ML19007A043

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RS-TD-313196-005, Rev. 0, LACBWR Open Air Demolition Limits.
ML19007A043
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 11/23/2015
From: Farr H
Energy Solutions
To:
Office of Nuclear Material Safety and Safeguards
M VAALER DUWP
Shared Package
ML19007A031 List:
References
RS-TD-313196-005, Rev 0
Download: ML19007A043 (116)
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RS-TD-313196-005 Revision 0 Summary of Changes in this Revision:

  • Rev. 0 -Initial issuance.

Page 2 of 116

RS-TD-313196-005 Revision 0 Table of Contents

1. PURPOSE ............................................................................................................................... 5
2. DISCUSSION OR BACKGROUND ..................................................................................... 5 2.1. Off-Site Dose Impact Method ............................................................................................. 5 2.2. Radiological Objectives for Open Air Demolition .............................................................. 6 2.3. Radiological Control Indicator Method and Pre-Test Values ............................................. 6
3. CALCULATIONS .................................................................................................................. 8 3.1. Summary of Connecticut Yankee Removable Contamination Limit Evaluation ................ 8 3.2. Connecticut Yankee Concrete Demolition Test Results ..................................................... 8 3.3. Summary and Conclusions from Connecticut Yankee Concrete Demolition Test Results ........................................................................................................................ 28 3.4. LACBWR Concrete Gamma Spectroscopy Results .......................................................... 31
4. CONCLUSION..................................................................................................................... 32
5. REFERENCES ..................................................................................................................... 33
6. ATTACHMENTS................................................................................................................. 34 6.1. Attachment 1.A - CY Test 1 B Charging Pump Cubicle Survey ................................... 35 6.2. Attachment 1.B - CY Test 1 B Charging Pump Cubicle Sample Data .......................... 39 6.3. Attachment 2 - CY Test 2 B Charging Pump Cubicle Survey and Sample ................... 42 6.4. Attachment 3.A - CY Test 3 B Charging Pump Cubicle Survey ................................... 50 6.5. Attachment 3.B - CY Test 3 B Charging Pump Cubicle Sample Data .......................... 54 6.6. Attachment 4.A - CY Tests 4a and 4b B Charging Pump Cubicle Survey .................... 62 6.7. Attachment 4.B - CY Tests 4a and 4b B Charging Pump Cubicle Sample Data ........... 69 6.8. Attachment 5.A - CY Tests 5 Metering Pump Cubicle Survey and Sample Data ............ 87 6.9. Attachment 5.B - CY Tests 5 Metering Pump Cubicle Survey and Sample Data............. 93 6.10. Attachment 6.A - CY Tests 6 Metering Pump Cubicle Survey ....................................... 101 6.11. Attachment 6.B - CY Tests 6 Metering Pump Cubicle Sample Data .............................. 107 6.12. Attachment 7 - MicroShield Model Embedded Cs-137 for Half Inch Thick Concrete Source ............................................................................................................... 115 Page 3 of 116

RS-TD-313196-005 Revision 0 List of Tables Table 1 - Summary of Offsite Dose Evaluations ...................................................................................... 5 Table 2 - Original Connecticut Yankee Contractual Radiological Control Indicators ............................ 7 Table 3 - Test 1 Pre-remediation Survey Data ....................................................................................... 10 Table 4 - Test 1 Post Remediation Survey Data ..................................................................................... 11 Table 5 - Test 1 Debris Gamma Spectroscopy Results and Scaled Air Sample Results ........................ 11 Table 6 - Test 2 Pre-remediation Survey Data ....................................................................................... 12 Table 7 - Test 2 Post-remediation Survey Data ...................................................................................... 13 Table 8 - Test 2 Debris Gamma Spectroscopy Results and Scaled Air Sample Results ........................ 14 Table 9 - Test 3 Pre-remediation Survey Data ....................................................................................... 14 Table 10 - Test 3 Post Remediation Survey Data ................................................................................... 15 Table 11 - Test 3 Debris Gamma Spectroscopy Results and Scaled Air Sample Results ...................... 16 Table 12 - Test 4a Pre-Remediation Survey ........................................................................................... 17 Table 13 - Test 4a Post Remediation Survey Data ................................................................................. 18 Table 14 - Test 4a Masslin Debris Gamma Spectroscopy Results and Scaled Air Sample Results ...... 19 Table 15 - Test 4a Debris Gamma Spectroscopy Results and Scaled Air Sample Results .................... 19 Table 16 - Test 4b Pre Remediation Survey Data .................................................................................. 19 Table 17- Test 4b Post Remediation Survey Data .................................................................................. 20 Table 18 - Test 4b Maslin Gamma Spectroscopy Results ...................................................................... 21 Table 19 - Test 5 Pre-remediation Survey Data ..................................................................................... 22 Table 20 - Test 5 Post Remediation Survey ........................................................................................... 23 Table 21 - Test 5 Air Sample Data and Debris Gamma Spectroscopy Results ...................................... 25 Table 22 - Test 6 Pre-remediation Survey Data ..................................................................................... 25 Table 23 - Test 6 Post Remediation Survey Data ................................................................................... 26 Table 24 - Test 6 Air Sample Data and Debris Gamma Spectroscopy Results ...................................... 28 Table 25 - Summary of CY Demolition Test Air Sample Results ......................................................... 28 Table 26 - Summary of Test Result Maximum Dose Rates and Maximum Beta/Gamma Removable Contamination ................................................................................................... 30 Table 27 - Summary of Test Result Average Dose Rates and Average Cubicle Beta/Gamma Removable Contamination ................................................................................................... 30 Table 28 - Summary of Post Remediation Gamma Spectroscopy Results ............................................. 31 Table 29 - La Crosse Highest Concrete Core Sample and Average ....................................................... 31 Table 30 - MicroShield Dose Rate Model Parameters ........................................................................... 32 Table 31 - Recommended Open Air Demolition Limits........................................................................ 33 Page 4 of 116

RS-TD-313196-005 Revision 0

1. PURPOSE This Technical Support Document (TSD) provides the basis for the Open Air demolition Radiological Control Indicators that are applied to buildings and structures for open air demolition. These indicators are designations used to characterize the acceptable removable contamination and concrete contact deep dose equivalent radiation levels that are acceptable for open air demolition. Structural materials other than concrete, such as metals, do not tend to sorb radionuclides and are not evaluated for acceptable embedded total contamination dose rates. Activated materials are also not evaluated under this TSD and should be evaluated and modeled separately using the radiological mix of nuclides present. The radiological control indicators evaluated in this TSD will ensure that open air demolition can proceed without creating a Contaminated Area, requiring radiological PPE, or resulting in environmentally significant airborne radioactivity releases.
2. DISCUSSION OR BACKGROUND 2.1. Off-Site Dose Impact Method Several decommissioning facilities established open air demolition criteria based upon the offsite dose impact from airborne radioactivity released during demolition. The facilities (1) (2) (3) used a conventional nuclear industry approach for safety related bounding calculations to establish limits for open demolition. This approach calculates the acceptable levels of fixed and removable contamination based upon re-suspension factors and site specific ground release dispersion models (X/Q). The limits at these facilities are based upon the calculated member of the public dose at the site boundary using Off Site Dose Calculation Manual (ODCM) (4) methodologies for a ground level airborne radioactivity release. As shown in Table 1 this approach results in relatively high levels of removable contamination being acceptable for open air demolition with minor off-site dose consequences.

Table 1 - Summary of Offsite Dose Evaluations Removable Contamination Total Contamination Offsite Dose Facility Level Level (mrem) Control Criteria Summary

> 25,000 dpm/100 cm2 removable of 250,000 dpm/100 cm2 total requires contamination control measure (e.g.,

1.7E-3 fixative, local ventilation, enclosures)

SONGS Unit 1 N/A 1.5E+6 dpm/100 cm2 instantaneous release Air samples not to exceed 0.05 DAC beta/gamma or >MDA alpha. Personnel contamination controls below 25,000 dpm/100 cm2 required.

6.66E-2 entire decommissioning Could result in up to 4600 dpm/100 cm2 2 2 based upon 5000 dpm/100 cm 500,000 dpm/100 cm deposition within 50 feet of demolition estimated surface Maine Yankee beta/gamma 20 beta/gamma 100 with 10% plate out. May require layer of area of buildings dpm/100 cm2 alpha dpm/100 cm2 alpha soil to be removed for FSS. Will have to be and average managed for equipment release.

contamination levels Maintain work zone air concentrations less Average < 5000 2E-3 mrem/yr than 0.25 DAC to maintain member of Yankee Rowe dpm/100 cm2 max organ public dose below 0.2 mrem/yr. No other limits specified.

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RS-TD-313196-005 Revision 0 Similar offsite dose evaluations of airborne radioactivity ground releases were performed at Connecticut Yankee (CY) as documented in reference (5). This TSD evaluated the offsite dose consequences of an instantaneous release of a 2000 DAC Am-241 source term due to a HEPA filter failure at CY. The calculated member of the public dose at the unrestricted area boundary was 1.77 mrem for a release of this magnitude. Similarly the LACBWR Post Shutdown Decommissioning Activity Report (PSDAR)

Accident Analysis (6) evaluated a series of accidents with potential for source term releases to the environment. These calculations assumed that 30% of the remaining estimated approximately 1.175 Ci of radioactive material present on plant surfaces in 2014 was released (e.g., 0.35 Ci, 7.83E+11 dpm) through the plant stack as airborne radioactivity. Resulting doses at 50, 70 and 120 meters were calculated. The maximum dose was 65 mrem at 50 meters. (6) Thus, demolition and sizing of contaminated structures and materials can be performed at high contamination levels without significantly increasing the radiation exposure of members of the public at the site boundary.

2.2. Radiological Objectives for Open Air Demolition Other objectives, in addition to the member of the public dose at the site boundary, should be considered when establishing Radiological Control Indicators for open air demolition of structures. The off-site dose based approach does not address additional considerations such as:

Allowing open air demolition without instituting Contaminated Area controls such as, posting, clearance, and protective clothing controls in outside areas.

Impact of the liberated source term on soil concentrations (Derived Concentration Guideline Levels - DCGLs) required for License Termination.

Ensuring radioactivity concentrations in high conductivity, high pH demolition water remain low enough to release without use of demineralizers. Groundwater intrusion during demolition at Connecticut Yankee required large quantities of water to be processed and released as part of the demolition process due to groundwater intrusion.

Given the above considerations, the objectives of the open air demolition limits are the following:

Ensure ground level airborne radioactivity levels and off-site dose consequences remain ALARA and within regulatory limits.

Ensure demolition liquid concentrations remain at levels which can be collected, processed and released using plant water treatment systems and discharge points.

Minimize the spread on contamination within the site boundary such that there is not a significant effect on groundwater or the scope of soil remediation required for License Termination.

Ensure open air demolition activities can be conducted using conventional demolition techniques with minimal radiological restrictions or controls (e.g., without area, equipment or personnel contamination controls).

2.3. Radiological Control Indicator Method and Pre-Test Values Initial pre-test Radiological Control Indicators (RCI) similar to those at other facilities were developed at Connecticut Yankee as part of the request for proposals and contract agreements with the Decommissioning Operation Contractor (DOC). The RCIs provided the contractual basis for radiologically acceptable levels for various phases and types of structure demolition. These indicators Page 6 of 116

RS-TD-313196-005 Revision 0 were used to clearly specify contractual requirements for the demolition of buildings with regards to acceptable levels of fixed and removable contamination. The CY RCIs were defined as the following:

R1 was designated for structures where the radiological contamination is indistinguishable from background. This designation was only applied to structures outside a Radiologically Controlled Area (RCA) of the facility. Prior to Release of a structure for R1 demolition, an Unconditional Release Survey (URS) was completed. The URS provides data to demonstrate that secondary side structures are suitable for unconditional release from the Site, (i.e., free released as clean materials). This material is designated as Secondary Side Waste. For structures designated as R1, no radiological controls were required during demolition.

R2 was designated for structures that reside within the RCA where the radiological contamination is greater than the R1 levels, but less than the limits specified as being suitable for open air demolition (R2Open Air) or interior demolition (R2Interior). When the structure is scheduled for open air exterior demolition, R2Open Air controls are instituted mainly to protect the environment and public whereas R2Interior controls are instituted to protect the worker and to limit the potential for spread of contamination to other interior areas. Prior to structure turnover for R2 demolition, a Contamination Verification Survey (CVS) was completed to verify that pre-demolition contamination levels of primary side structures were below the limits established for open air or interior demolition. The resulting demolition debris was designated as Primary Side Waste. For structures designated as R2, limited radiological controls were required, including but not limited to intermittent health physics coverage, misting, air sampling, periodic surveys, personnel protective equipment and personnel contamination monitoring upon exiting the area.

R3 was designated for structures, or portions of structures, within the RCA where the radiological conditions exceed the R2Open Air or R2Interior criteria. This material was also designated as Primary Side Waste. For structures designated as R3, significant radiological controls were required. These included but were not limited to controls such as constant health physics coverage, application of surface fixatives, use of tents and HEPA ventilation, more intense air and surface sampling and personnel protective equipment such as respirators.

Table 2 shows the original pre-test radiological criteria for fixed and removable contamination levels adopted for demolition at CY. These values were based upon regulatory requirements for R1 structures (e.g., no detectable licensed material for unrestricted release of materials) and estimates of the potential radiological consequences and controls for the demolition. Similar to other facilities, they allowed relatively high R2Open Air contamination levels on structures.

Table 2 - Original Connecticut Yankee Contractual Radiological Control Indicators Total Surface Demolition Contamination Loose Surface Contamination Category / /

R1 Non Detectable Non Detectable Non Detectable 2 2 500,000 dpm/100cm 1000 dpm/100cm Max 20 dpm/100cm2 Max R2 Open Air Max 50,000 dpm/100cm2 Avg 10,000 dpm/100cm2 Max 200 dpm/100cm2 Max Interior R2 10 mR/h Contact

>R2 and <100 mR/h >R2 and <100,000 >R2 and <5000 R3 Contact dpm/100cm2 Max dpm/100cm2 Max Page 7 of 116

RS-TD-313196-005 Revision 0 In 2004 Connecticut Yankee released the Decommissioning Operations Contractor (DOC) and resumed direct management of the decommissioning. Thus the contractual RCI criteria in Table 2 were no longer relevant. However, radiological criteria for building demolition still needed to be established. To ensure the criteria in Table 2 would meet the open air demolition objectives, testing was performed on concrete surfaces in the Primary Auxiliary Building (PAB) to determine empirically the proper R2Open Air fixed contamination levels and the Table 2 removable contamination levels were reevaluated. The objective of the test was to determine the appropriate contact count rate or dose rate on concrete at which the concrete could be demolished or sized and meet the four objectives summarized at the end in Section 2.2 in this document. The results of the evaluation and tests are summarized in Section 3.3 of this TD. The supporting data and surveys from CY Technical Support Document (7) are provided as attachments to this TD.

3. CALCULATIONS 3.1. Summary of Connecticut Yankee Removable Contamination Limit Evaluation During plant operations and throughout the decommissioning all of the open air demolition objectives in Section 2.2 were routinely met by maintaining the loose surface contamination levels below 1000 dpm/100 cm2 beta/gamma and 20 dpm/100 cm2 alpha on items stored or transported in outside areas.

Any materials released off-site were surveyed to less than detectable levels as defined by Nuclear Regulatory Commission guidance. The required sensitivity levels for unrestricted release are no detectable contamination with minimum detectable activities under 5000 dpm/100 cm2 beta/gamma total, 1000 dpm/100 cm2 beta/gamma removable and 20 dpm/100 cm2 alpha removable.

In practice, containers, tools, equipment were decontaminated down to less than detectable contamination levels that range from 30 dpm/100 cm2 to several hundred dpm/100 cm2 depending on the survey method, instrumentation, and background before they are released from buildings. The impracticality of instituting Contaminated Area Controls in outside areas, in addition to the regulatory scrutiny that such controls would illicit, is simply outweighed by the relative ease with which removable contamination can be removed or fixed. Removable contamination is easily locked down by applying a fixative such as latex paint prior to demolition. It was determined that there was already sufficient precedent and experience to justify use of these practices as acceptable targets for R2Open Air removable contamination limits. To meet the above objectives removable beta gamma contamination limits for open air demolition should not exceed 1000 dpm/100 cm2 and should on average be less than 300 dpm100 cm2. The removable alpha contamination should not exceed 20 dpm/100 cm2.

3.2. Connecticut Yankee Concrete Demolition Test Results The remaining question was what levels of fixed contamination would be acceptable to maintain work area loose surface contamination levels below 300 dpm/100 cm2 beta/gamma and 20 dpm/100 cm2 alpha during demolition. Maintaining loose surface contamination levels within acceptable ranges depends upon the amount of loose radioactive material present on the structure at the time of demolition and the amount of radioactive material that is liberated during the demolition process as concrete dust.

Conventional demolition uses large excavators with hydraulic rams to rubbelize concrete and mechanical or thermal methods to cut metallic materials. Embedded surficial fixed contamination becomes loose as part of the dust generated when concrete is fractured or cut by the demolition equipment. Typically, the vast majority of the contamination in the concrete surfaces of building interiors is embedded in the upper most portion, near the surface. Most of the concrete structure and rebar is not contaminated and therefore the fracture dust and metallic dust or cutting smoke is clean.

Dust generated fracturing the contaminated surface is diluted by uncontaminated dust from fracturing of Page 8 of 116

RS-TD-313196-005 Revision 0 subsurface material. To develop an R2Open Air fixed contamination limit for concrete, the relationship between fixed contamination levels as indicated by surface dose rates and the resulting loose surface contamination from the fracture dust liberated was evaluated. Tests were conducted at Connecticut Yankee to determine this correlation empirically, rather than by calculation.

In order to determine the appropriate R2Open Air fixed contamination criteria for concrete a series of in-situ tests were conducted in the Primary Auxiliary Building (PAB) at CY. The PAB was chosen because it had a series of cubicles with concrete floors exhibiting a range of contact dose rates which varied from as low as no detectable radiation levels above background to as high as 20 to 30 mR/hr contact. The cubicles could be decontaminated to low pre-test loose surface activity levels then sealed off to contain dust and contamination generated during demolition of concrete test areas of various dose rates, then surveyed after the test to evaluate the resulting contamination levels. The objective of these tests was to rubbelize concrete surfaces with different contact dose rates in the absence of engineering controls or dust suppression methods and monitor the airborne radioactivity and removable contamination levels generated.

The tests were performed by pre-surveying the area to determine average contact dose rates in order to select a test location with the appropriate contact levels to be evaluated. The cubicle was then decontaminated or locked down to provide low levels of initial removable contamination and sealed off using clear poly with no negative pressure ventilation applied. This provided a static environment in which airborne radioactivity levels and removable contamination levels resulting directly from the demolition could be evaluated. A test location was then remediated using needle guns, or jack hammers while an air sample was running. After the remediation was completed, the test area and cubicle contamination levels were assessed by smear survey and large area swipes (LAS). The test area was also re-surveyed to determine the post remediation contact dose rates and evaluate the amount of source term removed.

The first test area was in B Charging Pump Cubicle. The Test 1 surveys, air samples, and demolition debris gamma spectroscopy results from reference (7) are provided in Attachment 1. The pre-remediation survey was conducted on 3/3/04 at 16:00. The maximum pre-remediation test area contact dose rate was 1.5 mR/hr and averaged 0.66 mR/hr. Table 3 summarizes the pre-test data from this survey.

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RS-TD-313196-005 Revision 0 Table 3 - Test 1 Pre-remediation Survey Data Test Area Test Area Removable Contact Cubicle Removable Outside Test Area beta/gamma alpha beta/gamma Alpha Smear dpm/100 dpm/100 LAS Smear dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr Cpm Location cm2 cm2 ccpm 31 < MDA < MDA 1.5 8,000 2 62.17 < MDA 32 < MDA < MDA 0.7 14,000 4 122.84 < MDA 33 < MDA < MDA 0.6 13,000 23 62.17 < MDA 34 79.5 < MDA 0.7 40,000 All Other <MDA < MDA 35 < MDA < MDA 0.9 28,000 36 < MDA < MDA 0.8 28,000 37 105.51 < MDA 0.4 38 < MDA < MDA 0.3 39 62.17 < MDA 0.3 A NDA 40 62.17 < MDA 0.4 B NDA 41 < MDA < MDA C NDA 42 < MDA < MDA 43 < MDA < MDA Total Test Area Smears 13 Avg Avg Total Outside Test Area Smears 30 23.8 beta/gamma Smear Average 0 0.66 21,833 beta/gamma Smear Average 0.97 Total Cubicle Smears 43 Total Cubicle Average 12.94 Note: Blank Entries have no corresponding data for that column. Alphabetical locations are LAS locations. NDA =

No Detectable Activity, MDA = Minimum Detectable Activity Contact Dose Rate and Smear are not at same locations or at the smear locations in the test area.

The test area was remediated by chipping concrete using a jack hammer and needle guns in the sealed cubicle. After the surface concrete was removed a post remediation survey was conducted to establish test area contact dose rates and contamination levels in the cubicle. The CY post remediation survey for Test 1 was conducted on 3/4/04 at 12:00 P.M. A copy is provided in Attachment 1. The post remediation survey data is summarized in Table 4 and shows a drop in the maximum contact dose rates from 1.5 mR/hr to 0.7 mR/hr with the average dose rate dropping from 0.66 mR/hr to 0.43 mR/hr. The smear survey data shows that removable contamination levels remained well below 1000 dpm/100 cm2 in the cubicle with a maximum level of 253 dpm/100 cm2. LAS survey results increased from pre-remediation levels of No Detectable Activity (NDA) to up to 3000 ccpm in the cubicle. In addition, surveys of the remediation tooling, booties and gloves showed no detectable removable activity.

Table 5 provides the gamma spectroscopy results from samples of remediation dust and debris, the gross beta air sample result and the scaled Effluent Concentration. Air sample results are also provided in Attachment 1. They indicated very low levels of gross beta/gamma airborne radioactivity at 8.66E-12

µCi/cc or 0.043 DAC. Gamma spectroscopy of a sample of the fines and concrete chips generated during the remediation identified Co-60, Cs-134 and Cs-137 in the concrete as seen in Attachment 1.

The gross beta/gamma activity on the air sample was scaled to the radionuclide fraction in the debris and compared to the 10 CFR 20 Appendix B Table 2 Effluent Concentrations for Air as shown in Table 5.

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RS-TD-313196-005 Revision 0 This demonstrated that even though the remediation was performed in a tented cubicle with no dust suppression, ventilation or engineering controls, the resulting airborne radioactivity was well below the 10 CFR 20 Appendix B, Table 2, Effluent Concentrations.

Table 4 - Test 1 Post Remediation Survey Data Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr Cpm Location cm2 cm2 ccpm 21 53.5 < MDA 0.2 5,000 10 62.17 < MDA 22 < MDA < MDA 0.3 1,000 11 235.53 < MDA All 23 < MDA < MDA 0.6 5,000 Other <MDA < MDA 24 < MDA < MDA 0.7 8,000 25 < MDA < MDA 0.5 10,000 26 < MDA < MDA 0.3 15,000 A 3000 27 < MDA < MDA 80,000 B 3000 28 < MDA < MDA 25,000 C 3000 29 131.51 < MDA 10,000 30 < MDA < MDA Total Test Area Smears 10 Avg Avg Total Outside Test Area Smears 20 Beta/gamma Smear Average 18.50 0.43 17,667 Beta/gamma Smear Average 14.89 Total Cubicle Smears 30 Total Cubicle Average 16.09 Note: Blank Entries have no corresponding data for that column. Alphabetical locations are LAS locations. NDA

= No Detectable Activity, MDA = Minimum Detectable Activity Contact Dose Rate and Smear are not at same locations or at the smear locations in the test area.

Table 5 - Test 1 Debris Gamma Spectroscopy Results and Scaled Air Sample Results Scaled Weighted Weighted Air DAC Eff. EC Fraction of Sample DAC Fraction Conc. Fraction Nuclide µCi/gm Total µCi/cc µCi/cc (DACf) µCi/cc (ECf)

Co-60 2.77E-05 2.56E-02 2.21E-13 1.00E-08 2.21E-05 5.00E-11 4.43E-03 Cs-134 1.01E-05 9.35E-03 8.09E-14 4.00E-08 2.02E-06 2.00E-10 4.05E-04 Cs-137 1.04E-03 9.65E-01 8.36E-12 6.00E-08 1.39E-04 2.00E-10 4.18E-02 Total 1.08E-03 1.00E+00 8.66E-12 N/A 1.63E-04 N/A 4.66E-02 Air Sample Result 8.66E-12 µCi/cc A second area in Charging Pump Cubicle B with higher contact dose rates was selected for the next test.

This area had contact dose rates in the 1 to 2 mR/hr range with an average contact dose rate of Page 11 of 116

RS-TD-313196-005 Revision 0 approximately 1.4 mR/hr. The pre-remediation and post remediation surveys as well as the gross air sample results and debris gamma spectroscopy results are provided in Attachment 2.

The Test 2 pre-remediation survey was conducted on 3/8/04 at 11:00 A.M. The data for the survey area is shown in Table 6. There was no detectable removable contamination in the cubicle prior to Test 2.

Table 6 - Test 2 Pre-remediation Survey Data Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr cpm Location cm2 cm2 ccpm 1 < MDA < MDA 1.5 50,000 10 < MDA < MDA 2 < MDA < MDA 1.2 16,000 11 < MDA < MDA 3 < MDA < MDA 1.7 25,000 12 < MDA < MDA 4 < MDA < MDA 1.9 15,000 13 < MDA < MDA 5 < MDA < MDA 1.4 20,000 14 < MDA < MDA 6 < MDA < MDA 1.2 75,000 15 < MDA < MDA 7 < MDA < MDA 1.7 75,000 16 < MDA < MDA 8 < MDA < MDA 2 30,000 9 < MDA < MDA 1.2 10,000 A 500 1.2 B 500 1.4 C 200 1.5 D 200 1.5 E 200 1.2 F 200 1

1.4 1.5 1

1.5 1

1.7 1

2 Total Test Area Smears 9 Avg Avg Total Outside Test Area Smears 10

<MD Beta/gamma Smear Average <MDA 1.42 35,111 Beta/gamma Smear Average A Total Cubicle Smears 19

<MD Total Cubicle Average A Note: Blank Entries have no corresponding data for that column. Alphabetical locations are LAS locations.

NDA = No Detectable Activity, MDA = Minimum Detectable Activity Contact Dose Rate and Smear are not at same locations or at the smear locations in the test area.

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RS-TD-313196-005 Revision 0 The Test 2 Post Remediation Survey was conducted on 3/9/04 at 09:00. The post remediation surveys are provided in Attachment 2. The data is summarized in Table 7.

Table 7 - Test 2 Post-remediation Survey Data Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr cpm Location cm2 cm2 ccpm 11 < MDA < MDA 0.3 18,000 2 200.86 < MDA 12 < MDA < MDA 0.3 6,000 3 192.19 <MDA 13 < MDA < MDA 0.5 47,000 4 235.53 <MDA 16,000 5 261.53 <MDA 6 88.17 <MDA 8 103.51 <MDA 9 183.52 <MDA E 200 10 96.89 <MDA 14 <MDA <MDA 15 88.17 <MDA 16 96.84 <MDA 17 131.51 <MDA 18 62.17 <MDA All Other <MDA <MDA A 100 B 150 C 150 D 100 E 200 Total Test Area Smears 3 Avg Avg Total Outside Test Area Smears 28

<MD Beta/gamma Smear Average A 0.37 21,750 Beta/gamma Smear Average 62.17 Total Cubicle Smears 31 Total Cubicle Average 56.16 Note: Blank Entries have no corresponding data for that column. Alphabetical locations are LAS locations.

NDA = No Detectable Activity, MDA = Minimum Detectable Activity Contact Dose Rate and Smear are not at same locations or at the smear locations in the test area.

The maximum contact dose rate in the test area dropped from 2 mR/hr to 0.5 mR/hr. The average dose rate dropped from. 1.4 mR/hr to 0.37 mR/hr. It can be seen by the comparing post remediation removable contamination levels in Table 7 to the pre-remediation levels in Table 6, that there was an overall increase in the extent and levels of contamination in the cubicle. However, the contamination levels remained below the 1000 dpm/100 cm2 loose surface beta/gamma objective with a maximum of Page 13 of 116

RS-TD-313196-005 Revision 0 262 dpm/100 cm2. As seen in Attachment 2, the air sample during the remediation was 2.47E-11 µCi/cc or 0.124 DAC. A LAS was analyzed by gamma spectroscopy to provide the radionuclide profile of the concrete debris. Table 8 shows the anticipated effluent concentration for this air sample is 0.14 effluent concentrations. This is higher than the Test 1 air sample results but well below ground release concentrations that would result in any significant dose at the site boundary. There would be no significant off-site dose consequences from releases of this magnitude.

Table 8 - Test 2 Debris Gamma Spectroscopy Results and Scaled Air Sample Results Scaled Weighted Air DAC EC dpm per Fraction of Sample DAC Fraction Eff. Conc Weighted Nuclide sample Total µCi/cc µCi/cc (DACf) µCi/cc Fraction Co-60 2.15E+02 3.91E-02 9.65E-13 1.00E-08 9.65E-05 5.00E-11 1.93E-02 Cs-134 5.89E+01 1.07E-02 2.64E-13 4.00E-08 6.60E-06 2.00E-10 1.32E-03 Cs-137 5.24E+03 9.50E-01 2.35E-11 6.00E-08 3.91E-04 2.00E-10 1.17E-01 Total 5.51E+03 1.00E+00 2.47E-11 N/A 4.94E-04 4.50E-10 1.38E-01 Air Sample Result 2.47E-11 µCi/cc Test 3 was conducted on an area with average contact dose rates of approximately 1.8 mR/hr with a maximum contact dose rate of 2.5 mR/hr. As shown in the Test 3 surveys provided in Attachment 3, the cubicle had low removable contamination levels on 3/9/04 at 15:30 prior to the test. The pre-remediation contact dose rates are the ones at the left hand side of the test area shown in survey 04-1758 conducted on 3/10/04 at 10:00. This data is summarized in Table 9.

Table 9 - Test 3 Pre-remediation Survey Data Test Area Test Area Removable Contact Cubicle Removable alpha beta/gamma alpha Locatio beta/gamma dpm/100 LAS dpm/100 dpm/100 LAS n dpm/100 cm2 cm2 ccpm mR/hr cpm Location cm2 cm2 ccpm 12 62.4 <MDA 1.2 10,000 3 69 <MDA 13 52.9 <MDA 2.5 15,000 10 52.9 <MDA 14 55.3 <MDA 1.4 >50000 16 60 <MDA All A 225 2.0 >50000 Others <MDA <MDA B 155 C 225 D 175 Total Test Area Smears 3 Avg Avg Total Outside Test Area Smears 27 Beta/gamma Smear Average 56.87 1.78 20,833 Beta/gamma Smear Average 6.74 Total Cubicle Smears 30 Total Cubicle Average 11.75 Note: Blank Entries have no corresponding data for that column. Alphabetical locations are LAS locations.

NDA = No Detectable Activity, MDA = Minimum Detectable Activity Contact Dose Rate and Smear are not at same locations or at the smear locations in the test area.

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RS-TD-313196-005 Revision 0 The post remediation survey was conducted on 3/10/04 at 15:30. The post remediation survey results are also provided in Attachment 3 and summarized in Table 10. The maximum contact dose rate dropped from 2.5 mR/hr to 1.9 mR/hr and the average dropped from 1.8 mR/hr to 1.17 mR/hr. These results show similar removable contamination levels to those in Test 2 (Table 7) with a post remediation maximum of 200 dpm/100 cm2.

Table 10 - Test 3 Post Remediation Survey Data Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr cpm Location cm2 cm2 ccpm 1.3 10,000 4 200.2 < MDA No Smears taken in test area 1.2 9,000 5 86.2 < MDA 1 2,000 6 71.9 < MDA 1.9 4,000 8 90.9 < MDA 1 2,500 9 171.7 < MDA 1 8,000 10 79.8 < MDA 0.8 25,000 12 131.3 < MDA 7,000 13 163.6 < MDA All 1,000 Others <MDA < MDA 9,000 A 125 B 125 C 200 D 175 Total Test Area Smears 0 Avg Avg Total Outside Test Area Smears 34 Beta/gamma Smear Average 0.00 1.17 7,750 Beta/gamma Smear Average 29.28 Total Cubicle Smears 34 Total Cubicle Average 29.28 Note: Blank Entries have no corresponding data for that column. Alphabetical locations are LAS locations.

NDA = No Detectable Activity, MDA = Minimum Detectable Activity Contact Dose Rate and Smear are not at same locations or at the smear locations in the test area.

Page 15 of 116

RS-TD-313196-005 Revision 0 As shown in Table 11, a composite sample of the concrete chips from this area was obtained on 3/10/04 at 14:00. The sample was analyzed by gamma spectroscopy and showed Co-60, Cs-134, Cs-137 and Am-241. At CY Am-241 was approximately 50% of the alpha emitting transuranic (TRU) source term in all waste streams. Therefore a correction factor of 2 is applied to the Am-241 results when calculating the DAC and effluent concentration fractions. The airborne radioactivity was significantly higher than in Tests 1 and 2, but still less than 0.035 DAC. The air sample showed 1.114E-10 µCi/cc of Cs-137. The beta (Co-60, Cs-134, Cs-137) to alpha (2 X Am-241) ratio was 1,188 to 1. Well over the 50:1 beta/gamma to alpha ratio at which alpha monitoring is required for personnel and equipment exiting the area. When this Cs-137 level is scaled to the concrete chip sample results, the Effluent Concentration fraction (ECf) is 5.56, exceeding the 10 CFR 20 Appendix B Effluent Concentration Limit for Air but well below a value that would result in significant exposures at the site boundary when the ground release dispersion coefficient (X/Q) is considered.. Without the transuranic source term the ECf was 6.46E-01.

Table 11 - Test 3 Debris Gamma Spectroscopy Results and Scaled Air Sample Results Scaled Air Weighted EC Fraction Sample DAC DAC Eff. Conc Weighted Nuclide µCi/gm of Total µCi/cc µCi/cc Fraction µCi/cc Fraction Co-60 1.13E-04 3.72E-02 4.14E-12 1.00E-08 4.14E-04 5.00E-11 8.28E-02 Cs-134 3.54E-05 1.16E-02 1.30E-12 4.00E-08 3.24E-05 2.00E-10 6.49E-03 Cs-137 3.04E-03 1.00E+00 1.11E-10 6.00E-08 1.86E-03 2.00E-10 5.57E-01 Am-241/TRU 1.34E-06 4.41E-04 4.92E-14 3.00E-12 3.28E-02 2.00E-14 4.92E+00 Total 3.19E-03 1.17E-10 3.51E-02 5.56E+00 Air Sample Result 1.11E-10 µCi/cc Cs-137 Gross Beta 2.04E-10 Total includes radon daughters Am-241/TRU Correction Factor 2 Beta to Alpha Ratio 1,188 Test 4 was also conducted in B Charging Pump Cubicle and was intended to test the contamination and airborne radioactivity levels resulting from demolition of concrete reading up to 5 mR/hr on contact. There were two attempts to perform this test, 4a and 4b, but neither test was valid because dose rates increased as each of test areas were remediated due to embedded piping in the floor under the test area. As seen in the surveys provided in Attachment 4 and the test 4a and 4b pre and post remediation survey summary tables below the maximum and average dose rates increased as concrete was removed. It was therefore not possible to quantify the dose rate change on the concrete removed.

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RS-TD-313196-005 Revision 0 Table 12 - Test 4a Pre-Remediation Survey Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr cpm Location cm2 cm2 ccpm 7 50.5 < MDA 4.5 50,000 1 205 < MDA 8 < MDA < MDA 5 25,000 2 269.1 < MDA 9 < MDA < MDA 3.5 4,000 3 285.7 < MDA 10 55.3 < MDA 6 50,000 4 295.2 < MDA 3 45,000 5 52.9 < MDA 5 50,000 6 52.4 < MDA 3.2 45,000 11 71.9 < MDA 1.3 50,000 13 55.3 < MDA 3.5 15 62.4 < MDA 4.5 18 52.9 < MDA 2.4 25 55.3 < MDA 4.2 26 112.3 < MDA All 2.7 Others < MDA < MDA 1.5 3.8 A 200 3.2 B 75 3 C 225 2.7 D 125 3.2 E 25 2.9 F 675 2.8 G 275 2.2 H 225 Total Test Area Smears 4 Avg Avg Total Outside Test Area Smears 26 Beta/gamma Smear Average 105.80 3.37 39,875 Beta/gamma Smear Average 60.40 Total Cubicle Smears 30 Total Cubicle Average 55.87 Note: Blank Entries have no corresponding data for that column. Alphabetical locations are LAS locations.

NDA = No Detectable Activity, MDA = Minimum Detectable Activity Contact Dose Rate and Smear are not at same locations or at the smear locations in the test area.

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RS-TD-313196-005 Revision 0 As seen in Table 13 the maximum dose rate increased from 5 to 8 mR/hr and the average test area dose rate increased from 3.37 to 4.67 mR/hr.

Table 13 - Test 4a Post Remediation Survey Data Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr cpm Location cm2 cm2 ccpm 1 68.4 < MDA 4 32,000 3 66.8 <MDA 7 < MDA < MDA 7 22,000 4 77.9 <MDA 5 < MDA < MDA 8 8,000 11 63.6 <MDA 6 < MDA < MDA 3 18,000 13 66.8 <MDA 9 73.1 < MDA 4 18,000 18 75.5 <MDA 5 6,000 19 132.5 <MDA 2 4,000 21 104.8 <MDA 5 10,000 22 58.8 <MDA 4 40,000 23 132.5 <MDA 26 94.5 <MDA 32 61.2 <MDA 33 49.3 <MDA 34 49.3 <MDA 37 104.8 <MDA 39 49.3 <MDA All Others <MDA <MDA A 200 B 100 C 125 Total Test Area Smears 5 Avg Avg Total Outside Test Area Smears 35 Beta/gamma Smear Average 28.30 4.67 17,556 Beta/gamma Smear Average 33.93 Total Cubicle Smears 40 Total Cubicle Average 33.23 Note: Blank Entries have no corresponding data for that column. Alphabetical locations are LAS locations.

NDA = No Detectable Activity, MDA = Minimum Detectable Activity Contact Dose Rate and Smear are not at same locations or at the smear locations in the test area.

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RS-TD-313196-005 Revision 0 A Masslin LAS and a sample of the concrete debris generated during test 4a were analyzed by gamma spectroscopy. The analysis results and the Test 4a air sample result of 4.14E-11 µCi/ml are provided in Attachment 4. The results of the gamma spectroscopy analysis for each sample and the scaled effluent concentration fractions (ECf) are summarized in Table 14 and Table 15.

Table 14 - Test 4a Masslin Debris Gamma Spectroscopy Results and Scaled Air Sample Results 3/15/04 Gamma Spec 3/15/04 Dust 15:40 Scaled Weighted 3/16/04 Gamma Air DAC Dust EC Spec Dust Fraction of Sample DAC Fraction Eff. Conc Weighted Nuclide dpm/smear Total µCi/cc µCi/cc (DACf) µCi/cc Fraction Co-60 2.09E+02 1.39E-01 5.77E-12 1.00E-08 5.77E-04 5.00E-11 1.15E-01 Cs-134 2.07E+01 1.38E-02 5.70E-13 4.00E-08 1.43E-05 2.00E-10 2.85E-03 Cs-137 1.27E+03 8.47E-01 3.51E-11 6.00E-08 5.84E-04 2.00E-10 1.75E-01 Total 1.50E+03 1.00E+00 N/A 1.18E-03 2.94E-01 Air Sample Result Gross Beta 4.14E-11 µCi/cc Table 15 - Test 4a Debris Gamma Spectroscopy Results and Scaled Air Sample Results 3/15/04 3/15/04 Gamma 15:40 Spec Dust 3/16/04 Gamma Scaled Air Dust EC Spec Dust Fraction Sample Eff. Conc Weighted Nuclide µCi/gm of Total µCi/cc µCi/cc Fraction Co-60 2.90E-05 2.48E-02 1.03E-12 5.00E-11 2.06E-02 Cs-134 1.12E-05 9.61E-03 3.98E-13 2.00E-10 1.99E-03 Cs-137 1.13E-03 9.66E-01 4.00E-11 2.00E-10 2.00E-01 Total 1.17E-03 1.00E+00 2.22E-01 Air Sample Result Gross Beta 4.14E-11 µCi/cc A second test location was tried on test 4b at an area adjacent to the first location. The pre-remediation survey data is shown in Table 16.

Table 16 - Test 4b Pre Remediation Survey Data Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr cpm Location cm2 cm2 ccpm 1 < MDA < MDA 8 25,000 5 68.4 < MDA 2 < MDA < MDA 7 32,000 9 99.2 < MDA 3 < MDA < MDA 4.5 10,000 10 49 < MDA 2 16,000 11 80 < MDA Page 19 of 116

RS-TD-313196-005 Revision 0 Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr cpm Location cm2 cm2 ccpm 6 47,000 16 54.1 < MDA All 2.6 18,000 Others < MDA < MDA 1.6 13,000 9.5 9,000 A 125 2.2 8,000 B NDA 2 18,000 C 295 4.5 1,200 D 25 1.2 Total Test Area Smears 3 Avg Avg Total Outside Test Area Smears 13 Beta/gamma Smear Average <MDA 4.26 17,927 Beta/gamma Smear Average 26.98 Total Cubicle Smears 16 Total Cubicle Average 21.92 Note: Blank Entries have no corresponding data for that column. Alphabetical locations are LAS locations.

NDA = No Detectable Activity, MDA = Minimum Detectable Activity Contact Dose Rate and Smear are not at same locations or at the smear locations in the test area.

As seen in Table 17, dose rates increased significantly up to 20 mR/hr as the concrete was removed.

Table 17- Test 4b Post Remediation Survey Data Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr cpm Location cm2 cm2 ccpm 31 < MDA < MDA 8 32,000 1 130.1 <MDA 32 < MDA < MDA 20 38,000 5 355.8 <MDA 2 12,000 6 348.9 <MDA 5 50,000 7 189.5 <MDA 18 50,000 8 170.5 <MDA 13 22,000 9 113.5 <MDA 8 8,000 14 49.3 <MDA 22 45,000 20 49.3 <MDA All 8 18,000 Others <MDA <MDA 5 50,000 13 22,000 2.8 18,000 Total Test Area Smears 2 Avg Avg Total Outside Test Area Smears 38 Page 20 of 116

RS-TD-313196-005 Revision 0 Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr cpm Location cm2 cm2 ccpm Beta/gamma Smear Average <MDA 10.40 30,417 Beta/gamma Smear Average 37.02 Total Cubicle Smears 40 Total Cubicle Average 35.17 Note: Blank Entries have no corresponding data for that column. Alphabetical locations are LAS locations.

NDA = No Detectable Activity, MDA = Minimum Detectable Activity Contact Dose Rate and Smear are not at same locations or at the smear locations in the test area.

A Masslin from the test area was analyzed by gamma spectroscopy, there was no corresponding air sample to accompany it since the test was abandoned due to the increasing dose rates. Am-241 was also detected on this sample but the beta to alpha ratio remained above 50:1.

Table 18 - Test 4b Maslin Gamma Spectroscopy Results 3/16/04 Gamma Spec Masslin Fraction Nuclide dpm/smear of Total Co-60 2.18E+02 1.18E-01 Cs-134 2.12E+01 1.15E-02 Cs-137 1.59E+03 8.63E-01 Am-241 1.32E+01 7.18E-03 Total 1.84E+03 1.00E+00 Am-241/TRU Correction Factor 2 Beta to Alpha Ratio 69.15 Page 21 of 116

RS-TD-313196-005 Revision 0 Test 5 was conducted in the PAB Metering Pump Cubicle. The Pre-remediation contact dose rate survey was performed on 3/18/04. The pre-remediation smear survey was performed on 3/23/04. The surveys are provided in Attachment 5 and the data is summarized in Table 19. It can be seen that the initial removable contamination levels were higher than in the previous tests.

Table 19 - Test 5 Pre-remediation Survey Data Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr cpm Location cm2 cm2 ccpm 2 227.5 < MDA 1.5 1 73.1 < MDA D 400 2.5 3 118.2 < MDA 2 4 132.5 < MDA 2.5 50,000 5 130.1 < MDA 3.2 6 156.3 < MDA 2.8 7 172.9 < MDA 2 8 80.2 < MDA 10 9 144.4 < MDA 17 10 106.4 < MDA 3.8 11 244.2 < MDA 7 12 184.8 < MDA 10 13 142 < MDA 4.5 14 70.7 < MDA 8 15 427.1 < MDA 7.2 16 182.4 < MDA 3.5 17 172.9 < MDA 5.2 18 187.1 < MDA 2.5 19 123 < MDA 3.5 20 85 < MDA All Others < MDA < MDA A 250 B 300 C 200 Total Test Area Smears 1 Avg Avg Total Outside Test Area Smears 20 Beta/gamma Smear Average 227.50 5.19 50,000 Beta/gamma Smear Average 146.67 Total Cubicle Smears 21 Total Cubicle Average 150.51 Note: Blank Entries have no corresponding data for that column. Alphabetical locations are LAS locations.

NDA = No Detectable Activity, MDA = Minimum Detectable Activity Contact Dose Rate and Smear are not at same locations or at the smear locations in the test area.

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RS-TD-313196-005 Revision 0 The post remediation smear survey was performed on 3/24/04 14:30. The results are summarized in Table 20. Initially test area post remediation dose rates ranged from 1.5 to 4.5 mR/hr. The test area was resurveyed on 3/25/04 at 10:30 after the chips and fines had been cleared and the dose rates in the test area with the debris removed were significantly lower at less than 1 mR/hr.

Table 20 - Test 5 Post Remediation Survey Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr cpm Location cm2 cm2 ccpm 1 < MDA < MDA 0.4 450 1 244.2 < MDA 2 56.5 < MDA 0.4 600 3 146.8 < MDA 20 < MDA < MDA 0.1 800 4 158.6 < MDA 21 < MDA < MDA 0.4 600 5 144.4 < MDA 0.3 700 6 80.2 < MDA 0.6 600 7 146.8 < MDA 0.6 800 8 151.5 < MDA 0.6 600 9 66 < MDA 0.7 700 10 104 < MDA 11 75.5 < MDA 12 146.8 < MDA 13 104 < MDA 15 115.9 < MDA 18 87.4 < MDA 19 681.3 < MDA 23 87.4 < MDA 24 89.7 < MDA 26 56.5 < MDA 27 94.5 < MDA 28 49.3 < MDA 29 73.1 < MDA 30 54.1 < MDA 32 61.3 < MDA 34 96.9 < MDA 36 82.6 < MDA 38 73.1 < MDA 39 51.7 < MDA 40 96.9 < MDA 41 94.5 < MDA 42 87.4 < MDA 43 113.5 < MDA 44 284.6 < MDA Page 23 of 116

RS-TD-313196-005 Revision 0 Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr cpm Location cm2 cm2 ccpm 45 137.5 < MDA 46 77.9 < MDA 47 35.1 < MDA 48 77.9 < MDA 49 260.8 < MDA 50 186 < MDA All Others < MDA < MDA A 120 B 220 C 120 D 220 E 170 F 70 G 270 Total Test Area Smears 4 Avg Avg Total Outside Test Area Smears 46 Beta/gamma Smear Average 14.13 0.46 650 Beta/gamma Smear Average 103.82 Total Cubicle Smears 50 Total Cubicle Average 96.64 Note: Blank Entries have no corresponding data for that column. Alphabetical locations are LAS locations.

NDA = No Detectable Activity, MDA = Minimum Detectable Activity Contact Dose Rate and Smear are not at same locations or at the smear locations in the test area.

The dose rates were reduced significantly from a maximum of 17 to 0.7 mR/hr and from a pre-test average of 5.19 to a post-test average of 0.46 mR/hr. The pre-remediation and post remediation removable contamination results are similar because a thorough pre-remediation decontamination of the area was not performed. However, they were not detectably elevated by the demolition activity on concrete with an average dose rate 5 mR/hr. The highest smear read 681 dpm/100 cm2 which is close to the 1000 dpm/100 cm2 threshold at which posting as a Contaminated Area would be required, and is a level that would be detectable as contamination on personnel and equipment exiting the area.

A composite sample of the concrete chips from Test 5 was analyzed by gamma spectroscopy. The results identified Co-60 and Cs-137 at the concentrations shown in Table 21. The air sample had 1.85 E-10 µCi/cc of Cs-137 and 6.00E-11 µCi/cc of Co-60. This equaled 2.13 ECf which is minimal when the ground release X/Q is considered.

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RS-TD-313196-005 Revision 0 Table 21 - Test 5 Air Sample Data and Debris Gamma Spectroscopy Results Weighted Air DAC EC Fraction of Sample DAC Fraction Eff. Conc Weighted Nuclide µC/ml Total µCi/cc µCi/cc (DACf) µCi/cc Fraction Co-60 1.29E-05 1.83E-03 6.00E-11 1.00E-08 6.00E-03 5.00E-11 1.20E+00 Cs-134 <MDA 0.00E+00 0.00E+00 4.00E-08 0.00E+00 2.00E-10 0.00E+00 Cs-137 7.02E-03 1.00E+00 1.85E-10 6.00E-08 3.08E-03 2.00E-10 9.25E-01 Total 7.03E-03 1.00E+00 2.45E-10 N/A 9.08E-03 N/A 2.13E+00 Air Sample Results Cs-137 1.85E-10 µCi/cc Co-60 6.00E-11 µCi/cc Gross Beta 1.42E-10 µCi/cc Test 6 was performed on an area adjacent to Test 5. This was an additional test to verify that remediation of concrete in the 2 mR/hr range would meet the contamination control objectives of for open air demolition. The pre-test smear survey was performed on 3/25/04 at 10:30 and is provided along with the other data in Attachment 6. The pre-demolition contact dose rate survey was performed on 3/25/04 at 14:30. The pre-demolition survey data is summarized in Table 22.

Table 22 - Test 6 Pre-remediation Survey Data Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr Cpm Location cm2 cm2 ccpm 2 104 < MDA 2.3 20,000 4 99.2 < MDA 3 87.4 < MDA 1.5 25,000 5 118.2 < MDA 19 < MDA < MDA 1.8 15,000 6 111.1 < MDA 1.9 16,000 7 125.4 < MDA 0.8 10,000 8 70.7 < MDA 1.2 2,000 9 111.1 < MDA 1.5 12,000 11 99.2 < MDA 1.2 49,000 12 61.2 < MDA 1.2 35,000 13 87.4 < MDA 0.8 42,000 14 73.1 < MDA 0.8 15 54.1 < MDA 1 16 80.2 < MDA 1.4 17 182.4 < MDA 1.1 18 94.5 < MDA 1 19 127.7 < MDA 1 22 125.4 < MDA 1 23 80.2 < MDA 0.8 24 70.7 < MDA 0.6 26 379 < MDA 0.1 27 109 < MDA Page 25 of 116

RS-TD-313196-005 Revision 0 Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr Cpm Location cm2 cm2 ccpm 1 All Others < MDA < MDA 0.8 0.8 0.6 A 120 B 220 C 120 D 220 E 170 F 70 G 270 Total Test Area Smears 3 Avg Avg Total Outside Test Area Smears 27 Beta/gamma Smear Average 63.80 1.09 22,600 Beta/gamma Smear Average 83.70 Total Cubicle Smears 30 Total Cubicle Average 81.71 Note: Blank Entries have no corresponding data for that column. Alphabetical locations are LAS locations.

NDA = No Detectable Activity, MDA = Minimum Detectable Activity Contact Dose Rate and Smear are not at same locations or at the smear locations in the test area.

The post remediation smear survey was conducted on 3/29/04 at 10:30. After the debris was removed the post remediation dose rate survey was conducted on 3/29/04 at 14:20. This survey is mislabeled as a pre-chip survey in Attachment 6. This post demolition data is summarized in Table 23.

Table 23 - Test 6 Post Remediation Survey Data Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr cpm Location cm2 cm2 ccpm 4 < MDA < MDA 0.6 1,000 6 56.13 < MDA 5 < MDA < MDA 0.5 1,000 8 64.79 < MDA 0.4 10,000 10 73.46 < MDA 0.3 1,500 11 125.47 < MDA 0.4 500 12 73.46 < MDA 0.3 1,000 17 56.13 < MDA 0.4 1,000 23 64.79 < MDA Page 26 of 116

RS-TD-313196-005 Revision 0 Test Area Test Area Removable Contact Cubicle Removable beta/gamma alpha beta/gamma alpha dpm/100 dpm/100 LAS dpm/100 dpm/100 LAS Location cm2 cm2 ccpm mR/hr cpm Location cm2 cm2 ccpm 0.3 600 25 108.13 < MDA 0.4 1,000 27 64.79 < MDA 34 125.47 < MDA 35 220.82 < MDA 36 99.47 < MDA 38 212.15 < MDA 45 83.13 < MDA 51 64.79 < MDA All Others < MDA < MDA A 260 B 240 C 300 D 125 E 280 Total Test Area Smears 2 Avg Avg Total Outside Test Area Smears 27 Beta/gamma Smear Average <MDA 0.40 1,956 Beta/gamma Smear Average 55.30 Total Cubicle Smears 29 Total Cubicle Average 51.48 Note: Blank Entries have no corresponding data for that column. Alphabetical locations are LAS locations.

NDA = No Detectable Activity, MDA = Minimum Detectable Activity Contact Dose Rate and Smear are not at same locations or at the smear locations in the test area.

The Test 6 data showed no significant change in area contamination levels and a slight increase in Large Area Smear results. Maximum dose rates dropped from 2.3 mR/hr to 0.6 mR/hr and average dose rates were reduced from 1.09 mR/hr to 0.4 mR/hr. The maximum removable surface contamination was 221 dpm/100 cm2. This is below the personnel contamination threshold and well below the Contaminated Area posting requirement.

An LAS sample of the concrete dust generated during the remediation was analyzed by gamma spectroscopy. The results are shown in Table 24. The air sample obtained during the remediation was 2.41E-11 µCi/cc. When scaled to the gamma spectroscopy results, it is well below the effluent concentrations.

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RS-TD-313196-005 Revision 0 Table 24 - Test 6 Air Sample Data and Debris Gamma Spectroscopy Results Weighted Scaled Air DAC Fraction of Sample Fraction Eff. Conc EC Weighted Nuclide µCi/gm Total µCi/cc DAC µCi/cc (DACf) µCi/cc Fraction Co-60 7.13E-05 1.72E-02 4.14E-13 1.00E-08 4.14E-05 5.00E-11 8.29E-03 Cs-134 4.11E-06 9.91E-04 2.39E-14 4.00E-08 5.97E-07 2.00E-10 1.19E-04 Cs-137 4.07E-03 9.82E-01 2.37E-11 6.00E-08 3.94E-04 2.00E-10 1.18E-01 Total 4.15E-03 1.00E+00 2.41E-11 N/A 4.36E-04 N/A 1.27E-01 Air Sample Result 2.41E-11 µCi/cc Test 6 confirmed that of concrete with contact dose rates in the 2 mR/hr range could be demolished while maintaining maximum beta/gamma removable contamination levels below 1000 dpm/100 cm2 and average levels below 300 dpm/100 cm2. It also confirmed that airborne radioactivity levels will remain low.

3.3. Summary and Conclusions from Connecticut Yankee Concrete Demolition Test Results As stated in the section 2.2 of this TSD, the objectives of the R2 open air demolition limits were the following:

Ensure ground level airborne radioactivity concentrations remain ALARA and within regulatory limits.

Ensure demolition liquid concentrations remain at levels which can be collected, processed and released using plant water treatment systems and discharge points.

Minimize the spread on contamination within the site boundary such that there is no significant effect on groundwater or the scope of soil remediation required.

Ensure open air demolition activities can be conducted using conventional demolition techniques with minimal radiological restrictions or controls.

As noted previously, the test cubicles were sealed and no engineering controls or ventilation was used during the demolition tests. Air samples were obtained in the cubicles during the tests. As seen in Table 25, although Test 3 had Am-241 present which resulted in 5.56 ECf in the test area, all air samples remained well below the 0.3 DAC airborne radioactivity area limit at which posting and evaluation of respiratory protection would be required. In addition all results would be well below an effluent concentration at the site boundary when the ground release dispersion coefficient (X/Q) is considered.

Table 25 - Summary of CY Demolition Test Air Sample Results Pre-Test Post- Delta Effluent Without Max Test Max Max Air Conc. TRU ECf Contact Contact Contact Sample DAC Fraction Without per Test mR/hr mR/hr mR/hr µCi/cc Fraction ECf TRU ECf mR/hr Test 1 1.50 0.70 0.80 8.66E-12 1.63E-04 4.66E-02 4.66E-02 5.83E-02 Test 2 2.00 0.50 1.50 2.47E-11 4.94E-04 1.38E-01 1.38E-01 9.20E-02 Test 3 2.50 1.90 0.60 1.17E-10 3.51E-02 5.56E+00 6.46E-01 1.08E+00 Test 4a 6.00 8.00 -2.00 4.14E-11 1.18E-03 2.94E-01 2.94E-01 N/A Test 4b 9.50 22.00 -12.50 N/A N/A N/A N/A N/A Page 28 of 116

RS-TD-313196-005 Revision 0 Pre-Test Post- Delta Effluent Without Max Test Max Max Air Conc. TRU ECf Contact Contact Contact Sample DAC Fraction Without per Test mR/hr mR/hr mR/hr µCi/cc Fraction ECf TRU ECf mR/hr Test 5 17.00 0.70 16.30 4.50E-10 9.08E-03 2.13E+00 2.13E+00 1.30E-01 Test 6 2.30 0.60 1.70 2.41E-11 4.36E-04 1.27E-01 1.27E-01 7.45E-02 Combined Results Test 1 - 3 6.00 3.10 2.90 1.50E-10 3.57E-02 5.75E+00 8.31E-01 2.87E-01 All Results Test 4 Excluded 25.30 4.40 20.90 6.24E-10 4.53E-02 8.00E+00 3.08E+00 1.47E-01 Target Average 1 ECf Combined Test 1 - 3 3.5 mR/hr All Results Except Test 4 6.8 mR/hr When results from Tests 1, 2 and 3 are treated as a composite result, they indicate that concrete up to 3.5 mR/hr can be demolished without generating greater than 1 ECf for cobalt and cesium radionuclides. All test results except Tests 4a and 4b indicate a cut off dose rate of up to 7 mR/hr would be acceptable.

With regard to the objective of maintaining removable contamination well below the Contaminated Area limits of 1000 dpm/100 cm2 beta/gamma and 20 dpm/100 cm2 alpha, only the Tests 1 through 3 results are meaningful for calculating a dose rate cut off level. Test area dose rates increased during Tests 4a and 4b invalidating the data and pre-test contamination levels were too high in Tests 5 and 6 resulting in minimal to negative increases in post-test contamination levels. However, Test 5 results do indicate that overall contamination levels were not significantly elevated despite the high delta in pre-test and post-test maximum dose rates.

Another goal of the open air demolition criteria is to allow demolition to proceed without protective clothing being required to prevent personnel contaminations. Tests 1, 2, 3, and 6 indicate that the contamination levels in the area can be maintained below 300 dpm/100 cm2 when maximum dose rates on the concrete are remediated to less than 2 mR/hr prior to open air demolition. Test 5 resulted in a maximum beta/gamma removable contamination level of 681 dpm/100 cm2 which is approaching the Contaminated Area limit and is in the range that can be reliably detected by personnel contamination monitoring equipment. The data based upon Tests 1 through 3 as shown in Table 26 indicates that maximum area contamination levels can be maintained in the range of 300 dpm/100 cm2 at open air demolition cut off dose rates of 2 mR/hr contact on concrete. If all of the test results except 4a and 4b are considered relative to the maximum dose rates and maximum removable contamination levels, a cut off dose rate of 10 mR/hr is calculated. However, there is not enough test data at the dose rates exceeding 2 mR/hr to reliably demonstrate that contamination levels can be maintained under those at which personnel contaminations would occur.

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RS-TD-313196-005 Revision 0 Table 26 - Summary of Test Result Maximum Dose Rates and Maximum Beta/Gamma Removable Contamination Delta Max dpm/100 Pre-Test Delta Max Max Post- Delta cm2 per Max Post-Test Max Pre-Test Test Max Delta Contact Max Contact Contact dpm/100 dpm/100 dpm/100 Max Test mR/hr mR/hr mR/hr cm2 cm2 cm2 mR/hr Test 1 1.50 0.70 0.80 122.8 235.5 112.69 140.9 Test 2 2.00 0.50 1.50 0.0 261.5 261.53 174.4 Test 3 2.50 1.90 0.60 69.0 200.2 131.20 218.7 Test 4a 6.00 8.00 -2.00 295.2 132.5 -162.70 81.4 Test 4b 9.50 22.00 -12.50 99.2 355.8 256.60 -20.5 Test 5 17.00 0.70 16.30 427.1 681.3 254.20 15.6 Test 6 2.30 0.60 1.70 379.0 220.8 -158.18 -93.0 Combined Results Test 1 - 3 6.00 3.10 2.90 191.84 697.26 505.42 174.3 All Results Test 4 Excluded 25.30 4.40 20.90 997.94 1599.38 601.44 28.8 2

Target Average 300 dpm/100 cm Combined Test 1 - 3 1.7 mR/hr All Results Except Test 4 10.4 mR/hr Similarly, a cut off value of 7.4 mR/hr can be calculated based upon the pre and post test contact dose rate averages and pre and post-test cubicle removable contamination averages as seen in Table 27. The negative results in Table 27 for Tests 5 and 6 are due to dilution by concrete dust from the test.

However, as stated above there is insufficient data at contact dose rates exceeding 2 mR/hr to establish the frequency at which personnel performing open air demolition on concrete above 2 mR/hr would be exposed to removable contamination levels exceeding 300 dpm/100 cm2.

Table 27 - Summary of Test Result Average Dose Rates and Average Cubicle Beta/Gamma Removable Contamination Max Pre- Post-Test Post- Delta Max Pre- Test Delta Avg Test Avg Avg. Test Avg Avg Avg dpm/100 Contact Contact Contact dpm/100 dpm/100 dpm/100 cm2 per Test mR/hr mR/hr mR/hr cm2 cm2 cm2 mR/hr Test 1 0.66 0.43 0.23 12.9 16.1 3.15 13.9 Test 2 1.42 0.37 1.06 0.0 56.2 56.16 53.2 Test 3 1.78 1.17 0.60 11.8 29.3 17.53 29.0 Test 4a 3.37 4.67 -1.30 55.9 33.2 -22.65 17.4 Test 4b 4.26 10.40 -6.14 21.9 35.2 13.25 -2.2 Test 5 5.19 0.46 4.74 150.5 96.6 -53.87 -11.4 Test 6 1.09 0.40 0.69 81.7 51.5 -30.22 -43.7 Results Test 1 - 3 3.86 1.97 1.89 24.69 101.53 76.84 40.8 All Results Test 4 Excluded 10.14 2.83 7.32 256.91 249.66 -7.26 -1.0 Target Average 300 dpm/100 cm2 Page 30 of 116

RS-TD-313196-005 Revision 0 Test 1 - 3 7.4 mR/hr All Results Except Test 4 -302.4 mR/hr As seen in Table 28 the embedded source term was predominantly Cs-137 at the CY test locations.

Therefore, significant TRU or non-gamma high energy beta emitters (e.g., Sr/Y-90) could result in a cut-off dose rate lower than 2 mR/hr contact on concrete in order to maintain work area airborne radioactivity and contamination levels within the target ranges.

Table 28 - Summary of Post Remediation Gamma Spectroscopy Results Test 1 Test 2 Test 3 Test 4 Test 4 Test 4 Test 5 Test 6 Nuclide µCi/g dpm/sample µCi/g µCi/g µCi/g dpm/smear µCi/ml µCi/g Co-60 2.77E-05 2.15E+02 1.13E-04 2.90E-05 2.90E-05 2.18E+02 1.29E-05 7.13E-05 Cs-134 1.01E-05 5.89E+01 3.54E-05 1.12E-05 1.12E-05 2.12E+01 <MDA 4.11E-06 Cs-137 1.04E-03 5.24E+03 3.04E-03 1.13E-03 1.13E-03 1.59E+03 7.02E-03 4.07E-03 Am-241 <MDA <MDA 1.34E-06 0.00E+00 <MDA 1.32E+01 <MDA <MDA Total 1.08E-03 5.51E+03 3.19E-03 1.17E-03 1.17E-03 1.84E+03 7.03E-03 4.15E-03

% Cs-137 97% 95% 95% 97% 97% 86% 100% 98%

3.4. LACBWR Concrete Gamma Spectroscopy Results RS-TD-313196-001 (8) evaluated results from twelve (12) concrete core samples from the La Crosse end state structures, six (6) in the Reactor Building, three (3) in the Waste Treatment Building (WTB) and three (3) in the Piping Tunnel. The WTB had the highest concentrations up to 10,450 pCi/g of Cs-137. Cs-127 was 87% of the mix in this core as well as in the mean distribution of all 12 cores. Most of the remaining activity was Ni-63, a weak pure beta emitter, at 8% to 9% of the mix. Co-60 was just over 1% of the mix. Thus contact dose rates are driven by Cs-137.

Table 29 - La Crosse Highest Concrete Core Sample and Average WTB WTB (selected) (selected) Mean Avg Conc. Avg Distribution Nuclide pCi/g Fraction Fraction H-3 1.219E+00 0.01% 0.07%

C-14 6.083E+00 0.05% 0.07%

Fe-55 1.379E+01 0.11% 0.29%

Ni-59 1.629E+02 1.36% 1.04%

Co-60 1.345E+02 1.12% 1.22%

Ni-63 1.083E+03 9.02% 8.05%

Sr-90 1.089E+02 0.91% 0.91%

Nb-94 5.403E-01 0.00% 0.01%

Tc-99 6.330E-01 0.01% 0.02%

Cs-137 1.045E+04 87.03% 87.74%

Eu-152 7.413E+00 0.06% 0.09%

Eu-154 4.983E+00 0.04% 0.08%

Eu-155 3.553E+00 0.03% 0.05%

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RS-TD-313196-005 Revision 0 Np-237 4.840E-02 0.00% 0.00%

Pu-238 1.408E+00 0.01% 0.02%

Pu-239/240 1.329E+00 0.01% 0.01%

Pu-241 2.205E+01 0.18% 0.31%

Am-241 4.206E+00 0.04% 0.04%

Am-243 2.768E-01 0.00% 0.00%

Cm-243/244 3.275E-01 0.00% 0.01%

Total 1.201E+04 The sample with the highest activity in the first column of Table 29 was modeled using MicroShield 8.03 with embedded contamination in the first 1/2 inch of a 72 inch diameter source at 1.045E+4 pCi/g.

The input parameters and results are provided in Table 30 and the MicroShield report is provided in Attachment 6.

Table 30 - MicroShield Dose Rate Model Parameters Source Parameters Value Units Value Units Radius 36 inches 91.44 cm Thickness 0.5 inches 1.27 cm Volume 2035.8 in3 33360 cm3 Source Density N/A N/A 2.35 g/cc Source Mass N/A N/A 78396 grams Cs-137 N/A N/A 1.05E+04 pCi/g Source Cs-137 Activity 8.192E-04 Ci 8.192E+08 pCi Co-60 N/A N/A 1.345E+02 pCi/g Source Co-60 1.054E-05 N/A 1.054E+07 pCi/g Contact Dose Rate 1.91 mR/hr Open Air Demo Concentration 1.09E+04 pCi/g The contact dose rate calculated for the WTB Floor sample with a 1.045E+4 pCi/g source term was 1.91 mrem/hr. Based upon this, the 2 mR/hr contact open air demo limit equals approximately 1.09E+4 pCi/g of Cs-137 in the first half inch of concrete.

4. CONCLUSION Based upon the comparison to other facilities open air demolition limits, the results of the Connecticut Yankee tests, and the La Crosse concrete data, the following open air demolition limits are recommended for La Crosse.

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RS-TD-313196-005 Revision 0 Table 31 - Recommended Open Air Demolition Limits Demolition Total Surface Category Contamination Loose Surface Contamination

/ /

Less than 2 mR/hr contact on concrete 2

1000 dpm/100cm Max R2 Open Air Greater than 2 mR/hr 2 20 dpm/100cm Max contact on material other 300 dpm/100cm2 Avg.

than concrete as authorized by RP

5. REFERENCES
1. San Onofre Unit 1, HP&E Position Paper, Airborne Effluent Controls During Decommissioning, September 27, 2000.
2. Maine Yankee, Technical Evaluation TE-013-01, Radiological Consequences of Hotside Building Demolition, October 10, 2002.
3. Yankee Rowe, RP-Memo File No.03-024, Airborne Effluent Dose Consequences of Building Demolition, September 3, 2003.
4. SAFSTOR/Decommissioning Offsite Dose Calculation Manual, Vol. 4, Rev. 22, Humboldt Bay Power Plant, July 23, 2012.
5. Technical Support Document CY-HP-0029, Rev. 0, HEPA Units Environmental Release Evaluation February 9, 1999.
6. LACBWR Decommissioning Plan and Post-Shutdown Decommissioning Activities Report, March 12, 2014.
7. Technical Support Document CY-HP-0175, Rev. 0, Technical Basis for Structure/Building Open Air Demolition January 19, 2005.
8. EnergySolutions Technical Support Document RS-TD-313196-001, " Radionuclides of Concern During the Decommissioning of the La Crosse Boiling Water Reactor".
9. 10 CFR 20 Standards for Protection Against Radiation, Subpart ERadiological Criteria for License Termination http://www.nrc.gov/reading-rm/doc-collections/cfr/part020/.
10. NUREG-1575, Rev. 1, Multi-Agency Radiation Survey And Site Investigation Manual (MARSSIM), August 2000.
11. Canberra 31013E V4.2 Technical Reference Manual, Model S573 ISOCS Calibration Software.
12. NRC ML112140119, Containment Liner Corrosion, Darrell Dunn, U.S.N.R.C, August 2011.
13. Lacrosse Restoration Project License Termination Plan.

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RS-TD-313196-005 Revision 0

6. ATTACHMENTS 6.1. Attachment 1.A - CY Test 1 B Charging Pump Cubicle Survey 6.2. Attachment 1.B - CY Test 1 B Charging Pump Cubicle Sample Data 6.3. Attachment 2 - CY Test 2 B Charging Pump Cubicle Survey and Sample 6.4. Attachment 3.A - CY Test 3 B Charging Pump Cubicle Survey 6.5. Attachment 3.B - CY Test 3 B Charging Pump Cubicle Sample Data 6.6. Attachment 4.A - CY Tests 4a and 4b B Charging Pump Cubicle Survey 6.7. Attachment 4.B - CY Tests 4a and 4b B Charging Pump Cubicle Sample Data 6.8. Attachment 5.A - CY Tests 5 Metering Pump Cubicle Survey and Sample Data 6.9. Attachment 5.B - CY Tests 5 Metering Pump Cubicle Survey and Sample Data 6.10. Attachment 6.A - CY Tests 6 Metering Pump Cubicle Survey 6.11. Attachment 6.B - CY Tests 6 Metering Pump Cubicle Sample Data 6.12. Attachment 7 - MicroShield Model Embedded Cs-137 for Half Inch Thick Concrete Source Page 34 of 116

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ATTCHMENT 7 RS-TD-313196-005 LACBWR Concrete Sample MicroShield Model Revision 0 MicroShield 8.03 Radiation Safety & Control Services (8.03-0000)

Date By Checked Filename Run Date Run Time Duration LaCrosse Ope Air Demo.msd September 26, 2015 8:49:07 AM 00:00:00 Project Info Case Title WTB Disk Source Description Radius 36 Inches 1/2 Inch Thick 10,045 pCi/g Cs-137 Geometry 8 - Cylinder Volume - End Shields Source Dimensions Height 1.27 cm (0.5 in)

Radius 91.44 cm (3 ft)

Dose Points A X Y Z

  1. 1 0.0 cm (0 in) 2.54 cm (1.0 in) 0.0 cm (0 in)

Shields Shield N Dimension Material Density Source 2035.752 in³ Concrete 2.35 Air Gap Air 0.00122 Source Input: Grouping Method - Actual Photon Energies Nuclide Ci Bq µCi/cm³ Bq/cm³ Ba-137m 7.7496e-004 2.8674e+007 2.3230e-002 8.5952e+002 Co-60 1.0540e-005 3.8998e+005 3.1595e-004 1.1690e+001 Cs-137 8.1920e-004 3.0310e+007 2.4556e-002 9.0859e+002 Buildup: The material reference is Source Integration Parameters Radial 20 Circumferential 10 Y Direction (axial) 10 Page 115 of 116

RS-TD-313196-005 Revision 0 Results Fluence Rate Fluence Rate Exposure Rate Exposure Rate Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.0045 2.977e+05 1.003e-03 1.028e-03 6.875e-04 7.047e-04 0.0318 5.936e+05 1.194e-01 1.441e-01 9.946e-04 1.201e-03 0.0322 1.095e+06 2.294e-01 2.785e-01 1.846e-03 2.241e-03 0.0364 3.986e+05 1.249e-01 1.615e-01 7.098e-04 9.175e-04 0.6616 2.580e+07 6.298e+02 9.331e+02 1.221e+00 1.809e+00 0.6938 6.361e+01 1.643e-03 2.413e-03 3.173e-06 4.660e-06 1.1732 3.900e+05 1.887e+01 2.545e+01 3.372e-02 4.548e-02 1.3325 3.900e+05 2.197e+01 2.908e+01 3.811e-02 5.045e-02 Totals 2.897e+07 6.712e+02 9.882e+02 1.297e+00 1.910e+00 Page 116 of 116

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