ML18017A053
| ML18017A053 | |
| 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: |
| References | |
| EC-ENVR-1026, EC-ENVR-1026-R, EC-ENVR-1026-R00, NUDOCS 9705200153 | |
| Download: ML18017A053 (89) | |
Text
gg NUCLEAR ENGINEERING CALCULATIONI STUDY COVER SHEET and NUCLEAR RECORDS TRANSMITTALSHEET Fiie ¹ R2>>1
- 1. Page 1 of41 Total 1
'2. TYPE:
CALC
)'3. NUMBER:
EC-ENVR-1026
>4. REVISION:
0
- 5. TRANSMITTAL¹.
>6. UNIT:
3
">7. QUALITYCLASS:
R
'>8. DISCIPLINE:
R
>9. DESCRIPTION:
SSES Maximum Offsite Dose Rate from ISFSI & Other Fuel C cle Sources SUPERSEDED BY:
EC-
- 10. Alternate Number.
12: Computer Code or Model used:
See Section 4.1
- 13. Application:
'>14 Affected Systems:
089
- 'fN/A then line 15 is mandatory.
- >15. NON-SYSTEM DESIGNATOR:
ENVR
- 16. Affected Documents:
- 11. Cycle:
Fiche Q
Disks H Am'I
- 17.
References:
See Section 6.0
- 18. Equipment I Component ¹:
- 19. DBD Number.
>20.
PREPARED BY Print Name R. F. El Jr.
Si nature
>22. APPROVED BYI DAT Print Name C. J. Kalter Si nature I'd Z.
>21. REVIEWED BY Print Name R. K. Barcla Si nature
'eFC~j ~e c.
- 23. ACCEPTED BY PP&LI DATE Print Name Si nature P
e NR-DCS SIGNATURE/0 BECOMPLE D
Y,Nucl.EAR RECORDS RECEIvFD ADDA NEW COVER PAGE FOR EAGHREVISION FORM NEPM-QA4221-1, Revhlon1 NC-v
'ei
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SSES Calc. No.
EC-ENVR-1 026 Max Offsite Dose Rate Rev. 0 from ISFSI & Other'uel Cycle Sources Sh. No.
Section Description TABLE OF CONTENTS Page
~ 1.0 2.0 3.0 4.0 4;1
. 4.2 4.3 4.3.1 4.3.2 44 4.4.1 4.4.2 4.4.3 4 4 4 4.5 4.6 4.7 4.8 5.0 6.0 OBJECTIVE CONCLUSIONS AND RECOMMENDATIONS ASSUMPTIONS/INPUTS METHOD COMPUTER PROGRAMS USED LOCATION OF DOSE POINTS SPENT FUEL Transport of NUHOMS Transfer Cask ISFSI TURBINE BUILDINGSOURCES Dose Point 1 Dose Point 2 Dose Point 3 Dose Point 4 CONDENSATE STORAGE TANKS (CST)
LLRWHF TEMPORARY LAUNDRYFACILITY DAWVOLUMEREDUCTION SYSTEM RESULTS REFERENCES 17 17 17 18 18 19 19 19 21 22 24 28 30 31 32 39 39
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EC-ENVR-1026 Rev. 0 List of Tables 3-1 3-2 3-3 3-5 4-1 12 14 15 16 34 Total Dose Rate (n+ y) from NUHOMSO~ Transfer Cask During Transport as a Function of Distance 11 Total Dose Rate (n+ y) from ISFSI as a Function of Distance Dose Rates at the 500 kV Switchyard from the Turbine Building, CSTs, and LLRWHF N-16 Source Activities in Turbine/Main Steam Components Condensate Storage Tank Isotopic Inventory LLRWHF Dose Rates at Security Fence South of the Facility Distances from Sources to Dose Points 4-2 Dose Rates at the Specified Dose Points 35 List of Figures 4-1 Dose Point Locations 36 4-2 Total Dose Rate (n+ y) from NUHOMS Transfer Cask During Transport as a Function of Distance 37 4-3 Total Dose Rate (n+ y) from ISFSI as a Function of Distance 38 List of Attachments 1-Letter from J. L. Simpson, GE Nuclear Energy, to J. C. Pacer, PP8L, "Review of the Susquehanna Steam Electric Station Assessment of Impact of Hydrogen Water Chemistry on Radiation Field Buildup", 11/7/95 (Ref. 6.3) (5 pages).
2-3-
4-Turbine Building IVIICROSKYSHINEAND MICROSHIELD Models, Figures 1
through 6 of EC-HPHY-0518 (Ref. 6.1) (7 pages).
Memo from Robert K. Barclay to Kevin J. Kelenski, "Susquehanna Steam Electric Station Assumptions Regarding Movement of Spent Fuel to ISFSI," PLI-82098, 0/11/96 (Ref. 6.9) (3 pages).
Letter from, to Kevin Kelenski, PP8 L, "Total Dose Rate Contributed by Cask During Transfer to the Susquehanna ISFSI Site", 8/16/95 (Ref. 6.11) (1 page).
I
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SSES Gale. No.
EC-ENVR-1026 Max Offsite Dose Rate Rev. 0 from ISFSI 8 Other Fuel Cycle Sources Sh. No.
5-6-
7-8-
Letter from Norman Eng, VECTRATechnologies, to Kevin Kelenski, PP8L, "Total Dose Rate Contributed by NUHOMS Transfer Cask During Transfer to the Susquehanna ISFSI Site," Vectra Letter Number 16-77-96-052 dated 5/21/96 (Ref.
6.12) (4 pages).
MICROSKYSHINE Results (15 pages)
MICROSHIELD Results (19 pages)
Attachment 1 to Safety Evaluation NL-89-002 (Ref. 6.17) (4 pages).
)
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of 1.0 OBJECTIVE The purpose of this calculation is to determine the maximum dose rate (mrem/hr) in unrestricted areas from transport to and storage of spent nuclear fuel at the proposed location of the SSES Independent Spent Fuel Storage Installation (ISFSI) to assure compliance with 10CFR f20.1301 (Ref. 6.2). Dose rates calculated herein include contributions from ISFSI storage and transport on-site, shine from the turbine building under full power hydrogen water chemistry (HWC) conditions, shine from the condensate storage tanks (CSTs), and Low Level Radwaste Handling Facility (LLRWHF) storage and transportation on-site. Also addressed, are the impact of the Temporary Laundry Facility and the DAW Reduction System Facility.
This calculation is prepared in support of the licensing effort for the proposed ISFSI.
2.0 CONCLUSION
S AND RECOMMENDATIONS Based on results herein, the maximum dose rate in an unrestricted area from SSES fuel cycle components, including storage and transport of spent fuel to the ISFSI, is 1.2 mrem/hr; this occurs at the fence to the south of the plant, the area of closest approach of the NUHOMS transport trailer to an unrestricted area.
This dose rate is less than the 10CFR f20.1301 maximum allowed dose rate in an unrestricted area of2.0-mrem/hr. Almost all of this dose rate is attributed to transport of a loaded NUHOMS transfer cask to the ISFSI; all other sources, including consideration of HWC, contribute less than 1% of the dose rate.
It should be noted that the dose rate from the transfer cask is based on an assumed 10 year cooling time; reducing the cooling time for spent fuel to be transported to less, than 10 years would increase the maximum calculated dose rate in an unrestricted area, The maximum dose rate in an unrestricted area from transport of a loaded NUHOMS transfer cask to the ISFSI is 1.2 mrem/hr; this occurs along the south fence. The maximum dose rate in an unrestricted area from storage of the casks at the ISFSI is 0.02 mrem/hr, this occurs at the construction fence due west of the ISFSI.
The maximum dose rate in an unrestricted area from the Turbine Building including the effects of hydrogen water chemistry is 0.08 mR/hr.
3.0 ASSUMPTIONS/INPUTS The following assumptions and input are used.
There are no assumptions requiring later confirmation.
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EC-ENVR-1026 Rev. 0 3.1 References 6.4.c, d, and e show a construction fence between the security fence and Township Road T438. Credit is taken for this fence in determining the location of unrestricted areas.
3.2 3.3 The transport path from the Fuel Handling Building to the ISFSI is assumed to be the south road around the perimeter of the protected area (Ref. 6.9). Access to the ISFSI is via the gate at the southeast corner of the ISFSI. Transfer to the railroad track west of the ISFSI (i.e. ultimate disposition of the spent fuel)is not considered.
Total dose. rate (neutron plus gamma) from a NUHOMS transfer cask containing fuel with a 10 year cooling time as a function of distance is provided in Table 3-1 (Refs'. 6.11 and 6.12). This cooling time is consistent with the assumption that the minimum cooling time of fuel to be moved to the ISFSI is 10 years (Section 3.21). This is the dose rate from a closed transfer cask during transport.
It does not address local streaming effects when the cask top cover plate, ram access penetration shield plugs, and HSM shield
'ccess door are removed.
3.4 3.5 3.6 Total dose rate (neutron and gamma) from high-level waste storage in the ISFSI as a function of distance is provided in Table 3-2 (Ref. 6.10). The fullyoccupied 2010 Scenario loaded with base case fuel (10 year old spent fuel) and with theoretical limiting (design basis) case (5 year old fuel) are evaluated.
Transport of one transfer cask to the ISFSI at a time is considered.
Simultaneous transport of low level radwaste to the LLRWHFor a second transfer cask is not considered /Ref. 6.9).
Dose rates from major Turbine Building components, the Condensate Storage Tanks, and the LLRWHFwere calculated in Ref. 6.1 at a point 960'outh and 640'est of the Turbine Building, nominally the middle of the north fence around the 500 kV Switchyard (depicted as point A on Fig. 4-1). The results tabulated in Section 6.1 of this reference are summarized in Table 3-3 herein.
Key assumptions from Ref. 6.1 are included below; discussion and justification of all assumptions is provided in the reference calculation.
3.7 Implementation of Hydrogen Water Chemistry (HWC) at a moderate injection rate is assumed.
Based on discussion in Ref. 6.3, the N-16 source activities for the turbine/main steam components provided in Ref. 6.1 (i.e. no hydrogen water chemistry (NWC)) are increased by a factor of five (5.0).
It is noted that the Ref. 6.1 source term of 50 pCi/gm was conservatively assumed to be 100% N-16 instead of 80% N-16 and 20% C-15. Implementation. of HWC is not expected to affect C-15; thus, this
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EC-ENVR-1026 Max Offsite Dose Rate Rev. 0 from ISFSI & Other Fuel Cycle Sources Sh. No.
assumption is still conservative.
The NWC source activities developed in Ref. 6.1 and the corresponding HWC source activities are shown in Table 3-4.
3.8 Per Ref. 6.9, calculations for dose rate contributions from turbine component are 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; this corresponds to a power level of 3441 MWt (Ref. 6.18).
3.9 The effect of local shielding, such as the concrete panels over the moisture separators, is considered herein.
Shielding effects of intermediate equipment and structures are not considered except as discussed in Section 4.
3.10 The Turbine Bay Operating Floor geometry is shown in Ref. 6.1, Figure 1. This figure shows the overall layout and distances to the outside corners of the building. Location of individual components and shield walls is shown in Ref. 6.1, Figures 2 through 6.
The Unit 2 area is a mirror image of Unit 1; it is not separately shown.
Distance to the dose points from each unit are separately considered.
Figures 1 through 6 of Ref. 6.1 willbe used in Section 4 to develop the source to dose point distances in Section 4. These figures are provided in Attachment 2 for convenience.
3.11 Turbine component an'd steam source modeling is obtained from Ref. 6.1. This calculation considers the exposure rate contribution from the moisture separators, 42" cross-around piping from the moisture separators to the CIVs, CIVs, CIV~LP turbine piping, HP and LP turbines, and the HP turbine inlet piping. Unit 1 and Unit 2 turbine component sources are assumed to be identical, except for location.
Source models of the Turbine Building components were developed in Section 5.2 of Ref. 6.1. Those parameters that are used in Section 4 are presented in the following sections.
Source densities and strengths are given in Table 3-4.
3.11.1 Moisture Separators (Ref. 6.1, Section 5.2.1)
The Moisture Separator is modeled as a horizontal cylinder located as shown in Ref.
6.1, Figure 3. The labyrinth walls are ignored.
MICROSHIELD (Ref. 6.1, Section 5.2.1 8 Fig. 3) geometry-Source at Side (shield wall along column G for dose points west of the Turbine Building)-
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of L = source length = 67.29' 2051 cm T1 = radius = 163 cm T2 = iron shell = 3.18 cm T3 = (MS Ci to shield wall) - (MS radius) = 7.5'163 cm = 67 cm air T4 = concrete shield = 3' 91 cm 3.11.2 Cross-around piping (CAP) (Ref. 6.1, Section 5.2.2, Fig. 4)
Instead of modeling each cross-around pipe segment separately as a cylinder, the piping for each MS is modeled as an equivalent point source, located as shown in Ref.
6.1, Figure 4. A review of the piping drawings indicates all four Moisture Separators have similar piping arrangements; the detailed model is based on the west Unit 2 Moisture Separator (2B2T1 04B).
MICROSHIELD-CAP (Ref. 6.1, Section 5.4.1.2, Fig. 4) geometry 1- "Point Source-slab shields" T1 = 14.75' 450 cm (air space between source point and shield wall at column G)
T2 = 0.375" = 0.953 cm, steel pipe wall T3 = 3' 91 cm, concrete shield wall 3.11.3 CIV Piping Model (Ref. 6.1, Section 5,2.4 and Fig. 4)
Piping from the CIVs to the LP Turbines is depicted in Ref. 6.1, Figure 4. The N-16 inventory of the elbow as well as the horizontal pipe run is assumed to be in a horizontal cylinder of length equal to that of the horizontal run with its end at the outside edge of the partial shield wall ~ Neither the shielding nor the scattering provided by the turbines is considered in the skyshine calculations.
MICROSKYSHINE Parameters-CIV Piping L=10'=3m Radius = W = 0.52 m T1 = cover slab-none = 0 T2 = second shield = pipe wall = 0.375" = 0.01 m iron Y=7.8m Elevation of top of shield wall =
756.5'.12 Shield material densities used are those from the MICROSKYSHINEand MICROSHIELD codes:
Iron:
7.86 g/cm'oncrete:
2.35 g/cm'
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of 3.13 In Ref. 6.1, use of the center CIVs/piping (¹ 2 and ¹5) to model a set of three CIVs and piping associated with one moisture separator is justified. The CIV piping source presented in Table 3-4 is for one component, thus, the results of the CIV piping calculations are multiplied by three to encompass three components.
It is noted that the point source model for the cross-around piping represents the total CAP source for one moisture separator.
3.14 Buildup factors are based on air (Ref. 6.1).
3.15 The dose rate 1200'rom the Condensate Storage Tank (CST) (i.e. 500 kV Switchyard)
(Ref. 6,1, Section 5.6):
IVIICROSKYSHINE 3.1EW mR/hr MICROSHIELD 4.2E-5 mR/hr 3,16 LLRWHFdose rates (storage only; does not include movement or inspection activities):
500 kV Switchyard-2.1E-4 mR/hr (Ref. 6.1, Section 5.5.5) distance-288.2 m = 945'Ref. 6.1, Section 5.5.2).
Security fence (*) due south of the LLRWHF-Table 3-6 (Ref. 6.13, Table 12-3)
- (Dose point B depicted on Fig. 4-1, not the Construction Fence discussed in Section 3.1) 3,17 The skyshine contribution from the Temporary Laundry Facility to the EOF/Towers Club is 7.071E-5 mR/hr, this was based on an inventory of 1.2 Ci (Ref. 6.15).
The maximum exposure rate estimated for a receiver at the one foot perimeter of the laundry facility is 7.94 mR/hr (Ref. 6.15).
3.18 The skyshine contribution from the Turbine Building to the EOF/Towers Club is 2.24E-4 mR/hr (Table 4-1b of Ref. 6.16).
3.19 The DAW.Reduction System facilityparameters (Ref. 6.17) maximum inventory = 30 mCi, with a realistic estimate at one-tenth that amount (3 mCi total) maximum inventqry based on 150 bags each containing 200 pCi of Co0 with contact dose rate of 2 mR/hr bag dimensions = 38.1 cm radius x 76.2 cm high
0
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of 3.20 The dose rate equivalent (mrem/hr) was shown to be approximately the same as the dose rate (mR/hr) for the Turbine Building sources, CSTs, and LLRWHF in Section 6.4 of Ref. 6.1.
Do'se rates provided by Vectra are mrem/hr; no conversion is required.
3.21 The minimum cooling time of the fuel to be moved to the ISFSI is 10 years (Ref. 6.9).
3.22 Condensate Storage Tank MICROSKYSHINE Model (Ref. 6.1, Section 5.6):
geometry-vertical cylinder source in a silo Y
= Depth of source in silo = 0.01 m.
R1
= Distance between source and shield wall = 20.0 m'1
= Thickness of concrete slab cover = 0.0 m.
T2
= Thickness of second shield = 0.0 m L
= = Length of source = 9.75 m.
W
= Radius of source = 20' 6.1 m.
top of CST = 670' 32' 702'sotopic inventory for shielding purposes per FSAR Table 12.2-29 (Ref. 6.19). Six isotopes (Rb-91, Sr-94, Y-94, Y-95, Cs-140, and Cs-141) included in Ref. 6.19 are not included in the MICROSKYSHINE library. The half-lives of these isotopes range from 25 seconds to 19 minutes (Ref. 6.20). Further consideration of these isotopes is not necessary.
Values are tabulated in Table 3-5.
Source material-water, density 1 gm/cc.
3.23 Refueling Water Storage Tank Parameters (Ref. 6.21):
diameter
= 50' height
=48'.24 The dose points are assumed to be 6'bove grade.
PP &LCALCULATIONSHEET Rept ate 10/2/96 esigned By Checked By PROJECT:
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~1 of Table 3-1 Total Dose Rate (n+ y) from NUHOMS Transfer Cask During Transport as a Function of Distance (1)
Distance from Cask Dose Rate (n+ y) mrem/hr meters 10 15 20 25 30 feet 16.4 32.8 49.2 65.6 82.0 98.4 300 450 9.23 2.49 1.10 0.61 0.40 0.33 3.6E-3 6.1E-4 Notes:
- 1. Refs. 6.11 and 6.12.
Table 3-2 Total Dose Rate (n+ y) from ISFSI as a Function of Distance (1)
Distance (feet) 450 Townshi Rd. T438 1050 Townshi Rd. T419 1400 Towers Club 1450 500 kV Switch ard 1600 NIMS Center 2763 Res. Sector 16 Theoretical Limiting Case mrem/hr 3.42E-2 3:77E-3 1.20E-'3 1.01E-3 6.57E-4 2.78E-5 Base Case (mrem/yr) 2.03E-2 2.24E-3 7.16E-4 6.03E-4 3.92EQ 1.67E-G Notes:
- 1. Ref. 6.10, Table 13.
pt IIILIICb rate 10/2/96 Designed By Checked By PPBL CALCULATIONSHEET of PROJECT: SSES'ale.
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EC-ENVR-1026 Max Offsite Dose Rate Rev. 0 from ISFSI 8 Other Fuel Cycle Sources Sh. No.
Table 3-3 (page 1 of 2)
Dose Rates at the 500 kV Switchyard from the Turbine Building, CSTs, and LLRWHF (1)
Moisture Se arators Unit 1 East Unit 1 West Unit 2 East Unit 2 West Cross-around Pi in CAP Unit 1 East Unit 1 West Unit 2 East Unit 2 West skyshine mR/hr 1.0E-5 1.2E-5 2.2E-5 2.5E-5 5.4E-6 5.8E-6 1.1E-5 1.3E-5 direct mR/hr NA 1.4E-5 NA 1.9E-5 NA NA NA 1.2E-6 CIVs Unit 1 East Unit 1 West Unit 2 East Unit 2 West 3.2E-5 1.0E-5 5.8E-5 1.6E-5 NA NA NA NA CIVPi in Unit 1 East Unit 1 West Unit 2 East Unit 2 West 1.4E-4 5.2E-5 2.2E-4 6.4E-5 NA NA NA NA HPT Unit 1 Unit 2 9.4E-7
, 2.7E-6 NA 5.7E-7 LPT Unit 1 Unit 2 5.6EW 7.7E-6 4.4E-7 NA Note:
- 1. Section 6.1, Ref. 6.1.
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Dose Rates at the 500 kV Switchyard from the Turbine Building, CSTs, and LLRWHF (1)
HPT Inlet Pi in - Horizontal Unit 1 East Unit 1 West Unit 2 East Unit 2 West HPT Inlet Pi in - Horizontal Unit 1 East Unit 1 West Unit 2 East Unit 2 West skyshine mR/hr 2.8E-5 2.1E-G 6.0E-5 4.5E-5 1.6E-5 8.1E-6 3.5E-G 1.8E-5 direct mR/hr NA.
NA.
NA NA NA NA NA Subtotal Turbine Buildin 9.4E-4 3.5E-5 CST 3.1E-6 4.2E-5 LLRWHF sk shine+ direct.
2.1E-4 Total 1.2E-3 7.7E-G Total sk shine+ direct 1.3E-3 Note:
- 1. Section 6.1, Ref. 6.1.
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of Table 3-4 N-16 Source Activities in Turbine/Main Steam Components Turbine/Main Steam Component Source Density (1) m/cc N-1 6 Activity (NWC) (2)
Ci N-1 6 Activity (HWC) (3)
Ci Moisture Se arator Cross-around Pi in CIV i in 0.44 0.0064 51 255.0 37.0 5
5.0 6 Notes:
1.
2.
3.
4 5.
6.
Ref. 6.1, Section 5.2.
Normal Water Chemistry (NWC) inventory per Ref. 6.1.
Hydrogen Water Chemistry (HWC) a factor of five higher than NWC (Section 3.7).
Not applicable; point source.
Total activity for all cross-around piping for one Moisture Separator.
Activityfor piping associated with one CIV; the dose rates determined using this activity must be multiplied by a factor of three to encompass three piping runs associated with one moisture separator(Section 3.13).
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of Table 3-5 Condensate Storage Tank Isotopic Inventory (1)
Nuclide Ba-137m Ba-140 Ba-142 Br-84 Co-58 Cr-51 Cs-1 36 Cs-1 39 l-132 I-1 34 La-140 La-142 Mo-99 Ni-65 Rb-88 Rb-90 Sr-90 Sr-92 Tc-99m Te-132 Y-91 Y-92 Activity Ci 1.36e-04 2
1.12e-03 1.78e-03 1
~ 10e-02 5.67e-04 5.66e-05 6.20e-05 2.91e-02 1.36e-01 1.45e-01 6.12e-05 1.23e-03 2.41e-03 1.77e-05 2.13e-03 2.03e-02 2.61e-05 8.54e-03 2.35e-02 5.40e-03 1.46e-05 3.44e-03 Nuclide Ba-1 39 Ba-141 Br-83 Br-85 Co-60 Cs-134 Cs-138 I-131 I-133 I-135 La-141 IVIn-56 Na-24 N -239 Rb-89 Sr-89 Sr-91 Sr-93 Tc-101 W-1 87 Y-91m Y-93 Activity Ci 2.56e-02 4.72e-03 1.72e-02 5.05e-04 5.68e-05 9.08e-05 2.87e-02 2.92e-02 1.84e-01 2.19e-01 1.89e-03 2.97e-03 1.97e-04 2.62e-02 1.42e-02 3.78e-04 9.45e-03 7.89e-04 1.32e-03 3.11e-04 5.11e-03 1.71e-04 Notes:
- 1. Isotopic inventory for shielding purposes per Section 3.22.
- 2. Cs-137 has been listed as Ba-137m, because MICROSHIELD and MICROSKYSHINEattribute the 0.664 Mev gamma to the latter isotope.
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of Table 3-6 LLRWHF Dose Rates at Security Fence South of the Facility (1)
Exposure Source CD/SS Stora e: Direct CD/SS Stora e: Sk shine DAW Stora e: Direct DAWStora e: Sk shine LSM Stora e Outer Row: Direct LSM Stora e Inner Row: Direct LSMStora e: Sk shine Exposure Rate mR/hr 9.74E-4 3.39E-4 9.32E-5 1.29E-4 1.19E-2 9.22E-5 3.36E-3 Total 2 0.017 Notes:
- 1. Ref. 6.13, Table 12-3.
- 2. Total is sum of the individual sources; this was not provided in the reference.
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of 4.0 4.1 METHOD COMPUTER PROGRAMS USED 4.1.1 MICROSKYSHINE, Version 1.16, Grove Engineering, Inc. Rockville, MD, 20850, 1988 (Ref. 6.5 and 6.6).,
4.1.2 MICROSHIELD, Version 3.12, Grove Engineering, Inc. Rockville, MD, 20850, 1988 (Ref. 6.7 and 6.8).
4.2 LOCATION OF DOSE POINTS Figure 4-1 shows the location of the dose points that are analyzed in this calculation.
This figure is a partial view of Ref. 6.4.a; the ISFSI has been added based on its size and location shown on IDCN 7 to this drawing. Distances from the sources to the dose points are provided in Table 4-1; the'se were obtained from scaling from these drawings.
Point 1 is located adjacent to the security fence south of the plant; it was chosen, because it is the shortest distance between the transport path and an unrestricted area.
The east-west location of this point is not critical, because it is minimally affected by the Turbine Building and Condensate Storage Tanks to the northeast and by the ISFSI and LLRWHFto the northwest.
As shown in subsequent sections, the major dose component at this location is from the transfer cask itself. This dose point is conservatively shifted east-west to maximize each component of the dose rate in the following sections..
Point 2 is located south of the LLRWHFwhere the construction fence ends adjacent to the security fence; it was chosen, because it is close to the path of transit (i.e. the south road) and is close to both the LLRWHFand the ISFSI.
Point 3 is at the construction fence west of the ISFSI; it was chosen for its proximity to the ISFSI.
It is noted that the construction fence is 104'est of the security fence (scaled from Ref. 6.4.c).
Point 4 is adjacent to the security fence north of the plant; it was chosen for its proximity to the Turbine Building. Although the ISFSI and transport of spent fuel is expected to have minimal impact at this location, it is expected to be the highest dose point from the Turbine Building,
0
PP8 L CALCULATIONSHEET pl JlaaZaJI ate 10/2/96 Designed By Checked By PROJECT:
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EC-ENVR-1026 Rev. 0 The grade elevation at the dose points is determined from Ref. 6.4.g and 6.4.h.
Per Section 3.24, the dose points are assumed to be 6'bove grade.
Grade Elevation Dose point 1-700'06'-
730'36'-
725'31'-
710'16'.3 SPENT FUEL Dose rates from transport of spent fuel in a NUHOMS transfer cask to the ISFSI and from storage of spent fuel at the ISFSI are based on calculations performed by Vectra in support of the project (References 6.10, 6.11, and 6.12). These sources are considered first, because, as discussed in following s'ections, they are the major contributors to the dose rate at the selected dose points. Other contributions to the dose rate are considered only as they impact the total dose rate.
It should be noted that, although transport is the highest contributor to the dose rate at the fence, it is not significant to the annual dose to Members of the Public, because the transit time and number of transfers per year are small; evaluation of annual dose is beyond the scope of this calculation (see Ref. 6.16 for annual dose calculation).
4.3.1 Transport of NUHOMS Transfer Cask The distance from the transport path to the dose points is determined as follows:
Dose point:
1-48'rom outer security fence to edge of road (scaled from Ref. 6.4.f).
2-84'rom outer security fence to edge of road (scaled from Ref. 6.4.e).
3-The distance from the west fence of the ISFSI to the construction fence ranges from 342'o 348'scaled from Ref. 6.4.c). This is a minimum distanceactual movement of the transfer cask within the ISFSI and local streaming effects when the cask top cover plate, ram access penetration shield plugs, and HSM shield access door are removed are not addressed (Sections 3.2 and 3.3).
4-676'rom the center of the Reactor Building to the fence (scaled from Ref. 6.4.g).
This represents the nominal minimum distance the transport vehicle, as it exits the Reactor Building, would approach this dose point.
The total dose rate'from the transfer cask during transport to the ISFSI as a function of distance is provided in Table 3-1; this has been plotted for use in determining the dose
PP8 L CALCULATIONSHEET
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of rate at other distances in Fig. 4-2. The maximum dose rate from transport of a transfer cask at each of the dose points is provided in Table 4-2.
4.3.2 ISFSI The distance from the center of the ISFSI to the dose points is determined as follows:
Dose point:
1-1450'conservatively use 500 kV Switchyard dose point identified in Table 3-2);
this is the nearest point along the south fence to the ISFSI.
2-1190'scaled from Fig. 4-1) ~
3-The minimum distance from the center of the ISFSI to the construction fence is 450'scaled from Ref. 6.4.c).
4-1563'scaled from Fig. 4-1).
The total dose rate from the ISFSI for both the theoretical limiting and the base case loading as a function of distance is provided in Table 3-2; this has been plotted for use in determining the dose rate at other distances in Fig. 4-3. The dose rate from the ISFSI at each of the dose points is obtained from Fig. 4-3 and is provided in Table 4-2.
As noted in Section 3.4, the minimum cooling of the fuel to be stored at the ISFSI is 10 years, corresponding to the base case loading.
Use of the theoretical limiting loading at the ISFSI affects the total dose rate only at dose point 3.
The total dose rate at each of the dose points from transport of a transfer cask and from the ISFSI is also provided'in Table 4-2.
4.4 TURBINE BUILDINGSOURCES 4,4.1 Dose Point1 This dose point is adjacent to the 500 kV Switchyard. A dose rate of 9.8E-4 mR/hr from the Turbine Building (Table 3-3) has previously been determined for a point 960'outh and 640'est of the Turbine Building, nominally the middle of the north fence around the switchyard, considering both skyshine and direct radiation (point A on Fig, 4-1).
This point is farther from the Turbine Building than Dose Point 1. One Turbine Building source is evaluated at dose point 1 to demonstrate that the difference in location and consideration of HWC is not significant to the total dose rate at point 1, because the Turbine Building dose rate is insignificant (<0.1%) compared to the dose rate from transport of the transfer cask past this point (1.2 mrem/hr per Table 4-2).
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EC-ENVR-1026 Rev. 0 The largest dose contributor from the Turbine Building to point A is the Unit 2 East CIV piping (2.2E-4 mR/hr per Table 3-3; this is approximately 22% of the total dose rate from the Turbine Building, 9.8E-4 mR/hr per Table 3-3). This would be the largest contributor at dose point 1, because of the similarity in distance and direction from the Turbine Building to the two dose points. The skyshine component of the dose rate from this piping is calculated to demonstrate that the different location is not significant to the calculated dose rate at point 1. The factor of five increase due to the effects of HWC itself is not significant, because the dose rate is insignificant compared to the transfer cask dose rate.
MICROSKYSHINE Parameters-CIV Piping model per Section 3.11.3 frame ef reference:
+X: from east to west
+Z: from south to north o 4
~~
~
4 shield wall is along column Gd (distances are obtained from Table 4-1 and attachment 2 figures):
X = 300' 3'9" + 27' 1'2" = 332'.1 01 m Z = 830' 9" + 72' 36' 54' 993' 303 m (based on CIV-5)
H = 756.5' 706' 50.5' 15.4 m R1 =R2=9m The dose rate at dose point 1 from the CIV-5 piping run is 1.0E-3 mR/hr (MICROSKYSHINErun 2CIVEPT1.SKY in Attachment 6); multiplying by a factor of three as described in Section 3.13 gives a total dose rate of 3.0E-3 mR/hr from the Unit 2 East CIV piping. This value is less than a factor of 15 greater than that of dose point A (2.2EQ mR/hr). Note, the increase is a factor of five for HWC consideration and less than a factor of three for location, The dose rate at point 1'from the Turbine Building can be estimated by multiplying the total dose rate at point Afrom the Turbine Building (9.8E-4 mR/hr) by a factor of 15; giving 0.01 mR/hr. This is <1% of the transfer cask/ISFSI dose rate at point 1; therefore, additional analysis of the Turbine Building contribution to the dose rate at point 1 need not be performed.
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A second MICROSKYSHINE run was made to determine the effect of increasing the integration parameters from 5/5/5/1,6 to 20/20/20/32.
The difference in results is not significant (1.015E-3 and 1.017E-3 mR/hr in runs 2CIVEPT1.SKY and 2CIVEP1I.SKY, respectively in Attachment 6). Thus, since the result is not significant for this case; the smaller parameters are used here and for calculations for other dose points.
4.4.2 Dose Point 2 Dose point 2 is in the same general direction from the Turbine Building as the 500 kV Switchyard (point A on Fig. 4-1) and EOF analyzed in Ref. 6.1.
It is anticipated that the skyshine component of the dose rate at point 2 is bounded by that at point A, because of the greater distance.
The Unit 2 Cooling Tower is in the direct path between the Turbine Buildings and dose point 2; it provides a partial shield for the skyshine component from the Turbine Building sources, further decreasing the dose rate at point 2 compared with point A.
The largest dose contributor from the Turbine Building to point A is the Unit 2 East CIV piping (2.2E-4 mR/hr per Table 3-3); this would be the largest contributor at dose point 2, also. The skyshine component of the dose rate from this source is calculated to demonstrate that the dose rate at point 2 is bounded by that of point A. The effect of the Cooling Tower is not considered.
MICROSKYSHINE Parameters-CIV Piping model per Section 3.11.3 frame of reference:
+X: from east to west
+Z: from south to north shield wall is along column Gd (distances are obtained from Table 4-1 and attachment 2 figures):
X = 1140' 3'9" + 27' 1'2" = 1172' 357 m Z = 610' 9" + 72' 36' 54' 773' 235 m H = 756.5' 736' 20.5' 6.25 m R1 = R2=9m The dose rate at dose point 2 from one Unit 2 CIV piping run is 1.SEE mR/hr (MICROSKYSHINErun 2CIVEPT2.SKY in Attachment 6); multiplying by a factor of three as described in Section 3.13 gives a total dose rate of 5.4E-4 mR/hr from the Unit 2
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EC-ENVR-1026 Max Offsite Dose Rate Rev. 0 from ISFSI 8 Other-Fuel Cycle Sources 4.4.3 East CIV piping. The dose rate at point 2 from the CIV piping is slightly higher than that determined in Ref. 6.1 for the 500 kV Switchyard when the effects of Hydrogen Water Chemistry are considered (Table 3-3) and, as expected, is less than that at the 500 kV Switchyard with a consistent HWC basis.
Shielding by the Cooling Towers was not considered in determining the direct dose rate contribution from the Turbine Building at the Switchyard in Ref. 6.1; in addition the albedo effect was shown to be negligible. Table 3-3 shows that the direct dose at point A (3.5E-5 mR/hr) is <4% of the skyshine dose (9.4E-4 mR/hr). Fig. 4-1 shows that dose point 2 is shielded by the Unit 2 Cooling Tower from the Turbine Building and is farther away from the Turbine Building than dose point A. Thus, the direct dose rate is expected to be significantly less at point 2 than at point A. Thus, it is not necessary to calculate a direct dose rate at point 2.
The total dose rate at point 2 from the Turbine Building can be estimated by multiplying the total dose rate at the 500 kV Switchyard, 9.8E-4 mR/hr, by a'factor of (5.4E-4/2.2E-4); this gives a total dose rate at dose point 2 from the Turbine Building of 2.4E-3 mR/hr (the direct dose rate at point A is included for conservatism even though, as described above, the direct dose at point 2 is expected to be significantly less than at point A). This dose rate is <1% of the dose rate from transport of the transfer cask past this point (0.4 mrem/hr per Table 4-2). Therefore, additional analysis of the Turbine Building contribution to the dose rate at point 2 need not be performed.
Dose Point 3 Although Ref. 6.1 does not address a dose point due west of the plant, i.e. in the general direction of dose point 3, the magnitude of the dose rates computed for the 500 kV Switchyard are sufficiently small compared to the dose rate at point 3 from the ISFSI and transfer cask (0.024 mrem/hr per Table 4-2) that detailed analysis is not required for point 3. It is expected that the dose rate at the Switchyard bounds that at point 3, because point 3 is farther from the Turbine Building; the change in direction is expected to have little impact..
Based on a review of the dose rates shown in Table 3-3, the CIV piping, as modeled, is generally expected to be the major dose contributor. The Unit 1 East CIV piping would be the largest skyshine dose contributor from the Turbine Building at point 3, because Unit 1 is nearer the Unit 2 and the east piping has a larger forward scattering angle than the west piping, The effect of the Cooling Towers is not considered, MICROSKYSHINE Parameters-CIV Piping model per Section 3.11.3
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frame of reference:
+X: from east to west
+Z: from south to north shield wall is along column..Gd (distances are obtained from Table 4-1 and attachment 2 figures):
X = 1725'+ 3'9" + 27'+ 1'2" = 1757' 536 m Z = 0 m (conservatively assume dose point 3 is directly opposite the source)
H = 756.5' 731' 25.5' 7.8 m R1 =R2=9m
\\
The dose rate at dose point 3 from one Unit 1 CIV piping run is 4.9E-5 mR/hr (MICROSKYSHINErun 1CIVEPT3.SKY in Attachment 6); multiplying by a factor of three as described in Section 3.13 gives a total dose rate of 1.5E-4 mR/hr from the Unit 1 East CIV piping, compared with 2.2E-4 mR/hr at point A. Thus, even considering the effect of HWC, the Turbine Building skyshine component of the dose rate at point 3 from the CIV piping is bounded by that determined in Ref. 6.1 for the 500 kV Switchyard (9.4E-4 mR/hr. point A). This is 4% of the transfer cask/ISFSI dose rate at point 3.
Thus, 9.4E-4 mR/hr willbe used as the skyshine component of the dose rate at point 3 from the Turbine Building instead of calculating the dose rate from each Turbine Building source.
The only sources that are expected to contribute a direct dose component at dose point 3 are the Unit 2 west Moisture Separator and cross around piping; the Unit 1 sources being shielded by the Unit 1 Cooling Tower and the other sources by other components.
MICROSHIELD is used to determine the magnitude ef the direct dose contribution from the moisture separator.
MICROSHIELD geometry 9, "Cylinder Source from Side-Combination Shields" (SAS) requires the dose point to be adjacent to the source.
Although dose point 3 is not adjacent to the Unit 2 Moisture Separator, this geometry is used to bound the dose rate at point 3 by assuming the dose point is adjacent to the north end of the Moisture Separator.
MICROSHIELD Parameters-Moisture Separator model per Section 3.11.1
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EC-ENVR-1026 Rev. 0 shield wall is along column G (distances are obtained from Table 4-1 and attachment 2 figures):
X = 1725' 3'9" + 1' 7.5' 1737' 53000 cm Y = L/2 = 2051/2 = 1025 cm (conservatively assume dose point 3 is directly opposite the source)
The dose rate at dose point 3 from the Unit 2 west Moisture Separator is 4.8E-4 mR/hr (MICROSHIELD run 2MSWP3.MSH in Attachment 6); this is 2% of the transfer cask/
ISFSI dose rate.
MICROSHIELD Parameters-CAP model per Section 3.11.2 shield wall is along column G (distances are obtained from Table 4-1 and attachment 2 figures):
X = 1725'+ 3'9" + 1'+ 14.75' 1744' 53200 cm Y = 749'-(725'+ 6') = 18' 550 cm The direct dose rate at dose point 3 from the Unit 2 cross around piping is 4.2EQ mR/hr (MICROSHIELDrun 2CAPP3.MSH in Attachment 7.
The total dose rate at point 3 from the Turbine Building is the sum of the following:
total skyshine dose rate
= 9.4E-4 mR/hr Unit 2 Moisture Separator.
= 4.8E-4 Unit 2 cross around piping
= 4.2E-4 total
= 1.8E-3
~
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4.4.4 Dose Point 4 Dose point 4 was chosen for its proximity to the Turbine Building, It is nominally diagonal to the Turbine Building with respect to the 500 kV Switchyard, i.e. dose point A. The east CIVpiping provides 38% of the dose rate at point A (1.4E-4 and 2.2E-4 compared to 9.4EP mR/hr from Table 3.-3). The west CIV piping would be the major contributor to dose point 4, because of the symmetry in the sources and the relative location of dose points A and 4.
MICROSKYSHINE Parameters-CIV Piping model per Section 3.11.3 frame of reference:
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EC-ENVR-1026 Rev. 0
+X: from west to east
+Z: from south to north shield wall is along column J (distances are obtained from Table 4-1 and attachment 2 figures):
Unit 1 west CIV piping (CIV-5):
X = 102'+ 9" + 62'3" + 32' 199' 61 m Z = 361'+ 9" + 72'+ 36'+ 54' 524' 160 m H = 756.5' 716' 40.5' 12.3 m R1 = R2=9m The dose rate from the Unit 1 west CIV piping is 3.5E-3 mR/hr (MICROSKYSHINErun 1CIVWP4.SKY in Attachment 6); multiplying by a factor of three as described in Section 3.13 gives a total dose rate of 0.011 mR/hr from the Unit 1 west CIV piping. This is a factor of 48 greater than that calculated at dose point A for the Unit 2 east CIVpiping (2.2E~ mR/hr).
Unit 2 west CIVpiping (CIV-5):
X=61m Z = 361' 9" + 72' 36' 108' 198' 54' 830' 253 m The dose rate from the Unit 2 west GIV piping is 1.9E-3 mR/hr (MICROSKYSHINErun 2CIVWP4.SKY in Attachment 6); multiplying by a factor of three as described in Section, 3.13 gives a total dose rate of 5.7E-3 mR/hr. This is a factor of 41 greater than that calculated at dose point Afor the Unit 1 east CIVpiping (1.4EQ mR/hr).
Based on the above results showing increases of 48 and 41 for the two major contributors, the dose rate at point 4 is expected to be less than a factor of fifty(50) greater than that calculated in Ref. 6.1 at point A; this is a factor of 5 for HWC and a factor of 10 for location: Multiplyingthe Turbine Building skyshine dose rate at point A (9.4E-4 mR/hr) by a factor of 50 gives 0.05 mR/hr. This is less than 3% of the dose rate limitof 2 mR/hr; thus, further analysis of Turbine Building skyshine is not required for this dose point.
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EC-ENVR-1026 Rev. 0 A review of Table 3-3 shows that the direct radiation component of the Turbine Building dose rate at the 500 kV Switchyard is small compared to the skyshine component.
Simplified models were used to bound the contribution from the cross-around piping and the moisture separators at this location. Per Table 3-3, the turbines provide a small contribution with respect to the moisture separators and cross-around piping to the direct radiation; thus, they are not considered herein.
MICROSHIELD Parameters-Unit 1 CAP model per Section 3.11.2 frame of reference:
+X: from south to north
+Y: from west to east (the vertical offset is ignored) shield wall is north moisture separator wall between columns 18 and 19 (distances are obtained from Table 4-1 and attachment 2 figures):
X = -7.2'+ 54'+ 36'+ 72'+ 9" + 361' 517'15744 cm
~
~
Y,.~ = 14.75'+ 3'3'+ 62'3" 9" + 102' 183' 5578 cm (note, Attachment 2 figures do not show detail with respect to location of the CAP relative to column K; the values used are typical of the west CAP).
Y,=10.4' 10" + 21' 21' 32'+ 62'3" + 9" + 102' 250' 7627 cm T1 = 0.953 cm iron T2 = 37.3' 1137 cm T3 = 3' 91 cm The dose rates from the Unit 1 east and west CAP are 8.5E-3 and 5.8E-3 mR/hr, respectively (MICROSHIELD runs 1CAPEP4.MSH and 1CAPWP4.MSH in Attachment 7)
MICROSHIELD geometry 9, "Cylinder Source from Side-Combination Shields" (SAS) requires the dose'point to be adjacent to the side of the source while geometry 10, "Cylindrical Source from End-Slab Shields" (SAE) requires the dose point to be along the axis of the source.
Neither is directly applicable to dose point 4 with respect to the moisture separators.
SAE is used, since the dose rate along the MS axis is conservative with respect to the actual location of the dose point; SAS is not considered, because of the significant slant path in the east shield wall and floor. The dose rate along the axis of the source bounds that at displacements from the axis and
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EC-ENVR-1026 Rev. 0 will, thus, be determined.
This model is conservative, because it ignores the additional distance and shielding afforded by the slant path.
MICROSHIELD Parameters-Unit 1 Moisture Separator model per Section 3.11.1 frame of reference:
+X: from south to north shield wall north of the moisture separator between columns 18 and 19 X = 67.29' 18' 3'
6.5' 36' 72' 9" + 361' 565' 17207 cm T1 = source length = 67.29' 2051 cm T2 = iron shell = 3.18 cm T3 = air space between end of MS and shield wall =18' 549 cm (Att. 2, Fig. 3)
T4 = concrete shield = 3' 91 cm (Att. 2, Fig. 3)
The dose rate from one moisture separator is 4.5E-3 mR/hr, (MICROSHIELD run 1MSP4.MSH in Attachment 7). This is conservatively multiplied by 2 to account for both Unit 1 moisture separators.
Attributing the same dose rate to the west moisture separator is conservative, because of the shielding afforded by the turbines.
Further detail is not required at this time, because this is a small portion of the skyshine dose rate at point 4.
The total dose rate at point 4 from the Turbine Building is the sum of the following:
total skyshine dose rate
= 0.05 mR/hr Unit 1 cross around piping
= 0.014 Unit 1 Moisture Separators
= 9.0E-3 total
= 0.07 mR/hr
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EC-ENVR-1026 Max Offsite Dose Rate Rev. 0 from ISFSI 8 Other Fuel Cycle Sources 4.5 CONDENSATE STORAGE TANKS (CST)
A dose rate of 3.1E-6 mR/hr was previously determined from the skyshine component of the dose rate at the 500 kV Switchyard (point A) from the Unit 2 CST, a distance of 1200'Section 3.15). Table 4-1 shows that dose points 2 and 3 are farther than 1200'o the CST; thus, this dose rate bounds the dose rate at these dose points. This dose rate is insignificant compared to the dose rate from transport of the transfer cask past point 1 (1.2 mrem/hr per Table 4-2). As shown in Section 4.4.1, the skyshine dose rate at point 1 is expected to be a factor of three higher than point A (i.e. 9.3EW mR/hr); this difference has no impact on the total dose rate at dose point 1. The direct dose rate at point A was previously determined to be 4.2E-5 mR/hr (Section 3.15); correcting this for the closer distance at point1 also has no impact on the total dose rate at point 1. There is no direct dose contribution from the CSTs to dose points 2 and 3, because of shielding from the Turbine Buildings and Cooling Towers. Therefore,'additional analysis of the CST contribution to the dose rate at dose points 1, 2, and 3 neednot be performed.
The distance from the Unit 1 CST to dose point 4 is 430', even though it is not expected to be a significant contributor, the dose rate from the CST willbe determined, because the distance is much less than 1200'.
MICROSKYSHINE Parameters-CST model per Section 3.22 X=430'=131 m The simplified model, of the CST established in Ref. 6.1 cannot be used here, because an unshielded line-of-sight exists to'the dose point. This model does not explicitly model shielding beside the CSTs.
As shown on Fig. 4-1, the RWST is between the CST
'nd dose point 4. A review of the tank dimensions shown in Sections 3.22 and 3.23 show the RWST is larger than the CST, thus, the RWST serves as a shield to limitthe..
forward s'cattering angle from the CST and direct radiation. A shield wall willbe placed at the center of the RWST (R1, the distance between the source and shield wall, equals the distance between the centerlines of the two tanks) to take credit for the widest profile of the RWST. The minimum height of the shield wall to eliminate the line-of-sight willbe used instead of the actual height of the RWST to maximize the calculated dose rate.
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EC-ENVR-1026 Rev. 0 Dose Point 4-Ei.
716'hield Wall H
Y~
~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~
Top of CST-El. 702' Not to scale R1 = 24'+ 29' 53' 16 m (Ref. 6.4.i)
Y/ (R1 + W) = Y1/ (X + W)
Y1 = 71 6' 702' 14' 4.3 m Y = 4.3 *(16+ 6.1) /(131+ 6.1) = 0.7 m H = 0.7 - 4.3 = -3.6 m wall)
(similar triangles)
(negative H is above top of shield The RWST is 50'-32' 5.5m taller than the CST. This is larger than the value of Y determined above; thus, use of 0.7 m is conservative.
Z = horizontal offset of dose point from line normal to the shield wall. This is conservatively assumed to be zero to minimize the distance from the source to the dose point.
The dose rate from the Unit 1 CST is 1.1E-G mR/hr (MICROSKYSHINErun 1CSTP4.SKY in Attachment 6); this is insignificant with respect to the Turbine Building dose rate.
Dose point 4 is shielded from direct radiation from the Unit 1 CST by the north wall of the CST/RWST area (Ref. 6.4,i) and from the RWST (as described. above); and from the Unit 2 CST by the Reactor Buildings.
Further analysis of the CSTs for dose point 4 is not required at this time.
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EC-ENVR-1026 IYlax Offsite Dose Rate Rev. 0 from ISFSI 8 Other Fuel Cycle Sources 4.6 LLRWHF Dose rates of 2.1E-4 mR/hr and 0.017 mR/hr have previously been determined for the 500 kV Switchyard and points along the security fence due south of the LLRWHF, respectively (Section 3.16 and Table 3-6). These values bound the dose rate at dose points 1 and 2 from the LLRWHF, because the present dose points are located farther from the LLRWHFthan those previously analyzed.
These dose rates are not significant compared to those determined from the transfer cask and ISFSI, 1.2 and 0.4 mR/hr, respectively (Table 4-2).
Dose point 3 is located north of the LLRWHF. Although the reference calculations do not explicitly address dose rates in this direction, the dose rates determined south of the facility bound those expected north of the facility, because of the greater distance from the stored waste to the outside walls, an internal 18" thick concrete wall between the storage area and the truck bay on the north end of the facility, and the symmetry of the assumed loading of waste in the facility(Ref. 6.14, Sections 4.2.5 and 4.2.8).
Dose point 3 is 550'rom the northeast corner of the LLRWHF. The dose point at the security fence south of the facility is 135'rom the wall. Thus, the dose rate at the south security fence bounds that at dose point 3. Although the bounding LLRWHF dose rate of 0.017 mR/hr is significant with respect to the other dose rates determined for point 3, the total is well below the acceptance criterion of 2 mrem/hr; thus, additional analysis is not required at this time.
As shown on Table 4-1, dose point 4 is approximately 1730'rom the LLRWHF; this is greater than the distance from the LLRWHFto the 500 kV Switchyard (945'er Section 3.16).'hus, the dose rate calculated for the 500 kV Switchyard (2.1E-4 mR/hr) bounds that at dose point 4.
0
-PPSL CALCULATIONSHEET PL ate 10/2/96 Designed By Checked By PROJECT:
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EC-ENVR-1026 Rev. 0 4.7 TEMPORARY LAUNDRYFACILITY
~r Skyshine dose rates at the EOF/Towers Club from the Temporary Laundry Facility and Turbine Building are provided in Sections 3.17 and 3.18; the contribution from the Turbine Building clearly bounds that of the Temporary Laundry Facility at this location.
It is expected that the contribution from the Turbine Building would bound that of the-Temporary Laundry Facility at the dose points considered herein, because the distance from the sources to the dose points is comparable.
As discussed in Section 4.4, the contribution from the Turbine Building is not significant at any of these dose points; thus, additional skyshine analysis of the Temporary Laundry Facility is not required.
The Temporary Laundry Facility is located southwest of the Unit 2 Turbine Building, Dose points 2, 3, and 4 are shielded by the Unit 2 cooling tower and the Turbine Buildings; the only dose point that is not shielded from direct radiation from the facility is dose point 1. As noted in Section 3.17, the maximum exposure rate for a receiver at the-one foot perimeter of the laundry facilityhas been estimated to be 7.94 mR/hr (Ref.
6.15); this would decrease by several orders of magnitude over the nominal 800'etween the facility and dose point 1. Ref. 6.15 stated that this value exceeds that at which the area outside the facilitywould be posted as a RADIATIONAREA; the actual inventory would be limited and shielding would be provided to meet Radiation Protection requirements.
Therefore, additional analysis of the dose rate contribution from
, Temporary Laundry Facility at this dose point is not required at this time.
':3
lept.
J ate 10/2/96 Designed By Checked By PP8L CALCULATIONSHEET of PROJECT:
SSES Calc. No.
EC-ENVR-1 026 Max Offsite Dose Rate Rev. 0 from ISFSI 8 Other Fuel Cycle Sources Sh. No.
4.8 DAWVOLUMEREDUCTION SYSTEM The DAWVolume Reduction Trailer is located adjacent to the Radwaste Building. The inventory is limited to 30 mCi by the safety evaluation prepared to support its operation (Section 3.19). This is less than 4% of the inventory in the Temporary Laundry Facility (Section 3.17). Thus, the dose rate at dose points 1, 2, and 3 are bounded by the laundry facility. It was shown in Section 4.7 that the dose rate at these points from the laundry facility is negligible. Therefore, further analysis of the DAWfacilityat these points is not required.
The distance between the DAWfacility and dose point 4 is over 200'scaled from Fig.
4-1). The inventory limitof 30 mCi is based on 150 bags each containing 200 pCi of Co%0 with contact dose rate of 2 mR/hr (Section 3.19). A dose rate of 2.143 mR/hr was calculated using the current version of MICROSHIELD (run DAW1.MSH in Attachment 7); this compares favorably with the value of 2.099 mR/hr calculated in the safety evaluation (Attachment 8). The safety evaluation modeled one bag as a cylindrical source 76.2 crn high with a radius of 38.1 cm (Section 3.19).
Instead of modeling 150 cylindrical sources, a slab source is used.
The slab is modeled as a cube with the same volume as the cylinder:
volume of cylinder = n(38.1)
~ 76.2 = 347,500 cm'ide of cube
= (347,500)"'m = 70.3 cm A dose rate of 2.5 mR/hr was calculated using this model (run DAW2.MSH in );"The contact dose rate on the slab is larger than that of the cylinder, therefore, this model is conservative.
Two geometries of 150 bags are considered, a
10x1 Gx1 array which maximizes the face toward the dose point and a Gx5x6 array to make the source more compact.
10x1 Gx1 array W
= source width = 15 *70.3 cm = 1054.5 cm L
= source length = 10 *70.3 cm = 703 cm T1
= source thickness = 70.3 cm X
= distance from back face of source to dose point
= 200' 30.48 cm/ft + 70.3 cm = 6166 cm = 5170 cm
PP8L CALCULATIONSHEET 0 pt.
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, Sh. No.
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EC-ENVR-1026 Rev. 0 5x5x6 array W
= source length = 6 *70.3 cm = 421.8 cm L
= source width = 5 *70.3 cm = 351.5 cm T1
= source thickness = 5 *70.3 cm = 351.5 cm X
= distance from back face of source to dose point
= 200'0.48 cm/ft+ 351.5 cm = 6448 cm = 6450 cm The dose rate 200 feet from the slab for these two geometries is.011 and.010 mR/hr (runs DAW3.MSH and DAW4.MSH in Attachment 7). Although a much smaller inventory is expected in the facility, a dose rate of 0.01 mR/hr is used at dose point 4 from this source (Section 3.19).
PP8L CAI CULATIONSHEET Pt ate 10/2/96 Designed By Checked By PROJECT:
SSES M~ Offsite Dose Rate from ISFSI & Other Fuel
,Cycle Sources Gale. No.
EC-ENVR-1026 Rev. 0 Sh. No.
~
of Table 4-1 Distances from Sources to Dose Points Source Point ISFSI (1)
U1 CST U2 CST U1/U2 TB Outer Wall LLRWHF Outer Wall Dose Point II 3
Direct Distance feet 1450 2 1190 450 1563 1410 1710 1900 430 1090 1550 2000 N/A N/A N/A N/A 1280 570 550 4 1732 4 East-West Distance feet N/A N/A
'/A N/A N/A N/A N/A N/A N/A N/A N/A 300 1140 1725 102 1020 190 410 N/A North-South Distance feet N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 830 610 580 3 361 780 550 360 N/A Notes:
2.
3.
4 Measured from the center of the ISFSI.
This represents the minimum distance from the ISFSI to the south fence; the distance from the ISFSI to the location of dose point 1 shown on Fig. 4-1 is 1700'.
Measured from the southwest corner of the Turbine Building.
Measured from the northeast corner of the LLRWHF.
ate 10/2/96 Designed By Checked By PP8 L CALCULATIONSHEET PROJECT:
SSES of Gale. No.
EC-ENVR-1026 Max Offsite Dose'ate Rev. 0 from ISFSI 8 Other Fuel Cycle Sources Sh. No.
Table 4-2 Dose Rates at the Specified Dose Points (1)
Source Dose Point 1 mrem/hr Dose Point 2 mrem/hr Dose Point 3 mrem/hr Dose Point 4 mrem/hr Trans ort of Transfer Cask ISFSI base case theoretical limitin case 1.2 6.0E-4 1.0E-3 0.4 2.E-3 4.E-3 3.6E-3 2
2.03E-2 3.42E-2 1.E-4 5.E-4 9.E-4 Subtotal Turbine Buildin CSTs LLRWHF Tem ora Laund Facilit DAWFacilit 1.2 0.01 5.1E-5 2.1E-4 0.4 2.4E-3 3.1E4 0.017 0.024/0.038 3
1.8E-3 3.1EW 0.017 6.EQ/1.E>>3 3
0.07 1.1E 2.1E-4 0.01 Subtotal 0.01 0.020 0.019 0.08 Total 1.2 0.42 0.043/.057 3
0.08 Notes:
1.
In some cases, the values shown were not calculated for the specified dose point but shown to bound the dose rate expected at that location; in other cases scaling factors were developed to determine the v'alues shown (see Sections 4.4 through 4.7). Careful review of all of the results is required before they may be applied to other uses.
- 2. The dose rate for Dose Point 3 is conservatively based on a distance of 300'rom Table 3-1 instead of interpolation of the data.
3.
Base case/ theoretical limiting case dose rates, respectively, from ISFSI.
4.
Dose rates were not determined for the Temporary Laundry Facility. It was shown in Section 4.7 that these dose rates are negligible.
- 5. As discussed in Section 4.7, the inventory willbe limited and shielding provided to meet Radiation Protection requirements.
6.
Dose rates were not determined for the DAW Facility. It was shown in Section 4.8 that these dose rates are negligible.
PP8 L CALCULATIONSHEET
'lept.
ate 10/2/96 Designed By Checked By PROJECT:
SSEII Max Offsite Dose Rate
~
from ISFSI & Other Fuel Cycle Sources Sh. No.
of Calc. No.
EC-ENVR-1026 Rev. 0 Figure 4-1 Dose Point Locations IAd+thdoldNl Sport Fuel Sots e lfNNSh
)
M,
$4Rf" J
/
~AC (h8nes ~~
o pZPINHS FcHct
~~ 8C I
4
(
0
.)(
~
~
2
+ BM RQSLC'f weHs ALl'TY I
I t
uuvuCN~ C Note, points 1 through 4 represent location of dose points calculated herein, Points A and B represent location of dose points calculated in Ref. 6.1; they are shown here for reference,
>ept.
ate 10/2/96 Designed By Checked By PP8L CALCULATIONSHEET Sh. No.
~
of PROJECT:
SSES Calc. No.
EC-ENVR-1026 Max Offsite Dose Rate Rev. 0 from ISFSI 8 Other Fuel Cycle Sources Figure 4-2 Total Dose Rate (n+ y) from NUHOMS Transfer Cask During Transport as a Function of Distance (1) 10 E
Ql E
1
'- 0D 0.1 40 50 60 Distance(feet) 3 100 Notes:
- 1. Data from Table 3-1.
PP8L CALCULATIONSHEET
~
~
ept
~10/
M" Designed By Checked By PROJECT:
SSES Max Offsite Dose Rate from ISFSI 8 Other Fuel Cycle Sources Gale. No.
Sh, No.
C-ENVR-1 026 Rev. 0 of Figure 4-3 Total Dose Rate (n+ y) from ISFSI as a Function of Distance (1) 0.1 4l E
0.01 0.001 A
0.0001 0
200 400
~ LimitingCase 6fBase Case 600 800 1000 1200 1400 1600 Distance (feet)
Notes:
- 1. Data from Table 3-2.
lept.
~1a Designed By.
Checked By PP&L CALCULATIONSHEET Sh. No,
~
of PROJECT:
SSES Gale. No.
EC-ENVR-1026 Max Offsite Dose Rate Rev. 0 from ISFSI 8 Other Fuel
,Cycle Sources 5.0 RESULTS A summary of the contributions to the total dose rate at each of the specified dose points determined in Section 4 is provided in Table 4-2. The maximum dose rate in an unrestricted area is 1.2 mrem/hr along the south security fence, the point of closest approach of the transport trailer during transport to the ISFSI ~ Almost all of this dose rate is attributed to transport of spent fuel in the transfer cask to the ISFSI; all other sources, including consideration of HWC, contribute less than 1/o of this dose rate, The maximum dose rate in an unrestricted area from transport of a loaded NUHOMS transfer cask to the ISFSI is 1.2 mrem/hr; this occurs along the south fence. The maximum dose rate in an unrestricted area from storage of the casks at the ISFSI is.
0.02 mrem/hr; this occurs at the construction fence due west of the ISFSI.
The maximum dose rate in an unrestricted area from the Turbine Building including the effects of hydrogen water chemistry is 0.08 mR/hr.
6.0 REFERENCES
6.1 PP&L Calculation EC-HPHY-0518, "Dose Rates to Various Locations within the SSES Controlled Area: Fixed Plant Sources," Rev. 0, Issued 9/29/93.
II 6.2 10CFR $20.1301, Dose limits for individual members of the public.
6.3 Letter from J. L. Simpson, GE Nuclear Energy, to J. C, Pacer, PP8L, "Review of the Susquehanna Steam Electric Station Assessment of Impact of Hydrogen Water, Chemistry on Radiation Field Buildup,'1/7/95 (Attachment 1).
6.4 PP&L Dr'awings a,
E-105151, Rev. 17, "Plant Location Site Plan'C-1) (including IDCNs 7 and 8).
b.
E-105943-1, Rev. 14, "Finish Grades 8 Area Paving North Laydown Area'C-1401)
(including IDCN 4 and PCNs 96-0279 and 96-0390),
c.
E-105943-1, Rev. 14, IDCN 5.
d.
E-105943-3, Rev. 7, "Finish Grade &Area Paving West of Tower 2'C-1403)
(including IDCN 4).
e.
E-105943-4, Rev. 2, "Finish Grade &Area Paving South West of Tower 2" (C-1404)
(inclu'ding IDCN 1).
f.
E-105943-5, Rev. 6, "Finish Grades 8 Area Paving South of Tower 2" (C-1405).
PP&L CALCULATIONSHEET
't
- J t
~10/
Qs Designed By Checked By OJECT PR:
SSES Max Offsite Dose Rate from ISFSI & Other Fuel Cycle Sources Sh. No.
of Calc. No.
EC-ENVR-1026 Rev. 0 6.5 6.6 6.7 6.8 6.9 g.
E-105004-0, Rev. 10, "General Arrangement Fence and Patrol Road'A-5).
h.
E-105811, Rev. 10, "Finish Grades &Area Paving West Parking Area" (C-1030)
(including IDCN 4),
E-105789, Rev. 8, ""Refueling and Unit C1 Condensate Tanks-Plan'C-1008).
PP&L User's Manual Documentation UM-CDA-004for MICROSKYSHINEVersion 1.16, approved 9/30/91.
PP&L PCC-CDA-004 Production Computer Code 004 for MICROSKYSHINEVersion 1.16, approved 9/30/91.
PP&L User's Manual Documentation UM-CDA-002for MICROSHIELDVersion 3.12, approved 8/30/91.
PP&L PCC-CDA-002 Production Computer Code for MICROSHIELDVersion 3.12, approved 8/30/91.
Memo from Robert K. Barclay to Kevin J. Kelenski, "Susquehanna Steam Electric Station Assumptions Regarding Movement of Spent Fuel to ISFSI," PLI-82098, 6/11/96 (Attachment 3),
6.10 PP&L Calculation EC-ENVR-1024, "Susquehanna NUHOMS Site Dose Calculation'"
Rev. 0, accepted 11/1/95.
Letter from Norman Eng, VECTRATechnologies, to Kevin Kelenski, PP&L, "Total Dose Rate Contributed by Cask During Transfer to the Susquehanna ISFSI Site," 8/16/95 (Attachment 4).
6.12 Letter from Norman Eng, VECTRATechnologies, to Kevin Kelenski, PP&L, "Total Dose Rate Contributed by NUHOMS Transfer Cask During Transfer to the Susquehanna ISFSI Site, Vectra Letter Number 16-77-96-052 dated 5/21/96 (Attachment 5).
6.13 PP&L Calculation EC-RADN-0524, "LLRWHF-Calculation of Direct and Skyshine Dose Rates," Rev. 0, approved 12/27/94.
6.14 6.15 PP&L Calculation EC-RADNZ523, "Annual Dose and Exposure Rates to Walls for Operations at LLRWHF,'ev. 0, approved 12/27/94.
PP &LCalculation EC-RADN-1022, "Laundry Facility C. R. 96-01 56 Dose Calculations,'ev.
0, approved 4/3/96.
'l Gate 10/2/96 Designed By Checked By PP8L CALCULATIONSHEET Sh. No.
~
of
. PROJECT:
SSES Gale. No.
EC-ENVR-1026 Max Offsite Dose Rate Rev. 0 from ISFSI 8 Other Fuel Cycle Sources.
6.16 PP8L Calculation EC-ENVR-1025, "ISFSI Fuel Cycle 40CFR190 Offsite Dose Calculations,'ev.
0, approved 10/2/96.
6.17 PP8L Safety Evaluation NL-89-002, "DryActive Waste Volume Reduction System Safety Analysis," prepared by R. A. Stigers, PORC approved 2/17/89, meeting 89-027.
6.18 SSES Licensing Topical Report for Power Uprate With Increased Core Flow, NE-092-001a, Rev. 0, 6/92 6.19 SSES FSAR Table 12,2-29, "Condensate Storage Tank Source Terms."
6.20 Lederer, C. M. and Shirley, V. S., et al., "Table of Isotopes," Seventh Edition, 1978.:
6.21 Design Description Manual, chapter 40b, Design Description for Condensate and Refueling Water Storage System."
g 4'
ept.
J ate 10/2/96 Designed By Checked By PP&L CALCULATIONSHEET
~4 of PROJECT:
SSES Gale. No.
EC-ENVR-1026 Max Offsite Dose Rate Rev. 0 from ISFSI & Other Fuel Cycle Sources Sh. No.
6.5 6.6 6.7 g.
h.
E-105004-0, Rev. 10, "General Arrangement Fence and Patrol Road" (A-5).
E-105811, Rev. 10, "Finish Grades &Area Paving West Parking Area" (C-1030)
(including IDCN 4).
E-1 05789, Rev, 8, ""Refueling and Unit ¹1 Condensate Tanks-Plan" (C-1 008).
PP&L User's Manual Documentation UM-CDA-004for MICROSKYSHINEVersion 1.16, approved 9/30/91
~
PP&L PCC-CDA-004 Production Computer Code 004 for MICROSKYSHINEVersion 1.16, approved 9/30/91.
PP&L User's Manual Documentation UM-CDA-002 for MICROSHIELDVersion 3.12, approved 8/30/91.
6.8 6.9
.'.10 6.11 6.12 PP&L PCC-CDA-002 Production Computer Code for MICROSHIELDVersion 3.12, approved 8/30/91.
Memo from Robert K. Barclay to Kevin J. Kelenski, "Susquehanna Steam Electric Station Assumptions Regarding Movement of Spent Fuel to ISFSI," PLI-82098, 6/11/96 (Attachment 3).
PP&L Calculation EC-ENVR-1024, "Susquehanna NUHOMS Site Dose Calculation'"
Rev. 0, accepted 11/1/95.
Letter from Norman Eng, VECTRATechnologies, to Kevin Kelenski, PP&L, "Total Dose Rate Contributed by Cask During Transfer to the Susquehanna ISFSI Site," 8/16/95 (Attachment 4).
Letter from Norman Eng, VECTRATechnologies, to Kevin Kelenski, PP&L, "Total Dose Rate Contributed by NUHOMS Transfer Cask During Transfer to the Susquehanna ISFSI Site," Vectra Letter Number 16-77-96-052 dated 5/21/96 (Attachment 5).
6.13 PP&L Calculation EC-RADN-0524, "LLRWHF-Calculation of Direct and Skyshine Dose Rates," Rev. 0, approved 12/27/94.
6.14 6.15 PP&L Calculation EC-RADN-0523, "Annual Dose and Exposure Rates to Walls for Operations at LLRWHF," Rev. 0, approved 12/27/94.
PP&L Calculation EC-RADN-1022, "Laundry Facility C. R. 96-0156 Dose Calculations," Rev. 0, approved 4/3/96.
PPB L CALCULATIONSHEET pL Bate 10/2/96 Designed By Checked By PROJECT:
SSES'.
Max Offsite Dose Rate from ISFSI 8 Other Fuel Cycle Sources Calc. No.
EC-ENVR-1026 Rev. 0 Sh. No.
~
of 6.16 PP8L Calculation EC-ENVR-1025, "ISFSI Fuel Cycle 40CFR190 Offsite Dose Calculations," Rev. 0, approved 10/2/96.
6.17 PP8L Safety Evaluation NL-89-002, "DryActive Waste Volume Reduction System Safety Analysis," prepared by R. A. Stigers, PORC approved 2/17/89, meeting 89-027.
6.18 SSES Licensing Topical Report for Power Uprate With Increased Core Flow, NE-092-001a, Rev. 0, 6/92 6.19 SSES FSAR Table 12.2-29, "Condensate Storage Tank Source Terms."-
6.20 Lederer, C. M. and Shirley, V. S., et al., "Table of Isotopes," Seventh Edition, 1978.
6.21 Design Description Manual, chapter 40b, "Design Description for Condensate and Refueling Water Storage System."
DO NOTWRITE ANYTHINGABOVE THIS LINE CALCULATIONSEPARATOR DOCUMENTNO. SC'-&&Vie /d~
(20 characters)
SFGTlON (1 0 characters)
DO NOT DUPLICATF SEE NUCLEARRECORDS FOR ADDITIONALFORMS.
PP8L CALCULATIONSHEET pl~
ate 10/2/96 esigned By Checked By PROJECT SSES Max Offsite Dose Rate from ISFSI 8 Other Fuel Cycle Sources Attachment 1
Gale. No.
EC-ENVR-1026 Rev. 0 Sh. No.
~
of Attachment 1
Letter from J. L. Simpson, GE Nuclear Energy, to J. C. Pacer, PP8L, "Review of the Susquehanna Steam Electric Station Assessment of Impact of Hydrogen Water Chemistry on Radiation Field Buildup", 11/7/95 (Ref, 6.3)
GE Nuclear Energy General Eleetno Campany l75 Conner Avenue, San Jose. CA 95125 Mr. John C. Pacer Pennsylvania Power and Light Co.
2 N 9th Street A2-3 Allentown PA 18101 November 7, 1995
SUBJECT:
Review ofthe Susquehanna Steam Electric Station Assessment ofImpact nfHydrogen Water Chemistry on Radiation Field Buildup'ear Mr. Pacer:
BillMarble and Iboth reviewed the two documents supplied by the Pennsylvania Power and Light Co.. These documents were 1, SUSQUENHANNA STEAMELECTRIC STATION, ASSESSMENT OF IMPACTOF HYDROGEN WATERCHEMISTRYON RADIATIONFIELDBUILDUP,JOHN C. PACER, OPERATION TECHNOLOGY, JUNE 1995 and 2, HWC Evaluation for SSES, Radiation Effects, D. J.,Morgan, 9/22/95.
I called in early October, Ibelieve October 13th, and had the opportunity to discuss with you our review. This letter report details our review ofthe referenced documents.
GE Nuclear Energy recommends to the BWR fleet the implementation ofHydrogen Water Chemistry (HWC) at the moderate injection rate. The moderate injection rate is defined as that amount ofhydrogen to achieve a final 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 < 0.23 V(SHE) in the bottom plenum, core plate and below. In high power. density plants the recirculation piping system environment will also achieve this chemistry condition. An ECP of<0.23 V (SHE) is recognized as a chemistry condition that wiH immune metal components &om Intergrannular Stress Corrosion Cracking (IGSCC) initiation and ifcracks are present the crack growth rate will be reduced to approximately 5 mil/yr.
Two subsequent side effects ofimplementation ofmoderate HWC are 1, increased Main Steam Line Radiation (MSLR) levels to approximately 5 times normal 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 very plant specific. This was address in your CALL IKh EC-ENVR-I 02.4 am e).: 0 PAGE NO.: I-z QF
evaluation and considered manageable.
The,dry well dose rates are e6ected by the transport ofradionuclides Rom the fuel surfaces to the pipe walls resulting Rom the change in vessel chemistry to a more reducing condition.
Areview ofthe GE Chemistry Data Base shows the followingfor the Susquehanna Plants:
Feedwa erIr n ncentra i n Unit¹1 10 ppb Unit ¹2 - 6 ppb, last cycle through March - 2 ppb ReactorWaerl i
nc nt ai n h
lan Fe 4 times fleet average Mn-54, - 4 times fleet average (both Fe-59 and Mn-54 were lower in Unit¹2 when the source term was reduced)
Co-60i' 1/5 ofthe fleet average (this is consistent with other high iron plants, most likelya result ofthe Fe, Co spinel formed on the fuel. Co-60 could increase with a long term decrease in feedwater iron)
]+/ - normal to low compared to the fleet average "GE Nuclear Energy is for the most part in agreement with the summary evaluation ofthe effects that the Susquehanna Plant wiH experience with the implementation ofHWC with minor exceptions.
- l. Upon initiation ofHWC under the current chemistry conditions we feel that the dty well (piping) dose rates wiH increase closer to the factor of seven rather than the lower factor ofthree suggested in the report. The high crud loading resulting &om 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 wiH be small, possibly in the coHoidal range.
These small particles can easily incorporate into the oxide Glm. Brunswick, with a history'fhigh iron input, had a similar occurrence because ofthe high crud inventory in the vessel.
AtBrunswick, during a mid cycle outage, crud was visually detected in the bottom ofthe annulus. Itwas planned to vacuum this observed crud during the next full refueling outage, during the subsequent outage this crud in the bottom annulus was not found.
Fast SFooOo 2FooOo + l/2 Oo Slow
'I
- 2. Long term mitigation techniques for shutdown dose rate control should include both feedwater iron reduction and introduction ofdepleted zinc oxide (DZO). Ifnatural zinc
-was injected into the plants prior to HWC implementation one would expect an approximate 5% reduction in the overall dry well dose rates, the downside is the higher Zn-65 concentration.
The plants could benefit by injecting DZO, however, with the high feedwater iron concentrations this is most likelynot cost effective. Ifthe feedwater iron is'educed, GE would recommend that zinc injection be initiated six months before HWC to incorporate zinc into the crud.
Cobalt is held much more tenaciously in the fuel crud with
, the presence ofzinc.
1
- 3. With the implementation ofmoderate HWC a decontamination should be planned for after the first fuel cycle. This decontamination should be planned with'rwithout the implementation ofDZO injection. There is a 50/50 chance that a second decontamination willbe required, a contingency plari for a second decontamination after the second fuel cycle should be considered.
Decontamination should not be required during future fuel outages.
4.
The feedwater iron reduction is a necessity. Ifthe feedwater iron is reduced to 1-2 ppb, a test program to demonstrate the effectiveness ofDZO could be run. Our data base indicated that the cobalt concentrations in the reactor water should drop 2-3 times with in a three month period after the addition ofDZO. There are currently eighteen BWR's on zinc injection with twelve on DZO. Ofthe six plants currently on zinc but not DZO, four are strongly considering DZO. Several other plants are in the evaluation stage ofzinc injection.
- 5. Decontamination's willbe required after HWC implementation, The experience at Brunswick with Citrox was not acceptable, very lowDF's were obtained.
Subsequently, Vectra (currently PN Services - Westinghouse) performed a series ofdecon tests with artifacts from both Brunswick ¹I and ¹2, these tests indicate that Citrox or Citrox-AP-Citrox is not as effective as other decontamination solutions.
This should be discussed
, with the decon vendor. The Brunswick films were successfully decontaminated using a Lomi-AP-Lomiprocess.
Fitzpatrick films were also successfully removed with the Lomi-AP-Lomiwith a DF ofapproximately 12. The films &om both plants had even better DF's using Lomi-NP-Lomi. Hatch Unit ¹1 is planning to decontaminated several piping systems during their Spring 96 outage using Lomi-NP-Lomi. PN Services have recommended to Hatch the use ofthe Lomi-NP-Lomibased on the experience at the Brunswick Plant..
- 6. 'Hydrogen cycling has been shown to have a pronounced e6ect ofthe dry well dose rates. Laboratory studies as weH as, plant experiences have shown that resulting dose rates can be 25-40 % higher with sequent cycling compared to steady state HWC.
CaC. aO
.".C..-n
. /<<,
REV. NO.:g PAGE NO.. I-y
- 7. MSLR levels willincrease approximately Gve time normal with the implementation of moderate HWC.
These increases have or w'illhave varying degrees ofimpact on plants.
At several plants,'.e. Quad Cities, Dresden, Hatch, the impact has been minimal and have not required any plant modiGcations.
Other plants have managed the impacts with administrative control, i.e. Monticello while other domestic plants have installed minimal shielding at speci6c locations on the turbine deck.
Those plants that have are sensitive to the increases or plants are located very close to general population and have small owner controller acreage, i.e. Vermont Yankee, certain European Plants. In your evaluation the environmental dose rate increases were addressed and it was concluded that the increases were manageable.
Other than the above, we agree with the evaluation and conclusions that were stated in the reports. Any further questions feel &ee to call me at (408) 925-1106.
Sincerely,
- ames, im n
Principle Chemist GE Nuclear Energy cc:
BillMarble Marcus Urioste Tom Hurst CALL NO f6&
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