.59E-05 CD115M 0. 2.46E-05 7.95E-07 0. l.98E-05 l.76E-04 4.SOE-05 SN123 3.02E-05 6.67E-07 9.82E-07 5.67E-07 0. 2.SSE-04 3.92E-05 SN125+D 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0. 7.37E-05 6.SlE-05 SN126+D 1.58E-04 4.lSE-06 6.00E-06 l.23E~06 0. l.17E-03 l.59E-05 SB124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0. 3.lOE-04 5.0BE-05 SB125+0 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0. 2.lSE-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 1.31E-07 1.55E-06 3.92E-05 8.83E-06 TE127M+D 1.58E-06 7.21E-07 1.96E-07 4.llE-07 5.72E-06 1.20E-04 l.87E-05 TE127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 TE129M+D 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 l.45E-04 4.79E-05 TE129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 l.96E-08 TE131M+D 8.74E-09 5.45E-09 3.63E-09 6.SBE-09 3.86E-08 l.82E-05 6.95E-05 TE131+D l.39E-12 7.44E-13 4.49E-13 l.17E-12 5.46E-12 1.74E-07 2.30E-09 TE132+D 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 TE133M+D 7.24E-12 5.40E-12 4.17E-12 6.27E-12 3.74E-11 5.51E-07 5.49E-08 TE134+D 3.84E-12 3.22E-12 l.57E-12 3.44E-12 2.lBE-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 l.68E-06 6.60E-07 l.42E-04 2.61E-06 0. 9.61E-07 1131+0 3.15E-06 4.47E-06 2.56E-06 l.49E-03 7.66E-06 0. 7.85E-07 52
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
----------------------- TABLE 1.7 (contd)
ADULT INHALATION DOSE COMMITMENT FACTORS CMREM/50Y PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 l.45E-07 4.07E-07 l.45E-07 l.43E-05 6.48E-07 0. 5.0SE-08 1133+0 l.OBE-06 l.85E-06 5.65E-07 2.69E-04 3.23E-06 0. l.llE-06 1134 8.05E-08 2.16E-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 l.39E-06 0. 6.56E-07 XE131M 0. 0. 0. 0. 0. l.40E-09 0.
XE133M 0. 0. 0. 0. 0. 1.89E-09 0.
XE133 0. 0. 0. 0. 0. 1.57E-09 0.
XE135M 0. 0. 0. 0. 0. 2.22E-09 0.
XE135 0. 0. 0. 0. 0. 4.05E-09 0.
XE137 0. 0. 0. 0. 0. 1.74E-08 0.
XE138+0 0. 0. 0. 0. 0. 2.44E-08 0.
CS134M+O l.59E-08 3.20E-08 l.72E-08 0. l.83E-08 2.93E-09 7.92E-09 CS134 4.66E-05 l.06E-04 9.lOE-05 0. 3.59E-05 1.22E-05 1.30E-06 CS135 1~46E-05 l.29E-05 5.99E-06 0. 5.llE-06 l.57E-06 2.llE-07 CS136 4.BBE-06 1.83E-05 1.38E-05 0. l.07E-05 1.50E-06 l.46E-06 CS137+0 5.98E-05 7.76E-05 5.35E-05 0. 2.78E-05 9.40E-06 1.05E~06 CS138 4.14E-08 7.76E-08 4.05E-08 0. 6.00E-08 6.07E-09 2.33E~l3 CS139+0 2.56E-08 3.63E-08 l.39E-08 0. 3.05E-08 2.84E-09 5.49E-31 BA139 l.17E-10 8.32E-14 3.42E-12 0. 7.78E-14 4.70E-07 1.12E-07 BA140+0 4.88E-06 6.13E-09 3.21E-07 0. 2.09E-09 l.59E-04 2.73E-05
BA141+0 BA142+0 LA140 LA141 LA142 CE141 l.25E-ll 3.29E-12 4.30E-08 5.34E-10 8.54E-ll 2.49E-06 9.41E-15 4.20E-13 0.
3.38E-15 2.07E-13 0.
2.17E-08 5.73E-09 0.
l.66E-10 2.71E-ll 0.
3.88E-11 9.65E-12 0.
l.69E-06 1.91E-07 0.
8.75E-15 2.42E-07 l.45E-17 2.86E-15 l.49E-07 l.96E-26 0.
0.
0.
l.70E-05 5.73E-05 1.35E-06 7.31E-06 7.91E-07 2.64E-07 7.83E-07 4.52E-05 1.50E-05 CE143+0 2.33E-08 l.72E-08 l.91E-09 0. 7.60E-09 9.97E-06 2.83E-05 CE144+0 4.29E-04 1.79E-04 2.30E-05 0. 1.06E-04 9.72E-04 l.02E-04 PR143 l.17E-06 4.69E-07 5.80E-08 0. 2.70E-07 3.51E-05 2.SOE-05 PR144 3.76E-12 l.56E-12 l.91E-13 0. 8.81E-13 l.27E-07 2.69E-18 ND147+0 6.59E-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. 1~49E-05 6.60E-05 5.54E-06 PM148M+O 9.82E-06 2.54E-06 l.94E-06 0. 3.85E-06 2.14E-04 4. 18E-05 PM148 3.84E-07 6.37E-08 3.20E-08 0. l.20E-07 3.91E-05 5.80E-05 PM149 3.44E-08 4.87E-09 l.99E-09 0. 9.19E-09 7.21E-06 2.SOE-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 l.48E-05 3.55E-06 0. l.66E-05 4.45E-05 3.25E-06 SM153 l.?OE-08 l.42E-08 l.04E-09 0. 4.59E-09 4.14E-06 l.58E-05 EU152 2.38E-04 5.41E-05 4.76E-05 0. 3.35E-04 3.43E-04 l.59E-05 EU154 7.40E-04 9.lOE-05 6.48E-05 0. 4.36E-04 5.84E-04 3.40E-05 EU155 l.OlE-04 l.43E-05 9.21E-06 0. 6.59E-05 9.46E-05 5.95E-06 EU156 l.93E-06 l.48E-06 2.40E-07. 0. 9.95E-07 8.56E-05 4.50E-05 TB160 2.21E-05 0. 2.75E-06 0. 9.lOE-06 l.92E-04 2.68E-05 H0166M 3.37E-04 l.OSE-04 8.00E-05 0. l.57E-04 3.94E-04 1.59E-05 Wl81 6.23E-09 2.03E-09 2.l?E-10 0. 0. l.71E-06 2.53E-07 Wl85 l.95E-07 6.47E-08 6.81E-09 0. 0. 5.57E-05 l.07E-05 W187 l.06E-09 8.85E-10 3.lOE-10 0. 0. 3.63E-06 1.94E-05
53
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8

* TABLE 1.7 (contd)

ADULT INHALATION DOSE COMMITMENT FACTORS CMREM/SOY PER PCI INHALED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB210+D 2.64E-02 6.73E-03 8.37E-04 0. 2.12E-02 2.62E-02 3.65E-05 BI210+D 0. 1.59E-06 l.32E-07 0. l.92E-05 1.llE-03 2.95E-05 P0210 3.97E-04 8.60E-04 9.58E-05 0. 2.95E-03 3.14E-02 4.19E-05 RN222+D 0. 0. 0. 0. 0. 2.05E-06 0.
RA223+D 1.BOE-04 2.77E-07 3.60E-05 0. 7.85E-06 2.55E-02 2.84E-04 RA224+D 1.98E-05 4.78E-08 3.96E-06 0. l.35E-06 8.77E-03 3.0lE-04 RA225+D 3.00E-04 3.56E-07 5.99E-05 0. l.OlE-05 2.92E-02 2.71E-04 RA226+D 1.25E-Ol 2.39E-06 9.14E-02 0. 6.77E-05 1.l?E-01 2.94E-04 RA228+D 4.41E-02 l.23E-06 4.78E-02 0. 3.48E-05 l.61E-Ol 5.00E-05 AC225 4.23E-04 5.82E-04 2.84E-05 0. 6.63E-05 2.21E-02 2.52E-04 AC227+D 2.30E+OO 3.05E-01 1.36E-01 0. 9.82E-02 2.41E-01 5.0BE-05 TH227+D 2.l?E-04 3.92E-06 6.25E-06 0. 2.22E-05 3.77E-02 3.34E-04 TH226+D 2.00E-01 3.39E-03 6.77E-03 0. 1.89E-02 1.0lE+OO 3.49E-04.
TH229 8.88E+OO 1.33E-01 4.36E-01 0. 6.52E-01 3.49E+OO 3.l?E-04 TH230 2.29E+OO 1.31E-01 6.36E-02 0. 6.40E-01 6.21E-01 3.73E-05 TH232+D 2.56E+OO 1.12E-01 9.04E-02 0. 5.47E-01 5.96E-Ol 3.l?E-05 TH234 1.63E-06 9.56E-08 4.?0E-08 0. 5.41E-07 1.89E-04 7.03E~05 PA231+D 5.0BE+OO 1.91E-01 1.98E-01 0. 1.07E+OO 5.75E-02 4.44E-0'5 PA233 1.21E-06 2.42E-07 2.09E-07 0. 9.15E-07 3.52E-05 l.02E-05 U232+D 5.14E-02 0. 3.66E-03 0. 5.56E-03
2.22E-01 4.21E-05 U233+D 1.09E-02 0. 6.60E-04 0. 2.54E-03 5.32E-02 3.89E-05
U234 1.04E-02 0. 6.46E-04 0. 2.49E-03 5.22E-02 3.81E-05 .
U235+D 1.00E-02 0. 6.0?E-04 0. 2.34E-03 4.90E-02 4.84E-05 U236 1.00E-02 0. 6.20E-04 0. 2.39E-03 5.00E-02 3.57E-05 U237 3.67E-08 0. 9.77E-09 0. 1.51E-07 1.02E-05 1.20E-05 U238+D 9.58E-03 0. 5.67E-04 0. 2.lBE-03 4.58E-02 3.41E-05 NP237+D 1.69E+OO 1.47E-01 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 1.02E-05 2.13E-05 NP239 2.87E-08 2.82E-09 1.55E-09 0. 8.75E-09 4.?0E-06 l.49E-05 PU238 2.74E+OO 3.87E-Ol 6.90E-02 0. 2.96E-Ol 1.82E-01 4.52E-05 PU239 3.19E+OO 4.31E-Ol 7.75E-02 0. 3.30E-01 1.72E-Ol 4.13E-05 PU240 3.18E+OO 4.30E-Ol 7.73E-02 0. 3.29E-Ol 1.72E-01 4.21E-05 PU241+D 6.41E-02 3.28E-03 1.29E-03 0. 5.93E-03 l.52E-04 8.65E-07 PU242 2.95E+OO 4.15E-Ol 7.46E-02 0. 3.17E-Ol l.65E-Ol 4.05E-05 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-Ol 6.71E-02 0. 5.04E-Ol 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 l.OlE+OO 3.47E-Ol 6.57E-02 0. 4.95E-Ol 5.75E-02 5.40E-05 CM242 l.48E-02 l.51E-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. l.64E-Ol 6.06E-02 4.68E-05 CM245 l.26E+OO 3.59E-Ol 7.14E-02 0. 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 CM247+D l.22E+OO 3.53E-Ol 7.03E-02 0. 3.28E-Ol 5.85E-02 5.63E-05 CM248 l.OlE+Ol 2.91E+OO 5.79E-Ol 0. 2.70E+OO 4.82E-Ol 9.09E-04 CF252 9.78E-Ol 0. 2.33E-02 0. 0. l.99E-Ol l.78E-04 54
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 1.8 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATION GROUND (DFG 1l (MREM/HR PER PCI/M 2 )
ELEMENT TOTAL 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 2.20E-10 2.60E-iO Mn-54 5.80E-09 6.80E-09 Mn-56 1.lOE-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 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1. 70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 . 6 .40E-11 9.30E-11 Br-84 . 1.20E-08 l.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.lOE-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.lOE-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1. lOE-09 Tc-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 1.50E-09 1.80E-09 Ag.,llOm 1.80E-08 2.lOE-08 Te-125m 3.50E-11 4.80E-.11 Te-127m 1.lOE-12 1.30E-12
Te-127 1. OOE-11 55 1.lOE-11
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8

* TABLE 1.8 (continued)

EXTERNAL DOSE FACTORS FOR STANDING ON CO~TAMINATION GROUND CDFG 1l CMREM/HR PER PCI/M )
ELEMENT TOTAL BODY . SKIN Te-129m 7.70E-10 9.00E-10 Te-129 7.lOE-10 8.40E-10 Te-131m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1. 70E-09 2.00E-09 I-130 1.40E-08 1. 70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.SOE-09 I-134 1.60E-08 1. 90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1. 70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.lOE-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 Ba-142 7.90E-09 9.00E-09 La-140 1. 50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3. 20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2. OOE-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.lOE-09 3.60E-09 Np-239 9.50E-10 1. lOE-09 56
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
TABLE 1. 9 1994 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Dose Factor Annual Quantity Nuclide Organ mrem/Ci ~ ci )
Ag-llOm GI Tract-T 1. 06E+OO 1. 42E+Ol Ar-41 Total Body 3.51E-04 1. 42E+04 Ba-139 GI Tract-C 3.00E-03 5.00E+03 Ba-140 Lung-T 1.06E-01 l.42E+02 Br-82 Total Body-I 1.47E-03 3.40E+03 C-14 Bone-C 1.29E-Ol l.16E+02 Ce-141 GI Tract-T 1.17E-Ol l.28E+02 Ce-144 GI Tract-T 3.lOE+OO 4.84E+OO Co-57 GI Tract-T 7.85E-02 1. 91E+02 Co-58 GI Tract-T 1.39E-01 l.08E+02 Co-60 Total Body-C 2.77E-01 1.81E+Ol Cr-51 GI Tract-A.T 2.17E-03 6.91E+03 Cs-134 Liver-C 6.39E+OO 2.35E+OO Cs-136 Total Body- I 1. 51E-01 3.31E+Ol Cs-137 Bone-C 6.24E+OO 2.40E+OO Cs-138 Total Body-C 2.89E-05 1. 73E+05
Fe-55 Fe-59 H-3 I-131 I-132 I-133 I-134 Bone-C GI Tract-T Total Body-C Thyroid-I Thyroid-C Thyroid-C Thyroid-C 1.90E-01 2.22E-01
1. 48E-04 1.51E+Ol 1.0SE-02 2.09E-Ol 2.76E-03 7.89E+Ol 6.76E+Ol 3.38E+04 9.93E-Ol
1. 43E+03 7 .18E+Ol 5.43E+03 I-135 Thyroid-C 4.30E-02 3.49E+02 Kr-83m Skin 8.51E-07
1.76E+07 Kr-85 SKin 7.68E-05 1.95E+05 Kr-85m Total Body 4.65E-05 l.08E+05 Kr-87 Skin 8.24E-04 l.82E+04 Kr-88 Total Body 5.84E-04 8.56E+03 Kr-89 . Total Body 6.59E-04 7.59E+03 La-140 GI Tract-T 2.53E-02 5.93E+02 Mn-54 GI Tract-T 2.24E-Ol 6.70E+Ol Mn-56 GI Tract-C 6.41E-03 2.34E+03 Mo-99 GI Tract-T 1.40E-02 l.07E+03 N-13 Total Body-C 4.48E-06 1. 12E+06 Na-24 Total Body-C 8.37E-04 5.97E+03 Nb-95 GI Tract-T 9.88E-02 1. 50E+02 Ni-65 GI Tract-C 4.37E-03 3.43E+03 N~-239 GI Tract-T 6.86E-03 2.19E+03 R -88 Total Body-C 1.90E-05 2.63E+05 Ru-103 GI Tract-T 1. 27E-01 l.18E+02 Ru-105 GI Tract-C 5.17E-03 2.90E+03 Sb-124 GI Tract-T 7.15E-01 2. lOE+Ol Sb-125 GI Tract-T 4.03E-01 3.72E+Ol 57
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 1.9 (continued) 1994 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Dose Factor Annual Quantity Nuclide Organ mrem/Ci ~ ci 2 Sr-89 Bone-C 8.38E+OO l.79E+OO Sr-90 Bone-C 3.45E+02 4.35E-02 Sr-91 Bone-I 2.13E+OO 7.04E+OO Sr-92 GI Tract-C 1. 26E-02 l.19E+03 Tc-99m GI Tract-T 3.19E-04 4.70E+04 Tc-101 GI Tract-I 4.39E-05 3.42E+05 Te-127 GI Tract-T 4.20E-03 3.57E+03 Xe-13lm Skin 3.39E-05 4.42E+05 Xe-133 Total Body l.l?E-05 4.27E+05 Xe-133m Skin 7.08E-05 2.12E+05 Xe-135 Total Body 7.19E-05 6.95E+04 Xe-135m Total Body l.24E-04 4.03E+04 Xe-137 Skin 7.59E-04 1. 98E+04 Xe-138 Total Body 3.51E-04
l.42E+04 Zn-65 Total Body-C 4.22E-Ol l.18E+Ol Zr-95 GI Tract-T 2.93E-Ol 5.12E+Ol 58
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 II.
A.
LIQUID EFFLUENTS CONCENTRATION
1. Requirements Appendix A.Section III.G requires that the concentration of radioactive material released at any time from the site to unrestricted areas shall be limited to ten times the Effluent Concentration (EC) specified 4n 10 CFR 20. Appendix B. Table 2.
Column 2 for nuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases. the concentration shall be limited to 2E-04 µCi/ml total activity. To ensure compliance. the following approach will be used for each release.
2. Prerelease Analysis Most tank~ will be recirculated through two volume changes prior to sampling for release to the ~nvironment 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 sa_mpling data. may be used.
to determine appropriate recirculation time .
Prior to release. a grab sample will be analyzed for each release.
and the concentration of each radionuclide determined.
. C ;;;
n I:;;1 Ci l
( 2 .1) where:
c = Total concentration in the liquid effluent at the release point. µCi /ml ..
= Concentration of a single radionuclide i. µCi/ml.
59
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 *
3. Effluent Concentration CEC)
Sum of the Ratios The EC-Fraction (Rj) for each release point will be calculated by the relationship defined by Note 4 of Appendix B. 10 CFR 20:
R.=L.,.t J
'°'
l Ci ECi
~10.0 (2.2) where:
Effluent concentration of radionuclide i. µCi/ml.
The EC of radionuclide i. 10 CFR 20. Appendix B. Table 2.
Column 2 - µCi/ml.
~j The Total EC-Fraction for the release point.
The sum of the ratios at the discharge to the lake must be ~ 10 due to the releases from any or all concurrent releases. The following*
relationship will assure this criterion is met: **
f 1 (R 1 -l) + f 2 (R2 -l) + f 3 (R3 -l) ~ F (2.3) where:
The effluent flow rate (gallons/minute) for the respective releases. determined by Plant personnel.
The Total EC~Fractions for the respective releases as determined by Equation 2.2.
F = Minimum required dilution flow rate. Normally. a conservatively high dilution flow rate is used. that is. flow rate used= Cbi)(F) where bi is a conservative factor greater than 1.0.
60
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
- -INSTRUMENT B.
SETPOINTS
1. Setpoint Determination Appendix A.Section III.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 is contained in Figure 2-2.
The respective alarm/trip setpoints at each release point will be set such that the sum of the ratios at each point. as calculated 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 specifi~d in.*'
Section 2.1.1 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 -
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 .
61
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
3. Post-Release Analysis A post-release analysis will be done using actual release data to ensure that the limits specified in Section 1 were not exceeded.
A composite list on concentrations (Ci). 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 ~ompliance with the limits in Section 1.
This data and setpoints will be recorded in auditable records by Plant personnel.
C. DOSE
1. RETS Requirement Appendix A.Section III.H.l requires that the quantity of radionuclides released by limited such that the dose or dose 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 radionuclide released will be summed for each release and accumulated for each quarter as follows in Section 2.
2. Release Analysis Calculations shall be performed for each batch release. and weekly for continuous releases according to the formula:
E Ai/Ci 1
s; 0. 5 (2.5) where:
Cumulative quarterly activity of nuclide i identified in liquid release CC;).
= Design objective annual quantity of radionuclide from Table 2.2.
62
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 The design basis quantities are derived in such a conservative manner that doses may be greatly overestimated by this technique.
As a consequence of this conservatism. and in light 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 (Ci). and the dose per Curie (Oc/Cc)i for each 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 equation:
i Dj ~ (DCF) ij x Ii i=l (2.6) where:
Dose for the jth organ from radionuclides releases.
mrem.
j = The organ of interest.
= Ingestion ~ose commitment factor for the jth organ from the it radionuclide mrem/pCi. see Table 2.1.
I; Activity ingested of the ;th. radionuclide. pCi.
I; is described by:
I. = (Ai) (V) (365) (1E06)
]. (1000) (d)
( 2. 7) where:
365 Days per year.
A; Annual activity released of ;th 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.
63
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 1000 = Dispersion factor from discharge to nearest drinking water supply.
1E06 = Conversion µCi to pCi.
The dose equation then becomes:
i D*J = (3. 65E05) (V) d E (DCF) ij x Ai mrem i=l (2.8)
b. Fish Ingestion The dose to an individual from the consumption of fish is described by Equation 2.10. In this case the activity ingested of the ;th radionuclide CI 1 ) is described by:
Ai Bi F ( 1E09)
Ii = 15d = pCi (2 .9{
where:
Annual released of radionuclide. µCi.
th
µCi/gm Fish concentration factor of ;th radionuclide µCi/ml Csee Table 2. O) .
F = Amount of fish eaten per year (21 kg adult. 16 kg teen. 6.9 kg child. none infant.)
15 = Dispersion factor from discharge to 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:
Dj = (6. 7E07) F d
°"i
~ Ai x Bi x DCFi m:rem i=l (2.10) 64
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
c. Annual Analysis A complete analysis utilizing the NRC computer code LADTAP with the total source release will be done annually in conjunction with the annual environmental report. This analysis 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 radionuclides. Dj. is described by:
m Dj :::; L Dij mrem
~:::;1 (2.11) m
~ (DCF) ij x Ij mrem l

::;l where:
Dj Dose to the /h organ from the i th radionuclide. mrem.
j The organ of interest (bone. GI tract. thyroid.
liver. kidney, lung or total body).
Adult ingestion dose commitment factor for the jth organ from the ;th radionuclide. mrem/pCi (see Table 2.1).
Activity ingested of the ;th radionuclide. µCi.
I; for water ingestion is described by:
I.
1
= Ai Vr µCi vd (2.13) and for fish ingestion I; is described by:
Ai Bi Fr Ii = v d µCi where:
Activity release of jth radionuclide during the year.
µCi.
v Average rate of water consumption (2000 ml/d).
I Number of days during the year (365 d).
v Dispersion factor from point of discharge to point of exposure.
65
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 d Dilution water volume (ml).
µCi/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 di~posal) so that radioactivity in liquid effluent releases to unrestricted areas (see Figure 2-1) will not exceed the limits of Appendix A. III.H.1. 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 Cl.000 x nearest drinking water intake 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.BBE-03 mrem. The release rate which would result in a dose rate
. equivalent to 500 mrem/year Cusin~ 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 66
i
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&20 PALISADES NUCLEAR PLANT SITE BOUNDARY FIGURE 2 *I
PALISAbES RADWASTE EFFLUENTS - LIQUID J;
i:I_ r AN "~ .
Wl\~,Tf_
WSl!M STEAM GEN DLOWOOWN PRIMARY TANK SYSTEM STORAGE TANK rnr Afl.n Wl\STf T-90
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z r---.,
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5 :z a.. 0 REOlll t-1 SFRYICE ...&..~
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SUMP RUJn DrLUTION FLOW SERVICE WATER _ _...__ _.__ _ _ _ _ _ _ LA_K_E_IN_L_E_T_ _,"°
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
------------ TABLE 2.0 BIOACCUMULATION FACTORS
µCi/gm per µCi/ml FRESHWATER ELEMENT FISH H 9.0E-01 c 4.6E 03 NA 1. OE 02 p 1. OE OS CR 2.0E 02 MN 4. OE 02
, FE 1. OE 02 -
co S.OE 01 NI 1. OE 02 cu S.OE 01 ZN 2.0E 03 BR 4.2E 02 RB 2.0E 03 SR 3.0E 01 y 2.5E 01 ZR 3.3E 00 NB 3.0E 04 MO 1. OE 01 TC 1. SE 01 RU 1. OE 01 RH 1. OE 01 TE 4.0E 02 I 1. SE 01 cs 2.0E 03 BA 4.0E 00 LA 2.SE 01 CE 1. OE 00 PR 2.5E 01 ND 2.5E 01
.w 1. 2E 03 NP 1.0E 01 *
69
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS CMREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LU H3 0. 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.083-07 BElO l.71E-OS 2.49E-06 S.16E-07 0. 1. 64E-06 0. 2.78E-OS C14 2.37E-OS S.06E-06 S.06E-06 S.06E-06 S.06E-06 S.06E-06 S.06E-06 N13 S.BSE-08 S.8SE-08 S.8SE-08 S.83SE-08 S.85E-08 S.BSE-08 S.BSE-08 FlB S.19E-06 0. 4.43E.07 0. 0. 0. l.22E-06 NA22 9.83E-OS 9.83E-05 9.83E-OS 9.83E-OS 9.83E-05 9.83E-OS 9.83E-OS NA24 1. OlE-OS l.OlE-05 l.OlE-OS 1. OlE-OS 1.0lE-05 1. OlE-OS l.OlE-05 P32 1. 70E-03 1.00E-04 6.59E-05 0. 0. 0. 2 . 30E-OS AR39 0. 0. 0. 0. 0. 0. 0.
AR41 0. 0. 0. 0. 0. 0. 0.
CA41 3.74E-04 0. 4.0BE-OS 0. 0. 0. l.91E-07 SC46 3.75E-08 S.41E-08 1.69E-08 0. 3.56E-08 0. 3.S3E-05 CR51 O: 0. 1.41E-08 9.20E-09 2.0lE-09 1.79E-08 4.llE-07 MN54 0. 1.99E-05 4.51E-06 0. 4.41E-06 0. 7.31E-06 MN56 0. 8.lBE-07 1.41E-07 0. 7.03E-07 0. 7. 43E-*OS FESS 1. 39E-05 8.98E-06 2.40E-06 0. 0. 4.39E-06 1.14E-~Q6 FE59 3.0BE-05 5.38E-05 2.12E-05 0. 0. 1. 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. 1.0BE-05 2.55E-05 0. 0. 0. 2.57E-05 *
NI59 4.78E-05 1.45E-05 8.17E-06 0. 0. 0. 7.16E-07 NI63 6.34E-04 3.92E-05 2.20E-05 0. 0. 0. 1.9SE-06 NI65 4.70E-06 5.32E-07 2.42E-07 0. 0. 0. 4.0SE-OS CU64 0. 6.09E-07 2.82E-07 0. l.03E-06 0. l.2SE-05 ZN65 l.84E-05 6.31E-05 2.91E-05 0. 3.06E-05 0. S.33E-OS ZN69M+D l.SOE-06 3.06E-06 2.79E-07 0. 1.24E-06 0. 4.24E-05 ZN69 9.33E-08 l.68E-07 l.2SE-08 0. 6.98E-08 0. l.37E-05 SE79 0. 2.lOE-05 3.90E-06 0. 2.43E-05 0. 5.58E-07 BR82 0. 0. 1.27E-05 0. 0. 0. 0.
BR83+D 0. 0. 3.63E-07 0. 0. 0. 0.
BR84 0. 0. 3.82E-07 0. 0. 0. 0.
BR85 0. 0. 1. 94E-08 0. 0. 0. 0.
KR83M 0. 0. 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.
KRBB+D 0. 0. 0. 0. 0. 0. 0.
KR89 0. 0. 0. 0. 0. 0. 0.
RB86 0. 1.70E-04 8.40E-05 0. 0. 0. 4.35E-06 RB87 0. 8.BBE-05 3.52E-05 0. 0. 0. 5.98E-07 RB88 0. 4.98E-07 2.73E-07 0. 0. 0. 4.85E-07 RB89+D 0. 2.86E-07 1. 97E-07 0. 0. 0. 9.74E-08 SR89+D 2.51E-03 0. 7.20E-05 0. 0. 0. 5.16E-05 SR90+D l.85E-02 0. 4.71E-03 0. 0. 0. 2.31E-04 SR9l+D SR92+D 5.00E-05
1. 92E-05 0.
0.
l.BlE-06 0.
7.13E-07 0.
70 0.
0.
0.
0.
5.92E-OS 2.07E~04
71 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS CMREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI -LU Il32 l.66E-06 3.37E-06 l.20E-06 l.58E-04 3.76E-06 0. 2.73E.06 Il33+D l.25E-05 l.82E-05 5.33E-06 3.31E-03 2.14E-05 0. 3.0SE-06 Il34 8.69E-07 l.78E-06 6.33E-07 4.15E-05 l.99E-06 0. 1.84E-06 Il35+D 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0. 2.62E-06 XE131M 0. 0. 0. 0. 0. 0. 0.
XE133M 0. 0. 0. 0. 0. 0. 0.
XE133 0. 0. 0. 0. 0. 0. 0.
XE135M 0. 0. 0. 0. 0. 0. 0.
XE135 0. 0. 0. 0. 0. 0. 0.
XE137 0. 0. 0. 0. 0. 0. 0.
XE138+D 0. 0. 0. 0. 0. 0. 0.
CS134M+D l.76E-07 2.93E-07 1. 48E-07 0. 1.13E-07 2.60E-08 2.32E-07 CS134 3.-77E-04 7.03E-04 7.lOE-05 0. l.SlE-04 7.42E-05 l.91E-06 CS135 1.33E-04 1.21E-04 6.30E-06 0. 3.44E-05 l.31E-05 4.37E-07 CS136 4.59E-05 1.35E-04 5.04E-05 0. 5.38E-05 1. lOE-05 2.05E-06 CS137+D 5.22E-04 6. llE-04 4.33E-05 0. 1. 64E-04 6.64E-05 1. 91E.-'06 CS138 4.81E-07 7.82E-07 3.79E-07 0. 3.*90E-07 6.09E-08 1. 25E-Q6 CS139+0 3.lOE-07 4.24E-07 l.62E-07 0. 2.19E-07 3.30E-08 2.66E-08 BA139 8.81E-07 5. 84E-10 2.55E-08 0. 3.51E-10 3. 54E-10 5.58E-05 BA140+0 1.71E-04 1. 71E-07 8.81E-06 0. 4.06E-08 l.05E-07 4.20E-05
BA141+0 4.25E-07 2.91E-10 1. 34E-08 0. 1.75E-10 1.77E-10 5.19E-06
BA142+0 1.84E-07 1.53E-10 9.06E-09 0. 8.81E-ll 9. 26E-11 7.59E-07 LA140 2.llE-08 8.32E-09 2.14E-09 0. 0.. 0. 9.77E-05 LA141 2.89E-09 8.38E-10 1. 46E-10 0. 0. 0. 9.61E-05 LA142 1. lOE-09 4. 04E-10 9. 67E-11 0. 0. 0. 6.86E-05 CE141 7.87E-08 4.80E-08 5.65E-09 0. 1.48E-08 0. 2.48E-05 CE143+0 1.48E-08 9.82E-06 1.12E-09 0. 2.86E-09 0. 5.73E-05 CE144+0 2.98E-06 l.22E-06 1.67E-07 0. 4.93E-07 0. 1. 71E-04 PR143 8.18E-08 3.04E-08 4.03E-09 0. 1.13E-08 0. 4.29E-05 PR144 2.74E-10 1. 06E-10 1. 38E-ll 0. 3.84E-11 0. 4.93E-06 ND147+0 5.53E-08 5.68E-08 3.48E-09 0. 2.19E-08 0. 3.60E-05 PM147 3.88E-07 3.27E-08 1. 59E-08 0. 4.88E-08 0. 9.27E-06 PM148M+D 1.65E-07 4.18E-08 3.28E-08 0. 4.80E-08 0. 5.443-05 PM148 6.32E-08 9.13E-09 4.60E-09 0. 1.09E-08 0. 9.74E-05 PM149 1. 38E-08 1.81E-09 7.90E-10 0. 2.20E-09 0. 4.86E-05 PM151 6.18E-09 9.0lE-10 4.56E-10 0. 1.07E-09 0. 4.17E-05 SM151 2.90E-07 6.67E-08 1.44E-08 0. 4.53E-08 0. 5.58E-06 SM153 7.72E-09 5.97E-09 4.58E-10 0. l.25E-09 0. 3.12E-05 EU152 6.74E-07 1. 79E-07 l.SlE-07 0. 5.02E-07 0. l.59E-05 EU154 .2. 64E-06 3.67E-07 2.20E-07 0. 9.95E-07 0. 4.58E-05 EU155 5.42E-07 6.25E-08 3.23E-08 0. 1.40E-07 0. 8.37E-05 EU156 1.14E-07 7.06E-08 1.12E-08 0. 3.26E-08 0. 6.67E-05 TB160 2.59E-07 0. 3.24E-08 0. 7.37E-08 0. 3.45E-05 H0166M 1.25E-06 2. 69E-07 . 2.13E-07 0. 3.57E-07 0. 0.
Wl81 8.85E-08 2.72E-08 3.04E-09 0. 0. 0. 3.82E-07 Wl85 Wl87 3.62E-06 9.03E-07 1:13E-06 l.29E-07 0.
6.28E-07 2.17E-07 0.
72 0.
0.
0.
0.
1. 62E-05 3.69E-05
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
-*------------------------ TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB210+0 5.28E-02 1.42E-02 2.38E-03 0. 4.33E-02 0. 5.62E-05 BI210+0 4.16E-06 2.68E-05 3.58E-07 0. 2.08E-04 0. 5.27E-05 P0210 3.lOE-03 5.93E-03 7.41E-04 0. 1.26E-02 0. 6.61E-05 RN222+0 0. 0. 0. 0. 0. 0. 0.
RA223+D 4.41E-02 6.42E-05 8.82E-03 0. 1.17E-03 0. 3.43E-04 RA224+0 1.46E-02 3.29E-05 2.91E-03 0. 6.00E-04 0. 3.86E-04 RA225+0 5.78E-02 6.42E-05 1.15E-02 0. 1.19E-03 0. 3.24E-04 RA226+0 6.20E-01 4.76E-05 5.14E-01 0. 8.71E-04 0. 3.44E-04 RA228+0 4.32E-01 2.58E-05 4.86E-01 0. 4.73E-04 0. 5.86E-05 AC225 3.92E-05 5.03E-05 2.63E-06 0. 3.69E-06 0. 4.36E-04 AC227+0 4.49E-03 7.67E-04 2.79E-04 0. 1.56E-04 0. 8.50E-05 TH227+D 1.20E-04 2.0lE-06 3.45E-06 0. 7.41E-06 0. 5.70E-04 TH228+0 2,47E-03 3.38E-05 8.36E-05 0. 1.58E-04 0. 5.84E-04 TH229 1.48E-02 1.94E-04 7.29E-04 0. 9.29E-04 0. 5.31E-04 TH230 3.80E-03 1.90E-04 _ 1.06E-04 0. 9.12E-04 0. 6.24E-05 TH232+0 4.24E-03 1.63E-04 1.65E-04 0. 7.79E-04 0. 5.31E~b5 TH234 6.92E-07 3.77E-08 2.00E-08 0. 1.39E-07 0. 1.19E-04 PA231+0 7.57E-03 2.SOE-04 3.02E-04 0. 1.34E-03 0. 7.44E-05 PA233 3.llE-08 6.09E-09 5.43E-09 0. 1.67E-08 0; 1.46E-05
U232+0 U233+0 U234 U235+D U236 U237
2.42E-02 5.08E-03 4.88E-03 4.67E-03 4.67E-03 4.95E-07 0.
0.
0.
0.
0.-
0.
2.16E-03 0.
3.87E-04 0.
3.80E-04 0.
3.56E-04 0.
3.64E-04 0.
1.32E-07 0.
2.37E-03 0.
l.08E-03 0.
l.06E-03 0.
9.93E-04 o:
1.0lE-03 0.
1.23E-06 0.
7.04E-05 6.51E-05
6.37E-05 8.lOE-05 5.98E-05 2.llE-05 U238+D 4.47E-03 0. 3.33E-04 0. 9.28E-04 0. 5.71E-05 NP237+D 2.53E-03 1.93E-04 1.0SE-04 0. 6.34E-04 0. 8.23E-05 NP238 1.24E-07 3.12E-09 1.92E-09 0. 6.81E-09 0. 4.17E-05 NP239 1.llE-08 9.93E-10 5.61E-10 0. 1.98E-09 0. 2.87E-05 PU238 1.34E-03 1.69E-04 3.40E-05 0. l.21E-04 0. 7.57E-05 PU239 l.45E-03 l.77E-04 3.54E-05 0. l .. 28E-04 0. 6.91E-05 PU240 l.45E-03 l.77E-04 3.54E-05 0. l.28E-04 0. 7.04E-05 PU24l+D 4.38E-05 l.90E-06 8.82E-07 0. 3.l?E-06 0. l.45E-Q6 PU242 l.35E-03 l.?OE-04 3.41E-05 0. l.23E-04 0. 6.77E-05 PU244 l.57E-03 l.95E-04 3.91E-05 0. l.41E-04 0. l.OlE-04 AM241 l.53E-03 7.18E-04 l.09E-04 0. 6:55E-04 0. 7.70E-05 AM242M l.58E-03 7.02E-04 l.13E-04 0. 6.64E-04 0. 9.69E-05 AM243 l.51E-03 6.88E-04 l.06E-04 0. 6.36E-04 0. 9.03E-05 CM242 l.37E-04 l.24E-04 9.lOE-06 0. 2.62E-05 0. 8.23E-05 CM243 l.45E-03 6.88E-04 8.98E-05 0. 3.27E-04 0. 8.lOE-05 CM244 l.22E-03 6.16E-04 7.59E-05 0. 2.71E-04 0. 7.84E-05 CM245 l.88E-03 7.49E-04 l.13E-04 0. 4.32E-04 0. 7.30E-05 CM246 l.87E-03 7.49E-04 l.13E-04 0. 4.31E-04 0. 7.17E-05 CM247+D l.82E-03 7.36E-04 1.11E~04 0. 4.24E-04 0. 9.43E-05 CM248 l.51E-02 6.0?E-03 9.16E-04 0. 3.SOE-03 0. 1.52E-03
CF252 l.24E-03 0. 2.95E-05 0 73
0. 0. 2.99E-04
74 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
---------------------------- TABLE 2.1 CHILD INGESTION DOSE COMMITMENT FACTORS CMREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 4.llE-08 0. 1.lOE-09 0. 0. 0. 1.17E-04 Y91M+D 3.82E-10 0. 1.39E-11 0. 0. 0. 7.48E-07 Y91 6.02E-07 0. l.61E-08 0. 0. 0. 8.02E-05 Y92 3.60E-09 0. 1.03E-10 0. 0. 0. l.04E-04 Y93
1.14E-08 0. 3.13E-10 0. 0. 0. l.70E-04 ZR93+0 l.67E-07 6.25E-08 4.45E-08 0. 2.42E-07 0. 2.37E-05 ZR95+0 1.16E-07 2.55E-08 2.27E-08 0. 3.65E-08 0. 2.66E-05 ZR97+0 6.99E-09 1.0lE-09 5.96E-10 0. 1.45E-09 0. 1.53E-04 NB93M 1.0SE-07 2.62E-08 8.61E-09 0. 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-11 1.83E-11 0. 4.35E-11 0. 1.21E-05 M093 0. 2.41E-05 8.65E-07 0. 6.35E-06 0. 1.22E-06 M099+0 0. 1.33E-05 3.29E-06 0. 2.84E-05 0. 1.lOE-05 TC99M 9.23E-10 1.81E~09 3.00E-08 0. 2.63E-08 9.19E-10 1.03E~06 TC99 5.35E-07 5.96E-07 2.14E-07 0. 7.02E-06 5.27E-08 6.25E-06 TC101 1.07E-09 1.12E-09 1.42E-08 0. 1.91E-08 5.92E-10 3.56E~09 RU103+0 7.31E-07 0. 2.81E-07 0. 1.84E-06 0. 1.89E~G5 RU105+0 6.45E-08 0. 2.34E-08 0. 5.67E-07 0. 4.21E-05 RU106+0 1.17E-05 0. 1.46E-06 0.. 1.58E-05 0. 1.82E-04 RH105 5.14E-07 2.76E-07 2.36E-07 0. 1.lOE-06 0. 1.71E-05 P0107 0. 4.72E-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+O 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. 2.34E-07 0. 4.75E-05 CD113M 0. 1.02E-05 4.34E-07 0. 1.0SE-05 0. 2.63E-05 CD115M 0. 5.89E-06 2.51E-07 0. 4.38E-06 0. 8.0lE-05 SN123 1.33E-04 1.65E-06 3.24E-06 1.75E-06 0. 0. 6.52E-05 SN125+0 3.55E-05 5.35E-07 1.59E-06 5.55E-07 0. . 0. 1.lOE-04 SN126+0 3.33E-04 4.15E-06 9.46E-06 1.14E-06 0. 0. 2.SOE-05 SB124 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 1.50E-06 6.63E-09 0. 3.99E-06 1.71E-05 SB126 4.40E-06 6.73E-08 1.58E-06 2.58E-08 0.
2.lOE-06 8.87E-05 SB127 1.06E-06 1.64E-08 3.68E-07 1.18E-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 8.24E-05 0. 2.34E-05 TE127 4.71E-07 1.27E-07 l.OlE-07 3.26E-07 1.J4E-06 0. l.84E-05 TE129M+D 4.87E-05 l.36E-05 7.56E-06 1.57E-05 1.43E-04 0. 5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0. 8.34E-06 TE131M+D 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0. 1.0lE-04 TE131+0 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0. 4.36E-07 TE132+0 l.OlE-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0. 4.SOE-05 TE133M+D l.87E-07 7.56E-08 9.37E~os 1.45E-07 7.lBE-07 0. 5.77E-06 TE134+0 1.29E-07 5.80E-08 7.74E-08 1.02E-07 5.37E-07 0. 5.89E~07 1129 l.39E-05 8.53E-06 7.62E-06 5.58E-03 1.44E-05 0. 4.29E-07 1130 2.92E-06 5.90E-06 3.04E-06 6.SOE-04 8.82E-06 0. 2.76E-06 1131+0 l.72E-05 l.73E-05 9.83E-06 5.72E-03 2.84E-05 0. 1.54E-06 75
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 2.1 CHILD INGESTION DOSE COMMITMENT FACTORS CMREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0. 1.73E-06
1133+0 5.92E-06 7.32E-06 2.77E-06 1.36E-03 l.22E~05 0. 2.95E-06 1134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0. 5.16E-07 1135+0 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0. 2.40E-06 XE131M 0. 0. 0. 0. 0.
0. 0.
XE133M 0. 0. 0. 0. 0. 0. 0.
XE133 0. 0. 0. 0. 0. 0. 0.
XE135M 0. 0. 0. 0. 0. 0. 0.
XE135 0. 0. 0. 0. 0. 0. 0.
XE137 0. 0. 0. 0. 0. 0. 0.
XE138+0 0. 0. 0. 0. 0. 0. 0.
CS134M+O 8.44E-08 1.25E-07 8.16E-08 0. 6.59E-08 1.09E-08 1.58E-07 CS134 2:34E-04 3.84E-04 8.lOE-05 0. l.19E-04 4.27E-05 2.07E-06 CS135 8.30E-05 5.78E-05 5.93E-06 0. 2.04E-05 6.81E-06 4.33E-07 CS136 2.35E-05 6.46E-05 4.18E-05 0. 3.44E-05 5.13E-06 2.27E~06 CS137+0 3.27E-04 3.13E-04 . 4.62E-05 0. 1.02E-04 3.67E-05 1.96E~G6 CS138 2.28E-07 3.17E-07 2.0lE-07 0. 2.23E-07 2.40E-08 1.46E-07 CS139+0 1.45E-07 1.61E-07 7.74E-08 0. 1.21E-07 1.22E-08 1.45E-11 BA139 4.14E-07 2.21E-10 1.20E-08 0. 1.93E-10 1.30E-10 2.39E-05 BA140+0 8.31E-05 7.28E-08 4.85E-06 0. 2.37E-08 4.34E-08 4.21E-05 .
BA141+0 2.00E-07 1.12E-10 6.51E-09 0. 9.69E-11 6.58E-10 l.14E-07 BA142+0 8.74E-08 6.29E-11 4.88E-09 0. 5.09E-11 3.70E-ll l.14E-09 LA140 1.0lE-08 3.53E-09 1.19E-09 0. 0. 0. 9.84E-05 LA141 1.35E-09 3.17E-10 6.88E-11 0. 0. 0. 7.05E-05 LA142 5.24E-10 1.67E-10 5.23E-11 0. 0. 0. 3.31E-05 CE141 3.97E-08 1.98E-08 2.94E-09 0. 8.68E-09 0. 2.47E-05 CE143+0 6.99E-09 3.79E-06 5.49E-10 0. 1.59E-09 0. 5.55E-05 CE144+0 2.0BE-06 6.52E-07 1.llE-07 0. 3.61E-07 o.* 1.70E-04 PR143 3.93E-08 1.18E-08 1.95E~09 0. 6.39E-09 0. 4.24E-05 PR144 1.29E-10 3.99E-11 6.49E-12 0. 2.llE-11 0. 8.59E-08 ND147+0 2.79E-08 2.26E-08 1.75E-09 0. 1.24E-08 0. 3.58E-05 PM147 3.lBE-07 2.27E-08 1.22E-08 0. 4.0lE-08 0. 9.19E-06 PM148M+O 1.03E-07 2.05E-08 2.05E-08 0. 3.04E-08 0. 5.78E-05 PM148 3.02E-08 3.63E-09 2.35E-09 0. .6.17E-09 0. 9.ZOE-05 PM149 6.49E-09 6.90E-10 3.74E-10 0. 1.22E-09 0. 4.71E-05 PM151 2.92E-09 3.55E-10 2.31E-10 0. 6.02E-10 0. 4.03E-05
SM151 2.56E-07 3.BlE-08 1.20E-08 0. 3.94E-08 0. 5.53E-06 SM153 3.65E-09 2.27E-09 2.19E-10 0. 6.91E-10 0. 3.02E-05 EU152 6.15E-07 1.12E-07 1.33E-07 0. 4.73E-07 0. 1.84E-05 EU154 2.30E-06 2.07E-07 1.89E~07 0. 9.09E-07 0. 4.BlE-05 EU155 4.82E-07 3.47E-08 2.72E-08 0. 1.30E~07 0. 8.69E-05 EU156 5.62E~08 3.0lE-08 6.23E-09 0. 1.94~-08 0. 6.83E-05 TB160 1.66E-07 D. 2.06E-08 0. 4.94E-08 0. 3.68E-05 H0166M 1.08E-06 2.26E-07 1.91E-07 0. 3.22E-07 0. 0. .
Wl81 4.23E-06 l.04E-08 l.43E-09 0. 0. 0.
3.79E-07
Wl85 1.73E-06 4.32E-07 6.05E-08 0. 0. 0. 1.61E-05 Wl87 4.29E-07 2.54E-07 l.14E-07 0. 0. 0. 3.57E~05 76
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
CHILD INGESTION DOSE COMMITMENT Revision 8 TABLE 2.1 FACTORS CMREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI -LU PB210+0 4.75E-02 l.22E-02 2.09E-03 0. 3.67E-02 0. 5.57E-05 BI210+0 l.97E-06 1.02E-05 l.69E-07 0. l.15E-04 0. 5.l?E-05 P0210 l.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 2.12E-02 2.45E-05 4.24E-03 0. 6.50E-04 0. 3.38E-04 RA224+0 6.89E-03 l.25E-05 l.38E-03 0. 3.31E-04 0. 3.78E-04 RA225+0 2.SOE-02 2.50E-05 5.59E-03 0. 6.62E-04 0. 3.21E-04 RA226+0 5.75E-01 1. 84E-05 4.72E-01 0. 4.88E-04 o-. 3.41E-04 RA228+0 3.85E-01 9.99E-06 4.32E-01 0. 2.65E-04 0. 5.SlE-05 AC225 1.SBE-05 1.94E-05 1.26E-06 0. 2.0?E-06 0. 4.31E-04 AC227+0 4.12E-03 6.63E-04 2.55E-04 0. 1. 46E-04 0. 8.43E-05 TH227+0 5.85E-05 7.96E-07 1.69E-06 0. 4.22E-06 0. 5.63E-04 TH228+0 2.07E-03 2.65E-05 7.00E-05 0. 1. 38E-04 0. 5.79E-04 TH229 1.38E-02 1. SlE-04 6.80E-04 0. 8.84E-04 0. 5.27E-04 TH230 3.55E-03 l.78E-04 9.91E-05 0. 8.67E-04 0. 6.19E-05 TH232+0 3.96E-03 1.52E-04 3.0lE-04 0. 7.41E-04 0. 5. 27E~*Q5 TH234 3.42E-07 1. 51E-08 9.88E-09 0. 8.0lE-08 0. l.18E-04 PA231+0 7.07E-03 2.34E-04 2.81E-04 0. 1.28E-03 0. 7.37E-05 PA233 1. 81E-08 2.82E-09 3.16E-09 0. 1. 04E-08 0. 1.44E-05
U232+0 U233+0 U234 U235+0 U236 U237
1. 76E-02 3.72E-03 3.57E-03 3.42E-03 3.42E-03 2.36E-07 0.
0.
0.
0.
0.
0.
1.26E-03 0.
2.25E-04 0.
2.21E-04 0.
2.07E-04 0.
2.12E-04 0.
6.27E-08 0.
1.34E-03 0.
6. lOE-04 0.
5.98E-04 0.
5.61E-04 0.
5.73E-04 0.
6.BlE-07 0.
6.98E-05 6.45E-05 6.32E-05 8.03E-05 5.92E-05 2.0BE-05 U238+D 3.27E-03 0. 1. 94E-04 0. 5.24E-04 0. 5.66E-05 NP237+0 2.36E-03 1. 81E-04 9.79E-05 0. 6.05E-04 0. 8.16E-05 NP238 5.83E-08 1. lBE-09 9.08E-10 0. 3.76E-09 0. 4.04E-05 NP239 5.25E-09 3.77E-10 2.65E-10 0. 1. 09E-09 0. 2.79E-05 PU238 1.25E-03 1.56E-04 3.16E-05 0. 1.15E-04 0. 7.50E-05 PU239 1.36E-03 1. 65E-04 3.31E-05 0. 1.22E-04 0. 6.85E-05 PU240 1.36E-03 1. 65E-04 3.31E-05 0. 1. 22E-04 0. 6.98E-05 PU241+D 4.00E-05 1.72E-06 8.04E-07 0. 2.96E-06 0. 1.44E-06 PU242 1. 26E-03 1. 59E-04 3.19E-05 0. 1.17E-04 0. 6.71E-05 PU244 1.47E-03 1. 82E-04 3.65E-05 0. 1. 35E-04 0. l.OOE-04 AM241 1. 43E-03 6.40E-04 1.02E-04 0. 6.23E-04 0. 7.64E-05 AM242M 1.47E-03 6.25E-04 1. 04E-04 0. 6.30E-04 0. 9.61E-05 AM243 1.41E-03 6.14E-04 9.83E-05 0. 6.06E-04 0. 8.95E-05 CM242 8.80E-05 6.73E-05 5.84E-06 0. 1.87E-05 0. 8.16E-05 CM243 l.33E-03 6.03E-04 8.24E-05 0. 3.08E-04 0. 8.03E-05 CM244 1.llE-03 5.36E-04 6.93E-05 0. 2.54E-04 0. 7.77E-05 CM245 1. 76E-03 6.64E-04 1.05E-04 0. 4. llE-04 0. 7.24E-05 CM246 1.74E-03 6.64E-04 l.OSE-04 0. 4.lOE-04 0. 7.llE-05 CM247+0 1.?0E-03 6.53E-04 1. 03E-04 0. 4.04E-04 0. 9.35E-05 CM248 1.41E-02 5.38E-03 8.52E-04 0. 3.33E-03 0. 1.51E-03
CF252 l.O?E-03 0. 2.54E-05 0.
77
0. 0. 2.96E-04
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8

* TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS CMREM/50Y PER PC! INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LL!
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. 5.30E-07 0. 2.84E-05 Cl4 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Nl3 l.15E-08 l.15E-08 l.15E-08 l.15E-08 l.15E-08 1.15E-08 l.15E-08 FlB 8.64E-07 0. 9.47E-08 0. 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 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P32 2.76E-04 l.71E-05 l.07E-05 0. 0. 0. 2-.32E-05 AR39 0. 0. 0. 0. 0. 0. 0.
AR41 0. 0. 0. 0. 0. 0. 0.
CA41 1.97E-04 0. 2.13E-05 0. 0. 0. 1.95E-07 SC46 7.24E-09 1.41E-08 4.lBE-09 0. 1.35E-08 0. 4.BOE-05 CR51 0. 0. 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.0SE-07 MN54 MN56 o:
0.
5.90E-06 1.17E-06 0.
1.58E-07 2.BlE-08 0.
1.76E-06 0.
2.00E-07 0.
1.21E-05 1.04E-05 FE55 3.78E-06 2.6SE-06 6.25E-07 0. 0. l.?OE-06 l.16E.,.-06 FE59 5.S?E-06 1.37E-05 5.29E-06 0. 0. 4.32E-06 3.24E~S5 COS? 0. 2.3SE-07 3.99E-07 0. 0. 0. 4.44E-06 COSS 0. 9.72E-07 2.24E-06 0. 0. 0. 1.34E-05 C060 0 2.SlE-06 6.33E-06 0. 0. 0. 3.66E-05 NI59 1.32E-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-OS 4.36E-OS 0. 0. 0. 5.193-06 CU64 0. 1.15E-07 5.41E-OS 0. 2.91E-07 0. 8.92E-06 ZN65 5.76E-06 2.00E-05 9.33E-06 0. 1.2SE-05 0. S.47E-06 ZN69M+D 2.40E-07 5.66E-07 5.19E-OS 0. 3.44E-07 0. 3.llE-05 ZN69 1.47E-OS 2.SOE-OS 1.96E-09 0. 1.S3E-OS 0. 5. 16E-OS SE79 0. 3.73E-06 6.27E-07 0. 6.50E-06 0. 5.70E-07 BRS2 0. 0. 3.04E-06 0. 0. 0. 0.
BRS3+D 0. 0. 5 . 74E -OS 0. 0. 0. 0.
BRS4 0. 0. 7.22E-OS 0. 0. 0. 0.
BRS5 0. 0. 3.05E-09 0. 0. 0. 0.
KRS3M 0. 0. 0. 0. 0. 0. 0.
KRS5M 0. 0. 0. 0. 0. 0. 0.
KRS5 0. 0. 0. 0. 0. 0. 0.
KRS7 0. 0. 0. 0. 0. 0. 0.
KRSS+D 0. 0. 0. 0. 0. 0. 0.
KRS9 0. 0. 0. 0. 0. 0. 0.
RBS6 0. 2.9SE-05 1.40E-05 0. 0. 0. 4.41E-06 RBS? 0. 1.75E-05 6.llE-06 0. 0. 0. 6.llE-07 RBSS 0. 8.52E-08 4.54E-OS 0. 0. 0. 7.30E-15 RBS9+D 0. 5.SOE-OS 3.S9E-08 0. 0. 0. 8.43E-17 SR89+D 4.40E-04 0. 1.26E-05 0. 0. 0. 5.24E-05 SR90+D S.30E-03 0. 2.0SE-03 0. 0. 0. 2.33E-04 SR91+0 S.O?E-06 0. 3.21E-07 0. 0. 0. 3.66E-05 SR92+D 3.0SE-06 0. 1.30E-07 0. 0. 0. 7.77E-05
7S
PALISADES NUCLEAR PLANT -
OFFSITE DOSE CALCULATION MANUAL Revision 8
---------------------- TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PC! INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 l.37E-08 0. 3.69E-10 0. 0. 0. l.13E-04 Y91M+D l.29E-10 0. 4.93E-12 0. 0. 0. 6.09E-09 Y91 2.0lE-07 0. 5.39E-09 0. 0. 0. 8.24E-05 Y92 l.21E-09 0. 3.SOE-11 0. 0. 0. 3.32E-05 Y93 3.83E-09 0. l.OSE-10 0. 0. 0. l.17E-04 ZR93+0 5.53E-08 2.73E-08 l.49E-08
0. 9.65E-08 0. 2.58E-05 ZR95+0 4.12E-08 l.30E-08 8.94E-09 0. l.91E-08 0. 3.00E-05 ZR97+0 2.37E-09 4.69E-10 2.16E-10 0. 7.llE-10 0. l.27E-04 NB93M 3.44E-08 l.13E-08 2.83E-09 0. l.32E-08 0. 4.07E-06 NB95 8.22E-09 4.56E-09 2.SlE-09 0. 4.42E-09 0. l.95E-05 NB97 7.37E-ll l.83E-ll 6.68E-12 0. 2.14E-11 0. 4.37E-07 M093 0. 1.06E-05 2.90E-07 0. 3.04E-06 0. 1.29E-06 M099+0 O~ 6.03E-06 l.lSE-06 0. 1.38E-05 0. 1.0BE-05 TC99M 3.32E-10 9.26E-10 l.20E-08 0. l.38E-08 5.14E-10 6.0BE-07 TC99 1.79E-07 2.63E-07 7.17E-08 0. 3.34E-06 2.72E-08 6.44E-06 TC101 3.60E-10 5.12E-10 5.03E-09 0. 9.26E-09 3.12E-10 8.75E-17 RU103+0 2.SSE-07 0. 1.09E-07 0. 8.99E-07 0. 2.13E-B5 RU105+0 2.lBE-08 .O. 8.46E-09 0. 2.75E-07 0. l.76E-05 RU106+D 3.92E-06 0. 4.94E-07 0. 7.56E-06 0. l.BBE-04 RH105 1.73E-07 1.25E-07 8.20E-08 0. 5.31E-07 0. 1.59E-05 PD107 0. 2.0BE-07 1.34E-08 0. 1.88E-06 0. 9.66E-07
PD109 0. 2.51E-07 . 5.70E-08 0. 1.45E-06 0. 2.53E-05 AGllOM+D 2.05E-07 1.94E-07 1.lBE-07 0. 3.70E-07 0. 5.45E-05 AGlll 8.29E-08 3.44E-08 1.73E-08 0. 1.12E-07 0. 4.BOE-05 CD113M 0. 4.51E-06 1.45E-07 0. 4.99E-06 0. 2.71E-05 CD115M 0. 2.60E-06 8.39E-08 0. 2.0BE-06 0. 8.23E-05 SN123 4.44E-05 7.29E-07 1.0BE-06 5.84E-07 0. 0. 6.71E-05 SN125+0 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0. 0. l.12E-04 SN126+0 1.16E-04 2.16E-06 3.30E-06 5.69E-07 0. 0. 2.58E-05 SB124 3.87E-06 7.13E-08 1.51E-06 8.78E-09 0. 3.38E-06 7.BOE-05 SB125+0 2.48E-06 2.71E-08 5.BOE-07 2.37E-09 0. 2.lBE-06 1.93E-05 SB126 1.59E-06 3.25E-08 5.71E-07 8.99E-09 0. 1.14E-06 9.41E-05 SB127 3.63E-07 7.76E-09 1.37E-07 4.0BE-09 0. 2.47E-07 6.16E-05 TE125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0. 0. l.13E-05 TE127M+D 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0. 2.41E-05 TE127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0. 1.22E-05 TE129M+D 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0. 6.12E-05 TE129 . 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.BBE-07 0. 2.45E-07 TE131M+D 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0. 9.39E-05 TE131+0 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0. 2.29E-09 TE132+0 3.49E-06 2.21E-06 2.0BE-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 3.62E-07 0. 1.48E-07 TE134+0 4.47E-08 2.87E-08 3.00E-08 3.67E-08 2.74E-07 0. 1.66E-09 I129 4.66E-06 3.92E-06 6.54E-06 4.77E-03 7.0lE-06 0. 4.57E-07 I130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0. 2.29E-06 Il31+D 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0. l.62E-06 79
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Il32 2.79E-07 7.30E-07 2.62E-07 2.46E-05 l.15E-06 0. 3.18E-07 Il33+0 2.0lE-06 3.41E-06 l.04E-06 4.76E-04 5.98E-06 0. 2.58E-06 Il34 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 0. 0. 0. 0. 0. 0: 0.
XE133M 0. 0. 0. . 0. 0. 0. 0.
XE133 0. 0. 0. 0. 0. 0. . 0.
XE135M 0. 0. 0. 0. 0. 0. 0.
XE135 0. 0. 0. 0. 0. 0. 0.
XE137 0. 0. 0.
0. 0. 0. 0.
XE138+0 0. 0. 0. . 0. 0. 0. 0.
CS134M+O 2.94E-08 6.09E-08 3.13E-08 0. 3.39E-08 5.. 95E-09 4.05E-08 CS134 8.~7E-05 l.97E-04 9.14E-05 0. 6.26E-05 2.39E-05 2.45E-06 CS135 2.78E-05 2.55E-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 1.12E-04 1.49E-04 5.19E-05
0. 5.07E-05 1.97E-05 2.12E~Q6 CS138 7.76E-08 l.49E-07 7.45E-08 0. 1.lOE-07 1.28E-08 6.76E-11 CS139+0 4.87E-08 7.l?E-08 2.63E-08 0. 5.79E-08 6.34E-09 3.33E-23 BA139 1.39E-07 9.78E-11 4.0SE-09 0. 9.22E-11 6.74E-11 l.24E-06 BA140+0 2.84E-05 3.48E-08 1.83E-06 0. 1.18E-08 2.34E-08 4.38E-05. *
BA141+0 - 6,71E-08 5.0lE-11 2.24E-09 0. *4.65E-11 3.43E-11 l.43E-13 BA142+0 2.99E-08 2.99E-11 1.84E-09 0. 2.53E-11 1.99E-11 9.18E-20 LA140 3.48E-09 1.71E-09 4.55E-10 0. 0. 0. 9.82E-05 LA141 4.55E-10 1.40E-10 2.31E-11 0. 0. 0. 2.48E-05 LA142 1.79E-10 7.95E-11 1.98E-11 0. 0. 0. 2.42E-06 CE141 1.33E-08 8.88E-09 1.02E-09 0. . 4.18E-09 Q. 2.54E-05 CE143+0 2.35E-09 1.71E-06 1.91E-10 0. 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 1.31E~08 5.23E-09 6.52E-10 0. 3.04E-09 0. 4.JlE-05 PR144 4.30E-11 1.76E-11 2.lBE-12 0. 1.0lE-11 0. 4.74E-14 ND147+0 9.38E-09 1.02E-08 6.llE-10 0. 5.99E-09 0. 3.68E-05 PM147 1.0SE-07 9.96E-09 4.06E-O~ 0. 1.90E-08 . 0. 9.47E-06 PM148M+D 4.14E-08 1.0SE-08 8.21E~09 0. 1.59E-08 *o. 6.61E-05 PM148 1.02E-08 1.66E-09 8.36E-10 0. 3.00E-09 0. 9.90E-05 PM149 2.17E-09 3.0SE-10 1.25E~10 0. 5.81E-10 0. 4.49E-05 PM151 9.87E-10 1.63E~10 8.25E-11 0. 2~93E-10 0. 3.66E-05 SM151 8.73E-08 1.68E-08 3.94E-09 0. 1.84E-08 0. 5.?0E-06
SM153 1.22E-09 1.0lE-09 7.43E-11 0. 3.30E-10 0. 2.85E-05.
EU152 2.45E-07 5.90E-08 5.20E-08 0. 2.74E-07 0. 2.l?E-05 EU154 7.91E-07 1.02E-07 7.19E-08 0. 4.56E-07 0. 5.39E~05 EU155 l.74E-07 l.68E-08 1.04E-08
0. 6.57E-08 0. 9.63E-05 EU156 1.92E-08 1.44E-08 2.35E-09 0. 9.69E-09 0. 7.36E-05 TB160 6.47E-08 0. 8.0?E-09 0. 2.56E-08 0. 4.19E-05 H0166M 3.57E-07 l.lOE-07 7.96E-08 0. l.61E-07 0. 0.
Wl81 l.42E-08 4.58E-09 4.79E-10 0. 0. 0. 3.90E-07
Wl85 5.79E-07 l.91E-07 2.02E-08 0. 0. 0. l.65E-05 Wl87 l.46E-07 1.19E-07 4.l?E-08 0. 0. 0. 3.22E-05 80
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
---------------------- TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI -LLI PB210+D 1.81E-02 5.44E-03 7.0lE-04 0. l.72E-02 0. 5.74E-05 BI210+D 6.59E-07 4.51E-06 5.66E-08 0. 5.48E-05 0. 5.15E-05 P0210 6.09E-04 l.07E-03 l.23E-04 0. 3.60E-03 0. 6.75E-05 RN222+D 0. 0. 0. 0. 0. 0. 0.
RA223+D 7.llE-03 l.08E-05 l.42E-03 0. 3.lOE-04 0. 3.43E-04 RA224+D 2.31E-03 5.52E-06 4.61E-04 0. l.58E-04 0. 3.71E-04 RA225+D 9.37E-03 l.lOE-05 l.87E-03 0. 3.15E-04 0. 3.27E-04 RA226+D 3.22E-Ol 8.13E-06 2.39E-Ol 0. 2.32E-04 0. 3.51E-04 RA228+D l.37E-Ol 4.41E-06 l.51E-Ol 0. l.26E-04 0. 5.98E-05 AC225 6.29E-06 8.59E-06 4.22E-07 0. 9.85E-07 0. 4.36E-04 AC227+D 2.05E-03 3.03E-04 l.22E-04 0. 8.81E-05 0. 8.68E-05 TH227+D l.96E-05 3.52E-07 5.65E-07 0. 2.0lE-06 0. 5.75E-04 TH228+D 6.BOE-04 l.14E-05 2.30E-05 0. 6.41E-05 0. 5.97E-04 TH229 8.~9E~03 l.26E-04 4.llE-04 0. 6.lOE-04 0. 5.43E-04.
TH230 2.16E-03 l.23E-04 6.00E-05 0. . 5.99E-04 0. 6.38E-05 TH232+D 2.42E-03 l.05E-04 l.63E-04* 0. 5.llE-04 0. 5. 43L-.05 TH234 l.14E-07 6.68E-09 3.31E-09 0. 3.81E-08 0. 1. 21E-04 PA231+0 4.31E-03 l.62E-04 l.68E-04 0. 9.lOE-04 0. 7.60E-05 PA233 7.33E-09 l.41E-09 l.26E-09 0. 5.32E-09 0. 1. 61E-05 U232+0 5.89E-03 0. 4.21E-04 0. 6.38E-04 0. 7.19E-05 U233+0 l.24E-03 0. 7.543-05 0. 2.90E-04 0. 6.65E-05 U234 l.19E-03 0. 7.39E-05 0. 2.85E-04 0. 6.51E-05 U235+D l.14E-03 0. 6.94E-05 0. 2.67E-04 0. 8.28E-05 U236 l.14E-03 0. 7.09E-05 0. 2.73E-04 0. 6.llE-05 U237 7.89E-08 0. 2.lOE-08 0. 3.24E-07 0. 2.09E-05 U238+0 l.09E-03 0. 6.49E-05 0. 2.50E-04 0. 5.83E-05 NP237+0 l.44E-03 l.25E-04 5.85E-05 0. 4.33E-04 0. 8.41E-05 NP238 l.95E-08 5.22E-10 3.04E-10 0. l.79E-09 0. 3.83E-05 NP239 1.76E-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. 7.80E-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 2.0lE-05 0. 8.56E-05 0. 7.19E-05 PU241+0 1.84E-05 9.42E-07 3.69E-07 0. l.71E-06 0. 1. 48E-06 PU242 7.66E-04 l.08E-04 l.94E-05 0. 8.25E-05 0. 6.92E-05 PLJ244 8.95E-04 1.23E-04 2.22E-05 0. 9.45E-05 0. 1. 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 5.80E-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. 1.91E-04 0. 8.28E-05 CM244 5.32E-04 2.49E-04 3.19E-05 0. 1.49E-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+0 l.03E-03 3.27E-04 6.00E~05 0. 2.80E-04 0. 9.63E-05 CM248 8.60E-03 2.69E-03 4.95E-04 0. 2.31E-03 0. l.55E-03 CR252 3.51E-04 0. 8.37E-06 0. 0. 0. 3.05E-04 81
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL ADULT INGESTION DOSE COMMITMENT Revision 8 TABLE 2.1 FACTORS CMREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI -LU H3 0. l.05E-07 1. 05E-07 l.05E-07 l.05E-07 l.05E-07 l.05E-07 BElO 3.lBE-06 4.91E-07 7.94E-08 0. 3.71E-07 0. 2.68E-05 C14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 N13 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 FlB 6.24E-07 0. 6.92E-08 0. 0. 0. 1.85E-08 NA22 1. 74E-05 l.74E-05 1.74E-05 1.74E-05 1.74E-OS 1. 74E-OS 1. 74E-OS NA24 1.70E-06 1. 70E-06 1.?0E-06 1. 70E-06 1.70E-06 1. 70E-06 1.70E-06 P32 1. 93E-04 l.20E-OS 7.46E-06 0. 0. 0. 2.17E-OS AR39 0. 0. 0. 0. 0. 0. 0.
AR41 0. 0. 0. 0. 0. 0. 0.
CA41 1.83E-OS 0. 2.00E-OS 0. 0. 0. 1.84E-07 SC46 S.SlE-09 l.07E-08 3. llE-09 0. 9.99E-09 0. S.21E-OS CRSl 0 .- 0. 2.66E-09 1.S9E-09 S. 86E-10 3.S3E-09 6.69E-07 MNS4 0. 4.S7E-06 8.72E-07 0. 1. 36E-06 0. l.40E-OS MNS6 0. l.lSE-07 2.04E-08 0. l.46E-07 0. 3.67E-06 FESS 2.7SE-06 l.90E-06 4.43E-07 0. 0. 1. 06E-06 1. 09[~06 FES9 4.34E-06 1. 02E-05 3.91E-06 0. 0. 2.BSE-06 3.40E-OS C057 0. l.75E-07 2.91E-07 0. 0. 0. 4.44E-06 COSS 0. 7.45E-07 1.67E-06 0. 0. 0. 1. SlE-05 C060 0. 2.14E-06 4.72E-06 0. 0. 0. 4.02E-OS -
NI59 9.76E-06 3.35E-06 1. 63E-06 0. 0. 0. 6.90E-07 NI63 1.30E-04 9.0lE-06 4.36E-06 0. 0. 0. 1.88E-06 NI65 S.28E-07 6.86E-08 3.13E-08 0. 0. 0. 1. 74E-06 CU64 0. 8.33E-08. 3.91E-08 0. 2.lOE-07 0. 7.lOE-06 ZN65 4.84E-06 1. 54E-05 6.96E-06 0. 1. 03E-05 0. 9.70E-06 ZN69M+D 1.?0E-07 4.0BE-07 3.73E-08 0. 2.47E-07 0. 2.49E-05 ZN69 1.03E-08 1.97E-08 1.37E-09 0. 1.28E-08 0. 2.96E-09 SE79 0. 2.63E-06 4.39E-07 0. 4.55E-06 0. S.38E-07 BR82 0. 0. 2.26E-06 0. 0. 0. 2.59E-06 BR83+0 0. 0. 4.02E-08 0. 0. 0. S.79E-08 BR84 0. 0. 5.21E-08 0. 0. 0. 4.09E-13 BR85 0. 0. 2.14E-09 0. 0. 0. 0.
KR83M 0. 0. 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+0 0. 0. 0. 0. 0. 0. 0.
KR89 0. 0. 0. 0. 0. 0. 0.
RB86 0. 2.llE-05 9.83E-06 0. 0. 0. 4.16E-06 RB87 0. 1. 23E-05 4.28E-06 0. 0. 0. S.76E-07 RB88 0. 6.05E-08 *3.21E-08 0. 0. 0. 8.36E-19 RB89+0 0. 4.0lE-08 2.82E-08 0. 0. 0. 2.33E-21 SR89+0 3.0BE-04 0. 8.84E-06 0. 0. 0. 4.94E-OS SR90+0 7.SSE-03 0. 1.86E-03 0. 0. 0. 2.19E-04 SR91+0 5. "67E-06 0. 2.29E-07 0. 0. 0. 2.70E-05 SR92+0 2.lSE-06 0. 9.30E-08 0. 0. 0. 4.26E-05 82
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS CMREM/50Y PER PC! INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID . KIDNEY LUNG GI-LL!
Y90 9.62E-09 0. 2. 58E-10 0. 0. 0. 1. 02E-04 Y91M+D 9.09E-ll 0. 3.52E-12 0. 0. 0. 2.67E-10 Y91 1. 41E-07 0. 3.77E-09 0. 0. 0. 7.76E-05 Y92 8. 45E-10 0. 2.47E-ll 0. 0. 0. l.48E-05 Y93 2.68E-09 0. 7.40E-11 0. 0. 0. 8.50E-05 ZR93+D 4.lBE-08 2.34E-09 l.09E-09 0. 8.87E-09 0. 2.43E-06 ZR95+D 3.04E-08 9.75E-09 6.60E-09 0. 1. 53E-08 0. 3.09E-05 ZR97+0 l.68E-09 3.39E-10 l.55E-10 0. 5.12E-10 0. l.05E-04 NB93M 2.55E-08 8.32E-09 2.05E-09 0. 9.57E-09 0. 3.84E-06 NB95 6.22E-09 3.46E-09 1. 86E-09 0. 3.42E-09 0. 2.lOE-05 NB97 5.22E-ll 1. 32E-ll 4.82E-12 0. 1. 54E-ll 0. 4.87E-08 M093 0. 7.51E-06 2.03E-07 0. 2.13E-06 0. l.22E-06 M099+D 0. 4.31E-06 8.20E-07 0. 9.76E-06 0. 9.99E-06 TC99M 2~47E-10 6. 98E-10 8.89E-09 0. 1. 06E-08 3. 42E-10 4.13E-07 TC99 1.25E-07 1. 86E-07 5.02E-08 0. 2.34E-06 1.58E-08 6.0BE-06 TClOl 2. 54E-10 3.66E-10 3.59E-09 0. 6.59E-09 1.87E-10 l. lOE,:21 RU103+0 1. 85E-07 0. 7.97E-08 0. 7.06E-07 0. 2.16E:OG5 RU105+0 l.54E-08 0. 6.08E-09 0. l.99E-07 0. 9.42E-06 RU106+0 2.75E-06 0. 3.48E-07 0. 5.31E-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. 1.47E-07 9.40E-09 0. 1. 32E-06 0. 9. llE-07
PD109 0. 1. 77E-07 3.99E-08 0. 1. OlE-06 0. 1. 96E-05 AGllOM+D l.60E-07 1. 48E-07 8.79E-08 0. 2.91E-07 0. 6.04E-05 AGlll 5.81E-08 2.43E-08 1.21E-08 0. 7.84E-08 0. 4.46E-05 CD113M 0. 3.18E-06 1. 02E-0.7 0. 3.50E-06 0. 2.56E-05 CD115M 0. 1. 84E-06 5.87E-08 0. 1.46E-06 0.. 7.74E-05 SN123 3. llE-05 5.15E-07
7.59E-07 4.38E-07 0. 0. 6.33E-05 SN125+0 8.33E-06 1.68E-07 3.78E-07 1. 39E-07 0. 0. 1. 04E-04 SN126+D 8.45E-05 1.67E-06 2.40E-06 4.92E-07 0. 0. 2.43E-05 SB124 2.80E-06 5.29E-08 1.llE-06 6.79E-09 0. 2.lBE-06 7.95E-05 SB125+0 1.79E-06 2.00E-08 4.26E-07 1. 82E-09 0: 1.38E-06 l.97E-05 SB126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 0. 7.05E-07 9.40E-05 SB127 2.58E-07 5.65E-09 9.90E-08 3.lOE-09 0. 1. 53E-07 5.90E-05 TE125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0. l.07E-05 TE125M+D 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.7.SE-05 0. 2.27E-05 TE127 1. lOE-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0. 8.68E-06 TE129M+D l.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0. 5.79E-05 TE129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0. 2.37E-08 TE131M+D 1. 73E-06 8.46E-07 7.05E-07 1. 34E-06 8.57E-06 0. 8.40E-05 TE131+0 1.97E-08 8.23E-09 6.22E-09 l.62E-08 8.63E-08 0. 2.79E-09 TE132+0 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0. 7.71E-05 TE133M+D 4.62E-08 2.70E-08 2.60E-08 3.91E-08 2.67E-07 0. 6.64E-08 TE134+0 3.24E-08 2.12E-08 1.30E-08 2.83E-08 2.0SE-07 0. 3. 59E-ll 1129 3.27E-06 2.BlE-06 9.21E-06 7.23E-03 6.04E-06 0. 4.44E-07 1130 7.56E-07 2.23E-06 8.BOE-07 1. 89E-04 3.48E-06 0. l.92E-06
!131 +D 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0. l.57E-06 83
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI -LLI 1132 2.03E-07 5.43E-07 l.90E-07 .1.90E-05 8.65E-07 0. - 1.02E-07 I133+0 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0. 2.22E-06 1134 1. 06E-07 2.BBE-07 1.03E-07 4.99E-06 4.58E-07 0. 2.SlE-10 1135+0 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0. 1. 31E-06 XE131M 0. 0. 0. 0. 0.. 0. 0.
XE133M 0. 0. 0. 0. 0. 0. 0.
XE133 0. 0. 0. 0. 0. 0. 0.
XE135M 0. 0. 0. 0. 0. 0. 0.
XE135 0. 0. 0. 0. 0. 0. 0.
XE137 0. 0. 0. 0. 0. 0. 0.
XE138+0 0. 0. 0. 0. 0. 0. 0.
CS134M+D 2.13E-08 4.48E-08 2.29E-08 0. 2.43E-08 3.83E-09 1.58E-08 CS134 6.22E-05 1. 48E-04 1.21E-04 0. 4.79E-05 l.59E-05 2.59E-06 CS135 1. 95E-05 1.80E-05 7.99E-06 0. 6.81E-06 2.04E-06 4.21E-07 CS136 6.51E-06 2.57E-05 l.85E-05 0. 1.43E-05 1. 96E-06 2.92E-06 CS137+0 7.97E-05 1.09E-04 7.14E-05 0. 3.70E-05 1.23E-05 2. llE-06 CS138 6.52E-08 1.09E-07 5.40E-08 0. 8.0lE-08 7.91E-09 4.65E-J:3 CS139+D 3.41E-08 5.08E-08 l.85E-08 0. 4.07E-08 3.70E-09 1.lOE-30 BA139 9.70E-08 6.91E-11 2.84E-09 0. 6.46E-11 3.92E-11 i.72E-07 BA140+0 2.03E-05 2.55E-08 1.33E-06 0. 8.67E-09 1.46E-08 4. lBE-05
BA14l+D 4.71E-08 3. 56E-11 l.59E-09 0. 3.31E-11 2. 02E-11 2.22E-17
BA142+0 2.13E-08 2.19E-11 1. 34E-09 0. 1.85E-ll 1.24E-ll 3.00E-26 LA140 2.50E-09 l.26E-09 3. 33E-10 0. 0. 0. 9.25E-05 LA141 3.19E-10 9.90E-11 1. 62E-ll 0. 0. 0. 1.18E-05 LA142 1. 28E-10 5.82E-11 1. 45E-ll 0. 0. 0. 4.25E-07 CE141 9.36E-09 6.33E-09 7.18E-10 0. 2.94E-09 0. 2.42E-05 CE143+D 1.65E-09 1.22E-06 1.35E-10 0. 5.37E-10 0. 4.56E-05 CE144+0 4.88E-07 2.04E-07 2.62E-08 0. 1.21E-07 0. 1. 65E-04 PR143 9.20E-09 3.69E-09 4.56E-10 0. 2.13E-09 0. 4.03E-05 PR144 3.0lE-11 l.25E-11 1.53E-12 0. 7.05E-12 0. 4.33E-18 ND147+0 6.29E-09 7.27E-09 4. 35E-10 0. 4.25E-09 0. 3.49E-05 PM147 7.54E-08 7.09E-09 2.87E-09 0. 1. 34E-08 0. 8.93E-06 PM148M+D 3.0?E-08 7.95E-09 6.08E-09 0. 1.20E-08 0. 6.74E-05 PM148 7.l?E-09 1.19E-09 5.99E-10 0. . 2.25E-09 0. 9.35E-05 PM149 l.52E-09 2.15E-10 8. 78E-ll 0. 4.06E-10 0. 4.03E-05 PM151 6.97E-10 1.l?E-10 5.91E-ll 0. 2.09E-10 0. 3.22E-05 SM151 6.90E-08 l.19E-08 2.85E-09 0. 1.33E-08 0. 5.25E-06 SM153 8.57E-10 7 .15E-10 5. 22E-ll 0. 2.31E-10 0. 2.55E-05 EU152 l.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 1.22E-08 7.87E-09 0. 5.63E-08 0. 9.60E-06 EU156 1.37E-08 l.06E-08 1. 71E-09 0. 7.08E-09 0. 7.26E-05 TB160 4.?0E-08 0. 5.86E-09 0. l.94E-08 0. 4.33E-05 H0166M 2.?0E-07 8.43E-08 6.40E-08 0. 1.26E-07 0. 0.
W181 9.91E-09 3.23E-09 3.46E-10 0. 0. 0. 3.68E-07 Wl85 Wl87 4.05E-07 l.03E-07 1.35E-07 8.61E-08
1. 42E-08 3.0lE-08 0.
84
0. 0.
0.
0.
0.
l.56E-05 2.82E-05
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
Revision 8 TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS CMREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI -LU PB210+D 1.53E-02 4.37E-03 5.44E-04 0. l.23E-02 0. 5.42E-05 BI210+D 4.61E-07 3.18E-06 3.96E-08 0. 3.83E-05 0. 4.75E-05 P0210 3.56E-04 7.56E-04 8.59E-05 0. 2.52E-03 0. 6.36E-05 RN222+D 0. 0. 0. 0. 0. 0. 0.
RA223+D 4.97E-03 7.65E-06 9.94E-04 0. 2.17E-04 0. 3.21E-04 RA224+D l.61E-03 3.90E-06 3.23E-04 0. l. lOE-04 0. 3.40E-04 RA225+D 6.56E-03 7.78E-06 1. 31E-03 0. 2.21E-04 0. 3.06E-04 RA226+0 3.02E-Ol 5.74E-06 2.20E-Ol 0. 1. 63E-04 0. 3.32E-04 RA228+0 l.12E-Ol 3.12E-06 l.21E-Ol 0. 8.83E-05 0. 5.64E-05 AC225 4.40E-06 6.06E-06 2.96E-07 0. 6.90E-07 0. 4.07E-04 AC227+0 l.87E-03 2.48E-04 l. llE-04 0. 8.00E-05 0. 8.19E-05 TH227+0 1.37E-05 2.48E-07 3.95E-07 0. l.41E-06 0. 5.40E-04 TH228+D 4 .-96E-04 8.40E-06 1. 68E-05 0. 4.67E-05 0. 5.63E-04 TH229 7.98E-03 l.19E-04 3.91E-04 0. 5.75E-04 0. 5.12E-04 TH230 2.06E-03 l.17E-04 5.70E-05 0. 5.65E-04 0. 6.02E-05 TH232+0 2.30E-03 l.OOE-04 l.50E-04 0. 4.82E-04 0. 5 .12[~05 TH234 8.0lE-08 4. 71E-09 2.31E-09 0. 2.67E-08 0. l.13E-04 PA231+0 4. lOE-03 1. 54E-04 1. 59E-04 0. 8.64E-04 0. 7.17E-05 PA233 5.26E-09 l.06E-09 9.12E-10 0. 3.99E-09 o: 1.64E-05
U232+0 U233+0 U234 U235+0 U236 U237 4.13E-03
8. 71E-04 8.36E-04 8.0lE-04 8.0lE-04 5.52E-8 0.
0.
0.
0.
0.
0.
2.95E-04 0.
5.28E-05 0.
5.17E-05 0.
4.86E-05 0.
4.96E-05 0.
l.47E-08 0.
4.47E-04 0.
2.03E-04 0.
1. 99E-04 0.
l.87E-04 0.
1. 91E-04 0.
2.27E-07 0.
6.78E-05 .
6.27E-05 6.14E-05 7.81E-05 5.76E-05
1. 94E-05 U238+0 7.67E-04 0. 4.54E~05 0. 1. 75E-04 0. 5.50E-05 NP237+0 l.37E-03 l.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 0. 3.43E-05 NP239 l.19E-09 l.17E-10 6. 45E-ll 0. 3. 65E-10 0. 2.40E-05 PU238 6.80E-04 9.58E-05 1. 71E-05 0. 7.32E-05 0. 7.30E-05 PU239 7.87E-04 l.06E-04 1. 91E-05 0. 8. llE-05 0. 6.66E-05 PU240 7.85E-04 1. 06E-04 l.91E-05 0. 8.lOE-05 0. 6.78E-05 PU241+0 1. 65E-05 8.44E-07 3.32E-07 0. l.53E-06 0. l.40E-06 PU242 7.29E-04 l.02E-04 1. 84E-05 0. 7.81E-05 0. 6.53E-05 PU244 8.52E-04 l. l?E-04 2.llE-05 0. 8.95E-05 0. 9.73E-05 AM241 8.19E-04 2.88E-04 5.41E-05 0. 4.0?E-04 0. 7.42E-05 AM242M 8.24E-04 2.78E-04 5.43E-05 0. 4.05E-04 0. 9.34E-05 AM243 8.18E-04 2.78E-04 5.30E-05 0. 3.99E-04 0. 8.70E-05 CM242 2.06E-05 2.lOE-05 l.37E-06 0. 6.22E-06 0. 7.92E-05 CM243 6.39E-04 2.41E-04 3.75E-05 0. l.75E-04 0. 7.81E-05 CM244 4.83E-04 2.0?E-04 2.87E-05 0. l'. 34E-04 0. 7.55E-05 CM245 1. 02E-03 2. 87-E-04 5.76E-05 0. 2.69E-04 0. 7.04E-05 CM246 1. OlE-03 2.87E-04 5.75E-05 0. 2.68E-04 0. 6.91E-05 CM247+0 9.84E-04 2.83E-04 5.67E-05 0. 2.64E-04 0. 9.09E-05 CM248 8.18E-03 2.33E-03 4.67E-04 0. 2.18E-03 0. 1.47E-03
CF252 2.64E-04 0. 6.29E-06 0.
85
0. 0. 2.88E-04
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8 TABLE 2.2 PALISADES Liquid Effluent Design Objective Annual Quantity Design Objective Dose Conversion Annual Quantity Nuclide Half-Life Factors (mrem/Ci) Individual/Organ (Curies)
H-3 12.3 yr 1.75E-06 Adult/TB 1. 71E+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 1. 56E-03 Adult/GI (LU) 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 1. 86E-03 Teen/TB 1. 612. 0 Co-57 270 d 4.39E-03 Teen/TB 683.4 Co-58 71.3 d 1. 03E-02 Teen/TB 291.3 Fe-59 Co-60 Cu-64 Ni-65 Zn-~5 45.6 d
5. 26 yr 12.8 h 2.56 h 245 d 4.0BE-02 4.71E-01 1.32E-03 5.82E-04
1. 83E-Ol Adult/GI (LU)
Teen/TB Teen/GI CLLI)
Teen/TB Teen/TB 245.1 6.37 7.575.0 5.154.0 16.4 Br-84 31. 8 mo 2.02E-03 Teen/TB 1. 485. 2 Rb-86 1. 02 mo 3.06E-01 Child/TB 9.80 Rb-88 17.8 mo 6.92E-04 Teen/TB 4.335.3 Sr-89 52.7 d 1.56E-Ol Child/Bone 64.1 Sr-90 27.7 yr 2.71E-OO Adult/Bone 3.69 Sr-91 9.67 h 1.16E-03 Teen/TB 2.586.0 Sr-92 2. 71 h 1.51E-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 (LU) 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 1.llE-03 Teen/Kidney 9.009.0 Tc-99m 6.05 h 1.42E-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 86
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
TABLE 2.2 (continued)
PALISADES Liquid Effluent Design Objective Annual Quantity Design Objective Dose Conversion Annual Quantity Nuclide Half-Life Factors (mrem/Ci) Individual/Organ (Curies)
Cd-113m 13.6 yr 6.02E-02 Adult/GI (LLI) 166.1 Sb-124 60 d 1.51E-02 Teen/TB . 198. 7 Sb-125 2.T yr 5.llE-02 Teen/TB 58.7 Te-127 9.4 h 7.38E-03 Teen/GI (LLI) . 1. 355. 0 Te-127m 1Q9 d 1.39E-01 Teen/Kidney 71.9 Te-129m 34.1 d 2.66E-01 Adult/GI (LU) 37.6 .,
I-130 12.3 h 1.17E-02 Child/Thyroid 854.7 I-131 8.05 d 3.27E-01 Child/Thyroid 30.6 Te-131m 30 h 2.27E-01 Adult/GI (LU) 44.0 I-132 2.26 h 3.18E-05 Teen/TB 94.339.0
Te-132 I-133 Cs-134 I-134 I-135
77. 7 h 20.3 h 2 yr 52 mo 6.68 h 2.93E-01
3.94E-02 2.86E+OO 2.43E-03 1.64E-03 Adult/GI (LU)
Child/Thyroid Adult/TB Teen/TB
Child/Thyroid 34.1 253.8
1. 04
1. 234. 0 6.097.0 Cs-136 13.7 d 4.13E-01 Adult/TB 7.26 Cs-137 30 yr 1.71E+OO Adult/TB 1. 75 Cs-138 32.2 mo 2.31E-d3 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 1.85E-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-01 Teen/TB 9.25 W-187 23.9 h 1. 98E-01 Adult/GI (LU) 50.5 Np-239 2.346-d 2.26E-03 Adult/GI (LU) 4.424.0
87
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 8
I I I. URANIUM FUEL CYCLE DOSE A. SPECIFICATION In accordance with Appendix A.Section III.I.1. if either liquid or gaseous quarterly releases exceed the quantity which would cause offsite doses more than twice the limit of Appendix A. Sections III.C.1. III.D.1.
or III.H.1. then the cumulative dose contributions from combined release plus direct radiation sources (from the reactor unit and radwaste 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 exposed 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 shore line fishing Cat accessible shoreline adjacent to site security fence) is conservatively 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 quarters 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. Added 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.
040 = DG + DL + (Ry)(T) (2.15) where:
D40 = 40 CFR 190 dose (mrem)
DG = Limiting dose to an individual from gaseous source term Cmrem)
DL = Limiting dose to an individual from liquid source term Cmrem)
Rr Mean dose rate calculated to be applicable to Lake Michigan shoreline adjacent to plant site (mrem/hr)
T = Assumed shoreline fishing time for the quarter in questions (hours).
88
Procedure No ODCM APPENDIX A Revision 2 Issued Date 1/5/94
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERAL LETTER 89-01
<TAC NO 75060)
. '/
Oate
~ 11_;/~3
Technical Reviewer Date User Reviewer Date Rev #
~~ //v/Fy ,
Plant General Manager Date
Table of Contents I. INTRODUCTION 1 II. DEFINITIONS . 1 A. Channel Calibration 1 B. Channel Check . . . 1
c. Channel Functional Test 1 D. Source Check . . . . . 2 E. Offsite Dose Calculation Manual 2 F. Gaseous Radwaste Treatment System 2 G. Members of the Public . 2 H. Process Control Program (PCP) 2 I. Site Boundary . 2 J. Unrestricted Area 2 K. Ventilation Exhaust Treatment System 3, III. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES 3 A. Radioactive Gaseous Effluent Monitoring Instrumentation 3
1. Requirement 3
2. Action 3
3. Surveillance Requirements 4
4. Bases . . . 4 B. Gaseous Effluents Dose Rate 9
1. Requirement 9
2. Action 9
3. Surveillance Requirements 9
4. Bases 9
c. Noble Gases Dose 10
1. Requirement 10
2. Action 10
3. Surveillance Requirements 11
4. Bases . . . . . . . . . . 11
i
D. I-131, I-133, Tritium, and Particulates 11 1.
2.
3.
4.
Requirement Action Surveillance Requirements Bases 11 12 12 12 E. Gaseous Waste Treatment System 16
1. Requirement 16
2. Action 16
3. Surveillance Requirements 16
4. Bases 16 F. Radioactive Ligu:ld Effluent Monitoring Instrumentation 17
1. Requirement 17
2. Action 17
-3. Surveillance Requirements 17
4. Bases 17
-/
G. Liguid Effluents Concentration 22
1. Requirement 22
2. Action 22
3. Surveillance Requirements 22
4. Bases 22 H. Liguid Effluent Dose 26
1. Requirement 26
2. Action 26
3. Surveillance Requirements 26
4. Bases 26 I. Total Dose 27
1. Requirement 27
2. Action 27
3. Surveillance Requir~ments 28
4. Bases 28 J. Radiological Environmental Monitoring 29
1. Requirement 29
2. Action 29
3. Surveillance Requirements 30 ii
4. Bases 31
a. Monitoring Program 31
b. Land Use Ce.nsus 31
c. Interlaboratory Comparison Program 32 K. SIRW or Temporary Liquid Storage Tank 43
1. Requirement 43
. 2. Action 43
3. Surveillance Requirement 43
4. Bases . . . 43 IV. REPORTING REQUIREMENTS 44 A. Radiological Effluent Release Report 44
1. Supplemental Information 44
2. Gaseous Effluents 45
3. Liquid Effluents 46
4. Radiological Impact on Man 47
.*/
5. ODCM Changes . ....
B. Radiological Environmental Operating Report
c. _Nonroutine Reports V. MAJOR MOD!FICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE . . . . . 52 TREATMENT SYSTEMS A. Licensee Modifications 52 B. Definition of Major Radwaste System Modification 52
1. Purpose 52
2. Definition 52 TABLES A-1 Radioactive Gaseous Effluent Monitoring Instrumentation 5 A-2 Radioactive Gaseous Effluent Monitoring InstrumentatioD 7 Surveillance Requirements B-1 Radioactive Gaseous Waste Sampling and Analysis Program 14 C-1 Radioactive Liquid Effluent Monitoring Instrumentation 18 C-2 Radioactive Liquid Effluent Monitoring Instrumentation 20 Surveillance Requirements D-1 Radioactive Liquid Waste Sampling and Analysis Program . . . . . . . 24
iii
E-1 Radiological Environmental Monitoring Program ... 33 E-2 E-3 F-1 Reporting Level~ for Radioactivity Concentrations in Environmental Samples
.Detection Capabilities for Environmental Sample Analysis Enviro.nmental Radiological Monitoring Program Summary . .
39 40 50
.,.,..*/
iv
Relocated Technical Specifications I. INTRODUCTION The NRG, through 10CFR50. 36a, requires implementation of Technical Specifications on effluents from nuclear power plants. NRG Generic Letter 89-01, dated January 31, 1989, allowed relocation 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 Administrative Controls section of the Technical Specification to satisfy the regulatory requirements of 10CFR50. 36a. The Technical 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 i~
responds with the necessary range and accuracy to known values of*
the parameter which the channel monitors. The Channel Calibration shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the Channel Function Test. The Channel Calibra<tion 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 observation.
This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.
c. Channel Functional Test - a Channel Functional Test shall be:
1. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify operability including alarm and/or trip functions.
2. Bistable channels - the injection of a simulated signal into the sensor to verify operability including alarm and/or trip functions .
1 Rev 2 01/05/94
D. Source Check - a source check shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
E. Off site Dose Calculation Manual (per Plant Technical Specification) - the Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent 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 required by the Technical Specifications and, 2) descriptions of th~ information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by the Technical Sp~cifications.
F. Gaseous Radwaste Treatment System - any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the
/
total radioactivity prior to release to the environment.
G. Members of the Public - all persons who are not occupationally associated with the Plant. This category does not include H.
employees of the utility, its contractors or vendors.
excluded from this category are persons who enter the site to service equipment or to make deliveries.
Also Process Control Program (PCP) - shall contain the current formula, sampling, analyses, 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 wet solid wastes will be accomplished in such a way as to assure compliance 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 Area - any *area at or beyond the Site Boundary access which is not controlled by the licensee for purposes of protection of individuals f'rom exposure to radiation and radioactive materials or, any area within the Site Boundary used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
2 Rev 2 01/05/94
K. Ventilation Exhaust Treatment System - any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.
III. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES A. Radioactive Gaseous Effluent Monitoring Instrumentation
1. Requirement:
The radioactive gaseous effluent monitoring instrumentation channels shown in Table A-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 alarm/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 number of radioactive gaseous effluent monitoring instrumentation channels operable, take the action shown in Table A-1. Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent "Release Report why the inoperability was not corrected in a timely manner .
3 Rev 2 01/05/94
3. Surveillance Requirements:
Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check, Source Check, Channel Calibration and Channel Functional 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 during actual or potential releases of gaseous effluents.
The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20.
The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10CFR Part 50 .
4 Rev 2 01/05/94
Table A-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION
1. WASTE GAS HOLDUP SYSTEM
a. Noble Gas Activity Monitor (RIA 1113) Providing Alarm and Automatic Termination of Release ( 1) At All Times 1
b. Effluent System Flow Rate Measuring Device (FI 1121) (1) At All Times 2
2. CONDENSER EVACUATION SYSTEM (RIA 0631)
a. Noble Gas Activity Monitor (1) Above 210°F 3
3. STACK GAS EFFLUENT SYSTEM
a. Noble Gas Activity Monitor (RIA 2326) ( 1) At All Times 3
b.
c.
Iodine/Particulate/Sampler/
Monitor (RIA 2325)
Sampler Flow Rate Monitor
( 1)
(1)
At All Times At All Times 3
2
d. Hi Range Noble Gas (RIA 2327)* ( 1) Above 210°F 4
4. STEAM GENERATOR SLOWDOWN VENT SYSTEM
a. Noble Gas Activity Monitor (RIA 2320) (1) Above 210°F 3
5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE
a. Gross Gamma Activity Monitor
1 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 (RIA 1810 and 1811) per room
Setpoints for these instruments are exempted from III.B.l limits, but are governed by Emergency Implementing Procedures or Operating procedures .
Setpoints for these instruments are exempted from III.B.l limits, but are governed by Technical Specification 3.l6(f) and Table.3.16.l.
5 Rev 2 01/05/94
Table A-1 (cont'd)
ACTION 1 -
TABLE NOTATION - ACTION STATEMENTS 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 to initiating the release:
a. at least two independent samples of the tank's contents are analyzed, and
b. at least two technically qualified members of the Facility staff independently verify 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 leas.t1 once per 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 channels operable less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples 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 required by the Minimum Channels Operable requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s), within 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 NRG within 30 days following the event putlining the actions taken, the cause of the inoperability and 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 associated with 'that channel shall be closed immediately and action shall be taken to have the affected channel repaired. The dampers associated with the channel shall not be opened until the affected channel has been declared operable .
6 Rev 2 01/05/94
Table A-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST. REQUIRED
1. WASTE GAS HOLDUP SYSTEM
a. Noble Gas Activity Monitor-Providing Alarm D(4) p R(3) Q(l)(2) and Automatic Termination of Release
b. WGDT Effluent Flow Rate Device D(4) NA R NA *'
2. CONDENSER EVACUATION SYSTEM
a. Noble Gas Activity Monitor D M R(3) Q(2) Above 210°F
3. STACK GAS EFFLUENT SYSTEM
a. Noble Gas Activity Monitor .,.,.
D M R(3) Q(2)
b. Iodine Particulate Sampler/Monitor w M** R(3)** NA *
c. Sampler Flow Rate Monitor D NA R NA *
d. Hi Range Noble Gas D M R(3) Q(2) Above 210°F
4. STEAM GENERATOR BLOWDOWN VENT SYSTEM
a. Noble Gas Activity Monitor D M R(3) Q(2) Above 210°F
At all times other than when the line is valved out and locked.
Sampler not applicable.
7 Rev 2 01/05/94
Table A-2 (Cont'd)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK *cHECK CALIBRATION TEST REQUIRED
5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE
a. Gross Gamma Activity Monitor D M R( 3) Q(2) Above 325°F
6. ENGINEERED SAFEGUARDS ROOM VENT SYSTEM
a. Noble Gas Activity Monitor D M R(3) Q(l)(2) Above 210°F TABLE NOTATION (1) The Channel Functional Test shall also demonstrate that automatic isolation o*f this pathway occurs if instrument indicates measured levels above the alarm/trip setpoint.
(2) The Channel. Functional Test shall also demonstrate that control room alarm annunciation occurs if .either of tne following conditions exi~ts.
a. Instrument indicates measured levels above the alarm setpoint (not applicable for Item 3.d, Hi Range Noble Gas).
b. Circuit failure.
(3) a. The Channel Calibration shall be performed using one or more of the reference standards traceable to the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range.
b. For subsequent Channel Calibration, sources that have been related to the (1) calibration may be used.
(4) Channel Check shall consist of verifying indication of flow during periods of release. Channel Check shall be made at least once 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 once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months At least once per 92 days M At least once per 31 days At least once per 18 months p Prior to radioactive batch release At least once per week Rev 2 .1/05/94
B. Gaseous Effluents Dose Rate
1. Requirement:
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: 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
b. For Iodine-131, for Iodine-133, for tritium and for all radionuclides in particulate form with half-lives greater than 8 days: 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) . -.1
3. Surveillance Requirements:
a. The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of B.l.a in accordance with the methodology and parameters in the ODCM.
b. The dose rate 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.l.b in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table B-1.
4. Bases:
This is provided to ensure that the dose at any time at and beyond the Site Boundary from gaseous effluents from all units on the site will be within 10 times the annual dose limits of 10CFR Part 20 to Unrestricted Areas. The annual dose limits are the doses associated with the concentrations of 10 times 10CFR Part 20, Appendix B, Table 2, Column 1. These restrictions provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an Unrestricted Area, either within or outside the Site Boundary, to annual exposure greater than design objectives of 10CFR 50, Appendix I,Section II. B .1. For Members of the Public who may at times be within the Site Boundary, the occupancy of the Member of the Public 9 Rev 2 01/05/94
will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the Site Boundary.
Examples of calculations for such Members of the Public, with the appropriate occupancy factors, shall be given in the ODCM.
specified release rate limits restrict, at all times, The 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). Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA, "Limits for Qualitative Detection 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 gases released in gaseous effluents to areas at and beyond the Site Boundary (see Figure 2-1) shall be limited to the following:
a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation 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 than or equal to 20 mrads for beta radiation.
2. Action:
With the calculated air dose from radioactive noble gases 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 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 above limits.
10 Rev 2 01/05/94
3. Surveillance Requirements:
Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
4. Bases:
This requirement is provided to implement the requirements of Sections II.B, III.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 Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and dat~.
such that the actual exposure of a Member of the Public through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses
due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I,"
Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors", Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the Site Boundary are based upon the historical average atmospheric conditions.
D. I-131. I-133. Tritium. and Particulates
1. Requirement:
The dose to a Member of the Public from Iodine-131, Iodine-133, tritium and au* radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the Site Boundary (see Figure 2-1) shall be limited to the following:
a. During any calendar quarter: Less than or equal to 7. 5 mrems to any organ, and
11 Rev 2 0_1/05/94
2.
b.
Action:
During any calendar year:
mrems to any organ.
Less than or equal to 15 With the calculated dose from the release of Iodine-131, Iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC 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 above limits.
3. Surveillance Requirements:
Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131, Iodine-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 ODCM at least once per.
31 days.
4. Bases:
This requirement is provided to implement the requirements of Sections II.C, III.A and IV.A. of Appendix I, 10CFR Part 50.
The requirements are the guides set forth in Section II.C of Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to Unrestricted Areas will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section II .A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a Member of*
the Public through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I", R~vision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases From Light-Water-Cooled 12 Rev 2 01/05/94
Reactors", Revision 1, July 1977.
for Iodine-131, These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.
requirements Iodine-133, The release rate tritium and radionuclides in particulate form with half- lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the Site Boundary. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man .
13 Rev 2 01/05/94
Table B-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT SAMPLING ANALYSIS TYPE OF DETECTION (LLD) 3 GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (µCi/ml) p p A. Waste Gas Storage Each Tank Each Tank Principal Gamma Emittersb 1 x 104 Tank Grab Sample p p B. Contairunent PURGE Each PURGE Each PURGE Principal Gamma Emittersb 1 x 10 4 Grab Sample
c. Stack Gas Effluent Continuousc wd*e Charcoal I-131, I-133 1 x lo- 12 Sample Continuousc wd*e Particulate Principal Gamma Emittersb 1 x 10- 11 Sample (I-131, Others)
Continuousc Q Composite Sr-89, Sr-90 and 1 x 10- 11 Particulate Gross Alpha Sample Continuousc Noble Gas Noble Gases lE-06 Monitor Gross Beta 0r Gamma 14 Rev 2 01/05/94
Table B-1 (Cont'd)
TABLE NOTATION aThe LLD is defined, in Table E-3, note C.
bThe principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99>'<,
Cs-134, Cs-137, Ce-141, and Ce-144* for particulate emissions. 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 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 accordance with requirements III.B.l, III.C.l, and III.D.l.
1 dsamples shall be changed at least once per 7 days and analyses shall be, completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing or after removal from sampler.
ewith channels operable on iodine monitor RIA 2325 less than required per III .A. l, sampling shall also be performed at least once per 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 changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a.re analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if, 1) analysis shows that the Dose Equivalent I-131 concentration in the primary coolant has not increased more than a factor of 3, and 2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
15 Rev 2 01/05/94
E. Gaseous Waste Treatment System
1. Requirement:
When gaseous waste exceeds a Xe-133 concentration of lE-05
µCi/cc, the Waste Gas Decay Tank System shall be used to reduce radioactive gaseous effluents by holding gaseous waste collected by the system for a minimum of 15 days up to 60 days.
2. Action:
a. If a waste gas decay tank is required to be released with less than 60 days holdup time, the system waste gas tank contents shall be evaluated and the waste gas decay tank with the lowest Xe-133 content shall be released.
b. Gaseous waste may be discharged directly from the waste gas surge tank through a high-efficiency filter or from a waste gas decay tank 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 r~quirements III.B, C, and D.
3. Surveillance Requirements:
Not Applicable.
4. Bases:
The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable" by meeting the design objectives given in Section II.D of Appendix I to 10CFRSO.
It is expected that releases of radioactive materials in effluents shall be kept at small fractions of the limits specified in 20. 1302 of 10CFR20. At the same time the licensee is permitte.9. 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 which may temporarily result in releases higher than such small fractions, but still within the limits specified in III.B, C, and D.
16 Rev 2 01/05/94
F. Radioactive Liquid Effluent Monitoring Instrumentation
1. Requirement:
The radioactive liquid effluent monitoring instrumentation channels shown in Table C-1 shall be operable with their alarm/trip setpoints set to ensure that the limits of III.G are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in 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,
. without delay suspend the release of radioactive liquid 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 number of radioactive liquid effluent monitoring instrumentation channels Operable, take the Action shown in Table C-1. Exert best efforts
3~
to return the instruments to Operable status within 30 days and, if unsuccessful' explain in the next Radioactive Effluent Release Report why inoperability was not corrected in a timely manner.
Surveillance Requ1rements:
the
Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated Operable by performance of the Channel Check, Source Check, Channel Calibration and Channel Functional Test operations at the frequencies shown in Table C-2.
4. Bases:
The radioactive liquJd effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases *of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20. The Operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10CFR Part 50 .
17 Rev 2 01/05/94
Table C~l RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNEL INSTRUMENT OPERABLE ACTION
1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
a. Liquid Radwaste Effluent Line (RIA 1049) (1) 1
b. Steam Generator Blowdown Effluent Line (RIA 0707) (1) 2
2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
/
a. Service Water System Effluent Line (RIA 0833) (1) 3
b. Turbine Building (Floor Drains) Sumps Effluent 3.
Line (RIA 5211)
FLOW RATE MEASUREMENT DEVICES
a. Liquid Radwaste Effluent Line (FIC 1051 or 1050)
(1)
(1) 3 4
4. CONTINUOUS COMPOSITE SAMPLERS (Alarm/Trip Setpoints are not applicable)
a. Turbine Building Sumps Effluent Line (1) 3
b. Service Water System Effluent (1) 3
c. Steam Generator Blowdown Effluent (1) 3 18 Rev 2 01/05/94
Table C-1 (Cont'd)
TABLE NOTATION ACTION 1 - With the number of channels operable less than required by the Minimum Channels Operable requirement, effluent releases may continue provided that prior to initiating 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 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 thi:s*
pathway continue provided grab samples 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 releases via this pathway may continue provided that, 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 10~ microcurie/ml.
ACTION 4 - 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 per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves or tank levels may be used to estimate flow .
19 Rev 2 01/05/94
Table C-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST
1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
a. Liquid Radwaste Effluent Line (RIA 1049) p p R(3) Q(l)(2)
b. Steam Generator Blowdown Effluent Line (RIA 0707) D M R(3) Q(l)(2)
2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVID!NG AUTOMATIC TERMINATION OF RELEASE
a. Service Water System Effluent Line (RIA 0833) D M R(3) Q(2)
b. Turbine Building (Floor Drains) Sumps Effluent Line (RIA 5211) D M R(3) Q(2)
3. FLOW RATE MEASUREMENT DEVICES
a. Liquid Radwaste Effluent Line (FIC 1051 or 1050) 0(4) NA R NA
4. TURBINE SUMP EFFLUENT COMPOSITER D(4) NA NA NA
5. SERVICE WATER SYSTEM EFFLUENT COMPOSITE SAMPLER 0(4) NA NA NA
6. STEAM GENERATOR BLOWDOWN EFFLUENT COMPOSITER D(4) NA NA NA
Rev 2 01/05/94
Table C-2 (Cont'd)
TABLE NOTATION (1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if instrument indicates measured levels above the alarm/trip setpoint.
(2) The Channel Functional Test shall also demonstrate that Control Room alarm ahnunciation occurs if either of the following conditions exists:
a. Instrument indicates measured levels above the alarm setpoint.
b. Circuit failure.
(3) a. The Channel Calibration shall be performed using one or more of the referertce standards traceable to the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range.
b. For subsequent Channel Calibration, sources that*have been related to the (a) calibration may be used.
(4) Channel Check shall consist of verifying indication of flow during periods of releases. Channel Check shall be made at least once 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 once per 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 Rev 2 01/05/94
G. Liquid Effluents Concentration
1. Requirement:
The concentration of radioactive material 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 gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 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 Requirements:
>/
a. Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of' Table D-1.
4.
b.
Bases:
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 maintained within the limits of G.l above.
This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to Unrestricted Areas will be less than 10 times the concentration levels specified in 10CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in Unrestricted Areas will result in exposures within the Section II .A design objectives of Appendix I, 10CFR Part 50, to a Membe~ of the Public. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and 10 times the effluent concentration in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
22 Rev 2 01/05/94
The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA, "Limits for Qualitative Detection 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) .
23 Rev 2 01/05/94
. Table D-1 RADIOACTIVE LIQUID WA-STE SAMPLING AND ANALYSIS PROGRAM Sampling Minimum Analysis Type of Activity Lower Limit of Detection (LLD)a Gaseous Release Type Frequency Frequency Analysis (µCi/ml)
A. Batch Waste P P Principal Gamma s x 10-1 Release Each Batch Each Batch Emittersc Tanksb I-131 1 x 10-6 p M Diss.olved and 1 x 10-5 One Batch/M Entrained Gases (Gamma Emitters) p M H-3 1 x 10-s Each Batch Composited Gross Alpha 1 x 10-7
.'/
p Q Sr-89, Sr-90 5 x 10-8 Each Batch Composited B. Continuous Releasese (Turbine Sump, Steam Generator Continuousf w
Compositef Principal Gamma Emitters.c I-131 5 x to-7 1 x 10-6 Blowdown and Service Water) M M Dissolved and 1 x l0-5 Grab Sample Entrained Gases (Gamma Emitters M H-3 1 x 10-5 Continuousf Compositef Gross Alpha Q Sr-89, Sr-90 5 x 10-8 Continuousf Compositef FREQUENCY NOTATION P Prior to batch release M Calendar month Q Calendar quarter W Calendar week 24 Rev 2 01/05/94
Table D-1 (Cont'd)
TABLE NOTATION aThe LLD 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 batch shall be isolated and then thoroughly mixed to assure representative sampling.
cThe principal 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 analyzed and reported in the Radioactive Effluent Release Report.
>'( (LLD - 5ED-06 because of low gamma yields).
dA composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.
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 volume 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 2 01/05/94
H. Liquid Effluent Dose
1. Requirement:
The dose or dose commitment to a Member of the Public from radioactive materials in liquid effluents released from each 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 equal to 10 mrems to any organ.
2. Action:
With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRG within 30 days a Specia],1 Report that identifies the cause(s) for exceeding the limit(s) and defines the correctiv~ 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 3.
with the above limits. This Special Report shall also include the results of radiological analyses of the drinking water source.
Surveillance 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, 10CFR 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 implement the guides set forth in Section IV .A of Appendix I to assure that the releases of radioactive material in liquid effluents to Unrestricted Areas will be kept "as low as is reasonably achievable." Also, for freshwater sites with drinking water supplies that can be potentially affected by Plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide 26 Rev 2 01/05/94
concentrations in the finished drinking water that are in excess of the requirements of 40CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I conformance with the guides of Appendix I be shown by that calculational procedures based on models and data, such that the actual exposure of a Member of the Public through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 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. Requirement:
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 than 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 calculated 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.H.l.b, calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of III.I.l have been exceeded. If such is the case, prepare and submit to the NRC within 30 days a Special Report that defines the corrective act-ion to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10CFR Part 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a Member of the Public from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the.
release(s) covered by this report. It shall also *describe levels of radiation and concentrations of radioactive material 27 Rev 2 01/05/94
involved and concentrations.
the cause of the exposure levels If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40CFR Part 190.
or Submittal of the report is considered a timely request and a variance is granted until staff action on the request is complete.
3. Surveillance Requirements:
a. Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with III.C.l, III.D.l and III.H.l and in accordance 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 I. 2 above. ..,
4. Bases:
This requirement is provided to meet the dose limitations of 40CFR Part 190 that have been incorporated into 10CFR Part 20 by 46 FR 18525. I t also requires the preparation and submittal of a Special Report whenever* the calculated doses from Plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except for thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a Member of the Public will exceed the dose limits of 40CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I and if direct radiation doses from the reactor units and outside storage tanks are kept small.
The Special Report will describe a course of action that should result in the limitation of the annual dose to a Member of the Public to within the 40CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the Member of the Public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any Member of the Public is estimated to exceed the requirements of 40CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40CFR Part 190 have not already been corrected), in accordance with the provisions of 28 Rev 2 01/05/94
40CFR Part 190.11 and 10CFR Part 20.2203, is considered to be a timely request and fulfills the requirements 40CFR Part 190 until NRC staff actiori is completed.
of The variance only relates to the limits of 40CFR Part 190 and does not apply in any way to the other requirements for dose limitation of 10CFR Part 20. An individual is not considered a Member of the Public during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
J. Radiological Environmental Monitoring
1. Requirement:
The radiological environmental monitoring program shall be conducted as specified in Table E-1.
2. Action:
a. With the radiological e.nvirorunental monitoring program not being conducted as specified in Table E-1, prepare; and submit to the NRC, in the Annual Radiological Environmental Operating Report a description of the' reasons for not conducting the program as required and the plans for preventing a recurrence .
b. With the level of radioactivity as the result of Plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table E-2 when averaged 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 more than one of the radionuclides in Table E-2 are detected in the sampling medium, this report shall be submitted if:
Concentration (1) + Concentration (2) + ... -~ 1.0 Reporting Level (1) Reporting Level (2)
When radionuclides other than those in Table E-2 are detected and are the result of Plant effluents, this report shall be submitted if the potential annual dose to a Member of the Public is equal to or greater than the calendar year limits of III. C .1, III. D .1, and III.H.l. This report is not required if the measured level of radioactivity was not the* result of Plant effluents; however, in such an event, the condition shall be reported and
described in the Annual Radiological Environmental Operating Report .
29 Rev 2 01/05/94
c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table E-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Identify the cause of the unavailability of samples and identify the new location(s) for obtaining replacement samples in the next Annual Radiological Environmental Report.
3. Surveillance Requirements:
a. The radiological environmental monitoring 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 neares~'
milk animal, the* nearest residence and the nearest, garden of greater than 50 m2 (500 ft 2 ) producing broa~
leaf vegetation. Broad leaf vegetation sampling of at least three_ different kinds of vegetation may be .*
performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. For broad leaf vegetation sampling, Table E-1, item 4c, shall be followed, including analysis of control samples.
c. The land use census shall be conducted during the growing 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 local agriculture authorities. The results of. the land use census shall be included in the Annual Radiological Environmental.Operating Report and shall 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 Program that has been approved by the NRG.
e. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.
30 Rev 2 01/05/94
4.
f.
Bases:
The environmental air samplers shall be operationally checked monthly and airflow verified annually.
a. Monitoring Program The radiological environmental monitoring program provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of Members of the Public resulting from the station operation. This monitoring 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 radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological./
Assessment Branch Technical Position on Environmentat Monitoring. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table E-3 are considered optimum for routine environmental measurements in industrial laboratories.
Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL- 300 (revised annually), Currie, LA, "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry, " Anal Chem 40 , 5 8 6 - 92 ( 19 68) , and Hartwell, J K, "Detection Limits for Radioanalytical Counting Techn'.i.ques, " Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
b. Land Use Census:
This requirement is provided to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the radiological environmental monitoring program are made if required by results of this census. The best information from the 31 Rev 2 01/05/94
door-to-door survey, used.
from aerial survey or from consulting with local agricultural authorities shall be This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR Part 50.
Restricting the census to gardens of greater than 40 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (16 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (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 independent checks on the precision and accuracy o.fr the measurements of radioactive material in.
environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are
valid for the purposes of Section IV.B.2 of Appendix I .
to 10CFR Part 50.
32 Rev 2 01/05/94
Table E-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type of Frequency and/or Sample Samples and Sample Locations 3 Collection Frequency of Analysis
1. DIRECT RADIATIONb 21 routine monitoring stations Quarterly Gamma dose quarterly either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:
An inner ring of stations, one in each overland meteorological sector (9) in the general area of the
Site Boundary.
An outer ring of stations, one in each overland meteorological sector (9) within the 12 km range from the site.
The balance of the stations (3) to be placed to serve. as control stations.
33 Rev 2 01/05/94
Table E-1 (cont'd)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type of Frequency and/or Sample Samples and Sample Locationsa Collection Frequency of Analysis
2. AIRBORNE Radioiodine and Samples from 5 locations. Continuous sampler Radioiodine Canister:
Particulates operation with sample I-131 analysis weekly for 3 samples from within 6 km of collection weekly or each filter change.
the Site Boundary in different more frequently if sectors (2.4 km-SSW, 5.6 km-ESE, required by dust Particulate Sampler:
and 1.6 km-N). loading. Gross beta radioactivity analysis following filter
' 1 sample from the vicinity of a changed. Gamma isotopic community having the highest analysise if gross beta calculated annual average ground >l. 0 pCi/m3 .
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 2 01/05/94
Table E-1 (cont'd)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type of Frequency and/or Sample Samples and Sample Locationsa Collection Frequency of Analysis
3. WATERBORNE
a. Lake (surface) Plant lake water inlet. Composite sample over Gross beta (>10 pCi/l 1-month periodf. requires gamma) and tritium monthly.
b. Well (drinking) Samples from Plant, State Monthly - grab sample. Gross beta (>10 pCi/l Park, and Covert Township requires gamma) and park wells. tritium monthly.
c. Lake (drinking) 1 sample of South Haven Composite sample over Gross beta (>10 pCi/l drinking water supply. 1-month periodf. requires gamma) and tritium monthly.
d. Sediment from 1 sample from between north Semiannually. Gamma isotopic analysise shoreline boundary and Van Buren State semiannually.
Park beach.
35 Rev 2 01/05/94
Table E-1 (cont'd)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type of Frequency and or Sam le Sam les and Sam le Locations 3 Collection Fre uenc of Anal sis
4. INGESTION
a. Milk Samples from milking animals Monthly Gamma isotopice and I-131 in 3 locations between 5-13 km analysis monthly.
distance.
1 sample from milking animals at a control location, 15-30 km distance.
b. Fish and Sample 2 species of Sample in season or Gamma isotopic analysise Invertebrates commercially and/or semiannually if they on edible portions.
recreationally important are not seasonal.
species in vicinity of Plant discharge area. 1 sample of same species in areas not influenced by Plant discharge.
36 Rev 2 01/05/94
Table E-1 (cont'd)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type of Frequency and/or Sample Samples and Sample Locations 3 Collection Frequency of Analysis
c. Food Products 1 sainple each of two principal At time of harvestg. Gamma isotopic analysese fruit crops (blueberries and on edible portion.
apples).
Samples of 3 different kinds of Monthly when Gamma isotopice and I-131 broad leaf vegetation grown available. analysis.
nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milk sample is not performed. (SE or SSE sectors near site).
1 sample of each of the similar M~nthly when Gamma isotopice and I-131 broad leaf vegetation grown available. analysis.
15-30 km distance in the least prevalent wind direction if milk sampling is not performed.
(SSW or S sectors).
37 Rev 2 01/05/94
Table E-1 (cont'd)
Table Notation aDeviations are permitted from the required sampling schedule if .specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic .sampling equipm~nt and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program.
bone or more instruments, such as a pressurized ion chamber, for measuring and.recording dose rate continuously may be 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 zones in a packet are considered as two or more dosimeters.
cThe purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be sµbstituted.
dAirborne particulate sample filters shall be analyzed for gross 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 in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
eGamma isotopic analysis means 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) of liquid samples is proportional to the quantity of liquid discharged and in which the method of sampling employed results in a specimen that is representative of the liquid released (continuous composites or daily grab composites which meet this criteria are acceptable).
gif harvest occurs more than once a year, sampling shall be performed during each discrete harvest.
38 Rev 2 01/05/94

Table E-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Water Airborne Particulates Fish Milk Food Products Analysis (pCi/l)' or Gases (pCi/m3 ) (pCi/kg. Wet) (pCi/l) . (pCi/kg. Wet)
H-3 20,000*
Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 '400 I-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300
For drinking water samples. This is 40CFR Part 141 value. If no drinking water pathway exists,
. a value of 30, 000 pCi/l may be used.
39 Rev 2 01/05/94
Table E-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS 3 LOWER LIMIT OF DETECTION (LLD)bc Water Airborne* Particulates Fish Milk Food Products Sedi~ent Analysis (:QCiLl} or Gases (:QCiLm 3 } (:QCiLkg, Wet} (:QCiLl2 (QCit'.'.kg, Wet2 (QCiLkg, Dry2 Gross Beta 4 0.01 H-3 2,000*
Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30; 260 Zr-Nb-95 15 I-131 ld 0.07 1 60 Cs-134 15 0.05 130 15 . 80 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15
If no drinking water pathway exists, a value of 3,000 pCi/l may be used.
40, Rev 2 01/05/94
Table E-3 (Cont'd)
TABLE NOTATION a This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and r*eported in the Annual Radiological Environmental Operating Report.
bRequired detection capabilities for thermoluminescent dosimeters used for
.environmental measurements are given in Regulatory Guide 4.13.
cThe LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
LLD =
E
V
2 . 22
Y
Exp ( - ).t, t) ....
Where:
LLD is the "a priori" lower limit of detection as defined above, 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.
as 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 disiµtegrations per minute pet picocurie.
Y is the fractional radiochemical yield, when applicable.
). is the radioactive decay constant for the particular radionuclide.
t.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 ~t should be used in the calculation .
41 Rev 2 01/05/94
Table E-3 (Cont'd)
TABLE NOTATION It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.
dLLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
42 Rev 2 01/05/94
K. SIRW or Temporary Liquid
1. Requirement:
Stora~e Tank 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.
_gb . . . + _gi <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
IV. REPORTING REQUIREMENTS A. Radiological Effluent Release Report The Radioactive Effluent Release Report shall be submitted in accordance with 10CFR 50. 36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and Process Control Program and (2) in conformance with 10CFR 50.36a and Section IV.B.1 of Appendix I to 10CFR 50.
The report shall include an estimate of the uncertainty associated with the measurement of radioactive effluents. This error term is included to provide an estimate of the uncertainty and is not to be considered the absolute error associated with the measurements or to be used in determining compliance with these requirements.
These estimates will be based on a statistical analysis of a series of sample results (weighed appropriately for counting statistics) taken once a year from a minimum of one typical gaseous waste tank and from a minimum of one typical liquid waste tank. For noble.
gases released to the atmosphere from other than the waste gas 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 taken over one release per year) from each source contributing more than 10% of the total annual release.
The error term for iodine and particulates released to the atmosphere will be based on the counting statistics for one stack gas sample taken during the year.
The report shall include an estimate of the lower level of detection (in µCi/ml) if the unidentified portion of the release exceeds 10%
of the total annual releases. This estimate of the lower level of detection will be made for those gamma emitting isotopes listed in Appendix B of Regulatory Guide 1.21 (June 1974) and will be provided based on a typical background gamma spectrum.
The report shall provide ehe following specific terms:
1. Supplemental Information
a. Batch Releases:
The report should provide information relating to batch releases of liquid and gaseous effluents which are discharged to the environment. This information should include the number* of releases, total time period for 44 Rev 2 01/05/94
b.
batch releases, and the maximum, mean, and minimum time period of release.
Abnormal Releases The number of abnormal releases of radioactive material to the environment should be reported. The total curies of radioactive materials released as a result of abnormal releases should be included.
2. Gaseous Effluents
a. Gases
1) Total curies of fission and activation gases releases.
2) Average release rates (µCi/s) of fission and activation gases for the quarterly 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
b. Iodines 1) radionuclides determined to be released, based on analyses of fission and activation gases.
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 particulate form with half-lives greater than 8 days determined to be released.
2) Average release rate (µCi/s) of radioactive material in particulate form with half-lives greater than 8 days .
45 Rev 2 01/05/94
3) 4)
Percent of limit for radioactive material in particulate form *With half-lives greater than 8 days.
Total curies for each of the radionuclides in particulate form determined to be released based on analyses performed,
-5) Total curies of gross alpha radioactivity determined to be released.
d. Tritium
1) Total curies of tritium determined to be released in gaseous effluents.
2) Average release rate (µCi/s) of tritium.
3) Percent of applicable limits for tritium.
3. Liquid Effluents
.*-'/
a. Mixed Fission and Activation Products
1) Total curies of radioactive material determined to be. released in liquid effluents (not including tritium, dissolved and/or entrained gases, and alpha-emitting material).
2) Average concentrations (µGi/ml) of mixed fission and activation products 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) Quarterly sums of total curies for each of the radionuclides determined to be released in liquid effluents based on analyses performed.
b. Tritium*
1) Total curies of tritium determined to be released in liquid effluents.
2) Average concentrations (µCi/ml) of tritium released in liquid effluents to unrestricted areas, averaged over the quarterly periods covered by the report.
46 Rev 2 01/05/94
c.
3) Percent of applicable limit of average concentrations released to unrestricted areas.
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 radionuclides determined to be released as dissolved and/or entrained gases in liquid effluents.
d. Alpha Radioactivity .*/
Total curies of gross alpha-emitting material determined to be released in liquid effluents .
e. Volumes 1) 2)
Total measured. volume (liters),
dilution, of liquid effluent released.
prior Total determined volume, in liters, of dilution to water used during the period of the report.
4. Radiological Impact on Man:
The Radioactive Effluent Release Report shall include potential doses to individuals and populations calculated using measured effluent and averaged meteorological data 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 receiving water~related exposure pathways.
b. The maximum offsite air doses (greater than 1 millirad) due to beta and gamma radiation at locations near ground level from gaseous effluents .
47 Rev 2 01/05/94
c. Organ doses (greater than 1 millirem) to individuals in unrestricted areas from radioactive iodine radioactive material in particulate form from the major pathways of exposure.
and
d. Total body doses (greater than 1 manrem) to the population and average doses (greater than 1 millirem) to individuals in the population from receiving water-related pathways to a distance of SO miles from the site.
e. Total body doses (greater than 1 manrem) to the population and average doses (greater than 1 millirem) to individuals in the population from gaseous effluents to a distance of SO miles from the site.
5. ODCM Changes:
The Radiological Effluent Release Report shall include any changes made during the reporting period to the Offsite Dose Calculation Manual (ODCM), as well as a listing of ne~*/
locations for dose calculations and/or environmentai.
monitoring identified by the land use census pursuant_ to III.J.3.c.
B. Radiological Environmental Operating Report The Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results-of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in; (1) the ODCM, and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix 1 to 10CFRSO.
The Annual Radiological Environmental Operating Reports shall include summaries, interpretation and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the Plant operation on the environment. The reports shall also include the results of land use census pursuant to III.J.3.c.
48 Rev 2 01/0S/94
The Annual Radiological Environmental Operating Reports shall include summarized and tabulated results in the format of Table F-1 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data_
shall be submitted as soon as possible in a supplementary report.
The reports shall also include the following; a summary description of the radiological environmental monitoring program, including sampling methods for each sample type, a map of all sampling locations keyed to a table giving distances and directions from the reactor and the results of land use census required by III.J.3.c and results of the Interlaboratory Comparison Program required by III.J.3.e.
C. Nonroutine Reports
-A report shall be submitted to the NRG in the event that; 1) the Radiological Environmental Monitoring Programs are not substantially conducted as described* in Section III .J, or 2) an unusual O_l\t important event occurs from Plant operation that causes* *:.a.
significant environmental impact or affects a potential environmental impact. Reports shall be submitted within 30 days .
49 Rev 2 01/05/94
Table F-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility ~~~~~~~~~~~~~~~ Docket No Location of Facility ~~~~~~~~~~~~~~ Reporting Period ~~~~~~~~~-
(County, State)
Type/Total Lower Limit All Indicator Medium or Pathway Number of of Locations Control Locations Number of Sampled Analyses Detection 3 Mean (f)b Name Mean (f)b Mean(f)b REPORTABLE (Unit of Measure.) Performed (LLD) Rangeb Distance & Direction Rangeb Rangeb OCCURRENCES Air Particulates Gross {J 416 0.003 0.08 (200/312) Middletown 0.10(5/52) 0.08 (8/104)- 1
. (pCi/m3) (0.0S-2.0) 5 miles 340° (0.08-2.0) (0.05-1.40) rSpec 32 Cs-137 0.003 0.05 (4/24) Smithville 0.08 (2/4) <LLD 4 (0.03-0.13) 2.5 miles 160° (0.03-0.13)
Ba-140 0.003 0.03 (2/24) Podunk 0.05 (2/4) 0.02 (1/8) 1 (0.01-0.08) 4 miles 270° (0.01-0.08)
Sr-89 40 0.002 <LLD <LLD 0 Sr-90 40 0.0003 <LLD <LLD 0 50 Rev 2 01/05/94
Table F-1 (Cont'd)
Type/Total Lower Limit All Indicator Medium or Pathway Number of of Locations Control Locations Number of Sampled Analyses Detectiona Mean (f)b Name Mean (f)b Mean(f)b REPORTABLE (Unit of Measure.) Performed (LLD) Rangeb Distance & Direction Rangeb Rangeb OCCURRENCES Fish pCi/kg (dry weight) rSpec 8 Cs-137 80 <LLD <LLD 90 ( 1/4) 0 Cs-134 80 <LLD <LLD <LLD 0 Co-60 80 120 (3/4) River Mile 35 See Column 4 <LLD 0 (90-200) Podunk River aNominal Lower Limit of Detection (LLD) as defined in table notation c of Table E-3.
~ean and range based upon detectable measurements only. Fraction of detectable measurements at specific locations is indicated in parentheses* ( f).
The example data are provided for illustrative purposes only.
I 51 Rev 2 01/05/94
v.* MAJOR MODIFICATIONS SYSTEMS A.
TO RADIOACTIVE Licensee Modifications LIQUID AND GASEOUS W'ASTE TREATMENT Licensee initiated major modifications to the radioactive liquid and gaseous 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 interfaces 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 Plarit, General Manager.
B. Definition of Major Radwaste System Modification 1.
Purpose:
The purpose of this definition is to assure that this requirement will be satisfied under clearly identifiable circumstances, and with the objective that current radwaste system capabilities are not jeopardized.
2. Definition:
A major radwaste system modification is a modification which would remove (either by bypassing*for greater than 7 days or physical removal) or replace with less efficient equipment, any components of the radwaste system:
a. Letdown filte~s or demineralizers.
b. Vacuum degassifier (not applicable when the reactor is in cold shutdown and depressurized).
c. Miscellaneous or clean waste evaporators.
d. The present waste gas compressor/decay tank system.
e. Fuel Pool filters/demineralizers.
52 Rev 2 01/05/94
f.
g.
Radwaste polishing demineralizers.
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 degassifier with steam, jet degassifier, 2) replacement of waste gas system with cryogenic system, 3) replacement of asphalt solidification with cement system, and 4) change from deep bead resins to Powdex, etc .
53 Rev 2 01/05/94
ODCM Appendix B DOCKET 50-255 - LICENSE DPR PALISADES PLANT*
REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR 20.302 Revision 0 August 1, 1991 Approved I .'Y/io/e; I MRN Manager - Radi ol ogi cal Services Date
~ z_,I. .,. '!./
U:UT§tor Tech Review~
/ D*tr
~r 1-t ~(
Date C?OA.&h~ Sl- OB :2-4 6-14--ct. l PRC Date Applicability Reviewed: ~ 5-S" -f3
~~ //~~h-3 Plan t Ge_neral Nanager Date
ODCM Appendix B
Page 1 Request to Retain Soil in Accordance with 10CFR 20.302 Consumers Power Company correspondence dated November 12, 1987 and January 25, 1988 requested authorization to dispose of contaminated soil in place as specified by 10CFR 20.302. The area known as the South Radwaste Area has been contaminated by numerous c~oling tower overflows and contamination was redistributed by heavy rain showers. Although_ the majority of the radioactive material has been packed for waste shipment, a large volume of very low activity radioactive material remains. This volume of material would be very expensive to ship as waste.
The specific area contaminated is noted as Area B on the attached survey grid map in reference 1. The entire area is fenced and is about 12,000 sq ft of soil exposed with the remainder buildings and asphalt. The inhalation pathway is for breathing suspended soil from this area. The radworker could -receive 8.03E-04 mRem/50*-year maximum organ (liver) dose and the infant could receive 3 .16E-05 mRem/50-year maximum organ (liver) dose, both of which are insignificant. Direct dose to a radworker is less than 2E-03 mRem/hr. Occupancy in this area should not average more than 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s/week or 100 hour0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months s/year, which would result in a dose of <1 mRem/year.
The radwaste activities which caused." the contamination of the soil were
completely relocated to a new east radwaste area. The South Building has been deconned and is being used for non-radwaste activities. *Some fixed contamination is present in floor cracks and vaults. This has been documented for plant decommissioning. No further contamination will be added to the south area from the South Radwaste Building. In spite of this commitment, revocation of Michigan shipping privileges in November 1990 require the use of this area to store packaged low level radioactive waste (LLV). Use of this building is* addressed in CPCo's letter to NRC Document Control Desk, April 24, 1991 which is entered as reference 6.
This LLV, in the form of dry active waste (DAV) will be packaged in metal boxes and labeled, ready for future shipment to burial sites. The DAV metal shipping boxes will be stored off the floor to prevent water damage. The metal shipping
. boxes are strong, tight containers designed to prevent any leakage of radioactive material during transportation .. Incidental water contact will not result in the spread of contamination. Radioactive waste will not be processed in the South Radwaste Building and the building will be maintained as a normally clean (radiologically) area.
)
)
Rev 0.
8-1-91
ODCH Appendix B Page 2 References (1) CPCo's letters, T.C. Bordine to NRC Document Control Desk, November 12, 1987 and January 25, 1988.
(2) Memorandum from L.J. Cunningham, DREP to T.R. Quay, T.V. Wambach, "Request for Additional Information (RAI)", March 15, 1988, April 7, 1989, and January 12, 1990. *
(3) CPCo's supplement to Reference (1), J.L. Kuemin to NRC Document Control Desk, June 27, 1988.
(4) CPCo's supplement to References (1, 2), G.B. Slade to NRC Document Control Desk, August 31, 1990.
(5) CPCo's letter, T.P. Neal to B. Holian, October 23, 1990. (Typo of 10/13/90 in original reference).
(6) CPCo's letter, G.B. Slade to NRC Document Control Desk, April 24, 1991.
"Use of South Storage Building as an Interim Radioactive Waste Storage Building".
(7) NRC Letter, Brian Holian to G.B. Slade, CPCo, June 7, 1991, "Approval and Conditions to Retain Soil in Place".
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ODCM - APPENDIX B REFERENCE 1 General Offices:
ccnsumers Power POWERING MICHIGAN'S PROGRESS 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550
. November 12, l987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET .so~255 - LICENSE DPR PALISADES PLANT -
REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR20.302 The Code of Federal Regulations, Title 10, section 20.302 allows for approval of proposed procedures to dispose of licensed material in a manner not other-wise authorized in the regulations. Flooding of the South Radwaste Building has caused contamination of 4,173 cubic feet of soil with 2,992.6 µCi of Cs-137 and 79.3 µCi of Co-60. The area is approximately 30 meters from Lake
.r:. Michigan. Site hydrology (Attachment 2, FSAR 2.2) indicates most of the
'*-) activity will migrate to Lake Michigan in a few years. In July, 1986 a
two-fold evaluation began to identify and map the extent of the ground contamination in the flood plain. The initial findings and evaluation were provided to NRC and the Michigan Department of Public Health by internal letter dated September 26, 1986, to LHueter, NR~, Region III.
!.n Consumers Power Company requests authorization. to dispose of this soil inplace as the costs of disposal at a burial ground is estimated at $270,000 while radiological consequences to the general public and site employees is very low. The activities in the contaminated soil were input as a single radio-active liquid release to Lake Michigan into the NRC LADTAP Code. The output indicated an estimated wholebody dose to the general public (50 mile radius population l.05E06) of l.69E-02 manRem or l.6E-05 millirem per person. The maximum estimated wholebody dose to an individual would be 5.13E-03 millirem and maximum organ dose (teenage liver) would be 8.67E-03 millirem. The maximum whole body dose rate was.assumed to- be at 18 inches from contaminated soil. The maximum whole body dose rate calculated using the Microshiel.d Code was l.OZE-02 mR/hr. Occupancy of this area is controlled by the Radiological Safety Department and secured by a locked fence. Average yearly occupancy is approximately 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per week per individual for 4 to 5 individuals. A radiation worker should not exceed an additional wholebody dose of 4.08 millirem/year.
Flooding of the South Radwaste Building as a result of the cooling tower overflows is being addressed in two stages. *For the short term the cooling tower bypass valve is now electrically isolated during cooling tower opera-
tion. Most previous flooding has been due to instrument failures that cause the valve to open during normal operation. In addition the South Radwaste Building has been decontaminated to eliminate or minimize contamination that TPN-HPOl-NLOl Rev 0 8-1-91
~uclear Regulatory Commission 2 Palisades Plant 10CFR20.302 Request November 12, 1987
could be transported to the environment. A long term solution to remove radwaste activities from this area is being included in the.Five-Year Plan.
The activity released to the environment from a flooding release prior to 1986 was estimated and added to the liquid section of the Semi-Annual Radiological Effluent Release Report dated February,28, 1986. Following approval of this application, it is proposed to account for current activity as an abnormal liquid release included in the semi-annual effluent report. A background, evaluation and survey results discussion follows in Attachment A. Attachment 1 is the Microshield Code output and Attachment 2 is FSAR section 2.2 (including referenced tables and figures) on site hydrology.
Pursuant to 10CFR170.12(c) a check in the amount of $150 is attached.
Thomas C Berdine (Signed)
Thomas C Berdine Administrator, Nuclear Licensing CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Attachment
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TPN-HPOI-NLOI Rev 0 1-91.
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ATTACHMENT A Consumers Power .Company Palisades Plant Docket 50-255
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,i EVALUATION AND SURVEY RESULTS
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November 12, 1987
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I TPN-HPOl-NLOl 10 Pages *
Rev O 8-1-91
Background
In 1986, a soil survey was conducted south of the Turbine Building which included the South Radwaste area. The survey was cond.ucted due to the South Radwaste Building ~eing in the main flowpath of 'A' Cooling Tow.er, which has overflowed on three separate occasions in 8* years. The survey found that radioactive material was deposited in the soil due to the flooding of contami-*
nation and radioactive material areas inside the South Radwaste Building.
Other areas sampled that were not in th.e flood plain were; liquid radwaste
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storage tanks, T-90, T-91, storm drains., the beach and the sand dunes. The survey included a survey grid, surface sample results and core sample results.
All contaminated areas found in Are~ A (Figure 1) were packaged as radwaste.
In addition, the highest activity areas adjoining the South Radwaste Building were also packaged. A total of 16-98 cubic foot boxes were packaged containing over 85 percent of the estimated activity.
Evaluation In August of 1987, the survey was conducted again to prepare this report and to verify the location of the ground contamination and if any contamination migrated further into the ground since the 1986 survey. The survey was a two phase evaluation with the first phase being a mapped area consisting of 25' x 25' squares south of the Turbine Building. Once mapped out, surface samples were taken in this area *. The intent of this phase was to accurately map the location and determine the activity in ~Ci/gram of all ground surface contami-nation. Each surface sample consisted of approximately 20 $rams of soil taken Rev 0 MI0987-0066A-NL02 8-1-91
from the top 1/2" of ground and placed in a petri dish for analysis on the Multi-Channel Analyzer (MCA). Over 275 samples were collected and analyzed with two surface samples being taken in each sector. All samples were counted on MCA, Intrinsic Detector #1. Figure 2 shows the sector where activity was detected and their highest levels in µCi/gram.
Phase II was initiated after completion of the "surface" sample analysis. This consisted of taking core samples in 6" increments where activity was detected.
Core samples were taken until two consecutive core samples reflected no activ-ity. Core samples were also taken below the activity levels found in the 1986 soil survey ~ntil two consecutive core samples revealed no activity.
~:
"*') Figure 3 indicates the depth level where activity was no longer detectable.
For example, 6 inches is indicated in H-10 on Figure activity was only detected on the surface.
3. This indicates that H-9-and I-10 indicate 18" which t.n means activity was dete.cted only at 12". Table 1 shows the results summary in
µCi/gram of the highest activity at all sample locations. The sector numbers respond to grid coordinates shown on Figures 1, 2 and 3.
In addition to the sample sectors shown on.Figure 1, 25 samples were collected at various locations on site. These include surface and core samples around T-90, and T-91 on the Northwest side of the Turbine Building (location not shown on figures). Surface samples were taken under the asphalt around the South Radwaste Building. These are indicated by a hexagon on Figure 1 in F-11, fl -~
)
I-12 and K-10 sectors. Core samples taken under the South Radwaste Building are indicated by circles on Figure 1. Of the areas sampled above activity was Rev
o MI0987-0066A-NL02 8-1-91
found only under the East side of the South Radwaste Building in sector I-9 (Table 1).
In the 1986 soil survey other areas were sampled that were not in the flood plain of the South Radwaste Building. Those included Feedwater Purity Build-ing, North Storage Building, beach areas North and South of Plant, North and Northeast sand dunes and various storm drains. In all of these areas no activity was detected. Therefore, they were not sampled in the 1987 soil survey as they were not in the flood plain.
..n Since the 1986 soil survey, asphalt has been placed over various locations in
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the protected area. Asphalt was placed around all storm drains and approx!-
9') . mately 50% of the South end of the Turbine Building. Before asphalt was laid down, about 3-6" of the top soil was removed and taken offsite. The soil before leaving site was sampled and counted with no activ.ity detected.
Results To quantify activity and determine impact, the areas of ground contamination were separated into two areas. Area A which contains all the sectors (A-L, 1-8) North of the "black top" to the Turbine Building. Area B contains all sectors (C-L, 9-14) South of "black top" in the vicinity of the South Radwaste Building. In Area A no activity. was detected, therefore it was not used in determining activity or impact.
Rev 0 8-1-91 MI0987-0066A-NL02 .
In Area B activity was detected in almost* all sectors to the East of the South
. Radwaste Building (Figure 2). Activities ranged from 2.07E-6 µCi/gram (E-11) to 3.75E-5 µCi/gram (H-11). Cs-137 was the primary radionuclide present in all samples with two other samples containing Co-60 l .12E-5 µCi/gram at 6'.' and 5.80E-6 µCi/gram at 12" (I-9 East Figure 2). The greatest depth where activity was detected was in sector H-11 at 18" and when compared to the 1986 soil .
survey the activity has migrated down into the soil 6" inches further.
Activity was detected at the surface in sectors E-11, E-13, J-12 and L-9 and at 6" in L-9. This was a result of moving the sand deposited on the asphalt
...., during the flood to these sectors and the movement of soil during the grading and dumping* during the asphalting of the South Radwaste area.
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Activity in µCi was calculated for each_sector (Table 2) by the following formula: sector ft 2 x depth of activity ft x *48144 grams/ft 3 x activity
(µCi/gram) * µCi. *Average liter of soil weighed 1700 grams x 28.32 L/ft 3 *
'Jl 48144 grams/ft 3
The first level at which no activity was detected_ was used to
"'I" determine depth of activity. In a few sectors, activity was only detected on the first 1/2" of s~il, but for determining cubic feet and activity a depth of 6" was used. For example, activity for H-10 was calculated as. follows: 625 ft. 2 x .5 ft. depth x 48144 grams/ft 3 x 2.6E-6 µCi/gram activity of surface sample equals 39.12 µCi.
Total volume in cubic feet and total activity in µCi were calculated for each sector of Area B. For sectors with activity, the highest activity detected per sector was used in the µCi calculation. Total contaminated area in Area B is Rev 0 8-1-91 MI0987-0066A-NL02
4173 ft 3 , total activity is 3071.9 µCi. Sector H-11. contains 73.5% of the total activity which comprises 14.5% of the total contaminated. area of Area B.
To quantify the dose to the population projections, 2992.6 µCi of Cs-137 and 79.3 µCi of Co-60 was entered into the LADTAP computer program. Assuming that the total 3071,9 µCi was eventually released to Lake Michigan thru the water table, and the uptake pathways which included fish, drinking, swimming, boating and shoreline the 50 mile population estimated at 1.05E6 would receive a total body dose of l,69E-2 manRem, or 1.61E-5 millirem per person. The maximum wholebody dose to an individual would be 5.13E-3 millirem and maximum organ.
Pl) dose (teenage liver) would be 8.67E-03 millirem, Direct dose to an individual working in the affected areas was calculated using the MICROSHIELD code. The activities from sectors H-11 and I-9 were used for a dose 18 inches above the surface. The dose rates from H-i'l and I-9 are 8.75E-06 R/hr and 1.02E-05 R/hr respectively (Attachment 1)~* Therefore, a 50 hour5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months occupancy in one week could result in a maximum exposure of 0.51 millirem.
Normal occupancy of this area is on an as needed bases and averages less than 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s/~eek per individual in contact with contaminated soil.
Rev 0 MI0987-0066A-NL02 8-1-91
, ....:......~
Table* 1 Soil Sample Core Results.(uCi/gram)
Sector
Surface 6" 12 11 18" 24 30" 36" 42" 4 8" E-11 2.07£-6 <HDA <HOA <HOA E-13 4.39£-6 <HOA <ttOA <HOA H-9 4.19£-6 <HDA* 4.79£-6 <HDA <MDA <MDA H-10 2.60£-6 <HDA <HDA H-11 3.75£-5 <HDA <HDA 8.45E-6 <MDA <HDA <MDA 1-9 1.24£-5 <HDA <HDA 1-10 <HDA <HDA 5.39E-6 <HDA <MDA <HDA <HDA <HllA J-9 5.39E-6 <HOA <HOA J-12 6.39E-6 <HDA <HOA L-9 * <HDA 6. 77E-6 <HOA <HDA T-90 <HDA <HDA 0 T-91 <HDA <HDA
~rJ-9 #1 <HDA <MDA <HDA <HDA <MDA <MDA <HDA *
l-9 12 <HL>A 1.40£-51': 5.BOE-6+ <HDA <HDA <MDA <MDA
'°N **~1-10 #]
':I -11 #4
<HL>A
<HDA
<HDA
<HDA
h~K-10 <HDA 0 *'<>'<>': I - l2 <HUA
>h'n~f-11 <HUA
+ Activity is all Co-60
Includes l.12E-5 µCi/gram of Co-60. All other activities listed were identified t.n as Cs-137.
Core samples under foundation of the South Radwaste Building.
>'d: Surface samples under asphalt in South Radwaste area
MIO<J8b-UOb2A-tlPOl *
Table 2 Activity Calculat:ions oer Sector Area B Sector t} Sq.ft:. x Depth = ft: l x g/ft 3 X uCi/ g = Total uC i.
E-11 375 0.5 187.5 48144 2.07E-6 18.7 E-13 375 0.5 187.5 48144 4.39E-6 39.6 H-9 625 1.5 937.5 48144 4.79E-6 216.2 H-10 625 0.5 312. 5 48144 2.60E-6 39.l H-11 625 2.0 1250.0* 48144 3.75E-5 2256.8*
I-9 527 0.5 263.5 48144 1. 24E-5 157. 3 I-10 275 1.5 412.5 48144 5.39E-6 107.0 J-9 450 0.5 225 48144 5.39E-6 58.4 J-12 200 0.5 100 48144 6.39E-6 30.8 L-9 150 1.0 150 48144 6.77E-6 48.9 I-9 east 98 1.5 147 48144 l.40E-5 99.l
.O 4325 4173 . 3071.9 N
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. *1250 = *2256.8 =
73.5% of
.~~¢ total activity Rev 0 MI0986-0062A-HP01 ,
8-1-91
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AUGUST 1987
~1GURE 2 SURFACE Q:GEND "NI
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EXAMPLE ONLY
FIGL~E 3 DEPTH AUGUST 1987 H
I RESULTS * *
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ASPHALT AREAS
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t.n (1.00 E-6 ,.Cl/UNIT Q SURFACE AftEA UNDER ASPHALT CORE SAMPLE UNDER FOUNDATION I,
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ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 MICROSHIELD CODE OUTPUT November 12, 1987 8 Pages TPN-HPOl-NLOl
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ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 FSAR SECTION 2.2 - SITE HYDROLOGY November 12, 1987 r..n
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'i 10 Pages Rev 0 TPN-HPOl-NLOl 8-1-91
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2. 2 HYDROLOGY The ?alisades Plant site is surrounded on the north, east and south siies by sand dunes. The west sid~ of the site is the Lake ~ich1gan shoreline.
As a result of this local topography, the site drainage is independent of the Brandywine Creek drainage basin '-lhich drains the hinterland. All. sur-face water tunoff drains directly to the lake and the percolating runoff also discharges to the lake (see Reference 3). There are no data available to verify the amount of surface runoff from the site; however, the flow from the Brandywine Creek drainage basin should be useful for the putpose of comparison.
Data obtained to establish base flow figures for Van Buren County streams indicate that the Brandywine Creek drainage basin is about 17 square miles (see Reference 4). 'The average annual rainfall for the area is 34 inches.
Duri_ng the period September 1962 to October 1963, th.e base flow measure-ments varied from a minimum of 0.90 cubic .feet per second (ft3/s) to a maximum of 11.4 ft 3 /s. This resulted in a mean annual 7-day minimum flow of 1.6 ft 3/s or 0.094 ft 3 /s/sq mi (cubic feet per second per square mile).
The period of stream measurements was representative of drought conditions.
The deposits of Brandywine Creek drainage basin are of low permeability which results in a nearly total runoff to Lake Michigan. This runoff prob-ably occurs soon after precipitation. Minor groundwater storage in the old beach and reworked older* sandy lake deposits observed on the surface to the
east of the site area probably maintain Brandywine Creek during periods of low rainfall. * -*
2. 2. 1 GROUNDWATER Almost all the water used in Van Buren County is obtained from wells.
rn Exceptions are the City of South Haven that obtains its municipal supply from Lake Michigan and some irrigation supplies that are obtained from streams, lakes and local ditches (see Reference 4).
The glacial drift is the only known source of fresh. groundwater in the county. All the glacial deposits are capable of yielding some water to wells, but the sand and gravel outwash deposits yield the largest quantities (see Reference 4).
The area of sand dunes along Lake Michigan is not generally favorable for obtaining large supplies of .groundwater. Probably most of the dune sand is above the water table and most wells must be drilled into the underlying ..
lake deposits (see Reference 4). *
1. *General Groundwater levels were established by the 1966 Geology and Groundwater Investigation conducted by Bechtel Company for Consumers Power Company (see Reference 3). The results of the investigation are sh.own on Figure 2.-9 *
.)
It is readily apparent that subsurface drainage is generally westward fsl281-129la-09-72 2.2-1 Rev 0 8-1-91
...... - '-:.:'.<=-**-
toward the lake (see Profile A-A). ~inor variations; ie, flew to~arj surface streams, may exist but are not considered significant.
An average hydraulic gradient toward the lake of about 13 feet per mi~e ~as obtained along Profile A-A as shown on Figure 2-9. This gradient repre-settts only the upper surface of unconfined groundwater. Water released ~n the surface would move toward the lake at an estimated rate of 650 feet ?er .
year (see Reference 3).
The nearest domestic wells to the site are located one-half mile to the east and south. The data indicates that groundwater in the vicinity of the eastern wells is flowing west toward the site. local groundwater in the*
area of the southern wells is also flowing west toward the lake, perpendic-ular to the shoreline.
There are no major sources of groundwater withdrawal, eg, large-scale industrial or agricultural pumping, that might reverse the direction of groundwater flow and cause ,ground~ater to flow from the Plant area towar.d'
.o any existing domestic wells. Without such pumping, it is difficult to envision a condition which would cause sufficient groundwater lowerirtg at any of the domestic: wells such that the direction of flow might be reversed. ,
2. Plant Site Groundwater levels in the vicinity of the site are shown on Figure 2-9.
The water table generally slopes toward the lake. During the site investi-gations, groundwater elevations averaged 580 feet MSL beneath the building site. This elevation corresponds to the approximate mean level of Lake Michigan. As.shown by water levels measured during.drilling, groundwater levels rise to the east to approximately 604 feet MSL beneath the switc:h-yard and 601 fee~ MSL near the eastern site boundary (see Reference 3).
Fiel.d permeability tests perf9rmed during the 1965 exploratory drilling yielded values ranging from 30 to 1,720 feet per year in the site area, Table 2-11. In Drill Hole 5, located approximately 500 feet northwest of the containment building, the permeability values ranged from 30.4 feet per year to 143 feet per year. In Drill" Hole 7, located approximately 650 feet south of the containment building, the permeability values ranged from 156 feet per year to 1,720 feet per year.
3. Groundwater Movement An unconf:Lned aquifer.is present in the dune area with groundwater levels controlled by the level of Lake Michigan. The rate of movement of ground-water downward into material underlying the dunes appears to be very slow.
Nine samples from Drill Hole 22 in the site area were tested for sodium ab-sorption ratio (SAR), Table 2-12. A high.SAR indicates poor downward per-colation of water due to sodium deposition on and between soil particles.
At the Plant site, the SAR is considered to be bigh between elevations 596 and 566 feet MSL and low between 566 and 555 feet MSL (see Reference 3).
fsl281-1291a-09-72 2.2-2 Rev 0 8-1-91
Groundwater levels and permeability data from the sandy ta~e ieposi:s underlying the dunes indicate a slow rate of discharge into ~a~e ~~=~~~a~
.'.o. Conclusions
a. *Groundwater in the unconfined aquifer moves westerly from the Brandywine Creek basin to Lake jichigan.
b. The hydraulic gradient is approximately 13 feet per mile and flow is essentially perpendicular to the shoreline.
c. Water discharged on the ground surface at the Plant site will percolate downward at a slow rate and mix with groundwater moving toward Lake Michigan.
d. Infiltration of surface water from the site to domestic wells offsite does not appear to be possible under present groundwater conditions.
2.2.2 GENERAL LAKE HYDROLOGY
1. La"ke Levels The level of Lake Michigan is cyclic and is expected to fluctuate with time and is dependent on long-term above-normal or below-normal amounts of pre- .
cipitation. The highest monthly mean stage of Lake Michigan was
583.68 feet MSL in 1886. Subsequent modifications in the St Clair River and the opening of the diversion out of the basin at Chicago have tended to reduce the maximum level attainable. During the recent period of record (1900 to present), the highest recorded monthly mean stage was 582.6 feet MSL in July 1974, and the lowest monthly mean stage was 576.91 feet ~SL in March and April 1964 (see Reference 5). Great Lakes levels are reported using International .Great Lakes Datum which is converted to MSL* at the Palisades site by adding 1.558 feet. The 1.558-foot correction factor is taken from the reference point at St Joseph, Michigan.
Short-time variations in lake levels (seiches), caused by meteorological factors and measured in hours rather than days, occur occasionally. The greatest level change of this type on record over a 105-year period in-volved a sudden.rise of 6 feet at Michigan City, Indiana (8:10 AM, June 26, 1954) and a rise of 8 feet at Montrose Harbor, Chicago (9:30 AM on the same date) (see Reference 6). These seiches were reported in the "Science" article by Ewing, Press and Donn (Vol 120, Page 684). On passing into tije shallow water at Michigan City, the wave was reflected and refracted to reach the Chicago shore of the lake. The US Lake Survey gauge at Holland, Michigan, which is 30 miles north of the Palisades site and has similar lake geometry to the site, indicated no surge on June 26, 1954.
As part of the Systematic Evaluation Program (SEP Topic II-3.B), the maxi-mum probable surge elevation, was reevaluated. The offshore surge value was reevaluated to produce an onshore surge height of 10.9 feet. The maximum monthly mean level was also reduced from 583.6 feet HSL to 582.6 feet MSL . *
)
fsl281-129la-09-72 2.2-3 Rev 0 8-1-91
. : This resulted in a probable* maximum flood protection level for t.:'.e
?al1sades Plant of 593.5 feet ~SL.
The service water pump motors at 594. 7 feet ~SL provide the basis fo::-
d=te~mining the minimum flood protection requirements for the ?~ant.
The~ef6re, the resultant wave surges from Lake ~ichigan do not present a problem at Palisades.
2. water ~ovements Conclusions from a study of lake hydrology in the Palisades* Park, ~ichigan area by Dr J L Hough (see Reference 6) indicate that surface currents gen-erated by wirid conditions and modified by the earth's rotation and lake
configuration will provide adequate mixing of Plant liquid effluents into the lake. The study included actual measurements of lake water movement in the area near the Plant site, and water mixing where the Black River enters Lake Michigan at South Haven.
A sUmmary of the*study is as follows:
Lake water is almost constantly moving past the Palisades -site, with an appreciable velocity of flow, under the influence of winds. It is es-timated, on the basis of wind records, that an alongshore current flows
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northward about 33% of the time and an alongshore current flows south-
. ward about 23% of the time. Offshore drift of surface water should occur about 38% of .the time, according to frequency of offshore winds, but these would have a minimal effect close to shore, which is bordered by a high dune ridge. It is likely, therefore, that the alongshore currents would tend to persist, once set up, while offshore winds were blowing. Thus, the frequency of alongshore current flow is probably greater than _the 33\ and 23% based on wind directions.
Under the procedure of taking water from a depth of about 20 feet, 3,500 feet offsho~e, raising its temperature as it is used for service water and dilution of cooling tower blowdown, and returning the ef flu-ent to the lake near shore, the effluent water will almost always be warmer than the lake water into which it is discharged. This is because- a single Lake Michigan water mass is involved during most of the year. When the effluent is warmer, it will tend to float at the surface, to drift with the surface current, and to be mixed by surface turbulence due to wave action .. On rare occasions, during the spring warming period when the upper layer of lake water is less than 20 feet deep, and during the summer when strong offshore winds cause a thinning of the normally deep surface mass to less than 20 feet, the intake
water coming from a colder layer may not be warmed in the Plant suf f ic-1ently to have a temperature higher than that of the surface lake water. At such times,. the effluent water will tend to sink to the thermocline and it will not be subject to vigorous turbulence caused by surface wave action. It will tend to mix more slowly.
Surveys of the performance of Black River water, entering Lake ~ichigan at South Haven under various weather conditions, have .indicated that fsl281-129la-09-72 2.2-4 Rev 0 8-1-91
the river water is diluted rap(dly, reaching a cancentrattan ~:
only 1% in the lake within a mile "of the ri~er mouth.
The discharge of the Black River was evaluated because the rate ~as !e:er-mined to be nearly the same as the disch,rge rate from the Palisades ?~3~:
with once-through cooling. Since the Plant is now operated with cJol1~g towers, the discharge to the lake has been reduced to approximat~ly 60,000 gpm or about 1/7 the original rate. The mixing and dilution factJrs are considered to be as great as during the higher discharge periods and the discharge concentrat~ons should be diluted a_t least 1,000 times by the time the discharge could reach the public water intake at South Haven, Michigan. *
3. Conclusions
a. The level of Lake Hichigan is cyclic; however, the recorded high of 1886 is unlikely to be exceeded. High lake levels are not expected to present a problem at tAe Plant site.
b. There is no recorded evidence of short-time variations in lake levels (seiches) along the eastern shore of Lake Michigan which would be expected to affect the Plant site.
c. Surface currents generated by wind conditions and modified by the earth's rotation.and lake configuration will proviCie adequate mixing of Plant liquid effluents into the lake.
fsl281*1291a*09*72 2.2-5 Rev 0 8-1-91*
TABLE 2-11 FIELD PER.'1IABILITY TESL' RESLTIS Drill Hole Elevation Flow "Q" Head H" Permeabil o:.;;~"K"
~umber of Test (GEm) (Feet) (ft/Yr) cm s}
J '
5 576 0.0029 12.3 30.4 0,3 x 10 ,
I 570 0.0101 12.3 106.0 l. L x 10 --+t 565 0.0088 12.3 92.0 0.89 x 10 560 0.0035 12.3 36.8 0.36 x -...
10 ,
t 555 0.0136 12.3 143.0 1. 4 x 10 - ...
550 0.0064 12.3 67.0 0.65 x 10- 4 545 0.0033 12.3 34.6 0.34 x 10- 4 4
Average 72. 8 0. 72 x 10-
~ 7 580 0.0303 25 156 1. 5 x 10-~ .
575 0.0477 25 246 2.4 x 10 :""'+4
,:0 570 0.0588 25 303 2.9 x 10- 4 565 0.0588 25 303 2.9 x 10-
":"J 4 560 0.0834 25 430 4.2 x 10- 4
,..... 550 0;3333 25 1, 720 16.7 x 10-4
%, ;4; 545 540 535
0. 0677 0.2500 0.2000 25 25 25 350 1,290 1 1 035 3.4 12.5
10. l l< 10-x 10-x 10-4 4
Average 648 6.3 l< 10- 4 tn ... -*
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fs1281-1291n-09-72 Rev 0 8-1-91
TABLE 2-12 ASALYSES OF SO IL SA.'1PI.ES Saturation Extract Values
~illiesuivalents Eer Liter Sample Sample ~o _l?.!!_ ECe Calcium ~agnesium Sodium SAR 2esc~:.ot:.:rn 1 8.2S 1. 2 0.5 Trace 11. 7 23.5 DH ....
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-.L 516 2 8.4 1. 4 0.5 Trace 13.0 26 DH 22 El *5 9 l 3 8.3 1. 3 0.5 Trace 12.3 24.5 DH 22 El 536 4 8 .45 1. 4 0.5 Trace 14.4 29 DH 22 El 531 5 8.5 1.5 a.5 a. 1 14.8 27 DH 22 El 576 6 8.3 1.5 a.s Trace 14.8 29.5 DH 22 El 571 7 8.5 1. 3 a.5 a.as 12.7 24 DH 22 El 566 8 8.2 a.5 3.a a.4 1. 1 1 DH 22 El 561 9 8.1 a.6 3.4 a.7 2.4 1.5 DH 22 El 555
. ECe ~ Millimhos per centimeter SAR =Sodium adsorption ratio on saturation extract
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fsl281-129lo-09*72 Rev o 8-1-91
LEGEND I Sii[ PROPCRlY BOUNUAHY' lXCLUSION AHfA
_-' 2 POWER BLOCK PLAN 3 CIRCULAllNG WAllR COOLING IOWERS
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.} PQWERINli MICHlliAN"S PRQliRESS General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 January 25, 1988 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR-20" - PALISADES PLANT -
SUPPLEMENT - REQUEST TO' RETAIN SOIL IN ACCORDANCE WITH 10CFR20.302 Consumers Power Company letter dated November 12, 1987, requested authori-zation to dispose of soil in place as specified by 10CFR20.302. The letter included the results of a survey and evaluation performed in August, 1987.
Following submittal of that letter, a cooling tower overflow on November 13, 1987 again flooded the South Radwaste Building. The flooding
caused additional activity that necessitated Consumers Power Company to request placing our November 12, 1987 request on hold until further evaluation and surveys could be completed. This letter includes the results of our evaluation and survey of the November 13, 1987 flooding incident and is intended to supplement our original November 12, 1987 request.
Following the cooling tower overflow, a survey indicated additional activity had been released from.the building. The building was being maintained in a non-contaminated condition to prevent this type of occurrence; however, during this period a destructive testing program on waste packages was being con-ducted in a small area of the building. The. survey clearly showed the release
-~* ... o~ activity from the building adjoining the testing area. The top six inches of soii from the sectors adjoining the building were removed and packaged (588 cubic feet) to prevent additional dispersion of radioactivity. The area was then completely resurveyed.
An evaluation of the August 1987 and November 1987 (post packaging) activities is attached. The survey indicates a drop of 49% in activities between the August and November surveys. *We propose the activities specified in the November 12, 1987 submittal be used as ju.stification for the request because they are conservative. In addition since the November 13, 1987 flooding and
following the most recent survey the area was subject to heavy rains which could have diluted some activities to below minimum detectable activity (MDA is nominally lE-06 µCi/g)
Rev 0 OC0188-0018-NL02 8-1-91
~\uclear Regulatory Commission Palisades ~uclear Plant
}
Retain Soil in Accord. with 10CFR20.302 January 25, 1988 The one non-conservative value from our August survey and evaluation is the maximum dose rate at 18 inches above the. surface. The Novembe*r survey value from NICROSHIELD is 1.17 mR/hr as opposed to 1.02 mR/hr. This small increase only slightly changes the radiation workers' conservative dose estima.te from 4.08 mR/year to 4.7 mR/year.
Following approval of this application, it is proposed to account for the most conservative values of activity, which was stated in the.November 12, 1987 submittal, as. an abnormal release in the semi-annual report. In* order to prevent recurrence of these releases to the environment, Consumers Power Company is also committing to transfer radwaste.activities from this area, except for high level vault use which is not a potential flooding release problem.
Relocation of these activities to a new radwaste facility is currently scheduled to be comple~ed in 1988 *
.., A check in the amount of $150.00 was attached to our November 12, 1987 submittal pursuant to 10CFR170.12(c).
Thomas C Berdine (Signed)
Thomas C Berdine Administrator, Nuclear Licensing
., . CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Attachment Rev 0 8-1-21 OC0188-0018-NL02
Attachment A Consumers Power Company
..., Palisades Nuclear Plant Docket 50-255 Evaluation and Survey Results Comparison Post November
Flood and Packaging Versus the November 12, 1987 Submittal
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MI0188-0001A-HP01 Rev 0 8-1-91
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'A' Cooling Tower - South Radwaste Flood In August of 1987, a resurvey was conducted of the soil at the South Radwaste Building and its adjacent areas. The resurvey was conducted to verify the location of ground contamination and if any contamination migrated further into the ground since the 1986 survey.
After submittal of the 1987 soil results and request to retain, in accordance with 10CFR20.302, 'A' Cooling Tower Basin overflowed again flooding the South Radwaste Building and outlying areas. Immediately following the occurrence, one liter sample was taken with no activity detected on the Multi-Channel Analyzer (MCA). Then, another complete survey was conducted which included at least two surface samples and core samples in every sector (Figures 1 and 2).
Surf ace sample results showed that activities have increased as well as new sectors contaminated. The most heavily affected sectors were I-10, I-11, J-9 and K-9 (Figure lA). To keep these areas from spreading, the top 6" of each of these sectors was removed and placed in 6 LSA boxes (approx. 588 cu.ft) and stored for disposition at a later date
After removal of soil, the sectors were resurveyed (Figure lB) and core samples were taken in each sector in 6-inch increments. Core samples were taken as far down as in the 1986 and August 1987 surveys, and in some instances even further in this survey. Results showed that no activity was detected below 6 inches as shown in Figure 2.
Table 1 and Table 2 sho~ comparisons between the August and November 1987 soil surveys. Table 1 compares the depths, the activities, the total cu.ft. and
..,.. total µCi per sector. After the removal of soil, the November 1987 soil survey results showed approximately a 49.3% drop in total contaminated soil (cu.ft.)
and a 51.1% drop in total µCi in comparison to the August 1987 survey results.
In Table 2 the comparison is between sectors affected in each survey and the depth at which each of these sectors were sampled. No activity was detected past 6.inches in the November 1987 soil survey, in comparison to that of 18 inches detected in August 1987.
Direct dose to an individual working in the affected areas was calculated using the MICROSHIELD code. The* activities from sectors H-9 and J~9 were used for a dose at 18" inches above the surface. The dose rates from H-9 and J-9 are
9.97E-6 R/hr and l.17E-5 R/hr, respectively. Therefore, a SO-hour occupancy in one week could result in a ma.Ximum exposure of .59 millirem. Normal occupancy of this area is on_ an "as needed basis" and averages less than 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s/week per
.individual in contact with the contaminated soil.
In reviewing the soil results between August and November 1987, the August 1987 soil survey remains more conservative based on the information shown on Tables 1 and 2. Therefore, the August 1987 soil survey is still valid in support of our request to retain the soil in accordance with 10CFR20.302.
Rev 0 B-1-91 M~Ol88-0001A-HP01
Table 1 Comparison Table Between Total Cu. Ft. and Total µCi August 1987 Sector II Sq.ft. x De12th ft 3 x q/ft 3 x µCi/q = Total µCi E-11 375 0.5 187.5 48144 2.07E-6 18.7 E-13 375 0.5 187.5 .48144 4.39E-6 39.6 H-9 625 1.5 937.5 48144 4.79E-6 216.2 H-10 625 0.5 312.5 48144 2.60E-6 39.1 H-11 625 2.0 1250* 48144 3.75E-5 2256*.8 I-9 527 0.5 263.5 48144 l.24E-5 157.3 I-10 275 1.5 412.5 48144 5.39E-6 107.0 J-9 450 0.5 225 48144 5.39E-6 58.4 J-12 200 0.5 100 48144 6.39E-6 30.8 L-9 150 1.0 150 48144 6. 77E-6 48.9 I-9 East 98 1.5 147 48144 l.40E-5 99.l 4325 4173 3071.9
=
-:- *1250 = *2256.8 =
73.5% of
~ total activity E-11 H-9 H-10 375 625 625 0.5 0.5 0.5 November 1987 187.5 312.5 312.5 48144 48144 48144 1.80E-6 4.35E-5 3.20E-6 16.25 654.46 48.14
~ H-11 625 0.5 312.5 48144 3.22E-5 484.45 H-12 250 0.5 125 48144 2.20E-6 13.24
~ I-9 527 0.5 263.5 48144 6.79E-6 86.14 I-12 220 0.5 110 48144 3.0E-6 15.89 J-9 450 0.5 225 48144 2.05E-5 222.06
t J-12 200 0.5 100 48144 2.60E-6 12.52 K-9 216 0.5 108 48144 3.39E-6 17.63
~ 2056.5 1570!78 i
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8-1-91.
MI0188-0001A-HP01
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Sector Surf ace 6" 12 11 18 11 24 11 30 11 36 11 42" J'l"N. E-11 2.07E-6 <HOA <HOA* <HOA
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-f;~o H-9 4.19E-6 4.35E-5
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H-11 3.75E-5 <MDA <MDA 8.45E-6 <MDA <MDA <MDA 3.22E-5 <MDA <MDA <MDA <MDA <MDA <MDA
'. H-12 *<MDA *NIA:
.**, 2.20E-6 N/A I-9 l.24E-5 <MDA <MDA
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~cl I-10 <MDA <MDA' 5.39E-6 <MDA <MDA <MDA <MDA <MDA
.. ~ <MDA <MDA* <MDA <MDA <MDA <MDA <MDA <MDA
.;:._... I-11 <MDA N/A'
~ <MDA <HDA <MDA <MDA
.>o. I-12 <MDA N/A
~~ ... 3.00E-6 N/A 1;, J-9 5.39E-6 <HDA <MDA
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2.05E-5 <MDA <MDA J-12 6.39E-6 <MDA <MDA 2.60E-6 N/A <HDA
-*t, K-9 <MDA N/A 3.39E-6 <MDA <MDA <MDA <MDA <MDA <MDA L-9 <MDA 6. 77E-6 <MDA <MDA (P!:U <MDA N/A <MDA <HDA I CD 1--'~
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EC~ETGv CO~TAMINATEO 1 '

3:38 SOIL ~ H-9 L0CAfION iS INCHES OEEPl 11: Rectangular solid source - slsb shields Distance to detector.,,., ................... . x 60.960 C"I
Source !.iJidth ..... , ... , . . . . . . . . . . . . . . . . . . :I **** w 762.
Source length ............... : ...... ~ ......... . L 762.
Rectangular solid, thickness toward dose pt~. Tl 15.240 Thickness of second shield .................. . T2 45. 720 Source Volul"le: 8.84901e+6 cubic centil"leters MATERIAL DENSITIES (g/ccl:
Material Source Shield 2 Air .001220 .001220 Alul"linuM Carbon 1. 70
- Concrete Hydrogen Iron .
. *\ Lead
' Lithiul"I Nickel Tin Ti taniui"I Tungsten
-0' Urania Uraniul"I Water 1.0 Zirconiul"l Rev 0 8-1-91
c ~ : =:
- -*-: -*_::\I~*"'! l ['j~: =.U
- \.-. """"'=

::. _*::. ::.~ J
.} -' ;_:::.!.~G th~ :haracter1sti.:s ::.t the !"'1a1:er1~.is in sh1eld INTEGRATION =AR~MEfERS:
1 *
~,iu~s-=r ~:.r l3.ter~l angle s~g:'V"!ents <Ntheta ) . . . . . 5
~J LO :vi b i:: r o f a::: l i'l u t ha l an g i e s e g i'l en t s ( Np s i ) . * . . . 5 NuMber of radial seg111ents (Nradius) .......... . s SOURCE NUCLIOES:
Ba-i37111: 3.8493e-04 curies RESULTS:
Group Energy" Activity Dose point flux Dose rate
( MeV) (photons/sec) MeV/(sq cM)/sec (Mr/hr) 1 .664 1 .282e+07 4.808e+00 9.969e-03
-- 2 3-4 5
6 7
8 g
10 11 12 13 .;-...;_
14 - -
15 -*-
16 17 19 1g 20 9.969e-03 TOTALS: 1 .2B2e+07 4.809e+00 Rev 0 B-1-91 I,
? **, ( - .~ ,\' .. *f
I '- * * ~ ~ I *
=====
Pun :at:: Jan*.Jary
~* r-' n ~ : :':"I e: ..l : .:: S ~
~ASE:
s, :SS8
.M
CONTAMINATED SOIL@ J-9 LOCATION :5 INCHES DEEP>
GEOMET~f I l: Rectangular solid source - slab shields Distance to detector ........................ . x 60.:360 Cfll, Source Lvidth ................................ . w 762.
Source leni;;ith ....*........*....... ;, ........ . L 548.640 Rectangular solid, thickness toward do~e pt *. Tl 15.240 Thickness of second shield .........**........ T2 45. 720 Source Volul"le: 6.37129e+6 cubic centil"leters MATERIAL DENSITIES Cg/cc):
Material Source Shield 2 Air .001220 .001220 Alul"linul"'I Carbon I. 70 Concrete
Hydrogen Iron .
Lead
.Lithiul"'I Nickel Tin Titaniu111 Tungsten Urania UraniuM Water I. 0 Zirconiul'I Rev 0 8-1-91
Lls1rg t~e 3UILOUP F~CTJR:
~haracterlst1cs INTEGR~fION t3sed ~n of ~ne TAYLOR ~ethod.
Materials in sh1e!j I .
PARAMETERS:
'Ju Mo er :, f l a t er ::d a n g i e ::. e g Me n t s <. N t h e t a l . . . . . S Ni...;:,oer ,Jf aziMuthal angle segMents \Npsi ). . . . . 5 NuMber of radial segMents (Nradius ).. .. .. .. .. . 5 SOURCE NUCLIOES:
Co-60: 8.9198e-05 curies RESULTS:
Group Energy Activity Dose point flux Dose rate
(MeV) (photons/sec) MeV/(sq cM)/sec (Mr/hr) 1 1. 336 3.300e+06 3.411e+00 6. 155e-03 2 1. 180 3.300e+06 2.958e+00 5.497e-03 3 .695 5.383e+02 2.889e-04 S.950e-07 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 19 20 TOTALS: 6.601e+06 6.370e+00 1 .165e-02 Rev 0 8-1-91
FIGUIJ 1A
.. *:~ ..
.-~
\
Li rl 00\
I
~ r*I ClJ I
~OJ
r1 0 0\
I
> rl
' QJ I P:< co L
DOTH UYR. AT YnlCtl NO N:nVrrt WA9 DnaCTID
,,--- (~*.,
LICENSING CORRESPONDENCE - RECORD S~.ARY
.. ~
DATE: January 25, 1988 DOCKET 50-255 LICENSE DPR PALISADES PLANT SUPPLEMENT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR20.302 SlTMMARY:
Provides a comparison of existing activity versus levels previously reported on November 12, 1987. Concludes that the November 12, "1987 activities were the most conservative and therefore the original request to retain soil in place in accordance with 10CFR20.302 remains valid.
COMMITMENTS MADE: (Identify Close-out Document)
1. Account for the activity as an abnormal liquid release included in the Semi-Annual Radiological Effluent Report.
2. Move radwaste activities to new facility in 1988.
COMMITMENTS CLOSED:
None (commit~ent #1 should be cross-referenced to duplicate in the November 12, 1987 letter).
Previous NRC/CP Co Correspondence Special Distribution NRC letters dated IEIN 86-90, 11/3/86 Bill Miller, Michigan Dept of Public CPC letters dated 2/28/86; 11/12/87 Health AIR No UFI No
..o** A-NL-88-02 950-42*40*50
., (FSAR Change) 950-24*34 Individuals Providing Information: Individuals Assigned Responsibility for Implementing Commitments:
TPNeal, PAL TPNeal - 1, 2/22/88 TPNeal - 2, 1/01/89 Concurrences: Individual Responsible for Obtaining Budget Approval:
TPNeal, PAL JLKuemin; P24-610 CSKozup, PAL N/A KWBerry, P24-416A Budget - N/A FSAR/FHSR Change (Identify):
NSB - N/A Yes/'J/,
Category ~
Originator: Individual Responsible for Initiating Change Request:
TCBordine (82977)
TPNeal, PAL FSAR 11.5.3 Effluent Monitoring &. Sampling Rev o IC0188-0018-NL02 8-1-91
.--*""""**~ r,.,,.,,. *,~-* * * .... 1**f*' *****- ***** * -.
0
"*! - .. , . , ,** * * * *~~_ ....... , .**
ODCM - APPENDIX B REFERENCE 2
Jw c~ a/~ cs--.&
. UNITED STATES NUCLEAR REGULATORY COMMISSION ~Cf.l)LD WASHINGTON, D. C. 20555 Harch 15, 1988 ~rnR , R ,988
NUCLl:Atl UctNSING Docket No. 50-255 Mr. Kenneth W. Berry Director, Nucl.ear Licensing Consumers Power Company 1945 West Parnall Road Jackson, Michigan 49201
Dear Mr. Berry:
SUBJECT:
PALISADES PLANT .- REQUEST TO RETAIN CONTAMINATED SOIL IN ACCORDANCE WITH 10 CFR 20.302 (TAC NO. 67408)
The subject request submitted by Consumers Power Company by letter dated November 12, 1987 and supplemented by information forwarded by letter dated January 25, 1988. contains detailed information evaluating the -radiation doses
., via the.liquid pathways for very low levels of contamination presently in areas of soil near the Palisades Plant South Radwaste-Building. Detailed evaluations are also presented of potential occupational doses from this contaminated soil.
'\
One additional dose pathway should, however, be evaluated to complete the analysis.of the impact viz., the inhalation pathway. In your submittals, you *.
' ~.
}
have presented diagrams showing areas in which contamination has been detected. It appears that for some of these areas 611 of soil has been removed, others are now covered by black top, and still others have not been disturbed. In order for the staff to complete the evaluation under 10 CFR 20.302, we ask that you submit a diagram indicating all contaminated soil
.,. surface areas included in this request, the condition of this soil surface, and an evaluation of the radiation doses via the inhalation pathway,
.., associated with these soil surfaces. The request in this letter affects fewer than ten respondents; therefore, OMB clearance is not required under PL 96-511.
Sincerely,
~r~
Thomas V. Wambach, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects
,)
Mr. Kenneth W. Berry
.} '.*
Consumers Power Company cc:
M. I. Mi 11 er , Es q u i re Isham, Lincoln & Beale Palisades Plant Nuclear Facilities and Slst Floor Environmental Monitoring Three First National Plaza Section Office Chicago, Illinois 60602 Division of Radiological Health Mr. Thomas A. McNish, Secretary P.O. Box 30035 Consumers Power Company Lansing, Michigan 48909 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Regional Administrator, *Re~ion III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
')
Jerry Sarno
- Township Supervisor Covert Township
r~.'
.ilr 36197 M-140 Highway Covert, Michigan 49043 Office of the Governor Room 1 - Capitol Building Lansing, Michigan 48913
, Mr. David P. Hoffman Plant General Manager Palisades Plant 27780 Blue Star Memorial Hwy.
Covert,. Michigan 49043 Resident Inspector c/o U.S. Nuclear Regulatory Commission Palisades Plant 27782 Blue Star Memorial Hwy.
Covert, Michigan 49043 Rev 0 8-'1-91
.... ., , *; "*..(_ *,*,*.* :*:. *:* ..**. -.,*: *--\~:. ,.,, * , .. *-*... ,.,. *. q; .... ", ,.,.,_ . ':\" )"~ *,*r,. ') -'-"" , :* .. ..,.. -,*,*
. ;___ ++
'\~
L UNITED STATES
.J.h*~ '*' l '-'. !O'°i NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 l~ - :j ..,
1**1r.1 T"l\l) ~' :1-i1.1r.;.
January 12, 1990 '
ri.:. , ***'"'*
Docket No. 50-255 Serial No. PAL 90-002
~r. Kenneth W. Berry Director, Nuclear Licensing Consumers Power Company 1945 West Parnall Road Jackson, Michigan 49201
Dear Mr. Berry:
SUBJECT:
PALISADES PLANT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH
.10* CFR 20.302 (TAC NO. 67408)
By letters dated November 12, 1987 and January 25, 1988, Consumers Power Company requested authorization under the provisions of 10 CFR 20.302* to dispose
contaminated soil in place. The NRC staff replied wit~a request for additional information which was forwarded to you on March 15, 1988. *
By letter dated June 27, 1988, Consumers Power Company provided addition~l ~ ~
information in response to our request. However, in that response, CPCo expanded the original request to include the entire South Radwaste area as a contingency against future spread of contamination and to obviate the need for additional requests under 10 CFR 20.302. For the staff .to complete its review of this request, additional specific information is required. This is because NRC approval under 10 CFR 20.302 is for the disposal of specifically identified and characterized slightly ccntaminated*material by the applicant.
We request that you provide a revised submittal describing the licensed material for disposal and the analysis and evaluation called for under 10 CFR 20.302.
The attached request for additional information provides additional detail for the content of the revised submittal.
The reporting and/or recordkeeping requirements.cf this letter affect fewer than ten respondents; therefore, OMB clearance under PL 96-511 is not required.
Sincerely,
~1W~- ..
Albert W. De Ag:~~~::ject Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V &Special Projects Office of Nuclear Reactor Regulation .
cc: See next page Rev 0 -
8-1-91
./
Mr. Kenneth W. Berry Consumers Power Company cc:
(
Palisades Plant M. I. Miller, Esquire Sidley &Austin Nuclear Facilities and 54th Floor Environmental Monitoring One First National Plaza Section Office Chicago, Illinois 60603 Division of Radiological Health Mr. Thomas A. McNish, Secretary P.O. Box 30035 Consumers Power Company Lansing, Michigan 48909 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Regional Administrator, Region III U.S. Nuclear Regulatory C0111111ssion 799 Roosevelt Road Glen Ellyn, Illinois 60137 Jerry Sarno Township Supervisor Covert Township 36197 M-140 Highway Covert, Michigan 49043 Office of the Governor Room 1 - Capitol Building Lansing, Michigan 48913 Mr. Gerald B. Slade Plant General Manager Palisades Plant 27780 Blue Star Memorial Hwy.
Covert, Michigan 49043 Resident Inspector c/o U.S. Nuclear Regulatory Conm1ss1on Pa 11 sades Pl ant 27782 Blue Star Memorial Hwy.
Covert, Michigan 49043 Rev 0 8-1-91
E:'ICLOSUqE SECOND REQUEST FOR ADDITIONAL INFORMATION (RA!)
ON THE CONSUMERS POWER COMPANY PALISADES PLANT REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10 CFR 20.302 The subject request submitted by Consumers Power Company (licensee) by lette.r dated November 12, 1987 and supplemented by information forwarded by letter dated January 25, 1988 contained detailed information evaluating the radiation doses via the liquid pathways for very low levels of contamination presently in areas of soil near the Palisades Plant South Radwaste auilding. Detailed evaluations were also presented of potential occupational doses from this contaminated soil.
.. r.
-** , ** 1
.*:** :)
Three significant questions arose during the staff evaluation of this request:
1. The inhalation pathway for doses from the contaminated soil was'not addressed.
2. The proposals contain no delineation of the specific contaminated areas covered by the disposal req~est.
3. The licensee's Tech11ical Specifications for ~adiological environmental
-1 monitoring require an LLD of 2 x 10 µCi/gm for 137 Cs determinations in sediment - yet all of the measurements reported in the request were made with equipment 5 to 10 times less sensitive for these gamma radiations.
Rev 0 8-1-91
By letter dated June 27, 1988 the licensee submitted additional information in response to the staff's RAI of March 15, 1988. This submittal was unacceptable
in that it addressed potentially contaminated areas .and hypothetical maximum contamination parameters. rather than measured licensed material to be disposed of under the regulations.
It is requested that the licensee submit a complete, revised 20.302 request incorporating the dose evaluation information of the measured contamination considered in the November 12, 1987 and January*25, 1988 submissionsand updated if appropriate with dose evaluations of the inhalation pathway based on the same measured contamination. As pa~t of the proposal the licensee should record exactly what areas of measured contamination are covered by the request for which disposal under 10 CFR 20.302 is proposed.
_)
I Rev 0 2 8-1-91
ODCM - APPENDIX B REFERENCE 3 General Offices:
c~nsumars Power POWERiNii MICHlliAN"S PROliRESS 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 June 27, 1988 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
SUPPLEMENT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR20.302
., Consumers Power Company correspondence dated November 12, 1987 and January 25, 1988 requested authorization to dispose contaminated soil inplace as specified T
by 10 CFR 20.302. The area, known as the South Radwaste Area, has been contaminated by numerous cooling tower overflows and redistributed by heavy rain showers. Although the majority of the radioactive material has been packaged for waste shipment, a large volume of very low ac_tivity radioactive material remains. This volume of material would be very expensive to ship as waste. The NRC, by letter of March 15, 1988 to Consumers Power Company, requested additional inhalation dose information .and clarification of the contaminated area.
A generic inhalation dose evaluation is described in Attachment A. Conserva-tive assumptions have been made to get the maximum organ dose possible from inhalation of contaminated soil. The inhalation doses are not significant.
Consumers Power Company requests to expand this 10 CFR 20.302 request to include the entire South Radwaste Area. Periodic cooling tower overflows and occasional heavy rains have caused redistribution of radioactive material to areas which were below Lower Limits of Detec.tion (LLD) during previous evalua-tions. Expanding the area would *eliminate the need for a new 10 CFR 20.302 submittal if radioactive material is redistributed within the South Radwaste Area. The South Radwaste Area is completely fenced and located directly South of the Plant South Security fence. Area fence is shown in dark outline on Figure 1.
As described in our January 25, 1988, letter we intend to transfer the radwaste activities which caused the contamination of soil from the South Radwaste Area, except for the high level vault use which is not a potential flooding release problem.
Rev 0 8-1-91 OC0688-0049-NL02
uclear Regulatory Commission Palisades Nuclear Plant Retain Soil in Accordance w/10CFR20.302
. *f. June 27, 1988 Consumers Power Company requests approval to dispose of.inplace low level radioactive materials which meet the following conditions without further 10 CFR 20.302 submittals.
1. Material contained in the fenced area described as.South Radwaste Area.
2. Direct dose to a radiation worker would not exceed SE-02 mRem/hour from contaminated soil.
3. Average gross beta/gamma concentration not* to exceed SE-05 µCi/gm so inhalation doses to a radiation worker or at the site boundary would not exceed the values contained in Attachment 1.
4. Additional radioactive material releases shall be identified in liquid Semi-Annua Effluents Reports as an 'Abnormal Releas.e'
Sampling, analyses and Semiannual Effluent Report inclusions of 'Abnormal Release' will be performed only when further flooding of the area occurs.
James L Kuemin (Signed)
James L Kuemin Staff Licensing Engineer CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Rev 0 OC0688-0049-NL02 8-1-91
Attachment 1 The inhalation doses have *been calculated on a generic worst case basis. A generic basis has been selected to compensate for the elevated Lower Limit of Detection (LLD) in analysis and also to address movement of radioactivity
within the South Radwaste Area. The assumptions made are the worst case Dose Conversion Factor (DCF) used (see Table 3), a total average activity concentra~
tion of 5E-05 µCi/gram and the entire area (500 m2 ) used instead of the indi-cated contaminated area (117 m2 ) .
Increasing the area is self-explanatory. The total average activity concentra-tion is being used :il'istead of actual to account for dose important isotopes which may be present near the analysis LLD of lE-06 µCi/gm, but not detected.
The worst case DCF is used to demonstrate a maximum organ dose. A variation in.
isotope mixes could shift the maximum dose to a different organ but could not exceed the dose indicated.
Radworker and site boundary inhalation dose calculations are attached *
~
Rev 0 OC0688-0049-NL02 8-1-91
Inhalation Dose From Contaminated Soil -
Adult Radiation Worker Table 1 DW = Cs
f 18 DCF. . 1 Where: CS = concentration of waste: S.OE04 pCi/Kg.
Ef = occupancy factor: 2080 worker hours f 8760 hrs/yr = 0.237 areal mass available for resuspension (top 1 cm of soil): 16 Kg/m 2
£ = resuspension factor: 8.SE-9/m 14 f = adult annual inhalation rate: 7300 m3 (RG 1.109) 15 DCF = 7.46E-04 mRem/(50 yr
pCi): adult lung (RG 1.109) 1
. \
/
Substituting:
DW = 8.78E-03 mRem/50 yr: maximum organ dose
\
I l
j l
l 1*
Reference:
AIF/NESP-035 Evaluation of the Potential for De-Regulated*Disposal
.\ of Very Low Level Wastes From Nuclear Power Plants I , I Rev 0 OC0688-0049-NL02 8-1-91
..":.:: *; ::*~~ __ ._ . . :-:* ... **~ *: */*. :***~ ~~. ~~:~ *.i;*:~*,\f:'.~.x.~~*~; ~~\~:~-:~~._~: ~~:~. .- .: :.~ . . .~~1~\"j~:.~~~ .~{'..~°'-[_~~~;;*~~-~~:.?~ ~~t*~*::_;"';~: :-1~~- :-: ~'\Y ~.!~* :;__t ~ ~::.~ ;;._,: ~*; ;* ~{*:; ;~~ ~,~;::'.: ~: **1 ?;..i~.-. y' ~:;* \~~ .5_.,\"._:*~ ~-~:.: 1,'.*~_SJ :.~~-~:! ::~ ~.:,~-~~*{~~:r~:~~~~~~~r,.h~~-~:~~:;~;,~:::.~~
1* *::..
Inhalation Dose At Site Boundary -
Infant Most Limiting Table 2 X/Q µ A *. DCF.
l.
Where: Terms are identified in Table 1 and F
16
= 2045 ms: infant annual breathing rate (RG 1.109)
X/Q = L 4 E-6 sec/ms: actual 5 year site average
µ = 3.8 m/sec average *wind speed: actual 1986 1 A = 500 m2 : contaminated area
,., DCFi = 3.22E-03 mR/(50 yr pCi): infant lung (RG 1.109)
T Substituting
\
..*J DSB = l.19E-04 mRem/50 yr: maximum organ dose Rev 0 OC0688-0049-NL02 8-1-91
-~s~~~~~~~;~:.~&~~~1~;~~~,~'-~:?~<~ti1'~l*~:'~"Stµ.~\.:.~~!~~F~..;:.,~:~:::~1~ ~*VlV*(:y;~~:~:;.~:-~~-~*i_*.-.~~~ ~: .::.~ *~i~ ~: " ' ~::~**\: :.1~<~~.-. :, .-, . . :*:, .~,.~... *r~ :- ~ **~ . ::*:: *; i'_ ::. . *: , ....~. ~ ~., r,* "*1 :. ~.: ::*1;: :1*.1 *:* .*:: *,* .~Y ......... *: *..*.-.~
Table 3 Dose Conversion Factors for Inhalation: Committed dose (mRem) over 50 years per pCi inhaled, per Regulatory Guide 1.109~
Onsite - Radiation Worker Bone Liver Kidney Lung GI Cs-134 4.66E-05 l.06E-04 3.59E-05 1. 22E-05 l.30E-06 Cs-137 5.98E-05 7.76E-05 2.78E-05 9.40E-06 1.0SE-06 Ba-140+D 4.88E-06 6.13E-09 2.09E-09 1.59E-04 2.73E-05 Sr-90* l.24E-02 0.0 0.0 l.20E-03 9.02E-05 Co-60** o.o l.44E-06 o.o 7.46E-04 3.56E-05
Sr-90 is a factor of SE-03 lower than Cs-137 based upon 10 CFR 61 sampling analysis and cannot be limiting. Cs-137 was present in. all samples where
.., activity was identified.
'T ** Given the concentration restriction on Sr-90 noted above, Co-60 lung dose is most limiting.
l
. J Off site - Infant Most Limiting for Inhalation
.... Cs-134 2.83E-04 5.02E-04 1.36E-04 5.69E-05 9.53E-07 Cs-137 3.92E-04 4.37E-04 1.23E-04 S.09E-05 9.53E-07 Ba-140 4.00E-05 4.00E-08 9.59E-09 1.14E-03 2.74E-05 Sr-90* 2.92E-02 o.o 0.0 8.03E-03 9.36E-05 Co-60** o.o 5.73E-06 0.0 3.22E-03 2.28E-5
Sr-90 is a factor of SE-03 lower than Cs-137 based upon 10 CFR 61 sampling analysis and cannot be limiting. Cs-137 was present in all samples where activity was identified.
Given the concentration restriction on Sr-90 noted above, Co-60 lung dose is most limiting.
OC0688-0049-NL02 8-1-91*
I
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LICENSING CORRESPONDENCE - RECORD
SUMMARY
DATE: June 27, 1988 DOCKET 50-255 LICENSE DPR PALISADES PLANT SUPPLEMENT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR20.302.
SUMMARY
Request approval to dispose of inplace low level materials in south radwaste area in accordance with proposed conditions.
COMMITMENTS MADE: (Identify Ciose-out Document)
(See attached page)
COMMITMENTS CLOSED:
Revise previous submittals to account for inhalation dose and further containment from flooding.
Previous NRC/CP Co Correspondence Special Distribution Nl.C letters dated 3/15/88 Bill Miller, Mich Dept of Public Health CPC letters dated 1/25/88, 11/12/87 AIR No UFI No 950-42*40*50 950-24*34 Individuals Providing Information: Individuals Assigned Responsibility for Implementing Commitments:
TPNeal, PAL TPNeal - Revise FSAR to reflect the 4 conditions.
Concurrences: Individual Responsible for Obtaining Budget Approval:
KWBerry, P24-614A TCBordine, P24-608 N/A RAEnglish, P26-400 Budget - FSAR/FHSR Change (Identify):
NSB -
WLBeckman, PAL tia/No Category I TPNeal, PAL ---
Originator: Individual Responsible for Initiating i
l Change Request:
.) \ TPNeal/JLKuemin (85867) j / TPNeal 8-1-91.
IC0688-0049-NL02
Commitments Made
In the event of another flood over the south radwaste area meet the following conditiais:
1.
2.
I Material contained in the fenced area described as South Radwaste Area.
Direct dose to a radiation worker would not exceed SE-02 mRem/hour from contaminated soil.
3. Average gross beta/gamma concentration not to exceed SE-05 µCi/gm so inhalation doses to a radiation worker or at the site boundary would not exceed the values contained in Attachment 1.
4. Additional radioactive material releases shall be identified in liquid Semi-annual Effluents Reports as an 'Abnormal Release'.
~*
Rev 0 8-1-91 IC0688-0049-NL02
ODCM - APPENDIX B REFERENCE 4 Cjnsumers Power GB Slade General Afanager POWERING MICHlliA_N"S PROGRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043
August 31, 1990 Nuclear Regulatory Commission Document Control Desk Washington, D C 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT SUPPLEMENT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR 20.302 Consumers Power Company correspondence dated November 12, 1987 and January 25, 1988 requested authorization to dispose of contaminated soil in place as specified by _lOCFR 20.302. The area known as the South Radwaste Area has been contaminated by numerous cooling tower overflows and contamination was redistributed by heavy rain showers. Although the majority of the radioactive material has been packed for waste shipment, a large volume of very low activity radioactive material remains. This volume of material would be very expensive to ship as waste. The NRC, by* letter of March 15, 1988 to Consumers Power Company, requested additional inhalation dose information and
clarification of the contaminated area.
After discussions with the NRC reviewer, a supplement was submitted on June 27, 1988 which was based on generic approval. It proposed that further submittals would not be required if flooding moved activity from an identified to an unidentified sector. Subsequently, on January 12, 1990, the NRC Staff requested additional information. The information request required the licensee to submit a revised proposal incorporating the dose evaluation information of the measured contamination considered in the November 12, 1987 and January 25, 1988.submittals and updated, if appropriate, with dose evaluations of the inhalation pathway based on the same measured contamination. As part of the proposal, the licensee was asked to record exactly what areas of measured contamination are covered by the request for which disposal under 10CFR 20.302 is proposed.
The attached material supplies the requested information. The specific area contaminated is noted as Area B on the attached survey grid map. The entire area is fenced and is about 12,000 sq ft of soil exposed with the remainder buildings and asphalt. The inhalation pathway is for breathing suspended soil from this area. Table 2 addresses a radworker in Area B, and Table 3.
addresses an infant on the site boundary. The radworker could receive 8.03E-04 mRem/50-year maximum organ (liver) dose and the infant could receive 3.16E-05 mRem/50-year maximum organ (liver) dose, both of which are insignif-icant.
Rev.
8-1-91.
OC0890-0074A-NL03 A CMS ENER5Y COMPANY
.1*<, ;,
When the flooding problem was d.iscovered and planning for. a formal survey was done, the erivironmental sediment LLD was not considered, as this was a nuclear plant site. We attempted to get the bes~ LLD we could using our equipment and the number of samples we were *going to have to run. With the hundreds of samples run, we felt lE-06 uCi/gm was adequate. To be conservative, we expanded the August and November 1987 surveys to use l.OE-06 uci/gm Cs-137 in any sector which showed LLD. This will increase the radioactivity to 5,006 uCi from 4,643 uCi, an increase of 8%. The activities are on Table 1 and lA.
If this submittal is approved, we will add the released activity to the Liquid Semi-annual Effluent Report as an abnormal release, and the approval to retain the soil in place will be documented in the FSAR.
In summation, Consumers Power Company requests approval to dispose of in place the low-level radioactive materials which are contaminated soil contained in the fenced area described as South Radwaste Area (Area B). Direct dose to a radiation worker would not exceed l.7E-02*mRem/hour from this contaminated soil. Inhalation doses to a radiation worker or at the site boundary would not exceed 8.03E-04 mRem/50-year. Tables 1 and lA ra4ioactive material release shall be identified in liquid Semi-annual Effluent Reports as an
'abnormal release'. The disposal in place would be documented in the FSAR.
The radwaste activities which caused the contamination of the soil have been completely relocated to a new east radwaste area. The South Building has been deconned and is being used for non-radwaste activities. Some fixed
~~i) *contamination is present in floor cracks and vaults. This has been documented for plant decommissioning. No further contamination will be added to the south area from the South Radwaste Building.
Gerald B Slade (Signed)*
Gerald B Slade General Manager pc: Administrator, Region III, USNRC NRC Resident Inspector, Palisades Hev 0 8-1-91 OC0890-0074A-NL03 r *
,~,..~!~'~}~fi~'l~ *~~~~'l *:* J~!\'~~~*J\\~1'~1!~~~~~-~ 'i~~~f'\~;~q~~-ry.\\:~~t\r~i~~~;-J.~7~~~~~,~'t;::;;::.~ ;~?'l:~;s.:~ f~*~,~(!~~;::.:~.~t. ';!*~; ~~r: :_~-:, '.! ;\ *_, **J _..~: *:.r.~ ~:. ~-.:.~ .:*:;*~'.'~~~~<-~* .: ,~.:::- ~~*~r~~~ ~ ~ ~"*~*.:-. :_~'. .;.**--:~
Attachment A Consumers Pow~r Company Palisades Nuclear Plant Docket 50-255 Tables l and lA, Survey Results Microshield Direct Dose Calculation
. 'j Table 2 - Radworker Inhalation Dose Table 3 - Site Boundary Inhalation Dose Figure l - Survey Grid Figure 2 - Survey Results
.)
Rev.
8-1-91 M10890-0074A-HP01
Table lA November 1987 Survey ft J x g_/ ft J x [:!Cilg = Total uGi Sector {~ S9.ft. x De Eth = 3
.125 0.5 62.5 48144 lE-06 B-9 48144 lE-06 15 C-9 625 0.5 312.5 250 48144 lE-06 12 C-10 500 0.5 250 48144 lE-06 12 D-9 500 0.5 312.5 48144 lE-06 15 D-10 625 0.5 275 48144 lE-06 13 D-11 550 0.5 3 7. 5 48144 lE-06 2 D-12 75 0.5 62.5 48144 lE-06 3 E-10 125 0.5 187.5 48144 l.8E-06 16 E-11 375 0.5 312.5 48144 l.E-06 15 E-12 625 0.5 13 0.5 275 48144 lE-06 E-13 550 7 0.5 150 48144 lE-06 F-12 300 15 0.5 312.5 48144 lE-06 F-13 625 6 750 0.5 125 48144 lE-06 G-12 48144 lE-06 15 G-13 625 0.5 312.5 312.5 48144 4.4E-OS 662 H-9 625 0.5 48 0 .5 312.5 48144 3.2E-06
. H-10 625 462
' ~ ~
0.5 300 48144 3.2E-05
~'.; H-11 600 48144 2.2E-06 13 H-12 250 0.5 125 48144 l.OE-06 15 H-13 625 o.s 312.5 6.8E-06 86 527 0.5 263.5 48144 I-9 l.OE-06 7 I-10 275 o.s 137. 5 48144 l.OE-06 6 250 0.5 125 48144
[-11 3.0E-06 16 220 0 .5 . 110 48144 I-12 48144 2. lE-05* 227.
J-9 450 0.5 225 48144.. 2.6E-06 13 J-12 200 o.s 100 3.4E-06 18 216 0.5 108 48144 K-9 48144 l.OE-06 4 L-9 150 o.s 75 48144. l.OE-06 4 L-10 150 0 .5- 75 48144 l.OE-06 4 150 0 .5 .. - .......... 75 L-11 L-12 150 o.s 75 48~44 l.OE-06
- 4 3 Maximum 4 .4E-05 1751 Subtotals 11,938 ft 2 5 ,969 ft Average 6.lE-06 l
1 i
I l
l le**. .
} '} Re-v 0 8-l-91 MI0890-0074A-HP01
Table l August 1987 Survey Et i x g/ft 3 x ~c i I g = Total uci.
Sector IF S9.fc. x De Eth =
2.07E-6 18.7 375 0.5 187.5 48144 E-11 48144 4.39E-6 39.6 E-13 37 5 0.5 187.5 937.5 48144 4.79E-6 216.2 H-9 625 1.5 312.5 48144 2.60E-6 39.1 H-10 625 0.5 1250* 48144 3.75E-5 2256.8 H-11 625 2.0 263.5 48144 l.24E-5 157.3 1-9 527 0.5 412.5 48144 5.39E-6 107.0 I-10 27 5 1.5 225 48144 5.39E-6 58.4 J-9 450 0.5 100 48144 6.39E-6 30.8 J-12 200 0.5 48.9 1.0 150 48144 6. 77E-6 L-9 150 l.40E-5 99.l 98 i.5 147 48144 I-9 East 3071. 9 Subtotal:; 4325 4173 3807 48144 1.0E-06 183 Remainder 7613 0.5 Section
\1 Ii
,()
(, : . (3 l*
i 3,255.
j J TOTAL 11,938 i
I i
Rev.
8-1-91 MI0890-0074A-HP01
.:l -
~ -
- .- :i . - .,.
3urLSGP =~C~~~: :a5ea =~ r~YL~R ~e~~=c.
~5~rig ~r.e :~aracter:5~::5 =~* ~r.e ~ater:di5 1~ ~~:elj 1
'.J ,_ ~ c er :i r : a t er !I l a rig .l e s ~ g I"' en t 5 ~ 'H '"e ~ a 1 .. * * *
-"'-'"'t::er ~* 3Z::""utr.al ar;le 5egl'lent5 !.~~osi l .... .
\~~cer oi ~!lj1al 5egl'lents :Nrad1us I,, ........ . -
S1JlJRCE NUCUOES:
Sa- I 37,.,: .3. 8493e-~4 curl es Actual fi.51E-04 Ci (4.4E-05 uCi/gm)
RESlJLTS:
Gr~up £nergy ~ct1v1ty Oo!e i:io1nt flux Do!e r-ate i \MeVl <o~otor5/9ecl MeVl<!ICI C1"1)/5ec < ,.,,..; r-ir l
.. )'
l 1 t
.664 t .282e+~7 4.. 808e..,00 9. '36 3ei-03 2
i 3*
4 l
i s
l 1t 7
8 g
ia 12 13 14 15
., is i 17 l
18 l 19 l'
.j 21 TOTALS: I. 292e+07 4.808e+00 I' S.969e-03
...?,
. J l
" 6. 51 Ci l . Ratio of 3,85 Ci = 1.69 x 9.969E-03 = l.7E-02 !:l.H/hr j
1 j
sI, Rev 0 8-1-91
I l .,
..* 30IL1 .MSH Run date:. January 18, 1388 Run tl;oi1e:.4:17 ;::i.1"1.
CASE: CONTAMINATED SOIL~ H-9 LOCATION <6 INCHES OE~?l GEOMETRY 11: Rectangular 5ol1d source - slab shields Distance to detector .... , ......*.*......... ,, X 60.960 C*i"'I, Source width ................................. W 76-Z.
Source 1enQth *.*..*..*...*....**.. *..... *...*.. L 762.
Rectangular solid, thickness toward dose pt ** Tl 15.240
45. 720 "
Thickness of second shield **...*............. T2 Source VoluMe: 8.84901e+S cubic centiMeters MATERIAL DENSITIES (g/ccl:
Material Source' Shield 2 Air .001220 .001220 A luMinul'I Carbon 1. 70 Concrete Hydrogen Iron Lead.
Lithiul'I Nickel Tin Ti taniul'I TunQsten Urania Urani.ul'I Water f.0 ZirconiuM Re\l.
8-l 1
Table 3 Inhalation Dose At Site Boundary -
Infant ~ost Limiting DsB = Cs f18 f16 X/Q µ A Where: Terms are identified in Table 1 and F16 = 2045 mJ - infant *annual breathing rate (RG 1.109)
X/Q = 1.4 E-6 sec/m 3 - actual 5 year site average
µ = 3.8 m/sec average wind speed - actual 1986 A - 1110 m2 - contaminated area DCFi - 4.37E-04 mR/50 yr
pCi - Cs-137 infant liver (RG 1.109) lStituting:
i I
)
Dss = 3.16E-05 mRem/50 yr - maximum organ dose l
.J.
Rev 0 8-1-91
MI0890-0074A-HP01
Table 2 lnhalacion Dose From Contaminated Soil -
Adult Radiation Worker f 14 f15 DCFi Dw ;:: cs f18 Wher-e: Cg = concentr-ation ot waste - 4.4E04 pCi/Kg Cs-1.37 (actual max concentr-ation)
Ef = occupancy factor- - 2080 worker hours ~ 8760 hrs/yr = 0.237
£18 = ~*real/mass available for resuspension (top l cm of soii) - 16 Kg/m 2 f14 = r-esuspension factor- - ~.5E-9/m 3
£15 =adult annual inhalation rate - 7300 m (RC 1.109)
DCFi = 7.76E-05 mRem/50 yr
pCi - Cs-137 adult liver (RC 1.109) i; *;*,';r__'), * * '
\
~* ~ubst1tut1ng:
~~*::;.)
Dw = 8.03E-04 mRem/50 yr - maximum organ dose l
l 1
I
~ference: AIF/NESP~035 Evaluation of the Potential for De-regulated Disposal of Very Low Level Wastes From Nuclear Power Plants Rev.
8-1-91 MI0890-0074A-HP01
.. * ... J"'
'~ .... :-. .. .\
s FIGURE 1 SURVEY J\rea I3 GRID LEGEND
~ ASPHALT AREAS D 2 5' x 25' SECTORS
[2J Con Lam i n.*1 l.r-rl "REA *a*
0 ~REA ~*
rl 00\
I
> rl QJ I p-~ co
'**.* ----------,~**- _,, .... ------*
IGUff\ ~B ..*
URFACE.
0 0
........* IUfFAa ACTIVITY OF SECTOft ASPHALT AREAS
-EXAMPLE : ONLY
.-1 0 °'I
? r-1 QJ I
~ cO
Commitments ~ade In the event of another flood over the south radwaste area, meet the following conditions:
1.
2.
3.
~aterial contained in the fenced area described as South Radwaste Area.
Direct dose to a radiation worker would not exceed SE-02 mRem/hour from contaminated soil.
Average gross beta/gamma concentration not to exceed SE-05 uCi/gm so inhalatiori doses to a radiation worker or at the site boundary would not exceed the values contained in Attachment 1.
4. Additional radioactive material releases shall be identified in liquid semi-annual effluent report.s as an 'abnormal release'.
"i
-l
.,I j
l l
J l
Rev Q.
'*. 8-1-91 OC0890-0074A-NL03
LICENSING CORRESPONDENCE - RECORD Sl~~L~Y DATE: August 31, 1990 DOCKET 50-255 LICENSE DPR PALISADES PLANT Request for additional information - retain soil in accordance with 10CFR
20.302 (TAC 467408)
SUMMARY
Request approval to dispose of inplace low-level contamined soil as specified by 10CFR 20.302 COMMITMENTS MADE: (Identify Close-out Document) RESIDENT COMMITMENT Yes/No See Attached Commitment Sheet COMMITMENTS CLOSED:
Provide requested information.
Previous NRC/CP Co Correspondence Resident Commitment Information
NRC letters dated 3/15/88, 1/12/90 Air No. -
CPC letters dated 11/12/87, 1/25/88, Resident Document 6/27/88 Responsible Individual -
Due Date -
AIR No UFI No 90-15 950-42*40*50 Individuals Providing Information: Individuals Assigned Responsibility for Implementing Commitments:
TPNeal TPNeal Concurrences: Individual Responsible for Obtaining Budget Approval:
TPNeal, PAL JLKuemin N/A .
RWSmedley:
KMIIaas , PAL Budget - FSAR/FHSR Change (Identify):
NSSD -
Yes/'A(J Category fl 4 Special Distribution Originator: Individual Responsible for Initiating
Change Request:
TPNeal/HFCooper TPNeal; upon NRC approval OC0890-0074A-NL03 Rev 0 3-1-91
ODCM - APPENDIX B REFERENCE 6 consumers Power GB Sl*d*
G*nual Manag~r POWERiNii MICHIGAN'S PROGRESS PallsaCles ~uclear Plant: 27780 Blue Star Memorial Highway. Coven. Ml 49043 April - ....
I'* 1991 Nuclear Regulatory Commission*
Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT USE OF SOUTH STORAGE BUILDING AS AN INTERIM RADIOACTIVE WASTE STORAGE BUILDING On November 10, 1990, radioactive waste generators in the State of Michigan were banned from the three currently active burial sites. As a result of thi~
ban action must be taken to ensure that Palisades maintains the capability to store radioactive waste until such time as we are again able to gain access to the burial sites. We believe our actions are consistent with NRC guidance received in Generic letter 90-09. Therefore, the South Storage Building will
.i l
j" be utilized as an interim storage facility for low level radioactive waste (LLW}.
The South Storage Building (then referred to as the South Radwaste Building}
had been previously used for all processing and storing of radioactive waste produced at Palisades from 1976 to 1989. During that period several cooling
! tower overflows occurred which resulted in flooding this building and lt, spreading contamination from the processing area to the surrounding soil.
This spread in contamination resulted in NRC Open Items (85019-01 and 89025-
01) which required implementation* of actions to prevent future flooding. In 1988 it was decided to relocate the radwaste processing functions performed in i the South Radwaste Building to a new addition at the East Rad~aste Building to l
prevent the spread of contamination in the event of future cooling tower
! overflows. All radwaste processing equipment was relocated to the East i Radwaste Building and the South Radwaste Building was decontaminated. The
.(
1 I
South Radwaste Building (then re-named the* South Storage Building) has since
l been used for non-radiological m.aterial storage. * . .
i lI As a result of increases in radioactive waste, the-South Storage Building is now needed to store low level radioactive waste (LLW). This LLW, in the form 1 of dry active waste (DAW) will be packaged in metal boxes and labelled, ready for future shipment to burial sites. The DAW metal shipping boxes will be j stored off the floor to prevent water damage. The metal shipping boxes are I strong, tight containers designed to prevent any leakage of radioactive material during transportation. Incidental water contact will not result* in
.J j . the spread of contamination. Radioactive waste will not be processed in the Rev O A GffS' ENERGY COMPANY 8-1-91
The following samples were obtained from sectors H-9 and J-9 on October 23, 1990.
Sample Location uCi/gm H9-l 3.92E-6 H9-2 3.70E-6 H9-3 1.26E~6 I
H9-4 <MDA lI H9-5 <MDA i J9-l 1.90E-6 l J9-2 <MDA I I ;I J9-3 J9-4 J9-5
<MDA 2.28E-6 5.86E-6 *
'~
~
Sector H-9 was the highest reading in 1988 at 4.4E-05 uCi/gm and J-9, 2.lE-05. Both areas are now showing a factor of 10 drop in activity. Sector ~-11 could not be resampled because of equipment stored in this location. The data indicates direct dose would be less than 2E-03 mR/hr. Occupa~cy in this area should not exceed 2 I
hours/week or 100 weeks/year, which is less than 1 mR/year. Sample and analysis by MAWillers and GStama, review by TPNeal.
Rev 0 8-1-91
' rl
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1 ~ 1H:H* *_: * ' *_ ~ M *_' r r ' '. '..~~*-~*~- ~rrr::'~~r:~=: .. ,;,r.r.;,;,=**1..,1,. , 1.,.;.,.1.rn-.r-. m.111----~
. ~ .; :,.:*,
South Radwaste Building and the building will be maintained as a* normally clean (radiologically) area.
The current Palisades Radwaste Storage Plan requires low dose-rate DAW boxes to be placed adjacent to the walls of the South Radwaste Building to limit dose rates outside the building. All DAW boxes and the storage building will be inspected quarterly in accordance with Palisades Health Physics Procedure
HP 6.27. This procedure incorporates the storage and inventory guidelines contained in NRC Information Notice No. 90-09, "Extended Interim Storage of Low Level Radioactive Waste by Fuel Cycle and Material Licensee".
The same radiological and security controls currently in force at the East Radwaste Building will apply at the South Radwaste Bu\lding. The South Radwaste Building is surrounded by a locked fence and all building access doors will normally be locked, with keys controlled by Radiation Safety Department. All access to the building will be controlled through the Radiation Safety Office and the Palisades RWP/Dosimetry System. Building status sheets will be updated on a monthly ba~is or whenever radiological conditions change. Any areas outside the building reaching Smr/hr or greater shall be posted in accordance with current HP Procedures.
Since the South Radwaste Buil.ding will be used for the storage of low level radioactive waste and not for radioactive waste processing, it is believed that the public health and safety will not be adversely affected.
It is Palisades' intent to continue to use the South Radwaste Buildin~ to store low level radioactive waste (LLW) until. such time when radwaste generators in Michigan are again allowed to ship radioactive waste to the burial sites *. Upon resumption of shipping to the burial sites the South Radwaste Building will be emptied, surveyed and returned to the plant for non-radiological material storage.
~J./~--~--
Gerald B Slade General Manager CC Administrator, Region III, USNRC Resident Inspector, Palisades Rev 0 8-1-91
Mr. Gerald B. Slade Consumers Power Company Palisades Plant
cc:
M. I. Miller, Esquire Sidley & Austin. Nuclear Facilities and Environmental Monitoring 54th Floor One First National Plaza Section Office Chicago, Illinois 60603 Division of Radiological Health Mr. Thomas A. McNish, Secretary P.O. Box 30035 Consumers Power Company Lansing, Michigan. 48909 212 West Michigan Avenue Jackson, Michigan 49201 Gerald Charnoff, P.C.
Shaw, Pittman, Potts &
Trowbridge Judd L. Bacon, Esquire 2300 N. Street, N.W.
Consumers Power Company Washington, D.C. 20037 212 West.Michigan Avenue Jackson, Michigan 49201 Mr. David L. Brannen Vice President Regional Administrator, Region III Palisades Generating Company U.S. Nuclear Regulatory Co1T111ission c/o Bechtel Power Corporation 799 Roosevelt Road 15740 Shady Grove Road Glen Ellyn, Illinois 60137 Gaithersburg, Maryland 20877
J Jerry Sarno Township Supervisor Covert Township 36197 M-140 Highway Roy W. Jones Manager, Strategic Program Development Westinghouse Electric Corporation Covert, Michigan 49043 4350 Northern Pike Monroeville, Pennsylvania 15146 Office of the Governor Room 1 - Capitol Building Lansing, Michigan 48913 Mr. Patrick M. Donnelly Director, Safety and Licensing Palisades Plant 27780 Blue Star Memorial Hwy.
Covert, Michigan 49043 Resident Inspector c/o U.S. Nuclear Regulatory Conmission i
Palisades Plant i 27782 Blue Star Memorial Hwy.
1 i
Covert, Michigan 49043 l
l I
l*'t'.') Rev 0 8-1-91
ODCM - APPEJ:ID.LA .J::S REFERENCE 7 UNITED STATES NUCLEAR REGULATORY COM TPNeal, Pal WASHINGTON. D.C. 20565 June 7, 1991 Docke~ No. 50-255
Mr. Gerald B. Slade Plant General Manager Palisades Plant Consumers Power Company 27780 Blue Star Memorial Highway Covert,*Michigan 49043
Dear Mr. Slade:
SUBJECT:
REQUEST UNDER 10 CFR 20.302 TO RETAIN CONTAMINATED SOIL ONSITE AT PALISADES PLANT (TAC NO. 67408)
By letters dated November 12, 1987, and January 25, 1988, (Reference 1 of the enclosed Safety Evaluation (SE)), Consumers Power Company submitted a request pursuant to 10 CFR 20.302(a) for the disposal of contaminated soil onsite at the Palisades Plant. We have completed our review of the request and find your procedures (with conmitments as documented in Reference l) to be acceptable.
Thts. aPP.rovll>\,~Qr~~. . .~t. *,of U. MM Safety:>*
~::~ttt.l~~~~~i~ .;uiure *3'<rc~>*-* brit:'artfttti;.i=:Jis shall be reported to.the NRC in accordance with the applicable ODCM change protocol. We further find that the radiological environme~tal impact of the proposed action meets the staff criteria as reflected in Reference 6 of the encl~sed Safety Evaluation.
Sincerely, Brian Holian, Project Manager Project Directorate III-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
As stated Rev o 8-1-91
The specific area contaminated is noted as Area Bon the survey grid map (se~
Figure 2). The total ~ctivity of this area (5.1 mCi) is based on 6,000 cubic feet of soil contaminated with the spoils from the South Radwaste Building.
Table 1 lists the principal nuclides identified in the contaminated soil. The activity in thi.s table is based on measurements in 1987; see data from a recent submittal (Reference 5) shows that activity concentrations in the contaminated area have decreased by approximately 10 percent. The radionuclide half~lives, wh.ich are dominated by 30-year Cs-137, met:t the staff's 10 CFR 20.302 guidelines (Reference 6, which applies to.~adionuclides with half-lives less than 35 years).
Table 1 Average Nuclide Concentration (pCi/g) Total Activity (mCi)
Co-6a a.as a.a79 Cs-137 3a . 5.a Total 5.o79 RADIOLOGICAL IMPACTS The licensee has evaluated the following potential exposure pathways to members of the general public from the radionuclides in the contaminated soil: (1) external exposure caused by direct radiation from radionuclides in the soil; and (2) internal exposure from inhalation of resuspended radionucl1des. The staff has reviewed the licensee's calculational methods and assumptions and finds that they are consistent with NRC Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, Qctober 1977.
The staff finds the assessment methodology acceptable. The dose assessments are based on the following:
1. 5.1 mCi of contaminated soil distributed over 12,aoo square foot planar source having a thickness of 0.5 feet (6000 cubic feet source volume).
2. Direct radiation exposure of 2000 ~ours per year.
3. Inhalation exposure based on 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months per year is minimized due to six-inch layer of gravel (which inhibits wind erosion.)
4. Groundwater not considered because there are no domestic wells in the area down~gradient from the plant.
i\
! Doses calculated from these pathways are shown in Table 2. The total dose of ll 0.85 mrem per year h wUhin the staff's gu;deline of 1 mrem per year (Reference 6). .
I , *, "*
1** /i Rev 0 8-l-9l
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION RELATED* TO THE PALISADES NUCLEAR PLANT RETENTION OF CONTAMINATED SOIL ONSITE INTRODUCTION In reference (1), Consumers Power Company (CPCo) requested approval pursuant to Section 20.302 of Title 10 of the Code of Federal Regulations (CFR) for the disposal of licensed material not previously considered by the NRC in the Palisades Final Environmental Statement (FES), dated June 1972. The petition submitted contains a detailed description of the licensed material (i.e.,
contaminated soil) subject to this 10 CFR 20.302 request. The 6,000 cubic feet of onsite contaminated soil contains a total radionuclide inventory of 5.1 met, based on radioactive material that was deposited in the soil due to the flooding of the South Radwaste Building. The contaminated area is located inside the security fences, and is on company controlled land; This area (South Radwaste Area) is fenced in, within the plant's south security fences. Thus it is inaccessible to the public (see Figures 1 and 2).
In the submittals (References 1-5), the licensee addressed specific information .
requested in accordance with 10 CFR 20.302(a), provided a detailed description.
of the licensed material, thoroughly analyzed and evaluated the environmental
effects relative to retention of the contaminated soil onsite, and co11111itted
.' to follow specific procedures to minimize the risk of unex*pected exposures
Although the environmental impact of-.the proposed action is well within the dose
.1 criteria contained in the Conmission's Below Regulatory Concern (BRC) Policy Statement, dated Jul,l~~~ 1990, the licensee has not requested, and the staff has not considered, the ac.t.ions described:- herein. to be exempt from NRC regulation.
,..... ~
CPCo plans to dispose of the 6,000 cUbic feet of contaminated soil onsite pursuant to 10 CFR 20.302. The area, known as thd South Radwaste Area, has been contaminated by several cooling tower overflows (three times in an eight-year period), and has subsequently been redistributed by heavy rain showers.
The cooling tower overflows were caused by instrument failures that opened the cooling tower bypass valve during* normal operation. This valve is now electri-cally isolated.during cooling tower operation. The licensee conducted a soil survey because the South Radwaste Building was in the main path of the water overflows from the cooling tower~- - Survey results indicated that radioactive material was deposited ;n the soil. Although the majority of the radioactive material has been packaged as .radwaste and will be subsequently shipped offsite
(16 boxes each having a volume of 98 cubic feet, containing ssi of the estimated activity), a large volume of low level contaminated soil is contained in the fenced are~ described as the South Radwaste Area.
Rev 0 8-1-91
Table 2 Whole Body Dose Received by Maximally Exposed Individual Pathway (mrem/year)
Groundshine 0.85 .
Inhalation 0.00081 Groundwater Ingestion 0.0 TOTAL 0.85 The above doses are a small fraction of the 300 mrem received annually by members of the general public in the United States and Canada from sources of natural background radiation (Reference 7).
Based on our review of the proposed disposal of contaminated soil onsite, we conclude that:
(1) The radioactive material will be disposed in a manner such that it is unlikely that the material will be recycled; (2) Doses to the total whole body and any body organ of a maximally exposed individual (a member of the general public or a non-occupationally exposed member) from the probable pathways of exposure to the disposed material will be less than 1 mrem per year; (3) Doses to the total whole body and any body organ of an inadvertent intruder from the probable pathways*of exposure will be less than 5 mrem per year since the burial location is on company-controlled land; (4) The radiation exposures to the nuclear station workers are small compared to the routine occupational exposures at the Palisades Plant; (5) The possible radiation risks to members of the general public as a result of such disposal are well below regulatory limits and small in comparison to the doses* they receive each year from natural background radiation.
The licensee's procedures and .conmitments as documented in the submittal are acceptable, provided that they are permanently incorporated into the licensee
{)ffsite Dose Calculation Manua_l (ODCM) as an Appendix, and that future
modifications be reported to NRC in accordance with the applicable ODCM change protocol.
Rev 0 8""'.'l-91
REFERENCES (1) CPC0 1 s letters, T. C. Berdine to NRC Document Control Desk, November 12, 1987 and January 25, igaa.
(2) Memorandum from L. J. Cunningham, DREP to T. R. Quay, T. V. Wambach, 11 Request for Additional Information (RAI) , March 15, 1988, April 7, 11 1989, and January 12, 1990.
(3) CPCo's supplement to Reference (l),* J. L. Kuemin to NRC Document Control Desk, June 27, 1988.
(4) CPCo's supplement to References (1, 2), G. B. Slade to NRC Document Control Desk, August 31, 1990.
( 5) CPCo's letter, T. P. Neal to B. Holian, October 13, 1990.
( 6) E. F. Branagan, Jr. and F. J. Congel, "Disposal of Slightly-contaminated Radioactive Wastes from Nuclear Power Plants," presented at CONF-860203, Health Physics Considerations Decontamination Decornnissioning, Knoxville, TN, February, 1986.
(7) National Council on Radiation Protection and Measurements, "Exposure of the Population in the United States and Canada from Natural Background Radiation," NCRP Report No. 94, Bethesda, MD. December 30,
.~
1987.
Principal Contributor: J. L. Minns
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Rev 0 8-1-91
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ML18064A675

Text

SUMMARY

Purpose:

Background

=====

=====

Dear Mr. Berry:

SUBJECT:

Dear Mr. Berry:

SUBJECT:

Reference:

SUMMARY

SUMMARY

SUMMARY

Dear Mr. Slade:

SUBJECT:

Enclosure:

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