ML052140075
| ML052140075 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 10/30/2003 |
| From: | Donnachie P FirstEnergy Corp |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| E900-03-016, Rev 1 | |
| Download: ML052140075 (27) | |
Text
Appendix C SCM Survey Design Revision 1
SNEC CALCULATION COVER SHEET CALCULATION DESCRIPTION Calculation Number Revision Number Effective Date Page Number E900-03-016 1 10/30/03 1 of 9 Subject Shonka Discharge and Intake Tunnels FSS Survey Design Question I - Is this calculation defined as 'in QA Scope'? Refer to definition 3.5. Yes 0 No a Question 2-Is this calculation defined as a Design Calculation? Refer to definitions 3.2 and 3.3. Yes 0 No Ea Question 3 - Does the calculation have the potential to affect an SSC as described in the USAR? Yes Il No 0D NOTES: If a 'Yes answer Is obtained for Question 1, the calculation must meet the requirements of the SNEC Facility Decommissioning Quality Assurance Plan. If a 'Yes answer Is obtained for Question 2, the Calculation Originators immediate supervisor should not review the calculation as the Technical Reviewer. If a YES' answer is obtained for Question 3. SNEC Management approval Is required to implement the calculation. Calculations that do not have the potential to affect SSCs may be implemented by the TR.
DESCRIPTION OF REVISION
- 1. Section 2.1.1 - Increased the numberof Class 1 survey units from three (3) to four (4).
- 2. Section 2.1.1 - Reclassified survey unit SS4, Discharge Tunnel ceiling first 150 ft, from a Class 2 to Class 1.
' APPROVAL SIGNATURES I
I I
SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 1 Page 2 of____
Subject Shonka Discharge and Intake Tunnels FSS Survey Design 1.0 PURPOSE 1.1 The purpose of this calculation is to provide the survey design guidance to be followed for conducting final status surveys (FSS) in the SSGS Discharge and Intake Tunnels. The Intake Tunnel consists of multiple parts: the Main Intake Tunnel and both the North and South Intake tunnels, which split off from the Main Tunnel. These latter tunnels are located under the SSGS footprint.
1.2 Shonka Research Associates (SRA) will conduct scan surveys using procedures reviewed and approved by SNEC. These procedures are attached as Appendices.
2.0
SUMMARY
OF RESULTS 2.1 The following information will be used to conduct the applicable FSS for this survey design:
2.1.1 The Discharge Tunnel area is divided into nine (9)survey units, i.e. four (4)Class 1, one (1)Class 2 and four (4)Class 3 survey units.
2.1.2 The Discharge Tunnel Survey Unit (SU) Numbers are as follows:
SU Number Area Description Classification Area (m2)
SS1 Floor (first 150 ft) 1 120 SS2 Floor (next 235 ft) 2 175 SS3 Floor (last 315 ft) 3 234 SS4 Ceiling (first 150 ft) 1 120 I
SS5 Ceiling (last 550 ft) 3 400 SS6-1 South Wall (first 150 ft) 1 145 (Includes % of east wall @ beginning of tunnel)
SS6-2 North Wall (first 150 ft) 1 145 (Includes % of east wall @ beginning of tunnel)
SS7-1 West Wall (last 550 ft) 3 300 SS7-2 East Wall (last 550 ft) 3 300 Note: Area and linear dimensions are approximations.
2.1.3 The Intake Tunnel consists of three parts: Main Intake Tunnel, South Intake under SSGS footprint and the North Intake under the SSGS footprint. These areas are further subdivided into six (6)Class 2 and three (3) Class 3 survey units.
SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-O16 Page 3 of_9_
Subject Shonka Discharge and Intake Tunnels FSS Survey Design 2.1.4 The Survey Unit Numbers for these tunnels are as follows:
SU Number Area Description Classification Area (mi)
SS19-1 Main Intake Tunnel floor 2 167 SS19-2 North Tunnel Floor 2 184 SS19-3 South Tunnel Floor 2 154 SS20-1 Main Intake Walls 2 269 SS20-2 North Tunnel Walls 2 324 SS20-3 South Tunnel Walls 2 359 SS21-1 Main Intake Ceiling 3 162 SS21-2 North Tunnel Ceiling 3 184 SS21-3 South Tunnel Ceiling 3 154 2.1.5 The number of static measurement points will be developed, as applicable, after SRA completes their survey and results are reviewed by the FSS group.
2.1.6 The minimum scan coverage for Class 1 areas will be 100%, Class 2 areas, 50%
and for Class 3 areas, 10-50%.
2.1.7 Scan speed will be set in accordance with SRA procedures and the SNEC MDCsc 2n value calculated for structure surfaces.
2.1.8 The surface DCGLw for this design is determined to be 6174 dpml100 cm2 based on the attached spreadsheet calculation (Attachment 3). This value is the 75%
administrative limit of the calculated surrogate Cs-137 value (8233 dpm/100 cm2).
2.1.9 The surface area DCGLemc will use the Cs-137 surface area factor for a 1-M2 area equal to 11. This value is calculated to be 67,914 dpm1O00 cm2 .
2.1.10 The MDCSCI value for this design that SRA must achieve is 3087 dpm/100 cm 2 .
2.1.11 The volumetric DCGLw for this design is determined to be 4.78 pCilg based on the attached spreadsheet calculation (Attachment 9). This value represents the 75% administrative limit of the calculated surrogate Cs-137 value (6.38 pCi/g).
2.1.12 Areas greater than the DCGLW must be identified, documented, marked, and bounded to include an area estimate.
2.1.13 Class 1 areas with surface deformations that cannot be surveyed by Shonka will be identified by marking or painting around the suspect area's perimeter.
2.1.14 Remediation is indicated when any area exceeds 3 x the DCGL, for any scan measurement or when the value for any area of -1 square meter is greater than the DCGLoc. Note: If additional remediation is performed the survey unit design is void.
SNEC CALCULATION SHEET -
Calculation Number Revision Number Page Number E900-03-016 I1 Page 4 of 9-Subject Shonka Discharge and Intake Tunnels FSS Survey Design 2.1.15 Gas flow proportional counter (GFPC) will be used lAW SRA procedures.
3.0 REFERENCES
3.1 SNEC Facility License Termination Plan.
3.2 Procedure E900-IMP-4500.59, "Final Site Survey Planning and DQA".
3.3 SNEC procedure E900-IMP-4520.04, "Survey Methodology to Support SNEC License Termination".
3.4 SNEC procedure E900-IMP-4520.06, "Survey Unit Inspection in Support of FSS Design".
3.5 NUREG-1575, "Multi-Agency Radiation Survey and Site Investigation Manual', August 2000.
3.6 SRA Procedures - See Appendix Section 6.0.
3.7 SNEC Calculation E900-03-012, "Effective DCGL Worksheet Verification."
4.0 ASSUMPTIONS AND BASIC DATA 4.1 SRA procedures to be used to perform scan surveys.
4.2 SNEC LTP section 2.2.4.1.4 and Figure 2-18 provide a description of the SSGS Discharge Tunnel.
4.3 SNEC LTP section 2.2.4.1.7 and Figures 2-26 and 2-28 provide a description of the Main Intake Tunnels.
4.4 Remediation History The Discharge Tunnel was contaminated as a result of radioactive liquid effluent discharges from the SNEC Facility. Ground water and several inches of silt on the floor of this below grade structure have been removed to adequately survey this area for characterization and final release. Several piping sections have been removed as they were near or above initial DCGLs values. In addition the north wall opposite Seal Chamber
During operation of the SSGS, water was drawn from the Raystown Branch of the Juniata River. A dam was utilized to impound the river in the area of the intake structure, which included the Intake tunnel. The intake water system only provided intake of river water to the SSGS and no discharges to the river were made via this pathway. During freezing weather, warm water from the SSGS Discharge Tunnel was diverted and allowed to flow into the SSGS Intake Tunnel via a pathway that utilized the Spray Pond supply piping.
This configuration was established in order to prevent ice formation on the intake tunnel screen wash and filtration system components. This flow path, by use of discharge tunnel water, would have provided a mechanism for low-level radioactivity to enter the SSGS intake tunnel. In the SNEC LTP, Figures 2-25 and 2-28 show the SSGS Intake Tunnel in detail.
SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 - 1 Page 5 of 9 Subject Shonka Discharge and Intake Tunnels FSS Survey Design Sediment and concrete core sampling was performed in the Intake Tunnel. Results of these samples are documented in the SNEC LTP. In summary a total of 174 sediment samples were taken throughout the Intake Tunnel. Of these, 142 samples showed only Cs-1 37 above MDC. The average Cs-1 37 value was 0.46 pCVg and the highest, 1.8 pCilg.
Concrete core bores were obtained throughout the tunnel, analyzed and found to be
<MDC.
4.5 This survey determines the effective DCGLW value for Cs-137 using the spreadsheet mix in Attachment 2. A 25% reduction to the effective DCGLW was performed to address de-listed radionuclides. The SNEC facility has instituted an administrative limit of 75% for the allowable dose for all measurement results. The de-listed radionuclide dose is accounted for within the 75% administrative limit. The 75% administrative limit is then applied to the calculated Cs-137 limit, e.g. 0.75 x 8,233 dpm/100 cm2 = 6174 dpm/100 cm2 .
4.6 The MDCSn calculation is determined based on LTP section 5.5.2.5. The calculation consists of the following: 8,233 dpm/100 cm2 x 0.75 x 0.5 = 3,087 dpm/100 cm2.
4.7 Special measurements including gamma-ray spectroscopy are not included in this survey design.
4.8 Static and other survey measurements may be conducted as applicable after review of the SRA survey is completed. This design will be revised to incorporate these surveys as determined by the FSS group.
4.9 The survey design checklist is listed in Attachment 1.
5.0 CALCULATIONS
- The required DCGLw = 8,233 x 0.75 = 6,174 dpml100 cm2 .
- The MDCsan = 6,174 x 0.5 = 3,087 dpm/100 cm2.
- DCGL for 1 m2 = 6,174 XAF of 11=67,914 dpm/100 cm2.
6.0 APPENDICES 6.1 Attachment 1, Survey Design Checklist.
6.2 Attachment 2, Sample Results for Tunnels 6.3 Attachment 3, Effective Area & Volume DCGLs for Cs-137 6.4 Attachment 4, SRA SCM Procedure 001, Rev 6, Confirmation and Calibration of the Incremental Encoder.
6.5 Attachment 5, SRA SCM Procedure 005, Rev 6, Requirements for Completion of the Survey Using the SCM.
6.6 Attachment 6, SRA SCM Procedure 006, Rev 4, Performance of a Position Calibration on a PSPC.
6.7 Attachment 7, SRA SCM Procedure 007, Rev 7, Source Response Check and Performance Based Check of any PSPC Detector Configuration Installed on the SCM.
$:. ->SNECCALCULATION SHEET-Calculation Number Revision Number Page Number E900-03-016 I Page 6 of 9_
Subject Shonka Discharge and Intake Tunnels FSS Survey Design 6.8 Attachment 8, SRA SCM Procedure 008, Rev 3, Conduct of Operations for Surveys Using the SCM/SIMS.
6.9 Attachment 9, SRA SCM Procedure 011, Rev 1, Survey Naming Convention when Using the SCM.
_L. SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 1 Page 7 of 9_
Subject Shonka Discharge and Intake Tunnels FSS Survey Design Attachment I SurveV Design Checklist PrfVJ'O/ A //60 /f/ :
Calculation No. l Location Code: See attached design for location codes.
6900-03-016 _
ITEM rr MR VEW FOCUS REVIEW F C SStatus Reviewer (Circle One) Initials & Date I Has a survey design calculation number been assigned and is a survey design summary Yes, N/A description provided?
2 Are drawings/diagrams adequate for the subject area (drawings should have compass Yes, N/A headings)?
3 Are boundaries property identified and is the survey area classification clearly indicated? Yes, N/A 4 Has the survey area(s) been properly divided into survey units IAW EXHIBIT 10 Yes, NI/A 5 Are physical characteristics of the area/location or system documented? Yes, N/A 6 Is a remediation effectiveness discussion Included? Yes, N/A Have characterization survey and/or sampling results been converted to units that are Yes, Ni/A comparable to applicable DCGL values?
S Is survey and/or sampling data that was used for determining survey unit variance included? Yes, N/A 9 Is a description of the background reference areas (or materials) and their survey and/or Yes, N/A
.__ sampling results Included along with a lustification for their selection? .
10 Are applicable survey and/or sampling data that was used to determine variability Included? Yes, N/A 11 Will the condition of the survey area have an impact on the survey design, and has the Yes, Ni/A probable Impact been considered In the design? .
Has any special area characteristic including any additional residual radioactivity (not 12 previously noted during characterization) been Identified along with its Impact on survey Yes, N/A design?
13 Are all necessary supporting calculations and/or site procedures referenced or Included? Yes, N/A 14 Has an effective DCGLw been Identified for the survey unit(s)? Yes, N/A 15 Was the appropriate DCGLEwC included in the survey design calculation? Yes, N/A 16 Has the statistical tests that will be used to evaluate the data been identified? Yes, N/A 17 Has an elevated measurement comparison been performed (Class I Area)? Yes, N/A is Has the decision error levels been Identified and are the necessary Justifications provided? Yes, N/A 19 Has scan Instrumentation been Identified along with the assigned scanning methodology? Yes, N/A 20 Has the scan rate been Identified, and is the MDCscan adequate for the survey design? Yes, N/A 21 Are special measurements e.g., in-situ gamma-ray spectroscopy required under this design, Yes, N/A and is the survey methodology. and evaluation methods described? es, 22 Is survey instrumentation calibration data Included and are detection sensitivities adequate? Yes, N/A 23 Have the assigned sample and/or measurement locations been clearly Identified on a diagram Yes, N/A or CAD drawing of the survey area(s) along with their coordinates?
24 Are Investigation levels and administrative limits adequate, and are any associated actions Yes, N/A clearly Indicated?
25 For sample analysis, have the required MDA values been determined.? Yes, N/A 26 Has any special sampling methodology been identified other than provided In Reference 6.3? Yes, NiA NOTE: a copy of this completed form or equivalent, shall be Included within the survey design calculation.
SNEC CALCULATION SHEET Caculation Number Revision Number Page Number E900-03-016 i1 Page 8 of 9__
Subject Shonka Discharge and Intake Tunnels FSS Survey Design Attachment 2 Sample Results for Tunnels c .S t40 e- - ~X- 1 - 3 _s . _{.
T I F2(d) T 112 (di T112(d) 1T2 Cd- T12 (ddl T 112(dl T 1R Ml Q1039OI 000° 0.032 0.124 I 20Z3 0247 1 a9s3 2.427 056 1 24824 0.185 0018 0 00r2 0O8 I 0 020 ' 0om
.0n21 Q0C04 Q012 Z 1E.w 1.25EKO 2OE-O021 4.62Eo1 1.4960 1 1.9761 1 *C-0
%o TOi 2 ModW 1.43E-00I 6.34+01
SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 1 Page 9 of 9_
Subject Shonka Discharge and Intake Tunnels FSS Survey Design Attachment 3 Effective Area DCGL for Cs-137 (dpm/100 cm2 )
Effective DCGL Calculator for Cs-137 (dpm/100 cmA2) JW-eiCr.<f1 W 's !GA 1 8543 IdWW00a2 1 6407 .dpv103aw2 1 25I0Jmmm/7TE6Urn s14 . 8233 SMTSwc 4IVIOMC2 1 6174 ,d.MC10Oa,2 re4MEC AL- 1 75%/
3M 46. -14Lpa kdN4I d Unknl A~Hod dWW100 3.1, ~,i1m Alp#- C*VFM hpatops tt" c) %of Totl JdpV10Ma ) a.,2 a OrTEDE c.,2 cm'2 1'Arn-2AI 3.10E.0,0 0.129% 27 11.00 10,19 W 11.00 A ____2_1
-C14 0.000% 3,7W.000 0.00 0.00 0.00 C.
,-14 3C00 9.54E+00 0.396% 7.100 33.85 0.12 33.85 . 0-60M_
4X ~ '.VE.o
[ kM3647 .. 3 S6 3 % 82358 zr,-r 735y .ss: 82: ;
Eu-152 0.000% 13.00O 0.00 0.00 0.00 Eu-152
-3 0.000% 120.000,000 0.00 0.00 0.-.0.. -. H4-.':
3 NN63 0.34E+01 2.633% 1,800000 224 98 0.00 :- N63 N400 MdcDr1,-:_:_iA*:_-
Pu 258 M E.1101 0.038% 30 326 2.72 : 3.26 Pu-238 Pu-239 IA3E00 0.059% 28 5.07 4.53 .:A.. : 5.07
- ' . Pu-2 1 Pu-24M 0.O% 880 0.00 0.00 Q OOD. i. . _*--_____ Pu-241 11 Sr-iO S.1 5E00 0.380% 8.700 32.47 0.09 32.47 .. :.._:... Sr-#O 1m.000% 8543 25.0 a2m 19 Effective Volumetric DCGL for Cs-1 37 (pCilg)
Effct" DOOL Calculator forC5-137 (in pClvg) I L#l2 IPCUglI "7 Ivcis I 24 0. 40 0068 n.14pcug Cpeug 9 _ , 06.384% A .A6.6 6. 6 r _ 2-6 . -. t .8.
67 7.8- -
Epft-M %.fTm Lht to WlTr#E s 4 WS ws ,vTr#ME iAco. 4-18
. t .3430 00 0.00%3 1iS. p 4600 t0.03 a .5& a003 0.03 0.03 f3.14 I.*- 1S co4-g i H,3172 232LON 96.5364S$ t32 g o .3 ,,:c>< - 787.88s Co*>-137 Pu-44 n 0.038% 2. .03a0 0.03 12.7 UT u4 i 43 ex" 263316 747 0 QJ7 O 't7 e t2r M-3 P 21 A3 MM '0.03 00 0.03 0.07 -Pu24 M1 0." 1.2 0.040 M03 003 O. 196.03 sr-o0 I 100.Q00%&2 P6 N020 9 .704 113.775 cm OC." "
P" 1e T I T MftIiPCl w"
Appendix D SCM Survey Design Revision 2
i i l SNEC CALCULATION COVER SHEET CALCULATION DESCRIPTION Calculation Number Revision Number Effective Date Page Number E900-03-01 6 2 06107/04 1 of 16 Subject Shonka Discharge and Intake Tunnels FSS Survey Design Question I - Is this calculation defined as 'In QA Scope"? Refer to definition 3.5. Yes 0 No E]
Question 2 - Is this calculation defined as a 'Design Calculation'? Refer to definitions 3.2 and 3.3. Yes 0 No Question 3 - Does the calculation have the potential to affect an SSC as described in the USAR? Yes El No ED NOTES: If a 'Yes' answer Is obtained for Question 1, the calculation must meet the requirements of the SNEC Facility Decommissioning Quality Assurance Plan. If a 'Yest answer Is obtained for Question 2, the Calculation Originators Immediate supervisor should not review the calculation as the Technical Reviewer. If a 'YES' answer is obtained for Question 3, SNEC Management approval is required to implement the calculation. Calculations that do not have the potential to affect SSC's may be Implemented by the TR.
DESCRIPTION OF REVISION
- 1. Sections 2.1.8 - 2.1.13; Recalculated DCGL,, DCGL and MDC sn values based on new mix calculation logic.
- 2. Sections 4.5, 4.6 & 4.8; Provide discussion for the adjustment of the DCGLW through the use of an administrative limit reduction. Provide the LTP basis for calculation of the MDCsca.. Provide explanation on when scan measurements can suffice for static measurements.
- 3. Section 5.0; Complete rewrite
- 4. Sections 6.2 & 6.3; Revise to denote new Attachments I & 2
- 5. Revised Attachments 2 & 3.
_ APPROV S iATURES Calculation Originator P. Donnachie/ Date 6 Technical Reviewer R. Holmesl 11Date 6/3/o Additional Review A. Paynterl Date ^,0 Additional Review Date SNEC Management Approval Date
at n ~ SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 2 Page 2 of 16_
Subject Shonka Discharge and Intake Tunnels FSS Survey Design 1.0 PURPOSE 1.1 The purpose of this calculation is to provide the survey design guidance to be followed for conducting final status surveys (FSS) in the SSGS Discharge and Intake Tunnels. The Intake Tunnel consists of multiple parts: the Main Intake Tunnel and both the North and South Intake tunnels, which split off from the Main Tunnel. These latter tunnels are located under the SSGS footprint.
1.2 Shonka Research Associates (SRA) will conduct scan surveys using procedures reviewed and approved by SNEC. These procedures are attached as Appendices.
2.0
SUMMARY
OF RESULTS 2.1 The following information will be used to conduct the applicable FSS for this survey design:
2.1.1 The Discharge Tunnel area is divided into nine (9) survey units, i.e. four (4)
Class 1, one (1) Class 2 and four (4) Class 3 survey units.
2.1.2 The Discharge Tunnel Survey Unit (SU) Numbers are as follows:
SU Number Area Description Classification Area (mi 2)
SS1 Floor (first 150 ft) 1 120 SS2 Floor (next 235 ft) 2 175 SS3 Floor (last 315 ft) 3 234 SS4 Ceiling (first 150 ft) 1 120 SS5 Ceiling (last 550 ft) 3 400 SS6-1 South Wall (first 150 ft) 1 145 (Includes % of east wall @ beginning of tunnel)
SS6-2 North Wall (first 150 ft) 1 145 (Includes Y2 of east wall @ beginning of tunnel)
SS7-1 West Wall (last 550 ft) 3 300 SS7-2 East Wall (last 550 ft) 3 300 Note: Area and linear dimensions are approximations.
2.1.3 The Intake Tunnel consists of three parts: Main Intake Tunnel, South Intake under SSGS footprint and the North Intake under the SSGS footprint.
These areas are further subdivided into six (6) Class 2 and three (3) Class 3 survey units.
-n Y SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 2 Page 3 of _16_
Subject Shonka Discharge and Intake Tunnels FSS Survey Design 2.1.4 The Survey Unit Numbers for 'these -tunnels are as follows:
SU Number Area Description Classification Area (m')
SS19-1 Main Intake Tunnel floor 2 167 SS19-2 North Tunnel Floor 2 184 SS19-3 South Tunnel Floor 2 154 SS20-1 Main Intake Walls 2 269 SS20-2 North Tunnel Walls 2 324 SS20-3 South Tunnel Walls 2 359 SS21-1 Main Intake Ceiling 3 162 SS21-2 North Tunnel Ceiling 3 184 SS21-3 South Tunnel Ceiling 3 154 2.1.5 The number of static measurement points will be developed, as applicable, after SRA completes their survey and results are reviewed by the FSS group.
2.1.6 The minimum scan coverage for Class 1 areas will be 100%, Class 2 areas, 50% and for Class 3 areas, 10-50%.
2.1.7 Scan speed will be set in accordance with SRA procedures and the SNEC MDCn value calculated for structure surfaces.
2.1.8 Gross Activity Surface DCGL,, (75 % Admin. Limit)
Intake Tunnel - 48.184 dpm/100 cm2 (See Attachment 2, Table 6).
Discharge Tunnel - 6,726 dpm/100 cm2 (See Attachment 3, Table 6).
2.1.9 Cs-137 Surface DCGLW (75% Admin Limit)
Intake Tunnel - 20,994 dpm/100 cm2 (See Attachment 2, Table 6).
Discharge Tunnel - 6,605 dpm/100 cm2 (See Attachment 3, Table 6).
2.1.10 Total Activity Volumetric DCGLW (75% Admin. Limit)
Discharge Tunnel - 4.98 pCi/g (See Attachment 3, Table 7).
2.1.11 Cs-137 Volumetric DCGLW (Admin. Limit)
Discharge Tunnel - 4.89 pCi/g (See Attachment 3, Table 7).
2.1.12 The surface area DCGL mC will use the Cs-1 37 surface area factor for a 1-m2 area equal to 11.
SNEC CALCULATION SHEET Carcufation Number Revision Number Page Number E900-03-016 2 Page 4 of _16_
Subject Shonka Discharge and Intake Tunnels FSS Survey Design 2.1.13 The MDCSCn value for this design that SRA must achieve is- 15,745 dpm/TW00 cm for the Intake Tunnel and 4,954 dpmr/100 cm2 for the Discharge Tunnel.
2.1.14 Areas greater than the DCGLW must be identified, documented, marked, and bounded to include an area estimate.
2.1.15 Class 1 areas with surface deformations that cannot be surveyed by Shonka will be identified by marking or painting around the suspect area's perimeter.
2.1.16 Remediation is indicated when any area exceeds 3 x the DCGLW for any scan measurement or when the value for any area of -1 square meter is greater than the DCGLemc. Note: If additional remediation is performed the survey unit design is void. -
2.1.17 Gas flow proportional counter (GFPC) will be used IAW SRA procedures.
3.0 REFERENCES
3.1 SNEC Facility License Termination Plan.
3.2 Procedure E900-IMP-4500.59, uFinal Site Survey Planning and DQA".
3.3 SNEC procedure E900-IMP-4520.04, "Survey Methodology to Support SNEC License Termination".
3.4 SNEC procedure E900-IMP-4520.06, "Survey Unit Inspection in Support of FSS Design".
3.5 NUREG-1575, "Multi-Agency Radiation Survey and Site Investigation Manual",
August 2000.
3.6 SRA Procedures - See Appendix Section 6.0.
3.7 SNEC Calculation E900-03-012, "Effective DCGL Worksheet Verification."
4.0 ASSUMPTIONS AND BASIC DATA 4.1 SRA procedures to be used to perform scan surveys.
4.2 SNEC LTP section 2.2.4.1.4 and Figure 2-18 provide a description of the SSGS Discharge Tunnel.
4.3 SNEC LTP section 2.2.4.1.7 and Figures 2-26 and 2-28 provide a description of the Main Intake Tunnels.
4.4 Remediation History The Discharge Tunnel was contaminated as a result of radioactive liquid effluent discharges from the SNEC Facility. Ground water and several inches of silt on the floor of this below grade structure have been removed to adequately survey this area for characterization and final release. Several piping sections have been removed as they were near or above initial DCGLs values. In addition the north
BEVY SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 2 Page 5 of _16 Subject Shonka Discharge and Intake Tunnels FSS Survey Design wall opposite Seal Chamber #3 has been remediated (scabbled). In the SNEC--------
LTP, Figure 2-18 shows this tunnel in detail.
During operation of the SSGS, water was drawn from the Raystown Branch of the Juniata River. A dam was utilized to impound the river in the area of the intake structure, which included the Intake tunnel. The intake water system only provided intake of river water to the SSGS and no discharges to the river were made via this pathway. During freezing weather, warm water from the SSGS Discharge Tunnel was diverted and allowed to flow into the SSGS Intake Tunnel via a pathway that utilized the Spray Pond supply piping. This configuration was established in order to prevent ice formation on the intake tunnel screen wash and filtration system components. This flow path, by use of discharge tunnel water, would have provided a mechanism for low-level radioactivity to enter the SSGS intake tunnel. - -
In the SNEC LTP, Figures 2-25 and 2-28 show the SSGS Intake Tunnel in detail.
Sediment and concrete core sampling was performed in the Intake Tunnel.
Results of these samples are documented in the SNEC LTP. In summary a total of 174 sediment samples were taken throughout the Intake Tunnel. Of these, 142 samples showed only Cs-1 37 above MDC. The average Cs-1 37 value was 0.46 pCi/g and the highest, 1.8 pCi/g. Concrete core bores were obtained throughout the tunnel, analyzed and found to be <MDC.
4.5 This survey determines the effective DCGLW values for Cs-137 using the mixes in Attachments 2 and 3. A 25% reduction to the effective DCGLW was performed to address de-listed radionuclides. The SNEC facility has instituted an administrative limit of 75% for the allowable dose for all measurement results. The de-listed radionuclide dose is accounted for within the 75% administrative limit. The 75%
administrative limit is then applied to the calculated Cs-1 37 limit, e.g. in the case of the Intake Tunnel 0.75 x 27,992 dpm/100 cm2 = 20.994 dpm/100 cm2 .
4.6 The MDCSn calculation is determined based on LTP section 5.5.2.5. See Calculations section below.
4.7 Special measurements including gamma-ray spectroscopy are not included in this survey design.
4.8 Static and other survey measurements may be conducted as applicable after review of the SRA survey is completed. Per LTP section 5.4.3 instrumentation used for scan measurements that are capable of providing data of sufficient quality as that provided by static measurements, can be used in place of static measurements. If the scan measurements are < 10% of the applicable DCGL then no static measurements are required. This design will be supplemented to incorporate additional surveys as determined by the FSS group.
4.9 The survey design checklist is listed in Attachment 1.
SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 2 Page 6 of 16_
Subject Shonka Discharge and Intake Tunnels FSS Survey Design 5.0 CALCULATIONS
- The Intake Tunnel Surface Effective DCGLW (Ref. Attachment 2, Table 6) o 64,245 (gross activity DCGL) x 0.4357 (Cs-137 mix fraction) x 0.75 (admin adjustment) = 20,994 dpm/100 cm 2.
- The Discharge Tunnel Effective DCGLWs (Ref. Attachment 3, Tables 6 & 7) o Surface -8,968 (gross activity DCGL) x 0.982 (Cs-137 mix fraction) x 0.75 (admin adjustment) = 6,605 dpm/100 cm2 .
o Volumetric - 6.64 (total activity) x 0.982 (Cs-137 mix ratio) x 0.75 (admin adjustment) = 4,89 pCi/g
- MDCswn o Intake Tunnel- 20,994 x 0.75 = 15,745 dpm/100 cm2.
o Discharge Tunnel - 6,605 x 0.75 = 4954 dpm/100 cm2.
- DCGLe,,, for I m2 o Intake Tunnel - 20,994 x 11 (Cs-137 area factor) = 230,934 dpm/100 cm 2.
o Discharge Tunnel - 6,605 x 11 (Cs-137 area factor) = 72,655 dpm/100 cm2 6.0 APPENDICES 6.1 Attachment 1, Survey Design Checklist.
6.2 Attachment 2, DCGL Calculation Logic - Intake Tunnel 6.3 Attachment 3, DCGL Calculation Logic - Discharge Tunnel 6.4 Attachment 4, SRA SCM Procedure 001, Rev 6, Confirmation and Calibration of the Incremental Encoder.
6.5 Attachment 5, SRA SCM Procedure 005, Rev 6, Requirements for Completion of the Survey Using the SCM.
6.6 Attachment 6, SRA SCM Procedure 006, Rev 4, Performance of a Position Calibration on a PSPC.
6.7 Attachment 7, SRA SCM Procedure 007, Rev 7, Source Response Check and Performance Based Check of any PSPC Detector Configuration Installed on the SCM.
6.8 Attachment 8, SRA SCM Procedure 008, Rev 3, Conduct of Operations for Surveys Using the SCM/SIMS.
6.9 Attachment 9, SRA SCM Procedure 011, Rev 1, Survey Naming Convention when Using the SCM.
VWK. SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 2 Page 7 of _16_
Subject Shonka Discharge and Intake Tunnels FSS Survey Design Attachment I -
Survey Design Checklist Calculation No. Location Code: See attached design for location codes.
E900-03-016 l Status Reviewer ITEM REVIEW FOCUS (Circle One) Initials & Date Has a survey design calculation number been assigned and is a survey design summary (9 ) N/A I /
description provided? (a VM 37-/0 2 Are drawings/diagrams adequate for the subject area (drawings should have compass 8 N/A 2r r w n s d a r m d q a e f r headings)?
3 Are boundaries properly Identified and Is the survey area classification clearly Indicated? e NM q 4 Has the survey area(s) been properly divided Into survey units IAW EXHIBIT 10 Yes NA.
6 Are physical characteristics of the area/location or system documented?
6 Is a remediation effectiveness discussion Included? G; N/A 7 Have characterization survey and/or sampling results been converted to units that are N/A A comparable to applicable DCGL values? ___________
S Is survey and/or sampling data that was used for determining survey unit variance included? (J N/A 9 Is a description of the background reference areas (or materials) and their survey and/or Yes sampling results Included along with a lustification for their selection? ,/
10 Are applicable survey and/or sampling data that was used to determine variability Included? Yes(0 11 vWill the condition of the survey area have an Impact on the survey design, and has the A probable Impact been considered In the design? i/ 4/
Has any special area characteristic Including any additional residual radioactivity (not 12 previously noted during characterization) been Identified along with Its Impact on survey YesSn5) design?
13 Are all necessary supporting calculations and/or site procedures referenced or Included? N/A 14 Has an effective DCGLw been Identified for the survey unit(s)? NIA 4"&
15 Was the appropriate DCGLEMc Included In the survey design calculation? y N/A 16 Has the statistical tests that will be used to evaluate the data been Identified? Yes,e() 3 17 Has an elevated measurement comparison been performed (Class 1 Area)? YesZ) 18 Has the decision error levels been Identified and are the necessary justifications provided? Yes N/A d 19 Has scan instrumentation been Identified along with the assigned scanning methodology? N/A /'
20 T he scza~n ra ban identified, Is the MDCscan adequate for the survey design? _)_____4_
21 Are special measurements e.g., In-itu gamma-ray spectroscopy required under this design. Yes(D a and Is the survey methodology, and evaluation methods described? X VA0 41 22 Is survey Instrumentation calibration data Included and are detection sensitivities adequate? F N/A4/
23 Have the assigned sample and/or measurement locations been clearly Identified on a diagram ( N/A or CAD drawing of the survey area(s) along with their coordinates? y o S 24 Are Investigation levels and administrative limits adequate, and are any associated actions N/A / g43O 24 ~~~~clearly Indicated?v NM 26 For sample analysis, have the required MDA values been determined.? Y N 26 Has any special sampling methodology been Identified other than provided in Reference 6.3? Yes NOTE: a copy of this completed form or equivalent, shall be Included within the survey design calculation.
heav SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 2 Page 8 of _16 Subject Shonka Discharge and Intake Tunnels FSS Survey Design Attachment 2 DCGL Calculation Logic-Intake Tunnel Survey Unit: SNEC Intake Tunnel 11.
Purpose:
The purpose of this calculation is to determine a representative isotopic mix for the Intake Tunnel from available sample analyses. The effective surface area DCGLW is then determined from the mean percent of applicable samples.
III. Data Selection Logic Tables: The radionuclide selection logic and subsequent DCGL calculations are provided in eight (8)tables. These tables were developed using Microsoft Excel. Table explanation is as follows.
Table 1: Raw Data Listing - This table provides a list of Intake Tunnel sample analysis results from scoping, characterization, and pre/post remediation surveys. The samples consist of various soil and sediments that were taken in support of the aforementioned surveys. As applicable, a sample number, sample location/description, radionuclide concentration, analysis date and a footnote key designator are provided for each sample. The type of sample media is embedded in the sample number (e.g. soil is SL and sediment is SD). Positive nuclide concentrations are noted with yellow/shaded background fields while MDAs are denoted by the less than (<) symbol.
Per the key code column each line of data is selected or de-selected on the basis of the representativeness of the sample media to the final condition of the survey unit. Of the 9 samples listed in Table 1, only sample 1was deselected. This sample was deselected because the laboratory analytical performance for this sample did not meet prescribed MDAs and more recent samples provided more accurate information.
Table 2: Reduced Listing - This table provides the best overall representation of data selected from Table 1. Positive results are denoted in a yellow/shaded background field while MDA values are in a white background. The less than (<)sign has been dropped from the MDA values to allow mathematical operations within the spreadsheet.
Table 3: Decayed Listing - This table provides the decayed values of nuclides selected in Table 2. Half-life values (days) are listed above each respective nuclide column. Samples are decayed to the date noted above Table 2 (e.g. January 15, 2004).
Table 4: Decayed Listing-MDAs Removed - This table provides the final list of sample data that will be used to determine the percent of individual radionuclides relevant to the sample mix for the Intake Tunnel area of the SNEC site. MDA values have been removed except for the Cs-1 37 MDA in sample 8. Since there was not a positive value for Cs-1 37 in this sample the MDA was considered a representative Cs-1 37 concentration for this analysis result. This data point was then used to determine the Cs-1 371H-3 ratio.
Table 5: Decayed Listing-MDAs Removed-Mean Percent of Total - This table provides the calculation methodology for determining the relative fractions of the total activity contributed by each radionuclide. From this information the mean, sigma, and mean % of total are calculated. The mean %of total activity is used to calculate the effective surface gross activity DCGLW in accordance with MARSSIM equation 4-4. In this case the mean percentages for H-3 and Cs-1 37 are 56.43% and 43.57% respectively. Note that the H-3 mean percents were averaged using only samples 7 &8. This is because there is no positive data for samples 1 through 6. This results in the H-3 mean being higher, which is conservative. See Table 6.
Ft a SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 2 Page 9 of 16_
Subject Shonka Discharge and Intake Tunnels FSS Survey Design A question can be asked as to whether samples 1-6 (all Cs-137) should be considered one mix and samples 7-8 (primarily H-3) should be considered a separate mix. However, this was not considered for the following reasons:
- 1. If considered separate mixes the worst-case mix percentage would be H-3 @98.5%
and Cs-1 37 @1.5% from sample 7. Using this mix the calculated surface DCGL in Table 6 would only be reduced by 2%. See Figure 1.
- 2. Samples 7-8 are from an inaccessible area that connects the western section of the Intake Tunnel to the eastern part under the SSGS. This area would have been exposed to the same isotopic mix. These samples were taken during well drilling operations. The drawing for this area is described in Figure 2-28 in the SNEC License Termination Plan, Revision 3.
Therefore, a decision was made to average the results from samples 7-8 with the remaining samples to provide a best representative mix for this area.
Figure 1 2/10/2004 16:24:29 Cs-137 Administrative Limit DCGL vs % of Total Cs-137 In Source Term 100 (for Intake Tunnel Mix) --- Percent Cs.137 4% Loss In DCGL When Cs-137 Is 0.5% vs 99% of Mix
(. 2%Loss In DCGL when Cs.1371 1.5%vs eB.S%
of mi 0Is
- 10. -
CY)
(0 1' - A21000 dpm/tOO cm' 20000 20100 20200 20300 20400 20500 20600 20700 20800 20900 21000 21100 Cs-1 37 Admin. Limit DCGL in dpm/100 cm2 Table 6: Effective DCGL Calculator for Cs-137 (dpm/100 cmA2) - This table provides the surface gross activity DCGLW calculation results from data input from Table 5.
SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 2 Page IOof 16_
Subject Shonka Discharge and Intake Tunnels FSS Survey Design IV. Summary - Since the Intake Tunnel is a concrete structure the release limit is based on the surface area DCGLW. Using the data selection logic tables above, the calculated gross activity DCGLW for surface area is 64,245 dpm/100 cm2 as shown in Table 6. This value would be reduced by 25% to 48,184 dpm/100 cm2 as part of SNEC's requirement to apply an administrative limit for additional conservatism. This value is then multiplied by 0.4357 to correct for the Cs-137 fraction in the mix. Finally, the Cs-137 DCGL, would be 20,994 dpm/100 cm 2. which would be used in the survey unit design to determine the instrument scan set points.
TABLE 1 - Raw Data LbUting(pCiV IE SIm'r Nc, 1 I~rlo 5-5 ACrIm Ct.53 Cs 117 Asi 22B hi3 Zu 1_;7Pu:1 Cu14 .3 E-.52 rse O i }
- .5 TABLE 2 -Reduced Liating fpCifg ____________
- . 1....I'I 1nz K
TABLE 3 . Decayed L~i~ng Includ'ing MDAs (pCifg) 5,50 Sss5e 5:S'5<et5 p.o..
=r~
KEY I Ye 11 c*., '~hadled BaCckcFUnd = PCSJU'\e ReSL~t 1 II-A~s Not Mvet
SNEC CALCULATION SHEET Calculation Number Revision Number I Page Number E900-03-016 2 Page 11 of 16_
Subject Shonka Discharge and Intake Tunnels FSS Survey Design TABLE 4 - Decayed Listing of Positive Nuclides & MDAs Removed (pCilg)
SJEC Sample NO Location Description H-3 Cs-137 Total (pC:ig) 1 S IC-. _C~-2ifZ SvC ceScasci- 2 'S33 ta-e~ z -ea aeH_ -1c E_jje IE b03322 3 2 1CS_-'-..S S -.SSG'S rta e --e I50. i i S - 0 092 3 la39 3 S_ SCIS 1 j-aea22r re Sear: ert - Sciitr - S0.zci Q EC CC 5.1 i rpe 2 08i2 is 4 ~Sc SI1;5 I -<a;.e-u-e e.-r '.cr:-' - %'.ctl; .fScdl ~ 6-t a I.i I 1 99 5 S'XS-2zz ':a Ste~im - East Q 22C _ _1229 _. __
3 6 'cICZ, 1--e e 3eco e 'le - SC i -- , a I ^-cse C -_'CC5 2 032 2O 3
7 S'Ci *-15, - 2 cleer- cr7ectrr;-s fr-ei Rl -ae 65 84 U 22 704 E ' 'z S :-ot- .-1 35 i-c ce - 3 439~ O 051 3i '1 TABLE 5 - Mean Percent of Total for Positive Nuclides SIJEC Sample No Location.Description 11-3 Cs-137 To-al I ____________- S Sc
- _stace i- SSCS Mzase r_-clee ea -1' OS 13E cc- 100 00°c 100 G0%
2 = - 1 3= - ::a .c%:e :--l5S .c -} _--100 00% 10c 0o0 %
_ SXS-'.- rtse ,^ Seca -e, ' - '- Lcttc eCcc _ 10 )00% 10550 %
SS IK Z 1 SE nt3e- e-t 11i 7-'.c:--i .- c U- .a .z-Se cr 2E 100a0% 13(50
_ SXS!22222 :-a-. ur-e ert - Eas:t 22C 100 00% 105(0%01 6 SES:2- % i 7 : ei3ecirerz - 3C, ' - .ai' 9 c ae2 - 1CC 100 00% 1C0030e%
7 S-5:23 -\'-127 ~-ce32 Sc eer-- fi 5' 13%
S.,ecTh--c- 2 877% 103 40%o 8 -137 98 336 145% 100 0D0%
_a - 9S 76n S-01 - SE-01 1 '
3'6 ' c - : 43% 45 £7% 100 003%
Table 6 Effective DCGL Calculator for Cs-137 (dpmi100 cmA2) GrossAketivlS DCw 1i rs AfsiWVt Amgnattraehv U-ms 64245 idpml160 cm^2 i 48184 cipm'100 cm12 Le25 0 mm y TEDELa'i:
Cs-137 Urmit I cs-r3Adsmhajasfise v mLim SAPLEli - 27992 dpm100 cm'2 20994 dpm 100 cm-2 SNEC AL Sample lnpcc Limis Allo'.ed Eeta dpn' 10 Alpha dpil 10N lsoope g FCi uC,. etcl -, -osal sdpi100 cm^21 dpmitO9 cm'2 mrem yTEDE cm12 Cm'2 I Am 241 0 000%, 27 0G0 0 00 - a:'aC lAm-24t l C14 l l 0 3.700.000 550 SOC 30 1 C4 3 Co-60 _ 0a_300% 7,100 5 3C C"03 . 0 l Co'. -60 l CS-137 4136E071 43 51% MOM 27991 64 24.99 2719 5 .': B -137l 5 Eu-152 0 300%Q4 130000 0 00 !0-l lIl Eu-152 l l5C30 120,000.000 21351 N5 Deleclsblc ."' ilHi j N-63 0 5005% 1.800,000 l 3 Q0 0 00 ilO Detectabie ::-. :Ji-63 Pu,238 000% 30 1 0 00 00 l~qA 5GO Pu-239 Pu239 j __NO_ I 00% 28 000 000 a000 PU-239 FU-Z41 2 nj y 800 0 C1 l~clsat D l ee l : l lA --: PU.2 4 1 SIt-0 S M5C' PI 7610 'I vv 100 5003% 64245 i . _, _
25.0 27992 0 Ptlaximum Permissible CIPnl100 CM'?
C l Z
F--a SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 2 Page 12 of _16 Subject Shonka Discharge and Intake Tunnels FSS Survey Design Attachment 3 DCGL Calculation Logic-Discharge Tunnel Survey Unit: SNEC Discharge Tunnel
- 11.
Description:
The purpose of this calculation is to determine a representative isotopic mix for the Discharge Tunnel from available sample analyses. The effective surface area and volumetric DCGLWs are then determined from the mean percent of applicable samples.
1ll. Data Selection Logic Tables: The radionuclide selection logic and subsequent DCGL calculations are provided in seven (7) tables. These tables were developed using Microsoft Excel spreadsheet software. Table explanation is as follows.
Table 1: Data Listing - This table, which has been extracted from a larger database, provides a list of the most representative Discharge Tunnel sample analyses. These results are from scoping, characterization, and prelpost remediation surveys. The samples consist of various sediments, scrapings and concrete cores that were taken in support of the aforementioned surveys. As applicable, a sample number, sample location/description, radionuclide concentration, analysis date are provided for each sample. Positive nuclide concentrations are noted with yellow/shaded background fields while MDAs are noted in the gray shaded fields.
Table 2: Decayed Listing - This table provides the best overall representation of data selected and decayed from Table 1. In Table 1 half-life values (days) are listed above each respective nuclide column. Samples are decayed to the date noted above Table I (e.g. January 15, 2004). Positive results are denoted in a yellow background field while MDA values are in a gray background.
Table 3: Decayed Listing of Positive Nuclides & MDAs Removed- This table provides the decayed values of positive nuclides selected in Table 2. In addition MDA values have been removed from this table.
Table 4: Mean Percent of Total for Positive Nuclides - This table provides the calculation methodology for determining the relative fractions of the total activity contributed by each radionuclide. From this information the mean, sigma, and mean % of total are calculated. The mean % of total values is used to calculate the surface gross activity DCGLW per MARSSIM equation 4-4. See Table 6. Note that the Co-60 mean percents were averaged using only samples 1 & 2. In addition, the mean percents calculated from sample 2 for Am-241, Pu-238, Pu-239 and Ni-63 were not averaged throughout the spreadsheet since there was only one sample where these respective nuclides were positive. This results in higher 'mean percent of total" values in the mix, which are conservative.
Table 5: Ratio to Cs-1 37 for Positive Nuclides -This table provides the calculation methodology for determining the surrogate ratio to Cs-137 for each radionuclide. From this information the mean, sigma, and mean % of total are calculated. The mean % of total values is used to calculate the volumetric DCGLW per MARSSIM equation 1-14. See Table 7. Note that the Co-60 ratios were averaged using only samples 1 & 2. In addition, the ratios calculated from sample 2 for Am-241, Pu-238, Pu-239 and Ni-63 were not averaged throughout the spreadsheet since there was only one sample where these respective nuclides were positive. This results in higher "mean percent of total' values in the mix, which are conservative.
Note: From Tables 4 and 5 only the "mean % of total" values are used as input to the "Effective DCGL Calculation Spreadsheet" as Illustrated In Tables 6 and 7.
SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 2 Page 13 of _16_
Subject Shonka Discharge and Intake Tunnels FSS Survey Design Table 6: Effective DCGL Calculator for Cs-137 (dpml100 cmA2) - This table provides the surface gross activity DCGLW calculation results from data inputted from Table 4.
Table 7: Effective DCGL Calculator for Cs-137 (in pCilg) - This table provides the surrogate volumetric modified Cs-1 37 DCGLW calculation results from data inputted from Table 5.
IV. Summary - Since the Discharge Tunnel is a concrete structure the release limit is primarily based on the surface area DCGLW. However, a small portion of the Discharge Tunnel ceiling Class 1 area has volumetric contamination. Using the above data selection logic tables the calculated gross activity DCGLW for surface area is 8,968 dpm/100 cm2 . The Cs-137 volumetric DCGLW is 6.52 pCilg. These values would be reduced by 25% as part of SNEC's requirement to apply an administrative limit as required by the License Termination Plan (LTP).
TABLE 2 - Decayed Listing IpCifgl
-. I C .52 I Cc1l Is C is as jr -. F-t.42 a gA-t/s- ::
[ MUTE.
I OI - I t 99E 3 p
- OfF/U I XT L - -aJ i~ -_- 5: - ,- lt-JC - a kit-.. .--.
I_ 71SD -:16I
_______il£0i, fI i-..iE,
-~~---O _ S~t-Orc I
24-fiI >
1
.1-4~
o1
._a:.. ___,_;___
- ^I I X42{g I -
"'Er
- ci Sicea- nc~ Z;iCU7
- =;ts;t ~-R~est~ I If- IGa. So~ ~e,5C-;rtc";,^
E a = i 5_
Z i Co 3?
SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 2 Page 14 of _16 Subject Shonka Discharge and Intake Tunnels FSS Survey Design TABLE 3 - Decayed Listing of Positive Nuclides & MDAs Removed (pCig)
S EC StmpieNo LocatiorDesc pion Co-SO Cs-137 l Am-241 Pf-234 Pt2-2.S /l-63 Toaai JpCi~g) 1S.C-i- fcace~ ".<- a--":;r....
S..... 4 6'E-01 1OSE-02 ta
-CS *,, !r; 433E-03je 36E- I 34E-OO 2 .fDE-01: E 4_2
_ - :a -- e F -e- - 0E-0_
SE- 1 32E-'
____ __ C_, 2 I-O
'e-_SjE+OO 4 2I2- 3E-CC' ' 4E:O0,-N-EO'jw1-st
__-___ _E 3 33 :23 ___ t __ L G 30zI C
_c_ _ _____ 10 TABLE 4 -Mean Percent of Total for Positive Nuclides
_ S'NEC S-pm~e Tic 6 -- :.-6SC .s:--e~-e LOC31ion SF-.~0 Descr-iptior r-~5 S0-~5*4-C oS 05% 4e Cs-137 tOO~54 0030.
107f~ 575' se;e,-241~ -cePFt-23-23 2& .?235 lir-;' Tef^P.
1DIEOC 0 ___
_-S-eE-
___________5 1 03-C _c _ _ 10 c__
c__SSSC-S___ Loe3:ro3 D503 Pt or Co-SO C-j .nF - .2410 i PO-22S 13~-3 -O c~
0 _ E'.C6-
_ _ _ _ SS.:S 53te:
1ZiOZf
- an Percenrtof _________S-CC 15ZO5!V3 TAL - 4e 10fo 00%
105 0Potive_____ N e -
-~ ~ - C S- -3_3 03300% 0320% 2 4 C5% 17 1..
ea5 -~ e f 012DCC 1.i 33 a2t:oO___i__t__7____ t
______ ______100 00%1 e3- 4 S-5~ OO E-01 I22E-G57 E-3JO 7 E C- 2 E .7 57 33 45%
557~~ U i. J.% 1 TABLE 6 - Ratio to Cs-1'37 for Positive Nuclides L ocat c Co-60 Cs-17? Am 241 T a.1 4 31E-03 I 1 5E-50
, "0 I -e oaza 3 S34E-03 1 OQE-00 1 242E-03 I 00E-0 _____
_ IOOE-0C _ __ _ _
I OSE-OiD _ __ _ _
CI eC _ _^ Ce .3 ! ce - - 1I00E-00 1I00E-00 1 00E-nOSj I 00E-00 _ _ _
- 1.1- - -- --.1 i -4OSE-53 I 00F*05 4
__ . ._ _ I - -_
21___ 1 100 00___
CO+
SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 2 Page 15 of 16_
Subject Shonka Discharge and Intake Tunnels FSS Survey Design Table 6 Effective DCGL Calculator for Cs-137 (dpml100 cmA2) l r7.~': I ci i 88968 ldpmIloO cmM21 6726 ldpmr100 cm^2 25.0 mremly TEDE Limit 137 iC iUmit *,VCs-137
-< Administistifve-nitt W SAMPLE 1s DischargeTunnel 1 8807 ldpmlOO cm^2 6605 dPmMOO cm^2 l1SNEC AL~k 75%
Individual Sample Input Limits Allowed Beta dpm'100 Alpha dpmftOO Isotope (pCig, uCl. etc.) %ofTotaI (dpm,1OOcm'2) dpm:100cm^2 mremtYTEDE cm^2 cm^2 i Am-241 1.22E-03 0.120% 27 10.77 9.97 :tA:; 10 77 Am-241 2 C-14 0.000% 3.700,000 0.00 0.00 0.00 C.14 3 Co.60 4.03E.03 0.397% 7,100 35;66 0.13 35 .6 W A:{ i. Co-60 c137 iAt !,
DA g.g8E.01't. s r .98.203% . 000 ;8806.99 ! f4.7.86 ; '8807.0 .. ... C.37 s Eu.152 0.000%vO 13,000 0.00 0.00 0.00 : -A-:E::: Eu.152 6 H-3 ,_0.000% 120,000,000 0.00 0.00 Ilot Detectable **.-
09flAS,, 11 - - _-3 7 Ni-63 1.21E-02 1.191% 1.800.000 106.78 0.00 Nlot Detectable Y N; 63 a Pu-238 3.50E-04 0.034% 30 3.09 2.57 . ....... ss 3 09 Pu.238 Pu-239 5.67E.04 0.0i6% 28 5.00 4.47 PAC*S 5 00 Pu.239 10 Pu-241 0.000% 880 0.00 0.00 Hiot Detectable i: Pu-241 i Sr.90 _ 0.000% 8.700 0.00 0.00 0.00 A . Sr-90 100.000% 8968 25.0 8843 19 Maximum Permissible dpmllOO cm^2
- -- SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-016 2 Page 16 of 16_
Subject Shonka Discharge and Intake Tunnels FSS Survey Design Table 7 I%V"SNECAL%-%. 75% 'ToWAC%*y LMHtDCLw' .,:Admk sftzraUvLmIt I..
Effective DCGL Calculatorfor Cs-137 (in pCg) I 6.64 JpCilg 1 4.98 gpCug
- SAMlEIi~iKUESSERII es'e I Ce37Lknflt f~0I Ca-13T AmhiisutrewveLmt 25.0 mromiy TMOLint 1 6.52 1CI! 1 4.89 pCilq A 55L Sample lnptn Isotope Am-241 (pCVQ- uck %
of Total.efc.
t0.001
% of Total
_0.122%
25mremlyTcDE itmts(pCV;)
9.9 ___
A.A$owedpClgtor 25 mresq TEDE 0.01 - S vtue Checked from Vi Cohmn A or t 0.01 This Sanigil mremy TEDE 0.00 Pjwhj z00,u I
I C-8-.1 t 0.000% 2.0 0.00 00 0 00 C-14 Co _ 0.041 - 0.401% 3'3.5 _003 0 03 Co.60 Cs-137 ___ 1000 _ 98.178% 6.6 _6.52 __ E-c6, 3.79 lg Cs.137 Eu.152 0000% 10.1 _ 3 0.000 0.00 Eu.152 H-3__ 000% 132 a 000 _0 00 H.3 llt-63 _ _ 0123 _ 1.208% 747oa NI-S3 Pu.238 0.0004 0.035% 1.t 0.00 ______ 000 Pu.238 II Pu-239 0.0006.0- -. 0057% 1-.6- 00 0000 Pu.239 Pu.241 - 0.000% 86 0.00 0_00 PU.241 If Sr-90 ____0_000_ 1.2 00 0 Co
' 000 ~ Sr.90 1.02E-00 100.000% 6.64 183.53 6.64 --3.835 0 2 Maxdmum Permissible Ma1dmum To UseThis Iformadron.
PCI1g Permissible pCig Simple hWutUnlits ust Bein a2s mromlwl 1 (4 mremiyl pC~g not % of Total. l