Text

Semiannual Radioactive Effluent Release & Waste Disposal Rept,Jul-Dec 1986
	ML18052A877
Person / Time
Site:	Palisades
Issue date:	12/31/1986
From:	Johnson B; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 8703040145
	Download: ML18052A877 (46)
	v • d • e

.*

ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT JULY THROUGH DECEMBER 1986 February 27, 1987 07030400 10ia ~~6~~~55 PDR A

PDR R

44 Pages IC0287-0064-NL04

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J PALI~ADES NUCLEAR PLANT SEMIANNDAL EFFLUENT RELEASE REPORT July - December 1986 This report provides information relating to radioactive effluent releases and solid radioactive waste disposal operations of the Palisades Plant during the period of July through December 1986 in the format contained in Plant Tech-nical Specification 6.9.3.la.

The July - December 1986 semiannual effluent release report reflects effluent Technical Specifit~tion changes effective January 1, 1985.

Due to the extended maintenance outage since May 19, 1986, both the third and fourth quarter gaseous effluent releases reflect only residual activity levels.

1.

SUPPLEMENTAL INFORMATION A.

BATCH RELEASES Information relating to batch releases of liquid and gaseous effluent is provided in Table HP 10.5-1.

B.

ABNORMAL RELEASES None.

2.

GASEOUS EFFLUENTS Table HP 10.5-2 lists and summarizes all gaseous radioactive effluents released during the reporting period.

The unidentified beta was 9.67E-03%..

3.

LIQUID EFFLUENTS Table HP 10.5-3 lists and summarizes all liquid radioactive effluents released during the reporting period.

The unidentified beta was l.02E-02% of the total release.

4.

SOLID WASTE Solid radwaste classification, sources, volume shipped, curie and nuclide content are detailed in Table HP 10.5-4.

All radwaste shipments were made to either Barnwell, South Carolina or Richland, Washington for burial.

5.

SUMMARY

OF RADIOLOGICAL IMPACT ON MAN Potential doses to individuals and populations were calculated using GASPAR and LADTAP computer program codes.

The third and fourth quarter values for curies released were input for each nuclide and summarized as follows:

IC0287-0096A-HP01

A.

The ~aximum offsite air dose at the site boundary due to noble gas~ was 2.37E-06 millirad beta and 2.98E-07 millirad gamma for the third quarter; and 0.00 millirads beta and gamma for the fourth quarter.

B.

The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluents (tritium, particulate, and iodine) was the child GI tract.

Doses were 6.02E-04 and S.28E-04 millirem for the third and fourth quarters, respectively.

C.

The maximum total body dose to individuals in unrestricted water-related exposure pathways was 8.42E-03 millirems for the third quarter and 4.43E-03 millirem for the fourth quarter.

The maximum organ dose was (teenager liver) 1.32E-02 and 7.62E-03 millirem for the third and fourth quarters, respectively.

D.

Integrated total body doses to the general population and average doses to individuals within the population from liquid effluent releases within a distance *of SO miles from the site boundary were:

2.83E-02 manRem and 2.70E-OS millirem for the third quarter; and

1. 4SE-02 manRem and 1. 38E-05 millirem for the fourth quarter.

E.

Integrated total body doses to the general population and average doses to individuals within the population from gaseous effluent releases within a distance of SO miles from the site boundary were:

2.87E-03 manRem and 2.73E-06 millirem for the third quarter; and 2.72E-03 manRem and 2.59E-06 millirem for the fourth quarter.

F.

The SE-75 DBQ fractions in gaseous releases were not significant in either wholebody or organ doses.

There was no entrained noble gas in any liquid releases during the third or fourth quarters.

6.

PROCESS CONTROL PROGRAM (PCP) 2 Four changes were made to the PCP to answer the comments in the NRC submittal (12/30/86) - Safety Evaluation of the revised ODCM and PCP.

Changes in the text are indicated with a line in the right margin.

Radwaste system diagrams were added as Appendix B.

A complete Revision 2 of the PCP is being submitted per the requirements of Technical Specification 6.19.2.

7.

OFFSITE DOSE CALCULATION MANUAL (ODCM)

A new section B.1.5 was added to address methodology for calculating effluents from Steam Generator Blowdown Vent and Atmospheric Dump Valve steam releases.

This addresses the comment from NRC submittal (12/30/86)

- Safety Evaluation of the revised ODCM and PCP.

The Land Use Census results (table 1.4, page 33), Critical Receptor locations (table 1.4a, page 33.a) and Design Basis-Quantity-DBQ (table 1.9, pages 47, 48) *are submitted per the requirements of Technical Specification 6.18.2.

The submittal IC0287-0096A-HP01

{ncludes ~over page, table of contents (pages i, ii), pages 16 through 24 and abov~: addressed tables.

8.

CORRECTION OF JANUARY - JUNE 1986 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Table HP 10.5-3; Liquid Effluents - swnmation of all releases, item G, 2nd quarter:

Maximum Dose Commitment - Wholebody should be corrected to 5;10E-03 mRem instead of 5.08E-03 mRem.

The percent of Tech Spec limit is also changed from 3.39E-01% to 3.40E-01%.

A corrected copy of Table HP 10.5-3 (with indicated changes) is being submitted.

Reason for the error was the mis-transfer of data from the draft work sheets to the finished re~ort.

IC0287-0096A-HP01 3

A.

B.

c.

D..

IE.

F.

G.

H.

TABLE HP 10.5-3 PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES-JANUARY 1986 to JUNE 1986 FISSION AND ACTIVATION GASES UNITS 1st QUARTER

1.

Total release (not including.

tritium, gases, alpha)

Ci 1.llE-01

2.

Average diluted concentration during period uCi/ml 4.33E-09

3.

Percent of MPC 7.18E-02 TRITIUM

1.

Total release Ci 1.91E+Ol

2.

Average diluted concentration during period uCi/ml 7.43E-07

3.

Percent of MPC 2.48£-02 DISSOLVED AND ENTRAINED GASES I

L Total Release Ci None

2.

Average diluted concentration during period uCi/ml None

3.

Percent of MPC None GROSS ALPHA Radioacti vi ty;'d*

Total Release)

Ci 3.74£-06 VOLUME OF WASTE RELEASED (Prior to Dilution)

Liters 1.16£+06 VOLUME OF DILUTION WATER USED DURING PERIOD Liters 2.57E+10 MAXIMUM DOSE COMMITMENT - WHOLE BODY mRem 1.08£-02 Percent of TS 13.1.4.la limit 7.20£-01 MAXIMUM DOSE COMMITMENT - ORGAN mRem 2.07£-02 Percent of TS 13.1~4.la limit 4.14E-Ol 2nd QUARTER 7.98E-03

.2.56E-10 9.12E-04

1. 48E+Ol 4.75£-07 1.58£-02 4.87£-05 1.56£-12 7.80£-07 4.02E-06 5.02E+05

3. 12E+10 I S.lOE-03 3.40E-01 8.43£-03

' 1. 69E-Ol

,1;-;'; Calculated from vendor analysis of monthly radwaste composite samples.

IC0287-0096A-HP01

\\

.'..l Est Total !

Error 7.74 i

i 4.05 I

11. 9

! A.

GASEOUS Number of Releases Total Release Time Maximum Release Time Average Release Time Minimum Release Time B.

LIQUID Number of Releases I

I Total Release Time

! i Maximum Release Time I

i Average Release Time I Minimum Release Time T.ABLE HP 10. 5-1 PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES JULY 1986 to DECEMBER l986 Units 3rd Quarter 4th Quarter 14 4-'*

Minutes 2.85E+03

7. 61E+02 Minutes 4.92E+02 2.23E+02 Minutes 2.04E+02

1. 90E+02 Minutes 4.0E+Ol l.43E+02 Units 1st Quarter 2nd Quarter 42 23 Minutes 4.06E+03 2.64E+03 Minutes

5. 78E+02 5.80E+02 Minutes 9.66E+Ol l.15E+02 Minutes 3.SE+Ol 3.2E+Ol

4th Quarter releases did not contain radioactive material.

The waste gas decay tanks were pressurized for maintenance activities.

IC0287-0096A-HPOi 5

A.

I B.

c.

D.

E.

F.

TABLE HP 10.5-2 PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES JULY 1986 to DECEMBER 1986 FISSION AND ACTIVATION GASES UNITS 3rd QUARTER

1.

Total release Ci

4. 85E-02.

2.

Average release rate for.period uCi/sec

6. lOE-03

3.

Percent of annual avg MPC 2.71E-06 IODINES

1.

Total Iodine Ci 5.73E-06

2.

Average release rate for period uCi/sec 7.21£-07

3.

Percent of annual avg MPC 1.03£-06 PARTICULATES

1.

Particulates with half-life >

8 days Ci 4.56£-05

2.

Average release rate for period uCi/sec 5.73£-06

3.

Percent of annual avg limit MPC 2.19£-06

4.

Gross alpha radioactivity Ci 5.45£-06 TRITIUM

1.

Total release Ci 7.59£-01

2.

Average release rate for pe.riod uCi/sec 9.55£-02

3.

Percent of annual avg MPC 6.82E-05

1.

Beta air dose at site boundary due to Noble Gases (TS 3.24.5.2a) mRads 2.37£-06

2.

Percent limit 2.37E-05

3.

Gamma air dose at site boundary due to Noble Gases (TS 3.24.5.21) mRads 2.98£-07

4.

Percent limit 5.96E-06

1.

Maximum organ dose to public based based on critical receptors (TS 3.24.5.3) mRem 6.02E-04

2.

Percent of limit 8.03E-03

Note:

Data is reported for I-131 (no I-133 present)

IC0287-0096A-HP01 4th QUARTER None None None None None None

3. 08£-05 '

3.87£-06 4.78E-06

3. 54£-06 6.65E-Ol 8.36£-02 5.97£-05 None None None None 5.28E-04 7.04E-03 0

Est Total Error 12.4

16. p';

13.8 I

1.

FISSION GASES Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-13lm Xenon-133 Xenon-135 Xenon-135m Xenon-138 I

Argon-41

)

Total for Period

2.

IODINES Iodine-131 Iodine-132 Iodine 133 Iodine-135 Total for Period IC0287-0096A-HP01 TABLE HP 10.5-2 PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS JULY 1986 to DECEMBER 1986 Units 3rd QUARTER Ci l.72E-02 Ci None Ci None Ci None Ci l.35E-02 Ci l.78E-02 Ci None Ci None I

Ci None I

Ci I

None Ci 4.85E-02 I

Ci 5.73E-06 Ci None Ci None Ci None Ci S.73E-06 4th QUARTER None None None Non.e None None None None None None None None None None None None 7

I I

i I :

I I

3.

PARTICULATES-:'*

Chromium-51 Manganese-5.4 Cobalt-58 Cobalt-60 Zinc-65 Silver-llOm C'esium-134 Cesium-137 Barium-140 Mercury-203 Selenium-75 Strontium-89~il'*

Strontium-90'l'd*

I Net unidentified beta Total TABLE HP 10.5-2 PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS JULY 1986 to DECEMBER 1986

Units 3rd QUARTER Ci None Ci None Ci None

'Ci 7.02E-08 Ci None Ci None Ci None Ci.

None Ci None Ci

None Ci 3.58E-OS Ci

i. OSE-06

Ci 2.66E-06 Ci

.None Ci.

4.56E-OS

Particulates with half-lives >8 days.

'l'ni-*Calculated from vendor analysis of monthly stack gas filters.

8 4th QUARTER

None None None 7.69E-06 None None None None None -

None 1.34E-05 2.89E-06 2.13E-06 4.70E-6 I

3.08E-OS I

NOTE:

Reported net beta and vendor analyzed St-89/90 results were input to GASPAR code as Sr-90 to yield conservative dose estimates.

IC0287-0096A-HP01 I

I !

i I

I I

' ' i i !

I I

I

A.

B.

c.

TABLE HP 10.5-3 PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES JULY 1986 to DECEMBER 1986 FISSION AND ACTIVATION GASES UNITS 3rd QUARTER

1.

Total release {not including tritiwn, gases, alpha)

Ci 1.4SE-02

2.

Average diluted concentration during period uCi/ml 6.66E-10

3.

Percent of MPC 3.89E-02 TRITIUM

1.

Total release Ci 2.09E+Ol

2.

Average diluted concentration during period uCi/ml 9.SBE-07

3.

Percent of MPC 3.19E,..02 DISSOLVED AND ENTRAINED GASES

1.

Total Release Ci

None

2.

Average diluted concentration duri*ng period uCi/ml None

3.

Percent of MPC None

D.

GROSS ALPHA RADIOACTIVITY (Total Release) *'d:

Ci

4.0SE-06 F.

VOLUME OF WASTE RELEASED (Prior to Dilution)

VOLUME OF DILUTION WATER USED DURING PERIOD G. -MAXIMUM DOSE COMMITMENT - WHOLEBODY Percent of TS 3.24.4.la limit Liters I 8. 49E+OS I Liters

2. 18E+l0 mRem 8.42E-03 S.6iE-Ol 4th QUARTER 6.SOE-03 3.22E-10

1. lOE-02 8.39E+OO

4. lSE-07 l.38E-02 None None None 3.4SE-06 S.SSE+04

2. 02E+10 4.43E-03 2.9SE-Ol H.

MAXIMUM DOSE COMMITMENT - ORGAN mRem

1. 32E-02 I

7. 62E-03 Percent of TS 3.24.4.la limit 2.64E-Ol l.52E-Ol

,..,., Calculated from vendor analysis of monthly radwaste composite samples.

IC0287-0096A-HP01 9

Est Total I

i Error I

I 10.4 9.56 N/A

.l'

1.

NUCLIDES RELEASED Cesium-137 Cobalt-58 Manganese-54 Cobalt-60 Cesium-134 Niobium-95 Strontium-89;b';

Strontium-90;'d*

Net Unidentified Beta Fission & Activation Product Total (Above)

Xenon-133 I

Tritium I I Grand Total TABLE HP 10.5-3 PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS J1JLY 1986 to December 1986 Units 3rd QUARTER Ci 3.03E-03

. Ci 3.49E-03 Ci 7.81E-04 Ci

4. 13E-03 Ci 6.69E-04 Ci 2.74E-06 Ci 8.75E-06 Ci

1. 97E-OS Ci 2.40E-03 Ci l.4SE-02 Ci None Ci 2.09E+Ol Ci 2.09E+Ol I

h';

Calculated from vendor analysis of monthly radwaste composite samples.

4th QUARTER

1. 82E-03

6. 77E-04 3.52E-04 2.72E-03 2.87E-04 None 4.61E-05 l.90E-OS 5.76E-04 6.SOE-03 None 8.39E+OO 8.40E+OO NOTE:

Reported net beta and vendor analyzed Sr-89/90 results were input to LADTAP code as Sr-90 to yield conservative dose estimates.

IC0287-0096A-HP01 10 I !

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Waste Class A

A c

TABLE HP 10.5-4 PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Source of Solidification Waste Agent DAW N/A F-54 Filters N/A Resins N/A SOLID RADIOACTIVE WASTE JULY 1986 to DECEMBER 1986 Container Type B-25 Box-LSA HIC HIC-14-195H Volume (Cu.ft.)

2156.0 56.0.

193.0 Total Shipped 2405.0 Total Curies 2.28

10. 9 175.8 189.0 11

~*~Principal Radionuclides H3 1Mn-54,Fe-55,Co-57, Co-58,Co-60,Ni-63 Cs-134,Cs-137 Co-57,Co-58,Co-60, Cs-137,H3,Cr-51, Mn-54,Nb-95,Ni-63 Mn-54,Co-58,Co-60, Co-57,Cs-134,Cs-137, Ni-63,Tc-99,H3

-*Note:

Gamma Isotopes are measured quantities, all other isotopes are estimated, IC0287-0096A-HP01

IC0287-0064-NL04 PALISADES NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL Effective March 1, 1987 Revision 2

TABLE OF CONTENTS I.

GASEOUS EFFLL~NTS A.

ALAfil'1/TRIP SETPOINT ~1ETHOD

1.

Allowable C~ncentration

2.

Monitor Response

2. 1 Normal Releases 2.2 Accident Releases B.

DOSE RATE CALCULATION

1.

Appendix I Calculation Basis

1. 1 Equations and Assumptions for Noble Gas 1.2 Equations and Assumptions for Iodines and Particulates 1.3 Design Basis Quantities (DBQs) 1.4 Land Use Census and DBQ Changes 1.5 Gaseous Releases From th~ Steam Generator Blowdown Vent and Atmosphere Release Valves C.

DESIGN BASIS QUANTITY (DBQ) LIMITS

1.

Batch Releases

2.

Continuous Releases

3.

Exceeding DBQ Limits

4.

Releasing Radionuclides Not Listed in Table 1.9

D.

OPTIONAL QUARTERLY DOSE CALCULATIONS

1.

Methodology

1. 1 Simplified, Conservative 1.2 Realistic Method E.

GASEOUS RADWASTE TREATMENT SYSTEM OPERATION

1.

System Description

2.

Determination of Satisfactory Operation F.

RELEASE RATE FOR OFFSITE MPC (500 mRem/yr)

G.

PARTICULATE AND IODINE SAMPLING H.

NOBLE GAS SAMPLING I.

TRITIUM SAMPLING l

l 1

2 2

3 3

3 5

14 15 16 16 16 17 17 18 18 18 19 20 21 21 22 23 24 24 J.

TABLES 25-48 MI0885-0098A-HP01

I I.

LIQUID EFFLUENTS A.

CONCENTRATION

1.

Radiological Effluent Tech Spec Requirement

2.

Prerelease Analysis

3. - Maximum Permissible Concentration - Sum of the Ratios B.

INSTRUMENT SETPOINTS

1.

Setpoint Determination

'2.

Post Release Analysis C.

DOSE

1.

RETS Requirement

2.

Release Analysis 2.1 Water Ingestion 2.2 Fish Ingestion

3.

Annual Analysis D.

OPERABILITY OF LIQUID RADWASTE EQUIPMENT E.

RELEASE RATE FOR OFFSI.TE MPC (500 mrem/yr)

III.

URANIUM FUEL CYCLE DOSE A.

SPECIFICATION B.

ASSUMPTIONS C.

DOSE CALCULATION IV.

R..\\DWASTE SYSTEM MODIFICATIONS A.

TABLES MI0885-0098A-HP01

i. i.

Page 49 49 49 49 so 51 51 51 52 52 52 53 54 55 56 57 57 57 58 58 59 61-68

1.5 Gaseous Releases From the Steam Generator Blowdown Vent and

c.

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 gen~rator blowdown vent is normally routed to the main condenser and recirculated.

Radio-active 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 in the steam phase.

Volumes will be calculated using water balances or alternate means as available.

DESIGN OBJECTIVE QUANTITY (DBQ) LIMITS ON BATCH AND CONTINUOUS RELEASES 1.0 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 swruned in order to assure that the sum fraction of all nuclides does not exceed 1.0:

L Ai

< 1. 0 (DBQ).

i

l.

(1.17)

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.

.t*1I0885-0098A-HPO 1 15

2.0 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.1.0.

3.0 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 discre-tionary releases should be deferred until an accurate assessment of dose is made by use of GASPAR computer code or by analysis of appropriate release data via the segmented gaussian dose model used in emergency planning {inhalation dose, total body external dose, and bo-undary dose in air).

System Description

A flow diagram for the GRTS is given in Figure 1-1.

The system consists of three waste-gas compressor ~ackages, six gas decay tanks, and-the associated piping, valves, and instrumentation.

Gaseous wastes are received from the following:

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

Design of the system precludes hydrogen explosion by means of ignition source elimination (diaphragm valves, low flow dia~

phragm 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.

MI0885-0098A-HP01 20

F.

2.

_.Determination of Satisfactory Operation

~*

Design basis quantity fraction will be calculated for batch and continuous releases as described in.Section C.

These calcula-tions 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 gasses 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.

RELEASE RATE FOR OFFSITE MPC (500 mRem/yr) 10 CFR 20.106 requires radioactive effluent releases to unrestricted areas be in concentrations less than the limits specified in Appen-dix B, Table II 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 2-1.)

Concentrations at this level if present for one year.will result in a dose of 500 mrem due to external exposure or inhalation depending on the nuclide(s) released.

10 CFR S0.36a 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 flex-ibility 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 20.106 limits but still within those limits.

Appendix I to 10 CFR SO provides the numerical guideiines 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 MI088S-0098A-HP01 21

G.

ann~al average meteorology, to the most limiting organ of the person assumed to be residing at the site boundary with highest X/Q, is 2.15E~o2 mrem (for one year).

The release rate which would result in a dose rate equivalent to 500 mrem/year (using ~he more conserva-tive total body limit) is the Curies/year given in Table 1. 1 multi-plied by 500/2. 15E-02 or 1.11 Ci/sec.

PARTICULATE AND IODINE SAMPLING Particulate and 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 example), or a series of samples are obtained to.follow the course of a release.. In any event, sample intervals are weekly, at 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 esti-mation of pre-release design basis quantity fraction.

However, for the sake of maintaining accurate release totals, monitor results (for gasses) and sample results (for particulates and iodines) are utilized rather than the pre-release estimates, for cumulative records.

Gamma analytical results for particulate and halogen filters are combined for determination ~f 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, and 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.

MI0885-0098A-HP01

H.

I.

Si~~~arly, alpha activity not identified as natural radium or thorium or their daughters is assumed as Pu-239 until results of detailed analyses are obtained from quarterly composites.

NOBLE GAS SAMPLING Noble gasses 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 gasses.

Off gas will be sampled at least weekly and used to calculate monthly noble gas releases.

Nonroutine releases will be quantified from the stack noble gas monitor (RE 2326) which has a LLD of lE-06 µCi/cc (if RE1815 is used because RE 2326 is out of service, the LLD will be SE-05 µCi/cc).

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.

MI0885-0098A-HP01 23

33

Rev..

PALISADES LAND USE CENSUS REPORT TABLE J 4 Distance to the nearest residence, garden, dairy/beef cattle and goat in each sector.

SECTOR RESIDENCE GARDEN BEEF CATTLE DAIRY COW GOAT N

>5 mi

>_5 mi

>5 mi

>5 mi NNE 1.6 mi 3.4 111i

>5 mi

>5 mi*

NE 1.8 mi 1.8 mi

>5 mi

>5 iii ENE 1.3 mi 2.9 mi I

4.0 mi 4.0 mi 3.8 mi E

1.0 mi 2.9 mi I

>5 mi

>5 mi ESE 1.0 mi 2.9 mi I

3.1 mi

>5 mi

>5 *i SE

.9 mi 1.1 mi I

3.8 mi 4.3 mi

>5 *i SSE

.75 mi 1.5 mi

>5 mi

>5 mi s

.5 mi 1.5 mi

>5 mi

>5 mi SSW

.75 mi 1.5 mi

>5 mi

>5 mi IC1086-0252A-HP01

31n TABLE l.4a PALISADES PLANT 1987 GASPAR INPlTI' t

Distance X/Q X/Q Decay X/Q Decay & Dep D/Q*****

Location Sector

(*ile*l

~sec[m 3 )

(secLm3 )

~sec/m 3 )

~ll*Z)

Site Boundary SSE 0.48 t.43E-06 t.43E-06 1.31E-06 1.68E-08 Residence/Garden s

0.50 1.00E-06 1.00E-06 9.15E-07 9.12!-09 Beef Cow ESE 3.10 7.75E-08 7.70E-08 6.15E-08 6.09E-10 Dairy Cow SE 4.30 6.34E-08 6.28E-08 4.85!-08 4.88E-10 Goat ENE 3.80 6.41E-08 6.3SE-08 4.99E-08 4.20!-10 IC1286-0268A-HP01 I J

. 7 Rev.

~ -

Table 1. 9 PALISADES PLANT 1987 GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Dose Factor Annual Quantity Nuclide Organ aremlCi

~Ci~

Ag-110.

GI Tract 1.17E+OO 1.28E+Ol Ar-41 Total Body 2.SlE-04

1. 78E+04 Ba-139 GI Tract 2.58E-10 5.81E+l0 Ba-140 Bone-C 8.65E-02 1.73E+02 Br-82 Total Body 2.86E-03 l.75E+03 C-14 Bone-C l.54E-Ol 9.74E+Ol Ce-141 GI Tract*T 2.39E-Ol 6.28E+Ol Ce-144 GI Tract*T 6.34E+OO 2.37E+OO Co-57 GI Tract-T 1.60E-Ol 9.38E+Ol Co-58 Total Body-C 9.52E-02 5.25E+01 Co-60 Total Body-C 5.67E-Ol

. 8. 82E+OO Cr-51 GI Tract*A,T 4.43!-03 3.39E+03 Cs-134 Liver-C 1.31E+Ol 1.15E+OO Cs-136 Total Body-I 5.17E*02 9.67E+Ol Cs-137 Bone-C 1.28E+Ol 1.17E+OO Cs-138 Total Body 4.68E-21

1. 07E+21 Fe-55 Bone-C 3.89E-Ol 3.86E+01

.Fe-59 GI Tract-T 4.54E-01 3.30E+Ol H-3 Total Body-C 1.76E-04 2.84E+04 1-131 Thyroid-I 5.17E+OO 2.90E+OO I-132 Thyroid-C 6.69E-07 2.24E+07 1-133 Thyroid-C

7. lOE-02 2.11E+02 1-134 Thyroid-C 5.15E-l3 2.91E+13 1-135 Thyroid-C 8.69E-04 1.73E+04 Kr-83m Skin 6.SOE-07 2.21E+07 Kr-85 "

Skin 6.13!-05 2.45E+05 Kr-85m Total Body

3. 71!-05 1.35E+05 Kr-87 Skin

~.58!-04 2.28E+04 Kr-88 Total Body 4.66E-04 1.07E+04 Kr-89 Total Body 5.27E-04 9.49!+03 La-140 GI Tract-A l.28E-02 1.17!+03 Mn-54 GI Tract-T 4.58E-01 3.28!+01 Mn-56 GI Tract*C 4.63!-07 3.24E+07 Mo-99 Kidney-C 2.90E-03 5.17E+03 N-13 Total Body 1.52E-50 3.29E+50 Na-24 Total Body 2.27!-04

2. 20E+04 Nb-95 GI Tract-T 2.04!-0l 7.35E+Ol Ni-65 GI Tract-C

. 2.07E-07 7.25E+07 Np-239 GI Tract 2.73E-03 5.49E+03 Rb-88 Total Body-C 4.15E-32 1.20E+32 Ru-103 GI Tract-T 2.60!-0l s_. 77!+01 Sb-124 GI Tract-T 1.46E+o0 1.03E+Ol Sb-125 GI Tract-T 8.24E-01 1.82E+Ol IC1286-0268A-HP01

Table 1.9 (CONTD)

PALISADES PLANT

?age.'..8 Rev. /

~987 GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Nuclide Sr-89 Sr-90 Sr-91 Sr-92 Tc-99m Tc-101 Te-127 Xe-13lm Xe-133 Xe-133m Xe-135 Xe-135m Xe-137 Xe-138 Zn-65 Zr-95 Organ Bone-C Bone-C GI Tract GI Tract GI Tract-C Total Body GI Tract-A Skin

rotal Body Skin Total Body Total Body.

Skin Total Body Total Body-C GI Tract-T IC1286-0268A-HP01 Dose Factor mrem/Ci

1. 71.E+Ol 7.04E+02 1.38E-04 1.28E-06 9.20E-07

1. 36E-39 8.21E-05 2.71E-05 9.33E-06 5.66E-05 5.74E-05 9.90E-05 6.06E-04 2.SOE-04 8.62E-Ol 6.00E-Ol Design Objective Annual Quantity (Ci)

8. 77E-Ol 2.13E-02 1.09E+OS 1.17E+07 1.63E+07 3.68E+39 l.83E+OS 5.54E+05 5.36E+os*

2.65E+05 8.71E+04 5.05E+04 2.48E+04 1.79E+04 5.SOE+OO 2.SOE+Ol

IC0287-0064-NL04 Consumers Power Company Palisades Plant - Docket 50-255 PROCESS CONTROL PROGRAM (PCP)

July l_, 1985 Rev 2 3/1/87

PALISADES PROCESS CONTROL PROGRAM (PCP) 1.0 ALPIL.<\\LT VOLUME REDUCTION SYSTEM The Palisades Plant utilized a Waste Chem volume reduction and solidifi-cation system (VRS) to process various radioactive liquid waste streams.

The process utilizes thermal energy (heat) to evaporate water from the radioactive wastes thus reducing waste volume to anhydrous waste resi-due.

This residue is then encapsulated in a thermoplastic matrix (asphalt).

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 preventative maintenance or system repair with minimum expo-sure.

1.1 VARIABLES INFLUENCING SOLIDIFICATION The purpose of this section is to identify and define those process variables which ha~e a direct ~ffect on the ability of the final product to form a freestanding monolith with no free liquid.

The following variables influence the properties and consistency of the final product:

a.

Asphalt type

b.

Waste chemical species used as feed

c.

Ratio of waste-to-asphalt

d.

Process temperature

e.

pH MI0785-0095A-HP01

-2 1.2 ASPHALT lYPE 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'~ Pioneer 221.

The specifications for this asphalt are provided in Appendix A.

This grade of asphalt has a low residual volatile content and a high molecular weight.

At room temperature, and at all normal ambient temperature conditions, this material is a freestanding, monolithic, solid.

Utilization of an asphalt complying with ASTM-D-312-71, Type III, is the means by which process control of this variable is achieved.

1.3 WASTE CHEMICAL SPECIES The type and relative quantity (waste-to-asphalt ratio) of waste chemi-cals 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, or approximately 2°F lower per percent of oil.

This is within an acceptable range and, therefore, is the basis for the limit of 1% oil in the feed stream.

pH should be in the range of 7.5 to 8.5 for the best product.

Other chemical specifications on feed streams are specified below.

These are required primarily for calculating waste-to-asphalt ratio which is important to end product, and equipment protection (which will have no discernable effect on the end product).

REQUIRED ANALYSIS Concentrates pH (Equip Limit)

% Solids Sp Gravity Oil %

MI0785-0095A-HP01 Resin/Powdex pH (Equip Limit)

% Slurry

3 1.4 wASTE-Tq-ASPHALT RATIO Feed

1.

2.

3.

The ratio of waste-to-asphalt contained in the end product has the most signific~nt effect on the viscosity and physical consistency of that 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 Boric Acid Concentrates at 120 L/hr Evaporative Rate Spent Resins at 80 L/hr Evaporative Rate

~ 1.0/1.0

~.67/l.O

<.67/1.0 Powdex at 80 L/hr Evaporative Rate 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 fe~d rate can be determined by the following formula:

Cone Feed Rate =

0.528 GPM (1.0 - Solids Fraction) (Sp Gravity)

NOTE 0.528 gpm = 120 L/hr evaporative rate.

The corresponding asphalt feed is calculated by:

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

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

NOTES:l.

2.

3.

The density of Type III asphalt is 1.0 so a density correction is not needed.

The minimum asphalt flow is 0.065 gpm because of lubrication 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 main-tain the 1.0/1.0 waste-to-asphalt ratio as long as the MI0785-0095A-HP01

I

~

maximwn concentrate flow or the minimwn asphalt flows is not exGeeded.

Maximwn bead resin or Powdex can be determined by the following formula:

Resin Feed =

0. 35 GPM (1.0 - Solid Fraction)

NOTES:l.

Solid fraction = slurrv fraction slurry = 25 weight %.

2.

Example is a 50% *

2.

0.35 gpm = 80 L/hr evaporative rate.

The corresponding asphalt feed is calculated by:

Asphalt Feed (GPM) = (Resin Feed) (Solid Fraction)

(Waste-to-Asphalt Ratio) wnere the recommended waste-to-asphalt ratio is 0.67, the notes on the preceding 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 con-tainer.

At evaporative rates higher than specified, there will be excessive steaming at discharge nozzle.

At higher waste-to-asphalt loading the discharge will appear grainy and stringy.

1.5 PROCESS TEMPERATURES

-A proper temperature profile along the length of the extruder-evaporator is required to provide adequate evaporative (process) capacity, and to assure that free water is not discharged from the machine.

Process temperature profiles for waste feeds should be maintained as recommended below:

Waste TyPe Process Temperature (°F)

Zones:

1 2

3 4

5/6 7

Boric Acid Concentrates LWS Concentrates 300° 280° 280° 300° 300°

'\\

Chemical/Laundry Waste Spent Resins/Powdex 300°

/,-,',

NOTE:

No zone shall be maintained below 240°F.

~*, Cooling Zone - no specified temperature MI0785-0095A-HP01

5

""'~:steam supply control valves are fully open

. Low temperature alarms are provided to alert the operator to a low temperature out-of-specification condition which could potentially lead to the discharge of free water.

If the out-of-specification conditions persists for two (21 minutes, the extruder-evaporator is automatically tripped to prevent free water from being discharged into the container.

Free water cannot be discharged in the interim, since the residual heat of the extruder-evaporator itself is sufficient to effect evaporition~

Verification of the absence of free water and ptoduct solidification will be made on a minimum of one container from every tenth batch or run.

Verification is recommended to be done on every tenth drum shipped.

The required container shall be examined through a removable lid bung or equivalent means for solidification by checking penetration with a solid tool and inverted for a minimum of eight hours to check for

-free water.

Evidence of free water other than a few drops of condensa-tion shall be cause for rejection and evaluation system product.

2.0 DEWATERING SOLIDS IN HIGH INTEGRITY CONTAINERS (HIC) 2.1 Solids such as bead resin, filter cartridges and powdered resin (Powdex) may be dewatered and shipped in HICs per approved yendor procedures and the HIC certificate of compliance.

2.2 High integrity containers are approved by the individual burial ground agreement states as meeting 10CFR61 waste form stability requirements.

2.3 Free water determination shall be verified by the successful completion

.and documentation of the vendors approved dewatering procedure.

3.0 DELAWARE CUSTOM MATERIAL (DCM) - SILICATE CEMENT Liquid wastes tan be solidified by the DCM method*.

The silicate solidi-fies and the cement gives structural strength.

3.1 For solidification, acquire a representative sample of waste.

Before following the guidelines outlined below, determine the type of waste to be solidified, example, lab waste, laundry waste, de con so,lutions, boric acid, oil, etc.

Sample for E!!, boric acid, visible organics and radio-activity.

Use analy~is to determine the proper laboratory procedure to test.

All batches shall be lab tested. prior to solidification in a larger container unless sample analysis (pH+/- 0.2 and Boron +/- 20%) matches the analysis of a waste type which has previously passed lab test criteria.

For all oil waste, do not exceed 50% by voltµlle.

Oil must be emulsified to less than 50% by volume with a detergent or boric acid in some type of neutral aqu~ous waste or tap water.

MI0785-0095A-HP01

b NOTE Oil cannot be shipped to Barnwell, South Carolina.

ol,,;.:

For spent resins, liquid absorbent, or other earthen-like material, dilute with an equal volume of concentrate or tap water t*o solidify.

All results must be recorded initially, at approximately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and approximately 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after testing.

Grade observations to evaluate sample mixes.

The 48-hour test can be omitted if the 24-hour test is good.

3.2 SOLIDIFICATION AND FREE WATER DETERMINATION Solidification shall be considered successful if, 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after compl-etion of Appendix A solidification, there is not standing water on the waste surface and the surface is not penetrated more than 2" with a 1 11 diameter rod.

If deeper penetration is possible, then the drum can still be considered solid if the penetration hole remains open after the rod is withdrawn.

Silicate cement shall cure for a minimum of 28 days prior to shipment for disposal.

For silicate cement drums, the following shall be done:

Each drum shall be inspected for absence of detectable freestanding liquid after curing at least 28 days.

With the drum lid installed, invert each drum and allow drum to remain upside down for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

After 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , inspect each drum hy placing upright and removing the lid.

The RMC Supervisor or designate and a QC Inspector shall inspect each drum for presence of liquid.

Drums which failed the 48-hour solidification evaluation should be capable of passing at this point.

If no detectable freestanding liquid is present, the drum can be pre-pared for shipment.

RMC Supervisor and QC Inspector document if no detectable freestanding liquid is present.

In the event liquid is observed, those drums with liquid shall be drained of all liquid.

When no further liquid can be drained from the drum in a 24-hour period, the drum shall be core-bored or overpacked with two bags of approved absorbent and inspected by QC and RMC to verify that the drum is* dry.

After. this verification (and documen-tation) the drum may be prepared for shipment.

Inspect the drum lid and gasket for defects prior to lid installation.

Install lid.

Use a different lid if defects are found which prevent a tight seal between drum and lid.

4.0 10 CFR 61 REQUIREMENTS 4.1 10 CFR 61 classification requirements will be met using Wastetrak computer software program using the scaling factor methodology of AIF/NESP-027, Methodologies for Classification of Low-Level Radioactive Waste from Nuclear Power Plants, 1983.

MI0785-0095A-HP01

7 The scalfng factors will be updated by an ongoing analysis program of actual waste streams.

The program will initiate with semi-annual samples of available waste streams and may be modified to longer inter-vals if the data base warrants.

Waste streams should include; if available; bead resin, concentrates, reactor coolant, clean waste, filter crud and compacted trash.

4.2 10 CFR 61 waste form stability requirements will be met by generic testing of the asphalt/waste stream product.

The generic waste_ streams will be boric acid, bead resin and chemical regenerative wastes.

4.3 Documentation of the waste stream analysis, waste form stability and computer software scaling factor security shall be maintained by the Radiological Services Department.

5.0 RADWASTE SYSTEM 5.1 A radwaste system flow diagram is included in Appendix B, B-3.

MI0785-009SA-HP01

MI0785-0095A-HP01 APPENDIX A Consumers Power Company Palisades Plant PROCESS CONTROL PROGRAM CPCP)

Aslphalt Technical Data Summary

ASPHALT TECHNICAL DATA

SUMMARY

WITCO CHEMICAL - PIONEER 221

1.

Basic Constituent Pioneer 221 is plished by air 300°C (572°F).

content (0.1%),

2.

Flash Point an oxidized petroleum base asphalt.

Oxidation is accom-blowing at temperatures ranging from 200°C (392°F) to Air *blowing results in a product with minimum volatile greater inertness and higher molecular weight.

The Flash* Point of Pioneer 221 is in excess of 288°C (549°F): The Flash Point is oetermined by the Cleveland Open Cup (ASTM 092-71) method.

It is the lowest temperature at which surface vapor~ will momentarily ignite when a test flame is passed over the surfa~e.

3.

Fire Point The Fire Point of Pioneer 221 is in excess of 300°C (572°F).

The Fire Point, like the Flash Point, is determined by the Cleveland Open Cup (ASTM 092-72) method.

It is the lowest temperature at which the surface vapors will burn for at least 5 seconds before going out, the vapors being ignited as in the test for Flash Point.

4.

Ignition Point The Ignition Point of Pioneer 221 is approximately 400°C (752°F).

The Ignition Point is the lowest temperature at which the heat loss from the combustible mixture is exceeded by the heat produced in the chemical reaction.

It is thus the lowest temperature at which combustion begins and continues in an air environment.

5.

Softening Point The Softening Point of Pioneer 221 is in the temperature range of 88-94°C (190-201°F).

The Softening Point is determined by the Ring and Ball method (ASTM 0-36-70).

6.

Viscosity The Viscosity of Pioneer 221 in the temperature range from 250°F to 400°F is presented in attached graph.

The graph is based on the following data from Witco Chemical:

Saybolt Furol Viscosity MI0785-0095A-HP01 A-1

7.

Penetration at 205°C at 177°C 54.sec 161 sec The Penetrition of Pioneer 221 by ASTM Method D-5-73 for various tempera-tures is given below:

25°C (77°F) 46°C ( 115°F) 0°C (32°F) 22-30 dmm 40-60 dmm 13-18 dmm The abbreviation "dmm" means one-tenth of a millimeter.

The number of dmm's represents needle penetration under standard conditions of loading and time for a given temperature.

8.

Specific Gravity The Specific Gravity of Pioneer 221 is approximately 1.0 gram per cc.

Specific Gravity is determined by ASTM Method D-70-72, which employs a pyenorneter.

A pyenometer is a container of known volume which is weighed empty and filled with sample.

9.

Solubility Pioneer 221 may be considered to be entirely waterproof and insoluble in water.

Pioneer 221 is soluble in petroleum solvents such as naphtha, mineral spirits and kerosene, in addition to carbon tetrachloride, carbon disulfide and trichlorethylene.

MI0785-0095A-HP01 A-2

PIONEER 221 LAMINATING & INDUSTRIAL ASPHALT PIONEER E-7465 FOR SALT CARTON M.<\\NUFACTURERS Pioneer 221 in an all-purpose, tough, medium softening point asphalt for use i~ laminating paper, foil-to-paper, as a base pigment for paints and var-nishes, or in the manufac~ure of sealers and adhesives.

Pioneer 221 complies with federal specifications set forth by the Food & Drug Administration for use in packaging and sealing food products and will not stain, or impart an odor or taste when used properly in connection with packaging products.

PHYSICAL CHARACTERISTICS Softening Point Penetration @ 77°F Doctility @ 77°F Solubility CCL Flash Point (C.O.C.)

Weight Per Gallon Use Temperature Viscosity @ 400°F Viscosity @ 375°F Viscosity @ 350°F 190-210°F 20-30 dmm 2.5 ems +

99.0% +

550°F +

8.3 lbs 400°F +/- 25°

.94 secs .174 secs .360 secs Packaging: Bulk - Tankwagon ( 5000 gal), tank car ( 10,000 gal).

Packages - 100 lb cartons MI0785-0095A-HP01 A-3

TABLE 1 - COMf#.RISON OF ELEMENTAL ANALYSES AND OTHER CHEMICAL PROPERTIES OF ROAD TAR, COAL-TAR PITCH AND PETROLEill1 ASPHALTS ASPHALT ROAD ROOFING ROOFERS MATERIAL CEMENT TAR ASPHALT PITCH GRADE*

AC-10 RT-12 TYPE III TYPE A ELEMENTAL ANALYSIS, percent:

c 85.8 92.2 86.0 92.8 H

9.7 5.2 9.9 5.1 N

0.6

1. 5 0.5

1. 5 0

0.5 1.0 0.7 s

2.8 0.6 2.9

1. 53 C/H atomi.c ratio

0. 74

1. 49 0.73 1.53 MOLECULAR WEIGHT 1 (Numbers Avg) 1030 420 1160 497 CARBON ATOM DISTRIBUTION:

(percent of total carbon)

AROMATIC CARBON 34 80 37 79 NAPHTHENE CARBON 23 15 23 18.

PARAFFIN CARBON 43 5

40 3

MI0785-0095A-HP01 A-4

APPENDIX B Consumers Power Company.

Palisades Plant PROCESS CONTROL PROGRAM (PCP)

System Diagrams MI0785-009SA-HP01 A-5 J

APPENDIX 8

1

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APPENDIX B B-2 FLOW SYSTEM DIAGRAMS FOR RESINS F*11ftl.-11r~te c,,,.,erNn11.,,

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l'OWERINli MICHlliAN'S l'ROliRESS General Offices: 1945 West Parnall Road, Jackson, Ml 49201 ** (517) 788-0550 February 27, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT - JULY THROUGH DECEMBER 1986 Attached is the Semiannual Radioactive Effluent Release and Waste Disposal Report for the Palisades ~lant covering the period from July through December 1986.

This submittC:ll is made in accordance with 10CFR50~36a(2) and Technical Specification Section 6.9.3.1.

Included in this report are changes to the Process Control Program (PCP).and Off site Dose Calculation Manual (ODCM) that were made in response to comments received in NRG letter of December 30, 1986 on acceptance of the Palisades ODCM and PCP.

A correction to the January to June 1986 semiannual report is also included in this submittal as item number 8 in the report.

Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, NRG NRG Resident Inspector - Palisades Attachment OC0287-0064-NL04

ML18052A877

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