ML20092M986

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Revised Offsite Dose Calculation Manual
ML20092M986
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 05/14/1984
From: Shank K, Widner T
PENNSYLVANIA POWER & LIGHT CO.
To:
Shared Package
ML20092M973 List:
References
PROC-840514, NUDOCS 8407020437
Download: ML20092M986 (12)


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PENT:0YLVANIA POWER.& LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL i

Prepare'd By m Date I 9 S9 Reviewed By

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Date d Ok PORC k view Required Yes ( ) No (/) Date Approved By , W Date k Ik $4 ManageY-Nuclehrypport 8407020437 840613

'PDR ADOCK 05000387 P PDR L :-

TABLE OF CONTENTS Page Revision Date

1.0 INTRODUCTION

.................................. 1 7/12/82-2 5/11/82 3 4/27/83 4 5/11/82 5 5/11/82 6 4/27/83 2.0_SETPOINTS..................................... 7 4/27/83 2.I LIQUID EFFLUENT MONITORS.................. 7 4/27/83 8 10/25/83 Sb 1/20/84 2.2 GASEOUS EFFLUENT MONITORS................. 9 1/20/84 10 1/20/84 11 5/14/84 12 5/11/82 13 5/14/84

_3.0' LIQUID EFFLUENT CONCENTRATION MEASUREMENTS.... 14 10/25/83 15 10/25/83

. 4.0 GASEOUS EFFLUENT DOSE RATE MEASUREMENTS....... 16 4/27/83 4.1 N0BLE GASES............................... 16 4/27/83 4.2 RADIONUCLIDES OTHER THAN NOBLE GASES...... 17 10/25/83 18 4/27/83 19 4/27/83 20 4/27/83 5.0_ INDIVIDUAL DOSE DUE TO LIQUID EFFLUENT........ 21 4/27/83 22 10/25/83 23 5/11/82 24 5/11/82 6.0 INDIVIDUAL DOSE DUE TO GASEOUS EFFLUENT. . . . . . . 25 4/27/83 6.1 NOBLE GASES............................... 25 4/27/83 6.2 RADIONUCLIDES OTHER THAN NOBLE GASES...... 26 4/27/83 27 4/27/83 -

28 5/11/82 29 5/11/82 7.0-TOTAL 00SE.................................... 30 4/27/83 31 5/11/82 8~.0 OPERABILITY OF WASTE TREATEMENT SYSTEMS. . . . . . . 32 4/27/83

'8.1 LIQUID WASTE TREATEMENT................... 32 4/27/83' 4/27/83

8. 2 GASEOUS WASTE TREATMENT. . . . . . . . . . . . . . . . . . . 32 33 5/11/82 8.3 SOLID WASTE TREATMENT..................... 34 4/27/83 35 5/14/84 36 5/11/82 37 5/11/82 38 5/11/82 MAY 14 SSi 1

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9.0~ RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM. 39 7/12/82 9.1 DEFINITIONS............................... 39 7/12/82 9.2 MONITORING PR0 GRAM........................ 39a 5/14/84 9.3 CEUSUS PR0 GRAM............................ 40 5/14/84~

40a 7/12/82 41 10/25/83

42. 10/25/83 43 5/14/84 44 5/11/82 45 5/14/84 46 5/11/82 47 5/11/82 48 4/27/83 APPENDIX A - SAMPLE- CALCULATIONS OF ODCM PARAMETERS........................... A-1 10/25/83 I A-2 10/25/83 A-3. 5/11/82 A-4 5/11/82 A-5 5/11/82 A-6 5/11/82 A-7 5/11/82 A-8 5/11/82 A-9 5/11/82 A-10 5/11/82 A-11 5/11/82 A-12 5/11/82 A-13 5/11/82 APPENDIX B - REPORTING REQUIREMENTS............... B-1 5/11/82 ,

B-2 5/11/82 B-3 5/11/82 B-4 5/11/82 APPENDIX C - SITE SPECIFIC INFORMATION USED IN GASPAR.........~.............. C-1 5/11/82

APPENDIX D - SITE SPECIFIC INFORMATION USED IN LADTAP....................... D-1 4/27/83 D-2 4/27/83 D-3 4/27/83 Pipx 141984 11

LIST OF TABLES P m Revision Date Table 1_ ' Radiological Effluent Objectives and Standards.... 6 4/27/83 I Table 2. ~ Dose Factors for Noble Gases and Daughters........ 12 5/11/82 Table 3 Annual Average Relative Concentrations and Deposition Rates.................................. 18 5/11/82

. Table 4 , Dose' Parameters for Radionuclides Other Than Noble Gases....................................... 20 4/27/83 Table ~5' l Liquid Dose Parameters'for Adults................. 23 5/11/82 '

Table 6 Maximum Pathway ~ Dose Factors Due to Radionuclides Other Than Noble Cases. . . . . . . . . . . . . . 28 5/11/82 LTable 7 f0peraticnal Radiological Environmental Monitoring Program................................ 41 10/25/83

42. 10/25/83

. 43 5/12/84

Table.8 Detection Capabilities for Environmental Sample. Analysis................................... 46 5/11/82 Table B-1 Radiological Environmental Monitoring Program Annual Summary.................................... B-3 5/11/82 Table B-2 Reporting Levels for Nonroutine Operating i Reports............................................ B-4 5/11/82 MAY 141984 f

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> LIST OF. FIGURES c -

M Revision Date Figurejl Flow Chart of'Offsite Dose Calculations..... 3 4/27/83

Figure"2 ;uid Radwaste System Flow Diagram. . . . . . . . . 33 5/11/82

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Figure'3 Of fgas and Recombiner System Flow Diagram. . . 36 5/11/82 Figure:4 Standby: Gas Treatment System Flow Diagram... 37 5/11/82 Figure 5 Solid Waste Management System Flow Diagram. . 38 5/11/82 Figure 6 Onsite Environmental Sampling Locations -

Susquehanna SES........................:..... 44- 5/11/82 Figure 7'-Offsite Environmental' Sampling Locations -

(Susquehanna SES.........'...................

. 45 5/12/841 I

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MpX 1 4 1984 iv

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where:

Kg = the whole body dose factor due to gamma emissions for each identified noble gas radionuclide (1)

(mrem /yr per pCi/m3 ) from Table 2.

Q'iv = the release rate of radionuclide (1) from vent (v) which results in an annual dose rate of 500 mrem to the whole body or 3000 mrcm to the skin of the critical receptor (uCi/sec).

(i/Q)y - the highest calculated annual average relative concentration for estimating the dose to the

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critical offsite receptor in an unrestricted area from vent release point (v) (sec/m 8).

!' 500 = the 10 CFR 20 annual whole body dose limit (mren/yr) to an individual in an unrestricted area.

L i

=

.the skin dose factor due to beta emissions for each identified noble gas radionuclide (1) 8 (mrem /yr per pC1/m ) from Table 2.

Mg -- the air dose factor due to gamma emissions for

.each identified noble gas radionuclide (i)

(mrad /yr per pCi/m8 ) from Table 2. (conversion F

constant of 1.1 converts air dose-crad to skin dose- mrem) . -

3000 = the 10 CFR 20 annual skin dose limit (crem/yr) to an' individual in an unrestricted area.

Xenon-135 should be the principal noble gas radionuclide released from the reactor building vents and the standby gas treatment z system vent while Xenon-133 should be the principal noble gas L

radionuclide ' released f rom the turbine building vent due to the offgas holdup system. It is appropriate that these noble gas radionucides be used as the reference isotopes for establishing the particular monitor setpoints. The whole body dose will be the'most limiting and the release rate limit is calculated by substituting the appropriate values in Equation 4. After the release rate limit.is determined for each vent, the correspond-ing vent concentration limits can be calculated based on high limit vent flow rates:

Setpoint pCi = 9 iv (uCi/sec),

(6) cc Flow rate (cc/sec)

HAY 141984 7 u.

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Sample calculations for determining. release limits for the whole body dose and the skin dose are given in Section A.1.2 of Appendix A. Also, typical values for flow rates and calibration factor are given for determining the setpoint of the Unit 1

- turbine building vent gaseous effluent monitor.

- Vent flow rates and sample flow rates are monitored and recorded for each of the five SSES release points. The measured flow

. rates.are used to calculate vent concentrations and release rates. Flow channel setpoints are set at 10% and 90% of the calibrated sensor ranges to provide indication of possibly abnormal flow rates.

- SPECIFICATION 3.11.2.6 - THE CONCENTRATION OF HYDROGEN OR OXYGEN IN THE MAIN CONDENSER OFFGAS TREATMENT SYSTEM SHALL BE LIMITED TO LESS THAN OR EQUAL TO'4% BY VOLUME.

Hydrogen recombiners are used at SSES to maintain the relative concentration of components of potentially explosive gas mixtures outside the explosive envelope. The~ main. condenser offgas treatment system explosive gas monitoring system (offgas

- hydrogen analyzers) have setpoints of 1% hydrogen to alarm and 2% hydrogen to isolate.

t MAY 141984 9

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- The SSES solid radwaste system was designed to solidify all wet ,

wastes for ultimate offsite disposal. There are two Backwash Receiving Tanks, one per unit, which collect two filter-i demineralizer backwashes per tank (2450 gal capacity). Air spargers for resin mixing are driven by instrument air.

Regeneration Maste Surge Tanks (4) and Phase separators (3) have internal mixing eductors for sludge cixing driven by recircula- l tion flow. The Spent Resin Tank has a reversible progressing cavity pump and internal mixing eductors. Two solidification trains have waste mixing tank progressing cavity feed and mixing pumps, and screw-conveyors for feeding of dry Portland cecent.

Mixing is facilitated by the addition of sodium silicat.e.

b Common solidification equipment includes waste container fill-

., port, transfer cart, capper washdown station, and swipe tool; cement silo with rotary feed valve, aeration blower, baghouse, and exhaust fan; sodium silicate tank and pump. Dry contami-nated solids'are compacted into 55 gallon drums. The trash compactor was hydraulic pump and hydraulic press pisten with exhaust fan and EEPA' filter.

A flow diagram of the SSES solid radwaste treatment systen is shown in Figure 5.

NOTE: Vendor solidification services may be used in accordance with.the SSES Process Control Program to supplement the plant solidification system or to take the place of the plant system when the plant system is out of service. j MAY 141984 l

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9.2 MONITORING PROGRAM

-SPECIFICATION 3.12.1 - THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SHALL BE CONDUCTED AS SPECIFIED IN TABLE 3.12.1-1.

Environmental samples shall be collected and analyzed according to Table 7 at locations shown-in Figures 6 and 7. Analytical techniques used shall ensure that the detection capabilities in Table 8 are achieved.

A dust loading study (RMC-TR-81-01) was conducted to assure that cL the proper-transmission factor was used in calculating gross beta activity of air p' articulate samples. This study concluded that the sample collection frequency of once per week was sufficient and that the use of 1 for the transmission connection factor for gross beta analysis of air particulate samples is valid.

l The charcoal sampler cartridges used in the airborne radiciodine sampling program (Science Applications, Inc., Model CP-100) are designed and tested by the manufacturer to assure a high quality of radiciodine capture. A certificate from the manufacturer is supplied and retained with each batch of cartridges certifying the percent retention of radioiodine versus air flow rate through the cartridge.

The results of the radiological environmental monitoring program are intended to supplement the results of the radiological efflu-ent monitoring 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 model-ing of the environmental exposure pathways. Thus, the specified enviroimental monitoring program provides measurements of radia-tion and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radia-tion exposures of individuals resulting from station operation.

The initial radiological environmental monitoring program will

- 39a -

M Y 141984

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be conducted for'the first three years of commercial operation of Unit 1. -Fo-11owing this period, program changes may be proposed based on operational experience. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous' conditions, seasonal unavailability, malfunction of automatic sampling equipment-, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, ar. effort shall be made to complete corrective action prior to the~end of the next sampling period. All deviations from the sampl-ing schedule sh'll a be documented in the annual report. Reporting requirements for the radiological environmental surveillance program are given.in Appendix B.

9.3 CENSUS PROGRAM SPECIFICATION 3.12.2 - A LAND-USE CENSUS SHALL BE CONDUCTED AND 7: SHALL IDENTIFY-WITHIN A DISTANCE OF 8 KM (5 MILES) THE LOCATION

[ IN EACH OF'THE~16 METEOROLOGICAL SECTORS OF THE NEAREST MILK ANIMAL, THE NEAREST RESIDENCE AND THE NEAREST GARDEN

  • OF GREATER 2 2 THAN 50.M (500 FT ) PRODUCING B' ROAD LEAF VEGETATION.

A land use census will be conducted to identify the location of the nearest milk animal and the nearest residence in each of the 16

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meteorological. sectors within a distance of five miles. When a land

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use census identifies a location (s) which yields a calculated dose or dose'fcommitment greater than the values calculated from current sample locations, appropriate changes in the sample locations will be made. If a land use census identifies a location (s) with a higher average annual deposition rate (D/Q) than a current indicator loca-tion, the following shall apply:

  • Broad leaf vegetation sampling of at least three different kinds of vegetation'may be performed at the site boundary in each of_two 1 directional sectors with the highest predicted D/Q's in lieu of the

. garden census. Specifications for broad leaf vegetation sampling in Table 3.12.1-1, item 4C shall,be followed, including analysis of control

. samples.

MAY 141984 20 -

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~E TABLE 7 (Continu d)- -

Peg;33 cf'. ,30' Exposure Pathways Number of Samples Sampling'and. Type'and Frequency.

and/or Sampic' -and Locations Collection Frequency -ofJAnalysis S:diment from 7B Bell Ecud - 1.2.mi SE Semiannually; Camma' isotopic analysi  :

Shorelinc ' semiannually.

' Milk *** 12B2 Shultz Farm - 1.69.mi. WSW Semi-monthly when animals. Gamma isotopic and 1-131E 13E3 Dent. Farm - 4.9 mi. W are on pasture, monthly- analysis of each sample.

SE1 Bloss Farm ~~4.4 mi. E otherwisc 10G1 Davis Farm - 14 mi. SSW" Fish and 'Outfall. area Sample in season. Gamma' isotopic on Invertebrates 211 Falls, Pa. One sample of each of the edible portions.

(Approximately 30 mi NNE) following species":

1. Walleye
2. Catfish Food Products llD1 Zehner Farm - 4.3 mi SMJ At time of harvest Gamma isotopic on-

. vegetable edible portions.

  • The location of samples and equipment were designed using the guidance in the Branch Technical Position to NRC Reg.

Guide 4.8, Rev. I Nov. 1979, Reg. Guide 4.8 1975 and ORP/SID.72-2 Environmental Radioactivity Surveillance Guide.

Therefore, the airborne sampler locations were based upon X/Q and/or D/Q.

    • A dust loading study (RMS-TR-81-01) concluded that the assumption'of I for the transmission correction factor for gross beta analysis of air particulate samples'is valid. Air particulate sampics'need not be weighed to determine a transmission correction factor.
      • Tf a milk sample is unavailable for more than two sampling periods from one or more of the locations, a vegetation sample shall be substituted until a suitable milk location is evaluated. Such an occurrence will be documented in the RFMP annual report.

" Control sample location.

Temporary locations until' compositor is installed in intake and . discharge lines; then frequency changes to composite sample collected over one-month period and location changes to 6S6 intake line, 6S7 discharge line.

The upstream sample will be taken in the intake line and which is beycad significant influence of the discharges.

% e d wnstream sample will be taken in the discharge line.

c Other species in the same family could be sampled instead of the stated species if deemed desirable by the b' biological consultants.

((

gg There is no river water intake at Berwick for drinking water. See Susquehanna SES-ER-OL Appendix G, page RAD-3.1.

The calculated dose for Danville to the infant thyroid was 0.13 mrem per year. Therefore, there is no need to

take a composite sample over two-week period and perform an I-131 analysis.

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