ML18017A291

Rev 0 to EC-ENVR-1025, ISFSI Fuel Cycle 40CFR190 Offsite Dose Calculations.

ML18017A291
Person / Time
Site:	Susquehanna
Issue date:	10/02/1996
From:	Barclay R, Ely R, Kalter C PENNSYLVANIA POWER & LIGHT CO.
To:
Shared Package
ML17158C159	List: ML17158C158 ML17158C160 ML18017A053 ML18017A291
References
EC-ENVR-1025, EC-ENVR-1025-R, EC-ENVR-1025-R00, NUDOCS 9705200147
Download: ML18017A291 (214)

Text

ATTACHMENTTO PLA-4607 Page1of6 Provide information on mitigative actions that will be implemented to reduce the expected increase in dose to personnel in unrestricted areas, that would result from the operation of Hydrogen Water Chemistry. This should include cstimatcs of thc cxpectcd increase in the yearly dose rate (external gamma radiation) in unrestricted areas. Also provide estimates of the increase in exposure levels of external radiation in and around turbine building components.

Calculations of both dose rate (Ref: EC-ENVR-1026) and annual dose (Ref: EC-ENVR-1025) increases were performed to assess the impact of moderate hydrogen injection to personnel located in unrestricted areas. A factor of five increase in N-16 source activities (and associated exposure levels of external radiation) for turbine/main steam components was assumed based on vendor recommendations and industry experience. The maximum dose rate in an unrestricted area (factoring in all sources, including interim spent fuel storage scheduled to be implemented in 1998) was estimated to be 1.2 mR/hr. The bulk of this dose rate is the result of cask transfer activities to the interim storage facility. Less than 1% of this dose rate is attributed to all other sources (including hydrogen injection).

The maximum annual dose to an individual in an unrestricted area was estimated to be 5.3 mrem total body and 6.3 mrem organ. Based on the results of these calculations, it was determined that no additional mitigating actions were required for individuals in unrestricted areas.

How does the expected increase in the yearly dose rate impact compliance with 10 CFR Part 20? (Refer to specific reference 40 CFR Part 190 in 10 CFR Part 20)

As stated in the response to question 1 above, the calculated dose rate is 1.2 mR/hr. This is less than the 10CFR20.1301 maximum allowable dose rate of 2 mR/hr. The calculated annual doses of 5.3 mrem total body and 6.3 mrem organ are approximately one fifth of the 40CFR190 limit of 25 mrem/yr total body and 75 mrem per year organ (thyroid) from all sources. Again, the calculated dose and dose rate includes all inputs including interim spent fuel storage, low level radwaste storage and hydrogen injection.

Provide an estimate of thc increasing number of High Radiological Areas, locked High Radiological Areas and the increase in person-rem per year.

It is estimated that an additional 10-15 rooms may become high radiation areas. The bulk of these are the reactor feed pump turbine rooms. There is a potential that the RHR pump rooms may become a high radiation area due to crud relocation. Conservatively, we believe that up to six additional areas could become locked high radiation areas as a direct result of HWC implementation. The number of additional high radiation areas will be verified during startup testing.

ATTACHMENTTO PLA-4607 Page 2 of 6 Estimates for the increase in station person-rem were determined using a factor of five increase for steam affected areas and a factor of three increase for crud affected areas. The crud affected factor was determined using crud modeling software utilizing site specific information. An approximate increase of 320 to 350 person-rem annually as a result of hydrogen injection on both units was calculated. This is conservative in that it does NOT take into account dose mitigating efforts that have been, or are planned to be implemented.

These actions include installing a condensate filtration system, cameras in steam affected areas, and shielding enhancements. Taking into account mitigating actions, the annual increase as a result of HWC implementation is projected to be reduced to about 230 to 260 person-rem in the near future, and significantly less long term as the benefits of condensate filtration are fully realized.

Describe changes planned for plant maintenance and surveillance work in and around affected areas in the turbine building and main stcam tunnels.

An additional 28 cameras (total for both units) are being installed in steam affected areas, such as the reactor, feed pump rooms and the condenser bay, to minimize the need for personnel to access these areas during operation for routine inspection and investigation activities. Purchase of a surrogate tour system is being evaluated to assist in the planning and training of plant workers to minimize the amount of time spent in the affected areas and reduce or eliminate the need for walkdowns. Hydrogen cycling/reduction is currently being evaluated to determine the best strategy for minimizing exposures for work performed at power while limiting the impact to shutdown crud fields as a result of the hydrogen cycling. Other utilities have experienced crud bursts as a result of hydrogen cycling. The crud burst can result in an increase in shutdown dose rates, negating the dose reduction benefits gained from the hydrogen injection reduction/elimination. Once the hydrogen cycling- strategy is determined, it will be incorporated into the appropriate operational procedures.

Provide the data that was used to calculate the expected increase in dose rates resulting from the operation of HWC, at the site boundary. This should also include the expected increase in dose at the site boundary.

The information requested is located in EC-ENVR-1025 and EC-ENVR-1026.

(Calculations attached)

Has a test of Hydrogen addition bccn performed? If so, please provide the results of this test. Ifno demonstration has been run, explain thc basis for amendment request.

A test of hydrogen addition has not been performed, and there are no plans to perform one.

The benefits of a hydrogen addition test were evaluated in PP8cL Study EC-CHEM-1009.

The conclusion was that the value of the additional information that would be generated was minimal and insufficient to justify the cost of a test. A number of BWRs have already

ATTACHMENTTO PLA-4607 Page 3 of6 implemented hydrogen water chemistry, and the operating experience from these plants was sufficient to support the design of the systems for Susquehanna and to perform the impact studies.

During startup testing, hydrogen injection rates will be increased incrementally. Radiation surveys and radiation monitor readings will be taken during each testing plateau to fully characterize the effect of hydrogen water chemistry. Start-up testing will generate the data that will either confirm the initial estimates, or will be used to make appropriate adjustments to accommodate hydrogen injection up to approximately 2.0 ppm Hz in feed water.

This amendment is requested because background radiation fields at the Refueling Floor Wall Exhaust and High Exhaust monitors are expected to approach or to exceed current trip or alarm setpoints under "moderate" Hydrogen Water Chemistry. The BWR Water Chemistry Guidelines (EPRI TR-103515-Rl/BWRVIP-29) define "moderate" as between 1.0 and 2.0 ppm Hydrogen injected to feedwater. For this range of injection rates, main steam line radiation is expected to be four to five times the level without hydrogen injection, based on the experience at a number of BWRs (see Figure 3-1 of the EPRI Guidelines). A radiological dose analysis was performed in Calculation EC-RADN-1021 to assess the radiological impacts of Hydrogen Water Chemistry on the process and area radiation monitors at SSES. A factor of five increase in background radiation levels was assumed for this analysis based on the industry operating experience. The results for Unit 1 are as follows (Unit 2 is expected to be similar):

Current Current Background Calculated N-16 Dose Rates Sctpoints A/B NWC HWC 5X Alarm Trip Monitor mr/h mr/h mr/h mr/h mr/h Refueling Floor Wall 0.339/0.501 1.61 8.04 51.0 Exhaust (RE-1N010A,B)

Refueling Floor High 0.054/0.063 0.085 0.43 51.0 Exhaust (RE-1NO ISA,B)

Railroad Access Shaft 0.170/0.355 <0.01 <0.01 s1.0 Exhaust (RE-1N016A,B)

The Railroad Access Shaft Exhaust monitors will not be affected by Hydrogen Water Chemistry. They were included in the request to maintain a consistent basis for establishing trip setpoints for the radiation monitors in Technical Specifications. The bases for the proposed setpoints are discussed in the response to Question 8.

ATTACHMENTTO PLA-4607 Page4of6 With the operation of HWC, what will be the affect on the operability of the radiation monitors for the Main Steam Line? Have the sctpoints to these radiation monitors been increased to allow for HWC operation? If so, please provide the data used to calculate these setpoints and the setpoint values.

The operability of the Main Steam Line Radiation Monitors was evaluated under PP&L Studies EC-CHEM-1006 and Calculation EC-RADN-1021. The operability is not affected by Hydrogen Water Chemistry. These monitors have a range of 1 to 1,000,000 mr/h.

Under Normal Water Chemistry at 100% power, radiation levels of -500 mr/h to -1000 mr/h are detected by the four Main Steam Line Radiation Monitors. Under Hydrogen Water Chemistry, these are expected to increase to -2500 mr/h to -5000 mr/h. These levels are well within the range of the monitors.

The current trip setpoint for these monitors is 7 times the Normal Water Chemistry background at 100% power, with an allowable value of 8.4 times the Normal Water Chemistry background. The alarm setpoint (which is not in Technical Specifications) is 3.5 times background. Since HWC is expected to increase Main Steam Line Radiation Levels to approximately five times Normal Water Chemistry values, the alarm setpoint will be exceeded, but the trip and allowable values willnot, under steady-state conditions.

However, industry data indicates that a plant chemistry transient while on HWC could increase N-16 volatility further, up to 8.5 times the Normal Water Chemistry levels. With the current setpoint, this would result in closure of the Main Steam Isolation Valves (MSIV) and actuation of the Reactor Protection System (RPS), producing a unit scram.

PP&L is evaluating ways to eliminate the potential for unnecessary transients while on Hydrogen Water Chemistry. The alarm setpoint is projected to be raised to approximately three times the Hydrogen Water Chemistry background at full power, or approximately 15 times the Normal Water Chemistry background at full power. This will be sufficiently high to avoid unnecessary plant trips, but low enough to detect major fuel failure.

On what basis werc thc ncw values of the secondary containment isolation radiation monitor setpoints and allowable values determined to be acceptable? What criteria werc used for determining thc acceptance? How much has the margin been changed regarding Part 100 limits?

Provide thc justification for using the "[Final Safety Analysis Report] FSAR realistic source terms" instead of the "worst case source terms" for accident conditions that require isolation of the secondary containment in thc calculation of the revised setpoints.

Response to Questions 8 and 9: The response below answers questions 8 and 9 collectively since they are logically related.

ATTACHMENTTO PLA-4607 Page 5 of 6 In the Design Basis Fuel Handling Accident, a significant amount of activity is assumed to be released to the refueling floor, and ultimately the environment. The design functions of the secondary containment isolation radiation monitors are to isolate the refueling floor and to activate the SGTS system. The charcoal filters in SGTS reduce the iodine release from this event by a factor of 100, and therefore reduce the dose due to iodine release. The offsite dose consequences have been determined by design calculations in accordance with Regulatory Guide 1.25 requirements and assumptions. The design basis source term was used in these calculations, and provides a conservative evaluation of offsite dose. These dose consequences are shown in section 15.7.4 of the SSES FSAR.

The current radiation monitor setpoints are not related to the offsite dose consequences of a fuel handling accident. They were field set at what was thought a reasonable value above the radiation zoning criteria for the refueling floor. These low settings have required numerous bypasses to these monitors when moving irradiated components on the refueling floor. As noted in the response to Question 6, under Hydrogen Water Chemistry background radiation levels are expected to approach or exceed current alarm or trip setpoints. Therefore, it is necessary to raise the setpoints to a level that permits plant operation and provides operational flexibility. However, the setpoint must be low enough to assure that, in the event of a fuel handling accident, secondary containment isolates and SGTS initiates when necessary to keep offsite doses within regulatory limits. Establishing setpoints based on a quantifiable source term would reduce the potential for spurious activation of the monitors during normal plant evolutions, while still protecting public health and safety.

The radiation monitors will respond to the fission product activity that would be released to the refuel floor atmosphere from ruptured fuel elements. The FSAR Realistic fission product source term was selected to provide the homogeneously mixed activity concentration upon which to base the radiation level setpoint. The release of this quantity of activity, ~gt mitigation (that is, no secondary containment isolation or activation of SGTS), would produce lower offsite doses than the design basis source term with mitigation (isolation and SGTS). Therefore, a setpoint based on the realistic source term will be conservative. That setpoint will assure that secondary containment isolates and SGTS initiates when necessary to protect public health and safety. That setpoint will also be high enough to permit plant operation and to reduce the potential for spurious activation.

The determination of analytical setpoint was performed in PP&L calculation EC-RADN-0531. These analytical setpoints were then adjusted downward to account for instrumentation accuracy factors. The proposed amendment request reflects these adjustments.

ATTACHMENTTO PLA-4607 Page 6 of 6 Note that dose consequences associated with the Design Basis Fuel Handling Accident (as stated in current FSAR section 15.7.4) are the licensing basis commitment. The offsite dose consequences will remain below the calculated Design Basis dose consequences even without credit for SGTS system function while using the realistic source term to determine the monitor setpoints. As such, the calculated setpoints as based on the realistic source term were judged as both conservative and acceptable, and no margin with respect to the Design Basis Fuel Handling Accident was affected.

10. Provide the quantitative calculations for thc analytical limit which utilized FSAR realistic source terms. The information provided should include the actual calculations and results.

PP&L Calculations EC-RADN-0531, EC-ENVR-1025, and EC-ENVR-1026 are enclosed for review as deemed necessary by NRC staff..

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NUCLEAR ENGINEERING File ¹ R2-1 629 CALCULATIONI STUDY COVER SHEET and

1. Page 1 of121 NUCLEAR RECORDS TRANSMITTALSHEET

'2. TYPE:

6. TRANSMITTAL¹:

>9. DESCRIPTION:

'0CALO d

>3. NUMBER:

>6. UNIT: 3 EC-ENVR-1026

• >T. QUALITYCLASS: R

>4. REVISION:

'>6. DISCIPLINE:

ISFSI FUEL CYCLE 40CFR190 OFFSITE DOSE CALCULATIONS 0

R SUPERSEDED BY: EC-

10. Alternate Number. 11. Cycle: .

N/A 12: Computer Code or Model used: SECTION 3 Picks P Disks g Am'I 3

13. Application: SSES ISFSI

'>14 Affected Systems: 089

• 'fN/A then line 15 is mandatory.

'>15. NON-SYSTEM DESIGNATOR: ENVR

16. Affected Documents:

17.

References:

SECTION 6.0

18. Equipment / Component ¹:

19. DBD Number.

>20. PREPARED BY >21. REVIEWED BY Print Name R.K. Barcla Print Name R. F. El Si nature Si nature

>22. APPROVED BY/ DATE 23."ACCEPTED BY PP&L/ TE Print Name C.J Kalter Print Name Sl nature Si nature.

COMP E 8 CLEAR RECORDS RECEIVED NR-DCS SIGNATURE/DAT OCT 04 f996 ADD A NEW COVER PAGE FOR EACH REVISION NUC~R HO&@NFi ds FORM NEPhhQA4221-1, RavlsIan 1 >R S 9705200147 970509 PDR ADQCK 050003S7 P PDR s

,/

PP&L CALCULATIONSHEET ept. 0 s. Tech. PROJECT SSES ISFSI 'ale. No. EC-ENVR-1025 y iate 9/12/96 esigned By FUEL CYCLE 40CFR190 OFFSITE DOSE CALC.

Rev. 0 Checked By Sh. No. 2 of ~1 TABLE OF CONTENTS Section Description Page 1.0 OB JECTIVE .7

2.0 CONCLUSION

S AND RECOMMENDATIONS 3.0 ASSUIVIPTIONS/INPUTS 4.0 METHOD 29 4.1 Modeling Methodology Used to Obtain MICROSKYSHINE Exposure Rates from Turbine and Main Steam components for Both Operating Units 29

. 42 Determination of MICROSKYSHINE Input Parameters for Turbine/Main Steam Components 29 4.3 MICROSKYSHINE Calculations: Turbine Building 47 4.4 MICROSKYSHINE Calculations: Condensate Storage Tanks (CSTs);

Shielding from Ground between Unit 2 CST and Sector 7 Receiver 52 4.5- Direct Shine (MICROSHIELD) Calculations from Turbine Building Components 57 4.6 Airborne ENuent Data Base Creation 85.

4.7 Airborne ENuent Dose Calculation to Selected Members of the Public 93 4.8 I iquid ENuent Data Base Creation 99 4.9 Liquid ENuent Dose Calculation to Selected Members of the Public 107 4.10 Shine from Low Level Radwaste Handing Facility (LLRWHF) 108

PP8 L CALCULATIONSHEET ept. Jlp s. Tech. PROJECT SSESISPSI C I .N . EC-ENVRICEE ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 3 of 121 Section Description Page 4.11'kyshine from Temporary Laundry Facility (TLF) 4.12 Shine from ISFSI Storage and Transport 4.13 Sum of SSES Fuel Cycle Dose Contributions at Off Site Locations 5.0 RESULTS 115

6.0 REFERENCES

116 List of Tables Table 3-1 N-16 Source Activities in Turbine/Main Steam Components 22

[Includes Application of Moderate Hydrogen Water Chemistry (HWC): based on reference 6.1 Sections 5.2.1-5.2.7 (NWC)]

able 3-2: MICROSKYSHINE Turbine/Main Steam Component Geometry 22 (reference 6.1 Section 5.2)

Table 3-.3; MICROSHIELD Turbine/Main Steam Component Geometry 22 (reference 6.1 Section 5.2)

Table 34: Condensate Storage Tank Isotopic Inventory 23 (references 6.1 and 6.40.1)

Table 3-5: Distances from Building Walls and CSTsmOffsite Receivers 27 Table 3-6: Dose Rates (n+ y) from ISFSI Storage-pOffsite Receivers 27 (Base Case Analysis: reference 6.29)

Table 3-7: Dose Rates (n+ y) from DSC Transport '8 (reference 6.42: Included as Attachment 4)

Table 3N: Skyshine Exposure Rates (mR/hr) and Annual Integrated Dose 28 (mrem) from. Temporary Laundry Facility to Four Offsite Locations (Ref. 6.41)

PP8 L CALCULATIONSHEET ept. 0 s Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. of 121 Description

'ection Page Table 4-1 a; MICROSKYSHINE Run Results: Turbine Building Sources 48 Receiver: Resident Sector 7 (Location 1)

Table 4-1b: MICROSKYSHINE Run Results: Turbine Building Sources 49 Receiver: Towers Club (Location 2)

Table 4-1 c: MICROSKYSHINE Run Results: Turbine Building Sources 50 Receiver. Resident Sector 16 (Location 3)

Table 4-'1 d: MICROSKYSHINE Run Results: Turbine Building sources 51 Receiver: Resident Sector 12 (Location 4)

Table 4-2a: Direct Line of Sight Shielding of Turbine Building Sourcesm 59 Receiver: Sector 7 Residence (Location 1) able 4-2b: Direct Line of Sight Shielding of Turbine Building Sources-+ 60 Receiver: Sector 16 Residence (Location 3)

Table 4-2c: MICROSHIELD Run Results: Turbine Building Sources 84 Table 4-3: Airborne Effiuent Data Base from 1982-1994 inclusive (Ci) 86 (Page1 of 7)

Table 4-4a: Airborne Effluent Dose (mrem), Location 1 95 Table 4Mb: Airborne Effiuent Dose (mrem), Location 2 96 Table 4-4c: Airborne Effiuent Dose (mrem), Location 3 97 Table 44d: Airborne Effiuent Dose (mrem), Location 4 98 Table 4-5: Liquid Effiuent Data Base from 1982-1 994 Inclusive (Ci) 100 (Page 1 of 7)

Table 4: Shine to Off Site Locations from LLRWHF Sources 113

<'ble 4-7: Sum of SSES Fuel Cycle Dose Contributors at Off Site Locations 113

PP8L CALCULATIONSHEET pL Jlg.Td PROJECT SSES ISFSI Gale. No. EC-ENVR-1025

.rate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 5 of ~11 List of Figures Figure 3-1: Susquehanna Steam Electric Station: Off Site Dose 24 Receiver Locations Figure 3-2: Figure deleted. 25 Figure 3-3: ,: Unit 1 CST with Relation to Turbine Building Wall From C-1008 26 Rev. 8 (Ref. 6.32.4)

~ \

Figure 4-1: 'cale Model of U2 CST~Sector 7 Residence (Location 1) 114 Dose Point Showing Line of Sight Convergence at Grade List of Attachments - Letter from R.K. Barclay, PPB L, to Timothy J. Schott, Halliburton NUS, "Request for Atmospheric Dispersion Estimates in Support of ISFSI Calculation", PLI-81248, 12/8/95. (3 pp.)(Ref. 6.27) - Letter from Timothy J. Schott, Halliburton NUS, to R.K. Barclay, PPBL, transmitting atmospheric dispersion calculations, 12/11/95 (3 pp.)(Ref. 6.28) - Letter from J.L. Simpson, GE Nuclear Energy, to J.C. Pacer, PPBL, "Review of the Susquehanna Steam Electric Station Assessment of Impact of Hydrogen Water Chemistry on Radiation Field Buildup",11/7/95 (5 pp,')(Ref. 6.30) - Letter from Norman Eng, VECTRA Technologies, to Kevin Kelenski, PP8L, "Total Dose Rate Contributed by NUHOMS Transfer Cask During Transfer to the Susquehanna ISFSI Site": VECTRA Letter No. 16-77-96-052, 5/21/96 (4 pp.)(Ref.

6.42) - MICROSKYSHINE Results for U1/U2 Turbine Building Components to Residence in Sector 7 (Location 1)(57 pp.)

ttachment 6- MICROSKYSHINE Results for U1/U2 Turbine Building Components to Towers Club (Location 2)(57 pp.)

pl.

ate

~T 9/12/96 PP8L CALCULATIONSHEET PROJECT SSES ISFSI FUEL CYCLE 40CFR190 Gale. No. EC-ENVR-1025 Rev. 0 .

esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 6 of ~12 - MICROSKYSHINE Results for U1/U2 Turbine Building Components to Residence in Sector 16 (Location 3)(57 pp.) - MICROSKYSHINE Results for U1/U2 Turbine Building Components to Residence in Sector 12 (Location 4)(57 pp.) - Unit 1 CST Skyshine Exposure Rates:

Sector 7 Resident (Location 1)

Towers Club (Location 2)

Sector 16 Resident (Location 3)

Sector 12 Resident (Location 4)(9 pp.) 0- Unit 2 CST Skyshine Exposure Rates; Sector 7 Resident (Location 1)

Towers Club (Location 2)

Sector 16 Resident (Location 3)

Sector 12 Resident (Location 4)(9 pp.) 1- MICROSHIELD Results for Unit 2 Tb~ Sector 7 Resident (Location 1) (13 pp.) 2- MICROSHIELD Results for Unit 1 Tb~ Sector 16 Resident (Location.16) (17 pp.)z 3- GASPAR Input and Output: Airborne Effluent Dose (mrem), Off Site Locations, Year Source Terms (11 pp.) for'aximum 4- LADTAP II Input and Output; Maximum Year (10 pp.) 5- Critical Line Number Records, DATAFILE.WK1/1109AD.WK1 Output; Maximum Year and Summary Output; Maximum Year (8 pp.) 6- MICROSHIELD Results for LLRWHF Front Row CD LSM Shine:

Sector 7 Residence (Location 1: Without effect of U2 Cooling Tower Shielding)

Sector 7 Residence (Location 1: With effect of U2 Cooling Tower Shielding)

Towers Club (Location 2)

Sector 16 Residence (Locatiori 3'. Without effect of North-Wall Shielding)

Sector 16 Residence (Location 3; With effect of North Wall Shielding)

Sector 12 Residence (Location 4) (13 pp.)

'I ttachment 17- Letter from R.K. Barclay to KJ. Kelenski, "Assumptions Regarding Movement of Spent Fuel to ISFSI", PLI-82098, 6/11/96 (Ref. 6.58) (3 pp.)

PP8 L C'ALCULATIONSHEET ept. 0 s. Tech. PROJECT SSES ISFSI, Calc. No. EC-ENVR-1025 rate 9/12/96 Designed By FUEL CYCLE 40CFR190, OFFSITE DOSE CALC.

Rev. 0 Checked By Sh. No. 7 of 1.0, OBJECTIVE The purpose of this calculation is to determine the annual dose to off site receivers from all SSES fuel cycle components [as applied to the Independent Spent Fuel Storage Installation (ISFSI)]. By calculating the annual dose to members of the public at various selcted locations, the maximum annual dose to any member of the public can be determined. Doses calculated herein include'shine contributions from ISFSI storage and transportation on-site, Low Level Radwaste Handling Facility (LLRWHF) storage and transportation on-site, shine from condensate storage tanks (CSTs), shine from the turbine building under full power hydrogen water chemistry (HWC) conditions-~

and dose from liquid and gaseous effluent under bounding conditions.

2.0 CONCLUSION

S AND RECOMMENDATIONS 2.1 Based on results in Section 5.0, the maximum annual off site dose from SSES fuel cycle components, including storage and transport to the ISFSI, is 5.29 mrem total body and 6.26 mrem organ. These doses, which are calculated for the residence in Sector 7 (0.34 miles S.E. of the plant) are approximately one-fifth the 40 CFR 190,limit (reference 6,26.1) of 25 mrem/yr total body/other organ. The thyroid dose limit is 75 mrem/yr: thyroid dose is bounded by the stated maximum organ dose. The majority of this dose (-90%) is attributed to turbine building direct and skyshine radiation. Off site dose results calculated herein are generally consistent with the predominant N-16 contribution from HWC to the turbine building shine source term.

2.2. The maximum annual off site dose from transport of spent fuel casks to the

'ISFSI is 9.00 e-3 mrem (applied to all locations). The maximum annual off site dose from storage of the casks at the ISFSI is 1.50 mrem (Towers Club:

Location 2). The ISFSI transport and storage components of the total body dose, when summed together (1.50+ 9.00e%3 = 1.51 mrem) are -40% of the total dose from all sources (3.90 mrem) at the Towers Club. For the same location, the ISFSI components are -30% of the summed organ dose (5.21 mrem). The ISFSI dose components, total body and organ sums are not significant against the 40 CFR 190 (reference 6.26.1) limit of 25 mrem/yr total body/organ.

PP&L CALCULATIONSHEET ept. O s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 10/1/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 8 of ~11 3.0 ASSUMPTIONS/INPUTS 3.1 Turbine component and steam source modeling is derived from PP8L Calculation EC-HPHY-0518 (reference 6.1). This calculation considers the exposure rate contribution from the HP and LP turbines, moisture separators, CIVs, 42'ross-around piping from the moisture separators to the CIVs, CIV~LP turbine piping, and the vertical and horizontal HP turbine inlet piping runs. These references conservatively assume all source activity to be N-16, rather than include the contribution from C-15. (The C-15 constituent has lower photon energies than N;16, and has a half-life (2.45 seconds) less than or equal to the steam transit times to the turbine components). N-16 source activities for the turbine/main steam comporients for hydrogen water chemistry (HWC) applied assume a factor of five (5.0) increase compared to no hydrogen water chemistry (NWC) conditions, which is supported by reference 6.30. (HWC has little impact on C-15 levels). The source activities originally used in ref. 6.1, and with the HWC increment, are shown in Table 3-1.

3.2 Unit 1 and Unit 2 turbine component sources are assumed to be identical, except'for location, consistent with modeling in reference 6.1.

3.3 The effect of local shielding, such as the concrete cover slab over the moisture separator, is considered herein. Shielding effects of intermediate equipment and. -.

structures may also be considered when consistent with the shielding model.

3.4 N-16.sources below the operating floor (El. 729) are not considered herein.

Typically, these sources are pipes with smaller diameter than equipment on the operating floor, thus, they have smaller N-16 inventory than those on the operating floor. Exposure rates from these components will be limited by equipment on El.

729, and the heavy load-bearing floor provides additional shielding to limit the skyshine contribution from the sources below.

3.5 Layout of the turbine bay operating floor is provided in references 6.1 and 6.32.1.

These references are used to determine distances from the turbine steam sources to the turbine buildirig outside wall. Reference 6.32.3 provides information to estimate ground elevations of receiver points, used to calculate MICROSKYSHINE parameter H (vertical offset), and for elevation offsets in MICROSHIELD calculations. Ground elevation for the receiver (residence with garden) in the WSW sector 12 (Location 4) is assumed to be 700', which is consistent with elevation approximated from contour indications (ref. 6.32.3) for the nearest dose point (Towers Club: Location 2) in the same sector. Use of 700's conservative relative to a lower elevation, since the skyshine source is brought closer to the receiver (lower H value) for the Ground level elevations for other off site receivers are as follows:

700'levation.

PP &L CALCULATION-SHEET ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025

)ate 10/1/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 9 of 121 Residence sector 7 (Location 1):

sector 16 (Location 3): 600'esidence 1010'ose receiver points are assumed to occur at 6'bove ground level. Further description of offsite dose points is provided in Section 3.30.

The following physical data for turbine, main steam components and source densities are determined from reference 6.1:

3.5,1 Moisture Separator MICROSKYSHINE/MICROSHIELDdimensions (Ref. 6.1 Sections 4.12,,~

5.2.1, 5.3.1.1, Figs. 1, 3, 4; ref. 6.32.14, 6.32.15):

diameter = 10'8.5"; radius (W) = 5.35' 1.63 m.

overall length (L) = 67'3.5" = 20.51 m.

(NOTE: Unit 2 length is used since it maximizes the size of the source and its value is provided in the same references as other dimensions utilized).

center line; approximately el.

736'over slab = 0.457 m. concrete Shell thickness = 1.25" = 0.03 m. iron Source density = 0.44 g/cm'ater Bottom of concrete slab = 755'

. Moisture Separator centerline=

west moist. sep. centerlinewouter shield wall =

736'istance east m'oist. sep. centerline-+outer shield wall = 7.5'istance between west moist. sep. inner and outer shield walls = 25'"

12.5'istance Distance from west face of shield wall (inside face) ~ column line K = 1'"

Distance from east face of shield wall (inside face)~lumn J = 1.0'

0 pt.

ate

~ph.

9/12/96 PP8L CALCULATIONSHEET PROJECT SSES ISFSI FUEL CYCLE 40CFR190 Calc. No. EC-ENVR-1025 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 10 of ~12 3.5.2 Cross-around Piping (CAP)(Ref. 6.1 Sections 4.13 and 5.2.2):

Instead of modeling each CAP segment separately as cylinders, the piping for each Moisture Separator. segment is modeled as an equivalent point source, located as shown in Ref. 6.1, Figure 4. A review of piping drawings indicates all four Moisture Separators have similar piping arrangements.

The Ref. 6.1 detailed model is based on the Unit 2 west Moisture Separator (2B2T1048). The model in Ref. 6.1 is conservative since it reduces the cross around piping to a point source, with no credit taken for shieldin~om piping material.

The skyshine dose rate increases as the source point moves up, because a larger scattering cone results above the side shield walls. The elevation of the source point is conservatively taken as the elevation of the center line of the upper horizontal run of piping, i.e., at 749'. The source point is positioned as shown in Ref. 6.1 Figure 4; this location is nominally the geometric center of the piping (plan view) and tends to move the source away from the outer shield walls (which is conservative).

MICROSKYSHINE/MICROSHIELDdimensions (Ref. 6.1, Sections 5.2.2 and 5.3.1.2 Fig. 4) geometry 14, "Point Source in a Rectangular Enclosure" Cover slab = 1.5' 0.457 m concrete Bottom of cover slab:

wall = 0.375" = 0.01 m iron 755'ipe Quadrature order = 32,(Ref. 6.1 Attachment 2page 2-14)

Source Density: not applicable (modeled as point source)

R1 (Distance; center'of sources+shield wall: Ref. 6.1 Section 5.3.1.2)

=3.2m. (Units 1 and 2, East)

=4.5m. (Units1 and2, West)

R2 (Distance; center of sourcemshield wall: Ref. 6.1 Section 5.3.1.2)

=18.4m. (Unit1, East and West)

=11.4m, (Unit2, Eastand West)

W (Distance between right and left wail: Ref. 6.1 Fig..4):

= 14.75'+ 10.4' 25.15' 7.7 m.

PPRL CALCULATIONSHEET ept. 0 s. Tech.

• PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 11 of ~1 L (Distance between far and near wall: Ref. 6.1 Fig. 3):

= 97.5' 29.7 m.

MICROSHIELD parameters (Ref. 6.1 Section 5.4.1.2) geometry 1, "Point Source-Slab Shields" T1 (air space between source point and west shield wall) = 14.75' 450 cm T2 (steel pipe wall) = 0.375" = 0.953 cm T3 (concrete shield wall) = 3' 91 cm 3.5.3 Combined Intermediate Valves (CIVs)(Ref. 6.1 Sections 4.14, 5.2.3, 5;3.1.3)

The CIVs are inside the moisture separator rooms, but only partially shill'ded by the shield panels along column lines Gd and J. The piping from the-CIVs-+LP Turbines runs from the inside of the Moisture Separator room to the LP Turbine outside the room. The CIVs are modeled as vertical cylinders with dimensions as stated in Ref. 6.1 Section 4.14. Since IVllCROSKYSHINE does not address a partial shield wall configuration, the CIVs are assumed to be located on the turbine side of the shield panels, as shown in Ref 6.1 Figure 4. Neither the effect of shielding nor scattering bg the turbines is considered.

MICROSKYSHINE/MICROSHIELDdimensions (Ref. 6.1 Sections 5.2.3, '~

5.3.1.3)

Source Radius. = 3' 0.91 m Source Height = 64" = 1.63 m R'i (Distance; center of sourcemshield wall)

= 1 m for "near" CIVs (e.g.: west CIVs for dose points located to the west, or east CIVs for dose points located to the east)

= 11 1 m for "far" CIVs (e.g.: east CIVs for dose points located to the west,

~

or west CIVs for dose points located to the east)

Cover Slab: none Pipe wall = 0.05 m iron Y = 16,9' 5.2 m Source Density: 6.4 e%3 g/cm'ater

=

Top of shield wall 756.5'

PP&L CALCULATIONSHEET ept. 0 s. Tech. PROJECT SSES ISFSI 'alc. No. EC-ENVR-1025 iate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0.

esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 12 of 121 3.5.4 CIV Piping Model (Ref. 6.1 Section 5.2.4):

Piping from the CIVs to the LP Turbines is shown in Ref. 6.1 Figure 4. The N-16 inventory of the piping elbow as well as the horizontal pipe run is assumed to be in a horizontal cylinder length equal to that of the horizontal run with its terminus at the outside edge of the partial shield wall. As discussed in Section 3.5.3 for the CIVs, locating the source outside the Moisture Separator Room is conservative, Neither shielding nor the -.

scattering provided by the turbines is considered.

MICROSKYSHINE/MICROSHIELDdimensions (Ref. 6.1 Section 5.2.4g Source length = 10' 3.05 m.

Radius = 0.52 m.

Cover slab: none Pipe wall = 0.375" = 0.01 m. (iron)

Y = 25,75' 7.8 m.

Source density: 6.4 e-03 g/cm'ater 3.5.5 HP Turbine Model MICROSKYSHINE/MICROSHIELDdimensions (Ref. 6.1 Section 5.2.5):

Radius = 1.53 m = 5'.

Source length = 21' 6.4 m.

Cover slab: none HPT shell = 3" = 0.0762 m. (iron)

Y = 20' 6.1 m.

Source Density: 4.17 g/cm'ater 3.5.6 LP Turbine Model MICROSKYSHINE/MICROSHIELDdimensions (Ref. 6.1 Sections 5.2.6, 5.3.1.6):

Radius = 3.6 m. =

length = 28.5' 8.68 m.

11.8'ource Cover slab: none LPT shell = 3.18 cm. = 0.031 8 m. (iron)

Y =15.5'4.7m.

Source densit: 2.0 /cm'ater

PP8L CALCULATIONSHEET ept. 0 s Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 13 of ~12 R1 2.5 m R2 9.7 m.

3.5.7 HPT Inlet Piping MICROSKYSHINE/MICROSHIELDdimensions (Ref. 6.1, Section 5.2.7, Fig.

6, Section 5.3.1.7)

(HPT Inlet Vertical Segment)

Source radius = 12.75" = 0.32 m.

Source length = 8.25' 2.5 m.

Cover slab: none Pipe wall = 1.25" = 0.032 m. iron R1: Distance between source and shield wall:

R1 = 3.3 m. for west piping R1 = 8.8 m. for east piping Y = 16.75' 5.1 m.

Source density: 3.32 e-02 g/cm'ater (HPT Inlet Horizontal Segment)

Source radius = 12.75" = 0.32 m.

Source length = 11' 3.4 m.; height above Tb deck = 11.75'over slab: none Pipe wall = 1.25" = 0.032 m. iron R1/R2: Distance between source and shield wall:

R1 = R2 = 3.0 m. for west piping R1 = R2 = 6.1 m. for east piping Y = 13.25' 4.0m.

Source density: 3.32 e-02 g/cm'ater 3.6 Shield material densities used are those from the MICROSKYSHINE and MICROSHIELD codes:

Iron: 7.86 g/cm'oncrete:2.35 g/cm'

PP&L CALCULATIONSHEET ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No, EC-ENVR-1025 iate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. of 1

3.7 The turbine and main steam component geometries as represented in MICROSKYSHINE are shown in Table 3-2 (reference 6.1).

3.8 Turbine and main steam component geometries from reference 6.1, as represented in MICROSHIELD, are shown in Table 3-3. MICROSHIELD geometries for additional components (not treated in ref. 6.1) are stated for the cases as developed in Section 4.5.

3.9 'In reference 6.1, use of the center CIVs/piping (¹ 2 and ¹5) to model all CIVs and associated piping is justified. The use of the center LP turbine to represent all three components is also justified in reference 6.1. In that reference, the results of the 6V piping calculations, and the LP turbines are multiplied by three to include all components. '3 3.10 In reference 6.1, all MICROSKYSHINE calculations were performed using air as the buildup medium. Buildup factors are therefore based on air for calculations herein.

3.11 Airborne effluent quantities from the period September 1982 (SSES initial startup)..

through December 1994 are determined from references 6.34.24 Tables 2 and 3; liquid effluent quantities are determined from the same references Tables 4 and 5.

The earlier reference 6.3-6.18 tables list a range (designated by lower and uppei.'a values) for many isotope activities. The first value in the range includes only activity positively detected at the 95% confidence level. This value will be used in effluent data base compilation, The second value includes detected activity plus the Lover Limit of Detection (LLD) values of any samples in which activity was not detected. at the 95% confidence level. The higher value in the range is not an actual description of the released quantity. A value of zero is used for isotopes not positively identified (i.e. <LLD), which maintains consistency with the later references.

3.12 For periods beginning with the January-June 1984 Semiannual Effluent and Waste Disposal Report (ref. 6.6), estimated airborne and liquid effluent data are updated using data provided in,the subsequent SAE8WD period (this approach was also Used in reference 6.2). The following updates are made for airborne effluent:

1. Qtr, 2, 1984 (Sr-89): 3.33e-06 Ci Ref. 6.7 Table 11

2. Qtr. 4, 1984 (Sr-89): 6.75e-06 Ci Ref, 6.8 Table 11

3. Qtr. 4, 1987 (Sr-89): 1.09e-06 Ci Ref. 6.14 Table 11

4. Qtr. 4, 1989 (Sr-89): 6.69e%7 Ci Ref. 6.18 Table 16

q pt.

,ate

~~..

9/12/96 PP&L CALCULATiONSHEET PROJECT SSES ISFSI FUEL CYCLE 40CFR190 Gale. No. EC-ENVR-1025 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 121 The following updates are made for liquid effluent:

1. Qtr. 4, 1985 (Cr-51): 1.31 e-03 Ci Ref. 6.10 Table 11

2. Qtr. 4, 1990 (Fe-55): 1.06 e-02 Ci Ref. 6.20 Table 17

3. Qtr. 4, 1991 (Fe-55): 3.13 e-03 Ci Ref. 6.22 Table 15 4 Qtr. 4, 1992 (Fe-55): 5.70 E-03 Ci Ref. 6.24 Table 15 3.13 Dispersion (X/Q) and deposition (D/Q) values are determined from reference 6.28 (Attachment 2) for the off site dose points of interest as follows:

Location Direction Miles Meters XIQ X/Q DEC X/Q DEC+ DEP D/Q 0.34 551 3.433e-06 3.430e-06 3.201 e-06 2.621e-08 WSW 0.41 659 5.294e-05 5.281 e-05 4.888e-05 7.722e48 NNW 0.67 1082 5.080e-06 5.060e-06 4.549e-06 1.331e-0 WSW 1.04 1681 1.447e-05 1.437e-05 1.260e-05 2.074 e-08 Where X/Q = relative concentration (sec/m'); no decay, undepleted; X/Q DEC = decayed concentration (sec/m'); half-life 2.26 days, undepleted; X/Q DEC + DEP = decayed and depleted concentration (sec/m'); half-life 8 days; D/Q = relative deposition rate (m').

3.14 Releases of all airborne effluent are assumed to occur continuously throughout the period (year). Decay of radioiodine/particulate effluent with inhalation and immersion

. doses is considered by using the decayed, depleted dispersion factors (X/Q DE

+DEP) at each dose receiver location. No credit is taken for further decay of radioiodine or particulate once deposited (ground shine calculations).

3.15 Credit is taken for shielding from U2 cooling tower for direct shine from the LLRWHF at location 1 (Sector 7 residence). Credit is also taken for the north wall in the LLRWHF for direct shine to location 3 (Sector 16 residence).

3.16 The cooling tower blowdown rate used for the liquid effluent dose calculation = 5.50 e3. GPM (12.3 CFS). This value represents the minimum permitted by procedure (reference 6.38). Sufficient conservatism is lent to the liquid dose calculation by use of the minimum cooling tower blowdown rate combined with the maximum activity for each isotope in the source term.

pL

>ate

~Td 9/12/96 PP8 L CALCULATIONSHEET PROJECT .SSES ISFSI FUEL CYCLE 40CFR190 Gale. No. 'C-ENVR-1025 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 16 of ~1 3.17 Condensate Storage Tank (CST) physical data are determined from reference 6.1 Section 5.6 (except for R1 as indicated) as follows:

diameter = 40'radius = 20' 6.1 m.)

effective height = 32' = 9.75 m)

Parameter T1 (Thickness of concrete slab cover): = 0.0 m, Parameter T2 (Thickness of second shield): = 0.0 m.

R1: Distance between source center and shield wall; reactor or turbine buttdtnq R1 = 32.75' 9.98 m. U1 CSTwSector 7 Res. (Fig. 3-3)

R1 = 38.5' 11.74 m. U1, U2 CST-+ TOWERS CLUB, Sec. 12, 16 Res (Fig.9-3)

Parameter W; Radius of source W 6.1 m.

Parameter L: Length of source 9.75 m.

Isotopic inventory for shielding purposes is determined from reference 6.40,1. This same inventory (shown in Table 3-4) was used for MICROSKYSHINE calculations in reference 6.1. Six isotopes from ref. 6.40.1 are not available in the MICROSKYSHINE library; these are: Cs-140, Cs-141, Sr-94, Y-94, Y-95 and Rb-1.

The half-lives of these nuclides are short (< 10 minutes), and the sum of their stated activity is only 2% of that in the ref. 6.40.1 CST source term. Thus, sufficient justification exists to omit these six species from consideration in MICROSKYSHlNE calculations for the CST. Ba-.1 37m is used rather than Cs-1 37 in the source term, since gamma emissions are associated with Ba-137m, No shielding is available above the CSTs; none is applied for any skyshine calculations in Section 4.4. Grade elevation of both CSTs is 670'references 6.32.4 and 6.32.5),

3,18 References 6.32.7, -8, and -9 are used to determine that the edge of the site grade

=-

in the southeast direction ends at the south access road. Reference 6,32.3, which shows the entire SSES site, is used to scale the distance to the road on the line to the Sector 7 residence. This distance is determined to be 1000 ft, and is used in the analysis of the direct shine path from the Unit 2 CST to this location (Section 4.4.6).

PP8 L CALCULATIONSHEET gept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENYR-1025

)ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 17 of ~12 3.19 Dose rates (gamma and neutron) from high-level waste storage in the ISFSI, using the fully occupied 2010 Scenario with 71 loaded storage modules, have been calculated (reference 6.29) for numerous off site points of interest, including those analyzed herein. Reference 6.29 recommends the use of base case dose rates in the calculation for licensing purposes. Base case dose rates, using 10 year old fuel (Ref. 6.58) from ISFSI storage applicable to this calculation are shown in Table 34.

3.20 Dose rates (gamma plus neutron) from transported DSCs are shown in Table 3.7 (reference 6.42: Included as Attachment 4). Five (5) DSCs, containing spent fuel with a ten year cooling time, are assumed to transported each year). It is assuayd that thirty (30) minutes is required to transport a DSC from the SSES Radwaste Building to the ISFSI (reference 6.58: included as Attachment 21).

3.21 The occupancy factor of the Towers Club is assumed to be 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />s/week, or 0.24.

The occupancy factor for residences in Sectors 7, 12 and 16 is assumed to be unity, equivalent to 8?60 hrs/yr continuous exposure. Occupancy is considered in calculation of the annual integrated dose from fuel cycle components (Section 4.13).

3.22 Doses from liquid effluent are determined at the outfall (fish ingestion and shoreline exposure) and from drinking water from the Danville intake (nearest downriver intake point), according to methodology and parameters in the SSES ODCM (reference~

6.37). Input parameters for LADTAP II (Section 4.9) are obtained from reference 6.59 Attachment F, as follows:

Shorewidth factor: 0.2 Transit time for shoreline (hr): 1 0--

Dilution factor, aquatic foods: 15.9 Transit time for fish (hr): 25 Dilution factor, drinking water: 321 'ransit time for drinking water (hr): 25.8 Dilution factor, shoreline: 15.9 3,23 The skyshine contribution from the Temporary Laundry Facility to the four off site dose receivers is determined from reference 6.41, and is shown in Table 3-8.

I 3.24 From reference 6.48, the DAW Reduction System facility contains a maximum of 30 mCi of stored activity, with a realistic estimate of one-tenth that amount (3 mCi total)

Based on this activity, no shine calculations to members of the public will be performed, since the off site dose from skyshine will be bounded by the substantially i

greater inventory limit of the Temporary Laundry Facility. The total activity in the effluent/skyshine source term for the Temporary Laundry facility is 1.65 Ci (reference i 6.41) Table 4-3c), or approximately fifty (50) times that of the maximum in the DAW facility.

PP&L CALCULATIONSHEET pt. Jht . T PROJECT SSES ISFSI Gale. No. EC-ENVR-1025

>ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 18 of ~12 3.25 Per Reference 6.49, "...there are no radioactive wastes generated by the storage of spent fuel in a NUHOMS ISFSI. The radioactive wastes generated in the plant's fuel building during DSC loading and closure operations are handled and processed using existing plant facilities and procedures...The small volumes of these (gaseous, liquid and solid) wastes generated during DSC loading and closure operations in the plant's fuel (reactor) building have no significant impact on the ability of existing plant facilities to handle and process them". The operation of the ISFSI does not introduce a new airborne or liquid release point. The storage and transport of spent fuel at the ISFSI does not 'significantly increase airborne or liquid effluent above quantities routinely released from other fuel cycle operations at SSES.

3.26 Per Ref. 6.58, calculations for dose rate conributions from turbine components ace to be based on 3441 MWt. Ref. 6.1, Section 4.4 states the effects of power uprate were included in the development of the source terms, which corresponds to a power uprate level of 3441 MWt (Ref. 6.60).

3.27 The Unit 2 Cooling Tower is assumed to have a minimum thickness of 16" concrete (through two sides), per reference 6.1 Section 4.10.

3.28 Condensate demineralizer HICs in Liner Storage Modules (LSMs) are assumed to have a 7x2 orientation on the south face of the LLRWHF, and a 23x2 orientation on the east face, per reference 6.50. The south face model is considered for exposucy rate calculations to the residents in Sectors 12 and 16, and to the Towers Club (Sector 16 residence is to the north of the LLRWHF, but the CD/LSM configuration is shown as a symmetrical array (longitudinal and lateral axes) in reference 6.51, which means the north face of the CD/LSM configuration is identical to the south) .

The east face model is considered for exposure rate calculations to the resident in Sector 7, since this residence occurs to the east of the facility.

3.29 Base MICROSHIELD parameters for the condensate demineralizer radwaste container in concrete liner storage module (CD LSM) are taken from reference 6.1, as follows:

L (source length) = 170.66 cm Y (dose point hegiht from base) = 85.33 cm

.T1 (source cylinder radius: WATER) = . 93.35 cm T2 (second shield: LEAD) = 0.14 cm T3 (third shield: AIR) = . 5.57 cm T4 (fourth shield; CONCRETE) = 43.18 cm T5 (fifth shield): not used X sum of shields no additional distance = 142.5 cm

PP8 L CALCULATIONSHEET Qept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 iate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 19 of 122 LSIV!m Outer wall distances (reference 6.50):

South: 35'10.67 m)

East: 50'15.24 m)

North: this direction is not evaluated in reference 6.50, however, same value as South wall will be used (35'), since it is the lesser (more conservative) of the two used determination of X (Section 4.10.2).

Additional information (reference 6.52):

Source density: 0.740 g/cm'ater Radionuclide inventory (decayed CD waste):

Isoto e Activit Ci Isoto e Activit Ci Ba-137m 2.59 e-02 1-129 1.09 e-03 Cr-51 3.17 e-04 Sb-124 2.32 e-05 Fe-59 9.49 e-04 Co-60 1.12 e+00 Mn-54 1.66 e-01 Fe-55 1.40 e+00 Co-58 3.49 e-03 1-1 31 8.45 e-06 Cs-1 34 9.88 e-03 Zn5 5.67 e-02 3.30 Four off site locations, where members of the public are considered to reside or work were selected for atmospheric dispersion calculations to be performed by the PP%.

meteorglogical services consultant (reference 6.27). These locations were chosen under the assumption that they are conservatively representative. Location 1, in Sector 7, was chosen due its proximity to the site in the east direction. Location 2, the Towers Club, is the nearest location where members of the public are employed.

Location 3 was chosen since it lies close to the plant within the site boundary, and it represents a point not shielded substantially by cooling towers or the reactor building. Location 4, a residence in Sector 12, has a garden where the deposition pathway (ingestion) must also be considered.

PP8 L CALCULATIONSHEET

-Oept. O s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 rate 9/1 2/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 20 of 121 3.31 Distances from site locations, such as turbine buildings, CSTs, LLRWHF and the ISFSI to off site dose points are estimated by scaling from a map fo the Susquehanna Steam Electric Station (reference 6.27). This map is shown in Figure 3-1. The distances from the site facilities to receivers are shown in Table 3-5.

Additional drawings, listed below, are used to estimate distances which are required, along with those in Table 3-5, for MICROSHIELD or MICROSKYSHINE calculations in Sections 4.2-4.5, 4.10 and 4.12.

Reference Drw Shown in Fi Descri tion Distance 6.32.4 Width of Turbine Bldg. wall 3.0'I l4 Il 4 Center U1 CST~Turbine Bldg. wall N/A Center of CIV-4-+Column G 23.0' 38.5'.32.11 3.32 Dose factors for Ag-110m airborne deposition, inhalation and vegetation ingestion*

w are taken from the SSES ODCM (reference 6.37) page 4-24, as follows:

PATHWAY AGE BONE LIVER T.BODY THYROID KIDNEY LUNG G.I. SKIN GROUP GROUND ADULT 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.97Et09 TEEN 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.97E+09 CHILD 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.97E+09 INFANT 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.40E+09 3.97E+09 VEGTBLE ADULT 9.41E+06 8.70E+06 5.17E+06 O.OOE+00 1.71E+07 O.OOE+00 3.55E+09 N/A: .

TEEN 1.42E+07 1.34E+07 8.18E+06 0.00E+00 2.56E+07 O.OOE+00 3.78E+09 NIA CHILD 3.06E+07 2.06E+07 1.65E+07 O.OOE+00 3.85E+07 O.OOEt00 2.46E+09 N/A INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N/ '.00E+00 INHAL ADULT 1.08E+04 1.00E+04 5.94E+03 0.00E+00 1.97E+04 4.63E+06 3.02E+05 N/A TEEN 1.38E+04 1.31E+04 7.99E+03 0.00E+00 2.50E+04 6.75E+06 2.73E+05 N/A CHILD 1.69E+04 1 14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 NIA INFANT 9.98E+03 7.22E+03 5.00E+03 O.OOE+00 1.09E+04 3.67E+06 3.30E+04 N/A

• Inhalation pathway: units are mrem/yr/uCi/m3 Vegetable and ground pathways: units are mrem-m2/yr/uCi/sec 3.33 The turbine shield wall (El. 729') thickness is taken from Reference 6.1 Figure 2 as follows (values are applied in Section 4.5 for direct shine slant path calculations):

East side: 3' 3" (99.1 cm)

West side: 3'- 0" (91.4 cm)

PP8 L CALCULATIONSHEET ept. 0 s. Tech. PROJECT SSES ISFSI Calc. No. 'EC-ENVR-1025 iate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE C'ALC.

Checked By Sh. No. of 3.34 Input parameters for GASPAR calculations (Section 4.7.1) are obtained from Reference 6.59, as follows:

Distance from SSES to NE corner of U.S.: 590 Fraction of year leafy vegetables are grown: 0.33 Fraction of year cows are on pasture: 0.60 Fraction of crop from garden (USDA default): 0.76 Fraction of daily intake of cows derived from pasture while on pasture: 0.42 Absolute humidity over growing season (temperature not supplied, g/m'): 9.0 Average temperature over growing season ('F); 60.2 Fraction of year goats are on pasture: 0.60 Mo

'raction of daily intake of goat from pasture while on pasture: 0.75 Fraction of year beef cattle are on pasture: 0.60 Fraction of daily intake of beef cattle derived from pasture while on pasture: 0.58

'I pt.

iate

~T 9/12/96 PP8L CALCULATIONSHFET PROJECT SSES ISFSI FUEL CYCLE 40CFR190 Gale. No. EC-ENVR-1025 Rev. 0 esigned By OFFSITE DOSE'CALC.

Checked By Sh. No. 22 of ~11 Table 3-1: N-16 Source Activities in Turbine/Main Steam Components [Includes Application of Moderate Hydrogen Water Chemistry (HWC): based on reference 6.1 Sections 5.2.1-5.2.7 (NWC)]

Turbine/Main Steam Component N-1 6 Activity (NWC) N-16 Activity (HWC)

Ci Ci HP Turbine 6.6 33.0 LP Turbine 4.0 20.0 Moisture Se arator 51.0 255.0 Cross-around Pi in 7.4 37.0 Combined Intermediate Valve CIV 1.0 5.0 CIV/LPT Inlet Pi in 1.0 5.0 HP TB Inlet Pi in: Vertical 5.5 HP TB Inlet Pi in: Horizontal 7.0 e

Table 3-2: MICROSKYSHINE Turbine/Main Steam Component Geometry (reference 6.1 Section 5.2)

Turbine/Main Steam Com onent MICROSKYSHINE Geomet HP Turbine 13: Horizontal c linder source behind wall LP Turbine 13: Horizontal c linder source behind wall Moisture Se arator 13: Horizontal c Iinder source behind wall Cross-around Pi in 1: Point source inside rectan ular enclosure Combined Intermediate Valve CIV 12: Vertical c linder volume source behind wall CIV/LPT Inlet Pi in 13: Horizontal c linder source behind wall HP TB Inlet Pi in; Vertical 12: Vertical c linder volume source behind wall HP TB Inlet Pi in: Horizontal 13: Horizontal c linder source behind wall Table 3-3: MICROSHIELD Turbine/Main Steam Component Geometry (reference 6.1 Section 5.2)

Turbine/Main Steam Com onent MICROSHIELD Geomet No./Descri tion U1/U2 HP Turbine 10: C lindrical source from end-slab shields U2 East/West Cross-around Pi in 1: Point source-slab shields U2 East/West Moisture.Se arator 10: C lindrical source from end-slab shields

PP8L CALCULATIONSHEET pi Jill . T 8 . PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 late 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No of 121 Table 3A: Condensate Storage Tank Isotopic Inventory (references 6.1 and 6.40.1*}

Nuclide Activit Ci Nuclide Activit Ci Ba-137m 1.36e-04 Ba-139 . 2.56e-02 Ba-140 1.12e-03 Ba-141 4.72e-03 Ba-142 1.78e-03 Br-83 1.72e-02 Br-84 1.10e-02 Br-85 5.05e-04 Co-58 5.67e-04 Co-60 5.68e-05 Cr-51 5.66e-05 Cs-134 9.08e5 Cs-136 6.20e-05 Cs-138 2.87e-02 Cs-139 2.91e-02 I-131 2.92e%2 I-132 1.36e-01 l-1 33 1.84e-01 l-134 1.45e-01 I-1 35 2.19e41 La-140 6.12e-05 La-141 1.89e-03 La-142 1.23e-03 Mn-56 2,87e-03 IVlo-99 2.41e-03 Na-24 1.97e-04 1.77e-05 N -239 2.62e-02 Rb-88 2.13e-03 Rb-89 1.42e%2 Rb-90 2.03e-02 Sr-89 3.78e%4 Sr-90 2.61e-05 Sr-91 9.45e-03 Sr-92 8.54e-03 Sr-93 7.89e-04 Tc-99m 2.35e-02 Tc-101 1.32e-03 Te-132 5.40e-03 W-187 3.11e-04 Y-91 1 46e-05 Y-91m 5.11e-03 Y-92 3 44e-03 Y-93 1.71e-04

• Source term does not include Cs-140, Cs-141, Sr-94, Y-S4, Y-95 and Rb-91 (Section 3.17}

PPB L CALCULATIONSHEET Dept, s Tech PRO"ECT SSES ISFSI Gale. No. EC-ENGR-1026

)ate 9/12/96 FUEL CYCLE 40CFR190 Rev 0 Designed By OFFSITE DOSE C'ALC.

Checked By Sh. No. 24 of ~1 Figure 3-1: Susquehanna Steam Electric Station:

Offsite Dose Receiver Locations

~

~ 4

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Designed By Checked By 'h.

9/12/96 Figure 3-2:

PP8L CALCULATlONSHEET PROJECT SSES ISFSl FUEL CYCLE 40CFR190 OFFSlTE DOSE CALC.

This figure deleted.

Gale. No.

No.

EC-ENVR-1025 Rev. 0 25 of ~1

PP8L CALCULATIONSHEET Dept. s. T PROJECT SSES ISFSI Gale. No. 'C-ENVR-1025

)ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 26 of Figure 3-3: Unit 1 CST with Relation to Turbine Building Wall From C-1008 Rev. 8 (Ref. 6.32.4)

SOOI-0-9988 t GdP RWPP4tJZA'~

AVWC4V 4MB ~

Wj5AlfAc5'/cC

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~~

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+A.4. wITAf~7gg pie em+>

aa ~mraamm

'LA I

NW atda AA4 C0 AQASP g4gg, JVACg

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FLATFORM 8 FLASK'-0 5'-0 hl&P/DP/OO 6 > 150

PP8L CALCULATIONSHEET

'lept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENYR-1 025

>ate 9/12/96 FUEL CYCLE 4PCFR190 Rev. 0 Designed By OFFSITE DOSE CAI C.

Checked By Sh. No. 27 of ~21 Table 3-5: Distances from Building Walls and CSTs-+Offsite Receivers Source Point Receiver Location Direct East-West North-South Distance 1 Distance 1 Distance 1 U1 CST 1. Residence: Sector 7 2 N/A 1546 1410 2.Towers Club Sector 12 2 N/A 2001 2013

3. Residence: Sector16 2 N/A 2025 2841

4. Residence: Sector 12 2 N/A 5626 2211 U2 CST 1.Residence: Sector 7 3 N/A 1546. 964 2.Towers Club Sector 12 2 N/A 2001 1575 3.Residence: Sector 16 2 N/A 2025 3349

4. Residence: Sector12 2 N/A 5626 1727 U1/U2 TB 1. Residence: Sector 7 2 N/A 1607 875 Outer Wall 2,Towers Club Sector 12 2 N/A 1857 1477 3.Residence: Sector 16 2 N/A 1786 2800 4.Residence: Sector 12 2 N/A 5304 1661 LLRWHF 1.Residence: Sector 7 2 3282.1 N/A N/A Outer Wall 2.Towers Club Sector 12 2 1393.2 N/A N/A 3.Residence: Sector 16 2 3004.0 N/A N/A 4.Residence: Sector 12 2 4121.1 N/A N/A (1) All distances measured in feet (reference Fig. 3-1) .

(2) Distance from edge of shield wallwreceiver (3) Distance from source center-+receiver Table 3-6: Dose Rates (n+ y) from ISFSI Storage-+Offsite Receivers (Base Case Analysis: reference 6.29)

Receiver Location Neutron Gamma Dose Total Dose Total Dose Dose Rate Rate Rate Rate mrem/hr mrem/hr mrem/hr mrem/ r Sector 7 SE 1.68e-07 2.96e-06 3.13e-06 2.74e-02 i'.Residence:

2.Towers Club Sector 12 WSW 1.80e-05 6.98e-04. 7.16e4 6.27e+00 3.Residence: Sector 16 NNW 7.35e%7 1.59e5 1.67e-05 1.46e-01 I 4.Residence: Sector 12 WSW 2.06e-08 3.30e-07 3.51e-07 3.07e-03 Based on continuous occupancy (8760 hrs/yr)

PP8 L CALCULATIONSHEET

'1pL jig.T*h PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 Jate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 28 of ~12 Table 3-7: Dose Rates (n+ y} from DSC Transport (reference 6.42: Included as Attachment 4)

Distance from Cask meters Dose Rate n+: mrem/hr 300 3.6e-03 450 6.1e<4 750 6.2e-05 1000 8.9e-06 1500 1.1e-06 2000 1.6e-07 2500 2.6e-08 3000 4.1e-09 3500 6.2e-10 4000 9.4e-11 4500 1.4e-11 5000 2.2e-12 5500 3.6e-13 Table 3-8: Skyshine Exposure Rates (mR/hr) and Annual Integrated Dose (mrem} from Temporary Laundry Facility to Four Offsite Locations (Ref. 6.41)

Offsite Description Skyshine Exp, Rate Skyshine Annual Integrate Location mR/hr Dose mrem" Sector 7 residence 2.338 e-08 2.05 e-04 Towers Club 7.071 e-05 6.19 e%1 3 p ~ Sector 16 residence 5.480 e-07 4.80 e-03 Sector 12 residence 6.147 e-09 5.38 e-05 Based on continuous occupancy (8760 hrs/yr)

I pt.

>ate

~h 9/12/96 PP&L CALCULATIONSHEET PROJECT SSES ISFSI FUEL CYCLE 40CFR190 OFFSITE DOSE CALC.

Gale. No. EC-ENVR-1025 Rev. 0 Designed By Checked By Sh. No. 29 of ~1 4.0 METHOD 4.1 Modeling Methodology Used to Obtain MICROSKYSHINE Exposure Rates from Turbine and Main Steam Components for Both Operating Units 4.1.1 The turbine component and source modeling has been previously performed (Reference 6.1: Section 3.1). This reference gives extensive description of sourcewdose-receiver distance calculations, which are utilized herein whenever possible to determine MICROSKYSHINE input parameters in Section 4.2.

4.1.2 Total exposure rate (U1 + U2) to the four off site locations from Turbine skyshine sources is determined as follows: 'uilding

~up Rate (U$ + U2) = Exp Rate (HP Turbine + LP Turbine + Moisture Separator +Cross-around Piping + Combined Intermediate Valves +CI VMP TB Inlet Piping + HP TB Vertical and Horizontal Inlet Piping)~<,v> Eq. 4-1 4.2 Determination of MICROSKYSHINE Input Parameters for Turbine/Main Steam Components 4.2.1 Moistur'e Separators:

3 Note; Unit 1 and Unit 2 east moisture separators are located closer to Location 1 (Sector 7 residence); Unit 1 and Unit 2 west moisture separators are located closer to Locations 2, 3 and 4 (Towers Club, Sector 16 and Sector 12 residences, respectively). This provision considers the locations of the receivers, which in all cases are offset more from the plane of the end shield walls than the 500 kV yard in reference 6.1. The wall located on column line G is the shield wall for U1/U2 west moisture separators-+off site locations 2,3 and 4. The wall located on column line Gd is the shield wall for U1/U2 west moisture separators~off site location 1. The wall located on column line J is the shield wall for U1/U2 east moisture separators off site locations 2,3 and 4. The wall located on column line K is the shield wall for the U1/U2 west moisture separators-+off $ ite location 1.

- ")ept.

sate 0 'P8L

s. Tech.

9/12/96 Designed By FUEL CYCLE CALCULATIONSHEET PROJECT SSES ISFSI 40CFR190 OFFSITE DOSE CALC.

Gale. No. EC-ENVR-1025 Rev. 0 Checked By Sh. No. 30 of 121 4.2.1.1 Parameter Y: Depth of source behind wall (Section 3.5.1)

Y = [Bottom of cover slab - M.S. centerline]

755' 736'9' 5.8 m.

4.2.1.2 Parameter R1: Distance between near source edge and Tb wall.

R1 is determined with reference to shield walls on east and west sides of the moisture separators, depending on the location of the receiver (Section 3,5.1).

3 U1/V2 R1 West Moist. Sep.-+ W = Distance west moist. sep. C.L.~ Outer Tb wall -,VY (radius) 7.5' 5.35' 2.15' 0.66 m. (Locations 2, 3 and-4) v U1/U2 R1 West Moist. Sep.-+ E = Distance west moist. sep. C.L.~ Inner Tb wall - W (radius}

Distance between west moist. sep. inner and outer Tb walls - Distance west moist. sep. C.L.-+ Outer, Tb wall - W (radius)

(25'" - 7.5') - 5.35' 12.32' 3.76 m. (Location'1) a V1/V2 R5 East Moist. Sep.-+ W Distance columns K-+ J - (Distance turbine generator C.L.m K - Distance turbine generator C.L.-+ Distance east moist. sep. C.L.) - J-+ Inner Tb wall edge - W (radius) 32' (53' 44.5') - 1' 5.35'7.2' 5.23 m. (Locations 2, 3 and 4)

Ul/U2 R1 East Moist. Sep.-+ E (Distance turbine generator C.L.-+ K - Distance turbine generator C.L.-+ Distance east moist. sep.

C.L.) - K-+ Outer Tb wall edge - W (radius}

(53' 44.5') - 1'" - 5.35'.9 0.58 m (Location 1) 4.2.1.3 Parameter R2: Distance between far source edge and Tb wall.

the source axis (X) is perpendicular to the Tb, R2. = Rl + 'ince 2W (where W is source moisture separator radius) for each source-+ receiver combination determined in 4.2.=1.2.

PPBL CALCULATlONSHEET

'I pt.

Date

~Th.

9112196 PROJECT SSES lSFSI FUEL CYCLE 40GFR190 Gale. No. 'C-ENVR-1025 Rev. 0 Designed By OFFSlTE DOSE CALC.

Checked By Sh. No. 31 of 121 U1/U2 R2 West Moist. Sep.~ W = 2.15'+ 2(5.35')

12.85' 3.92 m. (Locations 2, 3 and 4)

V1/V2 R2 Nfest Moist. Sep.-+ E 12.32' 2(5.35')

23.02' 7.02 m. (Location 1)

V1/U2 R2 East Moist. Sep.-+ I 17.2' 2(5.35')

2?.90' 8.51 m. (Locations 2, 3 and 4)

U1/U2 R2 East Moist. Sep.-+ E 1.9 ' 2(5.35')

12.6' 3.84 m. (Location 1) 4.2.1.4 Parameter Z: N-+S displacement from end of moisture separator~dose point.

NOTE: Moisture separator parameter Z is calculated for NorthlSouth displacement from moisture separator, parameter. X is calculated for EasNNest displacement. Residence in Sector 16 lies closer to Unit 1 than to Unit 2 outer Tb wall; other receiver are closer to Unit 2 Tb. ln practice, parameter Z north of

'ocations source centerline is negative; south of source centerline valuepof Z are positive.

Ul Z Distance from source face-+inside Tb wall + distance from inside Tb wall-+ column 24+,distance columns [24-+34+ 34~40 +

40-+42 + 42 >46] + Distance from 46-+outer Tb wall + Distance (NwS) from outer Tb wallwdose receiver point

[12.21'+ 1'+ 198'+ 108'+ 36'+?2'+ 9" + 875'J (Sector 7 Res:

Loc. 1)

+ 1477'J (Towers Club: Loc 2)

+ 1661'] (Sector 12 Res: Loc. 4)

U1 Z 1303.0'397.2 m: Sector 7 Res: Loc. 1).

1905.0'580.8 m: Towers Club: Loc. 2) 2089.0'636.9 m: Sector 12 Res: Loc. 4)

'I pt.

ate

~T 9/12/96 PP8,L CALCULATlONSHEET PROJECT SSES ISFSI FUEL CYCLE 40CFR190 Gale. No. EC-ENVR-1025 Rev. 0 esigned By OFFSITE DOSE'CALC.

Checked By Sh. No. 32 of 121 U't Z Distance from source face-+ inside Tb wall + distance from inside Tb wall-+ column 18 + distance columns [18-+16 + 16 >12] +

Distance from 12~outer Tb wall + Distance (N~S) from outer Tb wall ~ dose receiver point

'- [18'+ 3'+ 6.5'+ 36'+ 72'+ 9" + 2800'] (Sector 16 Res: Loc. 3)

U1 Z -2936.25'(-895.2m: Sector16 Res: Loc. 3)

U2 Z Distance from source facem inside Tb wall + distance from inside Tb wall~ column 40+ distance columns t40m42+ 42m46] +

distance from 46~outer Tb wall + Distance (N-+S) from outer Tb wall -+ dose receiver'oint

[18'+ 3'+ 6.5'+ 36'+ 72'+ 9"+ 875'] (Sector 7 Res: Loc. 1)-

" + 1477'] (Towers Club: Loc 2)

[

[ +-1661' (Sector 12 Res: Loc. 4)

U2 Z 1011.25'(308.3m: Sector7Res: Loc.1) 1613.25'491.8 m; Towers Club: Loc. 2) 1797.25'547.9 m: Sector 12 Res: Loc. 4)

U2 Z Distance from source facem inside Tb wall + distance from inside Tb wall-+ column 34+ distance columns [34-+24 + 24-+18 + .

18-+16 + 16-+12] + Distance from 46~outer Tb wall + Distance (N~S) from outer Tb wall -+dose receiver point

- [12.21'+ 1'+ 198'+ 108'+ 36'+ 72'+ 9" + 2800'] (Sector 16 Res Loc. 3)

-3228.0'(-984.1m: Sector16Res: Loc3) 4.2.1.5 Parameter X: E~W Offset from inside Tb wall to dose point (ref 6.1 Figs. 1, 3, 5); east and west moisture separators.

U1/2 E X Distance from inside Tb wall~column J+ Distance columns

. ~

[J-+Gd+ Gd-+G]+ Distance from G outer Tb wall+ Distance i (E-+W) from outer Tb wall -+ dose receiver point

[(2'-1.2')+(2'21')+27'+3.8'5304'] (Sector12 Res: Loc. 4) -'

" " + 1786'] (Sector 16 Res: Loc. 3)

[ . +1857'] (Towers Club: Loc. 2)

PP8 L CALCULATIONSHEET

')ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 33 of 121 U1/2 E X 5377.6'1639.5 m: Sector 12 Res: Loc. 4) 1859.6'(567.0m: Sector16 Res: Loc. 3) 1930.6'588.6 m: Towers Club: Loc. 2)

U1/2 E X Distance columns [K-+N + 1'"] + Distance from N -+ outer Tb wall + Distance (E~W) from outer Tb wall -+ dose receiver point

.[1'"+ 62.3'+ 0.8']+ 1607'Sector 7 Res: Loc. 1) 1671.6'(509.6m: Sector7 Res: Loc1)

U1/2 W X Distance from inner Tb wallwG + [GmTb outer wall]+ Distance (EmW) from outer Tb wall -+ dose receiver point

[1'+ 3.8']+ 5304'(Sector 12 Res: Loc. 4) 3

+ 1786'(Sector 16 Res: Loc. 3)

+ 1857'(Towers Club: Loc. 2)

U1/2 W X 5308.8'(1618.5m: Sector12Res; Loc.4) 1790.8'(546.0m: Sector16 Res: Loc. 3) 1861.8'567.6 m: Towers Club: Loc. 2)

U1/2 W X (2'1.2') + Distance columns [ Gd-+ J +J-+K+ K-+N] +

Distance from N m outer Tb wall + Distance (EmW) from outer-Tb wall m dose receiver point

[0.8'+ (2 *21') + 32'+ 62.3') + 0.8']+ 1607'Sector 7 Res: Loc. 1) 1745.0'(532.0m: Sector7Res: Loc.1) 4.2.1.6 Parameter H: Vertical distance between top of shield wall and'ose receiver point H = Top of shield wall - ground level elevation -/+ 6' 755'-700'6'Sector 12 Residence, Towers Club)

= 755'600'6',(Sector 7 Residence)

= 755' 1010'+ 6'Sector 16 Residence) Note: For this case, 6'as added to bring receiver closer to source.

Although elevating the dose point (as with other locations) may be marginally conservative, the difference here is expected to be insignificant.

= 49'14.9 m: Sector 12 Residence, Towers Club)

= 149'(45.4m: Sector7 Residence)

= -249'-75.9 m: Sector 16 Residence)

PPSL CALCULATIONSHEET I pL JIH. T d . PROJECT SSES ISFSI Calc. No. EC-ENVR-1025 iate 10/1/96 FUEL CYCLE 40CFR190 . = Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 34 of ~11 4.2.2 Cross-around Piping (CAP):

MICROSKYSHINE geometry 14, "Point Source in a Rectangular Enclosure" is used. As described in the MICROSKYSHINE User's Manual (Ref. 6.33),

there is a lateral placement restriction: the line from the source point~dose point is bounded by the corner of the wall toward the dose point. This restriction dictates the orientation of L and W (length and width of rectangular confine), as welt as the values of R1 and R2 (distances fnormal]

from sourcewnearest walls). The program does not accept a case thaQoes not meet these criteria. This restriction does not impact calculations herein.

.4.2.2.1 Parameter Y: Depth of source behind wall (Section 3.5.2)

Y = [Bottom of cover slab - CAP centerline]

= 755'749' 1.83m.

4.2.2.2 Parameter R1: Distance between source and Tb wall (Section' 3.5.2)

R1 = 3.2m. (Units1and2, East)

R1 = 4.5m. (Units1and2, West) 4.2.2.3 Parameter R2:" Distance between near source edge and Tb wall (Section 3.5.2)

R2 = 18.4 m. (Unit1 East and West)

R2 = 11.4m. (Unit2 East and West) 4.2.2,4 Parameter W: Distance between right and left wall (Section 3.5.2)

W = 25.15' 7.7 m.

4.2.2.5 Parameter L: Distance between far and near wall (Section 3.5.2) 4 L = 97.5'29.7 m.

4,2.2.6 Parameter Z: N-+S Offset from inside Tb wall to dose receiver point (Ref. 6-1 Figs, 1, 4 and 5).

0ept.

ate 0 'P8

s. Tech.

9/12/96 esigned By Checked By L CALCULATIONSHEET PROJECT SSES ISFSI FUEL CYCLE 40CFR190 OFFSITE DOSE CALC.

Gale. No.

Sh. No.

EC-ENVR-1025 Rev. 0 35 of 121 U1 Z Distance from CAP source point -+ column 21 + Distance columns

[21-+24+ 24-+34+ 34-+40 + 40 A2+ 42m46] + Distance

~

from 46 -+ outer Tb wall + Distance from outer Tb wall dose receiver point

[7.2'+ 54'+ 198'+ 108'+ 36'+ 72'+ 9" + 875'] (Sector 7 Res:

Loc. 1)

+ 1477'] (Towers Club: Loc. 2)

+ 1661'] (Sector 12 Res: Loc.

4) .'3 U1 Z 1351.0' 411.9 m: Sector 7 Res: Loc. 1) 1953.0'595.4 m: Towers Club: Loc. 2) 2137.0'(651.5 m: Sector 12 Res: Loc. 4)

U1 Z - (Distance from CAP source point ~ column 21) + Distance columns [21~18 + 18-+16 + 16-+12] + Distance from 12 -+

outer Tb wall + Distance from outer Tb wall -+ dose receiver point

- [-7.2'+ 54'+ 36'+ 72'+ 9" + 2800'] (Sector 16 Res: Loc. 3) ~ .

-2970.0'-905.5 m: Sector 16 Res: Loc. 3)

U2 Z - (Distance from column 37 -+ CAP source point) + columns

[37-e40 + 40m42 + 42->46j + Distance from 46 -+ outer wall + Distance from outer Tb wall m dose receiver point

+

[-7.2'+ 54'+ 36'+ 72'+ 9" + 875'] (Sector 7 Res: Loc. 1)

" " + 1477'] (Towers Club: Loc. 2)

[ "

" . +1661'] (Sector12 Res: Loc. 4)

[

U2 'Z 1030.6'(314.2m: Sector7 Res: Loc.1) 1633.0'498.0 m: Towers Club: Loc. 2) 1816.6'(553.8 m: Sector 12 Res; Loc. 4)

U2 Z - (Distance from CAP source point -+ column 37 + Distance columns [37-+35+ 35-+23+ 23-+21 + 21-+19+ 1S >17+

17-+12 ) + Distance from.12-+ outer Tb wall + Distance from

~

outer Tb wall dose receiver point)

[7.2'+ 36'+ 234'+ 36'+ 36'+ 36'+ 90'+ 9".+ 2800'] (Sector 16 Res: Loc. 3)

-3276.0'(-998.8m: Sector16Res: Loc. 3)

PP8 L CALCULATIONSHEET

'7ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 Date 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 36 of 121 4.2.2.7 Parameter X: EwW Offset from inside Tb wall to dose point; east and west CAP. Parameter X is the same as for moisture separators, Section 4.2.1.5.

V1/2 E X 5377.6'(1639.5m: Sector12Res; Loc.4) 1859.6'567.0 m: Sector 16 Res: Loc. 3) 1930.6'588.6 m: Towers Club:. Loc. 2) 1671.6'509.6 m: Sector 7 Res: Loc. 1)

V)/2 W X 5308.8'(1618.5m: Sector12Res: Loc.4) 1790.8'546.0 m: Sector 16 Res:. Loc. 3) 1861.8'567.6 m: Towers Club: Loc. 2)

U1/2 W X 1745.7'(532.2m: Sector7Res: Loc.1) 4.2.2.8 Parameter H: Vertical distance between top of shield wall and source.

Since shield wall is the same for CAP as moisture separators, parameter H is the same as for moisture separators, Section 4.2.1.6.

H = 49'14.9 m: Sector 12 Residence, Towers Club)

= 149'45.4 m: Sector 7 Residence)

= -249'-75.9 m: Sector 16 Residence)

'4.2,3 Combined Intermediate Valves (CIVs):

4.2.3.1 Parameter Z: N~S Offset from inside Tb wall to dose point.

Z for CIVs 02/05 is taken from column 21 (Unit 1) and

'arameter column 37 (Unit 2) (Ref. 6-1 Figs. 1, 4 and 5).

U1 Z Distance columns [24~24+ 24-+34+ 34-AO + 40-+42 +

42-+46] + Distance from 46 ~ outer Tb wall+ Distance from outer Tb wall -+ dose receiver point

[54'+ 198'+ 108'+ 36'+ 72' 9'+ 875'] (Sector 7 Res: Loc. 1)

[

4 + 1477'] (Towers Club; Loc. 2)

[ +1661'] (Sector12 Res: Loc. 4)

PP8 L CALCULATIONSHEET Oept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC, Checked By Sh. No. 37 of ~11 U1 Z 1343.8'409.7 m: Sector 7 Res: Loc. 1) 1945.8'593.2 m: Towers Club: Loc. 2) 2129.8'649.3 m: Sector 12 Res: Loc. 4)

U1 Z Distance columns f21m18+ 18-+16 + 16-+12] + Distance from 12 w outer Tb wall + Distance from outer Tb wall -+ dose receiver point

-[54'+ (3 36') + 9" + 2800'] (Sector 16 Res: Loc. 3)

-2962.8'-903.3 m: Sector 16 Res: Loc. 3)

U2 Z Distance columns [37-+40 + 40-+42 + 42-+46] + Distance-~

from 46 ~ outer Tb wall + Distance from outer Tb wall -+ dose .

receiver point

[54'+ 36'+ 72'+ 9" + 875'] (Sector 7 Res: Loc. 1)

" " + 1477'] (Towers Club: Loc. 2) f "

" +1661') (Sector12 Res: Loc. 4) f U2 Z 1037.8'316.3 m: Sector 7 Res: Loc. 1) 1639.8'499.9 m: Towers Club: Loc. 2) 1823.8'556.0 m: Sector 12 Res: Loc. 4)

U2 Z Distance columns t'37-+34 + 34-+24 + 24-+18 + 18-+16 +,

16-+12] + Distance from 12 w outer Tb wall + Distance from

~

outer Tb wall dose receiver point

-[54'+198'+108'+ 36'+ 72'+ 9" + 2800'] (Sector16 Res: Los.

3)

-3268.8'-996.6 m: Sector 16 Residence) 4.2.3.2 Parameter X: E-+W Offset from inside Tb wall to dose point (ref 6.1 Figs. 1, 4, and 5); ¹2 and ¹5 CIVs. In reference 6.1, Section 5.3.1.3, CIVs are modeled on the turbine side of the partial shield wall, with no overhead slab shield. The wall on the Gd column line is the shield wall for dose points to the west (i.e. !ocations 2, 3 arid !

4). The wall on the J column line is the shieldwall for the dose point to the east (location 1).

PP8 L CALCULATIONSHEET 0ept. 0 s. Tech, PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 Bate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC; Checked By Sh. No. 38 of 121 U1/2 X Distance inside shield wallm column J + distance columns fJ~K

+ K-+N] + Distance from N outer Tb wall + Distance from ~

outer Tb wall m dose receiver point 1'.5" + 32' 62'" + 9" +

m: Sector 7 Res: Loc.1) 1607'?03.1'(519.2 Ul/2 Distance inside shield wall-+ column Gd + distance column Gd->G + Distance from G -+ outer Tb wall + Distance from outer Tb wall m dose receiver point rg 1'.5" + 2?' 3'" +

m: Sector 7 Res. Loc. 1) 1607'638.9'499.7 f

m: Towers Club: Loc. 2)

]+1857'888.9'575.9

[ ]+

Sector16 Res: Loc. 3) 1786'81?.9'(554.2m:

[ ]+

m: Sector 12 Res: Loc. 4) 5304'335.9'1626.8 4.2.3.3 Parameter H: Vertical distance between top of shield wall and ~

dose point. The top of shield wall for CAP is 756.5'slightly higher than for Moisture Separators); parameter H is determined similarly to Section 4.2.1.6.

H = 756.5'-700'-6'(Sector12 Residence, Towers Club)

= 756.5'600'6'Sector 7 Residence)

= 756.5'1010' 6'Sector 16 Residence)

= 50.5'(15.4m: Sector12 Residence, Towers Club).

= 150.5'(45.9m: Sector7Residence)

-247.5'-75.5 m: Sector 16 Residence) 4.2.4. HP Turbine Inlet Piping (Horizontal Elbow) 4.2.4.1 Parameters R1/R2: Distance between source and Tb wall. R1 and R2 depend on whether piping is east or west of the Turbine, and on the location (east or west) of the dose receiver point. For west dose points, shield wall is Gd; for east dose points, shield wall is J (Section 3.5.7). For dose points to the west (Locations 2, 3 and 4},

R1 and R2 are defined:

PP8L CALCULATIONSHEET I pL JIIL.T 8 PROJECT SSES ISFSI Calc. No. EC-ENVR-1025.

ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 39 of 121 WESTpiping: R1 =R2 3.0 m.

EAST piping: R1 = R2 6.1 m.

For dose point to the east (Location 1), R1 and R2 are defined:

WEST piping: R1 = R2 = 6.1m.

EAST piping: R1 = R2 = 3.0 m.

4.2.4.2 Parameter Z: N~S Offset from inside Tb wall to dose receiver point. Parameter Z for HPT horizontal inlet piping centerline is taken from columns 17 (Unit 1) and 41 (Unit 2) (ref. 6.1 Figs. 1, 4, and 5).

U1 Z Distance columns t1 7~19 + 19~21 + 21m23 + 23m36 + -;

36m37 + 37-+39 + 39-+41 + 41-+46] - Distance from horiz. inlet piping centerline+ Distance from column 46 colum'7mHPT m outer Tb wall + Distance from outer Tb wall -+ dose receiver' point

[(3*36') + 234'+ (3 36) + 90'+ 9" -3.6'+ 875'] (Sector 7 Res:

Loc. 1)

+ 1477'] (Towers Club; Loc. 2).

+ 1661'] (Sector 12 Res: Loc. 4)

U1 Z 1412.2'(430.5m: Sector 7 Res: Loc. 1) 2014.2'(614.1 m: Towers Club: Loc. 2) 2198.2'670.2 m: Sector 12 Res: Loc. 4)

U1. Z Distance columns t17-+12] + Distance from column 17~HPT horiz. inlet piping centerline+ Distance from 12 -+ outer Tb wall +

Distance from outer Tb wall -+ dose receiver point

-[9" + 3.6'+ 90' 2800'] (Sector 16 Res: Loc, 3)

-2894.4'-882.4 m Sector 16 Res: Loc. 3)

U2 Z Distance from column 41mHPT horiz. inlet piping centerline +

Distance column t41~46] + Distance from 46 -+ outer Tb wall +

~

Distance from outer Tb wall dose receiver point

[90'+ 3.6'+ 9" + 875'] (Sector 7 Res:"Loc. 1)

" + 1477'] (Towers Club: Loc. 2)

[ "

f + 1661'] (Sector 12 Res: Loc. 4)

'lept.

Date 0 'P8L

s. Tech.

9/12/96 Designed By CALCULATIONSHEET PROJECT SSES ISFSI FUEL CYCLE 40CFR190 OFFSITE DOSE CALC.

Gale. No. EC-ENVR-1025 Rev. 0 Checked By Sh. No. 40 of 121 U2 Z 969.4'295.5 m: Sector 7 Res: Loc. 1) 1571.4'479.1 m: Towers Club: Loc. 2) 1755.4'535.2 m: Sector 12 Res: Loc. 4)

U2 Z Distance columns t'41~39 + 39m37+ 37-+35+ 35-+23 +

23-+21+ 21-+19+ 19-+17+ 17-+12] - Distance from column 41~HPT horiz. inlet piping centerline + Distance from col. 12 ~

outer Tb wall + Distance from outer Tb wall -+ dose receiver point

-[(3"36') + 234'+ (3 36') + 90' 3.6' 9'+ 2800') (Sector 16 Res:

Loc 3)

-3337.2'-1017.4 m: Sector 16 Res: Loc. 3) 4.2.4.3 Parameter X: E~W Offset from inside Tb wall to dose point (ref.

6.1 Figs. 1, 2, 4, 5). X is taken from the inside face of the Tb wall, which means that for each receiver it is the same for Unit 1 and 2 sources, on both west and east sides of the turbine centerline.

U1/2 E,W X Distance from face of inside Tb wall~ Gd + Distance column ..

Gd-+G + Distance from G -+ outer Tb wall + Distance from outer Tb wall m dose receiver point

[1.2' 27'+ 3.8'+ 1857'] (Towers Club: Loc. 2)

" " + 1786'J (Sector 16 Res: Loc. 3)

[ " "

[ + 5304'] (Sector 12 Res: Loc. 4)

U1/2 E,W X 1889'575.9 m: Towers Club: Loc. 2) 1818'554:3 m: Sector 16 Res: Loc. 3) 5336'(1626.8 m: Sector 12 Res: Loc. 4)

U1/2 E,W X Distance columns t'J~K + K~M] + (3'" - 8.5") + Distance from N -+ outer Tb wall+ Distance from outer Tb wall -+ dose receiver point

[32'+ 62.3'+ 2.54'+ 9"J+ 1607'Sector 7 Res: Loc. 1) 1704.6'(519.7 m: Sector 7 Res: Loc. 1) .

4.2.4.4 Parameter H: Vertical distance between top of Tb wall and source (ref. 6.1 Fig. 6). Parameter H is determined similarly to Section 4.2.1.6.

PP8 L CALCULATlONSHEET Rept. 0 s. Te PROJECT SSES ISFSI Gale. No. EC-ENVR-1025

>ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE GALC.

Checked By Sh. No. 41 of 121 H = 754'700'6'Sector 12 Residence, Towers Club)

= 754' 600' 6'Sector 7 Residence)

= 754'1010'+ 6'Sector 16 Residence)

= 48'(14.6m: Sector12 Residence, Towers Club)

= 148'45.1 m: Sector 7 Residence)

= -250'-76.2 m: Sector 16 Residence) 4.2.5. HP Turbine inlet Piping (Vertical Segment) 4.2.5.1 Parameter R1: DistancebetweensourceandTbwall. R1 depends on whether piping is east or west of the Turbine, and on the (east or west) of the dose'receiver point. For west dose'ocation points, Tb wall is Gd; for east dose points, Tb wall is J (ref. 6.1 Section 5.3.1.7). For dose points to the west (Locations 2, 3 arid 4), R1 is defined:

WEST piping: R1 = 3.3 m.

EAST piping: R1 = 8.8 rn.

For dose point to the east (Location 1), R1 is defined:

WEST piping: R1 = 8.8 m, EAST piping: R1 = 3.3 m.

4.2.5.2 Parameter Z: NwS Offset to dose point. Parameter Z is the same for vertical and horizontal HPT inlet piping (ref. Section 4.2.4.2}.

U1 Z 1412.2'430.5 m: Sector 7 Res: Loc. 1) 2014.2'614.1 m: Towers Club: Loc. 2)

-2894.4'-882.4 m: Sector 16 Res: Loc. 3) 2198.2'(670.2 m: Sector 12 Res: Loc. 4)

U2 Z 969.4'(295.5 m: Sector 7 Res: Loc. 1) 1755.4'535.2 m: Sector 12 Res: Loc. 4) 1571.4'479.1'm: Towers Club: Loc. 2)

-3337.2'-1017.4 m: Sector 16 Res: l oc. 3)

PP8 L CALCULATIONSHEET a pL Jla.T PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 42 of ~21 4.2.5.3 Parameter X: E-+W Offset from inside Tb wall to dose point.

Parameter X is the same for vertical and horizontal HPT inlet piping (ref. Section 4.2.4.3).

U1/2 E,W X 5336'1626.8 m: Sector 12 Res: Loc. 4) 1818'(554.3 m: Sector 16 Res: Loc. 3) 1889'(575.9 m: Towers Club: Loc. 2) 1704.6'(519.7 m: Sector 7 Res: Loc. 1) 4.2.5.4 Parameter H: Vertical distance between top of Tb wall and dose point, Parameter H is determined similarly to Section 4.2.1.6.

H = 754'-700'-6'(Sector 12 Residence, Towers Club)

= 754'600'6'Sector 7 Residence)

= 754'1010'+ 6'Sector 16 Residence)

= 48'(14:6 m: Sector 12 Residence, Towers Club)

= 148'45.1 m: Sector 7 Residence)

= -250'-76.2 m: Sector 16 Residence) 4.2.6 CIV ¹2/¹5~LP Turbine Inlet Piping 4.2.6.1 Parameters R1/R2: Distance between source and Tb wall. R1>nd R2 depend on whether piping is east or west of the Turbine, and on the location (east or west) of the dose receiver point. For west dose points, Tb wall is Gd; for east dose points, Tb wall is J (ref.

6.1 Section 5.3.1.4) ). For dose points to the west (I ocations 2, 3 and 4), R1 and R2 are defined:

WEST piping: R1 = R2 = 0.1 m.

EAST piping: R1 = R2 = 9.0 m.

For dose point to the east (Location 1), R1 and R2 are defined:

WEST piping: R1 = R2 = 9.0m.

EAST piping: R1 = R2 = " 0.1 m.

PP8 L CALCULATIONSHEET Rept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 10/1/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 43 of 121 4.2.6.2 Parameter Z: N-+S Offset from inside Tb wall to dose point Parameter Z for CIV~LPT inlet piping centerline is taken from columns 21 (Unit 1) and 37 (Unit 2) Parameter Z is the same as for CIVs (Section 4.2.3.1).

U1 Z 1343.8'(409.7m: Sector7Res: Loc.1) 1945.8'593.2 m: Towers Club: Loc. 2)

-2962.8'.(-903.3 m: Sector 16 Res: Loc. 3) 2129.8'649.3 m: Sector 12 Res: Loc. 4)

U2 Z 1037.8'(316.3 m: Sector 7 Res: Loc. 1) 1639.8'499.9 m: Towers Club: Loc. 2)

-3268.8'-996.6 m: Sector 16 Res: Loc. 3) 1823.8'556.0 m: Sector 12 Res: Loc. 4) 4.2.6.3 Parameter X: E-+W Offset from inside Tb wall to dose point; parameter X for west CIV piping. is the same as for the west CIV distances; parameter X for east CIV piping is the same as for thy east CIV distances (Section 4.2.3.2).

U1/2 X 1703.1'519.2 m: Sector 7 Res: Loc. 1) 1888.9'575.9 m: Towers Club: Loc. 2) 1817.9'(554.2m: Sector16Res: Loc.3) 5335.9'(1626.8m: Sector12Res: Loc.4) 4.2.6.4 Parameter H: Vertical distance between top of shield wall and dose point (Ref. 6.1 Fig. 6). Parameter H is determined similarly to Section 4.2.1.6. [NOTE: Top of shield is 756.5'n moist. sep.

room. Value used (754') is conservative, because it is smaller].

H = 754' 700' 6'Sector 12 Residence, Towers Club)

= 754' 600' 6'Sector 7 Residence)

• =

754'1010'+ 6'Sector 16 Residence)

= 48'14.6 m: Sector 12 Residence, Towers Club)

= 148'45.1 m: Sector 7 Residence)

= -250'-76.2 m: Sector 16 Residence)

PP8 L CALCULATIONSHEET

.-. 0ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 Date 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 44 of 121 4.2.7 HP Turbine 4.2.?.1 Parameter R1: Distance between source and Tb wall (Ref. 6.1 Section 5.3.1.5)

R1 = 4.5m.

4.2.7.2 Parameter R2: Distance between near source edge and Tb wall (Ref. 6.1 Section 5.3.1.5)

R2 = 7.56 m.

4.2.7.3 Parameter Z: N~S Offset from inside Tb wall to dose point. In Ref. 6.1 (Section 5.3.1.5), Parameter Z for HPT is taken from north to south (south face of HPT: for dose points south of the HPT).~

Values of Z for the HPT are approximately the same as for the HPT horizontal inlet piping, which is taken from the HPT centerline (Section 4.2.4.2), with a difference of 0.5L, where L is the length of the HPT (21': Section 3.5.5).

U1 Z 1412.2' (0.5 21')

1401.7'427.3 m: Sector 7 Res: Loc. 1) 2014.2' (0;5 21')

2003.7'610.9 m: Towers Club: Loc. 2)

-[2894.4'- (0.5

• 21')

-2883.9'(79.2m: Sector16 Res: Loc. 3) 2198.2' (0.5 21')

2187.7'(667.0 m: Sector12 Res: Loc. 4)

U2 Z= 969.4' (0.5

• 21')

928.9'283.2 m: Sector 7 Res: Loc. 1) 1571.4' (0.5

• 21')

1560.9'475.9 m: Towers Club: Loc. 2)

PP8L CALCULATlONSHEET

'I pt. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 45 of ~1

-[3337.2' (0.5

• 21')]

-3326.7'-1014.2 m: Sector 16 Res: Loc. 3) 1755.4' (0.5

• 21')

1744.9'532.0 m: Sector 12 Res: Loc. 4) 4.2.7.4 Parameter X: E-+W Offset from inside Tb wall to dose point (ref..

6.1 Figs. 1, 2, 4 and 5). Parameter X for. High Pressure Turbine is the same as for the HPT horizontal inlet piping (Section 4.2.4.3).

U1/2 W X 5336'(1626.8m: Sector12Res: Loc.4) 1818'(554.3m: Sector16 Res: Loc. 3)

. 1889'(575.9m: Towers Club: Loc. 2)

U1/2 E 1704.6'(519.7 m: Sector 7 Res: Loc. 1) 4.2.7.5 Parameter H: Vertical distance between top of shield wall and--

dose point (Ref. 6.1 Fig. 6). Parameter H is determined similarly to Section 4.2.1.6.

H = 754'700'+ 6'Sector 12 Residence, Towers Club)

= 754'600'+ 6'Sector 7 Residence)

= 754'1010'+ 6'Sector 16 Residence)

= 48'(14.6m: Sector12 Residence, Towers Club)

= 148'45.1 m: Sector 7 Residence)

= -250'-76.2 m: Sector 16 Residence) 4.2,8 LP Turbine 4.2.8.1 Parameter R1: Distance between source and Tb wall (Section 3.5.6)

R1 = 2.5m.

4.2.8.2 Parameter R2: Distance between near source edge and Tb wall (Section 3.5.6)

R2 = 9.7m.

0 ~

~

~ 0 0

~ ~

~ I 0 ~ 0 I ~ 0 ~ ~

~ 0

~ ~ ~ ~ ~ ~ ~

~ ~

~ ~

~ I

~ ~ ~

~ ~

0 ~

~ ~ ~ ~

~ ~

0

~ 0 ~

~ ~

0 ~

~ ~

0

~ ~ 0

~ ~ I

~ I' 0

~ ~ ~ ~ ~ ~ I 0 ~

~ ~

PP&L CALCULATIONSHEET r 'Ipatee 10/1/96 PROJECT SSES ISFSI FUEL CYCLE 40CFR190 Gale. No. EC-ENVR-1025 Rev. 0 esigned By OFFSITE DOSE CALC.

'Ch ecked By Sh. No. 47 of '11 U1I2 E,W X 1704.6'(519.7 m: Sector 7 Res: Loc. 1) 1889.0'575.9 m: Towers Club: Loc. 2) 1818.0'(554.3 m: Sector 16 Res: Loc, 3) 5336'(1626.8m: Sector12Res: Loc.4) 4.2.8.5 Parameter H: Vertical distance between top of shield wall and source (Ref. 6.1 Fig. 6). Parameter H is determined similarly to Section 4.2.1.6. [NOTE: Top of shield is 756.5'n moist. sep. room.

Value used (754') is conservative, because it is smaller].

.3 H = 754'-700'-6'(Sector 12 Residence, Towers Club)

= 754'-600'-6'Sector 7 Residence)

= 754'1010'+ 6'Sector 16 Residence)

= 48'14.6 m: Sector 12 Residence, Towers Club) V ~

= 148'45.1 m: Sector 7 Residence)

= -250'-76.2 m: Sector-16 Residence) 4.3 MICROSKYSHINE Calculations: Turbine Building 4.3.1 MICROSKYSHINE is run for all source/receiver combinations developed in Section 4.2 (total 112 runs) and the source terms from Table 3-1. The filename coding for sources/receivers is shown in Tables 4-1 a-d, . Results of the runs are included in Attachments 5-8, 4.3.2 The results of MICROSKYSHINE calculations performed in Section 4.3.1 are entered into Tables 4-1 aM for each of the four off site receiver locations.

Results for CIVs, CIV piping, and LP turbines are shown multiplied by three (Section 3.9). The results from all eemponents are summed at the bottom of each table.

4.3.3 . The annual dose to the off site receiver from all turbine components is calculated:

Dase(annual) = g&p raies(mRlbr) e 8760hr I year(Seeiion321) Eq. 4-2 The annual dose from all turbine components is determined for each receiver using Equation 4-2. The annual dose for each receiver is shown at the bottom of Tables 4-1a-d,

PP&L CALCULATIONSHEET Rept. PROJECT SSES ISFSI Cate. No. EC-ENVR-1 025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 48 of Table 4-1a: MICROSKYSHINE Run Results: Turbine Building Sources Receiver: Resident Sector 7 (Location 1)

Adjusted MICROSKYSHINE Result Multiplication Result Tb Source Filename mR/hr Factor mR/hr Contrib.

U1 East Moisture Se arator U1EMS7 4.63E-06 4.63E-06 1.0 U2 East Moisture Se arator U2EMS7 7.20E-06 1 7.20E-06 1.5 U1 West Moisture Se arator U1WMS7 7.28E-06 1 7.28E-06 1.5 U2 West Moisture Se arator U2WMS7 1.10E-05 1 1.10E-05 U1 East Cross Around Pi in 1CAPE7 5.45E-06 1 5.45E-06 U2 East Cross Around Pi in 2CAPE7 8.52E-06 1 8.52E-06 U1 West Cross Around Pi in 1CAPW7 4.91E-06 1 4.91E-06 1.0 U2 West Cross Around Pi in 2CAPW7 7.59E-06 1 759E 06 1 U1 East CIV 1CIV2E7 1 ~ 12E-06 3 3.36E-06 0.7-U2 East CIV'1 2CIV2E7 1.60E-06 3 4.80E-06 1.0 West CIV'2 1CIV5W7 9.33E-06 3 2.80E-05 59 West CIV 2CIV5W7 1.27E-05 3 3.82E-05 U1 HPT East Inlet Piping: U1EHOR7 9.32E-06 1 9.32E-06 2.0 Horizontal U2 HPT East Inlet Piping: U2EHOR7 1.94E-05 1 1.94E-05 4 I Horizontal U1 HPT West Inlet Piping: 2.23E-05 1 2.23E-05 4:7 Horizontal U1WHOR7'2WHOR7 U2 HPT West Inlet Piping: 3.60E-05 1 3.60E-05 7.6 Horizontal U1 HPT East inlet Pi in: Vertical U1EVER7 3.43E-06 1 3.43E-06 0.7 U2 HPT East Inlet Pi in: Vertical U2EVER7 5.49E-06 1 5.49E-06 1.2 U1 HPT West Inlet Pi in; Vertical U1WVER7 1.14E-05 1 1.14E-05 2.4 U2 HPT West inlet Pi in: Vertical U2WVER7 1.70E-05 1 1.70E-05 3.6 U1 East CIV->LPT Inlet Pi in '2 3.87E-06 3 1.16E-05 2.5 East CIV->LPT Inlet Pi in 2CPE7 5.38E-06 3 1.61E-05 3.4 West CIV->LPT Inlet Pi in *

'1 1CPW7 2.95E-05 3 8.84E-05 18.7 U2 West CIV-+LPT Inlet Pi in * ~

2CPW7 2.93E-05 3 8.78E-05 18.6 U1 Hi h Pressure Turbine. U1HPT7 7.39E-07 7.39E<7 0.2 U2 Hi h Pressure Turbine Turbine'CPE7 U2HPT7 1.35E-06 1

1 1.35E-06 0.3 U1 Low Pressure Turbine'2 U1LPT7 1.57E-06 3 4.71E-06 1.0 Low Pressure U2LPT7 2.35E-06 3 7.04E-06 1.5 SUM EXP. RATES = 4.73E-04 100.0 ANNUALEXP. mR = 4.14E+00 eference Section 3.9

PP&L CALCULATlONSHEET gept s Te ~

PROJECT SSES ISFSl Gale. No. EC-ENVR-1025'ev.

)ate 9/12/96. '. FUEL CYCLE 40CFR190 0 Designed By OFFSITE DOSE GALC.

Checked By Sh. No. 49 of Table 4-1b: MICROSKYSHINE Run Results; Turbine Building Sources Receiver: Towers Club (Location 2)

Adjusted MICROSKYSHINE Result Multiplication Result Tb Source Filename mR/hr Factor mR/hr Contrib U1 East Moisture Se arator U1EMSTC 2.75E-06 1 2.7GE-06 1.2 U2 East Moisture Se arator U2EMSTC 4.36E-06 1 4.36E-06 1.9 U1 West Moisture Se arator U1WMSTC 1.28E-06 1 1.28E-06 0.6 U2 West Moisture Se arator U2WMSTC 2.08E-OB 2.08E-06 0.9 U1 East Cross Around Pi in 1CAP ETC 1.70E-06 1 1.70E-06 0.8 U2 East Cross Around Pi in 2CAPETC 2.74E-06 1 2.74E-06 1.2 U1 West Cross Around Pi in 1CAPWTC 1.99E-06 1 1.99E-06 0.9 U2 West Cross Around Pi in 2CAPWTC 3.26E-06 1 3.26E-06 1.5 U1 East CIV'2 1CIV2ETC 4.47E-06 3 1.34E-05 6.0 East CIV'1 2CIV2ETC 6.25E-06 3 1.87E-05 8.4 West CIV 1CIV5WTC 3.90E-07 3 1.17E-06 0.

U2 West CIV'l 2CIV5WTC 5.46E-O? 3 1.63E-06 0.7 .

HPT East Inlet Piping: U1EHORTC 1.27E-05 1.27E-OG 5.7 Horizontal U2 HPT East Inlet Piping; U2EHORTC 1.94E-05 1 1.94E-OG 8.7 Horizontal U1 HPT West inlet Piping: 01WHORTC 6.17E-06 1 B.17E-06 Horizontal U2 HPT West Inlet Piping: U2WHORTC 9.25E-06 1 9.25E-06 Horizontal U1 HPT East Inlet Pi in: Vertical U1EVERTC 6.05E-06 1 B.05E-06 U2 HPT East Inlet Pi in: Vertical U2EVERTC 9.12E-06 1 9.12E-06 U1 HPT West inlet Pi in: Vertical U1WVERTC 1.29E-OB 1 1.29E-06 U2 HPT West inlet Pi in: Vertical U2WVERTC 2.06E-06 1 2.06E-OB 0.9 U1 East CIV->LPT inlet Pi in 1CP ETC 1.28E-05 3 3.85E-05 17.2 U2 East CIV->LPT InletPI in 2CP ETC 1.59E-OG 3 4.77E<<05 21.3

'1 West CIV->LPT Inlet Pi in 1CPWTC 1.86E-06 3 5.57E-06 2.5 Inlet Pi in '2WestCIV->LPT 2CPWTC 1.99E-06 3 5.96E-06 2.7

'1 Hi h Pressure Turbine U1HPTl C 2.40E-07 1 2.40E-07 0.1 U2 Hi h Pressure Turbine U2HPTTC 4.74E-07 4.74E-07 0.2 U1 Low Pressure Turbine'2 U1LPTl C 6.78E-07 3 1:73E-06 0.8 Low Pressure Turbine U2LPTTC 8.94E-07 ~ 3 2.68E-06 1.2 SUM EXP. RATES = 2.24E-04 100.0 ANNUALEXP. mR>> 1.96E+00 eference Section 3.9

PP8 E. CALCULATIONSHEET Oept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 fate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 50 of Table 4-1 c: MICROSKYSHINE.Run Results: Turbine Building Sources Receiver: Resident Sector 16 (Location 3)

Adjusted Result Multiplication Result

'ICROSKYSHINE Tb Source U1 East Moisture Se arator Filename U1EMS18 mR/hr 1.07E-06 Factor mR/hr Contrib.

1.07E-06 0.8 U2 East Moisture Se arator U2EMS16 6.41E-07 6.41E-07 0.5 U1 West Moisture Se arator U1WMS18 4.50E-07 4.50E-07 0.4 U2 West Moisture Se arator U2WMS18 2.72E-07 2.72E-07 U1 East Cross Around Pi in 1CAPE16 6.99E-07 6.99E-07 0.5 U2 East Cross Around Pi in 2CAPE18 4.20E-07 4.20E-07 0.

U1 West Cross Around Pi in 1CAPW16 7.72E-07 7.72E-07 0.

U2 West Cross Around Pi in 2CAPW18 4.59E-07 4.59E-07 0.4 U1 East CIV'2 1CIV2E16 2.93E-O6 8.78E-06 East CIV'1 2CIV2E18 1.96E-06 5.88E-06 West CIV* 1CIV5W18 1.46E-07 4.37E-07 0.3 U2 West CIV* 2CIV5W18 1.29E-07 3.86E-07 0.8 U1 HPT East Inlet Piping: U1EHOR16 1.12E-05 1.12E-05 8.7 Horizontal U2 HPT East Inlet Piping: U2EHOR16- 6.62E-06 6.62E-06 Horizontal U1 HPT West Inlet Piping: U1WHOR16 5.56E-06 5.56E-06 4.3 Horizontal U2 HPT West Inlet Piping: U2WHOR16 3.47E-06 3.47E-06 27.

Horizontal U1 HPT East Inlet Pi in: Vertical U1EVER18 4.95E-OB 4.95E-06 3.8 U2 HPT East inlet Pi in: Vertical U2EVER18 3.02E-06 3.02E-06 2.3 U1 HPT West Inlet Pi in: Vertical u1WVER18 1.10E-06 1.10E-06 0.9 U2 HPT West Inlet Pi in: Vertical U2WVERIB 6.58E-07 6.58E-07 0.5 U1 East CIV->LPTlniet Pi In ' 1CPE18 1.23E-05 3.70E-05 28.7 U2 East CIV->LPT Inlet Pi in 'CPE16 9.44E-06 2.83E-05 22.0 U1 West CIV->LPT Inlet Pi in '. 1CPW18 8.22E-07 2.46E-06 1.9 U2 West CIV->LPT Inlet Pi in 2CPW18 7.93E-07 2.38E-06 1.8 U1 Hi h Pressure Turbine U1HPT16 3.84E-07 3.84E-07 0.3 U1 Low Pressure Turbine'.81E-08 U2 Hi h Pressure Turbine U2HPT18 U1LPT18 "

" 2.53E-07 5.81E-08 7.60E-07 0.0 0.6 U2 Low Pressure Turbine'2LPT18 1.57E-07 4.72E-07 0.4 SUM EXP. RATES = 1.29E-04 100.0 ANNUALEXP. mR = I 13E+00

~

Reference Section 3.9

PP8 L CALCULATIONSHEET ept. O s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1 025 fate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 51 of Table 4-1d: MICROSKYSHINE Run Results: Turbine Building Sources Receiver. Resident Sector 12 (Location 4)

Corrected MICROSKYSHINE Result Multiplication Result Tb Source Filename mR/hr Factor mR/hr Contrib U1 East Moisture Se arator U1EMS12 2.68E-09 2.68E-09 0.8 U2 East Moisture Se arator U2EMS12 3.11E-09 3.11E-09 0.9 U1 West Moisture Se arator U1WMS12 1.72E-10 1.72E-10 0.1 U2 West Moisture Se arator U2WMS12 2.05E-10 2.05E-10 0o U1 East Cross Around Pi in 'I CAPE12 3.97E-09 3.97E-09 U2 East Cross Around Pi in 2CAPE12 4.61E-09 4.61E-09 1.4 U1 West Cross Around Pi in 1CAPW12 6.74E-09 6.74E-09 2.0 U2 West Cross Around Pi in 2CAPW12 8.01E-09 8.01E-09 2.4 U1 East CIV'2 1CIV2E12 1.40E-OS 4.20E-OS 12.7 East CIV'1 2CIV2E12 1.55E-OS 4.66E-OS 14:1 West CIV'2 1CIV5W12 1.70E-11 5.10E-11 00 West CIV* 2CIV5W12 2.16E-11 6.47E-11 0.0 U1 HPT East Inlet Piping: U1EHOR12 4.38E-OS 4.38E-08 13.3 Horizontal U2 HPT East Inlet Piping; U2EHOR12 4.99E-OS 4.99E-OS 15.1 Horizontal U1 HPT West Inlet Piping: U1WHOR12 6.21E-09 6.21E-09 1.9 Horizontal U2 HPT West Inlet'Piping: U2WHOR12 6.93E-09 6.93E-09 2.1.

Horizontal U1 HPT East Inlet Pi in: Vertical U1EVER12 8.47E-09 8.47E-09 2.6 U2 HPT East Inlet Pi in: Vertical U2EVER12 9.48E-09 9.48E-09 2.9 U1 HPT West Inlet Pi in: Vertical U1WVER12 1.39E-10 1.39E-10 0.0 U2 HPT West Inlet Pi in: Vertical U2WVER12 1.61E-10 1.61E-10 0.0 U1 East CIV->LPT Inlet Pi in 1CPE12 1.24E-OS 3.71E-OS 11.2 East CIV->LPT Inlet Pi in *.

'2 2CPE12 1.32E-OS 3.95E-08 12.0 U1 West CIV->LPT Inlet Pi in

• 1CPW12 7.05E-11 2.11E-10 0.1 U2 West CIV->LPT Inlet Pi in 2CPW12 7.83E-11 2.35E-10 0.1 U1 Hi h Pressure Turbine U1HPT12 1.90E-10 1.9E-10 0.1 U2 Hi h Pressure Turbine U2HPT12 2.37E-10 2.37E-10 0.1 U1 Low Pressure Turbine U1LPT12 1.45E-09 4.34E-09 1.3 U2 Low Pressure Turbine* U2LPT12 1.69E-09 5.08E-09 1.5 SUM EXP. RATES = 3.30E-07 100.0 ANNUALEXP. mR = 2.89E-03 Reference Section 3.9

PP8L CALCULATIONSHEET

")ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 Jate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 121 4.4 MICROSKYSHINE Calculations: Condensate Storage Tanks (CSTs); Shielding from Ground between Unit 2 CST and Sector 7 Receiver Unit 1 and Unit 2 CSTs are located at elevation 670, which is grade for the power block lobby. The Unit 1 CST is shielded at the west side by the Unit 1 Turbine Building wall, on the east side by the Diesel Generator Building wall, and on the south side by the Unit 1 Reactor Building (reference 6.32.4). The Unit 2 CST is shielded at the west side by the Unit 2 Turbine Building, on the north side by the Unit 2 Reactor Building, and partially shielded on east and south sides by an overflow berm which extends 10.5 feet above grade (reference 6.32.5), which means that 21.5 feet is exposed above the berm height. The Turbine Building wall is a shield wall fear IVIICROSKYSHINE purposes up to the operating deck (el. 729). This wall is a substantial shield to direct radiation (three feet thick: Fig. 3-3) from Unit.1 and 2 ~

CSTs. The Unit 1 Reactor Building wall extends to el. 818'reference 6.32.6), and.is considered a shield wall up to that level for MICROSKYSHINE purposes. The Unit 1 Reactor Building wall is also a considerable shield to direct radiation (three feet tAitk

Fig. 3-4) from the Unit 1 CST. The MICROSKYSHINE program geometry 12 (vertical cylinder behind slab shield wall) is applicable to cases of skyshine from Unit 1 CST to all off site locations, and for the Unit 2 CST to location 2 (Towers Club),'

location 3 (Sector 16 residence) and location 4 (Sector residence): all these locations lie on a line which is intercepted by either turbine building or reactor -,

building walls. For Unit 2 CST shine to the Sector 7 residence, however, the cash is more complicated, since the Unit 2 CST extends partly above the berm as described.

For this situation, the skyshine exposure rate is determined by an approach simiJyr to that used in Reference 6,1; MICROSKYSHINE geometry 3 (cylinder in silo) is applied. For this geometry, the shield surrounding the tank must be raised for the computer program to run, which can be accomplished by minimizing the value of Y.

Raising the shield around the silo to a point level with the top of the CST will not have a significant effect of artificially lowering the exposure rate to the dose location, since the silo shield wall is effectively "black", i.e. the radiation from the tank is considered to emit from the circular surface area at the top only, and the buildup factors are applied to the transmission of radiation through the cylindrical source, from bottom to top (references 6.56, 6.57).

PP8 L CALCULATIONSHEET

")ept. 0 s. Tech. PROJECT SSES ISFSI Calc. No. EC-ENVR-1025

>ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 53 of 121 4.4.1 Determination of MICROSKYSHINE Input Parameters for Geometry 12 4.4.1.1 Parameter Y: Depth of source behind shield wall Y = Height of shield (818'or reactor building; 729 for turbine building) - effective height of the CST (32':

Section 3.17) - CST elevation at grade (670':from the top of the slab shield: Section 3.17).

818' 32' 670'16' 35.4 m. (U1 CST~Sector 7 Res: Loc. 1) 729' 32' 670'7' 8.2 m. (U1, U2CST~TOWERS CLUB, Sec.16,12 Res: Locs. 2, 34) 4.4.1.2 Parameter T1: Thickness of concrete slab cover (Section 3.17)

~ ~

T1 = 0.0m.

4.4.1.3 Parameter T2: Thickness of second shield (Section 3.17)

T2 = 0.0m 4.4.1.4 Parameter R1: Distance between source center and shield walli reactor or turbine building R1 = 32.75' 9.98 m. U1 CST~Sector 7 Res. (Fig. 3-3)

R1 = 38.5' 11.74 m. U1, U2 CST~ TOWERS CLUB, Sec. 12, 16 Res (Fig.. 3-3) 4.4.1:5 Parameter W: Radius of source (Section 3.17)

W = 61m..

4.4.1.6 Parameter L: Length of source (Section 3.17) F L = 9.75 m.

PP8L CALCULATIONSHEET

'I pt Jb! T PROJECT SSES ISFSI Calc. No. EC-ENVR-1025 sate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. of 121 4.4.1.7 Parameter X: Orthogonal distance (east-west) between shield wall and receiver (Table 3-5)

X = 1546' 471.2 m. U1 CST~Residence Sector 7 (Location 1)

X = 2001' 610.1 m. U1 CST~Towers Club (Location 2)

X = 2025' 617.2 m. U1 CST~Residence Sector 16 (Location 3)

X = 5626' 1714.8 m. U1 CST~Residence Sector 12 (Location 4)

X = 2001' 610.1 m. U2 CST-+Towers Club (Location 2)

X = 2025' 617.2 m. U2 CST-+Residence Sector 16 (Location 3)

X = 5626' 1714.8 m. U2 CST~Residence Sector 12 (Location 4) 4.4.1.8 Parameter Z: Offset distance (north-south) to receiver (Table 35)

Z = 1410' 429.8 m. U1 CST~Residence Sector 7 (Location 1)

Z = 2013' 613.6 m. U1 CST~Towers Club (Location 2)

Z = 2841' 855.2 m. U1 CSTwResidence Sector 16 (Location 3J Z = 2211' 673.9 m. U1 CSTwResidence Sector 12 (Location 4)

Z = 1575' 480.1 m. U2 CST~Towers Club (Location 2)

Z = 3349' 1021.0 m. U2 CST~Residence Sector 16 (Location 3)

Z = 1727' 526.5 m. U2 CST~Residence Sector 12 (Location 4) 4.4.1.9 Parameter H; Vertical distance between top of shield wall and receiver.

3 H = 818'00'6' 212' 64.6 m. U1 CST~Residence Sects 7 (Location 1)

H = 729' 700' 6' 23' 7.0 m. U1, U2 CST~Sector 12 Residence, Towers Club (Locations 2, 4)

H = 729' 1010' 6' -275' -83.8 m. U1, U2 CST~Sector 16 Residence (Location 3) Note: 6's added in this case to bring the receiver closer to the source.

i' PPRL CALCULATIONSHEET

)ept. O s. Tech.. PROJECT, SSES ISFSI Calc. No. EC-ENVR-1025 Jate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

.Checked By Sh. No. 55 of 121 4.4.2 Determination of MICROSKYSHINE Input Parameters for Geometry 3; Special Case of U2 CST-+Sector 7 Residence 4.4.2.1 Parameter Y: Depth of source in silo Y = 0.01 m (minimum height:)

4.4.2.2 Parameter T1: Thickness of concrete slab cover (Section 3.17)

T1 = 0.0m.

4.4.2.3 Parameter T2: Thickness of second shield (Section 3.17)

TX = 0.0m 4.4.2.4 Parameter R1: Outer silo radius; distance between U2 CST center and minimum distance to berm (ref. 6.32.5).

f R1 = 43'=13.1 m 4.4.2.5 Parameter W: Radius of source (Section 3.17)

W = 61m, 4.4.2.6 Parameter L: Length of source (Section 3.17)

L = 9.75 m.

4.4.2.7 Parameter X: Direct distance between source center and receiver X is calculated as the hypotenuse of the triangle formed by the orthogonal sides (east-west and north-south distances to the dose point: Table 3-5)

X = [(1546') + (964') ]"

1821.9' 555.3 m.

PP8 L CALCULATIONSHEET

-Qept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 fate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 56 of ~11 4.4.2.8 Parameter H: Vertical distance between top of shield wall and receiver. Shield wall in this case is the top of the CST.

H = (670'+ 32') -600'- 6' 96' 29.3 m.

4.4.3 MICROSKYSHINE is run for Unit 1 and Unit 2 CSTs to all off site locations, using parameters. developed in Section 4.4.1 and Section 4.4.2 using source term from Table 3-4. Results of the runs are included in Attachment 9 (Qhit

1) and 10 (Unit 2). With the exception of the case for U2 CSTmSector 7-residence (Location 1), the results for the other cases range from 1e-8 to 9e-1 3 mR/hr. These results, when integrated for annual exposure (8766 hrs/yr: Section 3.21), are minor relative to skyshine results for the turbine building, thus, theywillbedismissedfromfurtherconsideration. Onlythe result for U2 CST~Sector 7 residence (Location 1) is tabulated for annual contribution to the total dose.

4.4.4 The annual dose to the off site receiver in Sector 7 from CST skyshine using Equation 4-2 (Section 4.3.3): is'alculated Dose(tmmtat) = g [Zap rates(mRthr) e8760 hrtyr]

'3 Dose (annual) = 3.52 e-07 mR/hr 8760 hrlyr

= 3.08 e-03 mrem 4.4.5 fn the beginning of Section 4.4, the major shielding of the CSTs by turbine or reactor buildings is stated for the Unit 1 CST to all locations, and the Unit 2 CST to the Towers Club (location 2), Sector 16 residence (location 3) and Sector 12 residence (location 4). Reference 6.32.3 is reviewed to determine additional natural or man-made obstructions in the direct line-of-sight for these source-receiver combinations. Additional shielding is provided by the U2 Cooling Tower to direct radiation from the CSTs to receivers as follows:

Source Location No./Dose Receiver U1 CST 2. Towers Club U2 CST U1 CST 4. Sector 12 residence U2 CST

PP8 L CALCULATIONSHEET

')ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALG.

Checked By Sh. No 121 The Unit 2 Cooling Tower is a significant additional shield to direct radiation for these receivers, in addition to the turbine building. It is evident here that substantial concrete shielding is in place for all cases except U2 CSTmSector 7 residence (location 1). Thus, while further analysis is required for the U2 CST-+Sector 7 case, direct shine calculations from the CSTs are not justified, based on the available shielding, for the other seven cases: U2 CSTm locations 2, 3 and 4, and U1 CST~ all locations.

4.4.6 For the case of the U2 CSTmSector 7 residence, when references 6.32.7-9 are reviewed to determine that the edge of grade (el. 670') extends approximately to the south access road, (south east from U2 CST). When scaled from reference 6.32.3, the distance from the U2 CST to the south .v access'oad is determined to be 1000 ft. A scale model is prepared showing the U2 CST and the berm wall at grade (670': Section 3.17), the extension of the grade from the U2 CST to the south access road (1000'), the .

orthogonal distance from the U2 CST~Sector 7 residence (1822'. Section 4.4.2.7), and the difference between grade elevation for the U2 CST and the Sector 7 residence: 670' 600' 70'. This model is shown in Figure 4-t-.

When a line is projected from the top of the U2 CST over the berm walhto the Sector 7 residence dose point, it is evident that convergence with grade occurs at approximately 575'rom the CST (within the warehouse buildirig:

reference 6.32.7), which means that direct radiation is absorbed, by gro~ud beyond that point, well within the distance from the U2 CST~Sector 7 residence (1821.9'. Section 4.4.2.7). Therefore, calculation of the contribution of direct radiation from U2 CST-+Sector? residence is nob justified.

4.5 . Direct Shine (MICROSHIELD) Calculations from Turbine Building Components 4.5.1 Reference 6.1 justifies the basis for not calculating the direct shine contribution from certain turbine components. In those cases where the contribution has not been determined, the omission is due to the 'ose component being shielded locally by other components, concrete walls or floor, or else the direct shine contribution is shown to be insignificant relative to other. sources. Review of references 6.28 and 6.32.3 reveals that the line-of-sight paths from both Turbine Buildings to the Towers Club (location

2) and the Sector 12 residence (location 4) are shielded by the Unit 2 Cooling Tower. Consistent with reference 6.1, credit is taken for this shielding effect, and calculations will not be performed for Turbine Building direct shine to these receivers. To determine the shielding available from

PP8 L CALCULATIONSHEET Oept. 0 s. Tech PROJECT SSES ISFSI Gale. No. EC-ENVR-1025

>ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By . OFFSITE DOSE CALC.

Checked By Sh. No. 58 of 121 (4.5.1) other nearby buildings and components, references 6.32.1, 6.32.3 and 6.32.10 were reviewed for the direct line of slight from the major turbine co'mponents to the Sector 7(location 1) and Sector 16 (location 3) residences. Additionally, significant slant path effect (exposure rate reduction achieved by oblique rather than perpendicular transmission through shield walls) is expected for Unit1 sources to the Sector 7 residence, and Unit 2 sources to the Sector 16 residence. Table 4-2a lists the various shielding effects for U1 and U2 turbine components for the Sector 7, residence (southeast of the Turbine Building); the direct shine path for the turbine building-+ Sector 7 residence is through the east shield wall (ref. 6.32.3). Table 4-2b shows the shielding effects for the Sector 16 residence (northwest of the Turbine Building. Based on this evaluation, fqr the turbine building-+ Sector 7 residence, calculations will be performeNor the U2 HPT, U2 east cross around piping, U2A LPT, U2 east moisture separator and the U2 east HPT inlet piping (horizontal and vertical). For this location, the east shield wall is the primary (X) axis for cylindrical source behind wall (MICROSHIELD GEOMETRY 9) and point source (MICROSHIELD GEOMETRY 1) configurations. The HPT south (U2) shield wall is the primary (X) axis for the source at end (MICROSHIELD GEOMETRY 10) configuration. For the Sector 16 residence, calculations will be performed for the U1A LPT, U1 HPT, U1 west cross around piping, U1 west CIVs, U1 west CIVwLPT inlet piping, U1 west moisture separator, and the U1 west HPT inlet piping (horizontal and vertical). The direct shine path for the turbine building-+ Sector 16 residence is through the west sbjeld wall (ref. 6.32.3). For the turbine building-+ Sector 16 residence, the west shield wall is the primary (X) axis for cylindrical source behind wall (MICROSHIELD GEOMETRY 9) and point source (MICROSHIELD GEOMETRY 1) configuration. The HPT north (U1) shield wall is the primary (X) axis for the source at end (MICROSHIELD GEOMETRY 10) configuration.

PP8L CALCULATIONSHEET

'3ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By Checked By OFFSITE DOSE CALC.

Sh. No. '9 of 121 Table 4-2a: Direct Line of Sight Shielding of Turbine Building Sourcesm Receiver: Sector 7 Residence (Location 1)

Com onent Shieldin Offered b:

U1 A,B,C low ressure turbine Reactor buildin, slant ath effect U1 westcross around i in U1 LPTs, east moist. se, slant ath effect U1hi h ressure turbine Reactor buidlin, slant ath efect U1 east CIVs U1 east moist. se slant ath effect U1 west CIVs U1 LPTs, east moist. se, slant ath effect U1 east CIV~LPT inlet i in U1 east moist. se ~, slant ath effect, floor U1 west CIVmLPT inlet i in U1 LPTs, slant ath effect, floor U1 east moisture se arator Reactor buildin, slant ath efect U1 west moisture se arator Reactor buildin, U1 LPTs, slant ath effect U1 west HPT inlet piping (horizontal) Reactor building, U1 LPTs, U1 east moist. sep.,

slant ath effect U1 east HPT inlet piping (horizontal) Reactor building,'1 east moist. sep., slant path--

effect U1 west HPT inlet piping (vertical) Reactor building, U1 LPTs, U1 east moist. sep.,

slant ath effect U1 east HPT inlet piping (vertical) Reactor building, U1 east moist. sep., slant path .

effect U2 B,C low ressure turbine U2 east moist. se .

U2westcross around i in U2 LPTs U2 east moist. se .

U2 east CIVs U2 east moist. se ., floor U2 west CIVs U2 LPTs east. moist. se ., floor U2 east CIV-+LPT inlet i in U2 east moist. se ., floor U2 west CIV-+LPT inlet i in U2 LPTs, floor U2 west moisture se arator U2 LPTs U2 west HPT inlet i in horizontal U2 hi h ressure turbine U2west HPT inlet i in vertical U2 hi h ressure turbine

PP8 L CALCULATIONSHEET

")ept. 0 s. Tech. PROJECT SSES ISFSI Calc. No. EC-ENVR-1025 Jate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 121 Table 4-2b: Direct Line of Sight Shielding of Turbine Building Sourcesw Receiver: Sector 16 Residence (Location 3)

Com onent Shieldin Offered b:

U2 A B,C low ressure turbines U2 moist. se . shield anels, slant ath effect U2eastcross around i in U2 LPTs, alternator-exciter, slant ath effect U2west cross around i in U2westmoist. se .

U2 hi h ressure turbine U2 west moist. se .

U2 east CIVs U2 LPTs, generator, alternator-exciter, slant paà effect U2 west CIVs U1 coolin tower U2 east CIV-+LPT inlet piping U2 LPTs, generator, alternator-exciter, slant path effect U2west CIV-+LPTinlet i in U1 coolin tower U2 east moisture separator U1 west moist. sep., U2 generator, alternator-exciter U2 west moisture se arator U1 coolin tower U2 west HPT inlet i in horizontal U1 coolin tower U2 east HPT inlet i in horizontal U1 west moisture se arator, slant ath effect U2 west HPT inlet i in vertical U1 coolin tower U2 east HPTinlet i in vertical U1 west moisture se arator, slant ath effect U1 east cross around i in U1 low ressure turbines exce t 'A'1 U1 LPTs, HPTs moist. se . shield anels, slant ath effect U1 east CIVs U1 LPTs, HPTs U1 west CIVs exce t CIV - 4 U1 west moisture se arator, slant ath effect U1 east CIV~LPTinlet i in U1 LPTs, HPTs U1 east moisture se arator U1 LPTs, HPTs U1 east HPT inlet i in horizontal U1 hi h ressure turbine U1 east HPT inlet i in vertical U1 hi h ressure turbine

PPS L CALCULATIONSHEET a pt. she. T h. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 iate 10/1/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No 61 of 121 4.5.2 Shielding Slant Path (t,~ ) Calculations In reference 6.1, credit is taken for the increase in shielding offered by the slant path through concrete shields (t,~. MICROSHIELD parameter T3) for HPT, LPT and Moisture Separators, Slant path calculations are performed in this section for the sourcewreceiver combinations confirmed to be direct shine paths in Section 4.5.1. The effective shield thickness is determined, as shown in Ref. 6.1 Figure 9:

h = (Elevanonaisourcecenierline Ele-vaiionaidosepoinii Eq. 4-3 d= a'+z'+h'hree dimensional approximation Eq. 4-4 Eq. 4-5 v

where a = distance from source-+dose point along major axis; z = distance from source.-+dose point perpendicular to major axis; t = uncorrected concrete shield wall thickness (3.0'or west shield wall; 3.'"

for east shield wall: Section 3.33; add 2.0'or LPT/HPT inlet piping side shielding, east and west walls: ref. 6.1 Fig. 2).

d =slant path which includes t,g plus slant paths from other shield components, including air gap. For the purposes of this calculation, the minor addition of distance (air gap, distance through pipe wall) due to slant path between source and concrete shield (vs. orthogonal distance) is neglected. This omission is insignificant, and permits simple

'alculation of MICROSHIELD parameter X. For MICROSHIELD geometry 10, X is taken as the distance from the outermost shield to the receiver point. For MICROSHIELD geometries 8 (cylinder source from side/slab shield) and 9 (cylinder from side/combination shield), parameter X is equal to "d", since X includes all shields, including the source radius for these geometries. For MICROSHIELD geometries 8, 9 and 10 used herein, "d" is determined using a three-dimensional approximation (Eq. 4-4), since slant path, vertical and perpendicular offsets must be incorporated.

PPB L CALCULATlONSHEET pt.

ate

~Td 9/12/96

. PROJECT SSES ISFSl FUEL CYCLE40CFR190 Gale. No.

EC-ENVR-1025 Rev.0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 62 of ~11 II For the cases of cross around piping, which use a point source/slab configuration (MICROSHIELD geometry 1), parameter Y represents the offset from the major source axis, on both perpendicular and vertical axes.

This two-dimensional displacement is adjusted for by:

F= Eq. 4W

~z'+h'.5.2.1 U2 HPT~Sector 7 Residence (Location 1):

h a

128.0'4

= I (Elevation at HPT floor level + HPT radius) dose point I

= 1[729'+ 5'(Section 3.5.5)

=

-600'-6'I

- Elevation at

= longitudinal distance from south end of U2 HPT-+dose point

= distance U2 HPT->column 41 + distance column 41~

column 46 + distance column 46-+ outside TB wall +

. distance outside TB wall-+ dose point

= -(0.5 *21') + 3.6'+ 90'+ 9" + 875'Table 3-5, Ref. 6.1 Figs.

1, 5)

= 958.9'

= lateral distance U2 HPT~ dose point

= distance U2 HPT-+column J + distance column J~ colBnn K + distance column K-+ column N + distance column N~

outside TB wall + distance outside TB wall-+ dose point

= 21' 32' 62'3"+ 9" + 1607'Table 3-5, ref. 6.1 Figs. 1, 6)

= 1723.0'

[(128.0) +(958.9') +(1723.0) j

= [3.90 e6]" = 1976.0'~

= 3'1 976.0'/958.9'j = 6.18'. 188.4 cm.

PPSL CALCULATlONSHEET

'1 pt.

ate

~Th.

9/12/96 PROJECT SSES lSFSI FUEL CYCLE 40CFR1 90 Gate. No. EC-ENVR-1025 Rev. 0 Designed By OFFSlTE DOSE CALC.

Checked By Sh. No. 63 of ~12 4.5.2.2 U2 East Cross Around Piping-+ Sector 7 Residence (Location 1):

h = I Elevation at CAP floor level - Elevation at dose point I

= ) [749'ref. 6.1 Fig. 4) ] - 600' 6'

= 143.0':

z = longitudinal distance U2 east cross around piping ~ dose point

= - (distance U2 east cross around piping -+column 37) + ~

distance column 37-+ column 41 + distance column 4~~

column 46 + distance column 46~ outside TB wall +

distance outside TB wallm dose point (Table 3-5, ref. 6.1 Figs. 1,4, 5)

- 7.2' (2

• 36') + 90' 9" + 875' 1030.6'

= [(143.0) + (1030.6') ]

[1.08 e6]"

1040.0'.5.2.3 U2A Low Pressure Turbine~ Sector 7 Residence (Location 1):

h = l (Elevation at LPT floor level + LPT radius) - Elevation at~

dose point I 3.5.6) -600'6'I I [729'+ 11.8'Section

= 134.8'

= longitudinal distance U2A LPT~dose point

= - (distance U2A LPT-+.column 39) + distance column 39~

column 41 + distance column 4'f -+ column 46 + distance column 46-+ outside TB wall + distance outside TB wall~

dose point

=.-(05*285')+14" +36'+90'+ 9" +875'(Table3-5, Ref.

6.1 Fig. 5)

= 988.7.'

PP8L CALCULATIONSHEET

")ept. O s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 64 of ~12 a = lateral distance U2A LPT-+dose point

= distance U2A LPT~column J + distance column J-+

column K + distance column K~ column N + distance column N-+ outside TB wall + distance outside TB wall~

dose point

= 21'+ 32'+ 62'"+ 9" +1607'Table 3-5, ref. 6.1 Fig. 1)

= 1723.0'

= [(134.8) +(988.7') +(1723.0') ]

= (3'") [1991.1'/1 723.0'] = 3.76' ',~

114.5 cm.

d = [3.96e6]

'=1991.1'.5.2.4 U2 East Moisture Separators Sector 7 Residence (Location 1);-

h = I (Elevation at U2 EMS floor level+ EMS radius) - Elevation at dose point I

= ) [729'+ 5.35'Section 3.5.1) -600'6'] I

= 128.4'

= longitudinal distance U2 EMS-+dose point

= distance U2 EMS-+ column 40 + distance column 40-+

column 42+ distance column 42~ column 46 + distance column 46~ outside TB wall + distance outside TB wal&

dose point

= (18'+ 3'+ 6.5') + 36'+ 72'+ 9'+ 875'Table 3-5, Ref. 6.1 Figs. 1, 3)

= 1011.3'

= lateral distance U2 EMS-+dose point

= distance U2 EMS-+ column K+ distance column K~ column N + distance column Nm outside TB wall + distance outside TB wall + dose point

= (53'44.5') + 62'"+ 9" + 1607'Table 3-5, Section 3.5.1, ref. 6.1 Fig. 1)

.= 1678.5'

PP8L CALCULATIONSHEET

")ept. 0 s. Tech. PROJECT SSES ISFSI Calc. No. EC-ENVR-1025 iate 10/1/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 65 of 121 d = [3.86 e6]" = 1963.8',g

= 3'" [1963.8'/1678.5'] ='3.80' 115.9 cm.

4.5.2.5 U2 East HPT Inlet Piping (Horiz) -+ Sector 7 Residence (Location 1):

h z

= 134.8'3

= I (Elevation at U2E HPT horiz. inlet piping center above floor level) - Elevation at dose point I

= I [729'+ (11.75': Section 3.5.7) -600'6'] I

= longitudinal distance U2E HPT horiz. inlet piping nodose point

= distance U2E HPT horiz. inlet piping wcolumn 41 + distance column 41-+ column 46 + distance column 46m outsider'B wall + distance outside TB wall-+ dose point

- = 3.6'+ 90'+ 9" + 875'Table 3-5, Ref. 6.1 Figs. 1, 5)

= 969.4'

= lateral distance U2E HPT horiz. inlet piping -+ dose point

= distance U2E HPT horiz. inlet piping -+column J + distance column Jm column K + distance column K > column I9 +

distance column M-+ outside TB wall + distance outside TB wallw dose point

= (21'-107") + 32'+ 62'"+ 9" + 1607'Table 3-5, ref. 6.1 Figs. 1, 6)

= 1714.1' d =[(134.8) +(969.4') +(1714.1') ]

= [3.90 e6]" = 1973.8'

>> = (3'") " [1973.8'/1714.1'] = 3.74' 114.0 cm.

'lept.

ate 0 s. Tech.

10/1/96 esigned By Checked By PP8L CALCULATIONSHEET PROJECT SSES ISFSI FUEL CYCLE 40CFR190 OFFSITE DOSE CALC.

'ev.

Gale. No.

Sh. No.

EC-ENVR-1025 66 0

of 121 4.5.2.6 -

U2 East HPT Inlet Piping (Vert) -+ Sector 7 Residence (Location 1):

h = I (Elevation at U2E HPT vert. inlet piping center above floor level) - Elevation at dose point I

= I [729'+ (8.25"0.5) (Section 3.5.7) - 600' 6'] I

=

127.1'ote:

Parameters "a" and "d" for U2E HPT vert. inlet piping are the same as those developed for U2E KPT horiz. inlet piping (Section 4.5.2.5), since the component centerline distances are effectively the same, based on the model presented in-ref. 6.1 Fig. 6.

d = [(127.1) + (969.4') + (1714.1') ] '

= [3.89 e6]" = 1973.3',>>

= (3'") [1973.3'/1714.1'] = 3.74' 114.0 cm. (The slight change in height of the HPT vertical inlet piping vs. that for horizontal has no effect here) ~

4.5.2.7 U1 HPTmSector 16 Residence (Location 3):

h = I (Elevation at HPT floor level + HPT radius) - Elevatiorrat dose point I

= I [729'+ 5'Section 3.5.5) -1010'+ 6'] I

= 270.0'

= longitudinal distance U1 HPT-+dose point

= distance U1 HPTmcolumn 17 + distance column 17~

column 12+ distance column 12-+ outside TB wall +

distance outside TB wall-+ dose point

= 3.6'+ 90'+ 9" + 2800'Table 3-5, ref. 6.1 Figs. 1, 5)

= 2894.4'

PP&L CALCULATIONSHEET

")ept. 0 s. Tech. PROJECT SSES ISFSI Calc. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CAI C.

Checked By Sh. No. of 121 z = lateral distance U2 HPT~dose point

= distance U2 HPT~column Gd + distance column Gd~

'olumn 6 + distance column Gwoutside TB wall+ distance outside TB eall-+ dose point

= 21'+ 27'+ 3'" + 1786'Table 3-5, ref. 6.1 Figs. 1, 6)

= 1837.8'

= [(270.0') + (2894.4) + (1837.8) ]

= [1.18 e7]" = 3439.2',>>

= 3.0'3439.2'/2894.4'] = 3.56' 108.7 cm.

~ '4 4.5.2.8 U1A Low Pressure Turbine-+ Sector 16 Residence (Location 3):

h = I (Elevation at LPT floor level + LPT radius) - Elevation at" dose point I

= I [729'+ 11.8'Section 3.5.6) - 600'+ 6'

= 146.8'

= longitudinal distance U1A LPTmdose point

= - (distance U1A LPTm column '19) + distance column 19~

column 17 + distance column 17m column 12+ distance-column 12m outside TB wall + distance outside TB wall~

dose point

-.= - [(0.5 *28.5') + 14"]+ 36'+ 90'+ 9" + 2800'Table 3-5, Ref. 6.1 Fig. 5)

= 2911.3'

= lateral distance U1A LPT~dose point

= distance U1A LPTmcolumn Gd + distance column Gd-+

column G + distance column G-+ outside TB wall + distance outside TB wall-+ dose point

= 21'+ 27'+ 3'" + 1786'Table 3-5, ref. 6.1 Fig. 1)

= 1837.8'

=[(146.8) +(2911.3') +(1837.8') ]'

= [1 19~ e7]" = 3446.0'

PP8L CALCULATIONSHEET

't pt. Jla .p p. PROJECT SSES ISFSI Gale. No., EC-ENVR-1025 sate 10/1/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By . Sh. No. of t,>> = 3' [3446.0'/1 83?.8'] = 5.63' 171.5 cm.

4.5.2.9 U1 West Cross Around Piping'ector 16 Residence (Location 3):

h = Elevation at CAP floor level - Elevation at dose point I

[?49'ref. 6.1 Fig. 4) ] -1010'+ 6'

= 255.0'

= longitudinal distance U1 west cross around piping ~ dose point

= - (distance U1 west cross around piping ~column 21) +

column 21m column 18 + distance column 18~ 'istance column 16 + distance column 16-+ column 12 + distance column 12-+outside TB wall + distance outside TB wall~

dose point (Table 3-5, ref. 6.1 Figs. 1,4, 5)

= -7.2'+ 54'+36'+ 72'+ 9" + 2800' ~

= 2955.6'

= [(255 0'P + (2955 6')']"

= [8.80e6]

'=2966.6'.5.2.10 U1 West CIV - 4m Sector 16 Residence (Location 3):

h = Elevation at CIV floor level - Elevation at dose point I

[736'" (ref. 6.1 Fig. 4) ] - 1010'+ 6'

= 267.4'.

z = longitudinal distance U1 west CIV - 4m dose point

~

= U1 CIV-4 column 19+ distance column 19-+ column 16

+ distance column 16~ column 12 + distance column 12~utside TB wall .+ distance outside TB walt-+ dose point (Table 3-5, ref. 6.1 Figs, 1, 5, ref. 4.5.2.10)

= 14 +(3 18')+ 72' 9' 2800'2927.9'

PP8L CALCULATIONSHEET

'I pt.

sate

~Th.

10/1/96 PROJECT SSES ISFSI FUEL CYCLE 40CFR190 Gale. No. EC-ENVR-1025 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No, 69 of ~11 a = lateral distance U1 west CIV -4m dose point

= distance U1 west CIV +column G + distance column Gwoutside TB wall + distance outside TB wall-+ dose point (Section 3.31, Table 3-5, ref. 6.1 Figs. 1, 2, 4, 5)

= 23'+ 3'" +1786' 1812,8'

[(267.4') + (2927.9') + (1812.8') ]

[1.19 e7]" =

3' [3454.0'/1 812.8']

3454.0'.5.2.11 5,7274.2 cm.

U1 West CIV/LPT Piping-+ Sector 16 Residence (Location 3):--

= [ Elevation at CIV/LPT piping floor level - Elevation at dose potntl

= [729'ref. 6.1 Fig. 4) ] -1010'+6'I 1

= 275.0'

= longitudinal distance U1 west CIV dose point ~

= (U1 CIV/LPT piping C.L. on column line 21)+ distance column 21-+ column 18+ distance column 18-+ column 16

+ distance column 16-+ column 12+ distance column 12-+outside TB wall + distance outside TB wall~ dose ~

point (Table 3-5, ref. 6.1 Figs. 1,4, 5)

= 54'+36'+ 72'+ 9" + 2800' 2962.8'

= lateral distance U1 west CIV-+ dose point (U1 west CIV C.L.

on column line Gd ) + distance column Gd-+ column G +

distance column G >outside TB wall + distance outside TB wall-+ dose point (Table 3-5, ref. 6.1 Figs. 1, 2, 4, 5)

= 27' 3'" + 1786' 1816.8'

= [(275.0') + (2962.8') + (1816.8') ]

d = [1.22e7] '3486.3'

Oi PPBL CALCULATIONSHEET

'I pt. Jla: T h. PROJECT SSES lSFSf Calc. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSlTE DOSE CALC.

Checked By Sh. No. 70 of 121 t,< = 3' [3486.3'/1 816.6'] = 5.76' 175.5 cm.

4.5,2.12 U1 West Moisture Separator~Sector 16 Residence (Location 3):

h = Elevation at WMS - Elevation at dose point+ 6'I 736' 1010' 6'

= 268.0'

= longitudinal distance U1 WMS-+cjose point

= distance U1 WMS-+column 'I 8 + distance column 18~ ':

column 12 + column 12-+ outside TB wall + distance outside TB wall-+ dose point

= (18'+ 3'+ 6.5') + (36'+ 72') + 9" + 2800'ref. Table 3-5, ref.

e 6.1 Figs. 1, 3)

= 2936.3'

= lateral distance U1 WMS centerline-+dose point

= distance WMS ->column G + distance column G~outsidg TB wall + distance outside TB wallw dose point

= (?.5'+ 1.0') + 3'- 9" + 1?86'ref. Table 3-5, ref. 6.1 Figs. 1; 3)

= 1798.3'

= [(268.0') + (2936.3) + (1798.3) ]

= [1.19 e7]" = 3453.6'ee

= 3.0 [3453.6'/1798.3] = 5.76' 175.6 cm.

4.5.2,13 U1 West HPT inlet Piping (Horiz)-+ Sector 16 Residence (Location 3):

h = I (Elevation at U1W HPT horiz. inlet piping center above floor level) - elevation at dose point I

= I [729'+ (11.75'*0.5: Section 3.5.7) -1010'+ 6'] I

= 269.1'

PP8 L CALCULATIONSHEET Rept. 0 s. Tech. PROJECT SSES ISFSI Calc. No. EC-ENVR-1025 iate 10/1/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 71 of ~12

z. = longitudinal distance U1W HPT horiz. inlet piping ~dose point

= distance U1W HPT horiz. inlet piping ~column 17 +

distance column 17-+ column 12 + distance column 12~

outside TB wall + distance outside TB wallw dose point

= 3.6'+ 90'+ 9" + 2800'Table 3-5, Ref. 6.1 Fig. 1, 5)

= 2894.4'

= lateral distance U1W HPT horiz. inlet piping m dose point>

= distance U1W HPT horiz. inlet piping -+column Gd +

distance column Gd-+ column 6 + distance column G~

outside TB wall + distance outside TB wallm dose point---

= 21'107" + 27'+ 3'" +1786'Table 3-5, ref. 6.1 Figs. 1, 6)

= 1828.8'

= [(269.1') + (2884.4) + (1828.6)z~o.s

= [1.18 e7]" =.

3434.2'e>>

= (3') * [3434.2'/1 828.8J = 5.63' 171.6 cm.

g 4.5.2.14 U1 West HPT Inlet Piping (Vert.)-+ Sector 16 Residence (LocaNpn 3):

Based on identical results obtained in Sections 4.5.2.5 and 4.5.2.6 for U2 east horizontal and vertical HPT inlet piping, t,>> for U1 west inlet piping (vertical) is taken to be 171.6 cm.

4.5.3 MICROSHIELD Parameter Calculations 4.5.3.1 U2 HPT-+Sector 7 Residence (Location 1)

MICROSHIELD geometry used: 10.(cylinder from end/slab shield) 4.5.3.1.a Parameter R: Source cylinder radius R = 5.0' 152.4 cm. (Section 3.5.5) 4.5.3.1.b Parameter T1: Source cylinder length

PP8 L CALCULATIONSHEET

'1pL Jlg.T PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 iate 10/1/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE GALG.

Checked By Sh. No. 72 of 121 T1 = 21.0' 640.1 cm. (Section 3.5.5) 4.5.3.1.c Parameter TZ: Thickness of second shield T2 = 3" iron = 7.62 cm. (Section 3.5.5) 4.5.3.1.d Parameter T3: Concrete shield (t.~}

T3 = 6.18' 188.4 cm. (Section 4.5.2.1) 4.5.3.1.e Parameter T4, T5 not used.

4.5.3.1.f Parameter X: Distance to receiver X d+T1 (1976.0'0.48 cm/ft) + 640.1 cm (Sections 4.5.2.1, 3.5.5) 60868.6 cm.

4.5.3.1.g Source density = 4.17 g/cm (water: Section 3.5.5)'-.

. U2 East Cross Around Piping-+ Sector 7 Residence (Location f) '.5.3.2 MICROSHIELD geometryused: 1(pointsource/slabshield} -

-':3 4.5.3.2.a Parameter T1: Air gap between point source and slab shield (concrete)

T1 = [(14.75'+ 5': ref. 6.1 Figs. 1, 4} *30.48 cm/ft]

602.0 cm.

4.5.3.2.b Parameter T2: First shield beyond air gap (pipe wall)

T2 = 0.375" iron (1.0 cm: Section 3.5.2}

4.5,3.2.c'arameter T3: Concrete shield (t.g)

T3 = 3.25' 99.1 cm (ref. 6.1. Fig. 2) 4.5.3.2.d Parameters T4, TS: Not used

." 'I pt.

>ate

~T 9/12/96 PP8L CALCULATIONSHEET PROJECT SSES ISFSI FUEL CYCLE 40CFR190 Gale. No. EC-ENVR-1025 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By, Sh. No. 73 of ~12 4.5.3.2.e Parameter X: Distance to receiver from outer shield X (edge of east shield wall: approx. column K) distance column Kw column N + distance column N~ outside TB wall + distance outside TB wallm dose point (Table 3-5, ref. 6.1 Figs.

1,2,4,5) 62'" + 9' 1607'670.0'.5.3.2.f Parameter Y: Dose point offset Y = 1040.0 ft = 31699.2 cm. (Section 4.5.2.2) 4.5.3.2.g Source density: N/A: point source used (Section 3.5.2) 4.5.3.3 U2A Low Pressure Turbine-+ Sector 7 Residence (Location 1)-.

MICROSH)ELD geometry used: 8 (cylinder source from side/stab shield)

'll 4.5.3.3.a Parameter T't: Radius of source T't = 3.6 m = 360 cm (Section 3.5.6).

4.5.3.3.b Parameter T2: First shield beyond source (pipe wall)

T2 = 3.18 cm iron (Section 3.5.6).

4.5.3.3.c Parameter T3: Concrete shield wall thickness (t,~)

TS = 114.5 cm (Section 4.5.2.3).

4.5.3.3.d Parameters T4, TS: Not used, h

4.5.3.3.e Parameter X: Distance to receiver from source center X = "d" = 1991.1' 60688.7 cm (Section 4.5.2.3).

PP8L CALCULATIONSHEET

')ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 date 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By Checked By OFFSITE DOSE CALC.

Sh. No. '4 of ~12 4.5.3.3.f Parameter Y: Offset distance of dose point Y = 0.0 cm (offset has been accommodated in calculation of parameter X).

4.5.3.3.g Parameter L: Source length L = 868 cm (Section 3.5.6) 4.5.3.3.h Source density = 2.0 g/cia (water: Section 3.5.6) -"

4.5.3.4 U2 East Moisture Separators Sector 7 Residence (Location 1)

MICROSHIELD geometry used; 8 (cylinder source from side/st5b shield) 4.5.3.4.a Parameter T1: Radius of source T1 = 1.63 m = 163 cm (Section 3.5.1).

4.6.3.4.b Parameter T2: First shield beyond source (shell wall)

T2 = 1.25" = 3.18 cm iron (Section 3.5.1).

4.5.3.4.c Parameter T3: Concrete shield wall thickness (t,<)

T3 = 115.9 cm (Section 4.5.2.4).

4.5.3.4.d Parameters T4, TS: Not used..

4.5.3.4.e Parameter X: Distance to receiver from source center X = "d" = 1963.8' 59856.6 cm, (Section 4.5.2.4) 4.5.3,4.f Parameter Y: Offset distance of dose point Y = 0.0 cm (offset has been accommodated in calculation of parameter X).

PPB L CALCULATIONSHEET p pt.

Date

~Tp

'0/1/96

. PROJECT SSES ISFSI FUEL CYCLE 40CFR1 SO Calc. No. EG-ENVR-1025 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 75 of ~21 4.5.3.4.g Parameter L: Source length L= 67'.5" = 2051 cm. (Section 3.5.1) 4.5.3.4.h Source density = 4.40 e-1 g/cm'water: Section 3.5.1) 4.5.3.5 U2 East HPT Inlet Piping (Horiz) ~ Sector 7 Residence (Location 1): MICROSHIELD geometry used: 10. (cylinder from end/slab>

shield) 4.5.3.5.a Parameter R: Source cylinder radius R = 12.75" = 32.0 cm. (Section 3.5.7) 4.5.3.5.b Parameter T1: Source cylinder length T1 = 11.75' 358.1 cm. (Section 3.5.7)

'p 4.5.3,5.c Parameter T2: Thickness of second shield (pipe wal(

I T2 = 1.25" iron = 3.20 cm. (Section 3.5.7) 4.5,3.5.d Parameter T3: Concrete shield (t,~)

T3 = 3.74' 114.0 cm. (Section 4.5.2.5) 4.5.3.5.e Parameters T4, T5: Not used.

4.5.3.5.f Parameter X: Distance to receiver X d - (T1 + T2 + T3) 1973.8'* 30.48 cm/ft - (358.1 + 3.20+ 114.0 cm: Section 4.5.2.5) 5S686.1 cm.

4.5.3.5.g Source density = 3.32 e-2 g/cm'water: Section 3.5.7)

PP8L CALCULATIONSHEET l pL JtlL. T h. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 Date 10/1/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE GALC.

Checked By Sh. No. 121 4.5.3.6 U2 East HPT Inlet Piping (Vert) ~ Sector 7 Residence (Location 1): MICROSHIELD geometry used: 9 (cylinder from side/combination shield) 4.5.3.6.a Parameter T1: Source radius T1 = 12.75" = 32.0 cm. (Section 3.5.7) 4.5.3.6.b Parameter T2: Thickness of second shield (pipe wall)

T2 = 1.25" iron = 3.20 cm. (Section 3.5.7) 4.5.3.6.c Parameter T3; Concrete shield (t,~)

T3 = 3.74' 114.0 cm. (Section 4.5.2.6) 4.5.3.6.d Parameters T4, TS: Not used.

4.5.3.6.e Parameter X: Distance to receiver X = d=1973.8'"30.48cm/ft(Section 4.5.2.5) 60161.4 cm.

4.5,3.6.f Parametqr Y: Offset distance of dose point Y = 0.0cm(offsethasbeenaccommodatedin calculation of parameter X).

4.5.3.6.g Parameter L: Source length L = 8.25' 251.5 cm (Section 3.5.7) 4.5.3.6.h Source density = 3.32 e-2 g/cm'water: Section 3.5.7)

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~ ~

0 I 0

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~ ~

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~ ~ ~

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~ ~ ~

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~ > ~ ~ ~ I

~

~

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~

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~ ~ s ~ ~ ~

E ~

- ~ ~ s ~ ~

~ ~

~ ~

PP8 L CALCULATIONSHEET

")ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 Date 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed Q OFFSITE DOSE CAI C.

Checked By Sh. No. of 4.5.3.8.b Parameter T2: First shield beyond source (LPT shell)

. T2 = 3.18 cm iron (Section 3.5.6).

4.5.3.8.c Parameter T3: Concrete shield wall thickness (t,~):

T3 = 171.5 cm (Section 4.5.2.8).

4.5.3.8.d. Parameters T4, T5: not used.

4.5.3.8.e Parameter X: Distance to receiver from source ceder X = "d" = 3446.0'=105034.1cm(Section 4.5.2.3).

4.5.3.8.f Parameter Y: Offset distance of dose point Y = 0.0 cm (offset has been accommodated for in calculation of parameter X).

4.5.3.8.g Parameter L; Source length L = 868 cm. (Section 3.5.6) 4.5.3.8.h Source density = 2.0 g/cm'water: Section 3.5.6) 4.5.3.9 U1 West Cross Around Piping-+ Sector 16 Residence (Location 3)

MICROSHIELD geometry used: 1 (point source/slab shield) 4.5.3.9.a Parameter T1: Air gap between point source and slab shield (concrete)

T1 = [(14.75'+ 5'. ref. 6.1 Figs. 1, 4) 30,48 cm/fthm 602.0 cm.

4.5.3.9.b Parameter T2: First shield beyond air gap (pipe wall)

T2 = 0.375" iron (1.0 cm: Section 3.5.2)

PPB L CALCULATIONSHEET

'lept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 aate 10/1/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFS)TE DOSE CALC.

Checked By Sh. No. 79 of 121 4.5.3.9.c Parameter T3: Concrete shield T3 = 3.25' 99.1 cm (ref. 6.1 Fig. 2) 4.5.3.9.d Parameters T4, T5: Not used 4.5.3.9.e Parameter X: Distance to receiver from outer shield X - (column G-+ inside edge of outer shield wall) + distance column G ~ outside TB vBII +

distance outside TB wallm dose point (Table 3-5, ref. 6.1 Figs. 1, 2, 3, 4)

- 2' 3

1786'?87.8'.5.3.9.f Parameter Y: Dose point offset distance Y = 2811.6 ft = 85697.6 cm. (Section 4.5.2.9) 4.5.3.9.g Source density: N/A: point source used (Section 3:5.2) 4.5.3.10 U1 West CIV - 4m Sector 16 Residence (Location 3)

MICROSHIELD geometry used: 9 (cylinder from side/combinatPon shield) 4.4.3.10.a Parameter T1: Source radius T1 = 3' 91.0 cm. (Section 3.5.3) 4.5.3,10.b Parameter T2: Thickness of second shield (pipe wall)

T2 = 5.0 cm. iron (Section 3.5.3) 4.5.3.10.c Parameter T3: Concrete shield (t,~)

T3 = 5.72' 174.2 cm. (Section 4.5.2.10) 4.5.3.10.d Parameters T4, TS: Not used

~l PP8L CALCULATIONSHEET

'l pL date

~Td 9/12/96

. PROJECT SSES ISFSI FUEL CYCLE 40CFR190 Gale. No. EC-ENVR-1025 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 80 of ~11 4.5.3,10.e Parameter X: Distance to receiver X = "d" = 3454.0' 30.48 cm/ft (Section 4.5.2.10) 105277.9 cm.

4.5.3.10.f Parameter Y: Offset distance of dose point Y = 0.0 cm (offset has been accommodated in calculation of parameter X).

4.5.3.10.g Source density = 6.40 e-3 g/cm (water. Section 3.5.3Q 4.5.3.11 U1 West GIV/LPT Piping-+ Sector 16 Residence (Location 3)

MICROSHIEI D geometry used: 10 (cylinder from end/slab shield}

4.5.3,11.a Parameter R: Source cylinder radius R = 52.0 cm. (Section 3.5.4}

4.5.3.11b Parameter T1: Source cylinder length T1 = 10.0' 304.8 cm. (Section 3.5.4) 4.5.3.11c Parameter T2: Thicknessofsecondshield(CIVwag)

T2 = 0.375" iron = 0.95 cm. (Section 3.5.4) 4.5.3.11.d Parameter T3: Concrete shield (t,~)

T3 = 5.76' 175.5 cm. (Section 4.5.2.11) 4.5.3.11.e Parameters T4, T5: Not used 4.5.3.11.f ParameterX: Distancetoreceiver X d-(T1 + T2+ T3) 3486.3'0.48 cm/ft - (304.8+ 0.95+ 175,5 cm: Section 4.5.2.11) 105781.1 cm.

PP&L CALCULATIONSHEET

'l pt.

Jate

~Th.

9/12/96 PROJECT SSES ISFSI FUEL CYCLE 40CFR190 Gale. No. EC-ENVR-1025 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 81 of 121 4.5.3.11.g Source density = 6.40 e-3 g/cm'water: Section 3.5A) 4.5.3.12 U1 West Moisture Separator-+Sector 16 Residence (Location 3)

MICROSHIELD geometry used: 8 (cylinder source from side/slab shield) 4.5.3.12.a Parameter T1: Radius of source

'1 = 1.63m =163 cm(Section 3.5.1).

4.5.3.12.b Parameter T2: Moist. sep. shell wall thickness T2 = 1.25 " = 3.18 cm iron (Section 3.5.1).

4.5.3.12.c Parameter T3: Concrete shield wall thickness (t.~)

T3 = 175.6 cm (Section 4.5.2.12).

4.5.3.12.d. Parameters T4, TS: not used.

P 4.5.3.12.e Parameter X: Distance to receiver from source center X = "d" = 3453.6'Section 4.5.2.12) 105265.7 cm.

4:5.3.12.f Parameter Y: Offset distance of dose point Y = '.0 cm (offset has been accommodated in calculation of parameter X).

4.5.3.12.g Parameter L'. Source length L = 67'.5" = 2051 cm. (Section 3.5.1) 4.5.3.12.h Source density = 4.40 e-1 g/cm'water: Section 3.5.1)

'l pt.

Date

~Th..

9/12l96 Designed By Checked By PP8 L CALCULATIONSHEET PROJECT SSES ISFSI FUEL CYCLE 40CFR190 QFFSITE DOSE CALC.

'ev.

Calc. No.

Sh. No.

EC-ENVR-1025 82 0

of ~2

~

4.5.3.13 U1 West HPT Inlet Piping (Horiz) Sector 16 Residence (Location 3}: MICROSHIELD geometry used: 10 (cylinder from end/slab shield) 4.5.3.13.a Parameter R: Source cylinder radius R = 12.75" = 32.0 cm. (Section 3.5.7) 4.5.3.13.b Parameter T1: Source cylinder length T1 .=, 11.75' 358.1 cm. (Section 3.5.7) 4.5.3.13.c Parameter T2: Thickness of second shield (pipe wall)

T2 = 1.25" iron = 3.20 cm. (Section 3.5.7) 4.5.3.13.d Parameter T3: Concrete shield (t,<)

T3 = 5.63' 1?1.6 crn. (Section 4.5,2.13) 4.5.3.13.e Parameters T4, TS: not used 4.5.3.13.f Parameter X: Distance to receiver X = "d" = 3873.8' 30.48 cm/ft (Section 4.5.2.13) 104674.4 cm.

4,5.3.13.g Source density = 3.32 e-2 g/cm'water: Section 3.5.?)

4.5.3.14 U1 West HPT Inlet Piping (Vert.}m Sector 16 Residence (Location 3): MICROSHIELD geometry used: 9 (cylinder from side/combination shield)

. 4.5.3.14.a Parameter T1: Source radius T1 = 12.75" = 32.0 cm. (Section 3.5,7) 4.5.3.14.b Parameter T2: Thickness of second shield (pipe wall)

T2 '= 1.25" iron = 3.20 cm. (Section 3.5.7)

PPB L CALCULATIONSHEET

'lept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 9/12/96 'ate FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 83 of 121 4.5.3.14.c Parameter T3: Concrete shield (t.~)

T3 = 5.63' 171.6 cm. (Section 4.5.2.13/14) 4.5.3.14.d Parameters T4, TG: not used.

4.5.3.14.e Parameter X: Distance to receiver X = d-(T1 +T2+T3) 3434.2'30.48 cm/ft - (32.0+ 3.20+ 171.6 cm: Section 4.5.2.13/14) 104467.6 cm.

4.5.3.14.f Parameter Y: Offset distance of dose point Ol Y = 0.0 cm (offset has been accommodated forJn calculation of parameter X).

4.5.3.14.g Parameter L: Source length L = 8.25' 251.5 cm (Section 3.5.7) 4.5.3.14.h Source density = 3.32 e-2 g/cm'water: Section 3.5.7) 4.5.4 MICROSHIELD is run for all source/receiver combinations developed ih Sections 4.5.3.1-4.5.3.14 (total 14 runs) and the source terms from Table 3-

1. The IVIICROSHIELD geometries, file name coding, and the results for sources/receivers (mR/hr) are shown in Table 4-2c. Results of the runs are included in Attachments 11 and 12.

4.5.5 The annual dose from all turbine direct shine components is determined for each receiver using Equation 4-2 (Section 4.3.3). The annual dose (mrem) for each receiver is shown in Table 4-2c.

ate esigned By Checked By'P8

')ept. 0 s. Tech 9/12/96.-

L CALCULATIONSHEET PROJECT SSES ISFSI FUEL CYCLE 40CFR190 OFFSITE DOSE CALC.

Calc. No.

Sh. No..

EC-ENVR-1025 Rev. 0 84 of 121 Table 4-2c: MICROSHIELD Run Results: Turbine Building Sources Receiver Source Identification Geometp MSH File Result Multiplication Adj. Result Location No. Name mR/hr Factor mR/hr

1. Sector 7 U2 HPT 10 U2HPT7 6.45e-09 6.45e-09

1. Sector 7 U2 east CAP U2ECAP7 6.05e-05 6.05e-05

1. Sector 7 U2A LPT U2ALPT7 1.13e-07 1.13e-07

1. Sector 7 U2 east moisture se arator U2EMS7 1.92e-05 1.92e-05

1. Sector 7 U2eastHPTinl. n . horiz 10 U2EHIP7 2.88e-07 2.88e-07

1. Sector 7 U2 east HPTinl. n . vert. U2EVIP7 1.87e-07 1.87e-07.

TOTAL = 8.03e-05 ANNUAL= 7.03e-Ot .

mrem '.

Sector 16 U1 HPT 10 U1HPT16 6.29e-08 6.29e-08"'.75e-10

3. Sector 16 U1A LPT U1ALPT16 3.75e-10

3. Sector 16 U1 west CAP U1WCAP1B 1.07e-07 1.07e-07

3. Sector 1B U1 west CIVs U1WCIV16 5.70e-09 1.71e-08

3. Sector 16 U1 west CIV~LPT i in 10 U1WCLP16 2.23e-08 6.69e-08

3. Sector 16 U1 west moist. se . U1WMS16 5.10e-08 5.10e-OK

3. Sector16 U1 west HPT inl. n . horiz . '10 U1WHIP16 2.23e-08 2.23e-08

3. Sector1B U1 west HPTinl. n . vert. U1WVIP16 1.50e-08 1.50e-08 TOTAL = 3.43e-O ANNUAL= 3.00e-03 mrem ~

'Reference Section 3.9

PPBL CALCULATIONSHEET .

")ept. 0 s: Tech. PROJECT SSES ISFSI Gale. No, EC-ENVR-1025

'5 iate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. of 121 4.6 Airborne Effluent Data Base Creation 4.6.1 SSES Semiannual and Annual Effluent and Waste Disposal Reports (refs.

6.3-6.24a, tables as applicable) provide historical airborne effluent information from which to create a data base. The maximum effluent value for each isotope is identified for quarterly and annual data. Although the maximum effluent for all isotopes was not actually released in any particular quarter or year, the use of this approach provides a bounding, conservative source term for use in the dose calculations.

4.6.2 A data base is created in EXCEL 5.0 (reference 6.43) which contains quarterly airborne effluent quantities reported for SSES between Septernler,

. 1982, (SSES Unit 1 Initial Startup) and December 1994. For each year, -.

isotope activities (Ci) for particulate, iodine are entered (only two quarters reported in 1982). Annual activity totals, tritium and noble gas reported for each quarter of that year are determined by summing activities from the--

constituent quarters. This process is repeated for every year through 1994 inclusive. (Tritium was not reported released until the fourth quarter of 1983).

4.6.3 Effluent data for previous periods not available at the time the SAE&WD or AE8WD Reports were issued are entered from the appropriate tables to the data base as necessary, per Section 3.12. The data base is listed in Table 4-3.

4.6.4 The maximum activity for each isotope is selected from the data base. The selection considers all quarters and years. The results of this sort are shown in Table 4-3 (Page 7 of 7). These values are to be used as the .

source terms in Section 4.7 for airborne effluent dose calculations to Members of the Public at selected locations.

PP8L CALCULATIONSHEET hept. 0 s. Tech.. PROJECT SSES lSFSl, Calc. No. EC-ENVR-1025 Jate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 86 of 121 Table 4-3: Airborne Effluent Data Base from 1982-1994 Inclusive (Ci)(Page 1 of 7}

PERIOD Q3 Q4 Al I Q2 Q3 Q4 ALL Isotope 1982 1982 1982 1983 1983 1983 1983 1983 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.94E+00 2.94E+00 F-18 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.67E+01 O.OOE+OO Cr-51 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.97E-05 O.OOE+00 4.80E-05 7.77E-05 Mn-54 O.OOE+00 O.OOE+OO O.OOE+OO O.OOE+OO 9.88E%7 O.OOE+00 3.26E<5 3.36E-05 Fe-59 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Co-58 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.08E-05 O.OOE+00 5.69E-05 8.77EZ Co%0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 1.29E-05 1.29E-05 Zn<5 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.DOE+00 O.OOE+00 O.OOE+OO Sr-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Sr-90 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOF+00 O.OOE+00 O.OOF+00 O.OOE+00 Ag-110m 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 I-131 0.00E+00 6.76E-07 6.76E-07 O.OOE+00 O.OOE+00 O.OOE+00 7.31E-04 7.31E-04 1-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 5.43E-04 5.43E-04 Cs-137 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 '-

Kr<5m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 ~

Kr-87 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 Kr<8 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 Xe-127 4.29E+00 O.OOE+00 4.29E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 Xe-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 5.54E+01 5.54E+01 Xe-133m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+.

Xe-135 0.00E+00 0.00E+00 0.00E+00 4.64E-01 0.00E+00 0.00E+00 3.05E+01 3.10E+01 Xe-138 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00

PP8 L CALCULATIONSHEET

'lept. 0 s. Tech. PROJECT SSES ISFSI Calc. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 87 of 121 Table 4-3: Airborne Effluent Data Base from 1982-1994 Inclusive (Ci)(Page 2 of 7)

PERIOD 10 12 13 14 Q1 Q2 Q3 Q4 ALL Q1 Q2 Q3 Q4 ALL Isotope 1984 1984 1984 1984 1984 '985 1985 1985 1985 1985 3.29E+00 9.75E+00 6.46E+00 1.72E+01 3.67E+01 5.01E+00 1.39E+01 1.95E+01 3.94E+01 7.78E+01 F-18 O.OOE+00 1.91EZS 0.00E+00 0.00E+00 1.91E-05 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 Cr-51 2.23EAS 3.96E-05 0.00E+00 2.21E-03 2.27E-03 2.38E%2 8.58EZS O.OOE+00 2.76E%4 2.42E-02 Mn-54 1.36E<4 9.35E-06 9.00E-06 O.OOE+00 1.54E%4 2.16MI4 O.OOE+00 3.85E%6 1.79E-06 2.22E-04 Fe-59 3.01E-OS O.OOE+00 O.OOE+00 O.OOE+00 3.01E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OGE+0 Co-58 8.07E-05 0.00E+00 0.00E+00 2.71E-05 1.08E-04 3.22E-04 0.00E+00 0.00E+00 0.00E+00 3.22E-O Co%0 8.36EAS O.OOE+00 O.OOE+00 O.OOE+00 8.36E-OS 2.36E-04 1.50E-04 0.00E+00 2.54&)6 3.89E-O Zn45 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.32E-04 0.00E+00 O.OOE+00 0.00E+00 2.32E-04 Sr-89 O.OOE+00 3.33E-06 7.20E-06 6.75E-06 1.73E-05 2.24E-OS O.OOE+00 0.00E+00 0.00E+00 2.24E-OS Sr-90 O.OOE+00 0.00E+00 1.41E-08 1.34E-08 2.75E-08 0.00E+00 O.OOE+00 O.OOE+00 2.03E-08 2.03E48 Ag-110m 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.08E<4 0.00E+00 3.48E-OS 0.00E+00 1.43E-04 l-131 O.OOE+00 3.20E-03 8.94E-03 0.00E+00 1.21E-02 3.82M@ 0.00E+00 1.09E-05 7.53EZ4 1.15E:03 I-133 2.28&)5 2.92E<3 7.23E-03 1.11E-04 1.03E-02 5.52E<4 0.00E+00 1.66E<5 5.31E-05 6.22E-04 Cs-137 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.04E~ 0.00E+00 O.OOE+00 O.OOE+00 1.04E-G6 Ar<1 0.00E+00 4.90E+00 O.OOE+00 O.OOE+00 4.90E+00 0.00E+00 0.00E+00 0.00E+00 7.66E+00 7,66E+00 Kr-85m 0.00E+00 5.13E+00 1.04E+01 2.60E+00 1.81E+01 O.OOE+00 0.00E+00 0.00E+00 2.61E+01 2.61E+01 Kr<7 0.00E+00 1.39E<1 0.00E+00 0.00E+00 1.39E-01 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 Kr-88 O.OOE+00 2.28E+00 1.23E+01 3.08E+00 1.77E+01 0.00E+00 0.00E+00 0.00E+00 6.35E-01 6.35E-01 Xe-127 0.00E+00 O.OOE+00 .O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E'+00 Xe-133 2.92E+00 4.55E+01 2.51E+01 2.88E+00 7.64E+01 5.34E+00 1.31E+00 1.08E+02 2.26E+02 3.41E+02 Xe-133m O.OOE+00 2.86E%1 0.00E+00 O.OOE+00 2.86E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E 0 Xe-135 2.60E-01 O.OOE+00 O.OOE+00 O.OOE+00 2.60E-01 O.OOE+00 1.22E+01 1.51E+02 0.00E+00 1.63E402 Xe-138 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 3.12E+01 0.00E+00 3.12E+01

PP8 L CALCULATIONSHEET

- 'lept. 0 s Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 88 of 121 Table 4-3: Airborne Effluent Data Base from 1982-1994 Inclusive (Ci)(Page 3 of 7)

PERIOD 15 16 17 18 19 20 21 22 Q1 Q2 Q3 Q4 ALL Q1 Q2 Q3 Q4 ALL Isotope. 1986 1986 1986 1986 1986 1987 1987 1987 1987 1987 1.10E+01 1.11E+01 1.52E+01 5.48E+00 4.28E+01 8.83E+00 1.50E+01 9.34E+00 1.35E+01 4.67E+01 H-3'-18'r-51 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 1.66E-06 0.00E+00 7.27E-04 1.96E-03 2.69E-03 5.05E-03 4.46E45 5.07E<5 O.OOE+00 5.15E-03 Mn-54 7.98EZ5 4.84E-05 2.31E-05 1.21E<4 2.72E-04 5.10E-04 O.OOE+00 3.59E<5 1.07E-04 6.53E-04 Fe-59 O.OOE+00 O.OOE+00 O.OOE+00 6.23E-05 6.23E-05 8.25E<6 O.OOE+00 0.00E+00 O.OOE+00 8.25E-06 Co-58 8.45E-06 O.OOE+00 2.54E-06 4.59E-05 5.69E-05 6.03E-05 O.OOE+00 O.OOE+00 1.15E-05 7.18E45 Co%0 6.18E-05 1.85E-05 O.OOE+00 6.23E-05 1.43E-04 1.00E-04 5.70E-06 1.31E-05 5.05E-05 1.69E-04 Zn45 O.OOE+00 O.OOE+00 O.OOE+00 5.53E-05 5.53E-05 8.68E-06 0.00E+00 O.OOE+00 O.OOE+00 8.68E-'0 Sr-89 O.OOE+00 O.OOE+00 2.31E-06 1.28E-06 3.59E-06 2.03E-08 5.16E-07 2.09E-08 1.09E-06 3.66E-06 Sr-90 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Ag-110m O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 I-131 4.30E-05 6.36E-OS O.OOE+00 0.00E+00 1.07E-04 3.26E-06 O.OOE+00 O.OOE+00 O.OOE+00 3.26E-06 I-133 0.00E+00 0.00E+00 1.03E<3 1.10E<4 1.14E-03 1.67E-05 4.82&)5 0.00E+00 0.00E+00 6.49E45 Cs-137 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.16E-05 0.00E+00 O.OOE+00 0.00E+00 2.16E-05 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Kr-85m 2.86Ml1 0.00E+00 O.OOE+00 O.OOE+00 2.86E-01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Kr-87 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Kr-88 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-127 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00

. Xe-133 1.63E+02 2.66E+01 2.77E+01 1.65E+01 2.34E+02 5.18E+01 3.41E+01 1.81E+01 1.94E+01 1.23E402 Xe-133m O.OOE+00 '.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Xe-135 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Xe-138 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00 00

PP8L CALCULATIONSHEET "Iept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 iate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 89 of 121 Table 4-3: Airborne Effluent Data Base from 1982-1994 Inclusive (Ci)(Page 4 of 7)

PERIOD 23 24" 25 26 27 28 29 30 Q1 Q2 Q3 Q4 ALL Q1 Q2 Q3 Q4 ALL Isotope 1988 1988 1988 19SS 1988 1989 1989 1989 1989 1989 H-3 3.64E+00 1.10E+01 4.01E+00 1.85E+00 2.05E+01 1.44E+01 1.75E+01 3.60E+00 2.21E+01 5.76E+01 F-18 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Cr-51 0.00E+00 3.24E-05 7.05E-04 0.00E+00 7.37E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Mn-54 2.28E-04 4.63E-05 O.OOE+00 0.00E+00 2.74E-04 7.38E45 6.54E-05 9.29E-05 1.20E-04 3.52E-04 Fe-59 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 8.57E-07 O.OOE+00 O.OOE+00 0.00E+00 8.57E-07 Co-58 3.95E-05 O.OOE+00 O.OOE+00 0.00E+00 3.95E-05 1.28E-06 1.38E45 9.67E-06 0.00E+00 2.48E-05 Co+0 5.38EAS 1.18E-06 O.OOE+00 0.00E+00 5.50E-05 1.32E%4 3.43E-05 1.99E-05 2.45E-05 2.11E-04 ~

Zn45 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 1.37E-06 1.37E-05 O.OOE+00 0.00E+00 1.51E-05, Sr-89 7.81E-07 O.OOE+00 O.OOE+00 0.00E+00 7.81E-07 0.00E+00 0.00E+00 1.12E-06 6.69E-07 1.79E-06 Sr-90 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00" Ag-110m 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 I-131 6.98E-04 9.46E-06 O.OOE+00 Q+OE+00 7.07E-04 3.55E-04 9.09E-05 3.28E-05 2.18E-05 5.01E-04

!-133 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-137 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ar<1 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Kr-85m 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00-,

Kr-87 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Kr-8S 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Xe-127 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 '.OOE+00 Xe-133 3.67E+01 O.OOE+00 1.66E+01 1.92E+01 7.25E+01 5.35E+01 4.10E+01 1.29E+01 1.19E+01 1.19E+02 Xe-133m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+O~

Xe-135 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Xe-138 O.OOE+00 O.OOE+00 O.OOE+00 0OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00

PP8L CALCULATIONSHEET "Iept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 rate 9/12/96 FUEL CYCLE40GFR190 -

Rev.0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 90 Df 121 Table 4-3: Airborne Effluent Data Base from 1982-1994 Inclusive (Ci)(page 5 of 7)

PERIOD 31 34 35 36 37 38 Q1 Q2 Q3 Q4 ALL Q2 Q3 Q4 ALL Isotope 1990 1990 1990 1990 1990 1991 1991 1991 1991 1991 H-3 1.16E+01 1.24E+Q1 5.72E+01 1.12E+01 9.24E+01 1.36E+01 8.57E+00 6.90E+00 1.71E+01 4.62E+01 F-18 O.OOE+00 O.OOE+00 O.QOE+00 O.OOE+OO O.OOE+OO Q.QQE+00 0.00E+00 O.OOE+00 Q.OQE+00 Q.QOE+00 Cr-51 O.OOE+00 O.OOE+00 Q.QQE+00 Q.QOE+00 O.QQE+00 Q.QQE+00 O.OOE+00 Q.OOE+00 O.OOE+00 O.OOE+00 Mn-54 3.07E~ O.OOE+00 2.14E44 1.11E-04 3.28E-04 5.96E45 6.11E45 1.15E<5 2.81E46 1.35E-04 Fe-59 O.OOE+00 O.OOE+00 5.27E-05 0.00E+00 5.2? E%5 0.00E+00 O.QQE+OO O.OOE+OO Q.QOE+00 0.00E+00 Co-58 O.OOE+00 O.OOE+00 7.42E-05 0.00E+00 7.42E-05 1.45E45 O.QOE+00 Q.QQE+00 Q.QOE+00 1.45EZ5 Co40 O.OOE+00 O.OOE+00 1.37E-04 1.77E45 1.55E-04 4.97E-05 1.77EA5 Q.QQE+00 1.24E-05 7.98E-OS Zn%5 O.OOE+00 O.OOE+00 2.53E-04 Q.QOE+00 2.53E-04 O.OOEtoo O.OOE+00 O,OOE+00 O.OOE+00 O.QQE+OO Sr-89 O.OOE+00 O.OOE+00 Q.QOE+00 6.69E-07 6.69E-07 O.OQE+00 O.OOE+00 O.OOE+00 0.00E+00 Q.QQE+00 Sr-90 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Q.QQE+00 Ag-110m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Q.QOE+00 I-131 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.09E45 0.00E+00 Q.QQE+00 2.87E-06 1.38E-05 I-133 Q.QOE+00 O.QQE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Q.QQE+00 O.OOE+OQ Cs-137 0.00E+00 O.QOE+00 O.OOE+00 O.OOE+00 O.OQE+00 0.00E+00 O.OOE+00 O.OOE+00 0 QQE+00 0 QOE+00 OOE+00 O.OOE+00 O.OOE+00 Q.QOE+00 O.OOE+00 1.49E+01 Q.QOE+00 1.49E+01 Kr-85m 0.00E+00 O.QOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 1.22E+00 Q.QOE+00 1.22E+00 Kr%7 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OQE+00 Q.QOE+00 Kr-88 O.QOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.12E+00 O.OOE+00 1.12E+00 Xe-127 O.QOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.QQE+00 O.QOE+00 Xe-133 3.85E+00 O.OOE+00 7.91E+00 6.03E+01 7.21E+01 1.02E+00 4.24E+00 4.59E+00 3.05E+01 4.04E+01:-

Xe-133m O.QQE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.QOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.QOE+00 Xe-135 O.QQE+00 0.00F+00 O.OOE+00 O.OOE+00 O.OOE+00 O.QOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Xe-138 Q.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.QOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Q.QOE+00

I PPRL CALCULATIONSHEET

')ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 iate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 91 of 121 Table 4-3: Airborne Effluent Data Base from 1982-1994 Inclusive (Ci)(Page 6 of 7)

PERIOD 39 40 41 ,42 43 44 45 46 Q1 Q2 Q3 Q4 ALL Q1 Q2 Q3 Q4 ALL Isotope 1992 1992 1992 1992 1992 1993 1993 1993 1993 1993 H-3 6.46E+00 1.45E+01 .2.25E+01 8.88E+00 5.23E+01 8.05E+00 1.75E+01 7.19E+00 1.09E+01 4.36E+01 F-18 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Cr-51 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 Mn-54 9.05E<4 4.11E-04 6.24E44 6.96E-04 2.64E-03 1.23E<4 1.54E45 2.23EA4 1.42E<4 5.03E44 Fe-59 1.56EZ4 4.85E-06 6.44E-05 1.48E-04 3.73E-04 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Co-58 1.17E-04 0.00E+00 9.27E-05 3.50E-05 2.45E-04 0.00E+00 O.OOE+00 5.82E-05 2.88EZ6 6.11E-05 Co<0 3.32E<4 1.30E-05 1.69E-04 1.50H4 6.64E-04 1.90E-04 2.14EZ5 2.10E44 6.82EA5 4.90E-O Zn45 7.09E<4 0.00E+00 6.35E-05 0.00E+00 7.73E-04 O.OOE+00 O.OOE+00 2.18E<4 1.37E<5 2.32E4 Sr-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Sr-90 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 2.60E<7 O.OOE+00 O.OOE+00 0.00E+00 2.60E47 Ag-110m 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 l-131 0.00E+00 0.00E+00 8.75E-06 8.14E-06 1.69E-05 8.74E-09 O.OOE+00 0.00E+00 0.00E+00 8.74E=09 l-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Cs-137 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Kr<5m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 Xe-127 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E 00 Xe-133 1.01E+01 3.04E+01 1.25E+01 4.22E+00 5.72E+01 7.68E+00 7.21E+00 O.OOE+00 2.04E+00 1.69E+01 Xe-133m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Xe-135 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00 00 Xe-138 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

PP8L CALCULATIONSHEET

')ept. 0 s. Tech. PROJECT SSES ISFSI Calc. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 92 of 121 Table 4-3: Airborne Effluent Data Base from 1982-1994 Inclusive (Ci)(Page 7 of 7)

PERIOD 47 48 49 50 QUARTER YEAR Q1 Q2 Q3 Q4 ALL MAXIMUM MAXIMUM Isotope 1994 1994 1994 1994 1994 (CI) (Ci)

H-3 6.21E+00 1.42E+01 1.33E+01 2.01E+01 5.38E+01 5.72E+01 9.24E+01 F-1 8 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.67E+01 1.67E+01 Cr-51 0.00E+00 0.00E+00 8.90E-05 4.70E-05 1.36E-04 2.38E-02 2.42E-O Mn-54 5.17E-04 5.21E<4 2.16E<4 1.73EZS 1.27E-03 9.05E44 2.64E-03 Fe-59 0.00E+00 5.01E-OS O.OOE+00 0.00E+00 S.01E-OS 1.56E-04 3.73E-O4 Co-58 6.27EAS O.OOE+00 O.OOE+00 O.OOE+00 6.27E-05 3.22E-04 3.22E-04 Co<0 1.99E<4 1.01E-04 2.59E-05 1.19E-OS 3.38E-04 3.32E-04 6.64E-04 Zn-65 4.25E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.25E-05 7.09E-04 7.73E-04 Sr-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.24E-OS 2.24E-OS Sr-90 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.60E<7 2.60E-Ag-110m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.08EZ4 1.43E-04 l-131 1.01E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.01E<5 8.94E<3 1.21E-02 I-1 33 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 7.23E-03 1.03E-02 Cs-1 37 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 2.16E-OS 2.16E-05 Ar<1 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 1.49E+01 1.49E+01 Kr-85m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.61E+01 2.61E+01 Kr-87 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.39E-01 1.39E-01 Kr-88 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.23E+01 1.77E+01 Xe-127 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.29E+00 4.29E+00 Xe-133 8.66EC1 0.00E+00 0.00E+00 1.09E+01 1.18E+01 2.26E+02 3.41E+02 Xe-133m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.86E-01 2.86E-01 Xe-135 0.00E+00 0.00E+00 0.00E+00 6.29MI2 6.29E-02 1.51E+02 1.63E+02 Xe-138 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.12E+01 3.12E+01

PP8 L CALCULATIONSHEET

.")ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC, Checked By Sh. No. 93 of 121 4.7 Airborne ENuent Dose Calculation to Selected Members of the Public 4.7.1 The dose calculation from airborne eNuent is performed for selected Members of the Public at locations described in Section 3.30. The airborne source term developed in Section 4.6 is input to GASPAR (reference 6.45);

the program is run according to reference 6.59 Attachment D. GASPAR input parameters are taken from Section 3.34. GASPAR input and output is shown in Attachment 13 for off site locations 1 through 4. GASPAR tdtal-organ doses, transcribed to Tables 4-4a-d, will be used in the calculation of the total dose from airborne effluent (Section 4. 7.3).

4.7.2 Ag-110m in the source term is grieved (rejected) by the GASPAR program.

The problem with this isotope is documented in CR-095-0743 (reference'.31);

a separate calculation for Ag-110m must be performed for this isotope for all receiver locations in question. The calculations are performed using dose calculation constants for airborne effluent in the SSES ODCM (Section 3.32). The annual dose is determined using Equation 9 and dose rate parameters from reference 6.37:

Eq. 4W" where: = dose rate parameter for A'g-110m. For inhalation, units are in mrem/yr/uCi/m'. For ground shine and vegetation pathways (deposition), units are in mrem-m'/yr/uCi/sec (Section 3.32);

gi = annual average dispersion parameter for estimating dose from airborne effluent to the receiver: X/Q (sec/m') for inhalation pathway; D/Q (m') for deposition pathways (Section 3.13);

g = release rate of radionuoiide (I) from vent (v) in uci/seo. This value is determined by dividing the Ag-110m released (143.0 uCi) in the period (1 yr) by the number of seconds in a year (3,15 e7);,

= annual dose from Ag-110m, in mrem/yr.

D

Rept.

aate 0 s. Tech.

9l12/96 PP8 L CALCULATIONSHEET PROJECT SSES ISFSI FUEL CYCLE 40CFR190

'ale. No. EC-ENVR-.1025 Rev. 0 esigned By. OFFSITE DOSE CALC.

Checked By Sh. No. 94 of 121 Results are shown for applicable pathways in Tables 4-4a< for off site locations 1 through 4. The summation of doses from Ag-110m for the various pathways is shown as Ag-110m SUBTOTAL in each table. F-18 and Xe-127 are also grieved by the GASPAR program. F-18 is not listed in USNRC Reg. Guide 1.109 (reference 6.44) Table E-6 through E-14 (applicable to particulate radionuclides), however, and Xe-127 is not listed in Table B-1 of that reference (applicalbe to noble gas isotopes). Since USNRC Reg. Guide 1.109 is specified in SSES Technical Specifications (ref. 6.26.4) as the "acceptable method for calculating dose contributions from liquid and gaseous effluent", no further attention will be given to F-18 and Xe-127 as reported.

4.7.3 The total dose from airborne effluent is determined by summing the components from the GASPAR run (Section 4.7.1) and Ag-110m (Section 4.7.2), for each off site location, age group, and organ, These total quantities are shown in Tables 44a-d.

PP8L CALCULATIONSHEET

'lept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 95 of 121 Table 44a: Airborne EfflUent Dose (mrem), Location 1 PATHWAY AGE BONE LIVER T.BODY THYROID KIDNEY LUNG G.l. SKIN GROUP A -110m ADULT 4.04E44 4.04E44 4.04E44 4.04E44 4.04E44 4.04E44 4.04E44 4.72E44 GROUND TEEN 4.04E44 4.04E44 4.04E44 4.04E44 4.04E44 4.04E44 4.04E44 4.72E44 CHILD 4.04E44 4.04E44 4.04E44 4.04E44 4.04E44 4.04E44 4.04E44 4.72E44 INFANT 4.04E44 4.04E44 4.04E44 4.04E44 4.04E44 4.04E44 4.04E44 4.72E44 A 110m ADULT 1.57E47 1.45E47 8.63E48 O.OOE+00 2.86E47 6.72E45 4.39E46 O.OOE+00 INHAL TEEN 2.01E47 1.90E47 1.16E47 O.OOE+00 3.63E47 9.80E45 3.96E46 O.OOE+00 CHILD 2.45E47 1.65E47 1.33E47 O.OOE+00 3.08E47 7.95E45 1 46E46 O.OOEi00 INFANT 1.45E47 1.05E47 7.25E48 O.OOE+00 1.59E47 5.32E45 4.80E47 O.OOE+00 A 110m ADULT 4.05E44 4.04E44 4.04E44 4.04E44 4.05E44 4.72E44 4.09E44 4.72E44 SUBTOTAL TEEN 4.05E44 4.05E44 4.04E44 4.04E44 4.05E44 5.02E44 4.08E44 4.72E44 CHILD 4.05E44 4.05E44 4.04E44 4.04E44 4.05E44 4.84E44 4.06E44 4.72E44 INFANT 4.04E44 4.04E44 4.04E44 4.04E44 4.05E44 4.58E44 4.05E44 4.72E44 ASPAR ADULT 9.93E42 1.12E41 1.12E41 1.29E41 1.12E41 1.14E41 1.12E41 2.01E41 UBTOTAL TEEN 9.93E42 1.12E41 1.12E41 1.34E41 1 12E41 1 14E41 1 12E41 20 E CHILD 9.93E42 1.11E41 1.11E41 1.35E41 1.11E41 1.13E41 1.11E41 2.00E41 INFANT 9.93E42 1.06E41 1.06E41 1.28E41 1.06E41 1.08E41 1.06E41 1.95E41 AIRBORNE ADULT 9.97E42 1.12E41 1.12E41 1.29E41 1.12E41 1.14E41 1.12E41 2.01E41 EFFLUENT TEEN 9.97E42 1.1 2E41 1.12E41 1.34E41 1.12E41 1.15E41 1.12E41 2.01E41 TOTAL CHILD 9.97E42 1.11E41 1.11E41 1.35E41 1.11E41 1.13E41 1.11E41 2.00E41 INFANT. 9.97E42 1.06E41 1.06E41 1.28E41 1.06E41 1.08E41 1.06E41 1.95E41

PP8L CALCULATlONSHEET

')ept, 0 s. Tech. PROJECT SSES ISFSI Calc. No. 'C-ENVR-1025 Date 9/12/96 Designed By FUEL CYCLE40CFR190 OFFSITE DOSE CALC.

'ev. 0 Checked By Sh. No. 96 of 121 Table 4-4b: Airborne Effluent Dose (mrem), Location 2 PATHWAY AGE BONE LIVER T.BODY THYROID KIDNEY LUNG G.I. SKIN GROUP A 110m ADULT 1.19E43 1.19E43 1.19E43 1.19E43 1.19E43 1.19E43 1.19E43 1.39E43 GROUND TEEN 1.19E43 1.19E43 1.19E43 1.19E43 1.19E43 1.19E43 1.19E43 1.39E43 CHILD 1.19E43 1.19E43 1.19E43 1.19E43 1.19E43 1.19E43 1.19E43 1.39E43 INFANT 1.19E43 1.19E43 1.19E43 1.19E43 1.19E43 1.19E43 1.1 9E43 1.39E43 A 110m ADULT 2.39E46 2.22E46 1.32E46 O.OOE+00 4.36E46 1.03E43 6.70E45 O.OOE+00 INHAL TEEN 3.07E46 2.91E46 1.77E46 0.00E+00 5.55E46 1.50E43 6.05E45 O.OOE+00 CHILD 3.74E46 2.53E46 2.03E46 0.00E+00 4.71E46 1.21E43 2.22E45 0.00E+00 INFANT 2.21E46 1.60E46, 1.11E46 O.OOE+00 2.42E46 8.13E44 7.32E46 O.OOE+00 A 110m ADULT 1.19E43 1.19E43 1.19E43 1.19E43 1.20E43 2.22E43 1.26E43 1.39E43 SUBTOTAL TEEN 1.1 9E43 1.19E43 1.19E43 1.19E43 1.20E43 2.69E43 1.25E43 1.39E43 CHILD 1.20E43 1.19E43 1.19E43 1.19E43 1.20E43 2.41E43 1.21E43 1.39E43 INFANT 1.19E43 1.19E43 1.19E43 1.19E43 1.19E43 2.00E43 1.20E43 1.39E43 ADULT 1.19E+00 1.39E+00 1.39E+00 1.66E+00 1.39E+00 1.42E+00 1.39E+00 2.62E+00 ASPAR TEEN 1.1 9E+00 1.39E+00 1.39E+00 1.72E+00 1.39E+00 1.43E+00 1.39E+00 2.62E+00 SUBTOTAL CHILD 1.19E+00 1.37E+00 1.37E+00 1.75E+00 1.37E+00 1AOE>00 1.37E+00 2.60E+00 INFANT 1.19E+00 1.29E+00 1.29E+00 1.64E+00 1.29E+00 1.32E+00 1.29E+00 2.52E+00 AIRBORNE ADULT 1.19E+00 1.39E+00 1.39E+00 1.66E+00 1.39E+00 1.42E+00 1.39E+00 2.62E+00 EFFLUENT TEEN 1.19E+00 1.39E+00 1.39E+00 1.72E+00 1.39E+00 1.43E+00 1.39E+00 2 62E+00 TOTAL CHILD 1.1 9E+00 1.37E+00 1.37E+00 1.75E+00 1.37E+00 1.40E+00 1.37E+00 2.60E+00 INFANT 1.19E+00 1.29E+00 1.29E+00 1.64E+00 1.29E+00 1.32E+00 1.29E+00 2.52E+00

")ept. 0 s. Tech.

ate 9/12/96 esigned By Checked By PP8L CALCULATIONSHEET PROJECT SSES ISFSI FUEL CYCLE 40CFR190 OFFSITE DOSE CALC.

'ev.

Gale. No.

Sh. No.

EC-ENVR-1025 97 0

of 1I 2'I Table 4-4c: Airborne Effluent Dose (mrem), Location 3 PATHWAY AGE BONE LIVER T.BODY THYROID KIDNEY LUNG G.l. SKIN GROUP A 110m ADULT 2.05E~ 2.05E~ 2.05E44 2.05E44 2.05E44 2AOE44 GROUND TEEN 2.05'.05'.05'.05E~

2.05'.05E44 2.05'.05E44 2.05E44 2.05E44 2.05M4 2.40E~

CHILD 2.05E~ 2.05E44 2.05E44 2.40E~

2.05'.05E44 2.05'.05'.05'.05E44 INFANT 2.05E44 2.05E44 2.05E44 2.40E44 A 110m ADULT 2.23E47 2.06E47 1.23E47 O.OOE+00 4.06E47 9.55E45 6.24E46 O.OOE+00 INHAL TEEN 2.85E47 2.71E47 1.65E47 O.OOE+00 5.17E47 1.39E44 5.63E46 O.OOE+00 CHILD 3ASE47 2.35E47 1.89E47 O.OOE+00 4.38E47 1.13E44 2.07E46 O.OOE+00 INFANT 2.06E47 1.49E47 1.03E47 O.OOE+00 2.25E47 7.57E45 6.82E47 O.OOE+00 A -110m ADULT 2.06E~ 2.06E~ 2.05E~ 2.05E44 2.06E~ 3.01M'.12E~ 2.40'.40E44 SUBTOTAL TEEN 2.06E44 2.06E44 2.06E44 2.05E~ 2.06E~ 3.45E44 2.11E44 CHILD 2.06E44 2.06E44 2.05E~ 2.06E44 3.18E44 2.07E44 2.40E~

INFANT 2.06E~ 2.05E~ 2.05E~ 2.05E~ 2.06E44 2.81E44 2.06E44 2.40E44 GASPAR ADULT 1.08E41 1.27E41 1.27E41 1.52E41 1.27E41 1.30E41 1.27E41 2.38E41 UBTOTAL TEEN 1.08E41 1.27E41 1.27E41 1.59E41 1.27E41 1.31E41 1.27E41 2.38E41 CHILD 1.08E41 1.25E41 1.25E41 1.61E41 1.25E41 1.28E41 1.25E41 2.36E41 INFANT 1.08E41 1.18E41 1.18E41 1.51E41 1.18E41 1.20E41 1.18E4'I 2.28E41 AIRBORNE ADULT 1.08E41 1.27E41 1.27E41 1.52E41 1.27E41 1.30E41 1.27E41 2.38E41 EFFLUENT TEEN 1.08E41 1.27E41 1.27E41 1.59E41 1.27E41 1.31E41 1.27E41 2.38E41 TOTAL CHILD 1.08E41 1.25E41 1.25E41 1.61E41 1.25E41 1.28E41 1.25E41 2.36E41 INFANT 1.08E41 1.18E41 1.18E41 1.51E41 1.1 8E41 1.20E41 1.18E41 2.28E41

PP8 L CALCULATIONSHEET

")ept. 0 s. Tech. PROJECT SSES ISFSI Calc. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 98 of 121 Table 44d: Airborne Effluent Dose (mrem), Location 4 PATHWAY AGE BONE LIVER T.BODY THYROID KIDNEY LUNG G.I. SKIN GROUP A 110m ADULT 3.20E44 3.20E44 3.20E44 3.20E44 3.20E44 3.20E44 3.73E44 GROUND TEEN 3.20E44 3.20E44 3.20E44 3.20E44 3.20E44 3.20E44 3.20E44 3.73E44 CHILD 3.20E44 3.20E44 3.20E44 3.20E44 3.20E44 3.20E44 3.20E44 3.73E44 INFANT 3.20E44 3.20E44 3.20E44 3.20E44 3.20E44 3.20E44 3.73E~

3.20'.85EZ7 A 110m ADULT 8.18E<7 4.86E47 O.OOE+00 1.61E46 O.OOE+00 O.OOE+00 3.34'.55E44 VEGTBLE TEEN 1.34E~ 1.26E46 7.69E<7 O.OOE+00 2.41 E46 O.OOE+00 O.OOE+00 CHILD 2.88E46 1.94E46 1.55E46 O.OOE+00 3.62E~ O.OOE+00 2.31E~ O.OOE+00 INFANT O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 A -110m ADULT 6.17E47 5.71E47 3.40EC7 O.OOE+00 1.1 2E46 2.65E44 1.73E45 O.OOE+00 INHAL. TEEN 7.91EC7 7.50EZ7 4.57M)7 O.OOE+00 1 3.86E44 O.OOE+00 1.56'.73E46 CHILD 9.64E<7 6.51E47 5.22E47 1.21E-06 43'.OOE+00 3.13E44 O.OOE+00 INFANT 5.70EZ7 4.13E47 2.86EC7 O.OOE+00 6.24EZ7 2.10E44 1.89E46 O.OOE+00 A -110m ADULT 3.21E44 3.21E414 3.21E44 3.20E44 3.23E44 5.85E44 6.71E44 3.73E44 UBTOTAL TEEN 3.22E44 3.22E44 3.21E44 3.20'.24E44 7.06M4 6.91E44 3.73E44 CHILD 3.24E44 3.23EZ4 3.20E~ 3.25M4 6.33E44 5.57E44 3.73E44 INFANT 3.20E44 3.22'.21'.20E44 3.20'.21 E44 5.30E44 3.22E44 3.73E~

GASPAR ADULT 2.72E<1 4.06E<1 4.05E<1 5.29MH 4.06E41 4.12E411 4.08E<1 6.97E<I SUBTOTAL TEEN 2.72&M 4.23E<1 4.21 E41 5.56EZ1 4.22E41 4.30M) I 4.24E41 7.12E41 CHILD 2.73EA1 4.72M)1 4.70E41 6.43E<1 4.70EZ1 4.76EW1 4.70M)1 7.60E41 INFANT 2.71 E%1 2.99E<1 2.99E41 3.91E41 2.99E41 3.05E%1 2.99E<1 5.91E41 AIRBORNE ADULT 2.72E%1 4:06E41 4.05E41 5.29E41 4.06E41 4.13EC1 4.09E41 6.97E41 EFFLUENT TEEN 2.72E41 4.23EZI 4.21E41 5.56E41 4.22ECI 4.31EZ1 4.25E41 7.12E41 TOTAL CHILD 2.73E<1 4.72EC1 4.70E41 6.43E41 4.70E<1 4.77E<1 4.71EZ1 7.60E41 INFANT 2.71M)1 2.99E<1 2.99E41 3.91EZI 2.99E41 3.06M)1 2.99E<1 5.91E41

')ept.

Date 0 s. Tech.

9/12/96 PROJECT SSES ISFSI FUEL CYCLE 40CFR190

'ale.

PP8 L CALCULATIONSHEET No. EC-ENVR-1025 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 99 of 121 4.8 Liquid Effluent Data Base Creation 4.8.1 SSES Semiannual and Annual Effluent and Waste Disposal Reports (refs.

6.34.25, tables as applicable) provide historical liquid effluent information from which to create a data base. The maximum effluent value for each isotope is identified for quarterly and annual data. Although the maximum effluent for all isotopes was not actually released in any particular quarter or year, the use of this approach, provides a bounding, conservative source term for use in the dose calculations.

4.8.2 A data base is created in EXCEL 5.0 (reference 6.43) which contains quarterly liquid effluent quantities reported for SSES between September, 1982, (SSES Unit 1 Initial Startup) and December 1994. For each year.

isotope activities (Ci) reported for each quarter of that year are entered (only two quarters reported in 1982). One exception is P-32, for which only-annual quantities are reported in reference 6.25. For this case, P-32 is -.

entered for the first quarter of each of the two years it is reported >LLD (1990 and 1992): the maximum quarter and year are the same for this isotope. Entrained noble gases are not entered because they have no liquid effluent dose factors associated with them in Reference 6.44. Naturallly-occurring elements, such as Radon daughters (Bi-214 and Pb-214) are also not included in this data base. Annual activity totals are determined by summing activities from the constituent quarters. This process is repeated for every year through 1994 inclusive. Tritium is the predominant nuclide1n all quarters except the third quarter in 1982, where it is not reported.

4.8.3 Effluent data for previous periods not available at the time the SAE8WD or AE&WD Reports were issued are entered from the appropriate tables to the data base as necessary, per Section 3.12. The'data base is listed in Table 4-5.

4.8.4 The maximum activity for each isotope is selected from the data base. The selection considers all quarters and years. The results of this sort are shown in Table 4-5 (Page 7 of 7). These values are to be used as the source terms in Section 4.9 for liquid effluent dose calculations to Members of the Public at selected locations.

PPSL CALCULATIONSHEET

'3ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1 025 .

ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 100 of 121 Table 4-5: Li uid Effluent Data Base from 1982-1994 Inclusive Ci Pa e'1 of7)

PERIOD 1 2 3 4 5 6 Q3 Q4 ALL Q1 Q2 Q3 Q4 ALL Isoto e 1982 1982 1982 1983 1983 1983 1983 1983 H-3 O.OOE+00 7.32E-01 7.32E-01 2.66E+00 1.52E+00 2.35E+00 2.45E+00 8.98E+00 F-18 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.74E-05 6.74E-05 Na-24 4.95E-04 7.80E-03 8.30E-03 1.73E-01 1.70E-01 2.68E-02 0.00E+00 3.70E-01 P-32 O.OOE+00 O.OOE+00 O.OOE+00 . O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 So<6 O.OOE+00 O.OOE+00 0.00E+00 1.90E-04 0.00E+00 O.OOE+00 O.OOE+00 1.90E<4 Cr-51 O.OOE+00 7.64E-02 7.64E-02 6.64E-01 3.87E-01 3.06E-01 9.23E-03 1.37E+00 Mn-54 O.OOE+00 3.68E-03 3.68E-03 1.20E-01 '.62E<2 8.02E-03 1.99E-03 2.06E-01 Mn-56 3.11E-04 4.43E<4 7.54E-04 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Fe-55 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Fe-59 O.OOE+00 3.13E-03 3.13E-03 1.68E-01 5.67E<3 2.35E-05 3.91E-04 1.74E-01 Co-56 O.OOE+00 O.OOE+00 O.OOE+00 4.05E-04 0.00E+00 O.OOE+00 O.OOE+00 4.05E<4 Co-58 O.OOE+00 2.39E-02 2.39E-02 3.33E-01 1.54E-01 1.27E-02 1.72E-03 5.01E-01 Co%0 O.OOE+00 1. 1E-03 1.21E-03 2.42E-02 2.81E-02 1.51E-03 5.73E-04 5.44E-02 Zn45 O.OOE+00 O.OOE+00 0.00E+00 2.49E-03 2.69E-04 O.OOE+00 O.OOE+00 2.76E-03 As-76 O.OOE+00 6.30E-03 6.30E-03 1.44E-02 1.26E-02 9.11E-03 0.00E+00 3.61E-02 Br-82 O.OOE+00 2.17E-03 2.17E-03 6.12E<5 8.77E-02 5.22E-04 O.OOE+00 8.83E-02 Sr-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.63E-05 0.00E+00 5.63E-05 Sr-89 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 1.12E-03 O.OOE+00 O.OOE+00 1.12E-03 Sr-90 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Sr-92 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Y-91m O.OOE+00 4.49E-03 4.49E-03 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 Zr-95 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Nb-95 O.OOE+00 O.OOE+00 O.OOE+00 4.16E-04 4.73E-05 O.OOE+00 0.00E+00 4.63E-04 Zr-97 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Nb-97'o-99 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 6.95E-05 9.35E-05 4.23E-04 5.86E<4 O.OOE+00 4.91E-03 4.91E-03 0.00E+00 0.00E+00 6.95E-03 O.OOE+00 6.95E-03 Tc-99m 3.96E-05 2.16E-02 2.16EZ2 3.27E-03 8.39E43 8.47E-03 O.OOE+00 2.01E-02 A -110m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.77E-04 4.69EZ4 1.15E-03 A -110 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sb-122 O.OOE+00 3.49E-04 3.49E-04 9.80E-03 5.34E-03 1.01E-03 O.OOE+00 1.62E-02 Sb-124 O.OOE+00 1.38E-05 1.38E-05 4.64E-03 4.69E-04 6.22E44 O.OOE+00 5.73E<3 Te-131 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-132 O.OOE+00 3.17E-04 3.17E-04 9.29E-05 0.00E+00 O.OOE+00 O.OOE+00 9.29E-05 l-131 O.OOE+00 6.66EZ4 6.66E-04 5.81E-05 2.65E<5 2.42E-04 O.OOE+00 3.27E-04 1-133 O.OOE+00 4.82E-04 4.82E-04 2.55E-04 2.99E-04 5.78E-05 O.OOE+00 6.12E<4 l-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOEt00 O.OOE+00 Cs-134 O.OOE+00 5.68E<3 5.68E<3 O.OOE+00 3.12E-05 0.00E+00 O.OOE+00 3.12EZ5 Cs-136 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00

'Cs-137 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 3.78E-05 7.38E-07 O.OOE+00 3.85E-05 La-140 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Ce-141 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.38E-05 O.OOE+00 O.OOE+00 3.38E-05 Ce-144 .OOE+00 3.62E<3 3.62E-03 O.OOE+00 7.95E-04 9.74EZ4 O.OOE+00 1.77EZ3 Nd-147 O.OOE+00 3.88E-04 3.88E<4 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 Sm-153 O.OOE+00 O.OOE+00 O.OOE+00 1.82E-04 0.00E+00 O.OOE+00 0.00E+00 1.82E<4 W-187 0.00E+00 1.09E-03 1.09E<3 0.00E+00 1.63E-03 1.07E-03 O.OOE+00 2.70E<3 N -239 O.OOE+00 2.85E-03 2.85E<3 1.44M)3 O.OOE+00 O.OOE+00 O.OOE+00 1.44E-03

PP8 L'ALCULATIONSHEET Dept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 date 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 101 of 121 Table 4-5: Li uid Effluent Data Base from 1982-1994 Inclusive Pa e 2 of 7 PERIOD 7 8 9 10 11 12 13 14 Q1 Q2 Q3 Q4 ALL Q1 Q2 Q3 Q4 ALL Isoto e 1984 1984 1984 1984 1984 1985 1985 1985 '985 1985 H-3 2.95E+00 2.98E+00 3.91E+00 1.33E+00 1.12E+01 1.01E+00 3.04E+00 1.05E+00 4.04E+00 9.14E+00 F-18 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Na-24 5.53E-03 0.00E+00 6.08E-02 1.25E-03 6.76E-02 2.93E-03 0.00E+00 7.82E-04 O.OOE+00 3.71E-03 P-32 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Sc-46 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Cr-51 1.57E-03 0.00E+00 9.21E-03 1.09E-02 2.17E-02 4.88E<1 3.15E%2 5.10E-03 1.31E<3 5.26E-01 Mn-54 3.87E-03 2.44E-03 1.57E-03 1.49E-03 9.37E-03 4.55E-03 '.08E<2 1.39E-03 1.17E-04 3.69E-02 Mn-56 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 1.35E-06 0.00E+00 O.OOE+00 0.00E+00 1.35E-08 Fe-55 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 1.66E-04 1.69E-04 0.00E+00 5.80E-04 9.15E-04 1.83E-04 7.49E-03 O.OOE+00 0.00E+00 7.67E-03 Co-56 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0 Co-S8 1.49E-03 1.37E-03 1.42E-03 1.53E-03 5.81E-03 6.63E-03 6.67E-03 6.62E-04 1.58E-05 1.40E-02 Co%0 3.17E-02 1.59E-03 1.88E-04 1.17E-03 3.46E-02 2.66E-03 2.50E-02 5.90E-04 6.55E-05 2.83E-02 Zn45 7.76E-OS 1.16E-05 0.00E+00 O.OOE+00 8.92E-OS 2.31E-03 1.58E-03 2.13E-04 0.00E+00 4.10E-03 As-76 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.11E-03 0.00E+00 0.00E+00 0.00E+00 2.11E-03 Br-82 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Sr-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Sr-89 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 7.12E-OS 0.00E+00 0.00E+00 O.OOE+00 7.12E-05 Sr-90 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-92 O.OOE+00 O.OOE+00 0.00E+00 1.28E-04 1.28E-04 0.00E+00 1.28EZ4 O.OOE+00 0.00E+00 ~ 1.28E-04 Y-91m 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zr-95 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Nb-95 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Zr-97 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 Nb-97 0.00E+00 0.00E+00 5.69E<5 0.00E+00 5.69E-05 1.13E-04 .0.00E+00 0.00E+00 0.00E+00 1.13E-04 Mo-99 2.06E-06 O.OOE+00 0.00E+00 0.00E+00 2.06E-06 8.31E-03 0.00E+00 O.OOE+00 0.00E+00 8.31E-63 Tc-99m 6.66E-05 O.OOE+00 0.00E+00 0.00E+00 6.66E-05 3.32E-03 0.00E+00 O.OOE+00 O.OOE+00 3.32E 3 A -110m 4.67E-04 0.00E+00 8.61E-05 3.37E-04 8.90E-04 2.20E-04 5.08E-04 2.36E45 0.00E+00 7.52E- 4 A -1 10 7.53E-05 0.00E+00 6.32E-OS O.OOE+00 1.39E-04 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E 0 Sb-122 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sb-124 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 1.18E-04 O.OOE+00 0.00E+00 1.18E-04 Te-131 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 Te-132 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 I-131 0.00E+00 0.00E+00 3.16E-06 1.45E-05 1.77E-05 2.39E-04 1.45E-05 O.OOE+00 O.OOE+00 2.54E-04 1-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 I-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 Cs-1 34 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Cs-136 O.OOE+00 O.OOE+00 0.00E+00 3.31E-05 3.31E-05 0.00E+00 3.31E45 O.OOE+00 0.00E+00 3.31E-05 Cs-137 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 La-140 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Ce-141 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00Et00 0.00E+00 Ce-144 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Nd-147 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Sm-153 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 W-187 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.12E<4 0.00E+00 O.OOE+00 O.OOE+00 4.12E<4 N 239 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00

PP8 L CALCULATIONSHEET

'lept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1 025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 102 of 121 Table 4-5: Li uid Effluent Data Base from 1982-1994 Inclusive Pa e 3 of 7 PERIOD 15 16 17 18 19 20 21 22 Q1 Q2 Q3 Q4 ALL Q1 Q2 Q3 Q4 ALL Isoto e 1986 1986 1986 1986 1986 1987 1987 1987 1987 1987 H-3 6.61E+00 4.56E+00 1.33E+00 2.89E+00 1.54E+01 4.42E+00 6.17E+00 4.58E+00 3.56Ei00 1.87E+01 F 18 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Na-24 0.00E+00 6.48E-06 0.00E+00 0.00E+00 6.48E-06 6.46E-06 0.00E+00 0.00E+00 O.OOE+00 6.46E-06 P-32 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sc46 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cr-51 4.45E-02 1.57E-01 2.92E-01 9.66E-02 5.90E-01 3.74E-02 1.71E-01 2.13E-02 1.55E-02 2.45E-01 Mn-54 3.88E-03 2.51E-02 5.72E-03 3.13E-02 6.60E-02 3.78E-03 6.91E-03 2.57E<3 7.24E-03 2.05E-02 Mn-56 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Fe-55 O.OOE+00 O.OOE+00 9.82E-03 1.96E-02 2.94E-02 O.OOE+00 1.13E-02 0.00E+00 0.00E+00 1.13E-O Fe-59 2.19E-04 4.35E-03 1.61E-03 1.18E-03 7.36E-03 4.06E-OS 3.40E-03 3.55E-05 4.16E-04 3.89E-03 Co-56 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 1.98E-03 6.84E-03 2.49E-03 6.96E-03 1.83E-02 3.50E-04 1.96E-03 6.42E-04 8.48E-04 3.80E-03 Co40 2.90E-03 1.43E-02 4.28E-03 1.51E-02 3.66E-02 2.99E-03 4.33EZ3 2.43E-03 5.05E-03 1.48E-02 Zn45 1.27E-03 1.08E-02 2.68E-03 1.40E-02 2.88E-02 1.48E-04 3.65E-03 7.47E-04 3.15E-03 7.?OE-03 As-76 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 4.71E-04 1.42E-04 2.47E-04 0.00E+00 8.60E-04 Br-82 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-85 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-89 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 Sr-90 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-92 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00Et00 Y-91m O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zr-95 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+ 0 Nb-95 0.00E+00 8.05E-06 0.00E+00 0.00E+00 8.05E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zr-97 0.00E+00 0.00E+00 7.02E-05 0.00E+00 7.02E-05 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Nb-97 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+ 0 Tc-99m 0.00E+00 2.48E-06 4.03E-06 8.25E-06 1.48E45 0.00E+00 4.25E-06 O.OOE+00 0.00E+00 4.25E-06 A -110m 5.00E-04 4.79E43 8.06E-03 2.11E-03 1.55E42 6.82E-04 2.12E-03 2.79E-05 6.04E-04 3.43E- 3 A -110 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sb-122 . 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 Sb-124 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Te-131 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Te-132 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 I-1 31 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 1-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 I-134 0.00E+00 0.00E+00 6.70E-09 0.00E+00 6.70E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Cs-136 0.00E+00 6.54E-05 2.24E44 0.00E+00 2.89E-04 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00.

La-140 0.00E+00 O.OOE+00 1.57E-04 0.00E+00 1.57E-04 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Ce-141 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Ce-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Nd-147 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Sm-153 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 W-187 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N 239 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

PPSL CALCULATIONSHEET

')ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1 025 Jate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 103 of 121 Table 4-5: Li uid Effluent Data Base from 1982-1 994 inclusive Pa e 4 of 7 PERIOD 23 24 25 26 27 28 29 30 Q1 Q2 Q3 Q4 ALL Q1 Q2 Q3 Q4 ALL Isoto e 1988 1988 1988 1988 1988 1989 1989 1989 1989 1989 H-3 3.01E+00 3.57E+00 3.93E+00 4.00E+00 1.45E+01 5.91E+00 6.92E+00 3.55E+00 1.10E+01 2.74E+01 F-1 8 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Na-24 0.00E+00 0.00E+00 5.02E-03 0.00E+00 5.02E-03 1.42E-03 0.00E+00 O.OOE+00 0.00E+00 1.42E-03 P-32 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sc46 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Cf-51 2.08E-02 4.81E-04 1.25E-02 1.06E-02 4.44E-02 2.91E<2 2.1 3EC3 9.45E-05 2.31E%3 3.36E-02 Mn-54 6.99E-04 1.12E-02 4.92E-03 2.50E-03 1.93E-02 5.74E<3 2.53E<3 2.67E-04 6.41E<3 1.49E-02 Mn-56 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+

Fe-55 0.00E+00 8.18E-03 O.OOE+00 5.50E-03 1.37E-02 0.00E+00 8.70E-03 1.42E-02 1.69E<2 3.98E-02 Fe-59 0.00E+00 9.65EZ5 1.48E<4 1.25E-04 3.70E-04 1.47E-04 6.45E-06 O.OOE+00 1.12E-03 1.27E-03 Co-56 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Co-58 2.5'IE-05 1.14E-04 1.25E-05 2.13E-05 1.73E-04 6.77E-04 1.25E-04 0.00E+00 5.08E-04 1.31E-Co%0 6.13E-04 4.76E-03 2.91E-03 9.59E-04 9.24E-03 3.54E-03 1.27E-03 1.23E-04 2.85E-03 7.78E-03 Zn45 4.63E-04 1.31E-04 9.60E-05 0.00E+00 6.90E-04 1.12E-03 O.OOE+00 O.OOE+00 0.00E+00 1.12E-03 As-76 O.OOE+00 O.OOE+00 O.OOE+00 1.85E-05 1.85E-05 0.00E+00 4.08E-05 0.00E+00 0.00E+00 4.08E-05 Br-82 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Sr-85 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Sr-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-90 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.15EZ5 O.OOE+00 O.OOE+00 0.00E+00 4.15E 05 Sr-92 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91m 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+QO Zr-95 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Nb-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zr-97. O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+ 0

, Nb-97 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE4 Mo-99 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00' Tc-99m 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 7.09E-05 1.37E<5 0.00E+00 O.OOE+00 8.46E-'05 A -110m 1.29E-04 3.83E44 5.48E<4 2.81E-05 1.09E-03 5.57E-05 O.OOE+00 O.OOE+00 0.00E+00 5.57E-05 A -110 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 'O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+00 Sb-122 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sb-124 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-131 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Te-132 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 l-131 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 l-133 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 I-134 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 O.OOE+00 2.61E-05 3.92E-04 0.00E+00 4.18E-04 2.31E44 0.00E+00 O.OOE+00 0.00E+00 2.31E-04 Cs-136 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Cs-137 0. OE+00 O.OOE+00 4.01E-04 0.00E+00 4.01E-04 1.70E-04 0.00E+00 O.OOE+00 O.OOE+00 1.70E-04 La-140 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Ce-141 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 '.OOE+00 O.OOE+00 O.OOE+00 Ce-144 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nd-147 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Sm-153 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 W-187 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N 239 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

PPRL CALCULATIONSHEET

')ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1 025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 104 of 121 Table4-5: Li uid ENuent Data Base from1982-1994 Inclusive Pa e 5 of 7 PERIOD 31 32 33 34 35 36 37 38 Q1 Q2 Q3 Q4 ALL Q1 Q2 Q3 Q4 ALL lsoto e 1990 1990 1990 1990 1990 1991 1991 1991 1991 1991 HQ 6.53E+00 2.58E+01 1.67E+01 9.00E+00 5.80E+01 7.16E+00 1.32E+01 1.34E+01 1.18E+01 4.56E+01 F-18 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Na-24 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 P-32 1.14E-02 0.00E+00 0.00E+00 O.OOE+00 1.14E-02 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Sc46 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 6.77E-05 O.OOE+00 2.96E-03 2.50E-04 3.28E-03 0.00E+00 4.47E-05 0.00E+00 2.97E-OS 7.44E-05 Mn-54 1.49E-04 2.66E-04 1.72E-02 4.34E<3 2.20E-02 4.20E-04 1.75E-03 1.04E-04 1.97E-04 2.47E-03 Mn-56 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Fe-55 1.58E-02 O.OOE+00 6.56E-02 1.06E<2 9.20E-02 4.85E<3 4.98E-02 0.00E+00 3.13E<3 5.78E-02 Fe-59 O.OOE+00 O.OOE+00 8.00E-04 1.20E-03 2.00E-03 1.36E-05 1.1 5E-04 O.OOE+00 O.OOE+00 1.29E-04 Co-56 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0 Co-58 O.OOE+00 O.OOE+00 1.08E-03 1.13E-04 1.19E-03 0.00E+00 4.01E-05 O.OOE+00 O.OOE+00 4.01E-Co<0 7.97E-05 4.12E-05 1.12E-02 1.85E-03 1.32E-02 2.31E-04 1.03E-03 8.76E-05 2.17E-04 1.57'.79E-05 Zn<5 O.OOE+00 O.OOE+00 6.71E-04 2.91E-05 7.00E-04 1.68E-05 1.81E-05 0.00E+00 2.99E-06 As-76 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 Br-82 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOEtoo O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Sr-89 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Sr-90 O.OOE400 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E>00 Sr-92 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91m O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zr-95 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Nb-95 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Zr-97 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Nb-97 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 Mo-99 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO Tc-99m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 A -110m O.OOE+00 O.OOE+00 1.03E-04 O.OOE+00 1.03E-04 0.00E+00 0.00E+00 0.00E+00 2.45E-06 2.45E-D6 A -110 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sb-122 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Sb-124 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Te-131 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-132 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 I-131 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 I-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 I-134 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 2.84E-06 2.84E-06 Cs-136 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Cs-137 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.56EC7 3.66EZ6 4.12E-06 La-140 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-141 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-144 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Nd-147 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sm-153 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 W-187 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 N 239 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00

PP8 L CALCULATIONSHEET

")ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1 025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 105 of 121 Table 4-5: Li uid Effluent Data Base from 1982-1 994 Inclusive Pa e 6 of 7 PERIOD 39 40 41 42 43 44 45 46 Q1 Q2 Q3 Q4 ALL Q1 Q2 Q3 Q4 ALL Isoto e 1992 1992 1992 1992 1992 1993 1993 1993 1993 1993 H-3 1.99E+01 2.32E+01 2.28E+01 1.11E+01 7.70E+01 8.64E+00 9.42E+00 2.95E+01 2.03E+01 6.79E+01 F-18 0.00E+00 O.OOE+00 9.33E-08 0.00E+00 9.33E-08 0.00E+00 1.22E-07 1.01E-07 3.42E-07 5.65E-07 Na-24 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 7.44E-07 0.00E+00 0.00E+00 7.44E-07 P-32 3.13E-03 0.00E+00 0.00E+00 0.00E+00 3.13E-03 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sc46 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Cr-51 0.00E+00 1.63E-04 1.08E-02 4.85E-05 1.10E-02 1.33E-04 1.07E-03 1.22E43 2.76E44 2.70E-03 Mn-54 4.42E-04 2.68E-03 5.86E-03 9.10E-04 9.89E-03 3.73E-03 3.56E<3 3.26E-03 1.81E<3 1.24E42 Mn-56 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Fe-55 4.99E-03 6.77E-03 O.OOE+00 5.70E-03 1.75E-02 9.87E-04 1.28E-02 O.OOE+00 O.OOE+00 1.38E-O Fe-59 1.42E<5 4.78E-04 1.22E-03 8.11E-05 1.79E-03 4.12E-04 4.52E-04 3.48E<4 5.79E<5 1.27E-03 Co-56 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+0 Co-58 3.28E-06 5.95E-05 2.17E-04 2.05E-05 3.00E-04 4.07E-05 3.95E-05 3.23E-04 6.69E-04 1.07E-03 Co%0 5.60E-04 2.14E-03 3.19E-03 8.94E-04 6.78E-03 1.61E-03 1.52E-03 2.50E-03 1.06E-02 1.62E-02 Zn45 2.50E-05 2.10E-04 5.41E-04 9.23E-05 8.68E-04 2.27E-05 1.90E-06 9.21E-04 4.81E<4 1.43E-03 As-76 O.OOE+00 O.OOE+00 1.28E-04 0.00E+00 1.28E-04 O.OOE+00 1.14E-05 2.14E-05 0.00E+00 3.28E-O Br-82 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-85 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-89 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 8.82E-06 O.OOE+00 O.OOE+00 0.00E+00 8.82E-08 Sr-90 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOEi00 Sr-92 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 7.11E-07 3.42E<7 1.05E-06 Y-91m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zr-95 0.00E+00 1.76E-06 O.OOE+00 O.OOE+00 1.76E-06 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Nb-95 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 Zr-97 0.00E+00 5.03E-07 O.OOE+00 0.00E+00 5.03E-07 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Nb-97 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Mo-99 0.00E+00 O.OOE+00 6.66E-05 0.00E+00 6.66E-05 0.00E+00 1.30E<5 0.00E+00 0.00E+00 1.30E45 Tc-99m 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.30E-06 0.00E+00 O.OOE+00 4.30E-06 A -110m 2.39E-07 O.OOE+00 1.28E-05 O.OOE+00 1.30E-05 0.00E+00 2.10E-06 3.15E44 1.25E-05 3.30E- 4 A -110 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 .O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Sb-122 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0:OOE+00 O.OOE+00 O.OOE+00 Sb-124 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Te-131 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 4.01E-12 O.OOE+00 4.01E-12 Te-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 l-131 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.08E-07 O.OOE+00 O.OOE+00 5.08E-07 I-133 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 I-134 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 7.87E<7 0.00E+00 O.OOE+00 O.OOE+00 7.87E-07 0.00E+00 0.00E+00 O.OOE+00 6.86E<7 6.86E-07 Cs-136 O.OOE+00 O.GOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-137 1.29E-05 7.80E-07 1.39E<6 2.23E-06 1.73E-05 8.42E-07 3.44E-07 1.48E<6 2.64E45 2.91E.05 La-140 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-141 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 5.58E<7 0.00E+00 5.58E 07 Ce-144 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OG Nd-147 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 1.07E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.07E.G6 Sm-153 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+GO W-187 O.OOE+00 O.OOE+00 1.60E<5 O.OOE+00 1.60E-05 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+GC N 239 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOEiGC

PP8L CALCULATlONSHEET

")ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1 025 fate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 106 of '21 Table 4-5: Li uid Effluent Data Base from 1982-1994 Inclusive (Ci)(Page 7 of 7)

PERIOD 47 48 49 50 Q1 Q2 Q3 Q4 ALL YEAR Isoto e 1994 1994 1994 1994 1994 MAXIMUM H-3 4.31E+01 3.74E+01 1.07E+01 1.04E+01 1.02E+02 1.02E+02 F-18 1.28E-07 0.00E+00 O.OOE+00 6.67E-07 7.95E<7 6.74E-05 Na-24 1.43E-06 0.00E+00 0.00E+00 0.00E+00 1.43E-06 3.70E-01 P-32 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 1.14E-02 Sc46 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 1.90E-04 Cr-51 2.84E-04 6.63E-06 6.13E-04 1.40E-02 1.49E-02 1.37Et00 Mn-54 4.22E-03 3.09E-03 4.66E-03 3.28E-03 1.53E-02 2.06E-01 Mn-56 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 7.54E-04 Fe-55 0.00E+00 5.34E-03 3.48E-02 3.48E-02 7.49E-02 9.20E-02 Fe-59 2.49M)4 1.55E-04 1.26E-04 1.24E<3 1.77E-03 1.74E-01 Co-56 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 4.05E-04 Co-58 4.74E-05 4.52E-05 3.05E-05 1.58E-04 2.81E-04 5.01E-01 Co40 1.84E-03 1.93E-03 5.41E-03 1.24E-03 1.04E-02 5.44E<2 Zn45 2.96E-04 1.98E-04 3.40E-04 8.37E-05 9.18E-04 2.88E-02 As-76 5.84E-06 0.00E+00 O.OOE+00 7.96E-05 8.54E-05 3.61E-02 Br-82 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 8.83E-02 Sr-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 5.63E-05 Sr%9 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.12E-03 Sr-90 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 4.15E-05 Sr-92 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 1.28E-04 Y-91m O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 4.49E-03 Zr-95 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 1.76E-06 Nb-95 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 4.63E<4 Zr-97 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 7.02E-05 Nb-97 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 5.86E-04 Mo-99 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 8.31E<3 Tc-99m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.16E-02 A -110m 8.71E-05 1.97E-06 O.OOE+00 5.27E-05 1.42E-04 1.55E-02 A -110 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 1.39E-04 Sb-122 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 1.62E-02 Sb-124 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 5.73E-03 Te-131 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00'0 4.01E-12 Te-132 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 3.17E-04 l-131 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 6.66E-04 I-133 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 6.12E-04 I-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.TOE<9 Cs-134 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 5.68E-03 Cs-136 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 2.89E-04 Cs-137 7.61E-07 4.80E-07 O.OOE+00 2.62E-05 2.74E45 4.01E-04 La-140 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 1.57E<4 Ce-141 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 3.38E-05 Ce-144 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.62E-03 Nd-147 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 3.88E-04 Sm-153 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 1.82E-04 W-187 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 2;70E-03 N 239 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.85E<3

PP8 L CALCULATIONSHEET

'3ept. 0 s. Tech PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No 107 of 121 4.9 Liquid Effluent Dose Calculation to Selected Members of the Public 4.9.1. The dose calculation from waterborne effluent is performed for Members of the Public at the outfall and at the Danville drinking water intake (Section 3.22). Input parameters for LADTAP II are also taken from Section 3.22.

The liquid effluent source term (maximum year) developed in Section 4.8 is input to LADTAP II (reference 6.46); the program is run according to reference 6.59 Attachment F. Doses are calculated by LADTAP II for a maximum exposed member of the public at the edge of the initial mixingy zone (flish ingestion and shore exposure pathways), and for water ingeqtjon from the nearest downstream supply (Danville). These pathways are tI16'ame as those calculated in reference 6.40.2. LADTAP II input and output is shown in Attachment 14. Co-56, As-76, Sr-85, Ag-110, and Sb-1 22 are grieved (rejected) by LADTAP II. None of these isotopes have dose calculation parameters listed in Reg. Guide 1.109 (ref. 6.44) Tables E-7--

through E-14, thus, there is no requirement with regard to SSES Technical Specifications (ref. 6.26.4) for doses to be calculated for these nuclides.'

4.9.2 Files DATAFILE.WK1 and 1109AD.WK1 are opened (reference 6.47).

IVIACROs in these files produce printed output with the maximum total body and organ doses to the off site receiver shown (Attachment 15).

PP&L CALCULATIONSHEET

)ept. 0 s. Tech. PROJECT SSES ISFSI Calc. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By . OFFSITE DOSE CALC.

Checked By Sh. No. 108 of 121 4.10 Shine from Low Level Radwaste Handing Facility (LLRWHF) 4.10.1 In reference 6.1, a method is presented which permits estimation of the total shine from the LLRWHF, based on the outer row of CD LSMs in the facility.

It is stated in this reference that the total exposure rate contributed from the outer CD LSM row diminishes with distance; the proportion of skyshine to direct shine increases with distance. The prediction equation for the fraction of CD LSIVls/ total exposure rate is defined:

exp [0.30 - (0.15 ln x)] Eq. 4-7 where fraction CD LSM summed outer row: total exposure rate; "

distance from source~receiver (meters)..

The limiting distance used in developing this equation is for the Southeast.

Site Boundary: 621 meters. This distance is less than that for the LLRWHFmSector 7 residence (1000.6 m), Sector 16 residence (915.9 m) and Sector 12 residence (1256.4 m). The equation, however, encompasses the Towers Club distance (424.8 m). While it is recognized that using ...

equation 4W to predict the outer row: total exposure rate is extrapolation'for the three distances beyond 621 meters, it is also important to avoid underestimating the skyshine contribution at the greater distances. The.,

maximum distance of 1256.4 meters exceeds the limiting distance of 621 meters by only a factor of two. Furthermore, it can be seen in Reference.1 Figure 10, which sh'ows the log regression curve for this equation, that thy slope diminishes greatly as the limiting distance is approached; this characteristic reduces the probability that the prediction equation will seriously fail in estimating the outer row/ total exposure rate fractions for the distances, considered here. Thus, Equation 4-7 will be applied once the direct shine contribution of CD LSMs is evaluated.

4.10.2 In reference 6.1, the exposure rate at various distances from the outer row of CD LSMs in the LLRWHF is determined using MICROSHIELD. The exposure rate from the CD LSM array in the LLRWHF can be determined for the four off site dose locations using the MICROSHIELD base parameters (Section 3.29), adjusting as necessary for distance or additional shielding.

In the case of location 1 (Sector 7 residence), the direct shine path from the LLRWHF is impeded by the Unit 2 cooling tower; the effect of this additional concrete shielding will be significant and will be evaluated (Section 3.27). Off

PP8 L CALCULATIONSHEET

')ept. O s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 esigned By: OFFSITE DOSE CALC.

Checked By Sh. No. 109 of 121 (4.10.2) site location 3 (Sector 16 residence) is situated onto the north-northwest of the LLRWHF (in line with the LLRWHF north wall). Reference 6.54 (Section 4.2.8), which evaluates the exposure rates to walls for the fully-loaded LLRWHF, disregards the exposure rate to the north wall because it is bounded by the south wall, which is nearer, and direct radiation through the wall is further limited by a concrete shield wall 18" thick. This shield is 'orth expected to have a significant effect on direct radiation to Location 3; The need to evaluate the direct shine from the LLRWHF sources to Location 3 (Sector 16 residence) will be determined once the shielding effect of the Unit 2 cooling tower on the direct shine from the LLRWHFm Location 1 is kahn.

The concrete shield at the north wall of the LLRWHF is equivalent to the-Unit 2 cooling tower (2" thicker).

The MICROSHIELD calculations for direct shine from the LLRWHF are-prepared by establishing the increments to the base parameters for the CD LSM (Section 3.29), specifically T4 (concrete) for locations 1 and 3.

MICROSHIELD parameters are determined for each location as follows:".

Base parameter (5.57 cm air. Section 3.29)

T4 Base parameter (43.18 cm: Section 3.29) + Increment (for U2 C.T.: Sector 7 res.; North Wall: Sector 16 res.), location 1 (40.6 cm: Section 3.27) 83.78 cm concrete (Sector 7 res. only: Loc. 1) 45.72 cm concrete (Sector 16 res. only: Loc. 3) 43.18 cm concrete (Towers Club and Sector 12 res: Loc. 2 and 4)

X Base parameter (Sum of shields w/o additional distance [142.2 cm]: Section 3.29) + Distance LSM~LLRWHFwall (Section 3.29) + Distance from LLRWHF wallmdose receiver point (Table 3-5 value

• 30.48 cm/ft) +

. MICROSHIELD required air gap [0.5 cm]

142.5 cm+ (50 ft *30.48 cm/ft: East wall) + 100038 cm+ 0.5 cm = 101705.0 cm(Sector7 Res: Loc. 1) 142.5 cm + (35 ft 30.48 cm/ft: South wall) + 42465 cm+ 0.5 cm = 43674.8 cm (Towers Club; Loc. 2) 142.5 cm+ (35 ft *30.48 cm/ft: South wall) + 91582 cm+ 0.5 cm = 92791.8 cm (Sector 16 Res: Loc. 3) 142.5 cm+ (35 ft 30.48 cm/ft: North wall) + 125611 cm+ 0.5 cm 126820.8 cm (Sector 12 Res: Loc. 4)

PP8L CALCULATIONSHEET

')ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 Jate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No, 110 of 121 MICROSHIELD is run for each location, including the cases with and without the U2 cooling tower effect for the residence in Sector 7 (Location 1), and the cases with and without the north wall shield for Sector 16 (Location 3).

The MICROSHIELD results include a listing of the parameter inputs. The results of the MICROSHIELD runs are shown in Attachment 16. The effect of the Unit 2 cooling tower shielding on reducing the direct exposure rate to the Sector 7 residence (Location 1) is substantial, as expected: 6.10 e-11 mR/hr (with coooling tower) vs. 9.08 e-09 mR/hr (without cooling tower).

This reduction is a factor of approximately 150. The shielding effect ofhce north wall on the exposure rate to the Sector 16 residence (Location 3) is also substantial: 1.69e-08 mR/hr (without shield) vs. 6.10e-11 mR/hr (with shield). This reduction is a factor of approximately 275.

4.10,3 The total annual dose from LLRWHF shine is calculated for each off site location considering the total number of CD LSM containers in the front row, the effect of distance from the facility on the fraction of the front CD LSM-.

exposure rate: total exposure rate, and the influence, if any, of additional .

shielding. Total exposure rate (DTQT mR/hr) is determined as follows for each location:

DTOT (DcoLsM NcDLsM )/FGDTDT Eq. 4-8: Towers Club (Loc. 2), Sector 12 res. (Loc. 4)

DTOT (DGDLsM NcoLsM )/FcoTDT (DGDLsM NGDLsM) + (DsHD NcoLsM) Eq. 4-9 Sector 7 res.

(Loc.1), Sector 16 res. (Loc. 3) where DDDLsM = Exposure rate from CD LSM without additional shielding (Section 4.10.2);

NCOLSM = Number of CD LSMs in front row (Section 3:28);

FCOTOT = Fraction of the front CD LSM exposure rate: total exposure rate (Section 4.10.1);

DSHO = Exposure rate from CD LSM with additional concrete shielding from Unit2 cooling tower(Loc. 1) orfrom North Wall (Loc. 3),

Section 4.10.2 In Eq. 4-9, it is necessary to subtract the unshielded component, represented by the-(DcoLsM *NcDLsM) term, since this term is not actually

, contributing to the total dose from the LLRWHF. The shielded component.

represented by (DsHD

• NcoLsM), is added in its place.

PP8 L CALCULATIONSHEET

)ept. 0 . Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/96 FUEL CYCLE 40CPR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 111 of 121 The total exposure rates for each location are then multiplied by 8760 hrs/yr (Section 3.21) to determine the total annual dose from LLRWHF sources to each location (Occupancy factors will be applied in Section 4.13). The results of these calculations are shown in Table 4.

4.11 Skyshine from Temporary Laundry Facility (TLF) 4.11.1 In reference 6.41, the fully-loaded TLF is demonstrated to provide a small but determinate component of skyshine radiation to off site locations. This component should be accounted for in calcul'ations of the total fuel cycle impact of SSES and associated structures. Skyshine exposure rates ance <

annual integrated dose (Section 3.23) to four off site locations are 3-8. shown'able 4.12 Shine from ISFSI Storage and Transport 4.12.1 Neutron and gamma dose rates, and annual integrated dose from ISFSI storage are based on reference 6.42, and are shown in Table 3. Neutron a'nd gamma dose rates from transport are shown in Table 3-7, for distances of 300-5500 meters. By examining the data in Table 3-7, it is apparent that the dose rate from the casks effectively become so minor as to be insignificant beyond the distance of 1500 ft (457.3 m).

The annual integrated doses are determined based on a loading rate oNive (5) casks per year, (for facility occupancy nearing completion in year @10:

Section 3.19) with the assumption of thirty (30) minutes transit time from SSES Radwaste Bldg. to the ISFSI (Section 3.20). The dose rate (n+ y) at the minimum distance listed in Table 3-7 (3.60 e-03 mrem/hr) will be used to estimate the annual integrated dose from cask transit to the ISFSI. This dose (D>~) will be applied for all locations.

D>~ =. 3.60 e-03 mrem/hr

• 5 transits/yr *0.5 hr/transit D$ ~' 9.00 e-3 mrem/yr 4.13 Sum of SSES Fuel Cycle Dose Contributions at Off Site Locations 1

4.13.1 Annual integrated doses obtained for fuel cycle dose components in Sections 4.3P.12 are summed for each of the four off site locations. Table 4-7 shows all components summed for total body and organ doses. The total body dose is determined from the components as follows:

PP8 L CALCULATIONSHEET

')ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025

. Jate 9/12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By . OFFSITE DOSE CALC.

Checked By Sh. No. 112 of 121 Q, =g [(Q+Q )~Occ F.acror]+Qr +Q, Eq.4-10 where: D Total body integrated dose from all pathways; Der + Domcr Sum of doses from U1 and U2 Tb skyshine, U1 Tb direct shine, U2 Tb direct shine, U2 CST skyshine, Temporary Laundry Facility, LLRWHF, and ISFGI storage; Occ. Factor Occupancy factor, DTB:EEL Sum of total body doses from airborne and liquid--

eNuent pathways; Dam near Dose from transport to the ISFSI.

Total body doses from effluent ( D ) are summed for airborne and liquid pathways without regard for age group specificity, which is the conservative approach. The occupancy factor is applied only to the direct and skyshine dose components, not to the dose from liquid or airborne pathways, nor to the dose from transport to the ISFSI. While thea 'Nuent occupancy factor could be argued to apply for the conditions of ground wahine from eNuent (airborne deposition) and immersion, the approach used he'rein is conservatively consistent. The organ dose is determined from the components as follows:

[(Q +Q ) "Occ Factor.]+@ +I), Eq. 4-11 where: Doaa Total organ integrated dose from all pathways; DOao:SFFL Sum of maximum organ doses from airborne and liquid eNuent pathways; other terms as defined for Eq. 4-10. Maximum organ doses (D,,. ) from airborne and liquid eNuent pathways are added without regard for organ or age group specificity (similar to total body doses), which is the conservative approach.

PP8 L CALCULATIONSHEET

'lept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9I12/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By . OFFSITE DOSE CALC.

j* Checked By Sh. No. 113 of 121 Table 4W: Shine to Off Site Locations from LLRWHF Sources Exp. Rate from Exp. Rate from Total Total Distance from Single Source; Single Source Number of Fraction CO front Exposure Rate Annual Dose Locathn LLRWHF (matars) Unshielded (mR/hr) Shielded (mR/hr) Containers Total Exp. Rate (mR/hr) (mrem)

Sector 7 residence 1000.64 8.13e-09 5.46e-11 46 4.79e-01 4.09e-07 3.61 e43 Towers Club 424.75 1.56e-06 14 5.45e41 4.01e45 3.51 e-01 Sector 16 residence 915.85 1.69e-08 6.10e-11 14 4.85e-01 2.52e47 2.21e-03 Sector 12 residence 1256.4 1.10e-09 N/A 14 4.63e41 3.33e-08 2.91e-04 Table 4-7: Sum of SSES Fuel Cycle Dose Contributors at Off Site Locations Annual TID Annual TID Annual TIO Annual TID Dose Contributor Location 1 Location 2 Location 3 Location 4 Oescri tion Reference Section mrem mrem mrem mrem Total Bod Dose Calculations U1 &U2Tb: sk shine 4.3.3 4.14e+00 1.96e+00 1.13e+00 2.89e43 U1 Tb: direct 4.5.5 3.00e-03 U2Tb: direct 4.5.5 7.03e-01 U2 CSTsk shine 4.4.4 3.08e-03 Tem ora Laund Facili 4.11.1 2.05e-04 6.19e-01 4.80e43 5.38e45 LLRWHF 4.10.3 3.61~3 3.51+41 2.21e-03 2.91e-04 ISFSI Store e 4.12.1 2.74e-02 6.27e+00 1.46e-01 3.07e-03 Sk shine/Direct Shine Sub Total 4.88e+00 9.20e+00 1.29e+00 6.16e43 Occu anc Factor 3.21 1.00 0.24 1.00 1.00 Sk shine/Direct Shine w/Occ. Factor A lied 4.88e+00 2.21et00 1.29 a+00 6.30e-03 ISFSI Trans ort 4.12.1 9.00e-03 9.00e-03 9.00M3 9.00e43 SSES Airborne EN.: T.B. 4.7,3 1.12e-01 1.39e+00 1.27641 4.70e41 SSES LI uid Effl.: T.B. 4.9.2 2.90e-01 2.90M1 2.90e41 2.90~1 Effluent and ISFSI Trans ort Sub Total 4.11+41 1.69e+00 4.26e-01 7.69e41 Summed Dose: Total Bod mrem 5.29e+00 3.90e+00 1.71e+00 7.75e41 Organ Dose Calculations SSES Airborne EN.: Or an 4.7.3 '.35e-01 1.75e+00 1.61+41 6.43e41 SSES0 uidEN.:Or an 4.9.2 1.24e+00 1.24e+00 1.24e+00 1.24e+00 Summed Dose: Or an mrem 6.26e+00 5.21e+00 2.70e+00 1.90e+00

PP&L CALCULATIONSHEET Dept. 0 s. Tech. PROJECT SSES ISFSI Calc. No. EC-ENVR-1025 Date 9/12l96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 114 of 121 Figure 4-1: Scale Model of U2 CST~Sector 7 Residence (Location 1) Dose Point Showing Line of Sight Convergence at Grade 488.7fUk KOAO DOS(

SKCTOK dONT T

\

lOCATI~

SKSIOKNCK lO CONVKKOKHCK AT 0 1549 ft.

PP8 L CALCULATIONSHEET

')ept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 ate 9/12/9& FUEL CYCLE 40CFR190 Rev. 0 esigned By OFFSITE DOSE CALC.

Checked By Sh. No. 115 of 121 5.0 RESULTS 5.1 From Table 4-7, the highest dose calculated for total fuel cycle components occurs at Location 1 (5.29 mrem T.B., 6.26 mrem organ) ~, This location is in the SE sector, 0.34 miles from the plant. The majority of the total body dose calculated for this location (4.14+ 0.70) mrem/5.29 mrem, or -90%) is attributed to turbine building direct and skyshine radiation. This quantity is the highest component calculated for any of the four locations. In Section 3.1, it is stated that Hydrogen Water Chemistry accounts for a factor of five (5) increase in N-16 levels compared to NWC conditiqys, in other words, 80% of the main steam source term is due to HWC. Off site dose results shown in Table 4-7 are generally consistent with the predominant N-16 contribution from HWC to the turbine building shine source term.

5.2 From Table 4-7, the maximum annual total body dose from transport of ISFSI cask's is 9.00 e-03 mrem (applied to all locations). The maximum annual total body dose from ISFSI cask storage is 6.27 " 0.24 = 1.50 mrem, which occurs at the Towers. Club (Location 2). The ISFSI transport and storage components of the total body summed together (1.50+ 9.00e-03 = 1.51 mrem) are -40% of the total dose dose,'hen from all sources'(3.90 mrem) at the Towers Club. For the same location, the ISFSI components are -30% of the summed organ dose (5.21 mrem).

5.3 In Section 3.24, it is stated that the shine source term for the Temporary Laund~

Facility is approximately fifty times higher than for the DAW Reduction Facility. ft is assumed in that section that the DAW Reduction Facility does not contribute a ~

significant total body dose to a member of the public compared to other fuel cycle components. This assumption is fully justified by comparison to results determined for the Temporary Laundry Facility, which themselves are shown to be minor compared to other sources, such as shine from the turbine buildings, in Table 4-7.

PP8L CALCULATIONSHEET

')ept. 0 s. Tech.. PROJECT SSES ISFSI Calc. No. EC-ENVR-1025 Date 9/12/96 FUEL CYCLE 40CFR1 90 . Rev.,0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 116 of 121

6.0 REFERENCES

6.1 PP8L Calculation EC-HPHY-0518, "Dose Rates to Various Locations within the SSES Controlled Area: Fixed Plant Sources", Rev. 0, Issued 9/29/93.

6.2 PP8L Calculation EC-HPHY-0520, "Committed Effective Dose Equivalent (CEDE),

Ground Shine and Immersion Dose Equivalent Rates from Radioactive Airborne ENuent to Selected Locations within SSES Controlled Area", Rev. 0, Issued 9/3/93.

6.2a PP8 L Calculation EC-HPHY-0519, "Total Effective Dose Equivalent (TEDE) and Deep Dose Equivalent (DDE) to Individuals in SSES Controlled Area from Fixed ~

Plant Sources and Radioactive ENuent", Rev. 0, issued 10/28/93. "'3 6,3 SSES Semiannual Effluent and Waste Disposal Report from September (initial--

criticality)- December 1982, Tables 2, 3, and 5, 2/83.

6.4 SSES Semiannual ENuent and Waste Disposal Report for Report Period 1/1---

6/30/83, Tables 2, 3, and 5, 8/83.

6.5 SSES Semiannual Effluent and Waste Disposal Report for Report Period 7/1- '."

12/31/83, Tables 2, 3, and 5, 2/84.

6.6 SSES Semiannual ENuent and Waste Disposal Report for Report Period 1/1-'-

6/30/84, Tables 2, 3, 5, and 11,'8/84.

6.7 SSES Semiannual Effluent and Waste Disposal Report for Report Period 7/1'~

12/31/84, Tables 2, 3, 5,and 11, 2/85.

6.8 SSES Semiannual Effluent and Waste Disposal Report for Report Period 1/1-6/30/85, Tables 2, 3, and 5, 8/85.

6.9 SSES Semiannual ENuent and Waste Disposal Report for Report Period 7/1-12/31/85, Tables 2, 3, and 5, 2/86.

6.10 SSES Semiannual Effluent and Waste Disposal Report for Report Period 1/1-6/30/86, Tables 2, 3, 5, and 11, 8/86.

6.11 SSES Semiannual ENuent and Waste Disposal Report for Report Period 7/1-12/31/86, Tables 2, 3, and 5,'2/87.

PP&L CALCULATIONSHEET ept. a T ch;. -=

PROJECT SSES ISFSI Gale, No. EC-ENVR-1025 ate 9/12/96 '

FUEL CYCLE 40CPR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 117 of 121 6.12 SSES Semiannual'Effiuent and Waste Disposal Report for Report Period 1/1-6/30/87, Tables 2, 3, and 5, 8/87.

6,13 SSES Semiannual Effluent and Waste Disposal Report for Report Period 7/1-12/31/87, Tables 2, 3, and 5, 2/88.

6.14 SSES Semiannual Effluent and Waste Disposal Report for Report Period 1/1-6/30/88, Tables 2, 3, 5, and 11, 8/88.

6.15 SSES Semiannual Effluent and Waste Disposal Report for Report Period 7/1-12/31/88, Tables 2, 3, and 5, 2/89.

6.16 SSES Semiannual Effluent and Waste Disposal Report for Report Period 1/1-6/30/89, Tables 2, 3, and 5, 8/89.

6.17 SSES Semiannual Effluent and Waste Disposal Report for Report Period 7/1-12/31/89, Tables 2, 3, and 5, 2/90.

6.18 SSES Semiannual Effluent and Waste Disposal Report for Report Period 1/1-6/30/90, Tables 2, 3, 5, and 16, 8/90.

6.19 SSES Semiannual Effluent and Waste Disposal Report for Report Period 7/1-12/31/90, Tables 2, 3, and 5, 2/91. ~ .'3 6.20 SSES Semiannual Effluent and Waste Disposal Report for Report Period 1/1---

6/30/91, Tables 2, 3, 5,and 17, 8/91.

6.21 . SSES'emiannual Effluent and Waste Disposal Report for Report Period 7/1-12/31/91, Tables 2, 3, and 5, 2/92.

6.22 SSES Semiannual Effluent and Waste Disposal Report for Report Peiiod 1/1-6/30/92, Tables 2, 3, and 5, 8/92.

.6.23 SSES Semiannual Effluent and Waste Disposal Report for Report Period 7/1-12/31/92, Tables 2, 3, 5, and 15, 2/93.

6.24 SSES Annual Effluent and Waste Disposal Report for Report Period 1/1-12/31/93,

. Tables 2, 3, 5, and 15, 3/94.

PP&L CALCULATIONSHEET

'Dept: 0 s Tech'. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 Bate 9/12/96 FUEL'YCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 118 of ~12 6.25 SSES Annual ENuent and Waste Disposal Report for Report Period 1/1-12/31/94, Tables 2, 3, and 5,,3/95.

6.26 SSES Technical Specifications

1. 3/4.11.4 Total Dose

2. Table 4.11.2.1.2-1 a

3. 1.33 Rated Thermal Power'.

6.9.1.8 6.27 Letter from R.K. Barclay, PP&L, to Timothy J. Schott, Halliburton NUS, "Request for

.Atmospheric Dispersion Estimates in Support of ISFSI Calculation", PLI-81248, (included as Attachment 1) 12/8/95.

6.28 Letter from Timothy J. Schott, Halliburton NUS, to R.K. Barclay, PP&L, (response request in reference 6.27: included as Attachment 2) transmitting atmospheric dispersion calculations, 12/11/95.

6.29 PP&L Calculation EC-ENVR-1024, "Susquehanna NUHOMS Site Dose Calculation, Rev. 0, Accepted 11/1/95, 6.30 Letter from J.L. Simpson, GE Nuclear Energy, to J:C. Pacer, PP&L, "Review of the Susquehanna Steam Electric Station Assessment of Impact of Hydrogen.WateP Chemistry on Radiation Field Buildup'included as Attachment 3); 11/7/95.

6.31 Condition Report 95-0?43, "PP&L Mainframe Program 'GASPAR', Used t'o Perform Airborne Dose Calcs, Will Not Calculate for Ag-110m', submitted 12/14/95.

6.32 PP&L and Vendor Drawings:

E-105398, Sh. 7, Rev. 7, "Turbine Building Unit 1'perating Floor Plan El.

729'0" (C463).

. 2. E-162739, Rev. 5, "Shielding and Radiation Zoning Drawing Turbine Building El. 729'O'rea 7" (A-517).

3. E-105101, Sh. 1, Rev. 16, "Site and Yard Development-Plant Location Site Plan" (C-1)

4. E-105789, Rev. 8, "Site and Yard Development-Refueling and Unit 1 Condensate Tanks - Plan C-1008

PP&L CALCULATIONSHEET

")ept. 0 s, Tech:. 'ROJECT SSES ISFSI Gale. No. EC-ENVR-1025, ate 9/12/96" FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 119 of 121

5. E-105791, Rev. 6, "Site and Yard Development- Unit 2 Condensate Tanks-Foundation and Details'C-1 010)

6. E-105313, Sh. 12, Rev. 12, "Reactor Building Unit 1, Exterior Wall Areas 27 &

29 EI. 749'-1" - 818'1" " (C-147)

7. E-105809, Sh. 1, Rev. 11, "Site and Yard Development - Finish Grades and Area Paving - Construction Area" (C-1028)

8. E-105943, Sh. 7, Rev. 10, "Site and Yard Development - Finish Grades a~

Area Paving - South Plant Area" (C-1 407)

9. E-105943-8, Rev. 2, "Site and Yard Development - Finish Grades and Area-Paving - Southeast Plant Area" (C-1408)

10. E-105004, Sh, 4, Rev. 22, "General Floor Plans: EI. 719'-1" & El. 729'-0"-"

(A-14)

11. E-1 06152, Sh. 4, Rev. 6, "Plant Design Drawing - Turbine Building Unit 1 Area 2 Plan of Elev. 729'" " (M-2Q)

12. E-1 06152, Sh, 9, Rev. 2, "Plant Design Drawing - Turbine Building Unit 1 Area A-A Above 729' "

2 Sect. Elev. (M-2-9)

13. E-106153, Sh. 4, Rev. 0, "Plant Design Drawing - Turbine Building Unit 1 ArW 3 Plan of Elev. 729'" (M-3P)

14. E-10615?, Sh. 4, Rev. 5; "Plant Design Drawing - Turbine Building Unit 1 Area 7 Plan of Elev. 729'" (M-7-4)

15. E-105398, Sh. 7, Rev. 7, "Turbine Building Unit 1 -.

Operating Floor Plan-Elevation 729'" - Area 7" (CA63) 6.33 PP&L User's Manual Documentation UM-CDA-004 for MICROSKYSHINE Version 1.16, Approved 9/30/91.

6.34 PP&L PCC-CDA-004 Production Computer Code for MICROSKYSHINE Version

~

1.16, Authorized 9/30/91.

6.35 PP&L User's Manual Documentation UM-CDA-002 for MICROSHIELD Version 3.12, A roved 8/30/90.

PP&L CALCULATIONSHEET

')ept. 0 s"Teda- PROJECT SSES ISFSI Gale. No; EC-ENVR-1025 ate: 9/12/96. ":" FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 120 of 121 6.36 PP&L PCC-CDA-002 Production Computer Code for MICROSHIELD Version 3.12, Authorized 8/30/90.

6.37 SSES Offsite Dose Calculation Manual, Rev. 6 6.38 Procedure OP-069450, "Release of Liquid Radwaste, Rev. 18.

6.39 SSES Design Description Manual, chapter 40b, "Design Description for Condensate and Refueling Water Storage System".

6 40 SSES FSAR:

Table 12.2-29, "Condensate Storage Tank Source Terms"

\

2. Section 11.2.4, "Estimated Doses" 6.41 PP&L Calculation EC-RADN-1022, "Laundry Facility C.R. 964156 Dose Calculations", Rev. 0, Approved 4/3/96.

6.42 Letter from Norman Eng, VECTRA Technologies, to Kevin Kelenski, PP&L, "Total Dose Rate Contributed by NUHOMS Transfer Cask During Transfer to the Susquehanna ISFSI Site": VECTRA Letter No. 16-77-96-052, 5/21/96 (includWs Attachment 4).

6.43 EXCEL 5.0 User's Guide, MICROSOFT. Corp., 1993.

6.44 U.S.N.R.C. Reg'ulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR 50, Appendix I", Rev. 1, 10/77.

6.45 U.S.N.R.C. NUREG/CR-0597, "User's Guide to GASPAR Code", 1/80.

6 46 U.S.N.R.C. NUREG/CR-1276,"User's Manual for LADTAP II - A Computer Programfor Calculating the Radiation Exposure to Man from Routine Release of Nuclear Reactor Effluents", 3/80.

6.47 Procedure NEPM-QA-1012, "Offsite Liquid Dose Calculation: LADTAP II Output into LOTUS 1-2-3 Files DATAFILE.WK1and 1109AD.WK1, Rev. 1.

'3ept.

Date 0 s. Tech.

9/1 2/96 PROJECT SSES ISFSI FUEL CYCLE 40CFR190

'alc.

PP8 L CALCULATIONSHEET Na. EC-ENVR-1025 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By Sh. No. 121 of ~12 6.48 PP8L Safety Evaluation NL-89<02, "Dry Active Waste Volume Reduction SystemSafety Analysis', Prepared by R.A. Stigers, PORC Approved 2/17/89 Meeting 89-027.

6.49 Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel, Section 6, VECTRA Technologies, San Jose, CA, 6/2/95.

6.50 PPRL Calculation EC-RADN-0524, "LLRWHF Calculation of Direct and Skyshine Dose Rates", Rev. 0, Issued 7/21/92.

6.51 SSES FSAR Figure 11.6-1, "LLRW Holding Facility General Arrangement Interirh Storage - Plan" (From PP8L Drawing e-190378, Sh. 1).

6.52 PP8 L Calculation EC-012-3150, "Exposure Rate Profiles for LLRWHF Sources in Liner Storage Modules", Rev. 0, Issued 5/4/92.

6.53 Reference deleted.

~ '

~>>

6.54 PP8L Calculation EC-RADNZ523; "Annual dose and Exposure Rates to Walls for Operations at LLRWHF", Rev. 0, Issued 9/1/92.

6.55 Reference deleted.

6.56 Shultis, J.K., and Faw, R.E, "Improved Response Functions for the MICROSKYSHINE Method", Kansas State University Report 189, 5/89; 6.57 Shultis, J.K., et. al., "The Integral Line-Beam Method for Gamma Skyshine Analysis", Nuclear Science and Engineering, 107, 228-245, 3/91.

6.58 Letter from R.K Barclay to KJ. Kelenski, "Assumptions Regarding Movement of Spent Fuel to ISFSI', PLI-82098, 6/11/96 (Included as Attachment 17).

6.59 Procedure NEPM-QA-1011,"Radiological ENuent Dose Calculation and Reporting",

Rev. 3.

6,60 SSES Licensing Topical Report for Power Uprate with increased Core Flow, NE492-001a, Rev. 0, 6/92.

Im NOT WRITE ANYTHINGABOVE THIS LINE CALCULATIONSEPARATOR DOCuMENT WO. EC- uu'8 - /Oar (20charactera)

SECTION (10 characters)

~,

n

+

~

~

,'/// "n .

DO NOT DUPLICAm'EE NUCLEAR RECORDS FORADDITIONALFORMS~

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4+

PP&L CALCULATIONSHEET

-'lept. 0 s. Tech. PROJECT SSES ISFSI Gale. No. EC-ENVR-1025 iate 7/5/96 FUEL CYCLE 40CFR190 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By ATlACHIVIENT1 Sh. No. of ATlACHMENT,1 Letter from R.K Barclay, PP8L, to Timothy J. Schott, Halliburton NUS, "Request for Atmospheric Dispersion Estimates in Support of ISFSI Calculation", PLI-81248, 12/8/95. (3 pp.)(Ref. 6.27)

P8flll+Vanja Pa~el 8, gght Ca~

Vwo Nath Nh& Street~Ale~, PA ANN.tAQ~ONIVT44NN 4

'ecember 8, 1995 Mr. Timothy SctlcN Haltiburton NUS Corporation .

910 Clopper Road Gaithersburg, MG 20878-1389 SUSQUEHANNA STEAM ELECTRC STATION REQUEST FOR ATMOSPHERIC DISPERSION ESTIMATES lN SUPPORT OF ISFSI CALCUL'ATION CCM 402513 FILE R~

~PI- 81248

Dear Tlm:

This letter requests atmospheric dispersion estimates (X/Q, X/Q decayed, X/Q decayecf+depletsd, and D/Q) for the four locations shown ss nunSered black circles on the attached site map. These estimates should be annual average values based on Ns most recent five year meteorological history. We will be using these parameters in eNuent dose calculations to support licensing effete for the Independent Spent Fuel Storage Installation (ISFSI).

Please contact me at',610) 7744721 If you have any questions; Thank you for your attention here.

Yours truly, Robert K. Barclay Health Physicist Attachment

\

cc; B. H. Carson cALL Nor Kc-KNvR- log NR File A6-2 RS N. C)

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SUSOUEHANNA STEAM ELECTRlC STATlON 8 v SITE BOUNDARY DISTANCES

~

(QISTANCES IN FEHl wear ~ Of~ml ONE fayeeg %%Sod PENNSYLVANIA POWER 5 UGHT HALLIBURTON NUS

'hlcnnmber 02, 1883

DO NOT WRITE ANYTHINGABOVE THIS UNE CALCULATIONSEPARATOR DOCuMENTNO; Fd- ~~~< l~>S'K charadera)

SFC new (10 charactere)

~ Y DO NOT DUPLICATE SEE NUCLEAR RECORDS FOR ADDMOHAKFORMS..-'

PP8L CALCULATIONSHEET

• I pt.

Date

~TH 7/6/96

. PROJECT SSES ISFSI FUEL CYCLE 40CFR190 Gale. No. EC-ENVR-1025 Rev. 0 Designed By OFFSITE DOSE CALC.

Checked By ATTACHMENT2 Sh. No 2-1 of -

3 ATTACHMENT2 Letter from Timothy J. Schott, Halliburton NUS, to R.K. Barclay, PP8L, transmitting atmospheric dispersion calculations, 12/11/95 (3 pp.)(Ref. 6.28)

CORPORAYJON-NUS GNWknea~m 9toaopper ~

001) 2556000 kRP-95-182 December 11, 199S:

Mr. Rabat K. Satelay Pennsylvania Power 8r, Light eoaqaay Two North Ninth Street Allentown, Ph 18101-1179

Dear Mr. Barclay:

httached you will find the results of the attaospberic disyersha calculatioas perforined for the four site iocatioas which you xequested ia your Decetnber $ facsimile tnasmittaL Vfe used the I Ih 5 y I~Kll901994~d T

.Conection Factors dIted 1973-1976.

1f we can be of fuitther assisWxe ia your 1SHB investigations, please call me at 301-2584732.--

Sincerely, Timothy J. Schott Metanologist Environmental Pzogruns Center cc: . Bruce Carson h9-3" File 5N35 Z <0. Eq.E,NVR- t0 Re. No' +0~

pygmy, NQ.t 2 8

A Hallihuton Caepany

ISFSI hTMOSPHERIC DISPERSION ESTIMhTES MR 4 SELEClRD LOChTIONS'OChTIQN DHUXTION MILKS ME['EII8 x/Q x/Q DEC x/Q MC + DEP SEPOSmON I . SB 0.34 551 3A33846 3.430M6 3.201&06 ~

2 621MS 2 WSVf OA1 659 5.294IH5 $ .28IM5 4.888$ Q5 7.722$ 08 0.67 1,082 $ .080846 S.ONE 4.549846 1.331848 WSN 1.04 1,681 1.447845 1.437845 1.260M$ 2.074 SOS x/Rt Relative Concentation (sec/m ); no Clay, undepleted x/Q DEC! Decayed (sec/m~); half-life 2.26 days, 'undepleted x/q DEC+ DEI". Decayed and Depleted (sec/msj; half-Hfe 8 days DEPOSIT1ON! Relative Deposition Rate (I/aP)

DO NOT WRITE ANYTHINGABOVE THIS LINE

'CALCULATIONSEPARATOR DOCUMENT NO. E~ - EMPT /O>5 SECTlON (1 0 characters)

DO NOT DUPLICATE. SEE NUCLEAR-RECORDS FORADDITIONAXFORMS

pt.

ate Jla .

7/5/96 Designed By T d.

FUEL PP&L CALCULATIONSHEET PROJECT SSES ISFSI CYCLE 40CFR190 OFFSITE DOSE CALC.

'ev.

Gale. No. EC-ENVR-1025 0

Checked By ATTACHMENT3 Sh. No. 3-1 of 5 ATTACHMENT3 Letter from J.L. Simpson, GE Nuclear Energy, to J.C. Pacer, PPLL, "Review of the Susquehanna Steam Electric Station Assessment of Impact of Hydrogen Water Chemistry on Radiation Field Buildup",11/7/95 (5 pp.)(Ref. 6.30)

Gcnear hxae Qmaenr

7scunnetAwa>>. sen~c4ssQs Mr: John C. Pacer Novanber 7, 1995 Pemsyivama Power and Light Co.

2N 9th Street A2-3 Allentown PA 18101

SUBJECT:

Review of the Susquehama Steam Electric Station Assessment ofImpact ofHydrogen Water Chanistry on Radiation Field Buildup Dear Mr. Pacer.

BillMarble and I both reviewed the two docuinents suppHedby the Pennsylvania Power and Light Co.. These documents were 1, SUSQUE%hhNNh STEAM ELECHQC ASSESSh92G'F IMPACT OF HYDROGKNWATERCHEMISTRY 'TATION, HELD BUILDUP, JOHN C. PACER, OPERATION TKC294OLOGY; ON'ADIATION JUNE 1995 and 2, HWC Evaluation Sr SSES, Radiation ES'ects, D.J. Morgan, 9/22/95.

I called in early October, I beHeve October 13th, and had the opporttmity to discuss with you our review. This letter report details our review of the re6mmtced documents.

GE Nuclear Energy reconunends to the BWR Qeet the implementation ofHydrogen Water Chemistry piWC) at the moderate injection rate.'he moderate injection rate is defined as that amount of hydrogen to acheve a fina feedwater concentration between 1.0 and 1.6 ppm. At this hydrogen concentration, in-plant tests have shown that the Electrochemical Corrosion Potential (ECP) is reduced to < 023 V (SHE) in the bottom plenum, core plate and below. In high power density phmts the recircuhtion piping system environment will also achieve this chemistry condition. An ECP of <023 V (SHE) is recognized as a, chemistry conditio that vali nmmnm metal components &cnn Stress Corrosion Cracking (IGSCC) initiation and ifcracks are present the crack growth rate will be reduced to approxhnately 5 mil/yr.

Two subsequent side effects of implementation of moderate HWC are 1, increased Main Steam Line Radiation (MSLR) levels to appromnately 5 times nortnal and 2, increase in shutdown dose rates in the dry well. The increase in MSLR levels may impact on environmental dose rates although this is vety plant specific. This'was aldress in your gP,LQ, NOA 8Ã>~+ /+~

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p f~a change in vest chemistry UM~ ~W~

evaluation and considered rnanageaMe. The dry well dose rates to a mere reducing condition.

ae e8ectedby the Ibea Ih A review of the GE Chemistry Data Base shows the following for thc Susqu~Lnna plants Unit ¹1 10ppb Unit¹2 - 6ppb, la¹cyclethroughMarch-2ppb W

I Fe-59 - 4 times Beet average Mn 4 times Beet average (both Fc-59 and Mn-54 were lower in Umt ¹2 when the source term was reduced)

C~~ - 1/5 oftheQeet average (this is consistent with other high inn plants, most hkely a result ofthe Pc, Co spinel formed on thc fuel. C+40 couM increase with a long tenn decrease in feedwater iron)

CMO~ - normal to low cotnpared to the Qeet average GE Nuclear Energy is for the most part in agreement with the suntrntuy evaluation of the dfects that the Susquehama Plant wiu experience with the implementation ofHWC with minor exceptions.

l. Upon initiation ofHWC under thc current chenustry conditions we feel that the dry weu (pipmg) dose rates wB1 mcrease doser to the actor of seven rather than the lower factor of three suggested in the report. The high crud loading resulting &am the high iron input willdrive the dose rates and hot spots. The increase willbe driven by the transport of insoluble crud, the size ofthe crud particles willbc small, possibly in the colloidal range. These small particles can easily incorporate mto the oxide Shn. Brunswick, with a history ofhigh iron input, had a shnilar occurrence because of the high crud inventory in the vessel. At Brunswick, during a mid cycle outage, crud was visually detected in the bottom ofthe annulus. It was planned to vacuum this observed crud during the next Sdl refueling outage, during the subsequent outage this crud in the bottom annuhs was not found.

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'2. Long term mitigation teclmiques for slattdowa dose rle control shouldinchde both prior feedwater iron rection and introduction of depleted zmc oxide gQO). Ifnatural zmc was injected into the plants t HWC implementation one would cqxet an approxnnate 5% reductionin the overall dry well dose zaea, the downside is the higher

~5 concetttration. The plants could benefit by injecting DZO, hotwever, with the high feedwater iron coacemuations this is most likely aot cost e6cetitve. Kthe feedwater iron is rohced, GE would reconuaend that zine mjectionbe initiated six months before HVFC to incorporate zinc into the crud. CoMt is heM much more tenaciously in the fuel crud with the pressrun ofzinc.

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3. With the implementation of moderate HNC d Ddlhdggg . Ib' 5

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4. The featwater iron reduction is a necessity. Ifthe feedwater iron is reduced to 1-2 Pll,

.: Pl llbdlb bd 5 5 three month period I

aBer the addnion lb dg of ll DZO. There OIZO are Db 5 bldOZI 'lh' 0 d h antently eiglueen BWR's on zinc injection with twelve onDZO. Ofthe six plants currently on zinc but aot DZO, four are strongly considering DZO. Several other plants are in the evaluation stage ofzinc

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5. Deconaunination's willbe retuired after HWC implenumtationb The experience at Brunswick with Citrox was not acceptable, very low DF'i were obtamed. Subsequently, Vecaa (currently PN Services - Westmghouse) performed a series of decem tests with artif'acts from both Brunswick 01 and 02, these tests indicate that Citrox or Citrox-hP-

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Citrox is not as effective as other decontamination solutions. This shmdd be discussed U d .33 5 'dd Lomi-AP-Lomi process. Fitzpatrick Bhns were also successMly removed with the Lomi--

AP-Lomi with a DF of approxinutely 12. The Glms from both plarns had even better DFs gl NPI MO Pl Ph g IODO systems during thir Spring 96 outage using Lomi-NP-Lomi. PN Services have recommended to Hatch the use of the Lcnm-NP-Lomi based on the experience at the Brunswick Plant.

6. Hydrogen cychng has been shown to have a pronounced effect of the dry w'ell dose rates. Laboratory studies as well as plant experiences have shown that resulting dose rates .

can be 25<0 41m higher with frequent cycling compared to steady state HWC.

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7. MSLR level willmcrease Svo tune normal with the implementation of moderIte HWC. These increases have or willhave varying degrees ofin3pact on plants.

At several phats, Le. Quad Cities, Dresdag Hatch, the impact has been minimal and have I,'M 'h~~d not required any plant modi6cations. Other phnts have managed the impem with

'iet I shielding at speci6c locations ontheaubme deck. Those pbutts that have are sensitive to the increases or plants are located very dose to general polxdation and have small owner controller acreage,'Le. Vernant Yankee, certati Eurepean PlantL In your evaluation the environmental dose rate increases were ahhessed and it was concluded that the increases were manageable.

Other than the above, we agree with the evahation and conchsions that were stated in the reports. Any luther questions feel See to call me at(408) 925-1 106.

Sincerely, ames Principle Chemist GE Nuclear Energy cc: Bill Marble Marcus Urioste Tom Hurst

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