appendix c scm survey design revision 1 · 6.1 attachment 1, survey design checklist. 6.2...

Appendix C

SCM Survey DesignRevision 1

SNEC CALCULATION COVER SHEETCALCULATION 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 EaQuestion 3 - Does the calculation have the potential to affect an SSC as described in the USAR? Yes Il No 0DNOTES: If a 'Yes answer Is obtained for Question 1, the calculation must meet the requirements of the SNEC Facility Decommissioning QualityAssurance Plan. If a 'Yes answer Is obtained for Question 2, the Calculation Originators immediate supervisor should not review thecalculation as the Technical Reviewer. If a YES' answer is obtained for Question 3. SNEC Management approval Is required to implement thecalculation. 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

III

SNEC CALCULATION SHEETCalculation Number Revision Number Page Number

E900-03-016 1 Page 2 of____Subject


1.0 PURPOSE

1.1 The purpose of this calculation is to provide the survey design guidance to be followed forconducting final status surveys (FSS) in the SSGS Discharge and Intake Tunnels. TheIntake Tunnel consists of multiple parts: the Main Intake Tunnel and both the North andSouth Intake tunnels, which split off from the Main Tunnel. These latter tunnels are locatedunder the SSGS footprint.

1.2 Shonka Research Associates (SRA) will conduct scan surveys using procedures reviewedand approved by SNEC. These procedures are attached as Appendices.

2.0 SUMMARY OF RESULTS2.1 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:

I

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

SS5 Ceiling (last 550 ft) 3 400

SS6-1 South Wall (first 150 ft) 1 145(Includes % of east wall @ beginning oftunnel)

SS6-2 North Wall (first 150 ft) 1 145(Includes % of east wall @ beginning oftunnel)

SS7-1 West Wall (last 550 ft) 3 300

SS7-2 East Wall (last 550 ft) 3 300Note: Area and linear dimensions are approximations.

2.1.3 The Intake Tunnel consists of three parts: Main Intake Tunnel, South Intake underSSGS footprint and the North Intake under the SSGS footprint. These areas arefurther subdivided into six (6) Class 2 and three (3) Class 3 survey units.


E900-03-O16 Page 3 of_9_Subject


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, afterSRA 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 2nvalue calculated for structure surfaces.

2.1.8 The surface DCGLw for this design is determined to be 6174 dpml100 cm2 basedon 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 areaequal 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 cm2.

2.1.11 The volumetric DCGLw for this design is determined to be 4.78 pCilg based onthe attached spreadsheet calculation (Attachment 9). This value represents the75% 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, andbounded to include an area estimate.

2.1.13 Class 1 areas with surface deformations that cannot be surveyed by Shonka will beidentified 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 scanmeasurement or when the value for any area of -1 square meter is greater than theDCGLoc. Note: If additional remediation is performed the survey unit designis void.

SNEC CALCULATION SHEET -Calculation Number Revision Number Page Number

E900-03-016 I 1 Page 4 of 9-Subject


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 LicenseTermination".

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', August2000.

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 DischargeTunnel.

4.3 SNEC LTP section 2.2.4.1.7 and Figures 2-26 and 2-28 provide a description of the MainIntake Tunnels.

4.4 Remediation History

The Discharge Tunnel was contaminated as a result of radioactive liquid effluentdischarges from the SNEC Facility. Ground water and several inches of silt on the floor ofthis below grade structure have been removed to adequately survey this area forcharacterization and final release. Several piping sections have been removed as theywere near or above initial DCGLs values. In addition the north wall opposite Seal Chamber#3 has been remediated (scabbled). In the SNEC LTP, Figure 2-18 shows this tunnel indetail.

During operation of the SSGS, water was drawn from the Raystown Branch of the JuniataRiver. A dam was utilized to impound the river in the area of the intake structure, whichincluded the Intake tunnel. The intake water system only provided intake of river water tothe SSGS and no discharges to the river were made via this pathway. During freezingweather, warm water from the SSGS Discharge Tunnel was diverted and allowed to flowinto 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 tunnelscreen wash and filtration system components. This flow path, by use of discharge tunnelwater, would have provided a mechanism for low-level radioactivity to enter the SSGSintake tunnel. In the SNEC LTP, Figures 2-25 and 2-28 show the SSGS Intake Tunnel indetail.


E900-03-016 - 1 Page 5 of 9Subject


Sediment and concrete core sampling was performed in the Intake Tunnel. Results ofthese samples are documented in the SNEC LTP. In summary a total of 174 sedimentsamples were taken throughout the Intake Tunnel. Of these, 142 samples showed onlyCs-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 inAttachment 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 theallowable dose for all measurement results. The de-listed radionuclide dose is accountedfor within the 75% administrative limit. The 75% administrative limit is then applied to thecalculated 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 calculationconsists 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 surveydesign.

4.8 Static and other survey measurements may be conducted as applicable after review of theSRA survey is completed. This design will be revised to incorporate these surveys asdetermined 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 theIncremental Encoder.

6.5 Attachment 5, SRA SCM Procedure 005, Rev 6, Requirements for Completion of theSurvey Using the SCM.

6.6 Attachment 6, SRA SCM Procedure 006, Rev 4, Performance of a Position Calibration ona PSPC.

6.7 Attachment 7, SRA SCM Procedure 007, Rev 7, Source Response Check andPerformance Based Check of any PSPC Detector Configuration Installed on the SCM.

$:. ->SNEC CALCULATION SHEET-Calculation Number Revision Number Page Number

E900-03-016 I Page 6 of 9_Subject


6.8 Attachment 8, SRA SCM Procedure 008, Rev 3, Conduct of Operations for Surveys Usingthe SCM/SIMS.

6.9 Attachment 9, SRA SCM Procedure 011, Rev 1, Survey Naming Convention when Usingthe SCM.

_L. SNEC CALCULATION SHEETCalculation Number Revision Number Page Number

E900-03-016 1 Page 7 of 9_Subject


Attachment ISurveV Design Checklist PrfVJ'O/ A // 60 /f/ :

Calculation No. | Location Code: See attached design for location codes.6900-03-016 _

rr MR VEW F C SStatus ReviewerITEM REVIEW FOCUS (Circle One) Initials & Date

I Has a survey design calculation number been assigned and is a survey design summary Yes, N/Adescription provided?

2 Are drawings/diagrams adequate for the subject area (drawings should have compass Yes, N/Aheadings)?

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/Acomparable 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/Aprobable Impact been considered In the design? .

Has any special area characteristic including any additional residual radioactivity (not12 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/Aand 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/Aor 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/Aclearly 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 SHEETCaculation Number Revision Number Page Number

E900-03-016 i 1 Page 8 of 9__Subject


Attachment 2Sample 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

2.427056 1 248240.185

0018 0 00r2 0O8 I

0 020 ' 0om.0n21 Q0C04 Q012

%o TOi

2 ModW

Z 1E.w 1.25EKO 2OE-O021 4.62Eo1 1.4960 1 1.9761 1 *C-0

1.43E-00I 6.34+01




Attachment 3Effective Area DCGL for Cs-137 (dpm/100 cm2)

Effective DCGL Calculator for Cs-137 (dpm/100 cmA2) JW-eiCr.<f1 W 's !GA1 8543 IdWW00a2 1 6407 .dpv103aw2

1 25I0Jmmm/ 7TE6 Urn

s14 SMTSwc . 8233 4IVIOMC2 1 6174 ,d.MC10Oa,2

re4MEC AL- 1 75% /

3M 46. -14 Lpa kdN4I d Unknl A~Hod dWW100 3.1, ~,i1m Alp#- C*VFMhpatops tt" c) % of Totl JdpV10Ma ) a.,2 a Or TEDE 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

3 C00 9.54E+00 0.396% 7.100 33.85 0.12 33.85 . M_ 0-604X ~ '.VE.o [ 3 .. kM3647 % S6 3 82358 zr ,-r 735 .ss: ; y 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.. 4-.': H 3NN63 0.34E+01 2.633% 1,800000 224 98 0.00 N400 MdcDr1,-:_:_iA*:_- :- N63

Pu 258 M E.1101 0.038% 30 326 2.72 : 3.26 Pu-238Pu-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 OO D. i. . _*--_____ Pu-24111 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 for C5-137 (in pClvg) I L#| 2 IPCUg| I "7 Ivcis I

0. 24 40 0068 .1 4pcug n Cpeug

9 -0-_ , 06.384 % A .A6.6 6. 6 r _ 2-6 . -. 7.8- t 67 .8. -Epft-M %.fTm Lht to Wl Tr#E s 4 WS ws ,vTr#ME

i A . 4-18 00 3 1 . p 4600 t a a003 0.03 I.*- 1S

Pu- n 44 0.038% 2. .03a0 0.03 12.7 U T u4

.co t .3430 0.00% iS 0.03 .5& 0.03 f3.14 co4-gi H,3172 232LON 96.5364S$ t32 g o .3 ,,:c>< - 787.88s Co*> -137

i 43 ex" 263316 747 0 QJ7 O 't7 e r t2 M-3

P 21 A3 M M '0.03 00 0.03 0.07 -Pu24

0.040 M1 0." 1.2 M03 O. 003 196.03 sr-o0

I 100.Q00 %&2 P6 N02 9 .704 0 113.775

OC P" T T w"cm ." " 1e I MftIiPCl

Appendix D

SCM Survey DesignRevision 2

ii l

SNEC CALCULATION COVER SHEETCALCULATION DESCRIPTION

Calculation Number Revision Number Effective Date Page Number

E900-03-01 6 2 06107/04 1 of 16

Subject


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 QualityAssurance Plan. If a 'Yest answer Is obtained for Question 2, the Calculation Originators Immediate supervisor should not review thecalculation as the Technical Reviewer. If a 'YES' answer is obtained for Question 3, SNEC Management approval is required to implement thecalculation. 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 mixcalculation logic.

2. Sections 4.5, 4.6 & 4.8; Provide discussion for the adjustment of the DCGLW through the use ofan administrative limit reduction. Provide the LTP basis for calculation of the MDCsca.. Provideexplanation 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 & 25. 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

a n t ~ SNEC CALCULATION SHEETCalculation Number Revision Number Page Number



1.0 PURPOSE

1.1 The purpose of this calculation is to provide the survey design guidance to befollowed for conducting final status surveys (FSS) in the SSGS Discharge andIntake Tunnels. The Intake Tunnel consists of multiple parts: the Main IntakeTunnel and both the North and South Intake tunnels, which split off from the MainTunnel. These latter tunnels are located under the SSGS footprint.

1.2 Shonka Research Associates (SRA) will conduct scan surveys using proceduresreviewed 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 thissurvey 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 (mi2 )

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 oftunnel)

SS6-2 North Wall (first 150 ft) 1 145(Includes Y2 of east wall @ beginning oftunnel)

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 Intakeunder SSGS footprint and the North Intake under the SSGS footprint.These areas are further subdivided into six (6) Class 2 and three (3) Class3 survey units.

-n Y SNEC CALCULATION SHEETCalculation Number Revision Number Page Number

E900-03-016 2 Page 3 of _16_Subject


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 FSSgroup.

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 SNECMDCn 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 SHEETCarcufation Number Revision Number Page Number



2.1.13 The MDCSCn value for this design that SRA must achieve is- 15,745dpm/TW00 cm for the Intake Tunnel and 4,954 dpmr/100 cm2 for theDischarge 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 byShonka will be identified by marking or painting around the suspect area'sperimeter.

2.1.16 Remediation is indicated when any area exceeds 3 x the DCGLW for anyscan measurement or when the value for any area of -1 square meter isgreater than the DCGLemc. Note: If additional remediation is performedthe 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 SNECLicense Termination".

3.4 SNEC procedure E900-IMP-4520.06, "Survey Unit Inspection in Support of FSSDesign".

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 SSGSDischarge Tunnel.

4.3 SNEC LTP section 2.2.4.1.7 and Figures 2-26 and 2-28 provide a description ofthe Main Intake Tunnels.

4.4 Remediation History

The Discharge Tunnel was contaminated as a result of radioactive liquid effluentdischarges from the SNEC Facility. Ground water and several inches of silt on thefloor of this below grade structure have been removed to adequately survey thisarea for characterization and final release. Several piping sections have beenremoved as they were near or above initial DCGLs values. In addition the north

BEVY SNEC CALCULATION SHEETCalculation Number Revision Number Page Number

E900-03-016 2 Page 5 of _16Subject


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 theJuniata River. A dam was utilized to impound the river in the area of the intakestructure, which included the Intake tunnel. The intake water system only providedintake of river water to the SSGS and no discharges to the river were made via thispathway. During freezing weather, warm water from the SSGS Discharge Tunnelwas diverted and allowed to flow into the SSGS Intake Tunnel via a pathway thatutilized the Spray Pond supply piping. This configuration was established in orderto prevent ice formation on the intake tunnel screen wash and filtration systemcomponents. This flow path, by use of discharge tunnel water, would haveprovided 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 totalof 174 sediment samples were taken throughout the Intake Tunnel. Of these, 142samples showed only Cs-1 37 above MDC. The average Cs-1 37 value was 0.46pCi/g and the highest, 1.8 pCi/g. Concrete core bores were obtained throughoutthe tunnel, analyzed and found to be <MDC.

4.5 This survey determines the effective DCGLW values for Cs-137 using the mixes inAttachments 2 and 3. A 25% reduction to the effective DCGLW was performed toaddress de-listed radionuclides. The SNEC facility has instituted an administrativelimit of 75% for the allowable dose for all measurement results. The de-listedradionuclide 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 ofthe 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. SeeCalculations section below.

4.7 Special measurements including gamma-ray spectroscopy are not included in thissurvey design.

4.8 Static and other survey measurements may be conducted as applicable afterreview of the SRA survey is completed. Per LTP section 5.4.3 instrumentationused for scan measurements that are capable of providing data of sufficient qualityas that provided by static measurements, can be used in place of staticmeasurements. If the scan measurements are < 10% of the applicable DCGLthen no static measurements are required. This design will be supplemented toincorporate additional surveys as determined by the FSS group.

4.9 The survey design checklist is listed in Attachment 1.




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 cm2.

* 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) = 230,9342dpm/100 cm .

o Discharge Tunnel - 6,605 x 11 (Cs-137 area factor) = 72,655dpm/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 ofthe Incremental Encoder.

6.5 Attachment 5, SRA SCM Procedure 005, Rev 6, Requirements for Completion ofthe Survey Using the SCM.

6.6 Attachment 6, SRA SCM Procedure 006, Rev 4, Performance of a PositionCalibration on a PSPC.

6.7 Attachment 7, SRA SCM Procedure 007, Rev 7, Source Response Check andPerformance Based Check of any PSPC Detector Configuration Installed on theSCM.

6.8 Attachment 8, SRA SCM Procedure 008, Rev 3, Conduct of Operations forSurveys Using the SCM/SIMS.

6.9 Attachment 9, SRA SCM Procedure 011, Rev 1, Survey Naming Conventionwhen Using the SCM.

V WK. SNEC CALCULATION SHEETCalculation Number Revision Number Page Number



Attachment I -

Survey Design Checklist

Calculation No. Location Code: See attached design for location codes.

E900-03-016 |

Status ReviewerITEM REVIEW FOCUS (Circle One) Initials & Date

Has a survey design calculation number been assigned and is a survey design summary (9 ) N/A / Idescription provided? (a VM 37-/0

2 Are drawings/diagrams adequate for the subject area (drawings should have compass 8 N/A2 r 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 A N/Acomparable 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 Yessampling 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 Aprobable Impact been considered In the design? i/ 4/

Has any special area characteristic Including any additional residual radioactivity (not12 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)? 4" NIA &

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 aand 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/Aor 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/A24 ~~~~clearly Indicated?v NM / g43O

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 SHEETCalculation Number Revision Number Page Number



Attachment 2DCGL Calculation Logic-Intake Tunnel

Survey Unit: SNEC Intake Tunnel

11. Purpose: The purpose of this calculation is to determine a representative isotopic mix for theIntake Tunnel from available sample analyses. The effective surface area DCGLW is thendetermined from the mean percent of applicable samples.

III. Data Selection Logic Tables: The radionuclide selection logic and subsequent DCGLcalculations are provided in eight (8) tables. These tables were developed using MicrosoftExcel. Table explanation is as follows.

Table 1: Raw Data Listing - This table provides a list of Intake Tunnel sample analysisresults from scoping, characterization, and pre/post remediation surveys. The samplesconsist of various soil and sediments that were taken in support of the aforementionedsurveys. As applicable, a sample number, sample location/description, radionuclideconcentration, analysis date and a footnote key designator are provided for each sample. Thetype of sample media is embedded in the sample number (e.g. soil is SL and sediment isSD). Positive nuclide concentrations are noted with yellow/shaded background fields whileMDAs 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 therepresentativeness of the sample media to the final condition of the survey unit. Of the 9samples listed in Table 1, only sample 1 was deselected. This sample was deselectedbecause the laboratory analytical performance for this sample did not meet prescribed MDAsand more recent samples provided more accurate information.

Table 2: Reduced Listing - This table provides the best overall representation of dataselected from Table 1. Positive results are denoted in a yellow/shaded background fieldwhile MDA values are in a white background. The less than (<) sign has been dropped fromthe MDA values to allow mathematical operations within the spreadsheet.

Table 3: Decayed Listing - This table provides the decayed values of nuclides selected inTable 2. Half-life values (days) are listed above each respective nuclide column. Samplesare 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 datathat will be used to determine the percent of individual radionuclides relevant to the samplemix for the Intake Tunnel area of the SNEC site. MDA values have been removed except forthe Cs-1 37 MDA in sample 8. Since there was not a positive value for Cs-1 37 in this samplethe MDA was considered a representative Cs-1 37 concentration for this analysis result. Thisdata 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 thecalculation methodology for determining the relative fractions of the total activity contributedby each radionuclide. From this information the mean, sigma, and mean % of total arecalculated. The mean % of total activity is used to calculate the effective surface grossactivity DCGLW in accordance with MARSSIM equation 4-4. In this case the meanpercentages for H-3 and Cs-1 37 are 56.43% and 43.57% respectively. Note that the H-3mean percents were averaged using only samples 7 & 8. This is because there is no positivedata for samples 1 through 6. This results in the H-3 mean being higher, which isconservative. See Table 6.

F a t SNEC CALCULATION SHEETCalculation Number Revision Number Page Number



A question can be asked as to whether samples 1-6 (all Cs-137) should be considered onemix and samples 7-8 (primarily H-3) should be considered a separate mix. However, thiswas 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 inTable 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 theIntake Tunnel to the eastern part under the SSGS. This area would have beenexposed to the same isotopic mix. These samples were taken during well drillingoperations. The drawing for this area is described in Figure 2-28 in the SNECLicense Termination Plan, Revision 3.

Therefore, a decision was made to average the results from samples 7-8 with the remainingsamples 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

0Is10. -

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 thesurface gross activity DCGLW calculation results from data input from Table 5.


E900-03-016 2 Page IO of 16_Subject


IV. Summary - Since the Intake Tunnel is a concrete structure the release limit is based on thesurface area DCGLW. Using the data selection logic tables above, the calculated grossactivity DCGLW for surface area is 64,245 dpm/100 cm2 as shown in Table 6. This valuewould be reduced by 25% to 48,184 dpm/100 cm2 as part of SNEC's requirement to apply anadministrative limit for additional conservatism. This value is then multiplied by 0.4357 tocorrect for the Cs-137 fraction in the mix. Finally, the Cs-137 DCGL, would be 20,994dpm/100 cm2. which would be used in the survey unit design to determine theinstrument scan set points.

TABLE 1 - Raw Data LbUting (pCiVI E SIm 'r Nc, I~rlo ACrIm 1 5-5 Ct.53 Cs 117 Asi 22B Zu hi3 1_;7Pu:1 Cu 14 .3 E-.52 rse O i }

- .5 …- ..

TABLE 2 -Reduced Liating fpCifg ____________

:- t-

tIC -- C, L-55 5r15 -- VIr _51: i14 Zib-ll eb il L.1.

- . .. 1....I'IK 1 nzTABLE 3 . Decayed L~i~ng Includ'ing MDAs (pCifg)

5,50 Sss5e 5:S'5<et5 p.o..

=r ~

KEY

I Ye11c*., '~hadled BaCckcFUnd = PCSJU'\e ReSL~t1 II-A~s Not Mvet

SNEC CALCULATION SHEETCalculation Number Revision Number I Page Number



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~- SvC 2ifZ ceScasci 2 - 'S33 ta-e~ z -ea _ -1c E_ jje IE aeH b0 332 2 3

2 SSG'S S -.1CS_-'-..S rta e -- I50. S e i i - 0 092 3 la 393 S_ SCIS 1 a22 j-ae r re Sear: ert - Sciitr - S0.zci Q EC CC 5.1 i rpe 2 08i2 is

4 ~Sc I SI1;5 -<a;.e-u-e e.-r '.cr:-' - %'.ctl; I.i ~ .fScdl a 6-t I 1 99

5 S'XS-2zz ':a Ste~im - East Q 22C _ _1229 _. __

6 'cICZ, 1--e e 3eco e 'le - S C i -- , a I ^-cse C 5 -_ 'CC 2 032 2O3

7 S'Ci *-15, - 2 cleer- cr7ectrr;-s fr-ei Rl3

-ae 65 84 U 22 704E ' 'z S :-ot- .-1 35 i-c ce - 3 439~ O 051 3 i '1

TABLE 5 - Mean Percent of Total for Positive Nuclides

SIJEC Sample No Location.Description 11-3 Cs-137 To-al

I ____________- S ;_stace Sc i- SSCS Mzase -clee r _ 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 eC cc _ 10 )00% 10550 %

S IK S Z 1 SE nt3e- 11i e- t 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% 1C00 % 30e7 S-5:23 -\'-127 ~-ce32 Sc eer-- S.,ecTh--c- fi 5' 13% 2 877% 103 40%o

8 -137 98 336 145% 100 0D0%

_a 9 - 76n S 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 TEDE La'i:

Cs-137 Urmit I cs-r3Adsmhajasfise v mLim

SA''PLEli - 27992 dpm100 cm'2 20994 dpm 100 cm-2

SNEC AL

Sample lnpcc Limis Allo'.ed Eeta dpn' 10 Alpha dpil 10Nlsoope FCi g uC,. etc l -, -osal sdpi100 cm^21 dpmitO9 cm'2 mrem y TEDE cm12 Cm'2

I Am 241 0 000%, 27 0G0 0 00 a:'a - C lAm-24t

| C14 | | 0 3.700.000 550 SOC 30 C4 13 Co-60 a_ _ 0 300% 7,100 5 3C C" 03 . 0 Co'. l -60

| CS-137 4136E071 43 51% MOM 27991 64 24.99 2719 5 .' : B -137|5 Eu-152 0 300%Q4 130000 0 00 !0 -l lIl Eu-152| |5C30 120,000.000 21351 N5 Deleclsblc ."' ilHi

j N-63 0 5005% 1.800,000 | 3 Q0 0 00 ilO Detectabie ::-. :Ji-63Pu, 238 000% 30 1 0 00 00 l~qA 5GO Pu-239

Pu239 j __NO_ I 00% 28 000 000 a000 PU-239FU-Z41

SI t-0

2 nj y

S M5C'100 5003%

800PI 7610

0 C1'I vv

l~ s t D e l c l a l e : l l A --: P U .2 4 1

i . _, _ .

64245 25.0 27992 0Ptlaximum

PermissibleCIPnl100 CM'?

C l Z

F a -- SNEC CALCULATION SHEETCalculation Number Revision Number Page Number



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 theDischarge Tunnel from available sample analyses. The effective surface area and volumetric DCGLWsare then determined from the mean percent of applicable samples.

1ll. Data Selection Logic Tables: The radionuclide selection logic and subsequent DCGL calculations areprovided in seven (7) tables. These tables were developed using Microsoft Excel spreadsheetsoftware. Table explanation is as follows.

Table 1: Data Listing - This table, which has been extracted from a larger database, provides a list ofthe 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. Asapplicable, a sample number, sample location/description, radionuclide concentration, analysis dateare provided for each sample. Positive nuclide concentrations are noted with yellow/shadedbackground fields while MDAs are noted in the gray shaded fields.

Table 2: Decayed Listing - This table provides the best overall representation of data selected anddecayed from Table 1. In Table 1 half-life values (days) are listed above each respective nuclidecolumn. Samples are decayed to the date noted above Table I (e.g. January 15, 2004). Positiveresults 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 decayedvalues of positive nuclides selected in Table 2. In addition MDA values have been removed from thistable.

Table 4: Mean Percent of Total for Positive Nuclides - This table provides the calculation methodologyfor determining the relative fractions of the total activity contributed by each radionuclide. From thisinformation the mean, sigma, and mean % of total are calculated. The mean % of total values is usedto calculate the surface gross activity DCGLW per MARSSIM equation 4-4. See Table 6. Note that theCo-60 mean percents were averaged using only samples 1 & 2. In addition, the mean percentscalculated from sample 2 for Am-241, Pu-238, Pu-239 and Ni-63 were not averaged throughout thespreadsheet since there was only one sample where these respective nuclides were positive. Thisresults 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 fordetermining 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 thevolumetric DCGLW per MARSSIM equation 1-14. See Table 7. Note that the Co-60 ratios wereaveraged 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 onesample 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 "EffectiveDCGL Calculation Spreadsheet" as Illustrated In Tables 6 and 7.


E900-03-016 2 Page 13 of _16_Subject


Table 6: Effective DCGL Calculator for Cs-137 (dpml100 cmA2) - This table provides the surfacegross activity DCGLW calculation results from data inputted from Table 4.

Table 7: Effective DCGL Calculator for Cs-137 (in pCilg) - This table provides the surrogatevolumetric 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 thesurface area DCGLW. However, a small portion of the Discharge Tunnel ceiling Class 1 area hasvolumetric contamination. Using the above data selection logic tables the calculated gross activity DCGLWfor surface area is 8,968 dpm/100 cm2. The Cs-137 volumetric DCGLW is 6.52 pCilg. These values wouldbe reduced by 25% as part of SNEC's requirement to apply an administrative limit as required by theLicense Termination Plan (LTP).

TABLE 2 - Decayed Listing IpCifgl

XT '' L - J -_- i~ -a -5: ,-

is jr -. as F-t.42 a gA-t/s- ::-. I C .52 I C c1lC Is

[ I MUTE. OI - I t 99E 3 * p OfF/U Il�t-JC - a kit-..

_____ I � � .--.I 71SD -:16I -~~ i- ..iE,_ __ il£0i, f ---O _I I X42{g

S~t-Orc 24-fi 4~ I > ..- o1 .1-1 __ ._a:.. ___,_;__ _I - --. '

;^ I

"'Er

;ci Sice a- nc~ Z;iCU7:=;ts;t ~- R~est~ I

If- IGa. So E ~ a ~e, 5C-;rtc";,^ = i 5_ Z i

C o 3?




TABLE 3 - Decayed Listing of Positive Nuclides & MDAs Removed (pCig)

S EC Stmpie No LocatiorDesc pion Co-SO Cs-137 | Am-241 Pf-234 Pt2-2.S /l-63 Toaai JpCi~g)1S.C-i- fcace~ ".<- S..... a --":;r.... 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 33 3 t :23 G 30zI C ___ __ L _c_ _ 10 _____

TABLE 4 -Mean Percent of Total for Positive Nuclides

_ S'NEC S-pm~e Tic LOC31ion Descr-iptior oS Cs-137 ;e,-241 PFt-23-23 235 lir-;' Tef_ 0 ___________ 1DIEOC ___

___________5 _ -S-eE- 1 -C 03 _c 10 c__ _ _

6 -- :.-6SC .s:--e~-e SF-.~0 4e r-~5 se S0-~5 -ce *4-C tOO~54 107f~ 575' ^P.05% 0030. ~ 2& .?

TAL 4e - -an Percenrtof 10fo 0Potive N e -

c__SSSC-S___ Loe3:ro3 D503 Pt or Co-SO C-j i .nF - .2410 PO-22S 13~-3 -O c~0 _ _ _ _ _ E'.C6- SS.:S 53te: _________S-CC 1ZiOZf 15ZO 5!V3

-~ ~ S- C - -3_3 03300% 0320% 2 4 C5% 17 1..ea5 -~ e f

1.i a2t: 012DCC 33 oO___i__t__7____ t

105 00% _____

______ ______100 00%1

e3- ~ 4 S-5 OO E-01 I22E-G 57 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.14 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 _ __ _ _

1I00E-001I00E-001 00E-nOSjI 00E-00 _ _ _ _ _

-4 OSE-53 I 00F*05 4

C e I C _ _^ Ce .3 ! -ce -

---- � - 1.1- - -- -11---.1 i __ . . -_ _ I -_

21___ 1 100 00___. , _ , . _ _ , _ _

CO+




Table 6

Effective DCGL Calculator for Cs-137 (dpml100 cmA2) | r7.~': I ci i8 8968 |dpmIloO cmM21 6726 |dpmr100 cm^2

25.0 mremly TEDE LimitiC 137 iUmit -< *,VCs-137 Administistifve-nitt W

SAMPLE 1s DischargeTunnel 1 8807 |dpmlOO cm^2 6605 dPmMOO cm^2

|1SNEC AL~k 75%

IndividualSample 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.143 Co.60 4.03E.03 0.397% 7,100 35;66 0.13 35 .6 W A:{ i. Co-60

DA c137 iAt !, g.g8E.01't. r s .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.1526 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; 63a 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.23910 Pu-241 0.000% 880 0.00 0.00 Hiot Detectable i: Pu-241i Sr.90 _ 0.000% 8.700 0.00 0.00 0.00 A . Sr-90

100.000% 8968 25.0 8843 19Maximum

PermissibledpmllOO cm^2

- -- SNEC CALCULATION SHEETCalculation Number Revision Number Page Number



Table 7

Effective DCGL Calculatorfor Cs-137 (in pCg)I %V"SNECAL%-%. 75% 'ToWAC%*y LMHtDCLw' .,:Admk sftzraUvLmIt I..

I 6.64 JpCilg 1 4.98 gpCug

- SAMlEIi~iKUESSERII es'e

A 55L25.0 mromiy TMO Lint

I Ce37Lknflt f~0 I Ca-13T AmhiisutrewveLmt

1 6.52 1CI! 1 4.89 pCilq

I

II

If

Sample lnptn(pCVQ- uck % 25mremlyTcDE A.A$owedpClgtor Vi vtue Checked from

Isotope of Total.efc. % of Total itmts (pCV;) 25 mresq TEDE Cohmn A or t

Am-241 t0.001 _0.122% 9.9 ___ 0.01 - S 0.01C-8-.1 t 0.000% 2.0 0.00 00Co _ 0.041 - 0.401% 3 '3.5 _003 0 03Cs-137 __ _ 1000 _ 98.178% 6.6 _6.52 __ , c6 E-Eu.152 0000% 10.1 3 _ 0.00 0 0.00H-3__ 000% 132 a 000 _0 00llt-63 _ _ 0123 _ 1.208% 747oa

Pu.238 0.0004 0.035% 1.t 0.00 ______ 000Pu-239 0.0006.0- -. 0057% 1-.6- 00 0000

Pu.241 - 0.000% 86 __ . . 0.00 0_00Sr-90 0_000_ 1.2 ____ 00 0 Co

1.02E-00 100.000% 6.64 183.53 6.64

This Sanigil Imremy TEDE Pjwhj ;

0.00 z00,u

0 00

3.79 lg

' 000 ~--3.835 0 2

To Use This Iformadron.Simple hWut Unlits ust Be in

pC~g not % of Total.

C-14Co.60Cs.137Eu.152H.3NI-S3Pu.238Pu.239PU.241Sr.90

Maxdmum Permissible Ma1dmumPCI1g Permissible pCig

a2s mromlwl 1 (4 mremiyl l

appendix c scm survey design revision 1 · 6.1 attachment 1, survey design checklist. 6.2...

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