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| issue date = 10/24/2006
| issue date = 10/24/2006
| title = Transmittal of Survey Packages in Support of Big Rock Point Phased License Termination
| title = Transmittal of Survey Packages in Support of Big Rock Point Phased License Termination
| author name = Haas K M
| author name = Haas K
| author affiliation = Consumers Energy
| author affiliation = Consumers Energy
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:Consurs EneWj A CMS Energy Company Big Rock Point Nuclear Plant 10269 US-31 North Charlevoix, MI 49720 Kurt A. Haas General Manager October 24, 2006 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 DOCKETS 50-155 AND 72-043 -LICENSE DPR-6 -BIG ROCK POINT PLANT -TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION
{{#Wiki_filter:ConsursEneWj A CMS Energy Company                         Big Rock Point Nuclear Plant     Kurt A. Haas 10269 US-31 North               General Manager Charlevoix, MI 49720 October 24, 2006 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 DOCKETS 50-155 AND 72-043 - LICENSE DPR BIG ROCK POINT PLANT -
TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION


==References:==
==References:==
: 1. U.S. NRC to Big Rock Point dated March 24, 2005, Big Rock Point -Issuance of Amendment 126 to Approve the License Termination Plan (TAC No. L52096)2. Big Rock Point to U.S. NRC dated September 27, 2005, Revision 2 of the Big Rock Point License Termination Plan 3. Big Rock Point to U.S. NRC dated April 3, 2006, Letter of Intent Concerning the Release of Part of the Big Rock Point Site Property from the 10 CFR Part 50 License.4. U.S. NRC to Big Rock Point dated April 25, 2006, Report of April 12, 2006 Meeting to Discuss Partial Site Release and Final Status Survey Report Content 5. Big Rock Point to U.S. NRC dated August 24, 2006, Transmittal of Excavated Surface Surveys, Relocated Soil Surveys and Final Status Survey Packages in Support of Big Rock Point Phased License Termination
: 1.       U.S. NRC to Big Rock Point dated March 24, 2005, Big Rock Point - Issuance of Amendment 126 to Approve the License Termination Plan (TAC No. L52096)
: 6. Big Rock Point to U.S. NRC dated September 19, 2006, Transmittal of Relocated Soil Survey Packages in Support of Big Rock Point Phased License Termination
: 2.       Big Rock Point to U.S. NRC dated September 27, 2005, Revision 2 of the Big Rock Point License Termination Plan
: 7. Big Rock Point to U.S. NRC dated October 9, 2006, Transmittal of Survey Packages in Support of Big Rock Point Phased License Termination
: 3.       Big Rock Point to U.S. NRC dated April 3, 2006, Letter of Intent Concerning the Release of Part of the Big Rock Point Site Property from the 10 CFR Part 50 License.
: 8. Big Rock Point to U.S. NRC dated October 10, 2006, Transmittal of Survey Packages in Support of Big Rock Point Phased License Termination
: 4.       U.S. NRC to Big Rock Point dated April 25, 2006, Report of April 12, 2006 Meeting to Discuss Partial Site Release and Final Status Survey Report Content
: 9. Big Rock Point to U.S. NRC dated October 13, 2006, Transmittal of Survey Packages in Support of Big Rock Point Phased License Termination Attachment I contains a matrix of Final Status Survey (FSS) record numbers, survey area descriptions, and review status. This attachment is a revision to attachment of our letter dated October 13, 2006. It contains a list of the final status survey release records expected to be submitted in support of our FSS report. This FSS report is expected to be submitted on or around the fifteenth of November.
: 5.       Big Rock Point to U.S. NRC dated August 24, 2006, Transmittal of Excavated Surface Surveys, Relocated Soil Surveys and Final Status Survey Packages in Support of Big Rock Point Phased License Termination
Also attached, are the following survey release records: CLASS 1 FINAL STATUS SURVEY RELEASE RECORDS* North West Protected Area (Attachment 2)* Central Protected Area (Attachment 3)* South Central Protected Area (Attachment 4)CLASS 1 RELOCATED SOIL SUPPORTING SURVEY RECORD* Relocated Soils from Turbine Building/Containment Demolition (Attachment  
: 6.       Big Rock Point to U.S. NRC dated September 19, 2006, Transmittal of Relocated Soil Survey Packages in Support of Big Rock Point Phased License Termination
: 5)
: 7.       Big Rock Point to U.S. NRC dated October 9, 2006, Transmittal of Survey Packages in Support of Big Rock Point Phased License Termination
These records are being provided to facilitate U.S. Nuclear Regulatory Commission review, as discussed in our April 12, 2006 meeting. Attachments 2,Lnd 3 to this letter comprise those portions of survey packages which may be of use for final review and will be summarized in our FSS report.The phased release approach is described in Sections 1.4.2 and 5.1.2 of the BRP License Termination Plan (LTP). BRP intends to release site land from the 10 CFR Part 50 license using this phased approach.
: 8.       Big Rock Point to U.S. NRC dated October 10, 2006, Transmittal of Survey Packages in Support of Big Rock Point Phased License Termination
The first phase includes the majority of the site land scheduled for release after all demolition, remediation and FSS activities associated with plant operation are complete.BRP LTP Chapter 5 commits BRP to producing FSS package(s) for each survey area and outlines the contents of each supporting survey package.The intended partial site release supports the process of license termination by demonstrating that an additional portion of the remaining site lands can be released from the Site license. This letter, along with completed and future on-site inspections and letters, provides documentation that demolition activities have been performed in accordance with the LTP.Your timely review of FSS information and approval of our request to release the associated land is particularly important to the project and smooth transition to an Independent Spent Fuel Storage Installation (ISFSI)-only operation.
: 9.       Big Rock Point to U.S. NRC dated October 13, 2006, Transmittal of Survey Packages in Support of Big Rock Point Phased License Termination Attachment I contains a matrix of Final Status Survey (FSS) record numbers, survey area descriptions, and review status. This attachment is a revision to attachment of our letter dated October 13, 2006. It contains a list of the final status survey release records expected to be submitted in support of our FSS report. This FSS report is expected to be submitted on or around the fifteenth of November. Also attached, are the following survey release records:
CLASS 1 FINAL STATUS SURVEY RELEASE RECORDS
* North West Protected Area (Attachment 2)
* Central Protected Area (Attachment 3)
* South Central Protected Area (Attachment 4)
CLASS 1 RELOCATED SOIL SUPPORTING SURVEY RECORD
* Relocated Soils from Turbine Building/Containment Demolition (Attachment 5)
 
These records are being provided to facilitate U.S. Nuclear Regulatory Commission review, as discussed in our April 12, 2006 meeting. Attachments 2,Lnd 3 to this letter comprise those portions of survey packages which may be of use for final review and will be summarized in our FSS report.
The phased release approach is described in Sections 1.4.2 and 5.1.2 of the BRP License Termination Plan (LTP). BRP intends to release site land from the 10 CFR Part 50 license using this phased approach. The first phase includes the majority of the site land scheduled for release after all demolition, remediation and FSS activities associated with plant operation are complete.
BRP LTP Chapter 5 commits BRP to producing FSS package(s) for each survey area and outlines the contents of each supporting survey package.
The intended partial site release supports the process of license termination by demonstrating that an additional portion of the remaining site lands can be released from the Site license. This letter, along with completed and future on-site inspections and letters, provides documentation that demolition activities have been performed in accordance with the LTP.
Your timely review of FSS information and approval of our request to release the associated land is particularly important to the project and smooth transition to an Independent Spent Fuel Storage Installation (ISFSI)-only operation.
If you have any questions or comments on these reports, please contact Ken Pallagi, Radiation Protection and Environmental Services Manager at 231-547-8416.
If you have any questions or comments on these reports, please contact Ken Pallagi, Radiation Protection and Environmental Services Manager at 231-547-8416.
Kurt M. Haas Site General Manager ATTACHMENTS 2 cc: Administrator, Region Il, USNRC (w/o Attachments)
Kurt M. Haas Site General Manager ATTACHMENTS                                                                                         2 cc: Administrator, Region Il, USNRC (w/o Attachments)
NRC Decommissioning Inspector, Big Rock Point (w/o Attachments)
NRC Decommissioning Inspector, Big Rock Point (w/o Attachments)
NRC NMSS Project Manager, James Shepherd (w/o Attachments)
NRC NMSS Project Manager, James Shepherd (w/o Attachments)
NRC NMSS FSS Reviewer, Bruce Watson Michigan Department of Environmental Quality, Thor Strong (w/o Attachments)
NRC NMSS FSS Reviewer, Bruce Watson Michigan Department of Environmental Quality, Thor Strong (w/o Attachments)
ATTACHMENT I CONSUMERS ENERGY BIG ROCKPO1NT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION MATRIX OF FSS SUPPORTING DOCUMENTATION October 24, 2006 5 Pages MATRIX OF BIG ROCK POINT FINAL STATUS SURVEY REPORTS SURVEY RECORD 2  PACKAGE U.S. NRC PACKAGE LETTER AREA' NUMBER SURVEY AREA DESCRIPTION SIGNOFF REVIEW REVIEW DATE DATE METHOD DATE CLASS 1 AREAS -FINAL STATUS SURVEY OF SURFACES I 01Ci 1 Class I Final Status Release Record, South West Protected Area 10/11/06 Letter 10/13/06 2 02C 1 1 Class I Final Status Release Record, West Central Protected Area 10/11/06 Letter 10/13/06 3 03C, I Class I Final Status Release Record, North West Protected Area 10/16/06 Letter 10/24/06 4 04C, 1  Class I Final Status Release Record, North Central Protected Area 10/04/06 Letter 10/10/06 5 05C 1 I Class I Final Status Release Record, Central Protected Area 10/16/06 Letter 10/24/06 6 06C, 1 Class 1 Final Status Release Record, South Central Protected Area 10/23/06 Letter 10/24/06 7 07C, I Class I Final Status Release Record, South East Protected Area 8 08C, 1  Class I Final Status Release Record, East Central Protected Area 9 09C 1 I Class I Final Status Release Record, North East Protected Area 10/04/06 Letter 10/13/06 10 10C 1  Class I Final Status Release Record, East Protected Area III North 1 IC 1 Class I Final Status Release Record, North Radwaste Staging Area 11 South] 1C, 1 Class I Final Status Release Record, South Radwaste Staging Area On-Site Inspection 06/13-14/06 10/9/06 15 15(2R)C 1 I Class I Final Status Release Record, Woods Road Storage Area 05/23/06 and Letter Isetn 0/ 146090 20 20C, I Class I Final Status Release Record, East Radwaste Staging Area 23 23C, 1 Class I Final Status Release Record, North Protected Area 10/05/06 Letter 10/10/06 24 24C, I Class I Final Status Release Record, South Protected Area DiscargeOn-Site Inspection Discharge Canal C, 1 Class I Final Status Survey, Discharge Canal 01/27/05 On-Site 06/13-14/06 10/9/06 Canal 4  _____________________________________________and Letter_______________
 
CLASS 1 AREAS- EXCAVATED SOIL FINAL STATUS SURVEYS'2 02Cxj I Class I Final Status Survey, Excavated Soil from Retention Pond 10/13/2004 On-Site Inspection 06/13-14/06 10/9/06 Construction and Letter 8 08Cxl Class I Final Status Survey, Excavated Soil from Turbine Building 05/16/05 On-Site Inspection 06/13-14/06 10/9/06 Subfloor and Letter 9 09Cxj 1 Class 1 Final Status Survey, Excavated Soil from Screenhouse 12/09/04 On-Site Inspection 06/13-14/06 10/9/06 Area and Letter 9 09CX21 Class I Final Status Survey, Excavated Soil from Screenhouse 12/08/04 On-Site Inspection 06/13-14/06 10/9/06 Area and letter 1 Survey Area Map -Big Rock Point License Termination Plan, Chapter 5, figure 5-3, Initial Land Area Survey Units 2 Record Number nomenclature is defined in Procedure RM-76, Final Status Survey Design, step 6.2, Survey Unit Nomenclature 3 Surface of survey unit 11 was divided into North and South areas due to intermediate use of land between the quarry survey and the final surface survey (served as solid Radwaste storage yard in interim.)4 Discharge Canal is North East of the Protected Area 5 Soils removed from Class I Area excavations Page 1 of 5 MATRIX OF BIG ROCK POINT FINAL STATUS SURVEY REPORTS SURVEY RECORD 2  PACKAGE U.S. NRC PACKAGE LETTER AREA' NUMBER SURVEY AREA DESCRIPTION SIGNOFF REVIEW REVIEW DATE DATE METHOD DATE 9 0 Class I Final Status Survey, Excavated Soil from Screenhouse 12/09/04 On-Site Inspection 06/13-14/06 10/9/06 Area and letter 9 09CX41 Class 1 Final Status Survey, Excavated Soil from Screenhouse 12/09/04 On-Site Inspection 06/13-14/06 10/9/06 Area and letter 9 Class I Final Status Survey, Excavated Soil from Screenhouse 12/14/04 On-Site Inspection 06/13-14/06 10/9/06 9 09CX61 Class I Final Status Survey, Excavated Soil from Screenhouse 01/19/05 On-Site Inspection 06/13-14/06 10/9/06 Area and Letter 9 09CX1 Class I Final Status Survey, Excavated Soil from Screenhouse 05/16/05 On-Site Inspection 06/13-14/06 10/9/06 Area and Letter I I Cx Class I Final Status Survey, Excavated Soil from Radwaste 10/13/04 On-Site Inspection 06/13-14/06 10/9/06 Storage Vaults and Letter Slurry Wall Class I Final Status Survey, Excavated Soil from Slurry Wall 12/08/04 On-Site Inspection 06/13-14/06 10/9/06 Slurry 6 Wall Cxurr Wal Constructiona SttuSreyEcaaedSo__rmluryWll_2080 On-SiteInspection 06/13-14/06__
ATTACHMENT I CONSUMERS ENERGY BIG ROCKPO1NT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION MATRIX OF FSS SUPPORTING DOCUMENTATION October 24, 2006 5 Pages
10/9/06__Cxjl Construction and Letter Slurry Wall Slurry Wall Class I Final Status Survey, Excavated Soil from Slurry Wall 12/20/04 On-Site Inspection 06/13-14/06 10/9/06 Cx 2 1 Construction and Letter Turbine Class I Supporting Survey- Soil Excavated from Turbine Building On-Site Inspection Building7 TBCxj I Demolition Area, Supporting Subsurface Structure and Component 08/24/05 and Letter 06/13-14/06 10/9/06 Removal Turbine Class I Supporting Survey- Soil Excavated from Turbine Building On-Site Inspection Building TBCx21 Demolition Area, Supporting Subsurface Structure and Component 10/13/05 and Letter 06/13-14/06 10/9/06 Removal Turbine Class I Supporting Survey- Soil Excavated from Turbine Building On-Site Inspection Building TBCX31 Demolition Area, Supporting Subsurface Structure and Component 11/23/05 and Letter 06/13-14/06 10/9/06 Removal Turbine Class I Supporting Survey- Soil Excavated from Turbine Building On-Site Inspection Building TBCX41 Demolition Area, Supporting Subsurface Structure and Component 11/23/05 and Letter 06/13-14/06 10/9/06 Removal Turbine Class I Supporting Survey- Soil Excavated from Turbine Building On-Site Inspection Building TBCx5I Demolition Area, Supporting Subsurface Structure and Component 01/06/06 and Letter 06/13-14/06 10/9/06 Removal Turbine Class I Supporting Survey- Soil Excavated from Turbine Building On-Site Inspection Building TBCX61 Demolition Area, Supporting Subsurface Structure and Component 07/03/06 and Letter 06/13-14/06 10/9/06 Removal Turbine Class 1 Supporting Survey- Soil Excavated from Turbine Building On-Site Inspection Building TBCX71 Demolition Area, Supporting Subsurface Structure and Component 07/05/06 and Letter 06/13-14/06 10/9/06 Removal 6 Slurry Wall crossed several survey areas on the ease, south, and west sides of the protected area.7 Turbine building excavation was beneath survey areas 5, 6, and 8 Page 2 of 5 MATRIX OF BIG ROCK POINT FINAL STATUS SURVEY REPORTS SURVEY RECORD' PACKAGE U.S. NRC PACKAGE LETTER AREA' NUMBER SURVEY AREA DESCRIPTION SIGNOFF REVIEW REVIEW DATE DATE METHOD DATE Turbine TBCxg1 Class I Supporting Survey- Relocated Soil from Turbine 07/03/06 On-Site Inspection 06/13-14/06 10/9/06 Building Building/Containment Demolition and Letter Turbine TBCx91 Class I Supporting Survey -Relocated Soil from Turbine 07/03/06 On-Site Inspection 06/13-14/06 10/9/06 Building Building/Containment Demolition and Letter Turbine TBCxj01 Class 1 Relocated Soil Supporting Survey Release Record -08/03/06 Letter 8/24/06 Building Bx 1 I Relocated Soils from Turbine Building/Containment Demolition
 
________________
MATRIX OF BIG ROCK POINT FINAL STATUS SURVEY REPORTS SURVEY           RECORD2                                                                                PACKAGE         U.S. NRC         PACKAGE       LETTER AREA'           NUMBER                           SURVEY AREA DESCRIPTION                               SIGNOFF       REVIEW             REVIEW       DATE DATE       METHOD                 DATE CLASS 1 AREAS - FINAL STATUS SURVEY                     OF SURFACES I               01Ci1          Class I Final Status Release Record, South West Protected Area       10/11/06 Letter                             10/13/06 2               02C1 1         Class IFinal Status Release Record, West Central Protected Area     10/11/06 Letter                             10/13/06 3               03C, I         Class IFinal Status Release Record, North West Protected Area       10/16/06 Letter                             10/24/06 4               04C,1         Class IFinal Status Release Record, North Central Protected Area     10/04/06 Letter                             10/10/06 5               05C 1I        Class IFinal Status Release Record, Central Protected Area           10/16/06 Letter                             10/24/06 6               06C, 1         Class 1 Final Status Release Record, South Central Protected Area   10/23/06 Letter                             10/24/06 7               07C, I         Class IFinal Status Release Record, South East Protected Area 8               08C, 1         Class IFinal Status Release Record, East Central Protected Area 9               09C 1 I       Class I Final Status Release Record, North East Protected Area       10/04/06 Letter                             10/13/06 10               10C 1         Class I Final Status Release Record, East Protected Area III           North 1IC 1       Class IFinal  Status Release Record, North Radwaste Staging Area 11           South] 1C, 1     Class IFinal  Status Release Record, South Radwaste Staging Area On-Site Inspection   06/13-14/06   10/9/06 15             15(2R)C 1I      Class IFinal Status Release Record, Woods Road Storage Area           05/23/06 and LetterIsetn      0/   146090 20               20C, I         Class IFinal Status   Release Record, East Radwaste Staging Area 23               23C,1         Class IFinal Status   Release Record, North Protected Area           10/05/06 Letter                             10/10/06 24               24C, I         Class IFinal Status   Release Record, South Protected Area Inspection DiscargeOn-Site Discharge 4          Canal C, 1       Class I Final Status Survey, Discharge Canal                         01/27/05 On-Site               06/13-14/06   10/9/06 Canal       _____________________________________________and                                                         Letter_______________
Turbine Class I Relocated Soil Supporting Survey Release Record -08/14/06 Letter 8/24/06 Building TBCx, 1 I Relocated Soils from Turbine Building/Containment Demolition Turbine TB~x121 Class I Relocated Soil Supporting Survey Release Record -9/6/06 Letter 9/20/06 Building Relocated Soils from Turbine Building/Containment Demolition Turbine TBCx131 Class I Relocated Soil Supporting Survey Release Record -9/6/06 Letter 9/20/06 Building Relocated Soils from Turbine Building/Containment Demolition Turbine TBCx141 Class 1 Relocated Soil Supporting Survey Release Record -09/15/06 Letter 10/10/06 Building TBCx 4 1 Relocated Soils from Turbine Building/Containment Demolition Turbine Class I Relocated Soil Supporting Survey Release Record -10/23/06 Letter 10/24/06 Building BRelocated Soils from Turbine Building/Containment Demolition CLASS 1 AREAS -FINAL STATUS SURVEY -SUBSURFACE (QUARRY)On-Site Inspection 06/13-14/06 10/9/06 09Cq 1 I Class I Final Status Survey, Screenhouse Area Excavation 12/20/04 and Letter Isetn 0/ 146090 11 11 Cq I Class I Final Status Survey, Solid Radwaste Storage Area 10/13/04 On-Site Inspection 06/13-14/06 10/9/06 Excavation and Letter Containment8 CSCqj I Excavated Surface Supporting Survey Release Record -Base 08/03/06 Letter 8/24/06 Elevation Survey of Containment Structure Excavation Circulating CWCqj Excavated Surface Supporting Survey Release Record -Base 08/07/06 Letter 8/24/06 Water Piping Elevation Survey of Circulating Water Piping Excavation Turbine East TBCqj I Class 1 Final Status Release Record, Turbine Building East 03/30/06 Letter 4/03/06 Building Excavation Surface Turbine Excavated Surface Supporting Survey Release Record -Base West TBCq 1 1 Elevation Survey of the Turbine Building Excavation Following 08/14/06 Letter 8/24/06 Building Removal of West-Side Foundations and Subsurface Components 8 Containment quarry was beneath survey areas 4, 5, 8, and 9. Circulation Water quarry was beneath survey areas 7, 8, 9, and 10. Turbine Building quarry was beneath survey areas 5, 6, and 8 Page 3 of 5 MATRIX OF BIG ROCK POINT FINAL STATUS SURVEY REPORTS SURVEY RECORD 2  PACKAGE U.S. NRC PACKAGE LETTER AREA' NUMBER SURVEY AREA DESCRIPTION SIGNOFF REVIEW REVIEW DATE DATE METHOD DATE CLASS 2 AREAS -FINAL STATUS SURVEY OF SURFACE Class 2 Final Status Survey Release Record, Shoreline North of the 08/14/06 Letter 8/24/06 12 12C 1 2 Protected Area Class 2 Final Status Survey Release Record, Eastern Section 15 15(1)C 1 2 Woods Road Area 15 15(2)C,2 Class 2 Final Status Survey Release Record, Central Section 08/09/06 Letter 8/24/06 Woods Road Area 16 16C,2 Class 2 Final Status Survey Release Record, Shoreline East of 08/14/06 Letter 8/24/06 Breakwall Class 2 Final Status Survey Release Record, North West Transport 19 North 19C 1 2 Route Class 2 Final Status Survey Release Record, South West Transport 19 Southl19C 1 2 Route Class 2 Final Status Survey Release Record, North East Transport 21 North2C 1 C2 Route Class 2 Final Status Survey Release Record, South East Transport 21 South2C 1 C2 Route Class 2 Final Status Survey Release Record, East Powerline 22 East22C 1 2 Corridor Class 2 Final Status Survey Release Record, West Powerline 22 West22C 1 2 Corridor Class 2 Final Status Release Record, Drainage Ditch, South and 26 26C 1 2 West of the Industrial Area Septic Drain DFC,2 Class 2 Final Status Survey Release Record, Septic Field Drain 08/14/06 Letter 8/24/06 Field9 IIIII CLASS 2 AREAS -EXCAVATED SOIL FINAL STATUS SURVEYS 12 12Cx,2 Class 2 Final Status Survey Record, Excavated Soil from Building 12/07/04 On-Site Inspection 06/13-14/06 10/9/06 Construction and Letter 1 19 19Cx,2 Class 2 Final Status Survey Record, Excavated Soil from Storm 12/02/04 On-Site Inspection 06/13-14/06 10/9/06 Drain Modification and Letter 9 Septic Field Drain survey area is contained within survey area 15(1)Page 4 of 5 MATRIX OF BIG ROCK POINT FINAL STATUS SURVEY REPORTS SURVEY RECORD 2  PACKAGE U.S. NRC PACKAGE LETTER AREA 1  NUMBER SURVEY AREA DESCRIPTION SIGNOFF REVIEW REVIEW DATE DATE METHOD DATE CLASS 3 AREAS -FINAL STATUS SURVEY OF SURFACE 13 13C,3 Class 3 Final Status Survey Release Record, Shoreline East of the 08/14/06 Letter 8/24/06 13__13C_3 Industrial Site 14 14C,3 Class 3 Final Status Survey Release Record, Shoreline West of the 08/17/06 Letter 8/24/06 14___4C_3 Industrial Site 17 17C,3 Class 3 Final Status Survey Release Record, East Woods Boundary 18 18C,3 Class 3 Final Status Survey Release Record, Wooded Area West of 07/03/06"0 On-Site Inspection 06/13-14/06 10/9/06 18 _ 18C3 Industrial Site and Letter Class 3 Final Status Survey Release Record, South Woods 25 -I 25C 1 3 Boundary 59 59C, Class 3 Final Status Survey Release Record, Soil Storage Area 07/03/06 On-Site Inspection 06/13-14/06 10/9/06 1 South of US 31 and Letter I _I 1o Revisions to packages signed after NRC review were administrative only -no changes to technical content.Page 5 of 5 ATTACHMENT 2 CONSUMERS ENERGY BIG ROCKPOINT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION CLASS I FINAL STATUS SURVEY RELEASE RECORD, 03C 1 1, NORTH WEST PROTECTED AREA October 24, 2006 37 Pages Class I Final Status Survey Release Record 03C 1 l North West Protected Area SURVEY PACKAGE CLOSURE Final Status Survey Documentation is authorized for closure. All required reviews are complete and the evaluation of data results have satisfied the criteria established for unrestricted release.Signed: Signed: Signed:/ (ESSG)Y Date: /e)/6'-'-, Date: /0 -/(Df, Date:  (ES "Superintendent)
CLASS 1 AREAS- EXCAVATED SOIL FINAL STATUS SURVEYS' 2             02Cxj I         Class I Final Status Survey, Excavated Soil from Retention Pond     10/13/2004 On-Site Inspection   06/13-14/06   10/9/06 Construction                                                                   and Letter 8             08Cxl           Class I Final Status Survey, Excavated Soil from Turbine Building     05/16/05 On-Site Inspection   06/13-14/06   10/9/06 Subfloor                                                                       and Letter On-Site  Inspection                10/9/06 Area 1 Final Status Survey, Excavated Soil from Screenhouse 9              09Cxj 1        Class                                                                12/09/04 and Letter            06/13-14/06 9             09CX21          Area I Final Status Survey, Excavated Soil from Screenhouse Class                                                                12/08/04 On-Site and letterInspection  06/13-14/06   10/9/06 1 Survey Area Map - Big Rock Point License Termination Plan, Chapter 5, figure 5-3, Initial Land Area Survey Units 2 Record Number nomenclature is defined in Procedure RM-76, Final Status Survey Design, step 6.2, Survey Unit Nomenclature 3 Surface of survey unit 11 was divided into North and South areas due to intermediate use of land between the quarry survey and the final surface survey (served as solid Radwaste storage yard in interim.)
/ (RP & ES Manager)
4 Discharge Canal is North East of the Protected Area 5 Soils removed from Class I Area excavations Page 1 of 5
Survey Area Requirements Final Status Survey, Release Record 03C 1 1 North West Protected Area Survey Description Final Status Survey 03C 1 1 encompasses 1956 m 2 at or below the grade elevation present during plant power operations in the north west section of the Protected Area. No materials of plant origin remain in the survey area.History During power operations the Protected Area supported the components and systems necessary for electrical generation.
 
The location of Survey Unit 03 is adjacent to the transport route used to move spent resin and filter media for radiological survey and offsite removal. Structures and enclosures formerly located in this area were once used for the storage of contaminated materials.
MATRIX OF BIG ROCK POINT FINAL STATUS SURVEY REPORTS SURVEY           RECORD2                                                                          PACKAGE        U.S. NRC         PACKAGE         LETTER AREA'           NUMBER                         SURVEY AREA DESCRIPTION                             SIGNOFF       REVIEW             REVIEW           DATE DATE       METHOD               DATE 12/09/04 On-Site Inspection   06/13-14/06   10/9/06 9              0              Area I Final Status Survey, Excavated Soil from Screenhouse Class and letter 9             09CX41         Class 1 Final Status Survey, Excavated Soil from Screenhouse       12/09/04 On-Site Inspection   06/13-14/06   10/9/06 Area                                                                       and letter 9                             Class I Final Status Survey, Excavated Soil from Screenhouse       12/14/04 On-Site Inspection   06/13-14/06   10/9/06 9             09CX61         Class I Final Status Survey, Excavated Soil from Screenhouse Area                                                              01/19/05 and LetterInspection On-Site               06/13-14/06   10/9/06 9             09CX1         Class I Final Status Survey, Excavated Soil from Screenhouse     05/16/05 On-Site Inspection   06/13-14/06   10/9/06 Area                                                                       and Letter II                Cx         Class I Final Status Survey, Excavated Soil from Radwaste         10/13/04 On-Site Inspection   06/13-14/06   10/9/06 Storage Vaults                                                             and Letter Slurry6 Wall          Cxurr Slurry Wal Wall     Constructiona Class I Final SttuSreyEcaaedSo__rmluryWll_2080 Status Survey, Excavated Soil from Slurry Wall     12/08/04 On-SiteInspection On-Site Inspection   06/13-14/06__
A detailed review of the history and radiological characterization of Survey Unit 3 is provided in Appendix 2B and 2E of the LTP (License Termination Plan).Current Radiological Status Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Based on operational history and former locations of radioactive systems and material transport pathways the radiological status of this survey unit is Class 1.Post-Construction Expectations Final Status Survey 03C11 will be performed in the following activity sequence: 1. Walkdown:
06/13-14/06   10/9/06__
Environmental Services Survey Group (ESSG) personnel will perform a walkdown assessment to ensure survey area preparations are complete and confirm that the following post-construction expectations have been satisfied as applicable: " Groundwater and Surface water control is adequate* All construction debris has been removed from the survey area" The survey location status meets all applicable safety requirements
10/9/06 Cxjl        Construction                                                               and Letter Slurry Wall       Slurry Wall     Class I Final Status Survey, Excavated Soil from Slurry Wall       12/20/04 On-Site Inspection   06/13-14/06   10/9/06 Cx 2 1       Construction                                                               and Letter Turbine                           Class I Supporting Survey- Soil Excavated from Turbine Building             On-Site Inspection Building7           TBCxj I       Demolition Area, Supporting Subsurface Structure and Component   08/24/05 and Letter           06/13-14/06   10/9/06 Removal Turbine                           Class I Supporting Survey- Soil Excavated from Turbine Building             On-Site Inspection 10/13/05 and Letter           06/13-14/06   10/9/06 Building          TBCx21        Demolition Area, Supporting Subsurface Structure and Component Removal Turbine                           Class I Supporting Survey- Soil Excavated from Turbine Building             On-Site Inspection 11/23/05 and Letter           06/13-14/06   10/9/06 Building          TBCX31        Demolition Area, Supporting Subsurface Structure and Component Removal Turbine                           Class I Supporting Survey- Soil Excavated from Turbine Building             On-Site Inspection Demolition Area, Supporting Subsurface Structure and Component     11/23/05 and Letter           06/13-14/06   10/9/06 Building          TBCX41 Removal Turbine                           Class I Supporting Survey- Soil Excavated from Turbine Building             On-Site Inspection Demolition Area, Supporting Subsurface Structure and Component   01/06/06 and Letter           06/13-14/06   10/9/06 Building          TBCx5I Removal Turbine                           Class I Supporting Survey- Soil Excavated from Turbine Building             On-Site Inspection 07/03/06 and Letter           06/13-14/06   10/9/06 Building          TBCX61        Demolition Area, Supporting Subsurface Structure and Component Removal Turbine                           Class 1 Supporting Survey- Soil Excavated from Turbine Building             On-Site Inspection 07/05/06 and Letter           06/13-14/06   10/9/06 Building          TBCX71        Demolition Area, Supporting Subsurface Structure and Component Removal 6 Slurry Wall crossed several survey areas on the ease, south, and west sides of the protected area.
: 2. Survey Area Isolation and Control: Control measures will be established to ensure that any potential ongoing decommissioning activities in adjacent locations do not impact the current survey area status. Isolation and control measures include postings, barriers, access points, and the evaluation of ongoing work activities in adjacent areas.Survey Area Requirements FSS 3C 1 1 Page 1 of 2  
7 Turbine building excavation was beneath survey areas 5, 6, and 8 Page 2 of 5
: 3. Survey Design and Execution:
 
Survey design and execution will follow the Data Quality Objectives for 03Cl1 in accordance with the survey requirements established in procedures RM-76, Final Status Survey Design and RM-77, Final Status Survey Implementation, and LTP, Chapter 5. Survey size will be based on the statistical requirements of the Sign Test for Class 1 areas with soil samples collected in random start, systematic data point locations.
MATRIX OF BIG ROCK POINT FINAL STATUS SURVEY REPORTS SURVEY           RECORD'                                                                                   PACKAGE               U.S. NRC           PACKAGE         LETTER AREA'         NUMBER                         SURVEY AREA DESCRIPTION                                     SIGNOFF               REVIEW             REVIEW           DATE DATE             METHOD                 DATE Turbine         TBCxg1         Class I Supporting Survey- Relocated Soil from Turbine                     07/03/06       On-Site Inspection     06/13-14/06       10/9/06 Building                       Building/Containment Demolition                                                             and Letter Turbine         TBCx91         Class I Supporting Survey - Relocated Soil from Turbine                     07/03/06       On-Site Inspection     06/13-14/06       10/9/06 Building                       Building/Containment Demolition                                                             and Letter Turbine         TBCxj01         Class 1 Relocated Soil Supporting Survey Release Record -                   08/03/06       Letter                                 8/24/06 Building         Bx 1 I       Relocated Soils from Turbine Building/Containment Demolition         ________________
Surface scanning will be performed with 100%survey area coverage.
Turbine                         Class I Relocated Soil Supporting Survey Release Record -                   08/14/06       Letter                                 8/24/06 Building         TBCx,1 I       Relocated Soils from Turbine Building/Containment Demolition Turbine         TB~x121       Class I Relocated Soil Supporting Survey Release Record -                     9/6/06       Letter                                 9/20/06 Building                       Relocated Soils from Turbine Building/Containment Demolition Turbine         TBCx131       Class I Relocated Soil Supporting Survey Release Record -                     9/6/06       Letter                                 9/20/06 Building                       Relocated Soils from Turbine Building/Containment Demolition Turbine         TBCx141       Class 1 Relocated Soil Supporting Survey Release Record -                   09/15/06       Letter                                 10/10/06 Building         TBCx 41        Relocated Soils from Turbine Building/Containment Demolition Turbine                         Class I Relocated Soil Supporting Survey Release Record -                   10/23/06       Letter                                 10/24/06 Building         BRelocated               Soils from Turbine Building/Containment Demolition CLASS 1 AREAS - FINAL STATUS SURVEY - SUBSURFACE (QUARRY)                               On-Site Inspection     06/13-14/06     10/9/06 09Cq1 I       Class I Final Status Survey, Screenhouse Area Excavation                   12/20/04       and Letter Isetn           0/   146090 11           11 Cq I       Class I Final Status Survey, Solid Radwaste Storage Area                     10/13/04       On-Site Inspection     06/13-14/06     10/9/06 Excavation                                                                                 and Letter Containment8         CSCqj I       Excavated Surface Supporting Survey Release Record - Base                   08/03/06       Letter                                 8/24/06 Elevation Survey of Containment Structure Excavation Circulating       CWCqj         Excavated Surface Supporting Survey Release Record - Base                   08/07/06       Letter                                 8/24/06 Water Piping                       Elevation Survey of Circulating Water Piping Excavation Turbine       East TBCqj I     Class 1 Final Status Release Record, Turbine Building East                 03/30/06       Letter                                 4/03/06 Building                       Excavation Surface Turbine                         Excavated Surface Supporting Survey Release Record - Base West TBCq1 1     Elevation Survey of the Turbine Building Excavation Following               08/14/06       Letter                                   8/24/06 Building                       Removal of West-Side Foundations and Subsurface Components 8 Containment quarry was beneath survey areas 4, 5, 8, and 9. Circulation Water quarry was beneath survey areas 7, 8, 9, and 10. Turbine Building quarry was beneath survey areas 5, 6, and 8 Page 3 of 5
This survey will be conducted in accordance with approved BRP procedures and follow the guidance of NUREG 1575.4. Data Quality Assessment:
 
Isolation and control of the survey area will be maintained until the survey Data Quality Assessment demonstrates that the regulatory requirements for unrestricted site release have been satisfied.
MATRIX OF BIG ROCK POINT FINAL STATUS SURVEY REPORTS SURVEY             RECORD2                                                                              PACKAGE       U.S. NRC         PACKAGE     LETTER AREA'             NUMBER                         SURVEY AREA DESCRIPTION                               SIGNOFF       REVIEW             REVIEW       DATE DATE       METHOD               DATE CLASS 2 AREAS - FINAL STATUS SURVEY OF SURFACE Class 2 Final Status Survey Release Record, Shoreline North of the   08/14/06 Letter                             8/24/06 12               12C 1 2       Protected Area Class 2 Final Status Survey Release Record, Eastern Section 15               15(1)C 12      Woods Road Area 15               15(2)C,2       Class 2 Final Status Survey Release Record, Central Section         08/09/06 Letter                             8/24/06 Woods Road Area 16               16C,2         Class 2 Final Status Survey Release Record, Shoreline East of       08/14/06 Letter                             8/24/06 Breakwall Release Record, North West Transport 19             North 19C12      Route 2 Final Status Survey Class Survey Release Record, South West Transport 19             Southl19C 12    Route 2 Final Status Class Class 2 Final Status Survey Release Record, North East Transport 21             North2CC2 1     Route Class 2 Final Status Survey Release Record, South East Transport 21             South2C1C2      Route Class 2 Final Status Survey Release Record, East Powerline 22             East22C12      Corridor Class 2 Final Status Survey Release Record, West Powerline 22             West22C 12      Corridor Status Release         Drainage Ditch, South and 26               26C 12        Class 2 Final West of the Industrial Area Record, Septic Drain           DFC,2         Class 2 Final Status Survey Release Record, Septic Field Drain       08/14/06 Letter                             8/24/06 Field9       IIIII CLASS 2 AREAS - EXCAVATED SOIL FINAL STATUS SURVEYS 12               12Cx,2       Class 2 Final Status Survey Record, Excavated Soil from Building     12/07/04 On-Site Inspection   06/13-14/06 10/9/06 Construction                                                                   and Letter         1 19               19Cx,2       Class 2 Final Status Survey Record, Excavated Soil from Storm         12/02/04 On-Site Inspection   06/13-14/06   10/9/06 Drain Modification                                                             and Letter 9 Septic Field Drain survey area is contained within survey area 15(1)
Survey Area Requirements FSS O3C1 Page 2 of 2 DATA QUALITY OBJECTIVES Final Status Survey, Release Record 03C11 North West Protected Area STATE THE PROBLEM The Problem: To demonstrate that the level of residual radioactivity in Class 1 Survey Unit 03 does not exceed the release criteria of 25 mrem/year Total Effective Dose Equivalent (TEDE) as specified in the License Termination Plan (LTP).Stakeholders:
Page 4 of 5
The primary stakeholders interested in the answer to this problem are Consumers Energy Co., and the general public as represented by the Michigan Department of Environmental Quality (MDEQ), and the US Nuclear Regulatory Commission (USNRC).The Planning Team: The planning team consists of members of the BRP Environmental Services Survey Group (ESSG). The primary decision maker will be the Final Status Survey Supervisor.
 
The Final Status Survey Supervisor will obtain input from the site Construction Group and Scheduling Group for issues relating to schedule and costs.Schedule: Approximately five (5) working days are projected to implement the survey and to collect and analyze field data.Resources:
MATRIX OF BIG ROCK POINT FINAL STATUS SURVEY REPORTS SURVEY             RECORD2                                                                            PACKAGE         U.S. NRC         PACKAGE     LETTER AREA1              NUMBER                     SURVEY AREA DESCRIPTION                               SIGNOFF DATE        REVIEW METHOD REVIEW DATE DATE CLASS 3 AREAS - FINAL STATUS SURVEY OF SURFACE 13                 13C,3       Class 3 Final Status Survey Release Record, Shoreline East of the     08/14/06 Letter                             8/24/06 13__13C_3       Industrial Site 14                 14C,3       Class 3 Final Status Survey Release Record, Shoreline West of the     08/17/06 Letter                             8/24/06 14___4C_3       Industrial Site 17                 17C,3       Class 3 Final Status Survey Release Record, East Woods Boundary 18                 18C,3       Class 3 Final Status Survey Release Record, Wooded Area West of     07/03/06"0 On-Site Inspection   06/13-14/06 10/9/06 18     _         18C3       Industrial Site                                                                 and Letter Class 3 Final Status Survey Release Record, South Woods 25         -I     25C13      Boundary 59                 59C,       Class 3 Final Status Survey Release Record, Soil Storage Area         07/03/06 On-Site Inspection   06/13-14/06 10/9/06 1 South of US 31                                                                 and Letter         I     _I 1oRevisions to packages signed after NRC review were administrative only - no changes to technical content.
The primary resources needed to determine the answer to the problem are two (2)technicians to perform fieldwork, one (1) technician to prepare the samples and conduct laboratory analyses, and two (2) survey team members to prepare and review the design, generate maps, coordinate field activities and evaluate data.2. IDENTIFY THE DECISION Several decisions need to be defined to address the stated problem.Principal Study Question (1): Does the mean concentration of residual radioactivity in the survey unit exceed the release criteria stated above?Decision (1): Determine whether the mean concentration of residual radioactivity in the survey exceeds the release criteria stated in the problem.Actions (1): Alternative actions include failure of the survey unit, remediation, or no action required.Data Quality Objectives FSS 03C 1 1 Page 1 of 5 Principal Study Question (2): Do any areas of elevated activity in the survey unit exceed the release criteria?The Decision (2): Determine if any areas of elevated activity in the survey unit exceed the release criteria.Actions (2): Alternative actions include confirmation and investigation, performing the elevated measurement comparison (EMC), remediation, or no action required.Principal Study Question (3): Is the potential dose from residual radioactivity in the survey unit ALARA as stated?The Decision (3): Determine if the potential dose from residual radioactivity in the survey unit is ALARA.ALARA requirements for soil remediation are defined in Chapter 4 of the LTP.Actions (3): Alternative actions include remediation or no action required.3. IDENTIFY INPUTS TO THE DECISION Information Needed: Characterization measurements are required to define the radionuclides present and determine the extent and variability of residual radioactivity in the survey area for design and implementation of the survey. Survey area classification, ALARA analysis, potential radionuclides of interest, and site-specific DCGL values are also required inputs to the decision process. The primary information required for evaluation is the analytical results of survey measurements.
Page 5 of 5
 
ATTACHMENT 2 CONSUMERS ENERGY BIG ROCKPOINT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION CLASS I FINAL STATUS SURVEY RELEASE RECORD, 03C 1 1, NORTH WEST PROTECTED AREA October 24, 2006 37 Pages
 
Class I Final Status Survey Release Record 03C1 l North West Protected Area SURVEY PACKAGE CLOSURE Final Status Survey Documentation is authorized for closure. All required reviews are complete and the evaluation of data results have satisfied the criteria established for unrestricted release.
Signed:                               Date:     /e)/6'-'-,
                          /    (ESSG)
Y Signed:                              Date:       /0-/(Df, (ES "Superintendent)
Signed:                              Date:      /o-/*-06
                        /    (RP & ES Manager)
 
Survey Area Requirements Final Status Survey, Release Record 03C 1 1 North West Protected Area Survey Description Final Status Survey 03C 11 encompasses 1956 m2 at or below the grade elevation present during plant power operations in the north west section of the Protected Area. No materials of plant origin remain in the survey area.
History During power operations the Protected Area supported the components and systems necessary for electrical generation. The location of Survey Unit 03 is adjacent to the transport route used to move spent resin and filter media for radiological survey and offsite removal. Structures and enclosures formerly located in this area were once used for the storage of contaminated materials. A detailed review of the history and radiological characterization of Survey Unit 3 is provided in Appendix 2B and 2E of the LTP (License Termination Plan).
Current Radiological Status Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Based on operational history and former locations of radioactive systems and material transport pathways the radiological status of this survey unit is Class 1.
Post-Construction Expectations Final Status Survey 03C11 will be performed in the following activity sequence:
: 1. Walkdown: Environmental Services Survey Group (ESSG) personnel will perform a walkdown assessment to ensure survey area preparations are complete and confirm that the following post-construction expectations have been satisfied as applicable:
            "   Groundwater and Surface water control is adequate
* All construction debris has been removed from the survey area
            "   The survey location status meets all applicable safety requirements
: 2. Survey Area Isolation and Control: Control measures will be established to ensure that any potential ongoing decommissioning activities in adjacent locations do not impact the current survey area status. Isolation and control measures include postings, barriers, access points, and the evaluation of ongoing work activities in adjacent areas.
Survey Area Requirements FSS 3C 11 Page 1 of 2
: 3. Survey Design and Execution: Survey design and execution will follow the Data Quality Objectives for 03Cl1 in accordance with the survey requirements established in procedures RM-76, Final Status Survey Design and RM-77, FinalStatus Survey Implementation, and LTP, Chapter 5. Survey size will be based on the statistical requirements of the Sign Test for Class 1 areas with soil samples collected in random start, systematic data point locations. Surface scanning will be performed with 100%
survey area coverage. This survey will be conducted in accordance with approved BRP procedures and follow the guidance of NUREG 1575.
: 4. Data Quality Assessment: Isolation and control of the survey area will be maintained until the survey Data Quality Assessment demonstrates that the regulatory requirements for unrestricted site release have been satisfied.
Survey Area Requirements FSS O3C1 Page 2 of 2
 
DATA QUALITY OBJECTIVES Final Status Survey, Release Record 03C11 North West Protected Area STATE THE PROBLEM The Problem:
To demonstrate that the level of residual radioactivity in Class 1 Survey Unit 03 does not exceed the release criteria of 25 mrem/year Total Effective Dose Equivalent (TEDE) as specified in the License Termination Plan (LTP).
Stakeholders:
The primary stakeholders interested in the answer to this problem are Consumers Energy Co., and the general public as represented by the Michigan Department of Environmental Quality (MDEQ), and the US Nuclear Regulatory Commission (USNRC).
The Planning Team:
The planning team consists of members of the BRP Environmental Services Survey Group (ESSG). The primary decision maker will be the Final Status Survey Supervisor.
The Final Status Survey Supervisor will obtain input from the site Construction Group and Scheduling Group for issues relating to schedule and costs.
Schedule:
Approximately five (5) working days are projected to implement the survey and to collect and analyze field data.
Resources:
The primary resources needed to determine the answer to the problem are two (2) technicians to perform fieldwork, one (1) technician to prepare the samples and conduct laboratory analyses, and two (2) survey team members to prepare and review the design, generate maps, coordinate field activities and evaluate data.
: 2. IDENTIFY THE DECISION Several decisions need to be defined to address the stated problem.
PrincipalStudy Question (1):
Does the mean concentration of residual radioactivity in the survey unit exceed the release criteria stated above?
Decision (1):
Determine whether the mean concentration of residual radioactivity in the survey exceeds the release criteria stated in the problem.
Actions (1):
Alternative actions include failure of the survey unit, remediation, or no action required.
Data Quality Objectives FSS 03C 1 1 Page 1 of 5
 
PrincipalStudy Question (2):
Do any areas of elevated activity in the survey unit exceed the release criteria?
The Decision (2):
Determine if any areas of elevated activity in the survey unit exceed the release criteria.
Actions (2):
Alternative actions include confirmation and investigation, performing the elevated measurement comparison (EMC), remediation, or no action required.
PrincipalStudy Question (3):
Is the potential dose from residual radioactivity in the survey unit ALARA as stated?
The Decision (3):
Determine if the potential dose from residual radioactivity in the survey unit is ALARA.
ALARA requirements for soil remediation are defined in Chapter 4 of the LTP.
Actions (3):
Alternative actions include remediation or no action required.
: 3. IDENTIFY INPUTS TO THE DECISION Information Needed:
Characterization measurements are required to define the radionuclides present and determine the extent and variability of residual radioactivity in the survey area for design and implementation of the survey. Survey area classification, ALARA analysis, potential radionuclides of interest, and site-specific DCGL values are also required inputs to the decision process. The primary information required for evaluation is the analytical results of survey measurements.
Source of the Information:
Source of the Information:
The soil sample data to be used for survey development are the radionuclide-specific measurements of representative soil samples collected for radiological characterization and excavated soil surveys conducted to determine suitability for transport of excavated soil to the SVA. The soil samples obtained were judgmentally selected as a result of multiple surveys conducted during the excavation and transport process. The ALARA analysis for potential soil remediation is provided in LTP, Section 4.4.. Site-specific DCGL values and BRP radionuclides of interest are defined in LTP Chapter 5, Table 5-1 and Procedure RM-76, Final Status Survey Design.The survey will be conducted in accordance with applicable regulatory guidance as established in LTP Chapter 5 for Class 1 areas. Soil samples will be utilized for radionuclide-specific measurements in this evaluation.
The soil sample data to be used for survey development are the radionuclide-specific measurements of representative soil samples collected for radiological characterization and excavated soil surveys conducted to determine suitability for transport of excavated soil to the SVA. The soil samples obtained were judgmentally selected as a result of multiple surveys conducted during the excavation and transport process. The ALARA analysis for potential soil remediation is provided in LTP, Section 4.4.. Site-specific DCGL values and BRP radionuclides of interest are defined in LTP Chapter 5, Table 5-1 and Procedure RM-76, Final Status Survey Design.
: 4. BOUNDARIES OF THE STUDY Boundaries of the Survey: The target population for this survey is the total thickness of prepared soil in the survey area of 1956 M 2.Data Quality Objectives FSS 03Cll Page 2 of 5 Temporal Boundaries:
The survey will be conducted in accordance with applicable regulatory guidance as established in LTP Chapter 5 for Class 1 areas. Soil samples will be utilized for radionuclide-specific measurements in this evaluation.
Scanning and sampling in this survey unit will only be performed during daylight hours under dry weather conditions.
: 4. BOUNDARIES OF THE STUDY Boundariesof the Survey:
Surface soils must be free of significant snow cover and standing water prior to surface scanning.
The target population for this survey is the total thickness of prepared soil in the survey area of 1956 M2 .
Soils must be in a non-frozen state or fragmented for collection to satisfy BRP procedural sampling requirements.
Data Quality Objectives FSS 03Cll Page 2 of 5
The anticipated start date for the survey is September 19, 2006.Constraints:
 
Temporal Boundaries:
Scanning and sampling in this survey unit will only be performed during daylight hours under dry weather conditions. Surface soils must be free of significant snow cover and standing water prior to surface scanning. Soils must be in a non-frozen state or fragmented for collection to satisfy BRP procedural sampling requirements. The anticipated start date for the survey is September 19, 2006.
Constraints:
Cold weather or rainy conditions may effect the operation of electronic equipment.
Cold weather or rainy conditions may effect the operation of electronic equipment.
Adverse weather conditions that include accumulations of rain or snow may limit area access and delay survey efforts.5. DEVELOP A DECISION RULE The following decision rules have been developed to define a logical process for choosing among alternative actions for the principal study questions associated with this survey area.Decision Rule (1): If all reported concentrations for residual radioactivity are less than the site-specific DCGL's and the unity rule has been satisfied for each sample, then the survey unit meets release criteria.
Adverse weather conditions that include accumulations of rain or snow may limit area access and delay survey efforts.
No further action is required.Decision Rule (2): If the mean value of activity in the survey unit is greater than the DCGL, then the survey unit fails to meet the release criteria.1 Remediate, resurvey, and evaluate the results relative to the decision rule.Decision Rule (3): If the mean activity in the survey unit is less than the DCGL and any individual sample measurement exceeds this value, conduct the Sign Test and the elevated measurement comparison (EMC) per LTP, Chapter 5 and Procedure RM-76, Final Status Survey Design. If the EMC and the Sign Test have been satisfied then the survey unit meets the release Criteria and no further action is required.
: 5.       DEVELOP A DECISION RULE The following decision rules have been developed to define a logical process for choosing among alternative actions for the principal study questions associated with this survey area.
If the EMC or the Sign Test has not been satisfied then remediate the area(s) of elevated activity, resurvey as appropriate, and evaluate the results relative to the decision rule.Decision Rule (4): If the potential dose from residual radioactivity in the survey unit is ALARA, then no further action is necessary.
Decision Rule (1):
If the potential dose from residual radioactivity in the survey unit is not ALARA, then remediate and resurvey.6. SPECIFY TOLERABLE LIMITS ON DECISION ERRORS The Null Hypothesis:
If all reported concentrations for residual radioactivity are less than the site-specific DCGL's and the unity rule has been satisfied for each sample, then the survey unit meets release criteria. No further action is required.
Decision Rule (2):
If the mean value of activity in the survey unit is greater than the DCGL, then the survey unit fails to meet the release criteria. 1 Remediate, resurvey, and evaluate the results relative to the decision rule.
Decision Rule (3):
If the mean activity in the survey unit is less than the DCGL and any individual sample measurement exceeds this value, conduct the Sign Test and the elevated measurement comparison (EMC) per LTP, Chapter 5 and Procedure RM-76, Final Status Survey Design. If the EMC and the Sign Test have been satisfied then the survey unit meets the release Criteria and no further action is required. If the EMC or the Sign Test has not been satisfied then remediate the area(s) of elevated activity, resurvey as appropriate, and evaluate the results relative to the decision rule.
Decision Rule (4):
If the potential dose from residual radioactivity in the survey unit is ALARA, then no further action is necessary. If the potential dose from residual radioactivity in the survey unit is not ALARA, then remediate and resurvey.
: 6.     SPECIFY TOLERABLE LIMITS ON DECISION ERRORS The Null Hypothesis:
It is assumed that residual radioactivity in the survey unit exceeds the release criterion.
It is assumed that residual radioactivity in the survey unit exceeds the release criterion.
1 When multiple radionuclides are present the mean activity value is determined as the average of the weighted sum. The DCGL of the weighted sum is 1.Data Quality Objectives FSS 03C 1 1 Page 3 of 5 Type I Error (a ): The a error is the maximum probability of rejecting the null hypotheses when it is true.Thea error is defined in the LTP at a value of 0.05 (5%) and cannot be changed to a less restrictive value unless prior approval is granted by the USNRC. The a error value of 0.05 will be used for survey planning and data assessment for this survey area.Type ilError (,8)6 The ,8 error is the probability of accepting the null hypothesis when it is false. A value of 0.05 (5%) will be used for survey planning and data assessment for this survey area.The Lower Bound of the Gray Region (LBGR): The LBGR is initially set at one-half the DCGLw for this survey unit. The LBGR may be adjusted during survey design to achieve an optimum relative shift between 1.0 and 3.0.Relative Shift (A/c): The relative shift will be maintained within the range of 1.0 and 3.0 by adjusting the LBGR as appropriate.
1 When multiple radionuclides are present the mean activity value is determined as the average of the weighted sum. The DCGL of the weighted sum is 1.
: 7. OPTIMIZE DESIGN FOR OBTAINING DATA Statistical Test Sign Test: Radionuclides of potential plant origin also present in soil as background activity resulting from fallout constitute only a small fraction of the DCGL. Therefore, the Sign Test will be used where applicable in the survey evaluation to determine if the survey area meets the requirements for unrestricted release.Number of Samples Determined:
Data Quality Objectives FSS 03C1 1 Page 3 of 5
The number of samples required for this survey will be determined based on the relative shift as defined by the requirements of the Sign Test (LTP, Chapter 5.) and Procedure RM-76, Final Status Survey Design. The LBGR is initially set at one-half the DCGL, and may be adjusted as necessary for optimizing the survey design to achieve a relative shift between 1.0 and 3.0. Sample point locations are to be determined using a random start, systematic square grid spacing.Judgmental Sampling: Co-60 is the most limiting radionuclide for identification by surface scanning; judgmental surface and subsurface core samples will be collected in any location that exceeds the scan investigation level.Scan Coverage: Scanning for this survey area will provide 100% coverage.Number of Samples for Quality Control: A minimum of 5% of the sample population will be collected for quality evaluation.
 
These samples may include sample splits, sample recounts, or third party sample Data Quality Objectives FSS 03C 1 1 Page 4 of 5 analysis.
Type I Error(a ):
Quality analyses will be conducted as defined in LTP, Chapter 5 and Procedure RM-79, Final Status Survey Quality Control.Additional Sample Analysis Requirements:
The a error is the maximum probability of rejecting the null hypotheses when it is true.
The area of soil excavation intersects the identified waterborne pathway for Tritium migration and shall require Tritium in soil analyses for a minimum of 10% of the sample population.
Thea error is defined in the LTP at a value of 0.05 (5%) and cannot be changed to a less restrictive value unless prior approval is granted by the USNRC. The a error value of 0.05 will be used for survey planning and data assessment for this survey area.
Soil samples will be collected in the same random locations as those selected for QA/QC evaluation and sent to an independent laboratory for Tritium analysis.
Type ilError(,8)6 The ,8 error is the probability of accepting the null hypothesis when it is false. A value of 0.05 (5%) will be used for survey planning and data assessment for this survey area.
Data results will be provided in the survey package.Investigation Levels: Investigation levels defined in LTP, Chapter 5 and BRP Procedure RM-76, Final Status Survey Design, shall be conservatively established for this survey as shown below: Investigation Levels for Survey 03C 1 1 Scan Measurement Soil Sample Analysis> DCGL > DCGLw The investigation levels for soil sample measurements are meant to include any individual radionuclide result greater than the site-specific DCGL or where the combined radionuclide values exceed the unity rule. Co-60 is the most limiting radionuclide for identification by surface scanning; further investigation will be initiated at any location that exceeds the Co-60 Scan DCGL of 1818 CPM above background as detailed in the survey design.Data Quality Objectives FSS 03C 1 1 Page 5 of 5 FINAL STATUS SURVEY DESIGN Release Record 03C 1 1 North West Protected Area Survey Unit Description Survey 03C, 1 encompasses an area of 1956 m 2 in the north west section of the Protected Area.No materials of plant origin exist in this survey unit.Soil Sample Design Scopina Data Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Input data for survey design were conservatively estimated based on supporting surveys of excavated soils resulting from subsurface structure and component removal within the Protected Area.Table 1 Input Data for Survey Design (pCi/g)Radionuclides Cs-137 Co-60 a* 0.524 0.255 DCGL 11.93 3.21*Survey data detailed in Attachment 1 Sample Requirements The number of sample data points for this survey is based on the requirements of the Sign Test.The Unity Rule is used for the presence of multiple radionuclides.
The Lower Bound of the Gray Region (LBGR):
The Standard Deviation of the weighted sum is described by the following:
The LBGR is initially set at one-half the DCGLw for this survey unit. The LBGR may be adjusted during survey design to achieve an optimum relative shift between 1.0 and 3.0.
Cy C'sS37 2 + OYCOBO 2 DcGLcsl 3 7) -t DCG-co 6 o)C3 ,/0.524 /2 (0.255 )2 a = 0.091 Relative Shift Relative Shift = DCGLw-LBGR Relative Shift = 1-0.818 0.091 Relative Shift = 2.0 With (x and P3 error levels set at 0.05 and the relative shift of 2.0, the Sign Test requires 15 sample data points (Table 5.5 NUREG 1575).Survey Design FSS 03C, 1 Page 1 of 7 Sample Locations Sample locations are selected in a random start, systematic square grid pattern with the southwest corner of the survey unit as origin (X=0, Y=0). Two numbers between 0 and 1 have been randomly selected and then applied to the survey unit maximum X and Y dimensions to determine the random start location as shown below: Table 2 Random Numbers Random #, X Axis Random #, Y Axis 0.353393 0.688176 Survey Unit Dimensions:
Relative Shift (A/c):
X = 40.0 meters Y = 48.9meters Random Start Location X = (0.353393)(40.0)  
The relative shift will be maintained within the range of 1.0 and 3.0 by adjusting the LBGR as appropriate.
= 14.1 meters With SW Corner Origin: Y = (0.688176)(48.9)  
: 7. OPTIMIZE DESIGN FOR OBTAINING DATA Statistical Test Sign Test:
= 33.7 meters Sample Spacing As a conservative measure sample spacing will be calculated based on 18 samples for this survey. Samples are located in a systematic square grid pattern with sample spacing determined by the following:
Radionuclides of potential plant origin also present in soil as background activity resulting from fallout constitute only a small fraction of the DCGL. Therefore, the Sign Test will be used where applicable in the survey evaluation to determine if the survey area meets the requirements for unrestricted release.
A nA Where: A= area of survey unit, and n = number of samples.1956 L 95-6 10.4 meters 18 With sample spacing established at 10.4 meters, 20 data points are available for this survey.Data point locations are identified in Attachment 2.QA/QC Sampling A minimum of 5% of the sample population and 5% of the scan survey area are required to be selected for QA/QC verification in accordance with BRP Procedure RM-79, Final Status Survey Quality Control. As a conservative measure, three (3) soil samples and 10% of the scan survey area will be selected for QA/QC evaluation.
Number of Samples Determined:
Data point locations for soil samples will be determined by random number selection.
The number of samples required for this survey will be determined based on the relative shift as defined by the requirements of the Sign Test (LTP, Chapter 5.) and Procedure RM-76, Final Status Survey Design. The LBGR is initially set at one-half the DCGL, and may be adjusted as necessary for optimizing the survey design to achieve a relative shift between 1.0 and 3.0. Sample point locations are to be determined using a random start, systematic square grid spacing.
The QA/QC scan starting point and track direction are also determined by random number selection.
Judgmental Sampling:
The first random data point selected will identify the scanning start point and the second random data point will determine the direction in which the scan will track. QA/QC location results are provided in Table 3 below: Survey Design FSS 03C 1 1 Page 2 of 7 Table 3 Random Numbers Generated for QA/QC QA/OC Soil Random Random Samples Sample erification Scan Sample_____sNumber Number Split Sample: 2 Start Point: 5 Sample Recount: 10 Scan Toward: 13 Sample Recount: 13 IScan Area Requirement:
Co-60 is the most limiting radionuclide for identification by surface scanning; judgmental surface and subsurface core samples will be collected in any location that exceeds the scan investigation level.
196 M2 Surface Scanning The coverage requirement for surface scanning in this Class 1 area is 100%. The Scan MDC has been established at fractional values of the DCGLwfor typical background activity levels at Big Rock Point. Scan MDC values for varying backgrounds are provided in Attachment  
Scan Coverage:
: 3. The investigation level for identification of potential areas of elevated activity in this survey area will be the Scan DCGL as defined by the following:
Scanning for this survey area will provide 100% coverage.
Number of Samples for Quality Control:
A minimum of 5% of the sample population will be collected for quality evaluation.
These samples may include sample splits, sample recounts, or third party sample Data Quality Objectives FSS 03C11 Page 4 of 5
 
analysis. Quality analyses will be conducted as defined in LTP, Chapter 5 and Procedure RM-79, Final Status Survey Quality Control.
Additional Sample Analysis Requirements:
The area of soil excavation intersects the identified waterborne pathway for Tritium migration and shall require Tritium in soil analyses for a minimum of 10% of the sample population. Soil samples will be collected in the same random locations as those selected for QA/QC evaluation and sent to an independent laboratory for Tritium analysis. Data results will be provided in the survey package.
Investigation Levels:
Investigation levels defined in LTP, Chapter 5 and BRP Procedure RM-76, Final Status Survey Design, shall be conservatively established for this survey as shown below:
Investigation Levels for Survey 03C1 1 Scan Measurement                   Soil Sample Analysis
                                > DCGL                             > DCGLw The investigation levels for soil sample measurements are meant to include any individual radionuclide result greater than the site-specific DCGL or where the combined radionuclide values exceed the unity rule. Co-60 is the most limiting radionuclide for identification by surface scanning; further investigation will be initiated at any location that exceeds the Co-60 Scan DCGL of 1818 CPM above background as detailed in the survey design.
Data Quality Objectives FSS 03C1 1 Page 5 of 5
 
FINAL STATUS SURVEY DESIGN Release Record 03C 11 North West Protected Area Survey Unit Description Survey 03C,1 encompasses an area of 1956 m2 in the north west section of the Protected Area.
No materials of plant origin exist in this survey unit.
Soil Sample Design Scopina Data Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Input data for survey design were conservatively estimated based on supporting surveys of excavated soils resulting from subsurface structure and component removal within the Protected Area.
Table 1 Input Data for Survey Design (pCi/g)
Radionuclides                     Cs-137                       Co-60 a*                         0.524                       0.255 DCGL                           11.93                       3.21
          *Survey data detailed in Attachment 1 Sample Requirements The number of sample data points for this survey is based on the requirements of the Sign Test.
The Unity Rule is used for the presence of multiple radionuclides. The Standard Deviation of the weighted sum is described by the following:
2 +      OYCOBO 2 Cy    C'sS37 DcGLcsl37)   -t DCG-co6 o)
C3
    ,/0.524 /2     (0.255 )2 a = 0.091 Relative Shift Relative Shift = DCGLw-LBGR Relative Shift = 1-0.818 0.091 Relative Shift = 2.0 With (xand P3   error levels set at 0.05 and the relative shift of 2.0, the Sign Test requires 15 sample data points (Table 5.5 NUREG 1575).
Survey Design FSS 03C, 1 Page 1 of 7
 
Sample Locations Sample locations are selected in a random start, systematic square grid pattern with the southwest corner of the survey unit as origin (X=0, Y=0). Two numbers between 0 and 1 have been randomly selected and then applied to the survey unit maximum X and Y dimensions to determine the random start location as shown below:
Table 2 Random Numbers Random #, X Axis             Random #, Y Axis 0.353393                   0.688176 Survey Unit Dimensions:         X = 40.0 meters Y = 48.9meters Random Start Location           X = (0.353393)(40.0) = 14.1 meters With SW Corner Origin:         Y = (0.688176)(48.9) = 33.7 meters Sample Spacing As a conservative measure sample spacing will be calculated based on 18 samples for this survey. Samples are located in a systematic square grid pattern with sample spacing determined by the following:
A nA Where: A= area of survey unit, and n = number of samples.
1956 L     95-6     10.4 meters 18 With sample spacing established at 10.4 meters, 20 data points are available for this survey.
Data point locations are identified in Attachment 2.
QA/QC Sampling A minimum of 5% of the sample population and 5% of the scan survey area are required to be selected for QA/QC verification in accordance with BRP Procedure RM-79, FinalStatus Survey Quality Control. As a conservative measure, three (3) soil samples and 10% of the scan survey area will be selected for QA/QC evaluation. Data point locations for soil samples will be determined by random number selection.
The QA/QC scan starting point and track direction are also determined by random number selection. The first random data point selected will identify the scanning start point and the second random data point will determine the direction in which the scan will track. QA/QC location results are provided in Table 3 below:
Survey Design FSS 03C11 Page 2 of 7
 
Table 3 Random Numbers Generated for QA/QC QA/OC Soil               Random                                                     Random Samples                 Sample         erification Scan                             Sample
_____sNumber                                                                      Number Split Sample:                 2     Start Point:                                         5 Sample Recount:               10     Scan Toward:                                         13 Sample Recount:               13     IScan Area Requirement:                             196 M2 Surface Scanning The coverage requirement for surface scanning in this Class 1 area is 100%. The Scan MDC has been established at fractional values of the DCGLwfor typical background activity levels at Big Rock Point. Scan MDC values for varying backgrounds are provided in Attachment 3. The investigation level for identification of potential areas of elevated activity in this survey area will be the Scan DCGL as defined by the following:
Scan DCGL = Detector Rating CPM
Scan DCGL = Detector Rating CPM
* Exposure Model uR/hr
* Exposure Model uR/hr
* DCGLw uR/hr pCi/g Scan DCGL for Co-60 = 1818 CPM Scan DCGL for Cs-137 = 3518 CPM Where: 1 Detector Rating = 1200 CPM Cs- 137 and 565 CPM Co -60 uR/hr uR/hr Exposure Model = 1.229uR/hr Cs-1 3 7 and 5.029 uR/hr Co-60 5pCi/g 5 pCi/g DCGLw = 11.93 pCi/g Cs-137 and 3.21 pCi/g Co-60 The DCGLw for Co-60 is the most limiting value for scanning measurements performed to identify areas of potentially elevated activity.
* DCGLw uR/hr                           pCi/g Scan DCGL for Co-60 = 1818 CPM Scan DCGL for Cs-137 = 3518 CPM Where: 1 Detector Rating = 1200 CPM Cs- 137 and 565 CPM Co -60 uR/hr                     uR/hr Exposure Model = 1.229uR/hr Cs-             13 7 and 5.029 uR/hr Co-60 5pCi/g                       5 pCi/g DCGLw = 11.93 pCi/g Cs-137 and 3.21 pCi/g Co-60 The DCGLw for Co-60 is the most limiting value for scanning measurements performed to identify areas of potentially elevated activity. Scanning conducted for this survey will assume all residual radioactivity to originate from Co-60 and the instrument response at the Co-60 DCGLw (1818 cpm) will be used as the scanning investigation level for FSS 03C1 1.
Scanning conducted for this survey will assume all residual radioactivity to originate from Co-60 and the instrument response at the Co-60 DCGLw (1818 cpm)will be used as the scanning investigation level for FSS 03C 1 1.1 These values established in EA-BRP-SC-0201, Nal Scanning Sensitivity for Open Land Survey.Survey Design FSS 03ClI Page 3 of 7 Attachment 1 Design Data -FSS 03C 1 1 Protected Area Supporting Surveys Cs-1 37 Co-60 Survey No. Sequence Activity Activity No. (pCilg) (pCilg)HH060705 .165388 .26" .66 HH660705ý 1653ý9 0.06 07W6*HH060705" 16540 i-.05 -B062805 16755 1: t.16 -' 0.27-,,,,-TB062805 16756 ,0.147, _ _031_ _" VTB062805,,-
1 These values established in EA-BRP-SC-0201, Nal Scanning Sensitivity for Open Land Survey.
16774 0.9.3 Mean: 0.698 Std Dev: 0.524 0.352 0.255* Measurement system MDA -Co-60 not identified in this sample Survey Design FSS 03C 1 1 Page 4 of 7 Attachment 2 Soil Sample Locations  
Survey Design FSS 03ClI Page 3 of 7
-Survey 03C 1 1 North West Protected Area_11U I III II-. I q-ij Y= 48.9 m s o1 S30 5 7 1 2 8 1 91 01 11 21 3 3 1 4 7 1 81 9I O5 11 5 2 X=40 234 25 10 207 208 2D9-Survey Unit 03C_1* Sample Location 0 5 10 2 Mes i 0 B 6 S tiam pie spacing 15 1 U.' MeiMr Survey Design FSS 03C 1 1 Page 5 of 7 Attachment 3 Scan MDC In Varying Backgrounds Background d' j Si MDCRsurveyor Cs-1 37 Co-60 Cs-1 37 Co-60 2000 2.48 4 28.64 607.47 0.51 1.08 2.06 1.07 i 4 2;4-8 A___ 32.02:
 
10.5 , ý260&2130  
Attachment 1 Design Data - FSS 03C 11 Protected Area Supporting Surveys Cs-1 37           Co-60 Survey No. Sequence           Activity         Activity No.           (pCilg)           (pCilg)
.2 1,20-3000 2.48 4 35.07 744.00 0.62 1.32 2.52 1.31*3500 2.48 4 37.88 803.61 0.67 1.42 2.72 1.41 4000 2.48 4 40.50 859.10 0.72 1.52 2.91 1.51 4500 2.48 4 42.95 911.21 0.76 1.61 3.09 1.60 5500 2.48 4 47.49 1,007.38 0.84 1.78 3.42 1.77 6000 2.48 4 49.60 1,052.17 0.88 1.86 3.57 1.85 6500 2.48 4 51.63 1,095.14 0.91 1.94 3.71 1.93 7000 2.48 4 53.57 1,136.48 0.95 2.01 3.85 2.00 8000 2.48 4 57.27 1,214.95 1.01 2.15 4.12 2.14 8500 2.48 4 59.04 1,252.34 1.04 2.22 4.25 2.20 9000 2.48 4 60.75 1,288.65 1.07 2.28 4.37 2.27 9500 2.48 4 62.41 1,323.96 1.10 2.34 4.49 2.33 10500 2.48 4 65.61 1,391.90 1.16 2.46 4.72 2.45 11000 2.48 4 67.16 1,424.65 1.19 2.52 4.83 2.51 11500 2.48 4 68.67 1,456.67 1.21 2.58 4.94 2.56 12000 2.48 4 70.14 1,488.00 1.24 2.63. 5.04 2.62 1 2,'0d0 2"8 4 7.9 "~5 .8 1. .2 2.659~ 516 2.6 13000 2.48 4 73.01 1,548.76 1.29 2.74 5.25 2.73 13500 2.48 4 74.40 1,578.26 1.32 2.79 5.35 2.78 14000 2.48 4 75.77 1,607.22 1.34 2.84 5.45 2.83 14500 2.48 4 77.11 1,635.67 1.36 2.89 5.55 2.88-< i 5' 740u6636 1 U 2.4 ,Modeloo&Exposuire (uR/hr 5)-, CV -U6i'Survey Design FSS 03C 1 Page 6 of 7 Attachment 4 Area Factors for Open Land Survey Evaluation Conamiae Calculated Area Factors at Time of Peak Dose Area (Mt) H-3 Mn-54 Fe-55 Co-60 Sr-90 Cs-137 Eu-152 Eu-154 Eu-155 8094 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 4047 1.00 1.01 1.00 1.01 1.00 1.02 1.02 1.01 1.02 2024 1.00 1.03 1.00 1.03 1.00 1.03 1.03 1.03 1.03 1012 1.35 1.04 1.00 1.04 1.00 1.04 1.05 1.04 1.04 506 2.91 1.09 1.98 1.08 1.98 1.13 1.07 1.07 1.06 253 6.05 1.14 3.95 1.13 3.94 1.20 1.11 1.11 1.09 126 12.4 1.20 7.93 1.20 7.87 1.29 1.17 1.16 1.14 63 24.9 1.30 15.8 1.30 15.6 1.41 1.27 1.26 1.23 32 49.2 1.49 31.2 1.49 30.5 1.62 1.44 1.45 1.39 16 98.9 1.78 62.0 1.78 59.9 1.93 1.72 1.73 1.63 8 198 2.38 123 2.38 117 2.58 2.30 2.31 2.14 4 397 3.61 243 3.62 230 3.91 3.49 3.52 3.19 2 794 5.68 473 5.75 452 6.14 5.48 5.55 4.90 1 1590 9.57 905 9.73 887 10.3 9.24 9.39 7.88 Survey Design FSS 03C 1 l Page 7 of 7 RM-76 FINAL STATUS SURVEY DESIGN Revision 1 Page 19 of 19 RM-76-5 FINAL STATUS SURVEY APPROVAL AND AUTHORIZATION FOR IMPLEMENTATION Survey Code 03C, 1 Survey Area
HH060705         .165388 *          .26"         .66 HH660705&#xfd;         1653&#xfd;9           0.06             07W6*
HH060705"         16540           i-.05             0*66
  -B062805         16755           t.16 1: - '           0.27-
,,,,-TB062805       16756         ,0.147,       _     _031_ _"
VTB062805,,-       16774           0.9.3 Mean:       0.698             0.352 Std Dev:       0.524             0.255
* Measurement system MDA - Co-60 not identified in this sample Survey Design FSS 03C11 Page 4 of 7
 
Attachment 2 Soil Sample Locations - Survey 03C1 1 North West Protected Area
_11U    I   III             II-. I     q-ij Y= 48.9 m                                                               57 s o1           S30 1 91         01             11               21       33 12 8 1 81         9I             O5             11       52 14 7 X=40 25                 10     207             208       2D9 234
                -         Survey Unit 03C_1 0
i   0 5
B   6 10 S
2  Mes
* Sample Location tiam pie spacing 15 1U.' MeiMr Survey Design FSS 03C11 Page 5 of 7
 
Attachment 3 Scan MDC In Varying Backgrounds Background       d'       j         Si       MDCRsurveyor   Cs-1 37   Co-60   Cs-1 37 Co-60 2000       2.48       4       28.64         607.47       0.51     1.08   2.06   1.07 i           4 2;4-8
            *d:Q$        A___     32.02:   -69.I8<-**'            ,   &#xfd;260&2130 10.5            1,20-
                                                                                      .2 3000       2.48       4       35.07         744.00       0.62     1.32   2.52   1.31
  *3500       2.48       4       37.88         803.61       0.67     1.42   2.72   1.41 4000       2.48       4       40.50         859.10       0.72     1.52   2.91   1.51 4500       2.48       4       42.95         911.21       0.76     1.61   3.09   1.60 5500       2.48     4       47.49       1,007.38       0.84     1.78   3.42   1.77 6000       2.48     4       49.60       1,052.17       0.88     1.86   3.57   1.85 6500       2.48     4       51.63       1,095.14       0.91     1.94   3.71   1.93 7000     2.48       4       53.57       1,136.48       0.95     2.01   3.85   2.00 8000     2.48       4       57.27       1,214.95       1.01     2.15   4.12   2.14 8500     2.48       4       59.04       1,252.34       1.04     2.22   4.25   2.20 9000     2.48       4       60.75       1,288.65       1.07     2.28   4.37   2.27 9500     2.48       4       62.41       1,323.96       1.10     2.34   4.49   2.33 10500     2.48       4       65.61       1,391.90       1.16     2.46     4.72   2.45 11000     2.48       4       67.16       1,424.65       1.19     2.52     4.83   2.51 11500     2.48       4       68.67       1,456.67       1.21     2.58     4.94   2.56 12000     2.48       4       70.14       1,488.00       1.24     2.63. 5.04   2.62 12,'0d0   2"8 "~5    4       7.9                 .8     1..2     2.659~ 516       2.6 13000     2.48       4       73.01       1,548.76       1.29     2.74     5.25   2.73 13500     2.48       4       74.40       1,578.26       1.32     2.79   5.35   2.78 14000     2.48       4       75.77       1,607.22       1.34     2.84     5.45   2.83 14500     2.48       4       77.11       1,635.67       1.36     2.89     5.55   2.88
              <     i 5'         740u6636       -        1     U     2.4
  ,Modeloo&Exposuire (uR/hr     5)-,CV-U&#x17d;6i' Survey Design FSS 03C 1 Page 6 of 7
 
Attachment 4 Area Factors for Open Land Survey Evaluation Conamiae Calculated Area Factors at Time of Peak Dose Area (Mt) H-3   Mn-54   Fe-55 Co-60           Sr-90 Cs-137 Eu-152 Eu-154 Eu-155 8094     1.00   1.00   1.00     1.00         1.00 1.00   1.00   1.00 1.00 4047     1.00   1.01   1.00     1.01         1.00 1.02   1.02   1.01 1.02 2024     1.00   1.03   1.00     1.03         1.00 1.03   1.03   1.03 1.03 1012     1.35   1.04   1.00     1.04         1.00 1.04   1.05   1.04 1.04 506   2.91   1.09   1.98     1.08         1.98 1.13   1.07   1.07 1.06 253     6.05   1.14   3.95     1.13         3.94 1.20   1.11   1.11 1.09 126     12.4   1.20   7.93     1.20         7.87 1.29   1.17   1.16 1.14 63     24.9   1.30   15.8     1.30         15.6 1.41   1.27   1.26 1.23 32     49.2   1.49   31.2     1.49         30.5 1.62   1.44   1.45 1.39 16   98.9   1.78   62.0     1.78         59.9 1.93   1.72   1.73 1.63 8     198   2.38   123     2.38         117   2.58   2.30   2.31 2.14 4     397   3.61   243     3.62         230   3.91   3.49   3.52 3.19 2     794   5.68   473     5.75         452   6.14   5.48   5.55 4.90 1   1590   9.57   905     9.73         887   10.3   9.24   9.39 7.88 Survey Design FSS 03C 1l Page 7 of 7
 
RM-76                                                                         Revision 1 FINAL STATUS SURVEY DESIGN                                               Page 19 of 19 RM-76-5 FINAL STATUS SURVEY APPROVAL AND AUTHORIZATION FOR IMPLEMENTATION Survey Code     03C, 1 Survey Area


== Description:==
== Description:==


Final Status Survey 03C,1 encompasses 1956 m 2 at or below the grade elevation present during plant power operations in the north west section of the Protected Area. No materials of plant origin remain in the survey area.The survey area is authorized for Final Status Survey Implementation.
Final Status Survey 03C,1 encompasses 1956 m 2 at or below the grade elevation present during plant power operations in the north west section of the Protected Area. No materials of plant origin remain in the survey area.
by Technical Review by 09 Dat Date Date RM-76.doc RM-77 Revision 2 FINAL STATUS SURVEY IMPLEMENTATION Page 8 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 1 of 3 Step Initial Date (+)1.0 PREPARATION FOR SURVEY (DE_ I Survey 1.1 Survey Area Status:_ a. Final Status Survey Design has been approved for implementation (see RM-76-5, Final Status Survey Approval and Authorization for Supplementation).
The survey area is authorized for Final Status Survey Implementation.
: 1. Survey area walkdown complete 2. Survey area determined ready for FSS 3. Decommissioning activities that may impact the environmental status of the survey area have been completed.
09    Dat by                         Date Technical Review by                     Date RM-76.doc
: 4. Survey area environment is controlled by barriers LP and postings or other approved method to restrict SSG access.___ b. Survey area has been turned over to the Environmental Services Survey Group (ESSG) in acceptable condition for FSS.1.2 Field Preparation:
 
: a. Survey unit boundaries delineated (Step 6.1.1)_7 b. Statistical soil samples predetermined in the survey design are located and marked within the survey unit.(Step 6.1.2)c. Soil sample locations verified (Step 6.1.2.c)_.Z d. Instruments and equipment have been collected and calibrated for data measurement and collection (Step 6.1.3) a]LO____ e. Field documentation is prepared (Step 6.1.4) -/SSG RM-77.doc RM-77 FINAL STATUS SURVEY IMPLEMENTATION Revision 2 Page 9 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 2 of 3 Initial Date 2.0 DATA COLLECTION 2.1 Soil Survey: All soil samples collected and controlled (Step 6.2.1). 10J~2.2 Surface Scan: Surface Scan complete.
RM-77                                                                         Revision 2 FINAL STATUS SURVEY IMPLEMENTATION                                         Page 8 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 1 of 3 Step                                                                   Initial   Date
Action response requirements have been conducted on any identified areas exceeding the investigation level (Step 6.3).LZZ- .PE-S _SG~4~kLo 2.3' Judgmental Soil Samples: a. Judgmental soil samples have been collected and controlled (Step 6.2.3).b. Deep core profiles performed in areas identified to contain elevated residual activity (Step 6.2.3).3.0 SAMPLE PREPARATION AND LABORATORY ANALYSIS 3.1 Sample Preparation (Step 6.4.1): a. Soil samples are homogenous
(+)
_AZ b. Soil samples are visibly dry prior to packing# c. Non-soil materials have been removed from sample d. Soil samples have been transferred to one-liter Marinelli containers and are labeled and sealed.SESSG 449"'"IE _SS G O~q 1c93Id RM-77.doc RM-77 FINAL STATUS SURVEY IMPLEMENTATION Revision 2 Page 10 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 3 of 3 Initial Date 3.2 Laboratory Analysis:-< Isotopic analyses are complete.
1.0   PREPARATION FOR SURVEY               (DE_       I Survey 1.1   Survey Area Status:
The spectroscopy report requires a signature of completion by the laboratory analyst and a signature of evaluation documenting that a second level review has been performed (Step 6.4.2).3.3 Sample Control and Documentation:-Z Chain of custody documentation exhibits control of soil samples (Step 6.4.3).'&#xfd;"-ESSG alad'&#xfd;T'ESSG kRe~viewed by Date RM-77.doc RM-59 Revision 11 SAMPLING AND ANALYSIS OF OPEN LAND Page 7 of 13 AREAS FOR SITE CHARACTERIZATION SURVEYS ATTACHMENT RM-59-1 SAMPLING AND ANALYSIS REPORT Date: 09-19-2006 Time: 1600 Location:
_     a. Final Status Survey Design has been approved for implementation (see RM-76-5, Final Status Survey Approval and Authorization for Supplementation).
03C0 1 1 Tech: TRS/WMH/JNS SURVEY IDENTIFICATION  
: 1.     Survey area walkdown complete
/ DESCRIPTION Survey 03C 1 1 encompasses 1956 m2 at or below the grade elevation present during plant oower woerations in the north west section of the Protected Area. No materials of plant origin remain in this area.SURVEY TYPE Survey Type: Characterization X Scan (Motive)Remediation X Final Scan (Static)Trenching and Digging (use RM-59-4)SURVEY DESIGN Sample Collection:
: 2.     Survey area determined ready for FSS
_ Judgmental
: 3.     Decommissioning activities that may impact the environmental status of the survey area have been completed.
_ Random X Systematic
: 4.     Survey area environment is controlled by barriers                   LP and postings or other approved method to restrict   SSG access.
_ Large Container Assay Scan Coverage:
___   b. Survey area has been turned over to the Environmental Services Survey Group (ESSG) in acceptable condition for FSS.
100%ANALYSIS Inst.SN/Cal Due 186201/09-30-2006 DAILY CHECK: X SAT UNSAT INIT: TRS Inst.SN/Cal Due 186194/02-08-2007 DAILY CHECK: X SAT UNSAT INIT: TRS Inst.SN/Cal Due 193709/02-21-2007 DAILY CHECK: X SAT UNSAT INIT: TRS Inst.SN/CaI Due Det.# 6 DAILY CHECK: X SAT UNSAT INIT: JP Inst.SN/Cal Due DAILY CHECK: SAT UNSAT INIT: Investigation of Unidentified Peaks: X SAT UNSAT INIT: JLR Minimum Detectable Activity (Section 5.3.2) X SAT UNSAT INIT: JLR COMMENTS Survey 03C 1 , was performed in a random start, square grid. systematic sampling pattern with samples collected at 20 data point locations.
1.2   Field Preparation:
Laboratory analyses did not identify residual radioactivity above trace levels of the DCGL value. Surface scanning identified no areas of elevated residual radioactivity.
: a.     Survey unit boundaries delineated (Step 6.1.1)
The results of the QA/QC verification scan (10%) were consistent with the findings of the primary survey scan.Technician Sionature:i 5 Date: 94--Second Level Review Signature:
_7   b.     Statistical soil samples predetermined in the survey design are located and marked within the survey unit.
Date: l/"o /RM-59.doc Soil Sample Activity Summary Release Record 03C 1 1 North West Protected Area 109 Y =489 m 50 128 147 166 185 204 110 111 112 11i 3 -4* -'1 9@16 148 167 04 186 40 130@15 149@Wo 168187 2 131 i14 1)o 169 188 a3 132 013 151 912 170 Op 189 4 0 57 133 152 171 190 X =40 m 209 205 206 207 208 Survey Unit 03C1_1 0 Sample Location 0 5 10 20 Meters I i I I 1 S a i Surface Scan Summary Release Record 03C11 North West Protected Area 4,3 , 3.7 4.E 3 16 3.6 4.3 4.5 3.7 3.5 4.9 3.5 3,8 3.1 4.9 I I 3.9 3.6*14 4.1 04.7 oil 3.9 5.1 3.4 w 3.6 i;3 3.6 5.0 012 3.5 3,7 3.3 4.9 052
(Step 6.1.2)
* 5.4 3.8 3.7.1 3.2 O.4.1 3.4 3.43.6 w~3. 3.2 &#xfd; 1 Survey Unit 03C1_1* Sample Location 0 5 10 20 MOM I M a a i i i i RED BLUE GREY Values are Average Mobile Scan General Area Activity (kcpm)Values are Average Verification Scan General Area Activity (kcpm)Values are Average General Background Area Activity (kcpm)Afoa~cq du 4-&#xfd;j, {N"L Primary Scan : .O. %Tochnildin Signature:
: c.     Soil sample locations verified (Step 6.1.2.c)
Dia:Time: QC Verification Scan: it %Technician Signature:
_.Z     d.     Instruments and equipment have been collected and calibrated for data measurement and collection (Step 6.1.3)
Do 9 -19 9 o RM-72 SAMPLE CHAIN-OF-CUSI Revision 0 Page 4of 5 o9- 03C 1 1 RM-72-1 CHAIN-OF-CUSTODY RECORD Sample Number Sampling Location Date Time Final Disposition of Sample 1 Grid # 186 (3.7) (2.5) f-1.. "O vr-,,o0z'.
* a]LO
2 Grid # 187 (4.1) (2.5) f-'(o,4 /9Z7-2 QASplit Grid# 187 (4.1) (2.5) f-i-,. e,,I 3 Grid # 188 (4.5) (2.5) 9-R,0--o-13Z 5 4 Grid # 189 (4.9) (2.5) /j Z-5 Grid # 170 (4.9) (2.9) -8 /6 Grid # 169 (4.5) (2.9) 7"(/'oe -7 Grid # 168 (4.1) (2.9) /3..8 Grid # 167 (3.7) (2.9) f -g-T-, i3SY 9 Grid # 148 (3.7) (3.3) .10 (R) Grid # 149 (4.1) (3.3) 11 Grid # 150 (4.5) (3.3) '.../:(,k  
____  e.     Field documentation is prepared (Step 6.1.4)             -/SSG RM-77.doc
/3i'/12 Grid # 151 (4.9) (3.3) 9-'.-. /,.'," 13 (R) Grid # 132 (4.9) (3.7) -o /3'i 14 Grid # 131 (4.5) (3.7) /S,, ig'15 Grid # 130 (4.1) (3.7) ?-&9-o0 &.19 16 Grid # 129 (3.7) (3.7) -/.?ZO 17 Grid# 53 (3.7) (4.1) f/9t-, .18 Grid# 54 (4.1) (4.1) 9'.k. /3z-19 Grid # 55 (4.5) (4.1) -20 Grid # 56 (4.9) (4.1) -/3z9 (Samples may be analyzed and stored, shipped for offsite evaluation or analyzed and disposed of.)1.R linjUish Date Time Received in good condition by: 2. Relinquished by: 4 Date Time Received in good condition by: 3. Relinquished by: Date Time Received in good condition by: 4. Relinquished by: Date Time Received in good condition by: RM-72.doc RM-78 FINAL STATUS SURVEY ASSESSMENT Revision 2 Page 19 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 1 of 8 o3C2/FINAL STATUS SURVEY: 1.0 1.1 1.2 DATA VERIFICATION Data Acceptance Review the Implementation Checklist (RM-77-1) to verify that survey isolation and control measures were executed prior to FSS and are being maintained.
 
Review RM-77, Final Status Survey Implementation, to verify that methods,.techniques, and survey activities required for FSS have been applied in accordance with the appropriate procedures.
RM-77                                                                         Revision 2 FINAL STATUS SURVEY IMPLEMENTATION                                         Page 9 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 2 of 3 Initial     Date 2.0     DATA COLLECTION 2.1     Soil Survey:
Field QC Records: Review all assessments, Condition Reports and audits to ensure that identified issues have been resolved.Comments: Verify scan instrumentation was in calibration and the QC source checks were performed prior to and after surveys.Verify daily QC source checks for Canberra gamma spectroscopy detector properly logged prior to soil sample analysis.1.3 Review Verification:
All soil samples collected and controlled (Step 6.2.1).         E*SSG              10J~
Verify that the Data Quality Objectives are complete.Verify that the survey design has been technically reviewed.RM-78.doc RM-78 FINAL STATUS SURVEY ASSESSMENT Revision 2 Page 20 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 2 of 8 Verify that gamma spectroscopy results have received a technical review.Verify the Sample and Analysis Report (RM-59-1) is completed and reviewed.V/Data Verification Completed:
2.2     Surface Scan:
Comments&) No A ssessor6 ec a0-i 3-be Date RM-78.doc RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 21 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 3 of 8 2.0 DATA VALIDATION
Surface Scan complete. Action response requirements have been conducted on any identified areas exceeding the investigation level (Step 6.3).                               LZZ- . ~4~kLo PE-S_SG 2.3'   Judgmental Soil Samples:
: a.       Judgmental soil samples have been collected and controlled (Step 6.2.3).
: b.       Deep core profiles performed in areas identified to contain elevated residual activity (Step 6.2.3).
SESSG 3.0     SAMPLE PREPARATION AND LABORATORY ANALYSIS 3.1     Sample Preparation (Step 6.4.1):
: a.       Soil samples are homogenous Soil samples are visibly dry prior to packing
#_AZ    b.
: c.       Non-soil materials have been removed from sample
: d.       Soil samples have been transferred to one-liter Marinelli containers and are labeled and sealed.     449         O~q 1c93Id
                                                                      "'"IE
_SS G RM-77.doc
 
RM-77                                                                         Revision 2 FINAL STATUS SURVEY IMPLEMENTATION                                       Page 10 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 3 of 3 Initial     Date 3.2     Laboratory Analysis:
  -<     Isotopic analyses are complete. The spectroscopy report requires a signature of completion by the laboratory analyst and a signature of evaluation documenting that a second level review has been performed (Step 6.4.2).               '&#xfd;"-ESSG alad'&#xfd; 3.3   Sample Control and Documentation:
-Z       Chain of custody documentation exhibits control of soil samples (Step 6.4.3).
T'ESSG kRe~viewed by                   Date RM-77.doc
 
RM-59                                                                                                   Revision 11 SAMPLING AND ANALYSIS OF OPEN LAND                                                                     Page 7 of 13 AREAS FOR SITE CHARACTERIZATION SURVEYS ATTACHMENT RM-59-1 SAMPLING AND ANALYSIS REPORT Date: 09-19-2006               Time: 1600                 Location: 03C011                  Tech: TRS/WMH/JNS SURVEY IDENTIFICATION / DESCRIPTION Survey 03C1 1 encompasses 1956 m2 at or below the grade elevation present during plant oower woerations in the north west section of the Protected Area. No materials of plant origin remain in this area.
SURVEY TYPE Survey Type:                         Characterization     X       Scan (Motive)
Remediation X       Final                         Scan (Static)
Trenching and Digging (use RM-59-4)
SURVEY DESIGN Sample Collection:       _     Judgmental     _     Random     X     Systematic     _     Large Container Assay Scan Coverage:           100%
ANALYSIS Inst.SN/Cal Due 186201/09-30-2006             DAILY CHECK:         X     SAT               UNSAT       INIT: TRS Inst.SN/Cal Due 186194/02-08-2007             DAILY CHECK:         X     SAT               UNSAT       INIT: TRS Inst.SN/Cal Due 193709/02-21-2007             DAILY CHECK:         X     SAT               UNSAT       INIT: TRS Inst.SN/CaI Due Det.# 6                       DAILY CHECK:         X     SAT               UNSAT       INIT: JP Inst.SN/Cal Due                               DAILY CHECK:                 SAT               UNSAT       INIT:
Investigation of Unidentified Peaks:                                 X     SAT               UNSAT       INIT: JLR Minimum Detectable Activity (Section 5.3.2)                         X     SAT               UNSAT       INIT: JLR COMMENTS Survey 03C ,1 was performed in a random start, square grid. systematic sampling pattern with samples collected at 20 data point locations. Laboratory analyses did not identify residual radioactivity above trace levels of the DCGL value. Surface scanning identified no areas of elevated residual radioactivity. The results of the QA/QC verification scan (10%) were consistent with the findings of the primary survey scan.
Technician Sionature:i                                                         5   Date:     94--
Second Level Review Signature:                                                           Date:   l/"o   /
RM-59.doc
 
Soil Sample Activity Summary Release Record 03C11 North West Protected Area 109         110         111       112           11i3  -4*       -
Y =489 m 50                                                            57
                                        '1 9 128                      130        131          132        133
                @16         @15           i14           013 1)o           151       152 147          148          149
                            @Wo                        912 166          167          168        169            170       171 04          e*                          Op 187        188          189       190 185          186 2        a3                4 40                                      0 X =40 m 204          205         206         207           208       209 0         5   10           20 Meters Survey Unit 03C1_1            I       i   I I1    S a i 0    Sample Location
 
Surface Scan Summary Release Record 03C11 North West Protected Area 4,3 ,
3.7                                                               4.5 3       16 3.6 4.3             3.9 3.6          3.6 3.7
                                            *14          i;3 3,8                                        3.5 4.E  3.5 4.9      3.1 4.9           4.1       3.6 5.0 II oil04.7      012 3.5                         3.9              3,7 3.3                         4.9               4.1 5.1 052               5.4                       O.
3.8 3.7         3.2           3.4
                .1                           w                          3.4
:,&#xfd;I,* 3.6                      3.2 w~3.                       &#xfd;1     3.4 0       5   10                   20 MOM Survey Unit 03C1_1                  I   M a   a i   i     i   i
* Sample Location RED Values are Average Mobile Scan General Area Activity (kcpm)
BLUE Values are Average Verification Scan General Area Activity (kcpm)
GREY Values are Average General Background Area Activity (kcpm) du Afoa~cq N"L 4 {
                                                      -&#xfd;j, Primary Scan :           .O.           %
Tochnildin Signature:                           Dia:
                                                                            *_i    Time:
QC Verification Scan:           it     %
Technician Signature:                           Do   9 -199 o
 
RM-72                                                                                                         Revision 0 SAMPLE CHAIN-OF-CUSI                                                                                         Page 4of 5 o9-                 03C11 RM-72-1 CHAIN-OF-CUSTODY RECORD Sample Number               Sampling Location                       Date           Time     Final Disposition of Sample 1                 Grid # 186     (3.7) (2.5)                 f-1..           /3.--*        "O   vr-,,o0z'.
2                 Grid # 187     (4.1)   (2.5)               f-'(o,4           /9Z7-2     QASplit     Grid# 187       (4.1)   (2.5)               f-i-,.     e,,I 3                 Grid # 188     (4.5) (2.5)                 9-R,0--o-         13Z 5 4                 Grid # 189     (4.9) (2.5)                                   /j Z-5                 Grid # 170     (4.9) (2.9)                         -8       /
6                 Grid # 169     (4.5) (2.9)                 7"(/'oe             -
7                 Grid # 168     (4.1) (2.9)                                 /3..
8                 Grid # 167     (3.7) (2.9)               f -g-T-,           i3SY 9                 Grid # 148     (3.7) (3.3)               7-,-o*-              .
10         (R)   Grid # 149     (4.1) (3.3)             '.-*f-              /Ii*
11                 Grid # 150     (4.5) (3.3)               '.../:(,k           /3i'/
12                 Grid # 151     (4.9) (3.3)               9-'.-.               /,.',*"
13         (R)   Grid # 132     (4.9) (3.7)                     -o             /3'i 14                 Grid # 131     (4.5) (3.7)                                   /S,,ig' 15                 Grid # 130     (4.1) (3.7)                 ?-&9-o0           &.19 16                 Grid # 129     (3.7) (3.7)                     -             /.?ZO 17                 Grid#   53     (3.7) (4.1)               f/9t-,                     .
18                 Grid#   54     (4.1)   (4.1)             9
                                                                    '.*k.         /3z-19                 Grid # 55     (4.5) (4.1)                     -             /5j*
20                 Grid # 56     (4.9) (4.1)                     -             /3z9 (Samples may be analyzed and stored, shipped for offsite evaluation or analyzed and disposed of.)
1.R linjUish                               Date                 Time                   Received in good condition by:
: 2. Relinquished by:     4                   Date                 Time                   Received in good condition by:
: 3. Relinquished by:                         Date                 Time                   Received in good condition by:
: 4. Relinquished by:                       Date                 Time                   Received in good condition by:
RM-72.doc
 
RM-78                                                                       Revision 2 FINAL STATUS SURVEY ASSESSMENT                                           Page 19 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 1 of 8 FINAL STATUS SURVEY:             o3C2/
1.0       DATA VERIFICATION 1.1       Data Acceptance Review the Implementation Checklist (RM-77-1) to verify that survey isolation and control measures were executed prior to FSS and are being maintained.
Review RM-77, Final Status Survey Implementation, to verify that methods,
          .techniques, and survey activities required for FSS have been applied in accordance with the appropriate procedures.
1.2      Field QC Records:
Review all assessments, Condition Reports and audits to ensure that identified issues have been resolved.
Comments:
Verify scan instrumentation was in calibration and the QC source checks were performed prior to and after surveys.
Verify daily QC source checks for Canberra gamma spectroscopy detector properly logged prior to soil sample analysis.
1.3       Review Verification:
Verify that the Data Quality Objectives are complete.
Verify that the survey design has been technically reviewed.
RM-78.doc
 
RM-78                                                                         Revision 2 FINAL STATUS SURVEY ASSESSMENT                                           Page 20 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 2 of 8 Verify that gamma spectroscopy results have received a technical review.
V/      Verify the Sample and Analysis Report (RM-59-1) is completed and reviewed.
Data Verification Completed:   &)     No Comments ec           a0-i 3-be Date Assessor6 RM-78.doc
 
RM-78                                                                             Revision 2 FINAL STATUS SURVEY ASSESSMENT                                                 Page 21 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 3 of 8 2.0         DATA VALIDATION 2.1          Documentation Review:
Perform documentation review for quality control purposes and validate the data collected is complete and appropriate for use as defined by the survey design. Documentation includes:
                    &sect;Field measurement records
            .. ,*    Chain-of-custody
__j    Quality Control (QC) measurement records Current qualification of survey personnel Corrective Action Reports v1'    Data inputs (laboratory spectroscopy)
Sample preparation techniques 2.2        Detection Limit Review:
XScan MDCs are below established site DCGLs.
Forced-count values are assigned as necessary when activity is not detected in a sample.
Minimum Detectable Concentration (MDC) values of gamma spectroscopy are below established DCGLs.
2.3        Quality Control (QC) Data Review:
* Quality Control (QC) data results have received required reviews and are complete and consistent.
          ..      1 Results of judgmental samples have been reviewed and evaluated.
          .Z        Review to ensure that the analytical results of judgmental samples do not impact the evaluation for unrestricted release of the survey area.
RM-78.doc
 
RM-78                                                                            Revision 2 FINAL STATUS SURVEY ASSESSMENT                                              Page 22 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 4 of 8 2.4      Qualification of Data:
Statistical radionuclide-specific measurements for completeness. Evaluate the survey for determination of data usability and confirm that sufficient qualified data are present for the decision process.
: a.      Total number of statistical samples planned for the survey:    /J_ "
: b.      Total number of statistical samples determined as valid:        Q b x120
: c.      Calculate % Completeness:
a QQualified data      are :=400% completeness and are sufficient to support the Sign Test requirement for determination of unrestricted release.
Data Validation Completed:                  No Comments:
                                              /De -?-0(
Assessor                      Date RM-78.doc
 
RM-78                                                                                Revision 2 FINAL STATUS SURVEY ASSESSMENT                                                  Page 23 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 5 of 8 3.0      DATA QUALITY ASSESSMENT 3.1      Review the DQOs and Survey Design:
_          Confirm that all inputs to the decision have been reviewed and are complete.
____  Verify that boundaries or constraints identified in the survey area have not affected the quality of the data.
__        Review the Statement of Hypothesis and confirm that it remains relevant.
z..__  Confirm that Type I and Type II error limits are consistent with DQOs.
___      Confirm that the survey design is consistent with DQOs and that the appropriate number of data points were obtained.
3.2      Preliminary Review:
3.2.1    Preliminary Evaluation:
___    Quality Assessment (QA) reports consistent with procedure RM-79, Final Status Survey Quality Control.
Survey is of sufficient intensity to satisfy classification requirement.
____  Potential trends of radioactivity levels in the survey area do not impact a decision for unrestricted release.
Comments:
RM-78.doc


===2.1 Documentation===
RM-78                                                                                    Revision 2 FINAL STATUS SURVEY ASSESSMENT                                                      Page 24 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 6 of 8 3.2.2    Calculate Basic Statistical Quantities:
: a.          Number of qualified data points                *0
: b.          Calculation of the Mean                        fL*1Jrs.#
: c.          Calculation of the Median                          /a
: d.            Calculation Standard Deviation            ,1. 1/0 Cso)
          .!L          Attach graphic representation of the data if any radionuclide-specific measurements exceed 50% of the DCGL.
          ,jSample                QA/QC measurements consistent with FSS data 3.3      Statistical Evaluation:
NOTE:            If all measurement data are less than the DCGLw, statistical testing in not required and the survey unit meets the regulatory requirement for unrestricted release.
7/' All survey measurements are below the DCGLW.
3.3.1    Verify Assumptions of the Survey Design
____Review            the posting plot to verify that the data exhibits spatial independence. Spatial trends must be investigated and resolved prior to further assessment.
V 7
Review to verify dispersion symmetry. The appearance of skewed data must be investigated for cause and documented prior to further assessment.
RM-78.doc


Review: Perform documentation review for quality control purposes and validate the data collected is complete and appropriate for use as defined by the survey design. Documentation includes:&sect;Field measurement records.., Chain-of-custody
RM-78                                                                        Revision 2 FINAL STATUS SURVEY ASSESSMENT                                            Page 25 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 7 of 8
__j Quality Control (QC) measurement records Current qualification of survey personnel Corrective Action Reports v1' Data inputs (laboratory spectroscopy)
____  Review the dataset standard deviation and range for data variance.
Sample preparation techniques
Questionable data must be investigated for cause and documented prior to further assessment.
__    Verify that the data exhibits adequate power and confirm that the sample size is sufficient to satisfy the DQOs.
3.4      Draw Conclusions from the Data:
3.4.1    Investigation Levels and Response Actions L      Determine if data resul! have exceeded any investigation level.
Document findings. 1/1a                !AveJt4e-,
3.4.2    Evaluation for Unrestricted Release Select applicable conclusion:
          ,//. Survey area acceptance criteria met and survey area satisfies the requirements for unrestricted release:
v/j    All concentrations are less than the DCGLw. The Null Hypothesis is rejected.
4        The mean concentration of the survey area is below the DCGLw but individual measurements in the survey unit exceed the DCGLw. The Sign Test and EMC evaluation are successful and the Null Hypothesis is rejected.
RM-78.doc


===2.2 Detection===
RM-78                                                                          Revision 2 FINAL STATUS SURVEY ASSESSMENT                                              Page 26 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 8 of 8
            ,        Survey area acceptance criteria not met and survey area fails to satisfy the requirements for unrestricted release:
SThe  mean concentration in the survey area exceeds the DCGLw. and the null hypothesis is confirmed.
                    .J/      The mean concentration of the survey area is below the DCGLw but individual measurements in the Unit exceed the DCGLw..
The Sign Test and EMC evaluation are unsuccessful and the null hypothesis is confirmed.
Data Quality Assessment Completed:            &          No Comments f/
Dat1e3-0 R      Assessor                        Date Revie          vi Te  K~nicaL'  e v iew                /Datei-ni c l ES Superintendent                        Date 10 -16, -o6 RP&ES Manager                            Date RM-78.doc


Limit Review: XScan MDCs are below established site DCGLs.Forced-count values are assigned as necessary when activity is not detected in a sample.Minimum Detectable Concentration (MDC) values of gamma spectroscopy are below established DCGLs.2.3 Quality Control (QC) Data Review: Quality Control (QC) data results have received required reviews and are complete and consistent.
RM-78-3, Attachment I Statistical Quantities Release Record 03C1 l North West Protected Area Sample              Cs-1 37            Co-60      Weighted          "Weighted Sum Number            (pCi/gm)          (pCi/gm)      Sum (SOR)             <DCGLw?          DCGL-W. Sum Sign 1              0.0591            0.0023        0.0057                  yes            0.9943    +1 2               0.0912            0.0288        0.0166                  yes            0.9834    +1 3               0.0698            0.0118        0.0095                  yes            0.9905    +1 4                0.0872            0.0012        0.0077                  yes            0.9923    +1 5              0.0638            0.0073        0.0076                  yes            0.9924    +1 6                0.2535            -0.0063        0.0193                  yes            0.9807    +1 7                0.0529            0.0243        0.0120                  yes            0.9880    +1 8                0.3983            0.0343        0.0441                  yes            0.9559    +1 9                0.1171            0.0110        0.0132                  yes            0.9868    +1 10              0.2412            0.0077        0.0226                  yes            0.9774    +1 11              0.0677            0.0010        0.0060                  yes            0.9940    +1 12              -0.0001            -0.0101        -0.0032                  yes            0.9968    +1 13                0.0114            0.0117        0.0046                  yes            0.9954    +1 14                0.0503            0.0210        0.0108                  yes            0.9892    +1 15                0.0834            0.0175        0.0124                  yes            0.9876    +1 16                0.1165            0.0552        0.0270                  yes            0.9730    +1 17              0.0651            -0.0035        0.0044                  yes            0.9956    +1 18              0.0558              0.0250        0.0125                  yes            0.9875    +1 19              0.0458            0.0254        0.0118                  yes            0.9882    +1 20              0.1818            0.0046        0.0167                  yes            0.9833    +1 Std. Dev            0.0955            0.0157        0.0100 Mean              0.1056            0.0135        0.0131 Median            0.0688            0.0114        0.0119 Number of Positive Differences (S+):       n/a Critical Value, k, Table 1.3 of Marssim:      n/a S+ >thank?:         n/a Survey Unit Pass or Fail:   **Pass
..1 Results of judgmental samples have been reviewed and evaluated..Z Review to ensure that the analytical results of judgmental samples do not impact the evaluation for unrestricted release of the survey area.RM-78.doc RM-78 FINAL STATUS SURVEY ASSESSMENT Revision 2 Page 22 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 4 of 8 2.4 Qualification of Data: Statistical radionuclide-specific measurements for completeness.
*Note: Forced-Count values are used for samples with activity levels below the MDA.
Evaluate the survey for determination of data usability and confirm that sufficient qualified data are present for the decision process.a. Total number of statistical samples planned for the survey: /J_ " b. Total number of statistical samples determined as valid: Q c. Calculate
**Note: If all measurement data are less than the DCGL ., then the Sign Test is not required.
% Completeness:
b x120 a QQualified data are :=400% completeness and are sufficient to support the Sign Test requirement for determination of unrestricted release.Data Validation Completed:
No Comments: Assessor/De -?-0(Date RM-78.doc RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 23 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 5 of 8 3.0 DATA QUALITY ASSESSMENT


===3.1 Review===
"I .
the DQOs and Survey Design:_ Confirm that all inputs to the decision have been reviewed and are complete.____ Verify that boundaries or constraints identified in the survey area have not affected the quality of the data.__ Review the Statement of Hypothesis and confirm that it remains relevant.z..__ Confirm that Type I and Type II error limits are consistent with DQOs.___ Confirm that the survey design is consistent with DQOs and that the appropriate number of data points were obtained.3.2 Preliminary Review: 3.2.1 Preliminary Evaluation:
RM-79                                                                            Revision 1 FINAL STATUS SURVEY QUALITY CONTROL                                          Page 11 of 13 RM-79-1 FSS QUALITY CONTROL EVALUATION RESULTS FSS Package #            0'3 C4 z                      QC Package # 0 .& C,  /          -
___ Quality Assessment (QA) reports consistent with procedure RM-79, Final Status Survey Quality Control.Survey is of sufficient intensity to satisfy classification requirement.
QC Measurement Type              Acceptance Criteria Met*?        Reference vi1. 1. Replicate Scan                          No              Step 5.1.3
____ Potential trends of radioactivity levels in the survey area do not impact a decision for unrestricted release.Comments: RM-78.doc RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 24 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 6 of 8 3.2.2 Calculate Basic Statistical Quantities:
: 2. Sample Recounts                                          Step 5.1.4.1
: a. Number of qualified data points  b. Calculation of the Mean c. Calculation of the Median /a d. Calculation Standard Deviation
: a. In-house                        "e! No
,1. 1/0 Cso).!L Attach graphic representation of the data if any radionuclide-specific measurements exceed 50% of the DCGL.,jSample QA/QC measurements consistent with FSS data 3.3 Statistical Evaluation:
: b. Third party                    Yes / No
NOTE: If all measurement data are less than the DCGLw, statistical testing in not required and the survey unit meets the regulatory requirement for unrestricted release.7/' All survey measurements are below the DCGLW.3.3.1 Verify Assumptions of the Survey Design____Review the posting plot to verify that the data exhibits spatial independence.
: 3. Split Samples                                            Step 5.1.4.2
Spatial trends must be investigated and resolved prior to further assessment.
_            c. In-house                          e)/No
V 7 Review to verify dispersion symmetry.
      .jL            d. Third party                    Yes / No
The appearance of skewed data must be investigated for cause and documented prior to further assessment.
  *NOTE:      If Acceptance Criteria is not met, completion of Attachment RM-79-2, FSS Quality Control Investigation Results, is required.
RM-78.doc RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 25 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 7 of 8____ Review the dataset standard deviation and range for data variance.Questionable data must be investigated for cause and documented prior to further assessment.
Comments: )
__ Verify that the data exhibits adequate power and confirm that the sample size is sufficient to satisfy the DQOs.3.4 Draw Conclusions from the Data: 3.4.1 Investigation Levels and Response Actions L Determine if data resul! have exceeded any investigation level.Document findings.
(D.q X,::&#xfd;      A.W-4    JA              /   ~.z~  '
1/1a !AveJt4e-, 3.4.2 Evaluation for Unrestricted Release Select applicable conclusion:
Reviews:
,//. Survey area acceptance criteria met and survey area satisfies the requirements for unrestricted release: v/j All concentrations are less than the DCGLw. The Null Hypothesis is rejected.4 The mean concentration of the survey area is below the DCGLw but individual measurements in the survey unit exceed the DCGLw. The Sign Test and EMC evaluation are successful and the Null Hypothesis is rejected.RM-78.doc RM-78 FINAL STATUS SURVEY ASSESSMENT Revision 2 Page 26 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 8 of 8 , Survey area acceptance criteria not met and survey area fails to satisfy the requirements for unrestricted release: SThe mean concentration in the survey area exceeds the DCGLw. and the null hypothesis is confirmed..J/ The mean concentration of the survey area is below the DCGLw but individual measurements in the Unit exceed the DCGLw..The Sign Test and EMC evaluation are unsuccessful and the null hypothesis is confirmed.
Evator  -                    Date
Data Quality Assessment Completed:
                                                /
& No Comments f/R Assessor Revie vi T e K~nicaL'n i c l e v i e w ES Superintendent RP&ES Manager Dat1e3-0 Date/Datei-Date 10 -16, -o6 Date RM-78.doc RM-78-3, Attachment I Statistical Quantities Release Record 03C 1 l North West Protected Area Sample Cs-1 37 Co-60 Weighted "Weighted Sum Number (pCi/gm) (pCi/gm) Sum (SOR) <DCGLw? DCGL-W. Sum Sign 1 0.0591 0.0023 0.0057 yes 0.9943 +1 2 0.0912 0.0288 0.0166 yes 0.9834 +1 3 0.0698 0.0118 0.0095 yes 0.9905 +1 4 0.0872 0.0012 0.0077 yes 0.9923 +1 5 0.0638 0.0073 0.0076 yes 0.9924 +1 6 0.2535 -0.0063 0.0193 yes 0.9807 +1 7 0.0529 0.0243 0.0120 yes 0.9880 +1 8 0.3983 0.0343 0.0441 yes 0.9559 +1 9 0.1171 0.0110 0.0132 yes 0.9868 +1 10 0.2412 0.0077 0.0226 yes 0.9774 +1 11 0.0677 0.0010 0.0060 yes 0.9940 +1 12 -0.0001 -0.0101 -0.0032 yes 0.9968 +1 13 0.0114 0.0117 0.0046 yes 0.9954 +1 14 0.0503 0.0210 0.0108 yes 0.9892 +1 15 0.0834 0.0175 0.0124 yes 0.9876 +1 16 0.1165 0.0552 0.0270 yes 0.9730 +1 17 0.0651 -0.0035 0.0044 yes 0.9956 +1 18 0.0558 0.0250 0.0125 yes 0.9875 +1 19 0.0458 0.0254 0.0118 yes 0.9882 +1 20 0.1818 0.0046 0.0167 yes 0.9833 +1 Std. Dev Mean Median 0.0955 0.1056 0.0688 0.0157 0.0135 0.0114 0.0100 0.0131 0.0119 n/a Number of Positive Differences (S+): Critical Value, k, Table 1.3 of Marssim: n/a S+ >thank?: n/a Survey Unit Pass or Fail: **Pass*Note: Forced-Count values are used for samples with activity levels below the MDA.**Note: If all measurement data are less than the DCGL ., then the Sign Test is not required.
                                                -/0  -)-6 Terch'nical Review                    Date RM-79.doc
" I .RM-79 FINAL STATUS SURVEY QUALITY CONTROL Revision 1 Page 11 of 13 RM-79-1 FSS QUALITY CONTROL EVALUATION RESULTS FSS Package #0'3 C4 z QC Package #0 .& C, / -QC Measurement Type Acceptance Criteria Met*? Reference vi1. 1. Replicate Scan No Step 5.1.3 2. Sample Recounts Step 5.1.4.1 a. In-house "e! No b. Third party Yes / No 3. Split Samples Step 5.1.4.2_ c. In-house e)/No.jL d. Third party Yes / No*NOTE: If Acceptance Criteria is not met, completion of Attachment RM-79-2, FSS Quality Control Investigation Results, is required.Comments:
 
)(D.q X,::&#xfd; A.W-4 JA / ~.z~ 'Reviews: Evator -Date-/0 / -)-6 Date Terch'nical Review RM-79.doc QA Verification Split Sample Analysis Date: QA: 8/25/2006 03C 1 l North West Protected Area Type: Split Sample Lab: In-House A Resolution C= (A)10,< Indicates results less than the MDA.*Note Results are considered in agreement for MDA and near-MDA measurement comparisons Results fthat fail agreement must be investigated per RM-79.
QA Verification Split Sample Analysis Date:              8/25/2006 QA:                03C 1l North West Protected Area Type:              Split Sample Lab:                In-House Resolution C= (A)10,    A
QA Verification Sample Recount Analysis 6 Date: QA: 8125/2006 03C 1 I North West Protected Area.Table I Acceptance Criteria Resolution Ratio<4 N/A 4-7 0.5-2.0 8-15 0.6-1.66 16-50 0.75-1.33 51-200 0.8-1.25>200 0.85-1.18 Type: Sample Recounts Lab: In- House C A B D E F G BRP Results in Result BRP BRP BRP Acceptance Recount Comparison Agreement Sample Radionuclide Results % Error Ratio Recount Results Ratio Below Resolution Result Compare MDA (pCi/g) (Sigma) (Table 1) Below MDA (pCi/g) FI, Compare Be____ow_____D
< Indicatesresults less than the MDA.
______G with D)10 Co-60 0.0607 n/a n/a n/a < 0.0587 0.97 YES 10 Cs-137 0,2412 9.95 10.05 0M6-1.66 0.2059 0.85 YES 13 Co-60 < 00583 n/a n/a n/a < 0.0568 0.97 YES 13 Cs-137 < 0.0480 n/a n/a n/a < 0.0496 1.03 YES Resolution C= (AI( O< Indicates results less than the MDA.'Note Results are considered in agreement for MDA and near-MDA measurement comparisons Results fthat fail agreement must be investigated per RM-79.  
*Note  Results are considered in agreement for MDA and near-MDA measurement comparisons Results fthat fail agreement must be investigatedper RM-79.
,' i. V Tritium in Soil Data Results Final Status Survey 03C 1 1 Sample r Tritium in Soil Number j pCi/g 2 0.025 10 0.015 13 0.011 Mean: Median: St. Dev: 0.0170 0.0150 0.0072 Note: The DCGL for Tritium is 327 pCi/g.Sample results are less than 0.2% of the DCGL
 
-... Environmental, Inc.Midwest Laboratory an Allegheny Technologies Co.700 Landwehr Road
QA Verification Sample Recount Analysis 6
* Northbrook, IL 60062-2310 ph. (847) 564-0700 -fax (847) 564-4517 Mr. David W. Parish LABORATORY REPORT NO. 8022-100-239 Big Rock Point DATE: 09-27-2006 10269 US-31 North SAMPLES RECEIVED:
                                                                                                  . Table I Date:                  8125/2006                                                          Acceptance Criteria Resolution        Ratio QA:                    03C 1I North West Protected Area                                      <4             N/A 4-7            0.5-2.0 Type:                  Sample Recounts                                                      8-15          0.6-1.66 16-50        0.75-1.33 Lab:                 In- House                                                        51-200          0.8-1.25
09-22-2006 Charlevoix, MI 49720 PURCHASE ORDER NO: Below are the results of the analyses for tritium on three soil samples.Excavated Soil Survey 03C 1 1 Sample Collection Lab Concentration MDA Description Date Code (pCi/g of soil) (pCi/g of soil)H-3 2 09-19-06 BRSO-6484 0.025 +/- 0.008 < 0.013 10 09-19-06 BRSO-6485 0.015 +/- 0.007 < 0.011 13 09-19-06 BRSO-6486 0.011 +/- 0.005 < 0.009 The error given is the probable counting error at 95 % confidence level. The less than, (<), value is based on 4.66 sigma counting error for background sample.APPROVED BY/Tony Coorlim, Quality Assurance ATTACHMENT 3 CONSUMERS ENERGY BIG ROCKPOINT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION CLASS 1 FINAL STATUS SURVEY RELEASE RECORD, 05C, 1 , CENTRAL PROTECTED AREA October 24, 2006 37 Pages Class I Final Status Survey Release Record 05C 1 l Central Protected Area SURVEY PACKAGE CLOSURE Final Status Survey Documentation is authorized for closure. All required reviews are complete and the evaluation of data results have satisfied the criteria established for unrestricted release.Signed: Signed: Signed: f- (ESSG)(ERP& perintendent)
                                                                                            >200          0.85-1.18 A            B              C              D        E            F        G BRP Result          BRP            BRP          BRP                                                      Results in Acceptance                Recount  Comparison Agreement Radionuclide                        Results        % Error                        Ratio  Recount      Results    Ratio Sample Below                                      Resolution                  Result                          Compare MDA            (pCi/g)      (Sigma)                      (Table 1) Below  MDA ______G Be____ow_____D  (pCi/g)    FI,      Compare with D) 10                  Co-60                          0.0607          n/a          n/a            n/a        <          0.0587    0.97      YES 10                  Cs-137                          0,2412          9.95        10.05          0M6-1.66                0.2059    0.85      YES 13                  Co-60               <          00583            n/a          n/a            n/a        <         0.0568    0.97      YES 13                Cs-137              <          0.0480          n/a          n/a            n/a        <          0.0496    1.03      YES Resolution        C= (AI(        O
/(RP & ES Manager)Date: lo-/la- o&Date: /c/6 Date:
< Indicatesresults less than the MDA.
Survey Area Requirements Final Status Survey, Release Record 05C 1 1 Central Protected Area Survey Description Final Status Survey 05C 1 1 encompasses 1924 m 2 at or below the grade elevation present during plant power operations in the central section of the Protected Area. No materials of plant origin remain in the survey area.History During power operations the Protected Area supported the components and systems necessary for electrical generation.
'Note      Results are consideredin agreement forMDA and near-MDA measurementcomparisons Results fthat fail agreementmust be investigatedperRM-79.
The location of Survey Unit 05 is adjacent to the transport route used to move spent resin and filter media for radiological survey and offsite removal. Structures and enclosures formerly located in this area were once used for the storage of contaminated materials.
 
A detailed review of the history and radiological characterization of Survey Unit 5 is provided in Appendix 2B and 2E of the LTP (License Termination Plan).Current Radiological Status Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Based on operational history and former locations of radioactive systems and material transport pathways the radiological status of this survey unit is Class 1.Post-Construction Expectations Final Status Survey 05C 1 1 will be performed in the following activity sequence: 1. Walkdown:
,' i. V Tritium in Soil Data Results Final Status Survey 03C1 1 Sample Number r
Environmental Services Survey Group (ESSG) personnel will perform a walkdown assessment to ensure survey area preparations are complete and confirm that the following post-construction expectations have been satisfied as applicable:
j Tritium in Soil pCi/g 2                      0.025 10                      0.015 13                      0.011 Mean:        0.0170 Median:      0.0150 St. Dev:      0.0072 Note: The DCGL for Tritium is 327 pCi/g.
* Groundwater and Surface water control is adequate* All construction debris has been removed from the survey area* The survey location status meets all applicable safety requirements
Sample results are less than 0.2% of the DCGL
: 2. Survey Area Isolation and Control: Control measures will be established to ensure that any potential ongoing decommissioning activities in adjacent locations do not impact the current survey area status. Isolation and control measures include postings, barriers, access points, and the evaluation of ongoing work activities in adjacent areas.Survey Area Requirements FSS 05C 1 1 Page 1 of 2
 
: 3. Survey Design and Execution:
        .. Environmental, Inc.
Survey design and execution will follow the Data Quality Objectives for 05C,1 in accordance with the survey requirements established in procedures RM-76, Final Status Survey Design and RM-77, Final Status Survey Implementation, and LTP, Chapter 5. Survey size will be based on the statistical requirements of the Sign Test for Class 1 areas with soil samples collected in random start, systematic data point locations.
Midwest Laboratory an Allegheny Technologies Co.
Surface scanning will be performed with 100%survey area coverage.
700 Landwehr Road
This survey will be conducted in accordance with approved BRP procedures and follow the guidance of NUREG 1575.4. Data Quality Assessment:
* Northbrook, IL 60062-2310 ph. (847) 564-0700 - fax (847) 564-4517 Mr. David W. Parish                                                LABORATORY REPORT NO.               8022-100-239 Big Rock Point                                                        DATE:                              09-27-2006 10269 US-31 North                                                    SAMPLES RECEIVED:                  09-22-2006 Charlevoix, MI 49720                                                  PURCHASE ORDER NO:
Isolation and control of the survey area will be maintained until the survey Data Quality Assessment demonstrates that the regulatory requirements for unrestricted site release have been satisfied.
Below are the results of the analyses for tritium on three soil samples.
Survey Area Requirements FSS 05C 1 1 Page 2 of 2 DATA QUALITY OBJECTIVES Final Status Survey, Release Record 05C 1 1 Central Protected Area STATE THE PROBLEM The Problem: To demonstrate that the level of residual radioactivity in Class 1 Survey Unit 05 does not exceed the release criteria of 25 mrem/year Total Effective Dose Equivalent (TEDE) as specified in the License Termination Plan (LTP).Stakeholders:
Excavated Soil Survey 03C 11 Sample                              Collection            Lab            Concentration          MDA Description                              Date              Code            (pCi/g of soil)      (pCi/g of soil)
The primary stakeholders interested in the answer to this problem are Consumers Energy Co., and the general public as represented by the Michigan Department of Environmental Quality (MDEQ), and the US Nuclear Regulatory Commission (USNRC).The Planning Team: The planning team consists of members of the BRP Environmental Services Survey Group (ESSG). The primary decision maker will be the Final Status Survey Supervisor.
H-3 2                                      09-19-06            BRSO-6484        0.025 +/- 0.008            < 0.013 10                                    09-19-06            BRSO-6485        0.015 +/- 0.007            < 0.011 13                                     09-19-06            BRSO-6486        0.011 +/- 0.005            < 0.009 The error given is the probable counting error at 95 % confidence level. The less than, (<), value is based on 4.66 sigma counting error for background sample.
The Final Status Survey Supervisor will obtain input from the site Construction Group and Scheduling Group for issues relating to schedule and costs.Schedule: Approximately five (5) working days are projected to implement the survey and to collect and analyze field data.Resources:
APPROVED BY
The primary resources needed to determine the answer to the problem are two (2)technicians to perform fieldwork, one (1) technician to prepare the samples and conduct laboratory analyses, and two (2) survey team members to prepare and review the design, generate maps, coordinate field activities and evaluate data.2. IDENTIFY THE DECISION Several decisions need to be defined to address the stated problem.Principal Study Question (1): Does the mean concentration of residual radioactivity in the survey unit exceed the release criteria stated above?Decision (1): Determine whether the mean concentration of residual radioactivity in the survey exceeds the release criteria stated in the problem.Actions (1): Alternative actions include failure of the survey unit, remediation, or no action required.Data Quality Objectives FSS 05C 1 1 Page 1 of 5 Principal Study Question (2): Do any areas of elevated activity in the survey unit exceed the release criteria?The Decision (2): Determine if any areas of elevated activity in the survey unit exceed the release criteria.Actions (2): Alternative actions include confirmation and investigation, performing the elevated measurement comparison (EMC), remediation, or no action required.Principal Study Question (3): Is the potential dose from residual radioactivity in the survey unit ALARA as stated?The Decision (3): Determine if the potential dose from residual radioactivity in the survey unit is ALARA.ALARA requirements for soil remediation are defined in Chapter 4 of the LTP.Actions (3): Alternative actions include remediation or no action required.3. IDENTIFY INPUTS TO THE DECISION Information Needed: Characterization measurements are required to define the radionuclides present and determine the extent and variability of residual radioactivity in the survey area for design and implementation of the survey. Survey area classification, ALARA analysis, potential radionuclides of interest, and site-specific DCGL values are also required inputs to the decision process. The primary information required for evaluation is the analytical results of survey measurements.
                                                                          /          Tony Coorlim, Quality Assurance
 
ATTACHMENT 3 CONSUMERS ENERGY BIG ROCKPOINT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION CLASS 1 FINAL STATUS SURVEY RELEASE RECORD, 05C, 1 ,
CENTRAL PROTECTED AREA October 24, 2006 37 Pages
 
Class I Final Status Survey Release Record 05C1 l Central Protected Area SURVEY PACKAGE CLOSURE Final Status Survey Documentation is authorized for closure. All required reviews are complete and the evaluation of data results have satisfied the criteria established for unrestricted release.
Signed:                              Date:    lo-/la- o&
f-      (ESSG)
Signed:                               Date:     /c/*6 (ERP& perintendent)
Signed:                                Date:   /o-/~-o*
                          /(RP  & ES Manager)
 
Survey Area Requirements Final Status Survey, Release Record 05C 1 1 Central Protected Area Survey Description Final Status Survey 05C 11 encompasses 1924 m2 at or below the grade elevation present during plant power operations in the central section of the Protected Area. No materials of plant origin remain in the survey area.
History During power operations the Protected Area supported the components and systems necessary for electrical generation. The location of Survey Unit 05 is adjacent to the transport route used to move spent resin and filter media for radiological survey and offsite removal. Structures and enclosures formerly located in this area were once used for the storage of contaminated materials. A detailed review of the history and radiological characterization of Survey Unit 5 is provided in Appendix 2B and 2E of the LTP (License Termination Plan).
Current Radiological Status Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Based on operational history and former locations of radioactive systems and material transport pathways the radiological status of this survey unit is Class 1.
Post-Construction Expectations Final Status Survey 05C 1 1 will be performed in the following activity sequence:
: 1. Walkdown: Environmental Services Survey Group (ESSG) personnel will perform a walkdown assessment to ensure survey area preparations are complete and confirm that the following post-construction expectations have been satisfied as applicable:
* Groundwater and Surface water control is adequate
* All construction debris has been removed from the survey area
* The survey location status meets all applicable safety requirements
: 2. Survey Area Isolation and Control: Control measures will be established to ensure that any potential ongoing decommissioning activities in adjacent locations do not impact the current survey area status. Isolation and control measures include postings, barriers, access points, and the evaluation of ongoing work activities in adjacent areas.
Survey Area Requirements FSS 05C1 1 Page 1 of 2
: 3. Survey Design and Execution: Survey design and execution will follow the Data Quality Objectives for 05C,1 in accordance with the survey requirements established in procedures RM-76, Final Status Survey Design and RM-77, Final Status Survey Implementation, and LTP, Chapter 5. Survey size will be based on the statistical requirements of the Sign Test for Class 1 areas with soil samples collected in random start, systematic data point locations. Surface scanning will be performed with 100%
survey area coverage. This survey will be conducted in accordance with approved BRP procedures and follow the guidance of NUREG 1575.
: 4. Data Quality Assessment: Isolation and control of the survey area will be maintained until the survey Data Quality Assessment demonstrates that the regulatory requirements for unrestricted site release have been satisfied.
Survey Area Requirements FSS 05C 11 Page 2 of 2
 
DATA QUALITY OBJECTIVES Final Status Survey, Release Record 05C11 Central Protected Area STATE THE PROBLEM The Problem:
To demonstrate that the level of residual radioactivity in Class 1 Survey Unit 05 does not exceed the release criteria of 25 mrem/year Total Effective Dose Equivalent (TEDE) as specified in the License Termination Plan (LTP).
Stakeholders:
The primary stakeholders interested in the answer to this problem are Consumers Energy Co., and the general public as represented by the Michigan Department of Environmental Quality (MDEQ), and the US Nuclear Regulatory Commission (USNRC).
The Planning Team:
The planning team consists of members of the BRP Environmental Services Survey Group (ESSG). The primary decision maker will be the Final Status Survey Supervisor.
The Final Status Survey Supervisor will obtain input from the site Construction Group and Scheduling Group for issues relating to schedule and costs.
Schedule:
Approximately five (5) working days are projected to implement the survey and to collect and analyze field data.
Resources:
The primary resources needed to determine the answer to the problem are two (2) technicians to perform fieldwork, one (1) technician to prepare the samples and conduct laboratory analyses, and two (2) survey team members to prepare and review the design, generate maps, coordinate field activities and evaluate data.
: 2. IDENTIFY THE DECISION Several decisions need to be defined to address the stated problem.
PrincipalStudy Question (1):
Does the mean concentration of residual radioactivity in the survey unit exceed the release criteria stated above?
Decision (1):
Determine whether the mean concentration of residual radioactivity in the survey exceeds the release criteria stated in the problem.
Actions (1):
Alternative actions include failure of the survey unit, remediation, or no action required.
Data Quality Objectives FSS 05C 11 Page 1 of 5
 
PrincipalStudy Question (2):
Do any areas of elevated activity in the survey unit exceed the release criteria?
The Decision (2):
Determine if any areas of elevated activity in the survey unit exceed the release criteria.
Actions (2):
Alternative actions include confirmation and investigation, performing the elevated measurement comparison (EMC), remediation, or no action required.
PrincipalStudy Question (3):
Is the potential dose from residual radioactivity in the survey unit ALARA as stated?
The Decision (3):
Determine if the potential dose from residual radioactivity in the survey unit is ALARA.
ALARA requirements for soil remediation are defined in Chapter 4 of the LTP.
Actions (3):
Alternative actions include remediation or no action required.
: 3. IDENTIFY INPUTS TO THE DECISION Information Needed:
Characterization measurements are required to define the radionuclides present and determine the extent and variability of residual radioactivity in the survey area for design and implementation of the survey. Survey area classification, ALARA analysis, potential radionuclides of interest, and site-specific DCGL values are also required inputs to the decision process. The primary information required for evaluation is the analytical results of survey measurements.
Source of the Information:
Source of the Information:
The soil sample data to be used for survey development are the radionuclide-specific measurements of representative soil samples collected for radiological characterization and excavated soil surveys conducted to determine suitability for transport of excavated soil to the SVA. The soil samples obtained were judgmentally selected as a result of multiple surveys conducted during the excavation and transport process. The ALARA analysis for potential soil remediation is provided in LTP, Section 4.4. Site-specific DCGL values and BRP radionuclides of interest are defined in LTP Chapter 5, Table 5-1 and Procedure RM-76, Final Status Survey Design.The survey will be conducted in accordance with applicable regulatory guidance as established in LTP Chapter 5 for Class 1 areas. Soil samples will be utilized for radionuclide-specific measurements in this evaluation.
The soil sample data to be used for survey development are the radionuclide-specific measurements of representative soil samples collected for radiological characterization and excavated soil surveys conducted to determine suitability for transport of excavated soil to the SVA. The soil samples obtained were judgmentally selected as a result of multiple surveys conducted during the excavation and transport process. The ALARA analysis for potential soil remediation is provided in LTP, Section 4.4. Site-specific DCGL values and BRP radionuclides of interest are defined in LTP Chapter 5, Table 5-1 and Procedure RM-76, Final Status Survey Design.
: 4. BOUNDARIES OF THE STUDY Boundaries of the Survey: The target population for this survey is the total thickness of prepared soil in the survey area of 1924 M 2.Data Quality Objectives FSS 05C 1 1 Page 2 of 5 Temporal Boundaries:
The survey will be conducted in accordance with applicable regulatory guidance as established in LTP Chapter 5 for Class 1 areas. Soil samples will be utilized for radionuclide-specific measurements in this evaluation.
Scanning and sampling in this survey unit will only be performed during daylight hours under dry weather conditions.
: 4. BOUNDARIES OF THE STUDY Boundaries of the Survey:
Surface soils must be free of significant snow cover and standing water prior to surface scanning.
The target population for this survey is the total thickness of prepared soil in the survey area of 1924 M2 .
Soils must be in a non-frozen state or fragmented for collection to satisfy BRP procedural sampling requirements.
Data Quality Objectives FSS 05C 11 Page 2 of 5
The anticipated start date for the survey is September 18, 2006.Constraints:
 
Temporal Boundaries:
Scanning and sampling in this survey unit will only be performed during daylight hours under dry weather conditions. Surface soils must be free of significant snow cover and standing water prior to surface scanning. Soils must be in a non-frozen state or fragmented for collection to satisfy BRP procedural sampling requirements. The anticipated start date for the survey is September 18, 2006.
Constraints:
Cold weather or rainy conditions may effect the operation of electronic equipment.
Cold weather or rainy conditions may effect the operation of electronic equipment.
Adverse weather conditions that include accumulations of rain or snow may limit area access and delay survey efforts.5. DEVELOP A DECISION RULE The following decision rules have been developed to define a logical process for choosing among alternative actions for the principal study questions associated with this survey area.Decision Rule (1): If all reported concentrations for residual radioactivity are less than the site-specific DCGL's and the unity rule has been satisfied for each sample, then the survey unit meets release criteria.
Adverse weather conditions that include accumulations of rain or snow may limit area access and delay survey efforts.
No further action is required.Decision Rule (2): If the mean value of activity in the survey unit is greater than the DCGL, then the survey unit fails to meet the release criteria.1 Remediate, resurvey, and evaluate the results relative to the decision rule.Decision Rule (3): If the mean activity in the survey unit is less than the DCGL and any individual sample measurement exceeds this value, conduct the Sign Test and the elevated measurement comparison (EMC) per LTP, Chapter 5 and Procedure RM-76, Final Status Survey Design. If the EMC and the Sign Test have been satisfied then the survey unit meets the release criteria and no further action is required.
: 5.       DEVELOP A DECISION RULE The following decision rules have been developed to define a logical process for choosing among alternative actions for the principal study questions associated with this survey area.
If the EMC or the Sign Test has not been satisfied then remediate the area(s) of elevated activity, resurvey as appropriate, and evaluate the results relative to the decision rule.Decision Rule (4): If the potential dose from residual radioactivity in the survey unit is ALARA, then no further action is necessary.
Decision Rule (1):
If the potential dose from residual radioactivity in the survey unit is not ALARA, then remediate and resurvey.6. SPECIFY TOLERABLE LIMITS ON DECISION ERRORS The Null Hypothesis:
If all reported concentrations for residual radioactivity are less than the site-specific DCGL's and the unity rule has been satisfied for each sample, then the survey unit meets release criteria. No further action is required.
Decision Rule (2):
If the mean value of activity in the survey unit is greater than the DCGL, then the survey unit fails to meet the release criteria. 1 Remediate, resurvey, and evaluate the results relative to the decision rule.
Decision Rule (3):
If the mean activity in the survey unit is less than the DCGL and any individual sample measurement exceeds this value, conduct the Sign Test and the elevated measurement comparison (EMC) per LTP, Chapter 5 and Procedure RM-76, Final Status Survey Design. If the EMC and the Sign Test have been satisfied then the survey unit meets the release criteria and no further action is required. If the EMC or the Sign Test has not been satisfied then remediate the area(s) of elevated activity, resurvey as appropriate, and evaluate the results relative to the decision rule.
Decision Rule (4):
If the potential dose from residual radioactivity in the survey unit is ALARA, then no further action is necessary. If the potential dose from residual radioactivity in the survey unit is not ALARA, then remediate and resurvey.
: 6.     SPECIFY TOLERABLE LIMITS ON DECISION ERRORS The Null Hypothesis:
It is assumed that residual radioactivity in the survey unit exceeds the release criterion.
It is assumed that residual radioactivity in the survey unit exceeds the release criterion.
'When multiple radionuclides are present the mean activity value is determined as the average of the weighted sum. The DCGL of the weighted sum is 1.Data Quality Objectives FSS 05CO 1 Page 3 of 5 Type I Error (a): The a error is the maximum probability of rejecting the null hypotheses when it is true.Thea error is defined in the LTP at a value of 0.05 (5%) and cannot be changed to a less restrictive value unless prior approval is granted by the USNRC. The a error value of 0.05 will be used for survey planning and data assessment for this survey area.Type I/ Error (,6).The /6 error is the probability of accepting the null hypothesis when it is false. A value of 0.05 (5%) will be used for survey planning and data assessment for this survey area.The Lower Bound of the Gray Region (LBGR): The LBGR is initially set at one-half the DCGLW for this survey unit. The LBGR may be adjusted during survey design to achieve an optimum relative shift between 1.0 and 3.0.Relative Shift (A/cy): The relative shift will be maintained within the range of 1.0 and 3.0 by adjusting the LBGR as appropriate.
'When multiple radionuclides are present the mean activity value is determined as the average of the weighted sum. The DCGL of the weighted sum is 1.
: 7. OPTIMIZE DESIGN FOR OBTAINING DATA Statistical Test Sign Test: Radionuclides of potential plant origin also present in soil as background activity resulting from fallout constitute only a small fraction of the DCGL. Therefore, the Sign Test will be used where applicable in the survey evaluation to determine if the survey area meets the requirements for unrestricted release.Number of Samples Determined:
Data Quality Objectives FSS 05CO 1 Page 3 of 5
The number of samples required for this survey will be determined based on the relative shift as defined by the requirements of the Sign Test (LTP, Chapter 5.) and Procedure RM-76, Final Status Survey Design. The LBGR is initially set at one-half the DCGL, and may be adjusted as necessary for optimizing the survey design to achieve a relative shift between 1.0 and 3.0. Sample point locations are to be determined using a random start, systematic square grid spacing.Judgmental Sampling: Co-60 is the most limiting radionuclide for identification by surface scanning; judgmental surface and subsurface core samples will be collected in any location that exceeds the scan investigation level.Scan Coverage: Scanning for this survey area will provide 100% coverage.Number of Samples for Quality Control: A minimum of 5% of the sample population will be collected for quality evaluation.
 
These samples may include sample splits, sample recounts, or third party sample Data Quality Objectives FSS 05C 1 1 Page 4 of 5 analysis.
Type I Error(a):
Quality analyses will be conducted as defined in LTP, Chapter 5 and Procedure RM-79, Final Status Survey Quality Control.Additional Sample Analysis Requirements:
The a error is the maximum probability of rejecting the null hypotheses when it is true.
The area of soil excavation intersects the identified waterborne pathway for Tritium migration and shall require Tritium in soil analyses for a minimum of 10% of the sample population.
Thea error is defined in the LTP at a value of 0.05 (5%) and cannot be changed to a less restrictive value unless prior approval is granted by the USNRC. The a error value of 0.05 will be used for survey planning and data assessment for this survey area.
Soil samples will be collected in the same random locations as those selected for QA/QC evaluation and sent to an independent laboratory for Tritium analysis.
Type I/ Error(,6).
Data results will be provided in the survey package.Investigation Levels: Investigation levels defined in LTP, Chapter 5 and BRP Procedure RM-76, Final Status Survey Design, shall be conservatively established for this survey as shown below: Investigation Levels for Survey 05C 1 1 Scan Measurement Soil Sample Analysis>DCGL > DCGLw The investigation levels for soil sample measurements are meant to include any individual radionuclide result greater than the site-specific DCGL or where the combined radionuclide values exceed the unity rule. Co-60 is the most limiting radionuclide for identification by surface scanning; further investigation will be initiated at any location that exceeds the Co-60 Scan DCGL of 1818 CPM above background as detailed in the survey design.Data Quality Objectives FSS 05C, 1 Page 5 of 5 FINAL STATUS SURVEY DESIGN Release Record 05C 1 1 Central Protected Area Survey Unit Description Survey 05C, 1 encompasses an area of 1924 m 2 in the central section of the Protected Area. No materials of plant origin exist in this survey unit.Soil Sample Design Scoping Data Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Input data for survey design were conservatively estimated based on supporting surveys of excavated soils resulting from subsurface structure and component removal within the Protected Area.Table 1 Input Data for Survey Design (pCi/g)Radionuclides Cs-137 Co-60 O-
The /6 error is the probability of accepting the null hypothesis when it is false. A value of 0.05 (5%) will be used for survey planning and data assessment for this survey area.
* 0.524 0.255 DCGL 11.93 3.21*Survey data detailed in Attachment 1 Sample Requirements The number of sample data points for this survey is based on the requirements of the Sign Test.The Unity Rule is used for the presence of multiple radionuclides.
The Lower Bound of the Gray Region (LBGR):
The Standard Deviation of the weighted sum is described by the following:
The LBGR is initially set at one-half the DCGLW for this survey unit. The LBGR may be adjusted during survey design to achieve an optimum relative shift between 1.0 and 3.0.
0= V( CS137 2 +,YO02 DCGLcs137 W DC-oGo)(= 0.091 Relative Shift Relative Shift = DCGLw- LBGR (Y Relative Shift = 1-0.818 0.091 Relative Shift = 2.0 With ( and P3 error levels set at 0.05 and the relative shift of 2.0, the Sign Test requires 15 sample data points (Table 5.5 NUREG 1575).Survey Design FSS 05C 1 l Page 1 of 7 Sample Locations Sample locations are selected in a random start, systematic square grid pattern with the southwest corner of the survey unit as origin (X=0, Y=0). Two numbers between 0 and 1 have been randomly selected and then applied to the survey unit maximum X and Y dimensions to determine the random start location as shown below: Table 2 Random Numbers I Random #, X Axis Random #, Y Axis 0.091956 0.994458 Survey Unit Dimensions:
Relative Shift (A/cy):
X = 30.3 meters Y = 70.0 meters Random Start Location X = (0.091956)(30.3)  
The relative shift will be maintained within the range of 1.0 and 3.0 by adjusting the LBGR as appropriate.
= 2.8 meters With SW Corner Origin: Y = (0.994458)(70.0)  
: 7. OPTIMIZE DESIGN FOR OBTAINING DATA Statistical Test Sign Test:
= 69.6 meters Sample Spacing As a conservative measure sample spacing will be calculated based on 18 samples for this survey. Samples are located in a systematic square grid pattern with sample spacing determined by the following:
Radionuclides of potential plant origin also present in soil as background activity resulting from fallout constitute only a small fraction of the DCGL. Therefore, the Sign Test will be used where applicable in the survey evaluation to determine if the survey area meets the requirements for unrestricted release.
L=A n Where: A= area of survey unit, and n = number of samples.1924 L = 9 1-2 10.3 meters 18 With sample spacing established at 10.3 meters, 19 data points are available for this survey.Data point locations are identified in Attachment 2.QAIQC Sampling A minimum of 5% of the sample population and 5% of the scan survey area are required to be selected for QA/QC verification in accordance with BRP Procedure RM-79, Final Status Survey Quality Control. As a conservative measure, three (3) soil samples and 10% of the scan survey area will be selected for QA/QC evaluation.
Number of Samples Determined:
Data point locations for soil samples will be determined by random number selection.
The number of samples required for this survey will be determined based on the relative shift as defined by the requirements of the Sign Test (LTP, Chapter 5.) and Procedure RM-76, Final Status Survey Design. The LBGR is initially set at one-half the DCGL, and may be adjusted as necessary for optimizing the survey design to achieve a relative shift between 1.0 and 3.0. Sample point locations are to be determined using a random start, systematic square grid spacing.
The QA/QC scan starting point and track direction are also determined by random number selection.
Judgmental Sampling:
The first random data point selected will identify the scanning start point and the second random data point will determine the direction in which the scan will track. QA/QC location results are provided in Table 3 below: Survey Design FSS 05C 1 1 Page 2 of 7 Table 3 Random Numbers Generated for QA/QC SRandom Random Samples Sample Verification Scan Sample Samples Number Number Split Sample: 3 Start Point: 12 Sample Recount: 5 Scan Toward: 3 Sample Recount: 11 Scan Area Requirement:
Co-60 is the most limiting radionuclide for identification by surface scanning; judgmental surface and subsurface core samples will be collected in any location that exceeds the scan investigation level.
193 M 2 Surface Scanning The coverage requirement for surface scanning in this Class 1 area is 100%. The Scan MDC has been established at fractional values of the DCGLw for typical background activity levels at Big Rock Point. Scan MDC values for varying backgrounds are provided in Attachment  
Scan Coverage:
: 3. The investigation level for identification of potential areas of elevated activity in this survey area will be the Scan DCGL as defined by the following:
Scanning for this survey area will provide 100% coverage.
Scan DCGL = Detector Rating CPM .Exposure Model uR/hr .DCGLw uR/hr pCi/g Scan DCGL for Co-60 = 1818 CPM Scan DCGL for Cs-137 = 3518 CPM Where:'Detector Rating = 1200 CPM Cs- 137 and 565 CPM Co -60 uR/hr uR/hr Exposure Model = 1.229 uR/hr Cs-137 and 5.029 uR/hr Co -60 5pCi/g 5 pCi/g DCGLw = 11.93 pCi/g Cs-137 and 3.21 pCi/g Co-60 The DCGLw for Co-60 is the most limiting value for scanning measurements performed to identify areas of potentially elevated activity.
Number of Samples for Quality Control:
Scanning conducted for this survey will assume all residual radioactivity to originate from Co-60 and the instrument response at the Co-60 DCGLw (1818 cpm)will be used as the scanning investigation level for FSS 05C11.'These values established in EA-BRP-SC-0201, Nal Scanning Sensitivity for Open Land Survey.Survey Design FSS 05C, 1 Page 3 of 7 Attachment I Design Data -FSS 05C 1 1 Protected Area Supporting Surveys Cs-1 37 Co-60 Survey No. Sequence Activity Activity No. (pCi/g) (pCi/g).HH060705 16538,! , :.&#xfd;1.26 .0.66 HH060705 16539' &#xfd;0.06 0.06*"HHO60705-
A minimum of 5% of the sample population will be collected for quality evaluation.
_ 16540- 1.050.66 TB062805 '16755 1.16 "G27,.TB062805 16756", 0-47 .0.1*TB062805&#xfd;]
These samples may include sample splits, sample recounts, or third party sample Data Quality Objectives FSS 05C11 Page 4 of 5
16774 0.19 0.31 Mean: 0.698 Std Dev: 0.524 0.352 0.255* Measurement system MDA -Co-60 not identified in this sample Survey Design FSS 05C 1 1 Page 4 of 7 Attachment 2 Soil Sample Locations  
 
-Survey 05C 1 1 Central Protected Area 89 17190 191 19213 20821 211212 21" 227 229231 246 250 2369 35 31639 37 328 1 X=30.3 m 340 "343 4-Survey Unit 05C _1* Sample Location 0 5 10 20 Meters i i 1 I I Sample spacing Is 10.3 metors Survey Design FSS 05C 1 1 Page 5 of 7 Attachment 3 Scan MDC In Varying Backgrounds Background d' Si MDCasurveyor Cs-137 Co-60 Cs-137 Co-60 2000 2.48 4 28.64 607.47 0.51 1.08 2.06 1.07 3000 2.48 4 35.07 744.00 0.62 1.32 2.52 1.31 3500 2.48 4 37.88 803.61 0.67 1.42 2.72 1.41 4000 2.48 4 40.50 859.10 0.72 1.52 2.91 1.51 4500 2.48 4 42.95 911.21 0.76 1.61 3.09 1.60 5500 2.48 4 47.49 1,007.38 0.84 1.78 3.42 1.77 6000 2.48 4 49.60 1,052.17 0.88 1.86 3.57 1.85 6500 2.48 4 51.63 1,095.14 0.91 1.94 3.71 1.93 7000 2.48 4 53.57 1,136.48 0.95 2.01 3.85 2.00 8000 2.48 4 57.27 1,214.95 1.01 2.15 4.12 2.14 8500 2.48 4 59.04 1,252.34 1.04 2.22 4.25 2.20 9000 2.48 4 60.75 1,288.65 1.07 2.28 4.37 2.27 9500 2.48 4 62.41 1,323.96 1.10 2.34 4.49 2.33 10500 2.48 4 65.61 1,391.90 1.16 2.46 4.72 2.45 11000 2.48 4 67.16 1,424.65 1.19 2.52 4.83 2.51 11500 2.48 4 68.67 1,456.67 1.21 2.58 4.94 2.56 12000 2.48 4 70.14 1,488.00 1.24 2.63 5.04 2.62-4 71.5 -15i68 127 26 515~* 2T 13000 2.48 4 73.01 1,548.76 1.29 2.74 5.25 2.73 13500 2.48 4 74.40 1,578.26 1.32 2.79 5.35 2.78 14000 2.48 4 75.77 1,607.22 1.34 2.84 5.45 2.83 14500 2.48 4 77.11 1,635.67 1.36 2.89 5.55 2.88 re'--&4K248 4i&sect;7&21 ~~ 3 4 i64 64, Xi2_______ ~~o~0' 5,Q3E+to Survey Design FSS 05C 1 1 Page 6 of 7 Attachment 4 Area Factors for Open Land Survey Evaluation Contaminated_
analysis. Quality analyses will be conducted as defined in LTP, Chapter 5 and Procedure RM-79, Final Status Survey Quality Control.
Calculated Area Factors at Time of Peak Dose Contaminated H-3 Mn-54 Fe-55 Co-60 Sr-90 Cs-137 Eu-152 Eu-154 Eu-155 Area (in 2)8094 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 4047 1.00 1.01 1.00 1.01 1.00 1.02 1.02 1.01 1.02 2024 1.00 1.03 1.00 1.03 1.00 1.03 1.03 1.03 1.03 1012 1.35 1.04 1.00 1.04 1.00 1.04 1.05 1.04 1.04 506 2.91 1.09 1.98 1.08 1.98 1.13 1.07 1.07 1.06 253 6.05 1.14 3.95 1.13 3.94 1.20 1.11 1.11 1.09 126 12.4 1.20 7.93 1.20 7.87 1.29 1.17 1.16 1.14 63 24.9 1.30 15.8 1.30 15.6 1.41 1.27 1.26 1.23 32 49.2 1.49 31.2 1.49 30.5 1.62 1.44 1.45 1.39 16 98.9 1.78 62.0 1.78 59.9 1.93 1.72 1.73 1.63 8 198 2.38 123 2.38 117 2.58 2.30 2.31 2.14 4 397 3.61 243 3.62 230 3.91 3.49 3.52 3.19 2 794 5.68 473 5.75 452 6.14 5.48 5.55 4.90 1 1590 9.57 905 9.73 887 10.3 9.24 9.39 7.88 Survey Design FSS 05C 1 1 Page 7 of 7 RM-76 FINAL STATUS SURVEY DESIGN Revision 1 Page 19 of 19 RM-76-5 FINAL STATUS SURVEY APPROVAL AND AUTHORIZATION FOR IMPLEMENTATION Survey Code 1 Survey Area
Additional Sample Analysis Requirements:
The area of soil excavation intersects the identified waterborne pathway for Tritium migration and shall require Tritium in soil analyses for a minimum of 10% of the sample population. Soil samples will be collected in the same random locations as those selected for QA/QC evaluation and sent to an independent laboratory for Tritium analysis. Data results will be provided in the survey package.
Investigation Levels:
Investigation levels defined in LTP, Chapter 5 and BRP Procedure RM-76, Final Status Survey Design, shall be conservatively established for this survey as shown below:
Investigation Levels for Survey 05C 11 Scan Measurement                   Soil Sample Analysis
                                >DCGL                             > DCGLw The investigation levels for soil sample measurements are meant to include any individual radionuclide result greater than the site-specific DCGL or where the combined radionuclide values exceed the unity rule. Co-60 is the most limiting radionuclide for identification by surface scanning; further investigation will be initiated at any location that exceeds the Co-60 Scan DCGL of 1818 CPM above background as detailed in the survey design.
Data Quality Objectives FSS 05C, 1 Page 5 of 5
 
FINAL STATUS SURVEY DESIGN Release Record 05C11 Central Protected Area Survey Unit Description Survey 05C, 1 encompasses an area of 1924 m 2 in the central section of the Protected Area. No materials of plant origin exist in this survey unit.
Soil Sample Design Scoping Data Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Input data for survey design were conservatively estimated based on supporting surveys of excavated soils resulting from subsurface structure and component removal within the Protected Area.
Table 1 Input Data for Survey Design (pCi/g)
Radionuclides                     Cs-137                       Co-60 O-
* 0.524                       0.255 DCGL                           11.93                         3.21
        *Survey data detailed in Attachment 1 Sample Requirements The number of sample data points for this survey is based on the requirements of the Sign Test.
The Unity Rule is used for the presence of multiple radionuclides. The Standard Deviation of the weighted sum is described by the following:
0= V(     CS1372 +,YO02 DCGLcs137     WDC-oGo)
(= 0.091 Relative Shift Relative Shift = DCGLw- LBGR (Y
Relative Shift = 1-0.818 0.091 Relative Shift = 2.0 With ( and P3 error levels set at 0.05 and the relative shift of 2.0, the Sign Test requires 15 sample data points (Table 5.5 NUREG 1575).
Survey Design FSS 05C1 l Page 1 of 7
 
Sample Locations Sample locations are selected in a random start, systematic square grid pattern with the southwest corner of the survey unit as origin (X=0, Y=0). Two numbers between 0 and 1 have been randomly selected and then applied to the survey unit maximum X and Y dimensions to determine the random start location as shown below:
Table 2 Random Numbers I Random #, X Axis             Random #, Y Axis 0.091956                       0.994458 Survey Unit Dimensions:         X = 30.3 meters Y = 70.0 meters Random Start Location           X = (0.091956)(30.3)       = 2.8 meters With SW Corner Origin:         Y = (0.994458)(70.0)       = 69.6 meters Sample Spacing As a conservative measure sample spacing will be calculated based on 18 samples for this survey. Samples are located in a systematic square grid pattern with sample spacing determined by the following:
L=A n
Where: A= area of survey unit, and n = number of samples.
1924 L=     91-2     10.3 meters 18 With sample spacing established at 10.3 meters, 19 data points are available for this survey.
Data point locations are identified in Attachment 2.
QAIQC Sampling A minimum of 5% of the sample population and 5% of the scan survey area are required to be selected for QA/QC verification in accordance with BRP Procedure RM-79, Final Status Survey Quality Control. As a conservative measure, three (3) soil samples and 10% of the scan survey area will be selected for QA/QC evaluation. Data point locations for soil samples will be determined by random number selection.
The QA/QC scan starting point and track direction are also determined by random number selection. The first random data point selected will identify the scanning start point and the second random data point will determine the direction in which the scan will track. QA/QC location results are provided in Table 3 below:
Survey Design FSS 05C 11 Page 2 of 7
 
Table 3 Random Numbers Generated for QA/QC SRandom                                                   Random Samples                 Sample       Verification Scan                             Sample Samples                 Number                                                     Number Split Sample:                 3       Start Point:                                       12 Sample Recount:               5     Scan Toward:                                         3 Sample Recount:               11     Scan Area Requirement:                             193 M 2 Surface Scanning The coverage requirement for surface scanning in this Class 1 area is 100%. The Scan MDC has been established at fractional values of the DCGLw for typical background activity levels at Big Rock Point. Scan MDC values for varying backgrounds are provided in Attachment 3. The investigation level for identification of potential areas of elevated activity in this survey area will be the Scan   DCGL as defined by the following:
Scan DCGL = Detector Rating CPM . Exposure Model uR/hr . DCGLw uR/hr                         pCi/g Scan DCGL for Co-60 = 1818 CPM Scan DCGL for Cs-137 = 3518 CPM Where:'
Detector Rating = 1200 CPM Cs- 137 and 565 CPM Co - 60 uR/hr                     uR/hr Exposure Model = 1.229 uR/hr Cs-137 and 5.029 uR/hr Co -60 5pCi/g                       5 pCi/g DCGLw = 11.93 pCi/g Cs-137 and 3.21 pCi/g Co-60 The DCGLw for Co-60 is the most limiting value for scanning measurements performed to identify areas of potentially elevated activity. Scanning conducted for this survey will assume all residual radioactivity to originate from Co-60 and the instrument response at the Co-60 DCGLw (1818 cpm) will be used as the scanning investigation level for FSS 05C11.
          'These values established in EA-BRP-SC-0201, Nal Scanning Sensitivity for Open Land Survey.
Survey Design FSS 05C, 1 Page 3 of 7
 
Attachment I Design Data - FSS 05C 1 1 Protected Area Supporting Surveys Cs-1 37           Co-60 Survey No. Sequence         Activity           Activity No.         (pCi/g)           (pCi/g)
.HH060705         16538,! ,     :.&#xfd;1.26       . 0.66 16539'       &#xfd;0.06               0.06*
HH060705 "HHO60705-     _ 16540-           1.050.66 TB062805       '16755             1.16             "G27,
.TB062805         16756",         0-47 .           0.1*
TB062805&#xfd;]       16774           0.19             0.31 Mean:       0.698             0.352 Std Dev:       0.524             0.255
* Measurement system MDA - Co-60 not identified in this sample Survey Design FSS 05C11 Page 4 of 7
 
Attachment 2 Soil Sample Locations - Survey 05C11 Central Protected Area 89   17190 20821 191         19213 211212         21" 4
227         229231 246                                 250 2369 35     31639 37   328                                   1 X=30.3 m 340   "343
        -       Survey Unit 05C _1                       0 i i 1 5   10 I
20 Meters I
* Sample Location Sample spacing Is 10.3 metors Survey Design FSS 05C11 Page 5 of 7
 
Attachment 3 Scan MDC In Varying Backgrounds Background     d'                   Si       MDCasurveyor   Cs-137 Co-60 Cs-137 Co-60 2000       2.48         4       28.64         607.47     0.51   1.08 2.06   1.07 3000       2.48         4       35.07         744.00     0.62   1.32 2.52   1.31 3500       2.48         4       37.88         803.61     0.67   1.42 2.72   1.41 4000       2.48         4     40.50           859.10     0.72   1.52 2.91   1.51 4500       2.48         4     42.95           911.21     0.76   1.61 3.09   1.60 5500       2.48         4     47.49         1,007.38     0.84   1.78 3.42   1.77 6000       2.48         4     49.60         1,052.17     0.88   1.86 3.57   1.85 6500       2.48         4     51.63         1,095.14     0.91   1.94 3.71   1.93 7000       2.48         4     53.57         1,136.48     0.95   2.01 3.85   2.00 8000       2.48         4     57.27         1,214.95     1.01   2.15 4.12   2.14 8500       2.48         4     59.04         1,252.34     1.04   2.22 4.25   2.20 9000       2.48         4     60.75         1,288.65     1.07   2.28 4.37   2.27 9500       2.48         4     62.41         1,323.96     1.10   2.34 4.49   2.33 10500       2.48         4       65.61         1,391.90     1.16   2.46 4.72   2.45 11000       2.48         4       67.16         1,424.65     1.19   2.52 4.83   2.51 11500       2.48         4       68.67         1,456.67     1.21   2.58 4.94   2.56 12000       2.48         4       70.14         1,488.00     1.24   2.63 5.04   2.62
                          -4     71.5   -15i68               127   26     515~* 2T 13000       2.48         4       73.01         1,548.76     1.29   2.74 5.25   2.73 13500       2.48         4       74.40         1,578.26     1.32   2.79 5.35   2.78 14000       2.48         4       75.77         1,607.22     1.34   2.84 5.45   2.83 14500       2.48         4       77.11         1,635.67     1.36   2.89 5.55   2.88 4i&sect;7&21 re'--&4K248                              ~~ 3       4       i64 64,Xi2
_______ ~~o~0' 5,Q3E+to Survey Design FSS 05C 11 Page 6 of 7
 
Attachment 4 Area Factors for Open Land Survey Evaluation Contaminated_   Calculated Area Factors at Time of Peak Dose Contaminated   H-3 Mn-54   Fe-55   Co-60       Sr-90 Cs-137 Eu-152 Eu-154   Eu-155 Area (in 2) 8094       1.00   1.00   1.00     1.00       1.00 1.00     1.00   1.00 1.00 4047       1.00   1.01   1.00     1.01       1.00 1.02     1.02   1.01 1.02 2024       1.00   1.03   1.00     1.03         1.00 1.03     1.03   1.03 1.03 1012       1.35   1.04   1.00     1.04         1.00 1.04     1.05   1.04 1.04 506       2.91   1.09   1.98     1.08         1.98 1.13     1.07   1.07 1.06 253       6.05   1.14   3.95     1.13         3.94 1.20     1.11   1.11 1.09 126       12.4   1.20   7.93     1.20         7.87 1.29     1.17   1.16 1.14 63       24.9   1.30   15.8     1.30         15.6 1.41     1.27   1.26 1.23 32       49.2   1.49   31.2     1.49         30.5 1.62     1.44   1.45 1.39 16     98.9   1.78   62.0     1.78         59.9 1.93     1.72   1.73 1.63 8       198   2.38   123     2.38         117   2.58     2.30   2.31 2.14 4       397   3.61   243       3.62         230   3.91     3.49   3.52 3.19 2       794   5.68   473       5.75         452   6.14     5.48   5.55 4.90 1       1590   9.57   905       9.73         887   10.3     9.24   9.39 7.88 Survey Design FSS 05C 11 Page 7 of 7
 
RM-76                                                                         Revision 1 FINAL STATUS SURVEY DESIGN                                                 Page 19 of 19 RM-76-5 FINAL STATUS SURVEY APPROVAL AND AUTHORIZATION FOR IMPLEMENTATION Survey Code     05C* 1 Survey Area


== Description:==
== Description:==


Final Status Survey 05C,1 encompasses 1924 m 2 at or below the grade elevation present during plant power operations in the central section of the Protected Area. No materials of plant origin remain in the survey area.The survey area is authorized for Final Status Survey Implementation.
Final Status Survey 05C,1 encompasses 1924 m 2 at or below the grade elevation present during plant power operations in the central section of the Protected Area. No materials of plant origin remain in the survey area.
7 -[esigned by Tech al Review by 629/y 9oDat Date Date RM-76.doc RM-77 FINAL STATUS SURVEY IMPLEMENTATION Revision 2 Page 8 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 1 of 3 Step (1)1.0 Initial Date PREPARATION FOR SURVEY survey#W 1.1 Survey Area Status: a. Final Status Survey Design has been approved for implementation (see RM-76-5, Final Status Survey Approval and Authorization for Supplementation).
The survey area is authorized for Final Status Survey Implementation.
: 1. Survey area walkdown complete 2. Survey area determined ready for FSS 3. Decommissioning activities that may impact the environmental status of the survey area have been completed.
629/y      9oDat 7   - [esigned by                         Date Tech al Review by                       Date RM-76.doc
: 4. Survey area environment is controlled by barriers and postings or other approved method to restrict access.2 b. Survey area has been turned over to the Environmental Services Survey Group (ESSG) in acceptable condition for FSS.XESILj/G 1.2 Field Preparation:
 
: a. Survey unit boundaries delineated (Step 6.1.1)b. Statistical soil samples predetermined in the survey design are located and marked within the survey unit.(Step 6.1.2)c. Soil sample locations verified (Step 6.1 .2.c)d. Instruments and equipment have been collected and calibrated for data measurement and collection (Step 6.1.3)e. Field documentation is prepared (Step 6.1.4)r).,(Iz -01 Llrzoto 67ESS-G RM-77.doc RM-77 FINAL STATUS SURVEY IMPLEMENTATION Revision 2 Page 9 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 2 of 3 Initial Date 2.0 DATA COLLECTION 2.1 Soil Survey: v/ All soil samples collected and controlled (Step 6.2.1).SESSG 0-9kio&2.2 Surface Scan:.Surface Scan complete.
RM-77                                                                             Revision 2 FINAL STATUS SURVEY IMPLEMENTATION                                             Page 8 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 1 of 3 Step                                                                         Initial    Date (1) 1.0     PREPARATION FOR SURVEY survey#W 1.1     Survey Area Status:
Action response requirements have been conducted on any identified areas exceeding the investigation level (Step 6.3).2.3 Judgmental Soil Samples: uESSG A44 44 a. Judgmental soil samples have been collected and controlled (Step 6.2.3).b. Deep core profiles performed in areas identified to contain elevated residual activity (Step 6.2.3).fE S _SG 3.0 SAMPLE PREPARATION AND LABORATORY ANALYSIS 3.1 Sample Preparation (Step 6.4.1)::iz~a.b.C.d.Soil samples are homogenous Soil samples are visibly dry prior to packing Non-soil materials have been removed from sample Soil samples have been transferred to one-liter Marinelli containers and are labeled and sealed.rl&#xfd;&#xfd;tSSG 01j'pa2b 4 RM-77.doc RM-77 FINAL STATUS SURVEY IMPLEMENTATION Revision 2 Page 10 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 3 of 3 Initial Date 3.2 Laboratory Analysis: 7 Isotopic analyses are complete.
: a. Final Status Survey Design has been approved for implementation (see RM-76-5, Final Status Survey Approval and Authorization for Supplementation).
The spectroscopy report requires a signature of completion by the laboratory analyst and a signature of evaluation documenting that a second level review has been performed (Step 6.4.2).3.3 Sample Control and Documentation:
: 1.     Survey area walkdown complete
/E! YS-'SG V J, 9 JO6 (0 z Chain of custody documentation exhibits control of soil samples (Step 6.4.3).?E S -SG c9 2c a,, /Zyo Reviewed by Date RM-77.doc RM-59 Revision 11 SAMPLING AND ANALYSIS OF OPEN LAND Page 7 of 13 AREAS FOR SITE CHARACTERIZATION SURVEYS ATTACHMENT RM-59-1 SAMPLING AND ANALYSIS REPORT Date: 09-18-2006 Time: 1600 Location:
: 2.     Survey area determined ready for FSS
05C 1 1 Tech: TRS/WMH/JNS SURVEY IDENTIFICATION  
: 3.     Decommissioning activities that may impact the environmental status of the survey area have been completed.
/ DESCRIPTION Survey 05C01 encompasses 1924 m2 at or below the grade elevation present during plant Power operations in the central section of the Protected Area. No materials of plant origin remain in this area.SURVEY TYPE Survey Type: Characterization X Scan (Motive)Remediation X Final Scan (Static)Trenching and Digging (use RM-59-4)SURVEY DESIGN Sample Collection:
: 4.     Survey area environment is controlled by barriers and postings or other approved method to restrict access.
_ Judgmental
2*    b. Survey area has been turned over to the Environmental XESILj/G Services Survey Group (ESSG) in acceptable condition for FSS.
_ Random X Systematic
1.2   Field Preparation:
_ Large Container Assay Scan Coverage:
: a. Survey unit boundaries delineated (Step 6.1.1)
100%ANALYSIS Inst.SN/Cal Due 186201/09-30-2006 DAILY CHECK: X SAT UNSAT INIT: TRS Inst.SN/Cal Due 186194/02-08-2007 DAILY CHECK: X SAT UNSAT INIT: TRS Inst.SN/Cal Due 193709/02-21-2007 DAILY CHECK: X SAT UNSAT INIT: TRS Inst.SN/Cal Due Det. #6 DAILY CHECK: X SAT UNSAT IN IT: Jp Inst.SN/Cal Due DAILY CHECK: SAT UNSAT INIT: Investigation of Unidentified Peaks: X SAT UNSAT INIT: JLR Minimum Detectable Activity (Section 5.3.2) X SAT UNSAT INIT: JLR COMMENTS Survey 05C01 was performed in a random start, square arid, systematic samplina pattern with samples collected at 20 data point locations.
: b. Statistical soil samples predetermined in the survey design are located and marked within the survey unit.
Laboratory analyses did not identify residual radioactivity above trace levels of the DCGL value. Surface scanning identified no areas of elevated residual radioactivity.
(Step 6.1.2)
The results of the QA/QC verification scan (10%) were consistent with the scan values identified in the survey.Technician Signature:  
: c.     Soil sample locations verified (Step 6.1 .2.c)
,,Jt , ,LL -e: Second Level Review Signature:
: d.     Instruments and equipment have been collected and calibrated for data measurement and collection e.
Date: /01// /(RM-59.doc Soil Sample Activity Summary Release Record 05Cll Central Protected Area Survey Unit 05C1_1 S Sample Location 0 4.5 9 18 Meters i 1 1 1 :1 A Surface Scan Summary Release Record 05C 1 1 Central Protected Area 3.81 17 3.2 1 4.0 3. 7 3- 1 3. 9 .4.1 o 4.1 5.0~ 4,1 4.3 4.14.3.5 14A 36 4.4.4.04f 4.5 1I 0 4.4~ __ ____ ____ ___ 4.4 I ~ 4I 2-Survey Unit 05CI_1 S Sample Location 0 4.5 9 18 Meten Ili ii i ii i i RED Values are Average Mobile Scan General Area Activity (kcpm)BLUE Values are Average Verification Scan General Area Activity (kcpm)GREY Values are Average General Background Area Activity (kcpm)Primary Scan : Technician Signature:
(Step 6.1.3)
'A"920;91W&#xfd;W  
Field documentation is prepared (Step 6.1.4) r).,(Iz - 01 Llrzoto 67ESS-G RM-77.doc
%QC Verification Scan: ,/0 %Technician Signature:
 
Dats: Time: Date: &#xa3;Time:
RM-77                                                                       Revision 2 Page 9 of 12 FINAL STATUS SURVEY IMPLEMENTATION RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 2 of 3 Initial   Date 2.0   DATA COLLECTION 2.1     Soil Survey:
RM-72 SAMPLE CHAIN-OF-CUSTODY Revision 0 Page 4of 5 05C1l RM-72-1 CHAIN-OF-CUSTODY RECORD Sample Number Sampling Location Date Time Final Disposition of Sample 1 Grid#329 (2.8) (7.2) o-0g- IAqo 2 Grid#330 (3.1) (7.2) _ -__-0_ _____3 Grid#318 (3.1) (7.6) 0 )2fo 3 QA Split Grid # 318 (3.1) (7.6) 4 Grid#317 (2.8) (7.6)5 (R) Grid # 304 (2.5) (8.0) OIS D' C 6 Grid #305 (2.8) (8.0) 2SQ 7 Grid#306 (3.1) (8.0) -I)S 8 Grid#268 (3.1) (8.4) ?4-V ( O'9 Grid#267 (2.8) (8.4) 1(/3-0(p 120 10 Grid # 266 (2.5) (8.4) c4oI 3 03 11 (R) Grid#247 (2.5) (8.8) (13005 12 Grid # 248 (2.8) (8.8) --) ' ,,? O&'13 Grid # 249 (3.1) (8.8) Nj-0 61 13to 14 Grid#230 (3.1) (9.2) 1213 15 Grid #229 (2.8) (9.2) -I 31S\16 Grid #228 (2.5) (9.2) (17 Grid#209 (2.5) (9.6) qit"-o-0 13P, 18 Grid #210 (2.8) (9.6) ' _19 Grid#211 (3.1) (9.6) 13;3-T (Samples may be analyzed and stored, shipped for offsite evaluation or analyzed and disposed of.)* "/ t'v) R eDate Tim Re e odn~c, n 1. Reli quished/ :y:, I,, Dt Tie, y 2. Relinquishedb y: Date Time Received in good condition by: f 1 LT- ra, e____ __________6__-3
v/   All soil samples collected and controlled (Step 6.2.1).
: 3. Relinquished by: Date Time Received in good condition by: 4. Relinquished by: Date Time Received in good condition by: RM-72.doc RM-78 FINAL STATUS SURVEY ASSESSMENT Revision 2 Page 19 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 1 of 8 FINAL STATUS SURVEY: o5c, I 1.0 1.1 1.2 DATA VERIFICATION Data Acceptance Review the Implementation Checklist (RM-77-1) to verify that survey isolation and control measures were executed prior to FSS and are being maintained.
SESSG 0-9kio&
2.2   Surface Scan:
  .       Surface Scan complete. Action response requirements have been conducted on any identified areas exceeding the investigation level (Step 6.3).
uESSG 2.3   Judgmental Soil Samples:
A44     a.       Judgmental soil samples have been collected and controlled (Step 6.2.3).
44      b.       Deep core profiles performed in areas identified to contain elevated residual activity (Step 6.2.3).
fE_SG S
3.0   SAMPLE PREPARATION AND LABORATORY ANALYSIS 3.1   Sample Preparation (Step 6.4.1):
: a.       Soil samples are homogenous
: b.      Soil samples are visibly dry prior to packing C.      Non-soil materials have been removed from sample
:iz~    d.      Soil samples have been transferred to one-liter Marinelli containers and are labeled and sealed.     rl&#xfd;       01j'pa2b4
                                                                      &#xfd;tSSG RM-77.doc
 
RM-77                                                                         Revision 2 FINAL STATUS SURVEY IMPLEMENTATION                                     Page 10 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 3 of 3 Initial     Date 3.2   Laboratory Analysis:
7   Isotopic analyses are complete. The spectroscopy report requires a signature of completion by the laboratory analyst and a signature of evaluation documenting that a second                     V J, 9JO6 (0 level review has been performed (Step 6.4.2).                 /E! YS-'SG 3.3   Sample Control and Documentation:
z   Chain of custody documentation exhibits control of soil samples (Step 6.4.3).                                                           a,,
c9 /Zyo 2c
                                                                      ?E  S-SG Reviewed by                     Date RM-77.doc
 
RM-59                                                                                                   Revision 11 SAMPLING AND ANALYSIS OF OPEN LAND                                                                     Page 7 of 13 AREAS FOR SITE CHARACTERIZATION SURVEYS ATTACHMENT RM-59-1 SAMPLING AND ANALYSIS REPORT Date: 09-18-2006               Time: 1600                 Location: 05C1 1                   Tech: TRS/WMH/JNS SURVEY IDENTIFICATION / DESCRIPTION Survey 05C01 encompasses 1924 m2 at or below the grade elevation present during plant Power operations in the central section of the Protected Area. No materials of plant origin remain in this area.
SURVEY TYPE Survey Type:                       Characterization     X       Scan (Motive)
Remediation X     Final                         Scan (Static)
Trenching and Digging (use RM-59-4)
SURVEY DESIGN Sample Collection:       _     Judgmental     _     Random     X     Systematic     _     Large Container Assay Scan Coverage:           100%
ANALYSIS Inst.SN/Cal Due 186201/09-30-2006               DAILY CHECK:         X     SAT               UNSAT       INIT: TRS Inst.SN/Cal Due 186194/02-08-2007               DAILY CHECK:         X     SAT               UNSAT       INIT: TRS Inst.SN/Cal Due 193709/02-21-2007               DAILY CHECK:         X     SAT               UNSAT       INIT: TRS Inst.SN/Cal Due Det. #6                         DAILY CHECK:         X     SAT               UNSAT       INIT: Jp Inst.SN/Cal Due                                 DAILY CHECK:               SAT               UNSAT       INIT:
Investigation of Unidentified Peaks:                                 X     SAT               UNSAT       INIT: JLR Minimum Detectable Activity (Section 5.3.2)                         X       SAT               UNSAT       INIT: JLR COMMENTS Survey 05C01 was performed in a random start, square arid, systematic samplina pattern with samples collected at 20 data point locations. Laboratory analyses did not identify residual radioactivity above trace levels of the DCGL value. Surface scanning identified no areas of elevated residual radioactivity. The results of the QA/QC verification scan (10%) were consistent with the scan values identified in the survey.
Technician Signature: ,,Jt       ,       ,LL                 -e:
Second Level Review Signature:             */(t//$f*-4/,/.                                Date:     /01//   /(
RM-59.doc
 
Soil Sample Activity Summary Release Record 05Cll Central Protected Area Survey Unit 05C1_1                             0 4.5   9     18 Meters 1i 1 1   :1 A S Sample Location
 
Surface Scan Summary Release Record 05C11 Central Protected Area 3.81   17                 3.2                 14.0
: 3. 7         3-                 1 4.1 5.0~             4,1 4.3         4.14.
3.5 3. 9.        4.1                    o 14A 36    1I4.4.           0    4.4 4.04f              4.5
                                              ~ ____
__       ____   ___   4.4 I~       4I       2
-Survey     Unit 05CI_1 0 4.5 9         18 Meten S  Sample Location                                                                Ili ii   i ii     ii RED Values are Average Mobile Scan General Area Activity (kcpm)
BLUE Values are Average Verification Scan General Area Activity (kcpm)
GREY Values are Average General Background Area Activity (kcpm)
Primary Scan :               'A"920;91W&#xfd;W Technician Signature:                          Dats:
Time:
QC Verification Scan:         ,/0 %
Technician Signature:                         Date: &#xa3; Time:
 
RM-72                                                                                                           Revision 0 SAMPLE CHAIN-OF-CUSTODY                                                                                         Page 4of 5 05C1l RM-72-1 CHAIN-OF-CUSTODY RECORD Sample Number                 Sampling Location                     Date           Time       Final Disposition of Sample 1                   Grid#329         (2.8) (7.2)                       o-0g- IAqo 2                   Grid#330         (3.1) (7.2)             _   -__-0_     _____
3                    Grid#318       (3.1)   (7.6)                         0     )2fo 3       QA Split     Grid # 318     (3.1)   (7.6)             *j76              (.L*t *L 4                   Grid#317       (2.8) (7.6) 5             (R)   Grid # 304     (2.5) (8.0)                                   OISCD' 6                   Grid #305       (2.8) (8.0)                                   2SQ 7                   Grid#306       (3.1)   (8.0)                         -     I)S 8                   Grid#268       (3.1)   (8.4)             ?4-V           (       O' 9                   Grid#267       (2.8)   (8.4)                               1(/3-0(p 120 10                   Grid # 266     (2.5) (8.4)               c4oI               3 03 11           (R)   Grid#247       (2.5) (8.8)               qJ(g*fo (1300*5 12                   Grid # 248     (2.8) (8.8)                   - -) '         ,,? O&'
13                   Grid # 249     (3.1) (8.8)                     Nj-0 61 13to 14                   Grid#230       (3.1) (9.2)                               1213 15                   Grid #229       (2.8) (9.2)                   -             I 31S\
16                   Grid #228       (2.5) (9.2)                             (
17                   Grid#209       (2.5) (9.6)                 qit"-o-0 13P, 18                   Grid #210     (2.8) (9.6)                       '     _
19                  Grid#211       (3.1)   (9.6)               7-[*g&#xfd;-(, 13;3-T (Samples may be analyzed and stored, shipped for offsite evaluation or analyzed and disposed of.)
            *           "/ C* t'v)                               Tim                   RReeDate e       odn~c,       *ito n
: 1. Reli quished/ :y:,         I,,   *,      Dt                 Tie,                                                         y
: 2. Relinquishedb y:                           Date               Time                   Received in good condition by:
f1LT-               ra,   e____                                             __________6__-3
: 3. Relinquished by:                           Date               Time                   Received in good condition by:
: 4. Relinquished by:                         Date                 Time                   Received in good condition by:
RM-72.doc
 
RM-78                                                                           Revision 2 FINAL STATUS SURVEY ASSESSMENT                                               Page 19 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 1 of 8 FINAL STATUS SURVEY:                   o5c, I 1.0           DATA VERIFICATION 1.1           Data Acceptance Review the Implementation Checklist (RM-77-1) to verify that survey isolation and control measures were executed prior to FSS and are being maintained.
Review RM-77, Final Status Survey Implementation, to verify that methods, techniques, and survey activities required for FSS have been applied in accordance with the appropriate procedures.
Review RM-77, Final Status Survey Implementation, to verify that methods, techniques, and survey activities required for FSS have been applied in accordance with the appropriate procedures.
Field QC Records: Review all assessments, Condition Reports and audits to ensure that identified issues have been resolved.Comments:.i1 Verify scan instrumentation was in calibration and the QC source checks were performed prior to and after surveys.1.3 Verify daily QC source checks for Canberra gamma spectroscopy detector properly logged prior to soil sample analysis.Review Verification:
1.2          Field QC Records:
__ Verify that the Data Quality Objectives are complete.____Verify that the survey design has been technically reviewed.RM-78.doc RM-78 FINAL STATUS SURVEY ASSESSMENT Revision 2 Page 20 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 2 of 8 Verify that gamma spectroscopy results have received a technical review.Verify the Sample and Analysis Report (RM-59-1) is completed and reviewed.I Z.Data Verification Completed:
Review all assessments, Condition Reports and audits to ensure that identified issues have been resolved.
Comments&No Assesso'r/ /6/Do at/3-e O Date RM-78.doc RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 21 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 3 of 8 2.0 DATA VALIDATION
Comments:
      .i*1    Verify scan instrumentation was in calibration and the QC source checks were performed prior to and after surveys.
Verify daily QC source checks for Canberra gamma spectroscopy detector properly logged prior to soil sample analysis.
1.3          Review Verification:
__       Verify that the Data Quality Objectives are complete.
____Verify       that the survey design has been technically reviewed.
RM-78.doc
 
RM-78                                                                       Revision 2 FINAL STATUS SURVEY ASSESSMENT                                         Page 20 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 2 of 8 I  Z. Verify that gamma spectroscopy results have received a technical review.
Verify the Sample and Analysis Report (RM-59-1) is completed and reviewed.
Data Verification Completed:
                                  &No Comments Do  O at/3-e Assesso'r               Date
                  //
6/
RM-78.doc
 
RM-78                                                                            Revision 2 FINAL STATUS SURVEY ASSESSMENT                                              Page 21 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 3 of 8 2.0      DATA VALIDATION 2.1      Documentation Review:
Perform documentation review for quality control purposes and validate the data collected is complete and appropriate for use as defined by the survey design. Documentation includes:
Field measurement records Chain-of-custody Quality Control (QC) measurement records Current qualification of survey personnel Corrective Action Reports Data inputs (laboratory spectroscopy)
Sample preparation techniques 2.2      Detection Limit Review:
                ,__  Scan MDCs are below established site DCGLs.
                /j    Forced-count values are assigned as necessary when activity is not detected in a sample.
__      Minimum Detectable Concentration (MDC) values of gamma spectroscopy are below established DCGLs.
2.3       Quality Control (QC) Data Review:
              ,,__  Quality Control (QC) data results have received required reviews and are complete and consistent.
            ,_      Results of judgmental samples have been reviewed and evaluated.
__        Review to ensure that the analytical results of judgmental samples do not impact the evaluation for unrestricted release of the survey area.
RM-78.doc
 
RM-78                                                                            Revision 2 FINAL STATUS SURVEY ASSESSMENT                                              Page 22 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 4 of 8 2.4        Qualification of Data:
Statistical radionuclide-specific measurements for completeness. Evaluate the survey for determination of data usability and confirm that sufficient qualified data are present for the decision process.
: a.      Total number of statistical samples planned for the survey:
: b.      Total number of statistical samples determined as valid:      /
b  x 120    lo=
: c. Calculate % Completeness:                                f7______
Qualified data are A 00% completeness and are sufficient to support the Sign Test requirement for determination of unrestricted release.
Data Validation Completed:        O*-sNo Comments:
                                          /0 o(?
Assessor                      Date RM-78.doc
 
RM-78                                                                             Revision 2 FINAL STATUS SURVEY ASSESSMENT                                                 Page 23 of 26 RM-78-3 DATA ASSESSMENT REPORT
                                        .Page 5 of 8 3.0      DATA QUALITY ASSESSMENT 3.1      Review the DQOs and Survey Design:
Confirm that all inputs to the decision have been reviewed and are complete.
j/  Verify that boundaries or constraints identified in the survey area have not affected the quality of the data.
_--___  Review the Statement of Hypothesis and confirm that it remains relevant.
_      Confirm that Type I and Type IIerror limits are consistent with DQOs.
_"_"  Confirm that the survey design is consistent with DQOs and that the appropriate number of data points were obtained.
3.2      Preliminary Review:.
3.2.1    Preliminary Evaluation:
Quality Assessment (QA) reports consistent with procedure RM-79, Final Status Survey Quality Control.
Survey is of sufficient intensity to satisfy classification requirement.
Z      Potential trends of radioactivity levels in the survey area do not impact a decision for unrestricted release.
Comments:
RM-78.doc
 
I-RM-78                                                                              Revision 2 FINAL STATUS SURVEY ASSESSMENT                                                Page 24 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 6 of 8 3.2.2    Calculate Basic Statistical Quantities:
: a.        Number of qualified data points            /
: b.        Calculation of the Mean                0. 0OSI, (SOP-)
: c.        Calculation of the Median                t9.ocLog-)
: d.        Calculation Standard Deviation k    Attach graphic representation of the data if any radionuclide-specific measurements exceed 50% of the DCGL.
            ..      " Sample QA/QC measurements consistent with FSS data 3.3      Statistical Evaluation:
NOTE:        If all measurement data are less than the DCGLW, statistical testing in not required and the survey unit meets the regulatory requirement for unrestricted release.
All survey measurements are below the DCGLw.
3.3.1    Verify Assumptions of the Survey Design
_ _ Review the posting plot to verify that the data exhibits spatial independence. Spatial trends must be investigated and resolved prior to further assessment.
__Review            to verify dispersion symmetry. The appearance of skewed data must be investigated for cause and documented prior to further assessment.
RM-78.doc
 
I, RM-78                                                                        Revision 2 FINAL STATUS SURVEY ASSESSMENT                                            Page 25 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 7 of 8
                ,..I* Review the dataset standard deviation and range for data variance.
Questionable data must be investigated for cause and documented prior to further assessment.
jVerify that the data exhibits adequate power and confirm that the sample size is sufficient to satisfy the DQOs.
3.4      Draw Conclusions from the Data:
3.4.1    Investigation Levels and Response Actions v__    Determine if data results have exceeded any investigation level.
Document find ings~~~k7X/A20~                            ~4e~~
    *3.4.2  Evaluation for Unrestricted Release Select applicable conclusion:
Survey area acceptance criteria met and survey area satisfies the requirements for unrestricted release:
                        /'    All concentrations are less than the DCGLw. The Null Hypothesis is rejected.
The mean concentration of the survey area is below the DCGLw but individual measurements in the survey unit exceed the DCGLw. The Sign Test and EMC evaluation are successful and the Null Hypothesis is rejected.
RM-78.doc


===2.1 Documentation===
I, RM-78                                                                        Revision 2 FINAL STATUS SURVEY ASSESSMENT                                            Page 26 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 8 of 8 4,_    Survey area acceptance criteria not met and survey area fails to satisfy the requirements for unrestricted release:
                      ,4_    The mean concentration in the survey area exceeds the DCGLw. and the null hypothesis is confirmed.
4_.The mean concentration of the survey area is below the DCGLw but individual measurements in the Unit exceed the DCGLw..
The Sign Test and EMC evaluation are unsuccessful and the null hypothesis is confirmed.
Data Quality Assessment Completed:        Ye      No Comments
                                                /o-/3- O V Date Reviews:,
Date Tech i'ca fReview ES Superintendent                    Date RPES Manager                          Date RM-78.doc


Review: Perform documentation review for quality control purposes and validate the data collected is complete and appropriate for use as defined by the survey design. Documentation includes: Field measurement records Chain-of-custody Quality Control (QC) measurement records Current qualification of survey personnel Corrective Action Reports Data inputs (laboratory spectroscopy)
RM-78-3, Attachment I Statistical Quantities Release Record 05C 11 Central Protected Area Sample              Cs-137            Co-60      Weighted          **Weighted Sum Number            (pCi/gm)           (pCilgm)      Sum (SOR)              <DCGLw?          DCGL-W. Sum Sign.
Sample preparation techniques
1                0.0218            0.0120        0.0056                  yes            0.9944    +1 2                0.0279            0.0173        0.0077                  yes            0.9923    +1 3                0.0559            0.0106        0.0080                  yes            0.9920    +1 4                0.0501            0.0002        0.0043                  yes            0.9957    +1 5                0.0710            0.0404        0.0185                  yes            0.9815    +1 6                0.0745            0.0144        0.0107                  yes            0.9893    +1 7                0.1045            0.0059        0.0106                  yes            0.9894    +1 8                0.1357            -0.0099        0.0083                  yes            0.9917    +1 9                0.0861            0.0101        0.0104                  yes            0.9896    +1 10                0.0462            0.0048        0.0054                  yes            0.9946    +1 11                0.0124            -0.0006        0.0009                  yes            0.9991    +1 12                0.0018            0.0119        0.0039                  yes            0.9961    +1 13              0.0386            0.0082        0.0058                  yes            0.9942    +1 14              -0.0002            -0.0108      -0.0034                  yes            0.9966    +1 15              0.0390            0.0047        0.0047                  yes            0.9953    +1 16              0.0208            -0.0117        -0.0019                  yes            0.9981    +1 17              0.0531            -0.0152        -0.0003                  yes            0.9997    +1 18              0.0384            -0.0027        0.0024                  yes            0.9976    +1 19              0.0110            0.0126        0.0048                  yes            0.9952    +1 Std. Dev            0.0356            0.0129        0.0051 Mean              0.0468            0.0054        0.0056 Median              0.0390            0.0059        0.0054 Number of Positive Differences (S+):      n/a Critical Value, k, Table 1.3 of Marssim:      n/a S+ >than k?:        n/a Survey Unit Pass or Fail:    **Pass
*Note: Forced-Count values are used for samples with activity levels below the MDA.
**Note: If all measurement data are less than the DCGL ., then the Sign Test is not required.


===2.2 Detection===
RM-79                                                                    Revision 1 FINAL STATUS SURVEY QUALITY CONTROL                                    Page 11 of 13 RM-79-1 FSS QUALITY CONTROL EVALUATION RESULTS FSS Package #      5~5X2, /                      QC Package #
*NOTE: If Acceptance Criteria is not met, completion of Attachment RM-79-2, FSS Quality Control Investigation Results, is required.
Comments:
14U '
                                                      /      tj Reviews:
                                      !-/ ip060 valuato                          Date Technical Review                    Date RM-79.doc


Limit Review: ,__ Scan MDCs are below established site DCGLs./j Forced-count values are assigned as necessary when activity is not detected in a sample.__ Minimum Detectable Concentration (MDC) values of gamma spectroscopy are below established DCGLs.2.3 Quality Control (QC) Data Review: ,,__ Quality Control (QC) data results have received required reviews and are complete and consistent.
QA Verification Split Sample Analysis Table I Date:                9/20/2006                                                                  Acceptance Criteria Resolution          Ratio QA:                   05C,1 Central Protected Area                                                  <4            N/A 4-7            0.5-2.0 Type:                  Split Sample                                                              8-15          0.6-1.66 16-50          0.75-1.33 Lab:                  In-House                                                                51-200          0.8-1.25
,_ Results of judgmental samples have been reviewed and evaluated.
                                                                                                    >200          0.85-1.18 A              B                C                D          E              F BRP                                                                                                                        Results in Result            BRP            BRP              BRP        Acceptance        Split                    Comparison      Agreement Sample              Radionuclide          Below            Results        % Error            BRP              Ratio      Results    Split Results      Ratio Resolution(pi)                                                                  opr Beo              (pCi/g)      (Sigma)                         (Table 1)   Below MDA      (pC/g)          FIA            Compare MDA                                                                                                                        G with D) 3                  Co-60                              0.0633            n/a              n/a            n/a          <          0.0594          0.94              YES 3                  Cs-137                              0.0559          38.89            2.57              n/a                      0.0414          0.74              YES I                    .4            -I-             I                1              1                          4 I                    4              4.                                               4.            4-           I              4 I                    4              4              I                4              4-             4.          4              4-4                   .4              4.            4                4              4              .4           4              4-           4 I                    .4              .4            4                4              4.             4            4                            4
__ Review to ensure that the analytical results of judgmental samples do not impact the evaluation for unrestricted release of the survey area.RM-78.doc RM-78 FINAL STATUS SURVEY ASSESSMENT Revision 2 Page 22 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 4 of 8 2.4 Qualification of Data: Statistical radionuclide-specific measurements for completeness.
                        &#xa3;                    .4              .4            I                I              4.             I          4              4-L                    .4 _____        .4 _______    1 ________        1 ______        .4 _______      1                                          _________
Evaluate the survey for determination of data usability and confirm that sufficient qualified data are present for the decision process.a. Total number of statistical samples planned for the survey: b. Total number of statistical samples determined as valid: /c. Calculate
Resoltuionc            (A)(B7A    0 I
% Completeness:
< Indicatesresults less than the MDA.
b x 120 lo= f7______Qualified data are A 00% completeness and are sufficient to support the Sign Test requirement for determination of unrestricted release.Data Validation Completed: Comments: Assessor/0 o(?Date RM-78.doc RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 23 of 26 RM-78-3 DATA ASSESSMENT REPORT.Page 5 of 8 3.0 DATA QUALITY ASSESSMENT
*Note      Results are consideredin agreement for MDA and near-MDA measurementcomparisons Results fthat fail agreement must be investigatedper RM-79.


===3.1 Review===
QA Verification                                                          I Sample Recount Analysis Table I Date:               9/20/2006                                                            Acceptance Criteria Resolution        Ratio QA:                  05C,1 Central Protected Area                                            <4            N/A 4-7          0.5-2.0 Type:                Sample Recounts                                                      8-15        0.6-1.66 16-50      0.75-1.33 Lab:                 In- House                                                          51-200        0.8-1.25
the DQOs and Survey Design: Confirm that all inputs to the decision have been reviewed and are complete.j/ Verify that boundaries or constraints identified in the survey area have not affected the quality of the data._--___ Review the Statement of Hypothesis and confirm that it remains relevant._ Confirm that Type I and Type II error limits are consistent with DQOs._"_" Confirm that the survey design is consistent with DQOs and that the appropriate number of data points were obtained.3.2 Preliminary Review:.3.2.1 Preliminary Evaluation:
                                                                                              >200        0.85-1.18 A              B              C              D      E        F              G BRP                                                                                                    Results in BRP            BRP                    Acceptance            Recount      Comparison Sample          SapeRadionuclide Rdould              Result eut            BRe t Results        %
Quality Assessment (QA) reports consistent with procedure RM-79, Final Status Survey Quality Control.Survey is of sufficient intensity to satisfy classification requirement.
                                                                              % EBRP Error    Reouin          atio Ratio  Recount Reut    Results          RatioCopr Agreement Below                                      Resolution                Result MDA            (pCi/g)        (Sigma)                    (Table 1) Below MDA  (pCi/g)sCompare F/A        G with D)
Z Potential trends of radioactivity levels in the survey area do not impact a decision for unrestricted release.Comments: RM-78.doc I -RM-78 FINAL STATUS SURVEY ASSESSMENT Revision 2 Page 24 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 6 of 8 3.2.2 Calculate Basic Statistical Quantities:
___Below            MDAth__D)        ___D__G 5                  Co-60              <            0.0731            n/a          n/a            n/a            0.0822          1.12        YES 5                  Cs-137                          0.0710          24.90        4.02          0.5-2.0            0.0426          0.60        YES 11                  Co-60              <          0.0494            n/a          n/a            n/a            0.0607          1.23        YES 11                  Cs-137              <          0.0523            n/a          n/a            n/a            0.0564          1.08        YES Resolution        C =  (A)(B        0
: a. Number of qualified data points /b. Calculation of the Mean c. Calculation of the Median d. Calculation Standard Deviation 0. 0OSI, (SOP-)t9.ocLog-)
< Indicates results less than the MDA.
3.3 k Attach graphic representation of the data if any radionuclide-specific measurements exceed 50% of the DCGL..." Sample QA/QC measurements consistent with FSS data Statistical Evaluation:
*Note      Results are consideredin agreement for MDA and near-MDA measurementcomparisons Results fthat fail agreementmust be investigatedperRM-79.
NOTE: If all measurement data are less than the DCGLW, statistical testing in not required and the survey unit meets the regulatory requirement for unrestricted release.All survey measurements are below the DCGLw.Verify Assumptions of the Survey Design_ _ Review the posting plot to verify that the data exhibits spatial independence.
 
Spatial trends must be investigated and resolved prior to further assessment.
Tritium in Soil Data Results Final Status Survey 05C 1 1 Sample              Tritium in Soil Number                    pCi/g 3                     1.227 5                      0.009 11                      0.013 Mean:       0.4163 Median:       0.0130 St. Dev:      0.7021 Note: The DCGL for Tritium is 327 pCi/g.
__Review to verify dispersion symmetry.
Sample results are less than 0.4% of the DCGL
The appearance of skewed data must be investigated for cause and documented prior to further assessment.
 
3.3.1 RM-78.doc I , RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 25 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 7 of 8 ,..I Review the dataset standard deviation and range for data variance.Questionable data must be investigated for cause and documented prior to further assessment.
09/2')/200    18:09              8475644517                                                                  &#xfd;'Aor- I U / I '.&#xfd; Environmental, Inc.
jVerify that the data exhibits adequate power and confirm that the sample size is sufficient to satisfy the DQOs.3.4 Draw Conclusions from the Data: 3.4.1 Investigation Levels and Response Actions v__ Determine if data results have exceeded any investigation level.Document find ings~~~k7X/A20~
Midwest Laboratory
~4e~~*3.4.2 Evaluation for Unrestricted Release Select applicable conclusion:
      -*      131Allegheny Teconologles Co, 700 LUnmwehr Rozd
Survey area acceptance criteria met and survey area satisfies the requirements for unrestricted release: ' / All concentrations are less than the DCGLw. The Null Hypothesis is rejected.The mean concentration of the survey area is below the DCGLw but individual measurements in the survey unit exceed the DCGLw. The Sign Test and EMC evaluation are successful and the Null Hypothesis is rejected.RM-78.doc I , RM-78 FINAL STATUS SURVEY ASSESSMENT Revision 2 Page 26 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 8 of 8 4,_ Survey area acceptance criteria not met and survey area fails to satisfy the requirements for unrestricted release: ,4_ The mean concentration in the survey area exceeds the DCGLw. and the null hypothesis is confirmed.
* Nortnbrook, IL 6006&!2310 ph. (847) 564-0700 - fax (847) 564.4517 Mr. David W. Parish                                                LABORATORY REPORT NO.             8022-100-234 Big RocK Point                                                        DATE:                             09-22-2006 10269 US-31 North                                                    SAMPLES RECEIVED:                  09-20-2006 Charlevoix, MI 49720                                                  PURCHASE ORDER NO:
4_.The mean concentration of the survey area is below the DCGLw but individual measurements in the Unit exceed the DCGLw..The Sign Test and EMC evaluation are unsuccessful and the null hypothesis is confirmed.
Below are the results of the analyses for tritium on three soil samples.
Data Quality Assessment Completed:
Excavated Soil Survey 05C11 Sample                             Collection              Lab            Concentration          MDA Description                              Date                Code            (pCi/g of soil)       (pCi/g of soil)
Ye No Comments Reviews:, Tech i'ca fReview ES Superintendent RPES Manager/o-/3- O V Date Date Date Date RM-78.doc RM-78-3, Attachment I Statistical Quantities Release Record 05C 1 1 Central Protected Area Sample Cs-137 Co-60 Weighted **Weighted Sum Number (pCi/gm) (pCilgm) Sum (SOR) <DCGLw? DCGL-W. Sum Sign.1 0.0218 0.0120 0.0056 yes 0.9944 +1 2 0.0279 0.0173 0.0077 yes 0.9923 +1 3 0.0559 0.0106 0.0080 yes 0.9920 +1 4 0.0501 0.0002 0.0043 yes 0.9957 +1 5 0.0710 0.0404 0.0185 yes 0.9815 +1 6 0.0745 0.0144 0.0107 yes 0.9893 +1 7 0.1045 0.0059 0.0106 yes 0.9894 +1 8 0.1357 -0.0099 0.0083 yes 0.9917 +1 9 0.0861 0.0101 0.0104 yes 0.9896 +1 10 0.0462 0.0048 0.0054 yes 0.9946 +1 11 0.0124 -0.0006 0.0009 yes 0.9991 +1 12 0.0018 0.0119 0.0039 yes 0.9961 +1 13 0.0386 0.0082 0.0058 yes 0.9942 +1 14 -0.0002 -0.0108 -0.0034 yes 0.9966 +1 15 0.0390 0.0047 0.0047 yes 0.9953 +1 16 0.0208 -0.0117 -0.0019 yes 0.9981 +1 17 0.0531 -0.0152 -0.0003 yes 0.9997 +1 18 0.0384 -0.0027 0.0024 yes 0.9976 +1 19 0.0110 0.0126 0.0048 yes 0.9952 +1 Std. Dev Mean Median 0.0356 0.0468 0.0390 0.0129 0.0054 0.0059 Number of Positive Differences (S+): Critical Value, k, Table 1.3 of Marssim: S+ >than k?: Survey Unit Pass or Fail: 0.0051 0.0056 0.0054 n/a n/a n/a**Pass*Note: Forced-Count values are used for samples with activity levels below the MDA.**Note: If all measurement data are less than the DCGL ., then the Sign Test is not required.
H-3 3                                    09-18-06            BRSO-6400        1.227 +/- 0.031            < 0.018 3                                    09-18-06            BRSO-6401        0.980 +/-0.028              < 0.018 5                                    09-18-06            BRSO-6402        0.009 t 0.007            < 0.013 11                                    09-18-06            SRSO-6403        0.013 +/- 0.007            < 0.012 Denotes a duplicate, The error given is the probable counting error at 95 % confidence level. The less than, (<), value is based on 4.66 sigma counting error for background sample.
RM-79 FINAL STATUS SURVEY QUALITY CONTROL Revision 1 Page 11 of 13 RM-79-1 FSS QUALITY CONTROL EVALUATION RESULTS FSS Package #5~5X2, /QC Package #*NOTE: If Acceptance Criteria is not met, completion of Attachment RM-79-2, FSS Quality Control Investigation Results, is required.Comments: 14U '/ tj Reviews: valuato Technical Review!-/ ip060 Date Date RM-79.doc QA Verification Split Sample Analysis Date: QA: 9/20/2006 05C,1 Central Protected Area Table I Acceptance Criteria Resolution Ratio<4 N/A 4-7 0.5-2.0 8-15 0.6-1.66 16-50 0.75-1.33 51-200 0.8-1.25>200 0.85-1.18 Type: Split Sample Lab: In-House A B C D E F BRP Results in Result BRP BRP BRP Acceptance Split Comparison Agreement Sample Radionuclide Results % Error BRP Ratio Results Split Results Ratio Below Resolution(pi) opr Beo (pCi/g) (Sigma) (Table 1) Below MDA (pC/g) FIA Compare MDA G with D)3 Co-60 0.0633 n/a n/a n/a < 0.0594 0.94 YES 3 Cs-137 0.0559 38.89 2.57 n/a 0.0414 0.74 YES I .4 -I- I 1 1 4 I 4 4. 4. 4- I 4 I 4 4 I 4 4- 4. 4 4-4 .4 4. 4 4 4 .4 4 4- 4 I .4 .4 4 4 4. 4 4 4&#xa3; .4 .4 I I 4. I 4 4-L .4 _____ .4 _______ 1 ________ 1 ______ .4 _______ 1 _________A I Resoltuionc (A)(B7 0< Indicates results less than the MDA.*Note Results are considered in agreement for MDA and near-MDA measurement comparisons Results fthat fail agreement must be investigated per RM-79.
APPROVED BY Tony Coorlim.
QA Verification Sample Recount Analysis I Date: QA: 9/20/2006 05C, 1 Central Protected Area Table I Acceptance Criteria Resolution Ratio<4 N/A 4-7 0.5-2.0 8-15 0.6-1.66 16-50 0.75-1.33 51-200 0.8-1.25>200 0.85-1.18 Type: Sample Recounts Lab: In- House A B C D E F G BRP Results in BRP BRP Acceptance Recount Comparison Sample Radionuclide Result BRe t % EBRP atio Recount Agreement Sape Rdould eut Results % Error Reouin Ratio Reut Results RatioCopr Below Resolution Result sCompare MDA (pCi/g) (Sigma) (Table 1) Below MDA (pCi/g) F/A G with D)___Below ___D__G MDAth__D)5 Co-60 < 0.0731 n/a n/a n/a 0.0822 1.12 YES 5 Cs-137 0.0710 24.90 4.02 0.5-2.0 0.0426 0.60 YES 11 Co-60 < 0.0494 n/a n/a n/a 0.0607 1.23 YES 11 Cs-137 < 0.0523 n/a n/a n/a 0.0564 1.08 YES Resolution C = (A)(B 0< Indicates results less than the MDA.*Note Results are considered in agreement for MDA and near-MDA measurement comparisons Results fthat fail agreement must be investigated per RM-79.
Quality Assurance SEP 22 2006 18:51                                                                  8475644517          PFGE. 10
Tritium in Soil Data Results Final Status Survey 05C 1 1 Sample Tritium in Soil Number pCi/g 3 1.227 5 0.009 11 0.013 Mean: Median: St. Dev: 0.4163 0.0130 0.7021 Note: The DCGL for Tritium is 327 pCi/g.Sample results are less than 0.4% of the DCGL 09/2')/200 18:09 8475644517 Environmental, Inc.Midwest Laboratory
 
-* 131 Allegheny Teconologles Co, 700 LUnmwehr Rozd
/,
* Nortnbrook, IL 6006&!2310 ph. (847) 564-0700 -fax (847) 564.4517&#xfd;'Aor- I U / I '.&#xfd;Mr. David W. Parish LABORATORY REPORT NO. 8022-100-234 Big RocK Point DATE: 09-22-2006 10269 US-31 North SAMPLES RECEIVED:
ATTACHMENT 4 CONSUMERS ENERGY BIG ROCKPOINT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION CLASS 1 FINAL STATUS SURVEY RELEASE RECORD, 06C 1 1, SOUTH CENTRAL PROTECTED AREA October 24, 2006 37 Pages
09-20-2006 Charlevoix, MI 49720 PURCHASE ORDER NO: Below are the results of the analyses for tritium on three soil samples.Excavated Soil Survey 05C 1 1 Sample Collection Lab Concentration MDA Description Date Code (pCi/g of soil) (pCi/g of soil)H-3 3 09-18-06 BRSO-6400 1.227 +/- 0.031 < 0.018 3 09-18-06 BRSO-6401 0.980 +/-0.028 < 0.018 5 09-18-06 BRSO-6402 0.009 t 0.007 < 0.013 11 09-18-06 SRSO-6403 0.013 +/- 0.007 < 0.012 Denotes a duplicate, The error given is the probable counting error at 95 % confidence level. The less than, (<), value is based on 4.66 sigma counting error for background sample.APPROVED BY Tony Coorlim.Quality Assurance SEP 22 2006 18:51 8475644517 PFGE. 10
 
/, ATTACHMENT 4 CONSUMERS ENERGY BIG ROCKPOINT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION CLASS 1 FINAL STATUS SURVEY RELEASE RECORD, 06C 1 1, SOUTH CENTRAL PROTECTED AREA October 24, 2006 37 Pages Class 1 Final Status Survey Release Record 06C 1 1 South Central Protected Area SURVEY PACKAGE CLOSURE Final Status Survey Documentation is authorized for closure. All required reviews are complete and the evaluation of data results have satisfied the criteria established for unrestricted release.Signed: &#xfd;F -lin&#xfd; &#xfd;(ESSG)Signed: Date: to --- 5o6 Date: /d-,:9 --o.6 Date: /o--2-5-6o 6 TES Superintendent)
Class 1 Final Status Survey Release Record 06C1 1 South Central Protected Area SURVEY PACKAGE CLOSURE Final Status Survey Documentation is authorized for closure. All required reviews are complete and the evaluation of data results have satisfied the criteria established for unrestricted release.
Signed: , -&E-'- e ,(F'P&#xfd; & ES kan-ager)
Signed:            &#xfd;F -lin&#xfd;  &#xfd;        Date:  to ---5o6 (ESSG)
Survey Area Requirements Final Status Survey, Release Record 06C 1 1 South Central Protected Area Survey Description Final Status Survey 06C 1 1 encompasses 1977 m 2 at or below the grade elevation present during plant power operations in the south central section of the Protected Area. No materials of plant origin remain in the survey area.History During power operations the Protected Area supported the components and systems necessary for electrical generation.
Signed:                              Date: /d-,:9    -- o.6 TES Superintendent)
The location of Survey Unit 06 is adjacent to the transport route used to move spent resin and filter media for radiological survey and offsite removal. Structures and enclosures formerly located in this area were once used for the storage of contaminated materials.
Signed:  ,        -&E-'-       e    Date:    /o--2-5-6o 6
A detailed review of the history and radiological characterization of Survey Unit 06 is provided in Appendix 2B and 2E of the LTP (License Termination Plan).Current Radiological Status Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Based on operational history and former locations of radioactive systems and material transport pathways the radiological status of this survey unit is Class 1.Post-Construction Expectations Final Status Survey 06C, 1 will be performed in the following activity sequence: 1. Walkdown:
                          ,(F'P&#xfd;  & ES kan-ager)
Environmental Services Survey Group (ESSG) personnel will perform a walkdown assessment to ensure survey area preparations are complete and confirm that the following post-construction expectations have been satisfied as applicable:
 
* Groundwater and Surface water control is adequate 0 All construction debris has been removed from the survey area 0 The survey location status meets all applicable safety requirements
Survey Area Requirements Final Status Survey, Release Record 06C11 South Central Protected Area Survey Description Final Status Survey 06C 1 1 encompasses 1977 m 2 at or below the grade elevation present during plant power operations in the south central section of the Protected Area. No materials of plant origin remain in the survey area.
: 2. Survey Area Isolation and Control: Control measures will be established to ensure that any potential ongoing decommissioning activities in adjacent locations do not impact the current survey area status. Isolation and control measures include postings, barriers, access points, and the evaluation of ongoing work activities in adjacent areas.Survey Area Requirements FSS O6C 1 Page 1 of 2
History During power operations the Protected Area supported the components and systems necessary for electrical generation. The location of Survey Unit 06 is adjacent to the transport route used to move spent resin and filter media for radiological survey and offsite removal. Structures and enclosures formerly located in this area were once used for the storage of contaminated materials. A detailed review of the history and radiological characterization of Survey Unit 06 is provided in Appendix 2B and 2E of the LTP (License Termination Plan).
: 3. Survey Design and Execution:
Current Radiological Status Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Based on operational history and former locations of radioactive systems and material transport pathways the radiological status of this survey unit is Class 1.
Survey design and execution will follow the Data Quality Objectives for 06C 1 1 in accordance with the survey requirements established in procedures RM-76, Final Status Survey Design and RM-77, Final Status Survey Implementation, and LTP, Chapter 5. Survey size will be based on the statistical requirements of the Sign Test for Class 1 areas with soil samples collected in random start, systematic data point locations.
Post-Construction Expectations Final Status Survey 06C, 1 will be performed in the following activity sequence:
Surface scanning will be performed with 100%survey area coverage.
: 1. Walkdown: Environmental Services Survey Group (ESSG) personnel will perform a walkdown assessment to ensure survey area preparations are complete and confirm that the following post-construction expectations have been satisfied as applicable:
This survey will be conducted in accordance with approved BRP procedures and follow the guidance of NUREG 1575.4. Data Quality Assessment:
* Groundwater and Surface water control is adequate 0    All construction debris has been removed from the survey area 0    The survey location status meets all applicable safety requirements
Isolation and control of the survey area will be maintained until the survey Data Quality Assessment demonstrates that the regulatory requirements for unrestricted site release have been satisfied.
: 2. Survey Area Isolation and Control: Control measures will be established to ensure that any potential ongoing decommissioning activities in adjacent locations do not impact the current survey area status. Isolation and control measures include postings, barriers, access points, and the evaluation of ongoing work activities in adjacent areas.
Survey Area Requirements FSS O6C 1 Page 2 of 2 J DATA QUALITY OBJECTIVES Final Status Survey, Release Record 06C 1 1 South Central Protected Area STATE THE PROBLEM The Problem: To demonstrate that the level of residual radioactivity in Class 1 Survey Unit 06 does not exceed the release criteria of 25 mrem/year Total Effective Dose Equivalent (TEDE) as specified in the License Termination Plan (LTP).Stakeholders:
Survey Area Requirements FSS O6C 1 Page 1 of 2
The primary stakeholders interested in the answer to this problem are Consumers Energy Co., and the general public as represented by the Michigan Department of Environmental Quality (MDEQ), and the US Nuclear Regulatory Commission (USNRC).The Planning Team: The planning team consists of members of the BRP Environmental Services Survey Group (ESSG). The primary decision maker will be the Final Status Survey Supervisor.
: 3. Survey Design and Execution: Survey design and execution will follow the Data Quality Objectives for 06C1 1 in accordance with the survey requirements established in procedures RM-76, Final Status Survey Design and RM-77, Final Status Survey Implementation, and LTP, Chapter 5. Survey size will be based on the statistical requirements of the Sign Test for Class 1 areas with soil samples collected in random start, systematic data point locations. Surface scanning will be performed with 100%
The Final Status Survey Supervisor will obtain input from the site Construction Group and Scheduling Group for issues relating to schedule and costs.Schedule: Approximately five (5) working days are projected to implement the survey and to collect and analyze field data.Resources:
survey area coverage. This survey will be conducted in accordance with approved BRP procedures and follow the guidance of NUREG 1575.
The primary resources needed to determine the answer to the problem are two (2)technicians to perform fieldwork, one (1) technician to prepare the samples and conduct laboratory analyses, and two (2) survey team members to prepare and review the design, generate maps, coordinate field activities and evaluate data.2. IDENTIFY THE DECISION Several decisions need to be defined to address the stated problem.Principal Study Question (1): Does the mean concentration of residual radioactivity in the survey unit exceed the release criteria stated above?Decision (1): Determine whether the mean concentration of residual radioactivity in the survey exceeds the release criteria stated in the problem.Actions (1): Alternative actions include failure of the survey unit, remediation, or no action required.Data Quality Objectives FSS 06C 1 I Page 1 of 5 Principal Study Question (2): Do any areas of elevated activity in the survey unit exceed the release criteria?The Decision (2): Determine if any areas of elevated activity in the survey unit exceed the release criteria.Actions (2): Alternative actions include confirmation and investigation, performing the elevated measurement comparison (EMC), remediation, or no action required.Principal Study Question (3): Is the potential dose from residual radioactivity in the survey unit ALARA as stated?The Decision (3): Determine if the potential dose from residual radioactivity in the survey unit is ALARA.ALARA requirements for soil remediation are defined in Chapter 4 of the LTP.Actions (3): Alternative actions include remediation or no action required.3. IDENTIFY INPUTS TO THE DECISION Information Needed: Characterization measurements are required to define the radionuclides present and determine the extent and variability of residual radioactivity in the survey area for design and implementation of the survey. Survey area classification, ALARA analysis, potential radionuclides of interest, and site-specific DCGL values are also required inputs to the decision process. The primary information required for evaluation is the analytical results of survey measurements.
: 4. Data Quality Assessment: Isolation and control of the survey area will be maintained until the survey Data Quality Assessment demonstrates that the regulatory requirements for unrestricted site release have been satisfied.
Survey Area Requirements FSS O6C 1 Page 2 of 2
 
J DATA QUALITY OBJECTIVES Final Status Survey, Release Record 06C11 South Central Protected Area STATE THE PROBLEM The Problem:
To demonstrate that the level of residual radioactivity in Class 1 Survey Unit 06 does not exceed the release criteria of 25 mrem/year Total Effective Dose Equivalent (TEDE) as specified in the License Termination Plan (LTP).
Stakeholders:
The primary stakeholders interested in the answer to this problem are Consumers Energy Co., and the general public as represented by the Michigan Department of Environmental Quality (MDEQ), and the US Nuclear Regulatory Commission (USNRC).
The Planning Team:
The planning team consists of members of the BRP Environmental Services Survey Group (ESSG). The primary decision maker will be the Final Status Survey Supervisor.
The Final Status Survey Supervisor will obtain input from the site Construction Group and Scheduling Group for issues relating to schedule and costs.
Schedule:
Approximately five (5) working days are projected to implement the survey and to collect and analyze field data.
Resources:
The primary resources needed to determine the answer to the problem are two (2) technicians to perform fieldwork, one (1) technician to prepare the samples and conduct laboratory analyses, and two (2) survey team members to prepare and review the design, generate maps, coordinate field activities and evaluate data.
: 2. IDENTIFY THE DECISION Several decisions need to be defined to address the stated problem.
PrincipalStudy Question (1):
Does the mean concentration of residual radioactivity in the survey unit exceed the release criteria stated above?
Decision (1):
Determine whether the mean concentration of residual radioactivity in the survey exceeds the release criteria stated in the problem.
Actions (1):
Alternative actions include failure of the survey unit, remediation, or no action required.
Data Quality Objectives FSS 06C 1I Page 1 of 5
 
PrincipalStudy Question (2):
Do any areas of elevated activity in the survey unit exceed the release criteria?
The Decision (2):
Determine if any areas of elevated activity in the survey unit exceed the release criteria.
Actions (2):
Alternative actions include confirmation and investigation, performing the elevated measurement comparison (EMC), remediation, or no action required.
PrincipalStudy Question (3):
Is the potential dose from residual radioactivity in the survey unit ALARA as stated?
The Decision (3):
Determine if the potential dose from residual radioactivity in the survey unit is ALARA.
ALARA requirements for soil remediation are defined in Chapter 4 of the LTP.
Actions (3):
Alternative actions include remediation or no action required.
: 3. IDENTIFY INPUTS TO THE DECISION Information Needed:
Characterization measurements are required to define the radionuclides present and determine the extent and variability of residual radioactivity in the survey area for design and implementation of the survey. Survey area classification, ALARA analysis, potential radionuclides of interest, and site-specific DCGL values are also required inputs to the decision process. The primary information required for evaluation is the analytical results of survey measurements.
Source of the Information:
Source of the Information:
The soil sample data to be used for survey development are the radionuclide-specific measurements of representative soil samples collected for radiological characterization and excavated soil surveys conducted to determine suitability for transport of excavated soil to the SVA. The soil samples obtained were judgmentally selected as a result of multiple surveys conducted during the excavation and transport process. The ALARA analysis for potential soil remediation is provided in LTP, Section 4.4. Site-specific DCGL values and BRP radionuclides of interest are defined in LTP Chapter 5, Table 5-1 and Procedure RM-76, Final Status Survey Design.The survey will be conducted in accordance with applicable regulatory guidance as established in LTP Chapter 5 for Class 1 areas. Soil samples will be utilized for radionuclide-specific measurements in this evaluation.
The soil sample data to be used for survey development are the radionuclide-specific measurements of representative soil samples collected for radiological characterization and excavated soil surveys conducted to determine suitability for transport of excavated soil to the SVA. The soil samples obtained were judgmentally selected as a result of multiple surveys conducted during the excavation and transport process. The ALARA analysis for potential soil remediation is provided in LTP, Section 4.4. Site-specific DCGL values and BRP radionuclides of interest are defined in LTP Chapter 5, Table 5-1 and Procedure RM-76, Final Status Survey Design.
: 4. BOUNDARIES OF THE STUDY Boundaries of the Survey: The target population for this survey is the total thickness of prepared soil in the survey area of 1977 M 2.Data Quality Objectives FSS 06C,1 Page 2 of 5 Temporal Boundaries:
The survey will be conducted in accordance with applicable regulatory guidance as established in LTP Chapter 5 for Class 1 areas. Soil samples will be utilized for radionuclide-specific measurements in this evaluation.
Scanning and sampling in this survey unit will only be performed during daylight hours under dry weather conditions.
: 4. BOUNDARIES OF THE STUDY Boundariesof the Survey:
Surface soils must be free of significant snow cover and standing water prior to surface scanning.
The target population for this survey is the total thickness of prepared soil in the survey area of 1977 M2 .
Soils must be in a non-frozen state or fragmented for collection to satisfy BRP procedural sampling requirements.
Data Quality Objectives FSS 06C,1 Page 2 of 5
The anticipated start date for the survey is September 14, 2006.Constraints:
 
Temporal Boundaries:
Scanning and sampling in this survey unit will only be performed during daylight hours under dry weather conditions. Surface soils must be free of significant snow cover and standing water prior to surface scanning. Soils must be in a non-frozen state or fragmented for collection to satisfy BRP procedural sampling requirements. The anticipated start date for the survey is September 14, 2006.
Constraints:
Cold weather or rainy conditions may effect the operation of electronic equipment.
Cold weather or rainy conditions may effect the operation of electronic equipment.
Adverse weather conditions that include accumulations of rain or snow may limit area access and delay survey efforts.5. DEVELOP A DECISION RULE The following decision rules have been developed to define a logical process for choosing among alternative actions for the principal study questions associated with this survey area.Decision Rule (1): If all reported concentrations for residual radioactivity are less than the site-specific DCGL's and the unity rule has been satisfied for each sample, then the survey unit meets release criteria.
Adverse weather conditions that include accumulations of rain or snow may limit area access and delay survey efforts.
No further action is required.Decision Rule (2): If the mean value of activity in the survey unit is greater than the DCGL, then the survey unit fails to meet the release criteria.1 Remediate, resurvey, and evaluate the results relative to the decision rule.Decision Rule (3): If the mean activity in the survey unit is less than the DCGL and any individual sample measurement exceeds this value, conduct the Sign Test and the elevated measurement comparison (EMC) per LTP, Chapter 5 and Procedure RM-76, Final Status Survey Design. If the EMC and the Sign Test have been satisfied then the survey unit meets the release criteria and no further action is required.
: 5.       DEVELOP A DECISION RULE The following decision rules have been developed to define a logical process for choosing among alternative actions for the principal study questions associated with this survey area.
If the EMC or the Sign Test has not been satisfied then remediate the area(s) of elevated activity, resurvey as appropriate, and evaluate the results relative to the decision rule.Decision Rule (4): If the potential dose from residual radioactivity in the survey unit is ALARA, then no further action is necessary.
Decision Rule (1):
If the potential dose from residual radioactivity in the survey unit is not ALARA, then remediate and resurvey.6. SPECIFY TOLERABLE LIMITS ON DECISION ERRORS The Null Hypothesis:
If all reported concentrations for residual radioactivity are less than the site-specific DCGL's and the unity rule has been satisfied for each sample, then the survey unit meets release criteria. No further action is required.
Decision Rule (2):
If the mean value of activity in the survey unit is greater than the DCGL, then the survey unit fails to meet the release criteria. 1 Remediate, resurvey, and evaluate the results relative to the decision rule.
Decision Rule (3):
If the mean activity in the survey unit is less than the DCGL and any individual sample measurement exceeds this value, conduct the Sign Test and the elevated measurement comparison (EMC) per LTP, Chapter 5 and Procedure RM-76, Final Status Survey Design. If the EMC and the Sign Test have been satisfied then the survey unit meets the release criteria and no further action is required. If the EMC or the Sign Test has not been satisfied then remediate the area(s) of elevated activity, resurvey as appropriate, and evaluate the results relative to the decision rule.
Decision Rule (4):
If the potential dose from residual radioactivity in the survey unit is ALARA, then no further action is necessary. If the potential dose from residual radioactivity in the survey unit is not ALARA, then remediate and resurvey.
: 6.     SPECIFY TOLERABLE LIMITS ON DECISION ERRORS The Null Hypothesis:
It is assumed that residual radioactivity in the survey unit exceeds the release criterion.
It is assumed that residual radioactivity in the survey unit exceeds the release criterion.
When multiple radionuclides are present the mean activity value is determined as the average of the weighted sum. The DCGL of the weighted sum is 1.Data Quality Objectives FSS 06C 1 1 Page 3 of 5 Type I Error (a): The a error is the maximum probability of rejecting the null hypotheses when it is true.Thea error is defined in the LTP at a value of 0.05 (5%) and cannot be changed to a less restrictive value unless prior approval is granted by the USNRC. The a error value of 0.05 will be used for survey planning and data assessment for this survey area.Type II Error (,B): The f8 error is the probability of accepting the null hypothesis when it is false. A value of 0.05 (5%) will be used for survey planning and data assessment for this survey area.The Lower Bound of the Gray Region (LBGR): The LBGR is initially set at one-half the DCGLW for this survey unit. The LBGR may be adjusted during survey design to achieve an optimum relative shift between 1.0 and 3.0.Relative Shift (A/a): The relative shift will be maintained within the range of 1.0 and 3.0 by adjusting the LBGR as appropriate.
When multiple radionuclides are present the mean activity value is determined as the average of the weighted sum. The DCGL of the weighted sum is 1.
: 7. OPTIMIZE DESIGN FOR OBTAINING DATA Statistical Test Sign Test: Radionuclides of potential plant origin also present in soil as background activity resulting from fallout constitute only a small fraction of the DCGL. Therefore, the Sign Test will be used where applicable in the survey evaluation to determine if the survey area meets the requirements for unrestricted release.Number of Samples Determined:
Data Quality Objectives FSS 06C 11 Page 3 of 5
The number of samples required for this survey will be determined based on the relative shift as defined by the requirements of the Sign Test (LTP, Chapter 5.) and Procedure RM-76, Final Status Survey Design. The LBGR is initially set at one-half the DCGL and may be adjusted as necessary for optimizing the survey design to achieve a relative shift between 1.0 and 3.0. Sample point locations are to be determined using a random start, systematic square grid spacing.Judgmental Sampling: Co-60 is the most limiting radionuclide for identification by surface scanning; judgmental surface and subsurface core samples will be collected in any location that exceeds the scan investigation level.Scan Coverage: Scanning for this survey area will provide 100% coverage.Number of Samples for Quality Control: A minimum of 5% of the sample population will be collected for quality evaluation.
 
These samples may include sample splits, sample recounts, or third party sample Data Quality Objectives FSS 06C 1 1 Page 4 of 5 analysis.
Type I Error(a):
Quality analyses will be conducted as defined in LTP, Chapter 5 and Procedure RM-79, Final Status Survey Quality Control.Additional Sample Analysis Requirements:
The a error is the maximum probability of rejecting the null hypotheses when it is true.
The area of soil excavation intersects the identified waterborne pathway for Tritium migration and shall require Tritium in soil analyses for a minimum of 10% of the sample population.
Thea error is defined in the LTP at a value of 0.05 (5%) and cannot be changed to a less restrictive value unless prior approval is granted by the USNRC. The a error value of 0.05 will be used for survey planning and data assessment for this survey area.
Soil samples will be collected in the same random locations as those selected for QA/QC evaluation and sent to an independent laboratory for Tritium analysis.
Type II Error(,B):
Data results will be provided in the survey package.Investigation Levels: Investigation levels defined in LTP, Chapter 5 and BRP Procedure RM-76, Final Status Survey Design, shall be conservatively established for this survey as shown below: Investigation Levels for Survey 06C 1 1 Classification Scan Measurement Soil Sample Analysis Class 1 > DCGL > DCGLw The investigation levels for soil sample measurements are meant to include any individual radionuclide result greater than the site-specific DCGL or where the combined radionuclide values exceed the unity rule. Co-60 is the most limiting radionuclide for identification by surface scanning; further investigation will be initiated at any location that exceeds the Co-60 Scan DCGL of 1818 CPM above background as detailed in the survey design.Data Quality Objectives FSS 06C 1 1 Page 5 of 5 FINAL STATUS SURVEY DESIGN Release Record 06C11 South Central Protected Area Survey Unit Description Survey 06C11 encompasses an area of 1977 m 2 in the south central section of the Protected Area. No materials of plant origin exist in this survey unit.Soil Sample Design Scoping Data Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Input data for survey design were conservatively estimated based on supporting surveys of excavated soils resulting from subsurface structure and component removal within the Protected Area.Table 1 Input Data for Survey Design (pCi/g)Radionuclides I Cs-137 I Co-60 O"
The f8 error is the probability of accepting the null hypothesis when it is false. A value of 0.05 (5%) will be used for survey planning and data assessment for this survey area.
* 0.524 0.255 I DCGL 11.93 3.21*Survey data detailed in Attachment 1 Sample Requirements The number of sample data points for this survey is based on the requirements of the Sign Test.The Unity Rule is used for the presence of multiple radionuclides.
The Lower Bound of the Gray Region (LBGR):
The Standard Deviation of the weighted sum is described by the following:
The LBGR is initially set at one-half the DCGLW for this survey unit. The LBGR may be adjusted during survey design to achieve an optimum relative shift between 1.0 and 3.0.
JG CCS137 2 GCOSO 2 DCGLcsl37 ) +DCGLcoeo)
Relative Shift (A/a):
Cy 0.&#xfd;524 +2(0.2515  
The relative shift will be maintained within the range of 1.0 and 3.0 by adjusting the LBGR as appropriate.
&#xfd;y = 0.091 Relative Shift Relative Shift = DCGLw-LBGR Relative Shift = 1-0.818 0.091 Relative Shift = 2.0 With ca and [3 error levels set at 0.05 and the relative shift of 2.0, the Sign Test requires 15 sample data points (Table 5.5 NUREG 1575).Survey Design FSS 06C, 1 Page 1 of 7 Sample Locations Sample locations are selected in a random start, systematic square grid pattern with the southwest corner of the survey unit as origin (X=0, Y=0). Two numbers between 0 and 1 have been randomly selected and then applied to the survey unit maximum X and Y dimensions to determine the random start location as shown below: Table 2 Random Numbers Random #, X Axis Random #, Y Axis 0.803882 0.025830 Survey Unit Dimensions:
: 7. OPTIMIZE DESIGN FOR OBTAINING DATA Statistical Test Sign Test:
X = 60.0 meters Y = 39.3 meters Random Start Location X = (0.803882)(60.0)  
Radionuclides of potential plant origin also present in soil as background activity resulting from fallout constitute only a small fraction of the DCGL. Therefore, the Sign Test will be used where applicable in the survey evaluation to determine if the survey area meets the requirements for unrestricted release.
= 48.2 meters With SW Corner Origin: Y = (0.025830)(39.3)  
Number of Samples Determined:
= 1.0 meters Sample Spacing As a conservative measure sample spacing will be calculated based on 18 samples for this survey. Samples are located in a systematic square grid pattern with sample spacing determined by the following:
The number of samples required for this survey will be determined based on the relative shift as defined by the requirements of the Sign Test (LTP, Chapter 5.) and Procedure RM-76, Final Status Survey Design. The LBGR is initially set at one-half the DCGL and may be adjusted as necessary for optimizing the survey design to achieve a relative shift between 1.0 and 3.0. Sample point locations are to be determined using a random start, systematic square grid spacing.
L=A n Where: A= area of survey unit, and n = number of samples.1977 L 1- 10.4 meters 18 With sample spacing established at 10.4 meters, 20 data points are available for this survey.Data point locations are identified in Attachment 2.QAIQC Sampling A minimum of 5% of the sample population and 5% of the scan survey area are required to be selected for QA/QC verification in accordance with BRP Procedure RM-79, Final Status Survey Quality Control. As a conservative measure, three (3) soil samples and 10% of the scan survey area will be selected for QA/QC evaluation.
Judgmental Sampling:
Data point locations for soil samples will be determined by random number selection.
Co-60 is the most limiting radionuclide for identification by surface scanning; judgmental surface and subsurface core samples will be collected in any location that exceeds the scan investigation level.
The QA/QC scan starting point and track direction are also determined by random number selection.
Scan Coverage:
The first random data point selected will identify the scanning start point and the second random data point will determine the direction in which the scan will track. QA/QC location results are provided in Table 3 below: Survey Design FSS 06C 1 l Page 2 of 7 Table 3 Random Numbers Generated for QA/QC QA/QC Soil Random Random Samples Sample Verification Scan Sample Number ,Number Split Sample: 12 Start Point: 11 Sample Recount: 14 Scan Toward: 17 Sample Recount: 16 IMinimum Scan Area Requirement:
Scanning for this survey area will provide 100% coverage.
198 m 2 Surface Scanning The coverage requirement for surface scanning in this Class 1 area is 100%. The Scan MDC has been established at fractional values of the DCGLwfor typical background activity levels at Big Rock Point. Scan MDC values for varying backgrounds are provided in Attachment  
Number of Samples for Quality Control:
: 3. The investigation level for identification of potential areas of elevated activity in this survey area will be the Scan DCGL as defined by the following:
A minimum of 5% of the sample population will be collected for quality evaluation.
Scan DCGL = Detector Rating CPM .Exposure Model uR/hr .DCGLw uR/hr pCi/g Scan DCGL for Co-60 = 1818 CPM Scan DCGL for Cs-137 = 3518 CPM Where: 1 Detector Rating = 1200 CPMCs -137 and 565 CPM Co -60 uR/hr uR/hr Exposure Model = 1.229uR/hr Cs-1 3 7 and 5.029uR/hr Co-60 5pCi/g 5 pCi/g DCGLw = 11.93 pCi/g Cs-137 and 3.21 pCi/g Co-60 The DCGLw for Co-60 is the most limiting value for scanning measurements performed to identify areas of potentially elevated activity.
These samples may include sample splits, sample recounts, or third party sample Data Quality Objectives FSS 06C1 1 Page 4 of 5
Scanning conducted for this survey will assume all residual radioactivity to originate from Co-60 and the instrument response at the Co-60 DCGLw (1818 cpm)will be used as the scanning investigation level for FSS 06C, 1.'These values established in EA-BRP-SC-0201, Nal Scanning Sensitivity for Open Land Survey.Survey Design FSS 06C 1 1 Page 3 of 7 Attachment I Design Data -FSS 06C 1 l Protected Area Supporting Surveys Cs-1 37 Co-60 Survey No. Sequence Activity Activity No. (pCi/g) (pcilg)1111060705 :-.:26t, 0.m66',HH0607051&#xfd; 16539., 0i.'062 -.06&#xfd;,HH06075  
 
'16540, ~1.05 j0.6&11 TB062AQ5 '16755 1 16 0.27~TB062405 16756 0,47 '0.15*TB062805 16774 0.1903 Mean: 0.698 Std Dev: 0.524 0.352 0.255* Measurement system MDA -Co-60 not identified in this sample Survey Design FSS 06C 1 I Page 4 of 7 Attachment 2 Soil Sample Locations  
analysis. Quality analyses will be conducted as defined in LTP, Chapter 5 and Procedure RM-79, Final Status Survey Quality Control.
-Survey 06C11 South central Protected Area al 31 U 2 19 (17 2I 0 5 10 2 Meters SurveyUnit06C1 1.Sample Location Survey Design FSS 06C11 Page 5 of 7 Attachment 3 Scan MDC In Varying Backgrounds Background d' i Si MDCRsurvevor Cs-137 Co-60 Cs-137 Co-60 2000 2.48 4 28.64 607.47 0.51 1.08 2.06 1.07 25,00~ 2.48 ~4 b 2.27 >67&#xfd;,~ > 57,, >!,-1,U2O 2__30_ 1.20 3000 2.48 4 35.07 744.00 0.62 1.32 2.52 1.31 3500 2.48 4 37.88 803.61 0.67 1.42 2.72 1.41 4000 2.48 4 40.50 859.10 0.72 1.52 2.91 1.51 4500 2.48 4 42.95 911.21 0.76 1.61 3.09 1.60 5500 2.48 4 47.49 1,007.38 0.84 1.78 3.42 1.77 6000 2.48 4 49.60 1,052.17 0.88 1.86 3.57 1.85 6500 2.48 4 51.63 1,095.14 0.91 1.94 3.71 1.93 7000 2.48 4 53.57 1,136.48 0.95 2.01 3.85 2.00 8000 2.48 4 57.27 1,214.95 1.01 2.15 4.12 2.14 8500 2.48 4 59.04 1,252.34 1.04 2.22 4.25 2.20 9000 2.48 4 60.75 1,288.65 1.07 2.28 4.37 2.27 9500 2.48 4 62.41 1,323.96 1.10 2.34 4.49 2.33-1ii 2A-4 "1 `4403 4.5&5 11" 2.".4:____
Additional Sample Analysis Requirements:
10500 2.48 4 65.61 1,391.90 1.16 2.46 4.72 2.45 11000 2.48 4 67.16 1,424.65 1.19 2.52 4.83 2.51 11500 2.48 4 68.67 1,456.67 1.21 2.58 4.94 2.56 12000 2.48 4 70.14 1,488.00 1.24 2.63 5.04 2.62 2$ ~2.4&#xfd;Z ~> 7.9" 8 j15:8~6~~"1.7  
The area of soil excavation intersects the identified waterborne pathway for Tritium migration and shall require Tritium in soil analyses for a minimum of 10% of the sample population. Soil samples will be collected in the same random locations as those selected for QA/QC evaluation and sent to an independent laboratory for Tritium analysis. Data results will be provided in the survey package.
.9 62 13000 2.48 4 73.01 1,548.76 1.29 2.74 5.25 2.73 13500 2.48 4 74.40 1,578.26 1.32 2.79 5.35 2.78 14000 2.48 4 75.77 1,607.22 1.34 2.84 5.45 2.83 14500 2.48 4 77.11 1,635.67 1.36 2.89 5.55 2.88~ 24 Ai4 Z84~K 5Yi663.63 19 5.4 2 M~de ______ _ _____ ______________________
Investigation Levels:
I i~~~~~1~23'~
Investigation levels defined in LTP, Chapter 5 and BRP Procedure RM-76, Final Status Survey Design, shall be conservatively established for this survey as shown below:
0 _______ ______Survey Design FSS 06C 1 1 Page 6 of 7 Attachment 4 Area Factors for Open Land Survey Evaluation Contaminated
Investigation Levels for Survey 06C1 1 Classification       Scan Measurement                   Soil Sample Analysis Class 1                 > DCGL                             > DCGLw The investigation levels for soil sample measurements are meant to include any individual radionuclide result greater than the site-specific DCGL or where the combined radionuclide values exceed the unity rule. Co-60 is the most limiting radionuclide for identification by surface scanning; further investigation will be initiated at any location that exceeds the Co-60 Scan DCGL of 1818 CPM above background as detailed in the survey design.
_Calculated Area Factors at Time of Peak Dose Area (M2) H-3 Mn-54 Fe-55 Co-60 Sr-90 Cs-137 Eu-152 Eu-154 Eu-155 8094 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 4047 1.00 1.01 1.00 1.01 1.00 1.02 1.02 1.01 1.02 2024 1.00 1.03 1.00 1.03 1.00 1.03 1.03 1.03 1.03 1012 1.35 1.04 1.00 1.04 1.00 1.04 1.05 1.04 1.04 506 2.91 1.09 1.98 1.08 1.98 1.13 1.07 1.07 1.06 253 6.05 1.14 3.95 1.13 3.94 1.20 1.11 1.11 1.09 126 12.4 1.20 7.93 1.20 7.87 1.29 1.17 1.16 1.14 63 24.9 1.30 15.8 1.30 15.6 1.41 1.27 1.26 1.23.32 49.2 1.49 31.2 1.49 30.5 1.62 1.44 1.45 1.39 16 98.9 1.78 62.0 1.78 59.9 1.93 1.72 1.73 1.63 8 198 2.38 123 2.38 117 2.58 2.30 2.31 2.14 4 397 3.61 243 3.62 230 3.91 3.49 3.52 3.19 2 794 5.68 473 5.75 452 6.14 5.48 5.55 4.90 1 1590 9.57 905 9.73 887 10.3 9.24 9.39 7.88 Survey Design FSS 06Cl Page 7 of 7 RM-76 FINAL STATUS SURVEY DESIGN Revision 1 Page 19 of 19 RM-76-5 FINAL STATUS SURVEY APPROVAL AND AUTHORIZATION FOR IMPLEMENTATION Survey Code 06Cl1 Survey Area
Data Quality Objectives FSS 06C11 Page 5 of 5
 
FINAL STATUS SURVEY DESIGN Release Record 06C11 South Central Protected Area Survey Unit Description Survey 06C11 encompasses an area of 1977 m2 in the south central section of the Protected Area. No materials of plant origin exist in this survey unit.
Soil Sample Design Scoping Data Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Input data for survey design were conservatively estimated based on supporting surveys of excavated soils resulting from subsurface structure and component removal within the Protected Area.
Table 1 Input Data for Survey Design (pCi/g)
Radionuclides         I         Cs-137         I           Co-60 O"*
DCGL
          *Survey data detailed in Attachment 1 0.524 11.93 0.255 3.21           I Sample Requirements The number of sample data points for this survey is based on the requirements of the Sign Test.
The Unity Rule is used for the presence of multiple radionuclides. The Standard Deviation of the weighted sum is described by the following:
JG   CCS137 DCGLcsl37 )
2     GCOSO
                      +DCGLcoeo) 2 Cy   0.&#xfd;524   +2(0.2515&#xfd; y= 0.091 Relative Shift Relative Shift = DCGLw-LBGR Relative Shift = 1-0.818 0.091 Relative Shift = 2.0 With ca and [3 error levels set at 0.05 and the relative shift of 2.0, the Sign Test requires 15 sample data points (Table 5.5 NUREG 1575).
Survey Design FSS 06C,1 Page 1 of 7
 
Sample Locations Sample locations are selected in a random start, systematic square grid pattern with the southwest corner of the survey unit as origin (X=0, Y=0). Two numbers between 0 and 1 have been randomly selected and then applied to the survey unit maximum X and Y dimensions to determine the random start location as shown below:
Table 2 Random Numbers Random #, X Axis           Random #, Y Axis 0.803882                     0.025830 Survey Unit Dimensions:       X = 60.0 meters Y = 39.3 meters Random Start Location         X = (0.803882)(60.0) = 48.2 meters With SW Corner Origin:         Y = (0.025830)(39.3) = 1.0 meters Sample Spacing As a conservative measure sample spacing will be calculated based on 18 samples for this survey. Samples are located in a systematic square grid pattern with sample spacing determined by the following:
L=A n
Where: A= area of survey unit, and n = number of samples.
L    1977 1-       10.4 meters 18 With sample spacing established at 10.4 meters, 20 data points are available for this survey.
Data point locations are identified in Attachment 2.
QAIQC Sampling A minimum of 5% of the sample population and 5% of the scan survey area are required to be selected for QA/QC verification in accordance with BRP Procedure RM-79, Final Status Survey Quality Control. As a conservative measure, three (3) soil samples and 10% of the scan survey area will be selected for QA/QC evaluation. Data point locations for soil samples will be determined by random number selection.
The QA/QC scan starting point and track direction are also determined by random number selection. The first random data point selected will identify the scanning start point and the second random data point will determine the direction in which the scan will track. QA/QC location results are provided in Table 3 below:
Survey Design FSS 06C1 l Page 2 of 7
 
Table 3 Random Numbers Generated for QA/QC Random                                                      Random QA/QC Soil Sample       Verification Scan                             Sample Samples Number                                                     ,Number Split Sample:               12     Start Point:                                       11 Sample Recount:             14     Scan Toward:                                       17 Sample Recount:             16     IMinimum Scan Area Requirement:                     198 m 2 Surface Scanning The coverage requirement for surface scanning in this Class 1 area is 100%. The Scan MDC has been established at fractional values of the DCGLwfor typical background activity levels at Big Rock Point. Scan MDC values for varying backgrounds are provided in Attachment 3. The investigation level for identification of potential areas of elevated activity in this survey area will be the Scan DCGL as defined by the following:
Scan   DCGL = Detector Rating CPM . Exposure Model uR/hr . DCGLw uR/hr                           pCi/g Scan DCGL for Co-60 = 1818 CPM Scan DCGL for Cs-137 = 3518 CPM Where:1 Detector Rating = 1200 CPMCs -137 and 565 CPM Co -60 uR/hr                     uR/hr Exposure Model = 1.229uR/hr Cs-           137  and 5.029uR/hr Co-60 5pCi/g                       5 pCi/g DCGLw = 11.93 pCi/g Cs-137 and 3.21 pCi/g Co-60 The DCGLw for Co-60 is the most limiting value for scanning measurements performed to identify areas of potentially elevated activity. Scanning conducted for this survey will assume all residual radioactivity to originate from Co-60 and the instrument response at the Co-60 DCGLw (1818 cpm) will be used as the scanning investigation level for FSS 06C, 1.
        'These values established in EA-BRP-SC-0201, Nal Scanning Sensitivity for Open Land Survey.
Survey Design FSS 06C 11 Page 3 of 7
 
Attachment I Design Data - FSS 06C1 l Protected Area Supporting Surveys Cs-1 37           Co-60 Survey No. Sequence         Activity         Activity No.         (pCi/g)           (pcilg) 1111060705   *16588            :-.:26t,             0.m66'
,HH0607051&#xfd;       16539.,         0i.'062             06
&#xfd;,HH06075       '16540,       ~1.05             j0.6&11 TB062AQ5       '16755             1 16             0.27
~TB062405         16756           0,47             '0.15*
TB062805           16774           0.1903 Mean:       0.698             0.352 Std Dev:       0.524             0.255
* Measurement system MDA - Co-60 not identified in this sample Survey Design FSS 06C1 I Page 4 of 7
 
Attachment 2 Soil Sample Locations - Survey 06C11 South central Protected Area 31 U al        2   19 (17                   2I 1                    0   5 10     2 Meters SurveyUnit06C1
. Sample Location Survey Design FSS 06C11 Page 5 of 7
 
Attachment 3 Scan MDC In Varying Backgrounds Background                 d'           i           Si     MDCRsurvevor   Cs-137     Co-60     Cs-137 Co-60 2000                   2.48         4         28.64       607.47       0.51       1.08     2.06   1.07 25,00~                 2.48     ~4               2.27 b  >67&#xfd;,~           > 57,, >!,-1,U2O     2__30_ 1.20 3000                 2.48           4         35.07       744.00       0.62       1.32     2.52   1.31 3500                 2.48           4         37.88       803.61       0.67       1.42     2.72   1.41 4000                 2.48           4       40.50         859.10       0.72       1.52     2.91   1.51 4500                 2.48           4       42.95         911.21       0.76       1.61     3.09   1.60 5500                 2.48           4       47.49       1,007.38       0.84       1.78     3.42   1.77 6000                 2.48           4       49.60       1,052.17       0.88       1.86     3.57   1.85 6500                 2.48           4       51.63       1,095.14       0.91       1.94     3.71   1.93 7000                 2.48           4       53.57       1,136.48       0.95       2.01     3.85   2.00 8000                 2.48           4       57.27       1,214.95       1.01       2.15     4.12   2.14 8500                 2.48           4       59.04       1,252.34       1.04       2.22     4.25   2.20 9000                 2.48           4       60.75       1,288.65       1.07       2.28     4.37   2.27 9500                 2.48           4       62.41       1,323.96       1.10       2.34     4.49   2.33
    -1ii               2A-4           "1                                   11"          `4403 4.5&5 2.".4:____
10500                 2.48           4       65.61       1,391.90       1.16       2.46     4.72   2.45 11000                 2.48           4       67.16       1,424.65       1.19       2.52     4.83   2.51 11500                 2.48         4         68.67       1,456.67       1.21       2.58     4.94   2.56 12000                 2.48         4         70.14       1,488.00       1.24       2.63     5.04   2.62 2$                 ~2.4&#xfd;Z     ~>             7.9"             8 j15:8~6~~"1.7         .9           62 13000                 2.48         4         73.01       1,548.76       1.29       2.74     5.25   2.73 13500                 2.48         4         74.40       1,578.26       1.32       2.79     5.35   2.78 14000                 2.48         4         75.77       1,607.22       1.34       2.84     5.45   2.83 14500                 2.48         4         77.11       1,635.67       1.36       2.89     5.55   2.88
                    ~ 24           Ai4         Z84~K         5Yi663.63     19                   5.4   2 M~de     ______       _ _____ _______
I
_______________    i~~~~~1~23'~0   _______                               ______
Survey Design FSS 06C 11 Page 6 of 7
 
Attachment 4 Area Factors for Open Land Survey Evaluation Contaminated
_Calculated           Area Factors at Time of Peak Dose Area (M2)   H-3   Mn-54     Fe-55 Co-60       Sr-90 Cs-137 Eu-152 Eu-154   Eu-155 8094     1.00   1.00       1.00   1.00         1.00   1.00   1.00   1.00 1.00 4047       1.00   1.01       1.00   1.01         1.00   1.02   1.02   1.01 1.02 2024     1.00   1.03       1.00   1.03         1.00 1.03     1.03   1.03 1.03 1012     1.35   1.04       1.00   1.04         1.00 1.04     1.05   1.04 1.04 506     2.91     1.09       1.98   1.08         1.98 1.13     1.07   1.07 1.06 253     6.05     1.14     3.95   1.13         3.94 1.20     1.11   1.11 1.09 126     12.4     1.20     7.93   1.20         7.87 1.29     1.17   1.16 1.14 63     24.9     1.30     15.8   1.30         15.6 1.41     1.27   1.26 1.23
  .32     49.2     1.49     31.2   1.49         30.5   1.62     1.44   1.45 1.39 16     98.9     1.78     62.0   1.78         59.9   1.93     1.72   1.73 1.63 8       198     2.38       123   2.38         117   2.58     2.30   2.31 2.14 4       397     3.61       243   3.62         230   3.91     3.49   3.52 3.19 2     794     5.68     473   5.75         452   6.14     5.48   5.55 4.90 1     1590     9.57       905   9.73         887   10.3     9.24   9.39 7.88 Survey Design FSS 06Cl Page 7 of 7
 
RM-76                                                                         Revision 1 FINAL STATUS SURVEY DESIGN                                                 Page 19 of 19 RM-76-5 FINAL STATUS SURVEY APPROVAL AND AUTHORIZATION FOR IMPLEMENTATION Survey Code     06Cl1 Survey Area


== Description:==
== Description:==


Final Status Survey 06C, 1 encompasses 1977 m 2 at or below the grade elevation present during plant power operations in the south central section of the Protected Area. No materials of plant oriain remain in the survey area.The survey area is authorized for Final Status Survey Implementation.
Final Status Survey 06C, 1 encompasses 1977 m 2 at or below the grade elevation present during plant power operations in the south central section of the Protected Area. No materials of plant oriain remain in the survey area.
T esigned by*Technical Review by Date Date RM-76.doc RM-77 FINAL STATUS SURVEY IMPLEMENTATION Revision 2 Page 8 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 1 of 3 (+)1.0 Initial Date PREPARATION FOR SURVEY Survey #1.1 Survey Area Status:_ a. Final Status Survey Design has been approved for implementation (see RM-76-5, Final Status Survey Approval and Authorization for Supplementation).
The survey area is authorized for Final Status Survey Implementation.
: 1. Survey area walkdown complete 2. Survey area determined ready for FSS 3. Decommissioning activities that may impact the environmental status of the survey area have been completed.
T   esigned by                         Date
: 4. Survey area environment is controlled by barriers and postings or other approved method to restrict access.ILIJA eE5SG 0_-,Z b. Survey area has been turned over to the Environmental Services Survey Group (ESSG) in acceptable condition for FSS.,2L4O 4 (1.2 Field Preparation:
*Technical Review by                     Date RM-76.doc
//-7 a. Survey unit boundaries delineated (Step 6.1.1)b. Statistical soil samples predetermined in the survey design are located and marked within the survey unit.(Step 6.1.2)c. Soil sample locations verified (Step 6.1.2.c)d. Instruments and equipment have been collected and calibrated for data measurement and collection (Step 6.1.3)e. Field documentation is prepared (Step 6.1.4)azzz (/LSSG RM-77.doc RM-77 FINAL STATUS SURVEY IMPLEMENTATION Revision 2 Page 9 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 2 of 3 Initial Date 2.0 DATA COLLECTION 2.1 Soil Survey:.Z All soil samples collected and controlled (Step 6.2.1).2.2 Surface Scan: ,/ Surface Scan complete.
 
Action response requirements have been conducted on any identified areas exceeding the investigation level (Step 6.3).2.3 Judgmental Soil Samples: P/A a. Judgmental soil samples have been collected and controlled (Step 6.2.3).b. Deep core profiles performed in areas identified to contain elevated residual activity (Step 6.2.3).3.0 SAMPLE PREPARATION AND LABORATORY ANALYSIS 3.1 Sample Preparation (Step 6.4.1): 01,40 tS&#xfd;SG 2&#xfd; _44/ma 6j11{4 7-7" a.b.C.d.Soil samples are homogenous Soil samples are visibly dry prior to packing Non-soil materials have been removed from sample Soil samples have been transferred to one-liter Marinelli containers and are labeled and sealed."ESSG RM-77.doc RM-59 Revision 11 SAMPLING AND ANALYSIS OF OPEN LAND Page 7 of 13 AREAS FOR SITE CHARACTERIZATION SURVEYS ATTACHMENT RM-59-1 SAMPLING AND ANALYSIS REPORT Date: 09-14-2006 Time: 1600 Location:
RM-77                                                                           Revision 2 FINAL STATUS SURVEY IMPLEMENTATION                                           Page 8 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 1 of 3
06C, 1 Tech: T TSSO/JHW/LED/JNS SURVEY IDENTIFICATION  
(+)                                                                       Initial    Date 1.0   PREPARATION FOR SURVEY Survey #
/ DESCRIPTION Survey 06CI1 encompasses 1977 m 2 at or below the grade elevation present during plant power operations in the south central section of the Protected Area. No materials of plant ori-gin remain in this area.SURVEY TYPE Survey Type: Characterization X Scan (Motive)___ Remediation X Final Scan (Static)Trenching and Digging (use RM-59-4)SURVEY DESIGN Sample Collection:
1.1     Survey Area Status:
_ Judgmental
_       a. Final Status Survey Design has been approved for implementation (see RM-76-5, Final Status Survey Approval and Authorization for Supplementation).
_ Random X Systematic Large Container Assay Scan Coverage:
: 1.     Survey area walkdown complete
100%ANALYSIS Inst.SN/Cal Due 201195/02-10-2007 DAILY CHECK: X SAT UNSAT INIT: sso Inst.SN/Cal Due 186185/09-23-2006 DAILY CHECK: X SAT UNSAT INIT: LED Inst.SN/Cal Due 193709/02-21-2007 DAILY CHECK: X SAT UNSAT INIT: TRS Inst.SN/Cal Due 189086/01-26-2007 DAILY CHECK: X SAT UNSAT INIT: JHW Inst.SN/Cal Due Det. # 6 DAILY CHECK: X SAT UNSAT INIT: Jp Investigation of Unidentified Peaks: X SAT _ UNSAT INIT: JLR Minimum Detectable Activity (Section 5.3.2) X SAT UNSAT INIT: JLR COMMENTS Survey 06C,1 was performed in a random start, square grid, systematic sampling pattern with samples collected at 20 data point locations.
: 2.     Survey area determined ready for FSS
Laboratory analyses did not identify residual radioactivity above trace levels of the DCGL value. Surface scanninq identified no areas of elevated residual radioactivity.
: 3.     Decommissioning activities that may impact the environmental status of the survey area have been completed.
The results of the QA/QC verification scan (10%) were consistent with the findings of the primary survey scan.-I Date: /p -ZZ- OC(m II I RM-59.doc RM-77 FINAL STATUS SURVEY IMPLEMENTATION Revision 2 Page 10 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 3 of 3 Initial Date 3.2 Laboratory Analysis: L/ Isotopic analyses are complete.
: 4.     Survey area environment is controlled by barriers     ILIJA            0 and postings or other approved method to restrict   eE5SG access.
The spectroscopy report requires a signature of completion by the laboratory analyst and a signature of evaluation documenting that a second level review has been performed (Step 6.4.2).3.3 Sample Control and Documentation:
_-,Z     b. Survey area has been turned over to the Environmental Services Survey Group (ESSG) in acceptable condition for FSS.                                                               ,2L4O 4 (
/ Chain of custody documentation exhibits control of soil samples (Step 6.4.3).&#xfd;, t&#xfd;S-G-192 AI/W (/ESSG 0-&#xfd;Zoea ( -I &#xfd;,&#xfd;/ / 9 i 2 (1 &#xfd;-Zj Date RM-77.doc Soil Sample Activity Summary Release Record 06011 South Central Protected Area 304 305 30/309 316 328 340 352 310 290 291&#xfd;34 292 293 3,M8 294 60.0 m 370 295 X=I 364 365 366 369= Survey Unit 06C1_1 0 Sample Location 0 5 10 I .I .I 20 Meters Surface Scan Summary Release Record 06C 1 1 South Central Protected Area= Survey Unit 06C1_1 0 5 10 20 Motors* Sample Location! l ; , I = i r I RED Values are Average Mobile Scan General Area Activity (kcpm)BLUE Values are Average Verification Scan General Area Activity (kcpm)GREY Values are Average General Background Area Activity (kcpm)V, Primary Scan: Technician Signature:
1.2   Field Preparation:
QC Verification Scan: /0 %Technician Signature:  
  /     a.     Survey unit boundaries delineated (Step 6.1.1)
' JA Date: '1- A. 0 Time: '400 Date:  Time: 1l400 RM-72 SAMPLE CHAIN-OF-CUSTODY Revision 0 Page 4of 5 06C 1 1 RM-72-1 CHAIN-OF-CUSTODY RECORD Sample Number Sampling Location Date Time Final Disposition of Sample 1 Grid #353 (6.6) (1.0) "- u 2 Grid # 354 (7.0) (1.0) -.-O 17-4-D 3 Grid#355 (7.4) (1.0) 0('-i.( 13, 4 Grid#356 (7.8) (1.0)  
: b. Statistical soil samples predetermined in the survey
\2ifi 5 Grid #357 (8.2) (1.0) -.o0 IS'6 Grid # 358 (8.6) (1.0) 7 Grid#346 (8.6) (1.4) .I.5" 8 Grid #345 (8.2) (1.4) 9.- ,IUS0 12 1L 9 Grid #344 (7.8) (1.4) 9.1Llr 10 Grid # 343 (7.4) (1.4) -i" (z-0 9 I 3m 11 Grid # 342 (7.0) (1.4) 5L. +/--D &#xfd;,-12 Grid #341 (6.6) (1.4) jlH.(O .ZLA1e 12 QASplit Grid#341 (6.6) (1.4) Iq.t-o( \I-LI (p 13 Grid # 331 (7.4) (1.8) q,, V- M.Q 14 (R) Grid # 332 (7.8) (1.8) ".ILb 0 4 , I.,%,L 15 Grid #333 (8.2) (1.8) .9. jLLf.(I \7CQS 16 (R) Grid #334 (8.6) (1.8) I SOt /17 Grid # 322 (8.6) (2.2) 9. 1&I.oeC ID,(4 18 Grid#321 (8.2) (2.2) \ )19 Grid#320 (7.8) (2.2) -- 20 Grid#319 (7.4) (2.2) _0.O(_ _ _ __'_(Samples may be analyzed and stored, shipped for offsite evaluation or analyzed and disposed of.)',1 &#xa2;-WeI, I. l, 2. elnqishd y:Date .Time Received in good condition by: 2. Relinquished by: e Date Time Received in good condition by: 3. Relinquished by: Date Time Received in good condition by: 4. Relinquished by: Date Time Received in good condition by: RM-72.doc RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 19 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 1 of 8 FINAL STATUS SURVEY: O& (,//1.0 DATA VERIFICATION 1.1 Data Acceptance
  /-7          design are located and marked within the survey unit.
..~i,, Review the Implementation Checklist (RM-77-1) to verify that survey isolation and control measures were executed prior to FSS and are being maintained.
(Step 6.1.2)
: c.     Soil sample locations verified (Step 6.1.2.c)
: d.     Instruments and equipment have been collected and calibrated for data measurement and collection e.
(Step 6.1.3)
Field documentation is prepared (Step 6.1.4) azzz
(/LSSG RM-77.doc
 
RM-77                                                                       Revision 2 Page FINAL STATUS SURVEY IMPLEMENTATION                                             9 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 2 of 3 Initial     Date 2.0     DATA COLLECTION 2.1     Soil Survey:
  .Z       All soil samples collected and controlled (Step 6.2.1).                 01,40 2.2     Surface Scan:
    ,/   Surface Scan complete. Action response requirements have been conducted on any identified areas exceeding the investigation level (Step 6.3).                                         2&#xfd;_44/ma tS&#xfd;SG 2.3   Judgmental Soil Samples:
P/A     a.       Judgmental soil samples have been collected and controlled (Step 6.2.3).
: b.       Deep core profiles performed in areas identified to contain elevated residual activity (Step 6.2.3).               6j11{4 3.0     SAMPLE PREPARATION AND LABORATORY ANALYSIS 3.1   Sample Preparation (Step 6.4.1):
7    a.      Soil samples are homogenous
-7"     b.       Soil samples are visibly dry prior to packing C.      Non-soil materials have been removed from sample
: d.      Soil samples have been transferred to one-liter Marinelli containers and are labeled and sealed.
                                                                      "ESSG RM-77.doc
 
RM-59                                                                                                     Revision 11 SAMPLING AND ANALYSIS OF OPEN LAND                                                                       Page 7 of 13 AREAS FOR SITE CHARACTERIZATION SURVEYS ATTACHMENT RM-59-1 SAMPLING AND ANALYSIS REPORT Date: 09-14-2006 T  Time: 1600                 Location: 06C, 1                   Tech:
TSSO/JHW/LED/JNS SURVEY IDENTIFICATION / DESCRIPTION Survey 06CI1 encompasses 1977 m 2 at or below the grade elevation present during plant power operations in the south central section of the Protected Area. No materials of plant ori-gin remain in this area.
SURVEY TYPE Survey Type:                       Characterization     X         Scan (Motive)
___         Remediation X     Final                           Scan (Static)
Trenching and Digging (use RM-59-4)
SURVEY DESIGN Sample Collection:       _     Judgmental     _     Random     X     Systematic           Large Container Assay Scan Coverage:           100%
ANALYSIS Inst.SN/Cal Due 201195/02-10-2007             DAILY CHECK:         X     SAT               UNSAT       INIT: sso Inst.SN/Cal Due 186185/09-23-2006             DAILY CHECK:           X     SAT               UNSAT       INIT: LED Inst.SN/Cal Due 193709/02-21-2007             DAILY CHECK:         X     SAT               UNSAT       INIT: TRS Inst.SN/Cal Due 189086/01-26-2007             DAILY CHECK:           X     SAT               UNSAT       INIT: JHW Inst.SN/Cal Due Det. # 6                     DAILY CHECK:           X     SAT               UNSAT       INIT: Jp Investigation of Unidentified Peaks:                                 X     SAT     _         UNSAT       INIT: JLR Minimum Detectable Activity (Section 5.3.2)                         X     SAT               UNSAT       INIT: JLR COMMENTS Survey 06C,1 was performed in a random start, square grid, systematic sampling pattern with samples collected at 20 data point locations. Laboratory analyses did not identify residual radioactivity above trace levels of the DCGL value. Surface scanninq identified no areas of elevated residual radioactivity. The results of the QA/QC verification scan (10%) were consistent with the findings of the primary survey scan.
                                                                              -I m
Date:     /p -ZZ-II OC( I RM-59.doc
 
RM-77                                                                         Revision 2 FINAL STATUS SURVEY IMPLEMENTATION                                       Page 10 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 3 of 3 Initial     Date 3.2   Laboratory Analysis:
L/   Isotopic analyses are complete. The spectroscopy report requires a signature of completion by the laboratory analyst and a signature of evaluation documenting that a second level review has been performed (Step 6.4.2).               &#xfd;, t&#xfd;S-G-192 AI/W 3.3    Sample Control and Documentation:
  /     Chain of custody documentation exhibits control of soil samples (Step 6.4.3).
(/ESSG 0-&#xfd;Zoea
( -I &#xfd;,&#xfd;/ /i2(1 9  &#xfd;-Zj                   Date RM-77.doc
 
Soil Sample Activity Summary Release Record 06011 South Central Protected Area 304     305                       30/                   309         310         290 316                                                                              291 328                                                                        &#xfd;34   292 340                                                                              293 352                                                                          3,M8 294 X=I 60.0 m 364       365           366                               369         370        295
=   Survey Unit 06C1_1                           0I .
5I  .
10 I
20 Meters 0 Sample Location
 
Surface Scan Summary Release Record 06C 11 South Central Protected Area
= Survey Unit 06C1_1                         0     5       10           20 Motors
                                              ! l ;   ,   I   = i r I
* Sample Location RED Values are Average Mobile Scan General Area Activity (kcpm)
BLUE Values are Average Verification Scan General Area Activity (kcpm)
GREY Values are Average General Background Area Activity (kcpm)
V, Primary Scan:
Technician Signature:                         Date: '1-A. 0 Time:    '400 QC Verification Scan:         /0   %
Technician Signature:   '         JA         Date: 9*.14-o(o Time: 1l400
 
RM-72                                                                                                           Revision 0 SAMPLE CHAIN-OF-CUSTODY                                                                                         Page 4of 5 06C1 1 RM-72-1 CHAIN-OF-CUSTODY RECORD Sample Number                 Sampling Location                     Date           Time       Final Disposition of Sample 1                   Grid #353     (6.6) (1.0)                         u HT'o*        "-
2                   Grid # 354     (7.0) (1.0)                 - - .O           17-4-D 3                   Grid#355       (7.4) (1.0)               0('-i.(               13, 4                   Grid#356       (7.8) (1.0)               5I.I*-(do          \2ifi 5                   Grid #357     (8.2) (1.0)               *,l      -.o0       IS' 6                   Grid # 358     (8.6) (1.0)                   .Iq'ot*
7                   Grid#346     (8.6) (1.4)                   .             I.5" 8                   Grid #345     (8.2) (1.4)               9.-       ,IUS0     12   1L 9                   Grid #344     (7.8) (1.4)                 9.1Llr
* 10                 Grid # 343     (7.4) (1.4)                           -i"(z-0I9      3m 11                 Grid # 342     (7.0) (1.4)               5L. +/--D &#xfd;,-
12                 Grid #341     (6.6) (1.4)                 jlH.(O           .ZLA1e 12     QASplit     Grid#341       (6.6) (1.4)                     Iq.t-o(       \I-LI(p 13                 Grid # 331     (7.4) (1.8)               q,,               V- M.Q 14         (R)     Grid # 332     (7.8) (1.8)               ".ILb 0 4 ,       I.,%,L 15                 Grid #333     (8.2) (1.8)               .9. jLLf.(I   \7CQS 16         (R)     Grid #334     (8.6) (1.8)               q.IL*o.o(          I SOt                       /
17                 Grid # 322     (8.6) (2.2)               9. 1&I.oeC       ID,(4 18                 Grid#321       (8.2) (2.2)                   ,I-O(*        \                           )
19                   Grid#320       (7.8) (2.2)                   --
* 20                   Grid#319       (7.4) (2.2)                                         _0.O(_ _   _   __'_
(Samples may be analyzed and stored, shipped for offsite evaluation or analyzed and disposed of.)
                ',1   &#xa2;-WeI,   I. l,
: 2. elnqishd y:Date                         .           Time                     Received in good condition by:
: 2. Relinquished by:           e             Date               Time                     Received in good condition by:
: 3. Relinquished by:                         Date               Time                     Received in good condition by:
: 4. Relinquished by:                         Date               Time                     Received in good condition by:
RM-72.doc
 
RM-78                                                                           Revision 2 FINAL STATUS SURVEY ASSESSMENT                                               Page 19 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 1 of 8 FINAL STATUS SURVEY:              O& (,//
1.0        DATA VERIFICATION 1.1        Data Acceptance
    .. ~i,,  Review and      the Implementation Checklist (RM-77-1) to verify that survey isolation control measures were executed prior to FSS and are being maintained.
Review RM-77, Final Status Survey Implementation, to verify that methods, techniques, and survey activities required for FSS have been applied in accordance with the appropriate procedures.
Review RM-77, Final Status Survey Implementation, to verify that methods, techniques, and survey activities required for FSS have been applied in accordance with the appropriate procedures.
1.2        Field QC Records:
Review all assessments, Condition Reports and audits to ensure that identified issues have been resolved.
Comments:
    ,/1      Verify scan instrumentation was in calibration and the QC source checks were performed prior to and after surveys.
7        Verify daily QC source checks for Canberra gamma spectroscopy detector properly logged prior to soil sample analysis.
1.3        Review Verification:
v/"      Verify that the Data Quality Objectives are complete.
      "    Verify that the survey design has been technically reviewed.
RM-78.doc
RM-78                                                                        Revision 2 FINAL STATUS SURVEY ASSESSMENT                                          Page 20 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 2 of 8 V      Verify that gamma spectroscopy results have received a technical review.
Verify the Sample and Analysis Report (RM-59-1) is completed and reviewed.
Data Verification Completed:    YosN o Comments Assessor                Date RM-78.doc
RM-78                                                                          Revision 2 FINAL STATUS SURVEY ASSESSMENT                                              Page 21 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 3 of 8 2.0      DATA VALIDATION 2.1      Documentation Review:
Perform documentation review for quality control purposes and validate the data collected is complete and appropriate for use as defined by the survey design. Documentation includes:
IField measurement records SChain-of-custody Quality Control (QC) measurement records Current qualification of survey personnel Corrective Action Reports
          .*        Data inputs (laboratory spectroscopy)
Sample preparation techniques 2.2:      Detection Limit Review:
X      Scan MDCs are below established site DCGLs.
7/    Forced-count values are assigned as necessary when activity is not detected in a sample.
7Minimum Detectable Concentration (MDC) values of gamma spectroscopy are below established DCGLs.
2.3      Quality Control (QC) Data Review:
Quality Control (QC) data results have received required reviews and are complete and consistent.
4*        Results of judgmental samples have been reviewed and evaluated.
_*        Review to ensure that the analytical results of judgmental samples do not impact the evaluation for unrestricted release of the survey area.
RM-78.doc
RM-78                                                                            Revision 2 FINAL STATUS SURVEY ASSESSMENT                                              Page 22 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 4 of 8 2.4      Qualification of Data:
Statistical radionuclide-specific measurements for completeness. Evaluate the survey for determination of data usability and confirm that sufficient qualified data are present for the decision process.
: a.      Total number of statistical samples planned for the survey:  j*"j
: b.      Total number of statistical samples determined as valid:    c,2 D b x120_
: c.      Calculate % Completeness:
a
_      Qualified data are J00% completeness and are sufficient to support the Sign Test requirement for determination of unrestricted release.
Data Validation Completed:        2        No Comments:
Assessor                      Date RM-78.doc
RM-78                                                                            Revision 2 FINAL STATUS SURVEY ASSESSMENT                                                Page 23 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 5 of 8 3.0      DATA QUALITY ASSESSMENT 3.1      Review the DQOs and Survey Design:
__    Confirm that all inputs to the decision have been reviewed and are complete.
__j    Verify that boundaries or constraints identified in the survey area have not affected the quality of the data.
j      Review the Statement of Hypothesis and confirm that it remains relevant.
___  Confirm that Type I and Type II error limits are consistent with DQOs.
ZConfirm that the survey design is consistent with DQOs and that the appropriate number of data points were obtained.
3.2      Preliminary Review:
3.2.1    Preliminary Evaluation:
* Quality Assessment (QA) reports consistent with procedure RM-79, Final Status Survey Quality Control.
SSurvey is of sufficient intensity to satisfy classification requirement.
7    Potential trends of radioactivity levels in the survey area do not impact a decision for unrestricted release.
Comments:
RM-78.doc
RM-78                                                                            Revision 2 FINAL STATUS SURVEY ASSESSMENT                                                Page 24 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 6 of 8 3.2.2    Calculate Basic Statistical Quantities:
: a.      Number of qualified data points            0-9
: b.      Calculation of the Mean                            P,,1a-.00.1
: c.      Calculation of the Median                  .
: d.      Calculation Standard Deviation                    Co iP. o'7"2 COW il&      Attach graphic representation of the data if any radionuclide-specific measurements exceed 50% of the DCGL.
          .JL      Sample QA/QC measurements consistent with FSS data 3.3      Statistical Evaluation:
NOTE:      If all measurement data are less than the DCGLw, statistical testing in not required and the survey unit meets the regulatory requirement for unrestricted release.
____All survey measurements are below the DCGLw.
3.3.1    Verify Assumptions of the Survey Design
____  Review the posting plot to verify that the data exhibits spatial independence. Spatial trends must be investigated and resolved prior to further assessment.
Review to verify dispersion symmetry. The appearance of skewed data must be investigated for cause and documented prior to further assessment.
RM-78.doc
I RM-78                                                                        Revision 2 FINAL STATUS SURVEY ASSESSMENT                                            Page 25 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 7 of 8
___    Review the dataset standard deviation and range for data variance.
Questionable data. must be investigated for cause and documented prior to further assessment.
Verify that the data exhibits adequate power and confirm that the sample size is sufficient to satisfy the DQOs.
3.4      Draw Conclusions from the Data:
3.4.1    Investigation Levels and Response Actions
_*. Determine if data results have exceeded any investigation level.
Document findings. >        .    '&-'-J-y/
3.4.2    Evaluation for Unrestricted Release Select applicable conclusion:
j    Survey area acceptance criteria met and survey area satisfies the requirements for unrestricted release:
_      All concentrations are less than the DCGLW. The Null Hypothesis is rejected.
_Ap      The mean concentration of the survey area is below the DCGLw but individual measurements in the survey unit exceed the DCGLw. The Sign Test and EMC evaluation are successful and the Null Hypothesis is rejected.
RM-78.doc
RM-78                                                                        Revision 2 FINAL STATUS SURVEY ASSESSMENT                                          Page 26 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 8 of 8
            .4    Survey area acceptance criteria not met and survey area fails to satisfy the requirements for unrestricted release:
                  ,d      The mean concentration in the survey area exceeds the DCGLw. and the null hypothesis is confirmed.
A2&#xfd;, The mean concentration of the survey area is below the DCGLw but individual measurements in the Unit exceed the DCGLw..
The Sign Test and EMC evaluation are unsuccessful and the null hypothesis is confirmed.
Data Quality Assessment Completed:                No Comments 7    Assessor                    Date Reviews:
Ot Da(Z-3 Technical R    iew                  Date ES Superintendent                  'Date RPr&-ES Manager Date RM-78.doc
RM-78-3, Attachment 1 Statistical Quantities Release Record 06C11 South Central Protected Area Sample              Cs-1 37            Co-60      Weighted          **Weighted Sum Number            (pCi/gm)          (pCi/gm)      Sum (SOR)            <DCGLw?          DCGL-W. Sum Sign 1              0.0547              0.0319        0.0145                  yes            0.9855    +1 2              0.0490            -0.0036        0.0030                  yes            0.9970    +1 3              0.0472            -0.0083        0.0014                  yes            0.9986    +1 4              0.0853              0.0471        0.0218                  yes            0.9782    +1 5              0.0331              0.0291      0.0118                    yes            0.9882    +1 6              0.0902            -0.0150      0.0029                    yes            0.9971    +1 7              0.0581              0.0132      0.0090                    yes            0.9910    +1 8              0.0044              0.0023      0.0011                    yes            0.9989    +1 9              0.0667              0.0566      0.0232                    yes            0.9768    +1 10              0.0918              0.0369      0.0192                    yes            0.9808    +1 11              0.0468              0.0323      0.0140                    yes            0.9860    +1 12              0.0324            -0.0009      0.0024                    yes            0.9976    +1 13              0.0624            0.0013        0.0056                    yes            0.9944    +1 14              0.0417            0.0030        0.0044                    yes            0.9956    +1 15              0.0364            0.0474        0.0178                    yes            0.9822    +1 16              0.0213            0.0110        0.0052                    yes            0.9948    +1 17              0.0613            0.0049        0.0067                    yes            0.9933    +1 18              0.0422            0.0084        0.0062                    yes            0.9938    +1 19              0.0287            0.0119        0.0061                    yes            0.9939    +1 20              0.0524            0.0422        0.0175                    yes            0.9825    +1 Std. Dev            0.0224            0.0210        0.0072 Mean              0.0503            0.0176        0.0097 Median              0.0481            0.0115        0.0064 Number of Positive Differences (S+):      n/a Critical Value, k, Table 1.3 of Marssim:      n/a S+ >thank?:        n/a Survey Unit Pass or Fail:  **Pass
*Note: Forced-Countvalues are used for samples with activity levels below the MDA.
**Note: If all measurement data are less than the DCGL ., then the Sign Test is not required.


===1.2 Field===
I t RM-79                                                                          Revision 1 FINAL STATUS SURVEY QUALITY CONTROL                                        Page 11 of 13 RM-79-1 FSS QUALITY CONTROL EVALUATION RESULTS FSS Package #          0(a C' I                    QC Package #    o (c2Co /
QC Records: Review all assessments, Condition Reports and audits to ensure that identified issues have been resolved.Comments: ,/1 Verify scan instrumentation was in calibration and the QC source checks were performed prior to and after surveys.7 Verify daily QC source checks for Canberra gamma spectroscopy detector properly logged prior to soil sample analysis.1.3 Review Verification:
QC Measurement Type              Acceptance Criteria Met*?          Reference
v/" Verify that the Data Quality Objectives are complete." Verify that the survey design has been technically reviewed.RM-78.doc RM-78 FINAL STATUS SURVEY ASSESSMENT Revision 2 Page 20 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 2 of 8 Verify that gamma spectroscopy results have received a technical review.Verify the Sample and Analysis Report (RM-59-1) is completed and reviewed.V Data Verification Completed:
: 1. Replicate Scan                (2      No                Step 5.1.3.
Comments YosN o Assessor Date RM-78.doc RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 21 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 3 of 8 2.0 DATA VALIDATION
: 2. Sample Recounts                                          Step 5.1.4.1
_  _        a. In-house                            No 2/yL          b. Third party                  Yes / No
: 3. Split Samples                                              Step 5.1.4.2
: c. In-house                            No
: d. Third party                  Yes I No
    *NOTE:    If Acceptance Criteria is not met, completion of Attachment RM-79-2, FSS Quality Control Investigation Results, is required.
Comments:~
                                                      -w&#xfd;    4    AA              F  t        -
Reviews:
TEvaluator                          Date Technical Review                  Die RM-79.doc


===2.1 Documentation===
QA Verification Split Sample Analysis Table I Date:                  9/14/2006                                                            Acceptance Criteria Resolution        Ratio QA:                    06C,1 South Central Protected Area                                    <4            N/A 4-7          0.5-2.0 Type:                  Split Sample                                                        8-15        0.6-1.66 16-50      0.75-1.33 Lab:                  In-House                                                            51-200        0.8-1.25
                                                                                              >200        0.85-1.18 A            B              C              D        E            F          (3 BRP              BRP          BRP                                                                      Results in Sample              Radionuclide          Result          Results    % Error          BRP            Ratio  Results ResltsRatioSplit Results Rati                      Comparison Agreement Below                                      Resolution                              (pCi/g)              Compare MDA              (pCi/g)    (Sigma)                    (Table 1) Below MDA                    F/A      G with D) 12                  Co-60                <            0.0624        n/a          n/a            n/a      <          0.0638      1.02      YES 12                  Cs-137              <            0.0612        n/a          n/a            n/a      <          0.0622      1.02      YES A"
Resolution      C =     -
(A)(        IB I
< Indicates results less than the MDA.
*Note    Results are considered in agreement for MDA and near-MDA measurementcomparisons Results fthat fail agreement must be investigated per RM-79.


Review: Perform documentation review for quality control purposes and validate the data collected is complete and appropriate for use as defined by the survey design. Documentation includes: IField measurement records SChain-of-custody Quality Control (QC) measurement records Current qualification of survey personnel Corrective Action ReportsData inputs (laboratory spectroscopy)
QA Verification Sample Recount Analysis Table 1 Date:                 9/14/2006                                                              Acceptance Criteria Resolution      Ratio QA:                   06C,1 South Central Protected Area                                        <4            N/A 4-7        0.5-2.0 Type:                 Sample Recounts                                                        8-15        0.6-1.66 16-50      0.75-1.33 Lab:                 In- House                                                              51-200        0.8-1.25
Sample preparation techniques 2.2: Detection Limit Review: X Scan MDCs are below established site DCGLs.7/ Forced-count values are assigned as necessary when activity is not detected in a sample.7Minimum Detectable Concentration (MDC) values of gamma spectroscopy are below established DCGLs.2.3 Quality Control (QC) Data Review: Quality Control (QC) data results have received required reviews and are complete and consistent.Results of judgmental samples have been reviewed and evaluated.Review to ensure that the analytical results of judgmental samples do not impact the evaluation for unrestricted release of the survey area.RM-78.doc RM-78 FINAL STATUS SURVEY ASSESSMENT Revision 2 Page 22 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 4 of 8 2.4 Qualification of Data: Statistical radionuclide-specific measurements for completeness.
                                                                                                >200        0.85-1.18 A                B              C            DE                  F        G BRP              BRP          BRP      Acceptance    Recount  Recount  Comparison Agreement Sample              Radionuclide          Result Below          Results        % Error            RReonAgemt Ratio Resolution                  Result  Results    Ratio    Compare S        (pCi/g)        (Sigma)                     ( Table 1)   el      (pCi/g)    F/A      Compare MDA              pg,            Iga(Tbe                              Below MDA                      G with D) 14                  Co-60                <          0.0639            n/a          n/a            n/a        <    0.0749    1.17      YES 14                  Cs-137                            0.0417          38.44          2.60          n/a              0.0671    1.61      YES 16                  Co-60                <          0.0612            n/a          n/a            n/a        <    0.0479    0.78       YES 16                  Cs-137                <          0.0598            n/a          n/a            n/a              0.0506    0.85      YES Resolution        C=  (Al      OO
Evaluate the survey for determination of data usability and confirm that sufficient qualified data are present for the decision process.a. Total number of statistical samples planned for the survey: b. Total number of statistical samples determined as valid: c, 2 D c. Calculate
< Indicates results less than the MDA.
% Completeness:
  *Note      Results are considered in agreement for MDA and near-MDA measurement comparisons Results flhat fail agreement must be investigatedper RM-79.
b x120_a_ Qualified data are J 00% completeness and are sufficient to support the Sign Test requirement for determination of unrestricted release.Data Validation Completed:
2 No Comments: Assessor Date RM-78.doc RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 23 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 5 of 8 3.0 DATA QUALITY ASSESSMENT


===3.1 Review===
.4 if Tritium in Soil Data Results Final Status Survey 06C 1 1 Sample              Tritium in Soil Number                    pCi/g 12                      0.007 14                      0.015 16                      0.024 Mean:        0.0153 Median:        0.0150 St. Dev:       0.0085 Note: The DCGL for Tritium is 327 pCi/g.
the DQOs and Survey Design:__ Confirm that all inputs to the decision have been reviewed and are complete.__j Verify that boundaries or constraints identified in the survey area have not affected the quality of the data.j Review the Statement of Hypothesis and confirm that it remains relevant.___ Confirm that Type I and Type II error limits are consistent with DQOs.ZConfirm that the survey design is consistent with DQOs and that the appropriate number of data points were obtained.3.2 Preliminary Review: 3.2.1 Preliminary Evaluation:Quality Assessment (QA) reports consistent with procedure RM-79, Final Status Survey Quality Control.SSurvey is of sufficient intensity to satisfy classification requirement.
Sample results are less than 0.02% of the DCGL
7 Potential trends of radioactivity levels in the survey area do not impact a decision for unrestricted release.Comments: RM-78.doc RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 24 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 6 of 8 3.2.2 Calculate Basic Statistical Quantities:
 
: a. Number of qualified data points 0-9 b. Calculation of the Mean a-.00.1 P,,1 c. Calculation of the Median .d. Calculation Standard Deviation iP. o'7"2 Co COW il& Attach graphic representation of the data if any radionuclide-specific measurements exceed 50% of the DCGL..JL Sample QA/QC measurements consistent with FSS data 3.3 Statistical Evaluation:
  -
NOTE: If all measurement data are less than the DCGLw, statistical testing in not required and the survey unit meets the regulatory requirement for unrestricted release.____All survey measurements are below the DCGLw.3.3.1 Verify Assumptions of the Survey Design____ Review the posting plot to verify that the data exhibits spatial independence.
* Environmental, Inc.
Spatial trends must be investigated and resolved prior to further assessment.
Midwest Laboratory an Allegheny Technologies Co.
Review to verify dispersion symmetry.
700 Landwehr Road - Northbrook, IL 60062-2310 ph. (847) 564-0700
The appearance of skewed data must be investigated for cause and documented prior to further assessment.
* fax (847) 564-4517 Mr. David W. Parish                                                LABORATORY REPORT NO.              8022-100-230 Big Rock Point                                                        DATE:                               09-22-2006 10269 US-31 North                                                    SAMPLES RECEIVED:                   09-19-2006 Charlevoix, MI 49720                                                  PURCHASE ORDER NO:
RM-78.doc I RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 25 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 7 of 8___ Review the dataset standard deviation and range for data variance.Questionable data. must be investigated for cause and documented prior to further assessment.
Below are the results of the analyses for tritium on three soil samples.
Verify that the data exhibits adequate power and confirm that the sample size is sufficient to satisfy the DQOs.3.4 Draw Conclusions from the Data: 3.4.1 Investigation Levels and Response Actions_. Determine if data results have exceeded any investigation level.Document findings.  
Excavated Soil Survey 06C1 l Sample                            Collection              Lab            Concentration          MDA Description                              Date              Code            (pCi/g of soil)        (pCi/g of soil)
> .'&-'-J-y/3.4.2 Evaluation for Unrestricted Release Select applicable conclusion:
H-3 12                                    09-14-06            BRSO-6372        0.007 +/- 0.006              <0.011 14                                    09-14-06            BRSO-6373        0.015 +/- 0.008              < 0.014 16                                    09-14-06            BRSO-6374        0.024 +/- 0.007              < 0.013 The error given is the probable counting error at 95 % confidence level. The less than, (<), value is based on 4.66 sigma counting error for background sample.
j Survey area acceptance criteria met and survey area satisfies the requirements for unrestricted release:_ All concentrations are less than the DCGLW. The Null Hypothesis is rejected._Ap The mean concentration of the survey area is below the DCGLw but individual measurements in the survey unit exceed the DCGLw. The Sign Test and EMC evaluation are successful and the Null Hypothesis is rejected.RM-78.doc RM-78 FINAL STATUS SURVEY ASSESSMENT Revision 2 Page 26 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 8 of 8.4 Survey area acceptance criteria not met and survey area fails to satisfy the requirements for unrestricted release: ,d The mean concentration in the survey area exceeds the DCGLw. and the null hypothesis is confirmed.
APPROVED BY-               J-0&#xfd;4//&            A Tony Coorlim, Quality Assurance
A2&#xfd;, The mean concentration of the survey area is below the DCGLw but individual measurements in the Unit exceed the DCGLw..The Sign Test and EMC evaluation are unsuccessful and the null hypothesis is confirmed.
* t~
Data Quality Assessment Completed:
ATTACHMENT 5 CONSUMERS ENERGY BIG ROCKPOINT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION CLASS I RELOCATED SOIL RELEASE RECORD, TBCx1 51, RELOCATED SOILS FROM TURBINE BUILDING/CONTAINMENT DEMOLITION October 24, 2006 38 Pages
No Comments 7 Assessor Reviews: Technical R iew ES Superintendent RPr&-ES Manager Date Da(Z-3 Ot Date'Date Date RM-78.doc RM-78-3, Attachment 1 Statistical Quantities Release Record 06C 1 1 South Central Protected Area Sample Cs-1 37 Co-60 Weighted **Weighted Sum Number (pCi/gm) (pCi/gm) Sum (SOR) <DCGLw? DCGL-W. Sum Sign 1 0.0547 0.0319 0.0145 yes 0.9855 +1 2 0.0490 -0.0036 0.0030 yes 0.9970 +1 3 0.0472 -0.0083 0.0014 yes 0.9986 +1 4 0.0853 0.0471 0.0218 yes 0.9782 +1 5 0.0331 0.0291 0.0118 yes 0.9882 +1 6 0.0902 -0.0150 0.0029 yes 0.9971 +1 7 0.0581 0.0132 0.0090 yes 0.9910 +1 8 0.0044 0.0023 0.0011 yes 0.9989 +1 9 0.0667 0.0566 0.0232 yes 0.9768 +1 10 0.0918 0.0369 0.0192 yes 0.9808 +1 11 0.0468 0.0323 0.0140 yes 0.9860 +1 12 0.0324 -0.0009 0.0024 yes 0.9976 +1 13 0.0624 0.0013 0.0056 yes 0.9944 +1 14 0.0417 0.0030 0.0044 yes 0.9956 +1 15 0.0364 0.0474 0.0178 yes 0.9822 +1 16 0.0213 0.0110 0.0052 yes 0.9948 +1 17 0.0613 0.0049 0.0067 yes 0.9933 +1 18 0.0422 0.0084 0.0062 yes 0.9938 +1 19 0.0287 0.0119 0.0061 yes 0.9939 +1 20 0.0524 0.0422 0.0175 yes 0.9825 +1 Std. Dev Mean Median 0.0224 0.0503 0.0481 0.0210 0.0176 0.0115 0.0072 0.0097 0.0064 n/a Number of Positive Differences (S+): Critical Value, k, Table 1.3 of Marssim: n/a S+ >thank?: n/a Survey Unit Pass or Fail: **Pass*Note: Forced-Count values are used for samples with activity levels below the MDA.**Note: If all measurement data are less than the DCGL ., then the Sign Test is not required.
 
I t RM-79 FINAL STATUS SURVEY QUALITY CONTROL Revision 1 Page 11 of 13 RM-79-1 CONTROL EVALUATION RESULTS FSS QUALITY FSS Package #0(a C' I QC Package # o (c2Co /QC Measurement Type Acceptance Criteria Met*? Reference 1. Replicate Scan (2 No Step 5.1.3.2. Sample Recounts Step 5.1.4.1_ _ a. In-house No 2/yL b. Third party Yes / No 3. Split Samples Step 5.1.4.2 c. In-house No d. Third party Yes I No*NOTE: If Acceptance Criteria is not met, completion of Attachment RM-79-2, FSS Quality Control Investigation Results, is required.Comments:~-w&#xfd; 4 AA t -F Reviews: TEvaluator Technical Review Date Die RM-79.doc QA Verification Split Sample Analysis Date: QA: Type: Lab: 9/14/2006 06C, 1 South Central Protected Area Table I Acceptance Criteria Resolution Ratio<4 N/A 4-7 0.5-2.0 8-15 0.6-1.66 16-50 0.75-1.33 51-200 0.8-1.25>200 0.85-1.18 Split Sample In-House A B C D E F (3 BRP BRP BRP Results in Sample Radionuclide Result Results % Error BRP Ratio Results Split Results Comparison Agreement Rati ResltsRatio Below Resolution (pCi/g) Compare MDA (pCi/g) (Sigma) (Table 1) Below MDA F/A G with D)12 Co-60 < 0.0624 n/a n/a n/a < 0.0638 1.02 YES 12 Cs-137 < 0.0612 n/a n/a n/a < 0.0622 1.02 YES A" Resolution C = -I (A)( IB< Indicates results less than the MDA.*Note Results are considered in agreement for MDA and near-MDA measurement comparisons Results fthat fail agreement must be investigated per RM-79.
Supporting Survey, Relocated Soil Release Record TBCx151 Relocated Soils From Turbine Building/Containment Demolition SURVEY PACKAGE CLOSURE Final Status Survey Documentation is authorized for closure. All required reviews are complete and the evaluation of data results have satisfied the criteria established for unrestricted release and onsite use for excavation backfill.
QA Verification Sample Recount Analysis Date: 9/14/2006 QA: Type: Lab: 06C,1 South Central Protected Area Table 1 Acceptance Criteria Resolution Ratio<4 N/A 4-7 0.5-2.0 8-15 0.6-1.66 16-50 0.75-1.33 51-200 0.8-1.25>200 0.85-1.18 Sample Recounts In- House A B C DE F G BRP BRP BRP Acceptance Recount Recount Comparison Agreement Result RReonAgemt Sample Radionuclide Below Results % Error Resolution Ratio Result Results Ratio Compare S (pCi/g) (Sigma) ( Table 1) el (pCi/g) F/A Compare MDA pg, Iga(Tbe Below MDA G with D)14 Co-60 < 0.0639 n/a n/a n/a < 0.0749 1.17 YES 14 Cs-137 0.0417 38.44 2.60 n/a 0.0671 1.61 YES 16 Co-60 < 0.0612 n/a n/a n/a < 0.0479 0.78 YES 16 Cs-137 < 0.0598 n/a n/a n/a 0.0506 0.85 YES Resolution C= (Al OO< Indicates results less than the MDA.*Note Results are considered in agreement for MDA and near-MDA measurement comparisons Results flhat fail agreement must be investigated per RM-79.
Sianed&#xfd;&#xfd;'          -&#xfd;5 -5sy-&#xfd;&#xfd;        Date:  io(Z.5 (ESSG Supervisor)                  '
.4 if Tritium in Soil Data Results Final Status Survey 06C 1 1 Sample Tritium in Soil Number pCi/g 12 0.007 14 0.015 16 0.024 Mean: 0.0153 Median: 0.0150 St. Dev: 0.0085 Note: The DCGL for Tritium is 327 pCi/g.Sample results are less than 0.02% of the DCGL
z/ /
-Environmental, Inc.Midwest Laboratory an Allegheny Technologies Co.700 Landwehr Road -Northbrook, IL 60062-2310 ph. (847) 564-0700
Signed:                                Date:
* fax (847) 564-4517 Mr. David W. Parish LABORATORY REPORT NO. 8022-100-230 Big Rock Point DATE: 09-22-2006 10269 US-31 North SAMPLES RECEIVED:
                                'S Superintendent)
09-19-2006 Charlevoix, MI 49720 PURCHASE ORDER NO: Below are the results of the analyses for tritium on three soil samples.Excavated Soil Survey 06C 1 l Sample Collection Lab Concentration MDA Description Date Code (pCi/g of soil) (pCi/g of soil)H-3 12 09-14-06 BRSO-6372 0.007 +/- 0.006 <0.011 14 09-14-06 BRSO-6373 0.015 +/- 0.008 < 0.014 16 09-14-06 BRSO-6374 0.024 +/- 0.007 < 0.013 The error given is the probable counting error at 95 % confidence level. The less than, (<), value is based on 4.66 sigma counting error for background sample.APPROVED BY-J-0&#xfd;4//& A Tony Coorlim, Quality Assurance
Signed:                              Date:
* t~ATTACHMENT 5 CONSUMERS ENERGY BIG ROCKPOINT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION CLASS I RELOCATED SOIL RELEASE RECORD, TBCx 1 5 1, RELOCATED SOILS FROM TURBINE BUILDING/CONTAINMENT DEMOLITION October 24, 2006 38 Pages Supporting Survey, Relocated Soil Release Record TBCx 1 5 1 Relocated Soils From Turbine Building/Containment Demolition SURVEY PACKAGE CLOSURE Final Status Survey Documentation is authorized for closure. All required reviews are complete and the evaluation of data results have satisfied the criteria established for unrestricted release and onsite use for excavation backfill.Sianed&#xfd;&#xfd; ' -&#xfd;5 -5sy-&#xfd;&#xfd;Date: io(Z.5 Signed: Signed: (ESSG Supervisor) z/ /'S Superintendent)(RP & ES Manager)Date: Date: '
(RP & ES Manager)
I-, Survey Requirements Release Record TBCx5 1 l Relocated Soils From Turbine Building/Containment Demolition Area Survey Description Supporting survey TBCX 1 5 1 consists of soils excavated during Turbine/Containment demolition and the removal of subsurface piping components.
 
The excavated soil was transported to the soil verification area (SVA) and graded to maximum depth of 1.0 meter. The physical size of the survey area is 1800 square meters.The evaluation of excavated soil will be performed in accordance with procedure RM-76, Final Status Survey Design. Sample locations will be established by random start, systematic square grid pattern over the graded area. Each soil sample will be a full core homogenized composite that is representative of total soil thickness.
I-,
Surface scanning will be conducted over 100% of the survey area.History The soil for survey evaluation originated from a Class 1 area that was excavated to remove concrete and piping components in the Turbine Building/Containment demolition area. Soil remediation efforts were required for some areas associated with subsurface component removal.Current Radiological Status Based on post remediation analyses and supporting surveys the residual radioactivity in this excavated soil is not expected to exceed DCGL concentration values. Survey documentation is maintained in the 10 CFR 50.75(g) files. Input for this evaluation includes the following survey data: Turbine Building Demolition Supporting Surveys for Soil Transport and Evaluation TB051005 SB040405 SB042905 TB062805 HH060705 TB052405 SB040605 SB050205 HH050505 TB060905 TB052505 SB040705 SB051705 HH051705 TB080805 TB052605 SB041205 SB051805 HH051905 TB080905 TB060105 SB041905 HH042705 HH041905 Survey Requirements TBC.isI Page 1 of 2 40 &#xfd; i Post-Construction Expectations Survey TBCx 1 5 1 will be performed in the following activity sequence: 1. Walkdown:
Survey Requirements Release Record TBCx51 l Relocated Soils From Turbine Building/Containment Demolition Area Survey Description Supporting survey TBCX15 1 consists of soils excavated during Turbine/Containment demolition and the removal of subsurface piping components. The excavated soil was transported to the soil verification area (SVA) and graded to maximum depth of 1.0 meter. The physical size of the survey area is 1800 square meters.
Environmental Services Survey Group (ESSG) personnel will perform a walkdown assessment to ensure survey area preparations are complete and confirm that the following post-construction expectations have been satisfied as applicable:
The evaluation of excavated soil will be performed in accordance with procedure RM-76, Final Status Survey Design. Sample locations will be established by random start, systematic square grid pattern over the graded area. Each soil sample will be a full core homogenized composite that is representative of total soil thickness. Surface scanning will be conducted over 100% of the survey area.
0 0 0 Groundwater and Surface water control is adequate All construction debris has been removed from the survey area The survey location status meets all applicable safety requirements
History The soil for survey evaluation originated from a Class 1 area that was excavated to remove concrete and piping components in the Turbine Building/Containment demolition area. Soil remediation efforts were required for some areas associated with subsurface component removal.
: 2. Survey Area Isolation and Control: Control measures will be established to ensure that any potential ongoing decommissioning activities in adjacent locations do not impact the current survey area status. Isolation and control measures include postings, barriers, access points, and the evaluation of ongoing work activities in adjacent areas.3. Survey Design and Execution:
Current Radiological Status Based on post remediation analyses and supporting surveys the residual radioactivity in this excavated soil is not expected to exceed DCGL concentration values. Survey documentation is maintained in the 10 CFR 50.75(g) files. Input for this evaluation includes the following survey data:
Survey design and execution will follow the Data Quality Objectives for TBCxl 5 1 in accordance with the survey requirements established in procedures RM-76, Final Status Survey Design and RM-77, Final Status Survey Implementation, and LTP, Chapter 5. Survey size will be based on the statistical requirements of the Sign Test for Class 1 areas with soil samples collected in random start, systematic data point locations.
Turbine Building Demolition Supporting Surveys for Soil Transport and Evaluation TB051005            SB040405                SB042905          TB062805          HH060705 TB052405            SB040605                SB050205          HH050505          TB060905 TB052505            SB040705                SB051705          HH051705          TB080805 TB052605            SB041205                SB051805          HH051905          TB080905 TB060105            SB041905                HH042705          HH041905 Survey Requirements TBC.isI Page 1 of 2
Surface scanning will be performed with 100%survey area coverage.
 
This survey will be conducted in accordance with approved BRP procedures and follow the guidance of NUREG 1575.4. Data Quality Assessment:
40&#xfd; i Post-Construction Expectations Survey TBCx151 will be performed in the following activity sequence:
Isolation and control of the survey area will be maintained until the survey Data Quality Assessment demonstrates that the regulatory requirements for unrestricted site release have been satisfied.
: 1. Walkdown: Environmental Services Survey Group (ESSG) personnel will perform a walkdown assessment to ensure survey area preparations are complete and confirm that the following post-construction expectations have been satisfied as applicable:
Survey Requirements TBCX1 5 1 Page 2 of 2 DATA QUALITY OBJECTIVES Survey TBCx 1 5 1 Relocated Soils From Turbine Building/Containment Demolition Area STATE THE PROBLEM The Problem: To demonstrate that the level of residual radioactivity in soils excavated from the Turbine Building/Containment demolition area does not exceed the release criteria of 25 mrem/year Total Effective Dose Equivalent (TEDE) as specified in the License Termination Plan (LTP). This soil has been relocated to the soil verification area (SVA)and is to be prepared for survey by grading out to a depth of one (1) meter or less. The excavated soil for evaluation is to be designated as a Class 1 survey area. It must be demonstrated that soils in this survey area satisfy the criteria established for unrestricted release prior to disposition as fill material for onsite usage.Stakeholders:
0   Groundwater and Surface water control is adequate 0   All construction debris has been removed from the survey area 0   The survey location status meets all applicable safety requirements
The primary stakeholders interested in the answer to this problem are Consumers Energy Co., and the general public as represented by the Michigan Department of Environmental Quality (MDEQ), and the US Nuclear Regulatory Commission (USNRC).The Planning Team: The planning team consists of members of the BRP Environmental Services Survey Group (ESSG). The primary decision maker will be the Final Status Survey Supervisor.
: 2. Survey Area Isolation and Control: Control measures will be established to ensure that any potential ongoing decommissioning activities in adjacent locations do not impact the current survey area status. Isolation and control measures include postings, barriers, access points, and the evaluation of ongoing work activities in adjacent areas.
The Final Status Survey Supervisor will obtain input from the site Construction Group and Scheduling Group for issues relating to schedule and costs.Schedule: Approximately five (5) working days are projected to implement the survey and to collect and analyze field data.Resources:
: 3. Survey Design and Execution: Survey design and execution will follow the Data Quality Objectives for TBCxl 51 in accordance with the survey requirements established in procedures RM-76, Final Status Survey Design and RM-77, Final Status Survey Implementation, and LTP, Chapter 5. Survey size will be based on the statistical requirements of the Sign Test for Class 1 areas with soil samples collected in random start, systematic data point locations. Surface scanning will be performed with 100%
The primary resources needed to determine the answer to the problem are two (2)technicians to perform fieldwork, one (1) technician to prepare the samples and conduct laboratory analyses, and two (2) survey team members to prepare and review the design, generate maps, coordinate field activities and evaluate data.2. IDENTIFY THE DECISION Several decisions need to be defined to address the stated problem.Principal Study Question (1): Does the mean concentration of residual radioactivity in the survey unit exceed the release criteria stated above?Data Quality Objectives TBC, 1 5 1 Page 1 of 5 Decision (1): Determine whether the mean concentration of residual radioactivity in the survey exceeds the release criteria stated in the problem.Actions (1): Alternative actions include failure of the survey unit, remediation, or no action required.Principal Study Question (2): Do any areas of elevated activity in the survey unit exceed the release criteria?The Decision (2): Determine if any areas of elevated activity in the survey unit exceed the release criteria.Actions (2): Alternative actions include confirmation and investigation, performing the elevated measurement comparison (EMC), remediation, or no action required.Principal Study Question (3): Is the potential dose from residual radioactivity in the survey unit ALARA as stated?The Decision (3): Determine if the potential dose from residual radioactivity in the survey unit is ALARA.ALARA requirements for soil remediation are defined in Chapter 4 of the LTP.Actions (3): Alternative actions include remediation or no action required.3. IDENTIFY INPUTS TO THE DECISION Information Needed: Characterization measurements are required to define the radionuclides present and determine the extent and variability of residual radioactivity in the survey area for design and implementation of the survey. Survey area classification, ALARA analysis, potential radionuclides of interest, and site-specific DCGL values are also required inputs to the decision process. The primary information required for evaluation is the analytical results of survey measurements.
survey area coverage. This survey will be conducted in accordance with approved BRP procedures and follow the guidance of NUREG 1575.
: 4. Data Quality Assessment: Isolation and control of the survey area will be maintained until the survey Data Quality Assessment demonstrates that the regulatory requirements for unrestricted site release have been satisfied.
Survey Requirements TBCX1 51 Page 2 of 2
 
DATA QUALITY OBJECTIVES Survey TBCx15 1 Relocated Soils From Turbine Building/Containment Demolition Area STATE THE PROBLEM The Problem:
To demonstrate that the level of residual radioactivity in soils excavated from the Turbine Building/Containment demolition area does not exceed the release criteria of 25 mrem/year Total Effective Dose Equivalent (TEDE) as specified in the License Termination Plan (LTP). This soil has been relocated to the soil verification area (SVA) and is to be prepared for survey by grading out to a depth of one (1) meter or less. The excavated soil for evaluation is to be designated as a Class 1 survey area. It must be demonstrated that soils in this survey area satisfy the criteria established for unrestricted release prior to disposition as fill material for onsite usage.
Stakeholders:
The primary stakeholders interested in the answer to this problem are Consumers Energy Co., and the general public as represented by the Michigan Department of Environmental Quality (MDEQ), and the US Nuclear Regulatory Commission (USNRC).
The Planning Team:
The planning team consists of members of the BRP Environmental Services Survey Group (ESSG). The primary decision maker will be the Final Status Survey Supervisor.
The Final Status Survey Supervisor will obtain input from the site Construction Group and Scheduling Group for issues relating to schedule and costs.
Schedule:
Approximately five (5) working days are projected to implement the survey and to collect and analyze field data.
Resources:
The primary resources needed to determine the answer to the problem are two (2) technicians to perform fieldwork, one (1) technician to prepare the samples and conduct laboratory analyses, and two (2) survey team members to prepare and review the design, generate maps, coordinate field activities and evaluate data.
: 2. IDENTIFY THE DECISION Several decisions need to be defined to address the stated problem.
PrincipalStudy Question (1):
Does the mean concentration of residual radioactivity in the survey unit exceed the release criteria stated above?
Data Quality Objectives TBC,15 1 Page 1 of 5
 
Decision (1):
Determine whether the mean concentration of residual radioactivity in the survey exceeds the release criteria stated in the problem.
Actions (1):
Alternative actions include failure of the survey unit, remediation, or no action required.
PrincipalStudy Question (2):
Do any areas of elevated activity in the survey unit exceed the release criteria?
The Decision (2):
Determine if any areas of elevated activity in the survey unit exceed the release criteria.
Actions (2):
Alternative actions include confirmation and investigation, performing the elevated measurement comparison (EMC), remediation, or no action required.
PrincipalStudy Question (3):
Is the potential dose from residual radioactivity in the survey unit ALARA as stated?
The Decision (3):
Determine if the potential dose from residual radioactivity in the survey unit is ALARA.
ALARA requirements for soil remediation are defined in Chapter 4 of the LTP.
Actions (3):
Alternative actions include remediation or no action required.
: 3. IDENTIFY INPUTS TO THE DECISION Information Needed:
Characterization measurements are required to define the radionuclides present and determine the extent and variability of residual radioactivity in the survey area for design and implementation of the survey. Survey area classification, ALARA analysis, potential radionuclides of interest, and site-specific DCGL values are also required inputs to the decision process. The primary information required for evaluation is the analytical results of survey measurements.
Source of the Information:
Source of the Information:
The soil sample data to be used for survey development are the radionuclide-specific measurements of representative soil samples collected for characterization to determine suitability for transport to the SVA. The soil samples obtained were judgmentally selected as a result of multiple surveys conducted during the excavation and transport process. The ALARA analysis for potential soil remediation is provided in LTP, Section 4.4. Site-specific DCGL values and BRP radionuclides of interest are defined in LTP Chapter 5, Table 5-1 and Procedure RM-76, Final Status Survey Design.The survey will be conducted in accordance with applicable regulatory guidance as established in LTP Chapter 5 for Class 1 areas. Soil samples will be utilized for radionuclide-specific measurements in this evaluation.
The soil sample data to be used for survey development are the radionuclide-specific measurements of representative soil samples collected for characterization to determine suitability for transport to the SVA. The soil samples obtained were judgmentally selected as a result of multiple surveys conducted during the excavation and transport process. The ALARA analysis for potential soil remediation is provided in LTP, Section 4.4. Site-specific DCGL values and BRP radionuclides of interest are defined in LTP Chapter 5, Table 5-1 and Procedure RM-76, Final Status Survey Design.
Data Quality Objectives TBC, 1 5 1 Page 2 of 5  
The survey will be conducted in accordance with applicable regulatory guidance as established in LTP Chapter 5 for Class 1 areas. Soil samples will be utilized for radionuclide-specific measurements in this evaluation.
: 4. BOUNDARIES OF THE STUDY Boundaries of the Survey: The target population for this survey is the total thickness of prepared soil in the survey area of 1800 M 2.Temporal Boundaries:
Data Quality Objectives TBC, 15 1 Page 2 of 5
Scanning and sampling in this survey unit will only be performed during daylight hours under dry weather conditions.
: 4.       BOUNDARIES OF THE STUDY Boundaries of the Survey:
Surface soils must be free of significant snow cover and standing water prior to surface scanning.
The target population for this survey is the total thickness of prepared soil in the survey area of 1800 M2 .
Soils must be in a non-frozen state or fragmented for collection to satisfy BRP procedural sampling requirements.
Temporal Boundaries:
The anticipated start date for the survey is September 22, 2006.Constraints:
Scanning and sampling in this survey unit will only be performed during daylight hours under dry weather conditions. Surface soils must be free of significant snow cover and standing water prior to surface scanning. Soils must be in a non-frozen state or fragmented for collection to satisfy BRP procedural sampling requirements. The anticipated start date for the survey is September 22, 2006.
Constraints:
Cold weather or rainy conditions may effect the operation of electronic equipment.
Cold weather or rainy conditions may effect the operation of electronic equipment.
Adverse weather conditions that include accumulations of rain or snow may limit area access and delay survey efforts.5. DEVELOP A DECISION RULE The following decision rules have been developed to define a logical process for choosing among alternative actions for the principal study questions associated with this survey area.Decision Rule (1): If all reported concentrations for residual radioactivity are less than the site-specific DCGL's and the unity rule has been satisfied for each sample, then the survey unit meets release criteria.
Adverse weather conditions that include accumulations of rain or snow may limit area access and delay survey efforts.
No further action is required.Decision Rule (2): If the mean value of activity in the survey unit is greater than the DCGL, then the survey unit fails to meet the release criteria.'
: 5.     DEVELOP A DECISION RULE The following decision rules have been developed to define a logical process for choosing among alternative actions for the principal study questions associated with this survey area.
Remediate, resurvey, and evaluate the results relative to the decision rule.Decision Rule (3): If the mean activity in the survey unit is less than the DCGL and any individual sample measurement exceeds this value, conduct the Sign Test and the elevated measurement comparison (EMC) per LTP, Chapter 5 and Procedure RM-76, Final Status Survey Design. If the EMC and the Sign Test have been satisfied then the survey unit meets the release criteria and no further action is required.
Decision Rule (1):
If the EMC or the Sign Test has not been satisfied then remediate the area(s) of elevated activity, resurvey as appropriate, and evaluate the results relative to the decision rule.When multiple radionuclides are present the mean activity value is determined as the average of the weighted sum. The DCGL of the weighted sum is 1.Data Quality Objectives TBCx 1 5 1 Page 3 of 5 Decision Rule (4): If the potential dose from residual radioactivity in the survey unit is ALARA, then no further action is necessary.
If all reported concentrations for residual radioactivity are less than the site-specific DCGL's and the unity rule has been satisfied for each sample, then the survey unit meets release criteria. No further action is required.
If the potential dose from residual radioactivity in the survey unit is not ALARA, then remediate and resurvey.6. SPECIFY TOLERABLE LIMITS ON DECISION ERRORS The Null Hypothesis:
Decision Rule (2):
If the mean value of activity in the survey unit is greater than the DCGL, then the survey unit fails to meet the release criteria.' Remediate, resurvey, and evaluate the results relative to the decision rule.
Decision Rule (3):
If the mean activity in the survey unit is less than the DCGL and any individual sample measurement exceeds this value, conduct the Sign Test and the elevated measurement comparison (EMC) per LTP, Chapter 5 and Procedure RM-76, Final Status Survey Design. If the EMC and the Sign Test have been satisfied then the survey unit meets the release criteria and no further action is required. If the EMC or the Sign Test has not been satisfied then remediate the area(s) of elevated activity, resurvey as appropriate, and evaluate the results relative to the decision rule.
When multiple radionuclides are present the mean activity value is determined as the average of the weighted sum. The DCGL of the weighted sum is 1.
Data Quality Objectives TBCx151 Page 3 of 5
 
Decision Rule (4):
If the potential dose from residual radioactivity in the survey unit is ALARA, then no further action is necessary. If the potential dose from residual radioactivity in the survey unit is not ALARA, then remediate and resurvey.
: 6. SPECIFY TOLERABLE LIMITS ON DECISION ERRORS The Null Hypothesis:
It is assumed that residual radioactivity in the survey unit exceeds the release criterion.
It is assumed that residual radioactivity in the survey unit exceeds the release criterion.
Type I Error (a ): The a error is the maximum probability of rejecting the null hypotheses when it is true.Thea error is defined in the LTP at a value of 0.05 (5%) and cannot be changed to a less restrictive value unless prior approval is granted by the USNRC. The a error value of 0.05 will be used for survey planning and data assessment for this survey area.Type II Error (/3): The ,8 error is the probability of accepting the null hypothesis when it is false. A value of 0.05 (5%) will be used for survey planning and data assessment for this survey area.The Lower Bound of the Gray Region (LBGR): The LBGR is initially set at one-half the DCGLw for this survey unit. The LBGR may be adjusted during survey design to achieve an optimum relative shift between 1.0 and 3.0.Relative Shift (A/a): The relative shift will be maintained within the range of 1.0 and 3.0 by adjusting the LBGR as appropriate.
Type I Error(a ):
: 7. OPTIMIZE DESIGN FOR OBTAINING DATA Statistical Test Sign Test: Radionuclides of potential plant origin also present in soil as background activity resulting from fallout constitute only a small fraction of the DCGL. Therefore, the Sign Test will be used where applicable in the survey evaluation to determine if the survey area meets the requirements for unrestricted release.Number of Samples Determined:
The a error is the maximum probability of rejecting the null hypotheses when it is true.
The number of samples required for this survey will be determined based on the relative shift as defined by the requirements of the Sign Test (LTP, Chapter 5.) and Procedure RM-76, Final Status Survey Design. The LBGR is initially set at one-half the DCGLw and may be adjusted as necessary for optimizing the survey design to achieve a relative shift between 1.0 and 3.0. Sample point locations are to be determined using a random start, systematic square grid spacing.Data Quality Objectives TBC 1 5 1 Page 4 of 5 Judgmental Sampling: Co-60 is the most limiting radionuclide for identification by surface scanning; judgmental surface and subsurface core samples will be collected in any location that exceeds the scan investigation level.Scan Coverage: Scanning for this survey area will provide 100% coverage.Number of Samples for Quality Control: A minimum of 5% of the sample population will be collected for quality evaluation.
Thea error is defined in the LTP at a value of 0.05 (5%) and cannot be changed to a less restrictive value unless prior approval is granted by the USNRC. The a error value of 0.05 will be used for survey planning and data assessment for this survey area.
These samples may include sample splits, sample recounts, or third party sample analysis.
Type II Error(/3):
Quality analyses will be conducted as defined in LTP, Chapter 5 and Procedure RM-79, Final Status Survey Quality Control.Additional Sample Analysis Requirements:
The ,8 error is the probability of accepting the null hypothesis when it is false. A value of 0.05 (5%) will be used for survey planning and data assessment for this survey area.
The area of soil excavation intersects the identified waterborne pathway for Tritium migration and shall require Tritium in soil analyses for a minimum of 10% of the sample population.
The Lower Bound of the Gray Region (LBGR):
Soil samples will be collected in the same random locations as those selected for QA/QC evaluation and sent to an independent laboratory for Tritium analysis.
The LBGR is initially set at one-half the DCGLw for this survey unit. The LBGR may be adjusted during survey design to achieve an optimum relative shift between 1.0 and 3.0.
Data results will be provided in the survey package.Investigation Levels: Investigation levels defined in LTP, Chapter 5 and BRP Procedure RM-76, Final Status Survey Design, shall be conservatively established for this survey as shown below: Investigation Levels for Survey TBCx 1 5 1 Scan Measurement Soil Sample Analysis> DCGL > DCGLW The investigation levels for soil sample measurements are meant to include any individual radionuclide result greater than the site-specific DCGL or where the combined radionuclide values exceed the unity rule. Co-60 is the most limiting radionuclide for identification by surface scanning; further investigation will be initiated at any location that exceeds the Co-60 Scan DCGL of 1818 CPM above background as detailed in the survey design.Data Quality Objectives TBC, 1 5 1 Page 5 of 5 SURVEY DESIGN Survey TBCx 5 sl Survey Design Relocated Soils from Turbine Building/Containment Demolition Area Survey Unit Description Survey TBCx 1 5 1 consists of excavated soils that have been removed from the Turbine Building/Containment demolition area for subsurface structure and component removal. Areas of excavation include the Containment foundation and the following subsurface piping and components:
Relative Shift (A/a):
* Underground diesel storage tank (heating boiler),* Condenser cooling water piping,* Service water and firewater piping* East side storm drain, and* Radwaste effluent piping in Survey Units 8, 9, and 10.The soil has been graded out to a maximum thickness of one (1) meter over a total area of 1800 M 2.Soil sample locations for this survey will be determined using a random start, systematic, square-grid pattern over the graded area. Each soil sample will be a homogenized composite representative of the total thickness of soil. Surface scanning will be conducted over 100% of the graded area.Soil Sample Design Scoping Data Sample measurements obtained to determine suitability for soil transport to the designated survey area have not identified residual radioactivity above fractional concentrations of the DCGL value. Input data for survey design were conservatively estimated based on supporting surveys for transport suitability obtained in the Turbine Building demolition area.Table 1 Input Data for Survey Design (pCi/g)Radionuclides Cs-137 Co-60 a
The relative shift will be maintained within the range of 1.0 and 3.0 by adjusting the LBGR as appropriate.
* 0.524 0.255 DCGL 11.93 3.21*Survey data detailed in Attachment 1 Sample Requirements The number of sample data points for this survey is based on the requirements of the Sign Test.The Unity Rule is used for the presence of multiple radionuclides.
: 7. OPTIMIZE DESIGN FOR OBTAINING DATA Statistical Test Sign Test:
The Standard Deviation of the weighted sum is described by the following:
Radionuclides of potential plant origin also present in soil as background activity resulting from fallout constitute only a small fraction of the DCGL. Therefore, the Sign Test will be used where applicable in the survey evaluation to determine if the survey area meets the requirements for unrestricted release.
= ICDCG~cs1 3 7) +C~o Survey Design TBCx 1 5 1 Page 1 of 8  
Number of Samples Determined:
,/0.524 '2 (f0.255 '2 (= 0.091 Relative Shift Relative Shift = DCGLw-LBGR G Relative Shift = 1-0.818 0.091 Relative Shift = 2.0 With cc and P3 error levels set at 0.05 and the relative shift of 2.0, the Sign Test requires 15 sample data points (Table 5.5 NUREG 1575).Sample Locations Sample locations are selected in a random start, systematic square grid pattern with the southwest corner of the survey unit as origin (X=0, Y=0). Two numbers between 0 and 1 have been randomly selected and then applied to the survey unit maximum X and Y dimensions to determine the random start location as shown below: Table 2 Random Numbers Random #, X Axis 0.341663+/-Random #, Y Axis 0.184214 Survey Unit Dimensions:
The number of samples required for this survey will be determined based on the relative shift as defined by the requirements of the Sign Test (LTP, Chapter 5.) and Procedure RM-76, FinalStatus Survey Design. The LBGR is initially set at one-half the DCGLw and may be adjusted as necessary for optimizing the survey design to achieve a relative shift between 1.0 and 3.0. Sample point locations are to be determined using a random start, systematic square grid spacing.
Random Start Location With SW Corner Origin: X = 150 meters Y = 12 meters X = (0.341663)(150)  
Data Quality Objectives TBC 1 51 Page 4 of 5
= 51.2 meters Y = (0.184214)(12)  
 
= 2.2 meters Sample Spacing As a conservative measure sample spacing will be calculated based on 18 samples for this survey. Samples are located in a systematic square grid pattern with sample spacing determined by the following:
Judgmental Sampling:
L=A!n where A= area of survey unit, and n = number of samples.L, 18 = 10 meters= 180 Survey Design TBC&#xfd;1 5 1 Page 2 of 8 With sample spacing established at 10 meters, 15 data points are available for this survey.Data point locations are identified in Attachment 2.QAJQC Sampling A minimum of 5% of the sample population and 5% of the scan survey area are required to be selected for QA/QC verification in accordance with BRP Procedure RM-79, Final Status Survey Quality Control. As a conservative measure, three (3) soil samples and 10% of the scan survey area will be selected for QA/QC evaluation.
Co-60 is the most limiting radionuclide for identification by surface scanning; judgmental surface and subsurface core samples will be collected in any location that exceeds the scan investigation level.
Data point locations for soil samples will be determined by random number selection.
Scan Coverage:
The QA/QC scan starting point and track direction are also determined by random number selection.
Scanning for this survey area will provide 100% coverage.
The first random data point selected will identify the scanning start point and the second random data point will determine the direction in which the scan will track. QA/QC location results are provided in Table 3 below: Table 3 Random Numbers Generated for QA/QC QA/QC Soil Random Random Sample Verification Scan Sample Samples Number Number Split Sample: 2 Start Point: 8 Sample Recount: 4 Scan Toward: 2 Sample Recount: 7 Minimum Scan Area Requirement:
Number of Samples for Quality Control:
180 M 2 Surface Scanning The coverage requirement for surface scanning in this Class 1 area is 100%. The Scan MDc has been established at fractional values of the DCGLwfor typical background activity levels at Big Rock Point. Scan MDc values for varying backgrounds are provided in Attachment  
A minimum of 5% of the sample population will be collected for quality evaluation.
: 3. The investigation level for identification of potential areas of elevated activity in this survey area will be the Scan DCGL as defined by the following:
These samples may include sample splits, sample recounts, or third party sample analysis. Quality analyses will be conducted as defined in LTP, Chapter 5 and Procedure RM-79, Final Status Survey Quality Control.
Scan DCGL = Detector Rating CPM
Additional Sample Analysis Requirements:
* Exposure Model uR/hr , DCGLw uR/hr pCi/g Scan DCGL for Co-60 = 1818 CPM Scan DCGL for Cs-137 = 3518 CPM Where: 1 Detector Rating = 1200 CPM Cs-137 and 565 CPM Co- 60 uR/hr uR/hr Exposure Model = 1.229uR/hr Cs-1 3 7 and 5.029 uR/hr Co_-60 5pCi/g 5 pCi/g DCGLw = 11.93 pCi/g Cs-137 and 3.21 pCi/g Co-60 These values established in EA-BRP-SC-0201, Nal Scanning Sensitivity for Open Land Survey.Survey Design TBC 1 5 1 Page 3 of 8 The DCGLw for Co-60 is the most limiting value for scanning measurements performed to identify areas of potentially elevated activity.
The area of soil excavation intersects the identified waterborne pathway for Tritium migration and shall require Tritium in soil analyses for a minimum of 10% of the sample population. Soil samples will be collected in the same random locations as those selected for QA/QC evaluation and sent to an independent laboratory for Tritium analysis. Data results will be provided in the survey package.
Scanning conducted for this survey will assume all residual radioactivity to originate from Co-60 and the instrument response at the Co-60 DCGLw (1818 cpm)will be used as the scanning investigation level for Survey TBCx 1 5 1.Survey Design TBC, 1 5 1 Page 4 of 8 Attachment 1 Design Data -Survey TBCx, 1 5 Relocated Soils From Turbine Building Demolition Area Cs-I 37 Co-60 Survey No. Sequence Activity Activity No. (pCi/g) (pCi/g)H H060705, 1'6538 :126 0,66'-HH06070'5r 1653;9 0.06 0.06*HH675 16540 1.05 0&#xfd;66 TB062805t  
Investigation Levels:
-16755& 11 0.27 TB062805, C11617665 5&#xfd;*oTB062805 1"6774 019 03 Mean: 0.698 0.352 Std Dev: 0.524 0.255* Measurement system MDA -Co-60 not identified in this sample Survey Design TBCx 1 5 1 Page 5 of 8 Attachment 2 Soil Sample Locations  
Investigation levels defined in LTP, Chapter 5 and BRP Procedure RM-76, Final Status Survey Design, shall be conservatively established for this survey as shown below:
-Survey TBC, 1 5 1 Relocated Soils From Containment/Turbine Building Demolition Area V=IV) =X= 150 M-Sol Pise 0 5 10 20 0 8an~e Location 1L+/-.- LL.- Motors Sample no. 6 Is the random start location Sample spacing Is 10.0 meters Survey Design TBCxist Page 6 of 8 Attachment 3 Scan MDC In Varying Backgrounds Background d' _ Si MDCRsurveyor Cs-137 Co-60 Cs-137 Co-60 2000 2.48 4 28.64 607.47 0.51 1.08 2.06 1.07 3000 2.48 4 35.07 744.00 0.62 1.32 2.52 1.31 3500 2.48 4 37.88 803.61. 0.67 1.42 2.72 1.41 4000 2.48 4 40.50 859.10 0.72 1.52 2.91 1.51 4500 2.48 4 42.95 911.21 0.76 1.61 3.09 1.60______2.480  
Investigation Levels for Survey TBCx1 51 Scan Measurement                 Soil Sample Analysis
-4 4.8 -, 960.5,0 >0&#xfd;18O< ~1A7d 32~~ 1 5500 2.48 4 47.49 1,007.38 0.84 1.78 3.42 1.77 6000 2.48 4 49.60 1,052.17 0.88 1.86 3.57 1.85 6500 2.48 4 51.63 1,095.14 0.91 1.94 3.71 1.93 7000 2.48 4 53.57 1,136.48 0.95 2.01 3.85 2.00 8000 2.48 4 57.27 1,214.95 1.01 2.15 4.12 2.14 8500 2.48 4 59.04 1,252.34 1.04 2.22 4.25 2.20 9000 2.48 4 60.75 1,288.65 1.07 2.28 4.37 2.27 9500 2.48 4 62.41 1,323.96 1.10 2.34 4.49 2.33 10500 2.48 4 65.61 1,391.90 1.16 2.46 4.72 2.45 11000 2.48 4 67.16 1,424.65 1.19 2.52 4.83 2.51 11500 2.48 4 68.67 1,456.67 1.21 2.58 4.94 2.56 12000 2.48 4 70.14 1,488.00 1.24 2.63 5.04 2.62 1240,0 7.8 U4 71. 59 -i586 1.27 12:9 5. 1;5 i2.67 13000 2.48 4 73.01 1,548.76 1.29 2.74 5.25 2.73 13500 2.48 4 74.40 1,578.26 1.32 2.79 5.35 2.78 14000 2.48 4 75.77 1,607.22 1.34 2.84 5.45 2.83 14500 2.48 4 77.11 1,635.67 1.36 2.89 5.55 2.88 Sxpsr &#xfd;:(iR/hrfl5p)i~j. " 5,03Ej00&#xfd;C4$ 151;23E+OO,_____
                                > DCGL                             > DCGLW The investigation levels for soil sample measurements are meant to include any individual radionuclide result greater than the site-specific DCGL or where the combined radionuclide values exceed the unity rule. Co-60 is the most limiting radionuclide for identification by surface scanning; further investigation will be initiated at any location that exceeds the Co-60 Scan DCGL of 1818 CPM above background as detailed in the survey design.
Survey Design TBC, 1 5 1 Page 7 of 8 Attachment 4 Area Factors for Open Land Survey Evaluation Calculated Area Factors at Time of Peak Dose Area (Mt) H-3 Mn-54 Fe-55 Co-60 Sr-90 Cs-137 Eu-152 Eu-154 Eu-155 8094 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 4047 1.00 1.01 1.00 1.01 1.00 1.02 1.02 1.01 1.02 2024 1.00 1.03 1.00 1.03 1.00 1.03 1.03 1.03 1.03 1012 1.35 1.04 1.00 1.04 1.00 1.04 1.05 1.04 1.04 506 2.91 1.09 1.98 1.08 1.98 1.13 1.07 1.07 1.06 253 6.05 1.14 3.95 1.13 3.94 1.20 1.11 1.11 1.09 126 12.4 1.20 7.93 1.20 7.87 1.29 1.17 1.16 1.14 63 24.9 1.30 15.8 1.30 15.6 1.41 1.27 1.26 1.23 32 49.2 1.49 31.2 1.49 30.5 1.62 1.44 1.45 1.39 16 98.9 1.78 62.0 1.78 59.9 1.93 1.72 1.73 1.63 8 198 2.38 123 2.38 117 2.58 2.30 2.31 2.14 4 397 3.61 243 3.62 230 3.91 3.49 3.52 3.19 2 794 5.68 473 5.75 452 6.14 5.48 5.55 4.90 1 1590 9.57 905 9.73 887 10.3 9.24 9.39 7.88 Survey Design TBC.1 5 1 Page 8 of 8 RM-76 FINAL STATUS SURVEY DESIGN Revision 1 Page 19 of 19 RM-76-5 FINAL STATUS SURVEY APPROVAL AND AUTHORIZATION FOR IMPLEMENTATION Survey Code TBC,,isl Survey Area
Data Quality Objectives TBC, 15 1 Page 5 of 5
 
SURVEY DESIGN Survey TBCx 5sl Survey Design Relocated Soils from Turbine Building/Containment Demolition Area Survey Unit Description Survey TBCx15 1 consists of excavated soils that have been removed from the Turbine Building/Containment demolition area for subsurface structure and component removal. Areas of excavation include the Containment foundation and the following subsurface piping and components:
* Underground diesel storage tank (heating boiler),
* Condenser cooling water piping,
* Service water and firewater piping
* East side storm drain, and
* Radwaste effluent piping in Survey Units 8, 9, and 10.
The soil has been graded out to a maximum thickness of one (1) meter over a total area of 1800 M2. Soil sample locations for this survey will be determined using a random start, systematic, square-grid pattern over the graded area. Each soil sample will be a homogenized composite representative of the total thickness of soil. Surface scanning will be conducted over 100% of the graded area.
Soil Sample Design Scoping Data Sample measurements obtained to determine suitability for soil transport to the designated survey area have not identified residual radioactivity above fractional concentrations of the DCGL value. Input data for survey design were conservatively estimated based on supporting surveys for transport suitability obtained in the Turbine Building demolition area.
Table 1 Input Data for Survey Design (pCi/g)
Radionuclides                   Cs-137                     Co-60 a
* 0.524                     0.255 DCGL                           11.93                     3.21
        *Survey data detailed in Attachment 1 Sample Requirements The number of sample data points for this survey is based on the requirements of the Sign Test.
The Unity Rule is used for the presence of multiple radionuclides. The Standard Deviation of the weighted sum is described by the following:
    = ICDCG~cs1
: 37) +C~o Survey Design TBCx151 Page 1 of 8
 
        ,/0.524 '2 (f0.255'2
(= 0.091 Relative Shift Relative Shift = DCGLw-LBGR G
Relative Shift = 1-0.818 0.091 Relative Shift = 2.0 With cc and P3 error levels set at 0.05 and the relative shift of 2.0, the Sign Test requires 15 sample data points (Table 5.5 NUREG 1575).
Sample Locations Sample locations are selected in a random start, systematic square grid pattern with the southwest corner of the survey unit as origin (X=0, Y=0). Two numbers between 0 and 1 have been randomly selected and then applied to the survey unit maximum X and Y dimensions to determine the random start location as shown below:
Table 2 Random Numbers Random #, X Axis 0.341663           +/- Random #, Y Axis 0.184214 Survey Unit Dimensions:           X = 150 meters Y = 12 meters Random Start Location            X = (0.341663)(150) = 51.2 meters With SW Corner Origin:            Y = (0.184214)(12) = 2.2 meters Sample Spacing As a conservative measure sample spacing will be calculated based on 18 samples for this survey. Samples are located in a systematic square grid pattern with sample spacing determined by the following:
L=A!n where A= area of survey unit, and n = number of samples.
L,     18     = 10 meters
                        = 180 Survey Design TBC&#xfd;15 1 Page 2 of 8
 
With sample spacing established at 10 meters, 15 data points are available for this survey.
Data point locations are identified in Attachment 2.
QAJQC Sampling A minimum of 5% of the sample population and 5% of the scan survey area are required to be selected for QA/QC verification in accordance with BRP Procedure RM-79, FinalStatus Survey Quality Control. As a conservative measure, three (3) soil samples and 10% of the scan survey area will be selected for QA/QC evaluation. Data point locations for soil samples will be determined by random number selection.
The QA/QC scan starting point and track direction are also determined by random number selection. The first random data point selected will identify the scanning start point and the second random data point will determine the direction in which the scan will track. QA/QC location results are provided in Table 3 below:
Table 3 Random Numbers Generated for QA/QC Random                                                      Random QA/QC Soil Sample        Verification Scan                             Sample Samples                 Number                                                       Number Split Sample:                 2       Start Point:                                         8 Sample Recount:               4       Scan Toward:                                         2 Sample Recount:               7       Minimum Scan Area Requirement:                     180 M 2 Surface Scanning The coverage requirement for surface scanning in this Class 1 area is 100%. The Scan MDc has been established at fractional values of the DCGLwfor typical background activity levels at Big Rock Point. Scan MDc values for varying backgrounds are provided in Attachment 3. The investigation level for identification of potential areas of elevated activity in this survey area will be the Scan DCGL as defined by the following:
Scan   DCGL = Detector Rating CPM
* Exposure Model uR/hr , DCGLw uR/hr                         pCi/g Scan   DCGL for Co-60 = 1818 CPM Scan   DCGL for Cs-137 = 3518 CPM Where:1 Detector Rating = 1200 CPM Cs-137 and 565 CPM Co- 60 uR/hr                       uR/hr Exposure Model = 1.229uR/hr Cs-1             37  and 5.029 uR/hr Co_-60 5pCi/g                       5 pCi/g DCGLw = 11.93 pCi/g Cs-137 and 3.21 pCi/g Co-60 These values established in EA-BRP-SC-0201, Nal Scanning Sensitivity for Open Land Survey.
Survey Design TBC 15 1 Page 3 of 8
 
The DCGLw for Co-60 is the most limiting value for scanning measurements performed to identify areas of potentially elevated activity. Scanning conducted for this survey will assume all residual radioactivity to originate from Co-60 and the instrument response at the Co-60 DCGLw (1818 cpm) will be used as the scanning investigation level for Survey TBCx15 1.
Survey Design TBC,151 Page 4 of 8
 
Attachment 1 Design Data - Survey TBCx,1 5 Relocated Soils From Turbine Building Demolition Area Cs-I 37           Co-60 Survey No.     Sequence         Activity         Activity No.           (pCi/g)           (pCi/g)
H H060705,       1'6538           :126             0,66'
    -HH06070'5r       1653;9           0.06             0.06*
HH675       16540             1.05           0&#xfd;66 TB062805t       -16755&         11                 0.27 TB062805, C11617665               &#xfd;4&#xfd;7*,                5&#xfd;*
oTB062805     1"6774           019             03 Mean:       0.698             0.352 Std Dev:       0.524             0.255
* Measurement system MDA - Co-60 not identified in this sample Survey Design TBCx15 1 Page 5 of 8
 
Attachment 2 Soil Sample Locations - Survey TBC, 151 Relocated Soils From Containment/Turbine Building Demolition Area V=IV)
  =
X= 150 M
-   Sol Pise                                               0 5 10     20 Motors 0   8an~e Location                                         1L+/-.- LL.-
Sample no. 6 Is the random start location Sample spacing Is 10.0 meters Survey Design TBCxist Page 6 of 8
 
Attachment 3 Scan MDC In Varying Backgrounds Background             d'       _               Si   MDCRsurveyor   Cs-137 Co-60 Cs-137 Co-60 2000               2.48           4       28.64     607.47     0.51   1.08 2.06   1.07 3000             2.48             4       35.07     744.00     0.62   1.32 2.52   1.31 3500             2.48           4         37.88     803.61. 0.67   1.42 2.72   1.41 4000             2.48           4         40.50     859.10     0.72   1.52 2.91   1.51 4500             2.48           4         42.95     911.21     0.76   1.61 3.09   1.60
______2.480                   - 4         4.8   -, 960.5,0     >0&#xfd;18O< ~1A7d 32~~   1 5500             2.48           4         47.49   1,007.38     0.84   1.78 3.42   1.77 6000             2.48           4         49.60   1,052.17     0.88   1.86 3.57   1.85 6500             2.48           4         51.63   1,095.14     0.91   1.94 3.71   1.93 7000             2.48           4         53.57   1,136.48     0.95   2.01   3.85   2.00 8000             2.48           4         57.27   1,214.95     1.01   2.15   4.12   2.14 8500             2.48           4         59.04   1,252.34     1.04   2.22   4.25   2.20 9000             2.48           4       60.75     1,288.65     1.07   2.28   4.37   2.27 9500             2.48           4       62.41     1,323.96     1.10   2.34   4.49   2.33 10500             2.48           4       65.61     1,391.90     1.16   2.46   4.72   2.45 11000             2.48             4       67.16     1,424.65     1.19   2.52   4.83   2.51 11500             2.48             4       68.67     1,456.67     1.21   2.58   4.94   2.56 12000             2.48             4       70.14     1,488.00     1.24   2.63   5.04   2.62 1240,0                           U4        7.859
: 71.     -i586           1.27 12:9   5. 1;5 i2.67 13000             2.48             4       73.01     1,548.76     1.29   2.74   5.25   2.73 13500             2.48             4       74.40     1,578.26     1.32   2.79   5.35   2.78 14000             2.48             4       75.77     1,607.22     1.34   2.84   5.45   2.83 14500             2.48             4       77.11     1,635.67     1.36   2.89   5.55   2.88 Sxpsr
                  *5"        &#xfd;:(iR/hrfl5p)i~j.
5,03Ej00
                          &#xfd;C4$151;23E+OO,_____
Survey Design TBC, 151 Page 7 of 8
 
Attachment 4 Area Factors for Open Land Survey Evaluation Calculated Area Factors at Time of Peak Dose Area (Mt) H-3   Mn-54   Fe-55   Co-60       Sr-90 Cs-137 Eu-152 Eu-154   Eu-155 8094     1.00   1.00   1.00     1.00       1.00 1.00     1.00   1.00 1.00 4047     1.00   1.01   1.00     1.01       1.00 1.02     1.02   1.01 1.02 2024     1.00   1.03   1.00     1.03       1.00 1.03     1.03   1.03 1.03 1012   1.35   1.04   1.00     1.04       1.00 1.04     1.05   1.04 1.04 506   2.91   1.09   1.98     1.08       1.98 1.13     1.07   1.07 1.06 253   6.05   1.14   3.95     1.13         3.94 1.20     1.11   1.11 1.09 126   12.4   1.20   7.93     1.20         7.87 1.29     1.17   1.16 1.14 63   24.9   1.30   15.8     1.30         15.6 1.41     1.27   1.26 1.23 32     49.2   1.49   31.2     1.49         30.5 1.62     1.44   1.45 1.39 16   98.9   1.78   62.0     1.78         59.9 1.93     1.72   1.73 1.63 8     198   2.38   123     2.38         117   2.58     2.30   2.31 2.14 4     397     3.61   243     3.62         230   3.91     3.49   3.52 3.19 2     794     5.68   473     5.75         452   6.14     5.48   5.55 4.90 1   1590   9.57   905     9.73         887   10.3     9.24   9.39 7.88 Survey Design TBC. 151 Page 8 of 8
 
RM-76                                                                           Revision 1 FINAL STATUS SURVEY DESIGN                                                   Page 19 of 19 RM-76-5 FINAL STATUS SURVEY APPROVAL AND AUTHORIZATION FOR IMPLEMENTATION Survey Code     TBC,,isl Survey Area


== Description:==
== Description:==


Survey TBCx 1 5 1 is the final status evaluation of soil that was excavated from the Turbine Buildingq/Containment demolition area. The soil has been relocated to the SVA and prepared for survey by -gradingq to a maximum depth of 1 meter over an area of 1800 square meters.The survey area is authorized for Final Status Survey Implementation.
Survey TBCx15 1 is the final status evaluation of soil that was excavated from the Turbine Buildingq/Containment demolition area. The soil has been relocated to the SVA and prepared for survey by -gradingq to a maximum depth of 1 meter over an area of 1800 square meters.
Designed by Technical Review by... 2-/D- ate o Date on- Date RM-76.doc RM-77 FINAL STATUS SURVEY IMPLEMENTATION Revision 2 Page 8 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 1 of 3 Step (+)1.0 Initial Date PREPARATION FOR SURVEY Survey #1.1 Survey Area Status: Z a. Final Status Survey Design has been approved for implementation (see RM-76-5, Final Status Survey Approval and Authorization for Supplementation).
The survey area is authorized for Final Status Survey Implementation.
: 1. Survey area walkdown complete 2. Survey area determined ready for FSS 3. Decommissioning activities that may impact the environmental status of the survey area have been completed.
                                  ...2-/D-ate o Designed by                            Date on- I*-'*Im~o Technical Review by                      Date RM-76.doc
: 4. Survey area environment is controlled by barriers and postings or other approved method to restrict access./ b. Survey area has been turned over to the Environmental Services Survey Group (ESSG) in acceptable condition for FSS.,ESSG 4&#xfd;-Iw(a 1.2 Field Preparation:
 
+a. Survey unit boundaries delineated (Step 6.1.1)b. Statistical soil samples predetermined in the survey design are located and marked within the survey unit.(Step 6.1.2)c. Soil sample locations verified (Step 6.1.2.c)d. Instruments and equipment have been collected and calibrated for data measurement and collection (Step 6.1.3)e. Field documentation is prepared (Step 6.1.4)/(/ESSG RM-77.doc RM-77 FINAL STATUS SURVEY IMPLEMENTATION Revision 2 Page 9 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 2 of 3 Initial Date 2.0 DATA COLLECTION 2.1 Soil Survey: All soil samples collected and controlled (Step 6.2.1).2.2 Surface Scan: Surface Scan complete.
RM-77                                                                           Revision 2 FINAL STATUS SURVEY IMPLEMENTATION                                           Page 8 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 1 of 3 Step                                                                       Initial    Date
Action response requirements have been conducted on any identified areas exceeding the investigation level (Step 6.3).2.3 Judgmental Soil Samples: 4 a. Judgmental soil samples have been collected and controlled (Step 6.2.3).b. Deep core profiles performed in areas identified to contain elevated residual activity (Step 6.2.3).3.0 SAMPLE PREPARATION AND LABORATORY ANALYSIS 3.1 Sample Preparation (Step 6.4.1):/ a. Soil samples are homogenous
(+)
: b. Soil samples are visibly dry prior to packing c. Non-soil materials have been removed from sample d. Soil samples have been transferred to one-liter Marinelli containers and are labeled and sealed.EdSSG_62;&#xfd;OIL4,&#xfd;rlo
1.0   PREPARATION FOR SURVEY Survey #
&XES-SG d4z JESSG ,22Zzs1-(;(0 RM-77.doc RM-77 FINAL STATUS SURVEY IMPLEMENTATION Revision 2 Page 10 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 3 of 3 Initial Date 3.2 Laboratory Analysis: Isotopic analyses are complete.
1.1     Survey Area Status:
The spectroscopy report requires a signature of completion by the laboratory analyst and a signature of evaluation documenting that a second level review has been performed (Step 6.4.2).SSG 3.3 Sample Control and Documentation:
Z     a. Final Status Survey Design has been approved for implementation (see RM-76-5, Final Status Survey Approval and Authorization for Supplementation).
Chain of custody documentation exhibits control of soil samples (Step 6.4.3).d&eME8SG 7 Reviewed b&#xfd;Date RM-77.doc RM-59 SAMPLING AND ANALYSIS OF OPEN LAND AREAS FOR SITE CHARACTERIZATION SURVEYS Revision 11 Page 7 of 13 ATTACHMENT RM-59-1 SAMPLING AND ANALYSIS REPORT Date: 09-22-06 Time: 1600 I Location:
: 1.     Survey area walkdown complete
TBC.1 5 1 Tech:WMHILED/JHW/JNS SURVEY IDENTIFICATION I DESCRIPTION Survey TBC x15 1 consists of excavated soils removed from the Turbine/ Containment Building demolition area and the removal of subsurface Dinino and components.
: 2.     Survey area determined ready for FSS
The phvsical size of the survey prep is ISMlfl SURVEY TYPE Survey Type: Characterization X Scan (Motive)Remediation Scan (Static)X Final Trenching and Digging (use RM-59-4)SURVEY DESIGN Sample Collection:
: 3.     Decommissioning activities that may impact the environmental status of the survey area have been completed.
_ Judgmental
: 4.     Survey area environment is controlled by barriers and postings or other approved method to restrict   ,ESSG access.
_ Random X Systematic Large Container Assay Scan Coverage:
      /   b. Survey area has been turned over to the Environmental Services Survey Group (ESSG) in acceptable condition for FSS.                                                               4&#xfd;-Iw(a 1.2   Field Preparation:
100 %ANALYSIS Inst.SN/Cal Due 186194/02-08-2007 DAILY CHECK: X SAT UNSAT INIT: WMH Inst.SN/Cal Due 186192/03-14-2007 DAILY CHECK: X SAT UNSAT INIT: WMH Inst.SN/Cal Due 201195/02-10-2007 DAILY CHECK: X SAT UNSAT INIT: WMH Inst.SN/Cal Due 189086/01-26-2007 DAILY CHECK: X SAT UNSAT INIT: WMH Inst.SN/Cal Due Det #6 DAILY CHECK: X SAT UNSAT INIT: JP Investigation of Unidentified Peaks: X SAT UNSAT INIT: JLR Minimum Detectable Activity (Section 5.3.2) X SAT UNSAT INIT: JLR COMMENTS Survey TBC 1 5 1 was performed in a random start, square grid, systematic sampling pattern with samples Collected at 15 data point locations.
+       a.
Laboratory analyses did not identify residual radioactivity above trace Levels of the DCGL value. Surface scannina at 100% coveraae identified no areas of elevated residual Radioactivity.
b.
The results of QA/QC verification scanning (10% coverage) were consistent with the scan values identified in the survey.A PJ Technician Signature:
Survey unit boundaries delineated (Step 6.1.1)
Date: ______i_____
Statistical soil samples predetermined in the survey design are located and marked within the survey unit.
Second Level Review Signature:
(Step 6.1.2)
_ 6 4 Date: /Z2-O0 RM-59.doc Soil Sample Activity Summary Release Record TBCx1 51 Relocated Soil from Containment/Turbine Building Demolition Area Y= 12m X = 150 m-Soil Pile 0 5 10 20 S Sample Location I I i I I I I I Meters Prorcea-count values Coordinate location relative to SW comer of survey unit where X=O m. and Y=O m.
: c.     Soil sample locations verified (Step 6.1.2.c)
Surface Scan Summary Release Record TBCx1 51 Relocated Soil from Containment/Turbine Building Demolition Area 4.2 4.5 4.3 4.4 4.2 4,2 4.0 4.4 4.0 3.8 4.3 4.0 4,2 4.1 4.2 0Soil Pile* Sample Location 0 5 10 20 I 1 i i I 1 , 1 I Meters RED Values are Average Mobile Scan General Area Activity (kcpm)BLUE Values are Average Verification Scan General Area Activity (kcpm)GREY Values are Average General Background Area Activity (kcpm)Primary Scan: / _xwo %TechnIcian Signature:
: d.     Instruments and equipment have been collected and calibrated for data measurement and collection (Step 6.1.3)
QC Verification Scan: 10 %Technician Signature:
/      e.     Field documentation is prepared (Step 6.1.4)             (/ESSG RM-77.doc
Date: 2-:t-O;Time: Mlop Date: *?.- Time: IS'"
 
RM-72 SAMPLE CHAIN-OF-CUSTODY Revision 0 Page 4of 5 TBCx 1 5 1 RM-72-1 CHAIN-OF-CUSTODY RECORD Sample Number Sampling Location Date Time Final Disposition of Sample 1 (1.2)(2.2) / ro.2 (11.2)(2.2) " -3 (11.2)(2.2) 9~cl, gsj0j/L 2 QASplit (11.2)(2.2) 7-7 25"o- (130 3 (21.2)(2.2) 1-15'o4 I L-4 .. (R) (31.2)(2.2)  
RM-77                                                                       Revision 2 FINAL STATUS SURVEY IMPLEMENTATION                                       Page 9 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 2 of 3 Initial     Date 2.0     DATA COLLECTION 2.1     Soil Survey:
&#xfd;S-c6 /3 /5 (41.2)(2.2)  
All soil samples collected and controlled (Step 6.2.1).
-'061 t 3 &#xa3; 2" 6 (51.2)(2.2) 7- d'-e6 1/ 3 11" 7 (1) (61.2)(2.2)  
EdSSG_
! 3 d/8 (71.2)(2.2) 7-.-5,01 132j 3 9 (81.2)(2.2) cI-,5"o6 1 10 (91.2)(2.2) 7- 0 OK 3d7o 11 (101.2)(2.2) 3" c""&deg; I d, 12 (111.2)(2.2) 7"o5'O6 /3 A 13 (121.2)(2.2) 9"O 1330 14 (131.2)(2.2)  
OIL4,&#xfd;rlo &
-"A.S'o6 13 3A 15 (141.2)(2.2)  
2.2     Surface Scan:
', ;5-06 1 3 3_ _ _ _ _ _ _ _(Samples may be analyzed and stored, shipped for offsite evaluation or analyzed and disposed of.)1. Relinquis, d by:
Surface Scan complete. Action response requirements have been conducted on any identified areas exceeding the investigation level (Step 6.3).
Date Time Received in go condition by: 3. Relinquished by Date Time Received in good condition by: 3. Relinquished by: Date Time Received in good condition by: 4. Relinquished by: Date Time Received in good condition by: RM-72.doc RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 19 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 1 of 8 FINAL STATUS SURVEY: "1' w/1.0 DATA VERIFICATION 1.1 Data Acceptance X Review the Implementation Checklist (RM-77-1) to verify that survey isolation and control measures were executed prior to FSS and are being maintained.
62;&#xfd; 2.3   Judgmental Soil Samples:
X Review RM-77, Final Status Survey Implementation, to verify that methods, techniques, and survey activities required for FSS have been applied in accordance with the appropriate procedures.
4       a.     Judgmental soil samples have been collected and controlled (Step 6.2.3).
: b.     Deep core profiles performed in areas identified to contain elevated residual activity (Step 6.2.3).
XES-SG 3.0     SAMPLE PREPARATION AND LABORATORY ANALYSIS 3.1     Sample Preparation (Step 6.4.1):
  /     a.       Soil samples are homogenous
: b.     Soil samples are visibly dry prior to packing
: c.     Non-soil materials have been removed from sample
: d.     Soil samples have been transferred to one-liter Marinelli containers and are labeled and sealed.     d4z       ,22Zzs1-(;(0 JESSG RM-77.doc
 
RM-77                                                                         Revision 2 FINAL STATUS SURVEY IMPLEMENTATION                                     Page 10 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 3 of 3 Initial     Date 3.2     Laboratory Analysis:
Isotopic analyses are complete. The spectroscopy report requires a signature of completion by the laboratory analyst and a signature of evaluation documenting that a second level review has been performed (Step 6.4.2).                   SSG 3.3     Sample Control and Documentation:
Chain of custody documentation exhibits control of soil samples (Step 6.4.3).                                         d&
eME8SG b&#xfd;                     Date Reviewed 7
RM-77.doc
 
RM-59                                                                                             Revision 11 SAMPLING AND ANALYSIS OF OPEN LAND                                                               Page 7 of 13 AREAS FOR SITE CHARACTERIZATION SURVEYS ATTACHMENT RM-59-1 SAMPLING AND ANALYSIS REPORT Date: 09-22-06             Time: 1600                 I Location: TBC. 15 1       Tech:WMHILED/JHW/JNS SURVEY IDENTIFICATION I DESCRIPTION 1
Survey TBC x15 consists of excavated soils removed from the Turbine/ Containment Building demolition area and the removal of subsurface Dinino and components. The phvsical size of the survey         prep is ISMlfl SURVEY TYPE Survey Type:                     Characterization     X       Scan (Motive)
Remediation                   Scan (Static)
X       Final                         Trenching and Digging (use RM-59-4)
SURVEY DESIGN Sample Collection:     _     Judgmental   _     Random     X     Systematic         Large Container Assay Scan Coverage:         100     %
ANALYSIS Inst.SN/Cal Due 186194/02-08-2007         DAILY CHECK:       X     SAT               UNSAT       INIT: WMH Inst.SN/Cal Due 186192/03-14-2007           DAILY CHECK:       X     SAT               UNSAT       INIT: WMH Inst.SN/Cal Due 201195/02-10-2007           DAILY CHECK:       X     SAT               UNSAT       INIT: WMH Inst.SN/Cal Due 189086/01-26-2007           DAILY CHECK:       X     SAT               UNSAT       INIT: WMH Inst.SN/Cal Due       Det #6               DAILY CHECK:       X     SAT               UNSAT       INIT: JP Investigation of Unidentified Peaks:                           X     SAT               UNSAT       INIT: JLR Minimum Detectable Activity (Section 5.3.2)                     X     SAT               UNSAT       INIT: JLR COMMENTS Survey TBC   15 1 was performed in a random start, square grid, systematic sampling pattern with samples Collected at 15 data point locations. Laboratory analyses did not identify residual radioactivity above trace Levels of the DCGL value. Surface scannina at 100% coveraae identified no areas of elevated residual Radioactivity. The results of QA/QC verification scanning (10% coverage) were consistent with the scan values identified in the survey.
A         PJ Technician Signature:                                                         Date: ______i_____
Second Level Review Signature:                   _6    4                       Date:           /Z2-O0 RM-59.doc
 
Soil Sample Activity Summary Release Record TBCx1 51 Relocated Soil from Containment/Turbine Building Demolition Area Y= 12m X = 150 m
-   Soil Pile                                                                       0 5 10     20 I I i I I I I I Meters S    Sample Location Prorcea-count values Coordinate location relative to SW comer of survey unit where X=O m. and Y=O m.
 
Surface Scan Summary Release Record TBCx1 51 Relocated Soil from Containment/Turbine Building Demolition Area 4.2       4.5               4.3               4.4                   4.2           4,2               4.0 4.4   4.0           3.8           4.3         4.0               4,2                     4.1           4 .2 0Soil Pile                                                                           0   5 10       20
* Sample Location                                                                    I 1 i i I 1 , 1 IMeters RED Values are Average Mobile Scan General Area Activity (kcpm)
BLUE Values are Average Verification Scan General Area Activity (kcpm)
GREY Values are Average General Background Area Activity (kcpm)
Primary Scan:           /   * %_xwo TechnIcian Signature:                         Date: 2-:t-O; Time: Mlop QC Verification Scan:      10  %
Technician Signature:                          Date: * *?.-
* Time:       IS'"
 
RM-72                                                                                                         Revision 0 SAMPLE CHAIN-OF-CUSTODY                                                                                     Page 4of 5 TBCx151 RM-72-1 CHAIN-OF-CUSTODY RECORD Sample Number               Sampling Location                   Date         Time       Final Disposition of Sample 1                 (1.2)(2.2)                               q-*-o6          / 3a*          e_*    *.y,'-v          ro.
2                   (11.2)(2.2)                                 "                                         -
23 QASplit          (11.2)(2.2)                             7-7 gsj0j/L(130 25"o-9~cl, 3                 (21.2)(2.2)                                               I L- 1-15'o4 4   ..     (R)   (31.2)(2.2)                                         &#xfd;S-c6/3 /
5                 (41.2)(2.2)                                 -'061 &#xa3;     t 3 2" 6                 (51.2)(2.2)                               7- d'-e6 1/ 3 11" 7           (1)   (61.2)(2.2)                                   -,-*5-od; ! 3 d/
8                 (71.2)(2.2)                               7-.-5,01         132j 3 9                 (81.2)(2.2)                               cI-,5"o6 1 39*-S 10               (91.2)(2.2)                               7- 0   OK       3d7o 11               (101.2)(2.2)                                               I  3"c""&deg; d,
12               (111.2)(2.2)                             7"o5'O6 /3             A 13               (121.2)(2.2)                                   9"O         1330 14               (131.2)(2.2)                                 -"A.S'o6 13 3A 15               (141.2)(2.2)                               ', ;5-06       1   33_            _ _ _     _ _ _ _
(Samples may be analyzed and stored, shipped for offsite evaluation or analyzed and disposed of.)
: 1. Relinquis, d by: *-4/*o1*.              Date                Time                 Received in go         condition by:
: 3. Relinquished by                       Date                 Time                 Received in good condition by:
: 3. Relinquished by:                       Date                 Time                 Received in good condition by:
: 4. Relinquished by:                       Date                 Time                 Received in good condition by:
RM-72.doc
 
RM-78                                                                         Revision 2 FINAL STATUS SURVEY ASSESSMENT                                             Page 19 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 1 of 8 FINAL STATUS SURVEY:             "1'       w/
1.0         DATA VERIFICATION 1.1         Data Acceptance X       Review the Implementation Checklist (RM-77-1) to verify that survey isolation and control measures were executed prior to FSS and are being maintained.
X       Review RM-77, Final Status Survey Implementation, to verify that methods, techniques, and survey activities required for FSS have been applied in accordance with the appropriate procedures.
1.2          Field QC Records:
X        Review all assessments, Condition Reports and audits to ensure that identified issues have been resolved.
Comments:
____    Verify scan instrumentation was in calibration and the QC source checks were performed prior to and after surveys.
_Verify          daily QC source checks for Canberra gamma spectroscopy detector properly logged prior to soil sample analysis.
1.3          Review Verification:
7'        Verify that the Data Quality Objectives are complete.
  *        .. Verify that the survey design has been technically reviewed.
RM-78.doc
 
RM-78                                                                        Revision 2 FINAL STATUS SURVEY ASSESSMENT                                          Page 20 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 2 of 8 Verify that gamma spectroscopy results have received a technical review.
Verify the Sample and Analysis Report (RM-59-1) is completed and reviewed.
Data Verilfication Completed:            No Comments Assessor                  Dafe RM-78.doc
 
RM-78                                                                          Revision 2 FINAL STATUS SURVEY ASSESSMENT                                              Page 21 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 3 of 8 2.0      DATA VALIDATION 2.1      Documentation Review:
Perform documentation review for quality control purposes and validate the data collected is complete and appropriate for use as defined by the survey design. Documentation includes:
Field measurement records Chain-of-custody Quality Control (QC) measurement records Current qualification of survey personnel Corrective Action Reports Data inputs (laboratory spectroscopy)
Sample preparation techniques 2.2      Detection Limit Review:
___    Scan MDCs are below established site DCGLs.
X/    Forced-count values are assigned as necessary when activity is not detected in a sample.
ffi      Minimum Detectable Concentration (MDC) values of gamma spectroscopy are below established DCGLs.
2.3      Quality Control (QC) Data Review:
Quality Control (QC) data results have received required reviews and are complete and consistent.
4      Results of judgmental samples have been reviewed and evaluated.
4*    Review to ensure that the analytical results of judgmental samples do not impact the evaluation for unrestricted release of the survey area.
RM-78.doc
 
RM-78                                                                            Revision 2 FINAL STATUS SURVEY ASSESSMENT                                              Page 22 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 4 of 8 2.4      Qualification of Data:
Statistical radionuclide-specific measurements for completeness. Evaluate the survey for determination of data usability and confirm that sufficient qualified data are present for the decision process.
: a.      Total number of statistical samples planned for the survey:
: b.      Total number of statistical samples determined as valid:    /
b x120
: c.      Calculate % Completeness:                      -/,-"  ()&#xfd;0    --
a
_zQualified data are A 00% completeness and are sufficient to support the Sign Test requirement for determination of unrestricted release.
Data Validation Completed:                  No Comments:
A~s'ses'so r                  Date RM-78.doc
 
RM-78                                                                            Revision 2 FINAL STATUS SURVEY ASSESSMENT                                                Page 23 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 5 of 8 3.0      DATA QUALITY ASSESSMENT 3.1      Review the DQOs and Survey Design:
X1      Confirm that all inputs to the decision have been reviewed and are complete.
Z1*    Verify that boundaries or constraints identified in the survey area have not affected the quality of the data.
Review the Statement of Hypothesis and confirm that it remains relevant.
__    Confirm that Type I and Type IIerror limits are consistent with DQOs.
J      Confirm that the survey design is consistent with DQOs and that the appropriate number of data points were obtained.
3.2      Preliminary Review:
3.2.1    Preliminary Evaluation:
Quality Assessment (QA) reports consistent with procedure RM-79, Final Status Survey Quality Control.
v/    Survey is of sufficient intensity to satisfy classification requirement.
__    Potential trends of radioactivity levels in the survey area do not impact a decision for unrestricted release.
Comments:
RM-78.doc
 
RM-78                                                                          Revision 2 FINAL STATUS SURVEY ASSESSMENT                                              Page 24 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 6 of 8 3.2.2    Calculate Basic Statistical Quantities:
: a.      Number of qualified data points
: b.      Calculation of the Mean                O2ocOV
: c.      Calculation of the Median
: d.      Calculation Standard Deviation Attach graphic representation of the data if any radionuclide-specific measurements exceed 50% of the DCGL.
Sample QA/QC measurements consistent with FSS data 3.3      Statistical Evaluation:
NOTE:      If all measurement data are less than the DCGLw, statistical testing in not required and the survey unit meets the regulatory requirement for unrestricted release.
            .wj" All survey measurements are below the DCGLw.
3.3.1    Verify Assumptions of the Survey Design
              -__ Review the posting plot to verify that the data exhibits spatial independence. Spatial trends must be investigated and resolved prior to further assessment.
_    Review to verify dispersion symmetry. The appearance of skewed data must be investigated for cause and documented prior to further assessment.
RM-78.doc
 
RM-78                                                                        Revision 2 FINAL STATUS SURVEY ASSESSMENT                                            Page 25 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 7 of 8 X/      Review the dataset standard deviation and range for data variance.
Questionable data must be investigated for cause and documented prior to further assessment.
_      Verify that the data exhibits adequate power and confirm that the sample size is sufficient to satisfy the DQOs.
3.4      Draw Conclusions from the Data:
3.4.1    Investigation Levels and Response Actions Determine if data results have exceeded any inyestiation level.
Document findings.
3.4.2    Evaluation for Unrestricted Release Select applicable conclusion:
Survey area acceptance criteria met and survey area satisfies the requirements for unrestricted release:
___      All concentrations are less than the DCGLw. The Null Hypothesis is rejected.
The mean concentration of the survey area is below the DCGLw but individual measurements in the survey unit exceed the DCGLw. The Sign Test and EMC evaluation are successful and the Null Hypothesis is rejected.
RM-78.doc
 
RM-78                                                                        Revision 2 FINAL STATUS SURVEY ASSESSMENT                                          Page 26 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 8 of 8
_A4L Survey area acceptance criteria not met and survey area fails to satisfy the requirements for unrestricted release:
: 4. The mean concentration in the survey area exceeds the DCGLw. and the null hypothesis is confirmed.
The mean concentration of the survey area is below the DCGLw but individual measurements in the Unit exceed the DCGLw..
The Sign Test and EMC evaluation are unsuccessful and the null hypothesis is confirmed.
Data Quality Assessment Completed:        O*No W)
Comments Assessor                    Date Reviews:
Technical Oview                      bate ES Superintendent                    Date RlM&ES Manager                      Date RM-78.doc


===1.2 Field===
RM-78-3, Attachment I Statistical Quantities Release Record TBCx1 51 Relocated Soil from Containment/Turbine Building Demolition Area Sample              Cs-I 37            Co-60        Weighted        **Weighted Sum Number            (pCi/gm)          (pCi/gm)        Sum (SOR)            <DCGLw?          DCGL-W. Sum Sign 1               0.0694            0.0121          0.0096                yes            0.9904    +1 2               0.0431            0.0065          0.0056                yes            0.9944    +1 3                0.0391            0.0283          0.0121                yes            0.9879    +1 4                0.0299            -0.0181        -0.0031                yes            0.9969    +1 5                0.0190            -0.0144        -0.0029                yes            0.9971    +1 6                0.0256            0.0002          0.0022                yes            0.9978    +1 7                0.0332            0.0000          0.0028                yes            0.9972    +1 8               0.0442            -0.0209        -0.0028                yes            0.9972    +1 9                0.0183            0.0151          0.0062                yes            0.9938    +1 10              -0.0020            -0.0016        -0.0007                yes            0.9993    +1 11                0.0212            0.0003          0.0019                yes            0.9981    +1 12                0.0312            0.0206          0.0090                yes            0.9910    +1 13                0.0706            0.0144          0.0104                yes            0.9896    +1 14                0.0427            0.0319          0.0135                yes            0.9865    +1 15                0.0458            -0.0087          0.0011                yes            0.9989    +1 Std. Dev            0.0189            0.0161          0.0056 Mean              0.0354            0.0044          0.0043 Median              0.0332            0.0003          0.0028 Number of Positive Differences (S+):        n/a Critical Value, k, Table 1.3 of Marssim:        n/a S+ >thank?:          n/a Survey Unit Pass or Fail:
QC Records: X Review all assessments, Condition Reports and audits to ensure that identified issues have been resolved.Comments:____ Verify scan instrumentation was in calibration and the QC source checks were performed prior to and after surveys._Verify daily QC source checks for Canberra gamma spectroscopy detector properly logged prior to soil sample analysis.1.3 Review Verification:
                                                        **Pass
7' Verify that the Data Quality Objectives are complete.* ..Verify that the survey design has been technically reviewed.RM-78.doc RM-78 FINAL STATUS SURVEY ASSESSMENT Revision 2 Page 20 of 26 Data Veril RM-78-3 DATA ASSESSMENT REPORT Page 2 of 8 Verify that gamma spectroscopy results have received a technical review.Verify the Sample and Analysis Report (RM-59-1) is completed and reviewed.fication Completed:
*Note: Forced-Count values are used for samples with activity levels below the MDA.
No Comments Assessor Dafe RM-78.doc RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 21 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 3 of 8 2.0 DATA VALIDATION
**Note: If all measurement data are less than the DCGL w, then the Sign Test is not required.


===2.1 Documentation===
I.  .
RM-79                                                                      Revision I FINAL STATUS SURVEY QUALITY CONTROL                                    Page 11 of 13 RM-79-1 FSS QUALITY CONTROL EVALUATION RESULTS FSS Package #        -                              QC Package #
QC Measurement Type            Acceptance Criteria Met*?    Reference
: 1. Replicate Scan                    --;/ No            Step 5.1.3
: 2. Sample Recounts                                      Step 5.1.4.1
: a. In-house
* No
    ,            b. Third party                  Yes / No
: 3. Split Samples                                        Step 5.1.4.2
: c. In-house                                No 4,.,L/A      d. Third party                  Yes / No
*NOTE: IfAcceptance Criteria is not met, completion of Attachment RM-79-2, FSS Quality Control Investigation Results, is required.
Comments:        Q A                  44q                -      4,4 1
_-i
                                                                /
Reviews:
Date
          ,Evaluator Technical Review                    Date RM-79.doc


Review: Perform documentation review for quality control purposes and validate the data collected is complete and appropriate for use as defined by the survey design. Documentation includes: Field measurement records Chain-of-custody Quality Control (QC) measurement records Current qualification of survey personnel Corrective Action Reports Data inputs (laboratory spectroscopy)
QA Verification Split Sample Analysis Table 1 Date:                9/25/2006                                                            Acceptance Criteria Resolution      Ratio QA:                   TBC.,gl Excavated Soil from Contain. Bldg. Area                        <4            N/A 4-7        0.5-2.0 Type:                Split Sample                                                          8-15        0.6-1.66 16-50      0.75-1.33 Lab:                 In- House                                                          51-200        0.8-1.25
Sample preparation techniques
                                                                                              >200        0.85-1.18 A            B              C              D          E        F        G RP BResults                                                                                                in Sample              Radionuclide          Result Below          Results      % Error        BRP Resolution  Acceptancetio  Recount  Recount  Comparison Agreement Result                        Compare MDA            (pCi/g)      (Sigma)                    (Table 1)  Belo        (pCi/g)    F/A      CowphrD MABelow                                                MDA                      G with D) 2                  Co-60                <            0.0754          n/a          n/a            n/a        <      0.0588    0.78      YES 2                  Cs-137                            0.0431        46.17          2.17            n/a        <      0.0605    1.40      YES Resolution        C=()t Indicates results less than the MDA.
*Note      Results are consideredin agreement for MDA and near-MDA measurementcomparisons Results fihat fail agreement must be investigatedper RM-79.


===2.2 Detection===
QA Verification Sample Recount Analysis Table I Date:                9/25/2006                                                        Acceptance Criteria Resolution        Ratio QA:                  TBC,,.l Excavated Soil from Contain. Bldg. Area                    <4            N/A 4-7          0.5-2.0 Type:                Sample Recounts                                                  8-15        0.6-1.66 16-50        0.75-1.33 Lab:                  In- House                                                      51-200        0.8-1.25
                                                                                          >200        0.85-1.18
                                                                                            ~t A        B              C              D          E        F      G RP BResults                                                                                      in Sample              Radionuclide          Result          Results  % Error        BRP            Ratio      Recount  Results Ratio Agreement Below                    (Sigma)      Resolution              1'  Result  (pCi/g)  F/A  Compare MDA                                                              Below MDA                G with D) 4                    Co-60            <            0.0387      n/a          n/a            n/a          <    0.0641  1.66    YES 4                  Cs-137            <            0.0568      n/a          n/a            n/a          <    0.0568  1.00    YES 7                    Co-60              <          0.0541      n/a          n/a            n/a          <    0.0442  0.82    YES 7                  Cs-137                          0.0332    44.44          2.25            n/a          <    0.0547  1.65    YES Resolution      C          A)(aZ O
<Indicates results less than the MDA.
*Note Results are consideredin agreement for MDA and near-MDA measurementcomparisons Results Ithat fail agreementmust be investigatedper RM-79.


Limit Review:___ Scan MDCs are below established site DCGLs.X/ Forced-count values are assigned as necessary when activity is not detected in a sample.ffi Minimum Detectable Concentration (MDC) values of gamma spectroscopy are below established DCGLs.2.3 Quality Control (QC) Data Review: Quality Control (QC) data results have received required reviews and are complete and consistent.
n S -, 5'-
4 Results of judgmental samples have been reviewed and evaluated.Review to ensure that the analytical results of judgmental samples do not impact the evaluation for unrestricted release of the survey area.RM-78.doc RM-78 FINAL STATUS SURVEY ASSESSMENT Revision 2 Page 22 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 4 of 8 2.4 Qualification of Data: Statistical radionuclide-specific measurements for completeness.
Tritium in Soil Data Results Final Status SurveyTBC, 15 1 Sample              Tritium in Soil Number                    pCi/g 2                     0.007 4                     0.006 7                      0.004 Mean:        0.0060 Median:       0.0060 St. Dev:     0.0010 Note: The DCGL for Tritium is 327 pCi/g.
Evaluate the survey for determination of data usability and confirm that sufficient qualified data are present for the decision process.a. Total number of statistical samples planned for the survey: b. Total number of statistical samples determined as valid: /c. Calculate
Sample results are less than 0.2% of the DCGL
% Completeness:
b x120 a-/,-" ()&#xfd; 0 --_zQualified data are A 00% completeness and are sufficient to support the Sign Test requirement for determination of unrestricted release.Data Validation Completed:
No Comments: A~s'ses'so r Date RM-78.doc RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 23 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 5 of 8 3.0 DATA QUALITY ASSESSMENT


===3.1 Review===
    -Environmental,                               Inc.
the DQOs and Survey Design: X1 Confirm that all inputs to the decision have been reviewed and are complete.Verify that boundaries or constraints identified in the survey area have not affected the quality of the data.Review the Statement of Hypothesis and confirm that it remains relevant.__ Confirm that Type I and Type II error limits are consistent with DQOs.J Confirm that the survey design is consistent with DQOs and that the appropriate number of data points were obtained.3.2 Preliminary Review: 3.2.1 Preliminary Evaluation:
Midwest Laboratory an Aliegheny Technologies Co.
Quality Assessment (QA) reports consistent with procedure RM-79, Final Status Survey Quality Control.v/ Survey is of sufficient intensity to satisfy classification requirement.
700 Landwehr Road
__ Potential trends of radioactivity levels in the survey area do not impact a decision for unrestricted release.Comments: RM-78.doc RM-78 FINAL STATUS SURVEY ASSESSMENT RM-78-3 DATA ASSESSMENT REPORT Page 6 of 8 3.2.2 Calculate Basic Statistical Quantities:
* Northbrook, IL60062-2310 ph. (847) 564-0700 . fax (847) 564-4517 Mr. David W. Parish                                                   LABORATORY REPORT NO.               8022-100-243 Big Rock Point                                                           DATE:                               10-02-2006 10269 US-31 North                                                       SAMPLES RECEIVED:                   09-27-2006 Charlevoix, MI 49720                                                     PURCHASE ORDER NO:
: a. Number of qualified data points Revision 2 Page 24 of 26 b. Calculation of the Mean c. Calculation of the Median d. Calculation Standard Deviation O2ocOV 3.3 Attach graphic representation of the data if any radionuclide-specific measurements exceed 50% of the DCGL.Sample QA/QC measurements consistent with FSS data Statistical Evaluation:
Below are the results of the analyses for tritium on three soil samples.
NOTE: If all measurement data are less than the DCGLw, statistical testing in not required and the survey unit meets the regulatory requirement for unrestricted release..wj" All survey measurements are below the DCGLw.Verify Assumptions of the Survey Design-__ Review the posting plot to verify that the data exhibits spatial independence.
Excavated Soil Survey TBCx1 5-1 Sample                                 Collection             Lab           Concentration           MDA Description                                   Date             Code           (pCi/g of soil)       (pCi/g of soil)
Spatial trends must be investigated and resolved prior to further assessment.
H-3 2                                         09-25-06           BRSO-6591       0.007 +/- 0.006             < 0.011 4                                         09-25-06           BRSO-6592       0.006 +/- 0.006             < 0.010 7                                         09-25-06           BRSO-6593       0.004 +/- 0.005             < 0.010 The error given is the probable counting error at 95 % confidence level. The less than, (<), value is based on 4.66 sigma counting error for background sample.
_ Review to verify dispersion symmetry.
Sincerely, Bronia Grob, Laboratory Manager
The appearance of skewed data must be investigated for cause and documented prior to further assessment.
                                                                                      -x APPROVED BY Tony Coorlim, Quality Assurance}}
3.3.1 RM-78.doc RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 25 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 7 of 8 X/ Review the dataset standard deviation and range for data variance.Questionable data must be investigated for cause and documented prior to further assessment.
_ Verify that the data exhibits adequate power and confirm that the sample size is sufficient to satisfy the DQOs.3.4 Draw Conclusions from the Data: 3.4.1 Investigation Levels and Response Actions Determine if data results have exceeded any inyestiation level.Document findings.3.4.2 Evaluation for Unrestricted Release Select applicable conclusion:
Survey area acceptance criteria met and survey area satisfies the requirements for unrestricted release:___ All concentrations are less than the DCGLw. The Null Hypothesis is rejected.The mean concentration of the survey area is below the DCGLw but individual measurements in the survey unit exceed the DCGLw. The Sign Test and EMC evaluation are successful and the Null Hypothesis is rejected.RM-78.doc RM-78 FINAL STATUS SURVEY ASSESSMENT Revision 2 Page 26 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 8 of 8_A4L Survey area acceptance criteria not met and survey area fails to satisfy the requirements for unrestricted release: 4. The mean concentration in the survey area exceeds the DCGLw. and the null hypothesis is confirmed.
The mean concentration of the survey area is below the DCGLw but individual measurements in the Unit exceed the DCGLw..The Sign Test and EMC evaluation are unsuccessful and the null hypothesis is confirmed.
Data Quality Assessment Completed:
Comments W)Assessor Reviews: Technical Oview ES Superintendent RlM&ES Manager Date bate Date Date RM-78.doc RM-78-3, Attachment I Statistical Quantities Release Record TBCx 1 5 1 Relocated Soil from Containment/Turbine Building Demolition Area Sample Cs-I 37 Co-60 Weighted **Weighted Sum Number (pCi/gm) (pCi/gm) Sum (SOR) <DCGLw? DCGL-W. Sum Sign 1 0.0694 0.0121 0.0096 yes 0.9904 +1 2 0.0431 0.0065 0.0056 yes 0.9944 +1 3 0.0391 0.0283 0.0121 yes 0.9879 +1 4 0.0299 -0.0181 -0.0031 yes 0.9969 +1 5 0.0190 -0.0144 -0.0029 yes 0.9971 +1 6 0.0256 0.0002 0.0022 yes 0.9978 +1 7 0.0332 0.0000 0.0028 yes 0.9972 +1 8 0.0442 -0.0209 -0.0028 yes 0.9972 +1 9 0.0183 0.0151 0.0062 yes 0.9938 +1 10 -0.0020 -0.0016 -0.0007 yes 0.9993 +1 11 0.0212 0.0003 0.0019 yes 0.9981 +1 12 0.0312 0.0206 0.0090 yes 0.9910 +1 13 0.0706 0.0144 0.0104 yes 0.9896 +1 14 0.0427 0.0319 0.0135 yes 0.9865 +1 15 0.0458 -0.0087 0.0011 yes 0.9989 +1 Std. Dev Mean Median 0.0189 0.0354 0.0332 0.0161 0.0044 0.0003 Number of Positive Differences (S+): Critical Value, k, Table 1.3 of Marssim: S+ >thank?: Survey Unit Pass or Fail: 0.0056 0.0043 0.0028 n/a n/a n/a**Pass*Note: Forced-Count values are used for samples with activity levels below the MDA.**Note: If all measurement data are less than the DCGL w, then the Sign Test is not required.
I ..RM-79 FINAL STATUS SURVEY QUALITY CONTROL Revision I Page 11 of 13 RM-79-1 CONTROL EVALUATION RESULTS FSS QUALITY FSS Package # -QC Package #QC Measurement Type Acceptance Criteria Met*? Reference 1. Replicate Scan --;/ No Step 5.1.3 2. Sample Recounts Step 5.1.4.1 a. In-house No , b. Third party Yes / No 3. Split Samples Step 5.1.4.2 c. In-house No 4,.,L/A d. Third party Yes / No*NOTE: If Acceptance Criteria is not met, completion of Attachment RM-79-2, FSS Quality Control Investigation Results, is required.Comments:
Q 44q -4,4 1 A_-i/Reviews: ,Evaluator Technical Review Date Date RM-79.doc QA Verification Split Sample Analysis Date: QA: Type: Lab: 9/25/2006 TBC.,gl Excavated Soil from Contain. Bldg. Area Split Sample In- House Table 1 Acceptance Criteria Resolution Ratio<4 N/A 4-7 0.5-2.0 8-15 0.6-1.66 16-50 0.75-1.33 51-200 0.8-1.25>200 0.85-1.18 C D A B E F G RP BResults in Sample Radionuclide Result Results % Error BRP Acceptancetio Recount Recount Comparison Agreement Below Resolution Result Compare MDA (pCi/g) (Sigma) (Table 1) Belo (pCi/g) F/A CowphrD MABelow MDA G with D)2 Co-60 < 0.0754 n/a n/a n/a < 0.0588 0.78 YES 2 Cs-137 0.0431 46.17 2.17 n/a < 0.0605 1.40 YES Resolution C=()t Indicates results less than the MDA.*Note Results are considered in agreement for MDA and near-MDA measurement comparisons Results fihat fail agreement must be investigated per RM-79.
QA Verification Sample Recount Analysis Date: QA: 9/25/2006 TBC,,.l Excavated Soil from Contain. Bldg. Area Type: Sample Recounts Table I Acceptance Criteria Resolution Ratio<4 N/A 4-7 0.5-2.0 8-15 0.6-1.66 16-50 0.75-1.33 51-200 0.8-1.25>200 0.85-1.18~t Lab: In- House A B C D E F G RP BResults in Sample Radionuclide Result Results % Error BRP Ratio Recount Results Ratio Agreement Below (Sigma) Resolution 1' Result (pCi/g) F/A Compare MDA Below MDA G with D)4 Co-60 < 0.0387 n/a n/a n/a < 0.0641 1.66 YES 4 Cs-137 < 0.0568 n/a n/a n/a < 0.0568 1.00 YES 7 Co-60 < 0.0541 n/a n/a n/a < 0.0442 0.82 YES 7 Cs-137 0.0332 44.44 2.25 n/a < 0.0547 1.65 YES Resolution C A)(aZ O< Indicates results less than the MDA.*Note Results are considered in agreement for MDA and near-MDA measurement comparisons Results Ithat fail agreement must be investigated per RM-79.
n S -, 5'-Tritium in Soil Data Results Final Status SurveyTBC, 1 5 1 Sample Tritium in Soil Number pCi/g 2 0.007 4 0.006 7 0.004 Mean: Median: St. Dev: 0.0060 0.0060 0.0010 Note: The DCGL for Tritium is 327 pCi/g.Sample results are less than 0.2% of the DCGL
-Environmental, Inc.Midwest Laboratory an Aliegheny Technologies Co.700 Landwehr Road
* Northbrook, IL 60062-2310 ph. (847) 564-0700 .fax (847) 564-4517 Mr. David W. Parish LABORATORY REPORT NO. 8022-100-243 Big Rock Point DATE: 10-02-2006 10269 US-31 North SAMPLES RECEIVED:
09-27-2006 Charlevoix, MI 49720 PURCHASE ORDER NO: Below are the results of the analyses for tritium on three soil samples.Excavated Soil Survey TBCx 1 5-1 Sample Collection Lab Concentration MDA Description Date Code (pCi/g of soil) (pCi/g of soil)H-3 2 09-25-06 BRSO-6591 0.007 +/- 0.006 < 0.011 4 09-25-06 BRSO-6592 0.006 +/- 0.006 < 0.010 7 09-25-06 BRSO-6593 0.004 +/- 0.005 < 0.010 The error given is the probable counting error at 95 % confidence level. The less than, (<), value is based on 4.66 sigma counting error for background sample.Sincerely, Bronia Grob, Laboratory Manager-x APPROVED BY Tony Coorlim, Quality Assurance}}

Latest revision as of 18:36, 13 March 2020

Transmittal of Survey Packages in Support of Big Rock Point Phased License Termination
ML070600673
Person / Time
Site: Big Rock Point  File:Consumers Energy icon.png
Issue date: 10/24/2006
From: Haas K
Consumers Energy
To:
Document Control Desk, NRC/FSME
References
Download: ML070600673 (161)
v • d • e


Text

ConsursEneWj A CMS Energy Company Big Rock Point Nuclear Plant Kurt A. Haas 10269 US-31 North General Manager Charlevoix, MI 49720 October 24, 2006 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 DOCKETS 50-155 AND 72-043 - LICENSE DPR BIG ROCK POINT PLANT -

TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION

References:

1. U.S. NRC to Big Rock Point dated March 24, 2005, Big Rock Point - Issuance of Amendment 126 to Approve the License Termination Plan (TAC No. L52096)
2. Big Rock Point to U.S. NRC dated September 27, 2005, Revision 2 of the Big Rock Point License Termination Plan
3. Big Rock Point to U.S. NRC dated April 3, 2006, Letter of Intent Concerning the Release of Part of the Big Rock Point Site Property from the 10 CFR Part 50 License.
4. U.S. NRC to Big Rock Point dated April 25, 2006, Report of April 12, 2006 Meeting to Discuss Partial Site Release and Final Status Survey Report Content
5. Big Rock Point to U.S. NRC dated August 24, 2006, Transmittal of Excavated Surface Surveys, Relocated Soil Surveys and Final Status Survey Packages in Support of Big Rock Point Phased License Termination
6. Big Rock Point to U.S. NRC dated September 19, 2006, Transmittal of Relocated Soil Survey Packages in Support of Big Rock Point Phased License Termination
7. Big Rock Point to U.S. NRC dated October 9, 2006, Transmittal of Survey Packages in Support of Big Rock Point Phased License Termination
8. Big Rock Point to U.S. NRC dated October 10, 2006, Transmittal of Survey Packages in Support of Big Rock Point Phased License Termination
9. Big Rock Point to U.S. NRC dated October 13, 2006, Transmittal of Survey Packages in Support of Big Rock Point Phased License Termination Attachment I contains a matrix of Final Status Survey (FSS) record numbers, survey area descriptions, and review status. This attachment is a revision to attachment of our letter dated October 13, 2006. It contains a list of the final status survey release records expected to be submitted in support of our FSS report. This FSS report is expected to be submitted on or around the fifteenth of November. Also attached, are the following survey release records:

CLASS 1 FINAL STATUS SURVEY RELEASE RECORDS

  • North West Protected Area (Attachment 2)
  • Central Protected Area (Attachment 3)
  • South Central Protected Area (Attachment 4)

CLASS 1 RELOCATED SOIL SUPPORTING SURVEY RECORD

  • Relocated Soils from Turbine Building/Containment Demolition (Attachment 5)

These records are being provided to facilitate U.S. Nuclear Regulatory Commission review, as discussed in our April 12, 2006 meeting. Attachments 2,Lnd 3 to this letter comprise those portions of survey packages which may be of use for final review and will be summarized in our FSS report.

The phased release approach is described in Sections 1.4.2 and 5.1.2 of the BRP License Termination Plan (LTP). BRP intends to release site land from the 10 CFR Part 50 license using this phased approach. The first phase includes the majority of the site land scheduled for release after all demolition, remediation and FSS activities associated with plant operation are complete.

BRP LTP Chapter 5 commits BRP to producing FSS package(s) for each survey area and outlines the contents of each supporting survey package.

The intended partial site release supports the process of license termination by demonstrating that an additional portion of the remaining site lands can be released from the Site license. This letter, along with completed and future on-site inspections and letters, provides documentation that demolition activities have been performed in accordance with the LTP.

Your timely review of FSS information and approval of our request to release the associated land is particularly important to the project and smooth transition to an Independent Spent Fuel Storage Installation (ISFSI)-only operation.

If you have any questions or comments on these reports, please contact Ken Pallagi, Radiation Protection and Environmental Services Manager at 231-547-8416.

Kurt M. Haas Site General Manager ATTACHMENTS 2 cc: Administrator, Region Il, USNRC (w/o Attachments)

NRC Decommissioning Inspector, Big Rock Point (w/o Attachments)

NRC NMSS Project Manager, James Shepherd (w/o Attachments)

NRC NMSS FSS Reviewer, Bruce Watson Michigan Department of Environmental Quality, Thor Strong (w/o Attachments)

ATTACHMENT I CONSUMERS ENERGY BIG ROCKPO1NT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION MATRIX OF FSS SUPPORTING DOCUMENTATION October 24, 2006 5 Pages

MATRIX OF BIG ROCK POINT FINAL STATUS SURVEY REPORTS SURVEY RECORD2 PACKAGE U.S. NRC PACKAGE LETTER AREA' NUMBER SURVEY AREA DESCRIPTION SIGNOFF REVIEW REVIEW DATE DATE METHOD DATE CLASS 1 AREAS - FINAL STATUS SURVEY OF SURFACES I 01Ci1 Class I Final Status Release Record, South West Protected Area 10/11/06 Letter 10/13/06 2 02C1 1 Class IFinal Status Release Record, West Central Protected Area 10/11/06 Letter 10/13/06 3 03C, I Class IFinal Status Release Record, North West Protected Area 10/16/06 Letter 10/24/06 4 04C,1 Class IFinal Status Release Record, North Central Protected Area 10/04/06 Letter 10/10/06 5 05C 1I Class IFinal Status Release Record, Central Protected Area 10/16/06 Letter 10/24/06 6 06C, 1 Class 1 Final Status Release Record, South Central Protected Area 10/23/06 Letter 10/24/06 7 07C, I Class IFinal Status Release Record, South East Protected Area 8 08C, 1 Class IFinal Status Release Record, East Central Protected Area 9 09C 1 I Class I Final Status Release Record, North East Protected Area 10/04/06 Letter 10/13/06 10 10C 1 Class I Final Status Release Record, East Protected Area III North 1IC 1 Class IFinal Status Release Record, North Radwaste Staging Area 11 South] 1C, 1 Class IFinal Status Release Record, South Radwaste Staging Area On-Site Inspection 06/13-14/06 10/9/06 15 15(2R)C 1I Class IFinal Status Release Record, Woods Road Storage Area 05/23/06 and LetterIsetn 0/ 146090 20 20C, I Class IFinal Status Release Record, East Radwaste Staging Area 23 23C,1 Class IFinal Status Release Record, North Protected Area 10/05/06 Letter 10/10/06 24 24C, I Class IFinal Status Release Record, South Protected Area Inspection DiscargeOn-Site Discharge 4 Canal C, 1 Class I Final Status Survey, Discharge Canal 01/27/05 On-Site 06/13-14/06 10/9/06 Canal _____________________________________________and Letter_______________

CLASS 1 AREAS- EXCAVATED SOIL FINAL STATUS SURVEYS' 2 02Cxj I Class I Final Status Survey, Excavated Soil from Retention Pond 10/13/2004 On-Site Inspection 06/13-14/06 10/9/06 Construction and Letter 8 08Cxl Class I Final Status Survey, Excavated Soil from Turbine Building 05/16/05 On-Site Inspection 06/13-14/06 10/9/06 Subfloor and Letter On-Site Inspection 10/9/06 Area 1 Final Status Survey, Excavated Soil from Screenhouse 9 09Cxj 1 Class 12/09/04 and Letter 06/13-14/06 9 09CX21 Area I Final Status Survey, Excavated Soil from Screenhouse Class 12/08/04 On-Site and letterInspection 06/13-14/06 10/9/06 1 Survey Area Map - Big Rock Point License Termination Plan, Chapter 5, figure 5-3, Initial Land Area Survey Units 2 Record Number nomenclature is defined in Procedure RM-76, Final Status Survey Design, step 6.2, Survey Unit Nomenclature 3 Surface of survey unit 11 was divided into North and South areas due to intermediate use of land between the quarry survey and the final surface survey (served as solid Radwaste storage yard in interim.)

4 Discharge Canal is North East of the Protected Area 5 Soils removed from Class I Area excavations Page 1 of 5

MATRIX OF BIG ROCK POINT FINAL STATUS SURVEY REPORTS SURVEY RECORD2 PACKAGE U.S. NRC PACKAGE LETTER AREA' NUMBER SURVEY AREA DESCRIPTION SIGNOFF REVIEW REVIEW DATE DATE METHOD DATE 12/09/04 On-Site Inspection 06/13-14/06 10/9/06 9 0 Area I Final Status Survey, Excavated Soil from Screenhouse Class and letter 9 09CX41 Class 1 Final Status Survey, Excavated Soil from Screenhouse 12/09/04 On-Site Inspection 06/13-14/06 10/9/06 Area and letter 9 Class I Final Status Survey, Excavated Soil from Screenhouse 12/14/04 On-Site Inspection 06/13-14/06 10/9/06 9 09CX61 Class I Final Status Survey, Excavated Soil from Screenhouse Area 01/19/05 and LetterInspection On-Site 06/13-14/06 10/9/06 9 09CX1 Class I Final Status Survey, Excavated Soil from Screenhouse 05/16/05 On-Site Inspection 06/13-14/06 10/9/06 Area and Letter II Cx Class I Final Status Survey, Excavated Soil from Radwaste 10/13/04 On-Site Inspection 06/13-14/06 10/9/06 Storage Vaults and Letter Slurry6 Wall Cxurr Slurry Wal Wall Constructiona Class I Final SttuSreyEcaaedSo__rmluryWll_2080 Status Survey, Excavated Soil from Slurry Wall 12/08/04 On-SiteInspection On-Site Inspection 06/13-14/06__

06/13-14/06 10/9/06__

10/9/06 Cxjl Construction and Letter Slurry Wall Slurry Wall Class I Final Status Survey, Excavated Soil from Slurry Wall 12/20/04 On-Site Inspection 06/13-14/06 10/9/06 Cx 2 1 Construction and Letter Turbine Class I Supporting Survey- Soil Excavated from Turbine Building On-Site Inspection Building7 TBCxj I Demolition Area, Supporting Subsurface Structure and Component 08/24/05 and Letter 06/13-14/06 10/9/06 Removal Turbine Class I Supporting Survey- Soil Excavated from Turbine Building On-Site Inspection 10/13/05 and Letter 06/13-14/06 10/9/06 Building TBCx21 Demolition Area, Supporting Subsurface Structure and Component Removal Turbine Class I Supporting Survey- Soil Excavated from Turbine Building On-Site Inspection 11/23/05 and Letter 06/13-14/06 10/9/06 Building TBCX31 Demolition Area, Supporting Subsurface Structure and Component Removal Turbine Class I Supporting Survey- Soil Excavated from Turbine Building On-Site Inspection Demolition Area, Supporting Subsurface Structure and Component 11/23/05 and Letter 06/13-14/06 10/9/06 Building TBCX41 Removal Turbine Class I Supporting Survey- Soil Excavated from Turbine Building On-Site Inspection Demolition Area, Supporting Subsurface Structure and Component 01/06/06 and Letter 06/13-14/06 10/9/06 Building TBCx5I Removal Turbine Class I Supporting Survey- Soil Excavated from Turbine Building On-Site Inspection 07/03/06 and Letter 06/13-14/06 10/9/06 Building TBCX61 Demolition Area, Supporting Subsurface Structure and Component Removal Turbine Class 1 Supporting Survey- Soil Excavated from Turbine Building On-Site Inspection 07/05/06 and Letter 06/13-14/06 10/9/06 Building TBCX71 Demolition Area, Supporting Subsurface Structure and Component Removal 6 Slurry Wall crossed several survey areas on the ease, south, and west sides of the protected area.

7 Turbine building excavation was beneath survey areas 5, 6, and 8 Page 2 of 5

MATRIX OF BIG ROCK POINT FINAL STATUS SURVEY REPORTS SURVEY RECORD' PACKAGE U.S. NRC PACKAGE LETTER AREA' NUMBER SURVEY AREA DESCRIPTION SIGNOFF REVIEW REVIEW DATE DATE METHOD DATE Turbine TBCxg1 Class I Supporting Survey- Relocated Soil from Turbine 07/03/06 On-Site Inspection 06/13-14/06 10/9/06 Building Building/Containment Demolition and Letter Turbine TBCx91 Class I Supporting Survey - Relocated Soil from Turbine 07/03/06 On-Site Inspection 06/13-14/06 10/9/06 Building Building/Containment Demolition and Letter Turbine TBCxj01 Class 1 Relocated Soil Supporting Survey Release Record - 08/03/06 Letter 8/24/06 Building Bx 1 I Relocated Soils from Turbine Building/Containment Demolition ________________

Turbine Class I Relocated Soil Supporting Survey Release Record - 08/14/06 Letter 8/24/06 Building TBCx,1 I Relocated Soils from Turbine Building/Containment Demolition Turbine TB~x121 Class I Relocated Soil Supporting Survey Release Record - 9/6/06 Letter 9/20/06 Building Relocated Soils from Turbine Building/Containment Demolition Turbine TBCx131 Class I Relocated Soil Supporting Survey Release Record - 9/6/06 Letter 9/20/06 Building Relocated Soils from Turbine Building/Containment Demolition Turbine TBCx141 Class 1 Relocated Soil Supporting Survey Release Record - 09/15/06 Letter 10/10/06 Building TBCx 41 Relocated Soils from Turbine Building/Containment Demolition Turbine Class I Relocated Soil Supporting Survey Release Record - 10/23/06 Letter 10/24/06 Building BRelocated Soils from Turbine Building/Containment Demolition CLASS 1 AREAS - FINAL STATUS SURVEY - SUBSURFACE (QUARRY) On-Site Inspection 06/13-14/06 10/9/06 09Cq1 I Class I Final Status Survey, Screenhouse Area Excavation 12/20/04 and Letter Isetn 0/ 146090 11 11 Cq I Class I Final Status Survey, Solid Radwaste Storage Area 10/13/04 On-Site Inspection 06/13-14/06 10/9/06 Excavation and Letter Containment8 CSCqj I Excavated Surface Supporting Survey Release Record - Base 08/03/06 Letter 8/24/06 Elevation Survey of Containment Structure Excavation Circulating CWCqj Excavated Surface Supporting Survey Release Record - Base 08/07/06 Letter 8/24/06 Water Piping Elevation Survey of Circulating Water Piping Excavation Turbine East TBCqj I Class 1 Final Status Release Record, Turbine Building East 03/30/06 Letter 4/03/06 Building Excavation Surface Turbine Excavated Surface Supporting Survey Release Record - Base West TBCq1 1 Elevation Survey of the Turbine Building Excavation Following 08/14/06 Letter 8/24/06 Building Removal of West-Side Foundations and Subsurface Components 8 Containment quarry was beneath survey areas 4, 5, 8, and 9. Circulation Water quarry was beneath survey areas 7, 8, 9, and 10. Turbine Building quarry was beneath survey areas 5, 6, and 8 Page 3 of 5

MATRIX OF BIG ROCK POINT FINAL STATUS SURVEY REPORTS SURVEY RECORD2 PACKAGE U.S. NRC PACKAGE LETTER AREA' NUMBER SURVEY AREA DESCRIPTION SIGNOFF REVIEW REVIEW DATE DATE METHOD DATE CLASS 2 AREAS - FINAL STATUS SURVEY OF SURFACE Class 2 Final Status Survey Release Record, Shoreline North of the 08/14/06 Letter 8/24/06 12 12C 1 2 Protected Area Class 2 Final Status Survey Release Record, Eastern Section 15 15(1)C 12 Woods Road Area 15 15(2)C,2 Class 2 Final Status Survey Release Record, Central Section 08/09/06 Letter 8/24/06 Woods Road Area 16 16C,2 Class 2 Final Status Survey Release Record, Shoreline East of 08/14/06 Letter 8/24/06 Breakwall Release Record, North West Transport 19 North 19C12 Route 2 Final Status Survey Class Survey Release Record, South West Transport 19 Southl19C 12 Route 2 Final Status Class Class 2 Final Status Survey Release Record, North East Transport 21 North2CC2 1 Route Class 2 Final Status Survey Release Record, South East Transport 21 South2C1C2 Route Class 2 Final Status Survey Release Record, East Powerline 22 East22C12 Corridor Class 2 Final Status Survey Release Record, West Powerline 22 West22C 12 Corridor Status Release Drainage Ditch, South and 26 26C 12 Class 2 Final West of the Industrial Area Record, Septic Drain DFC,2 Class 2 Final Status Survey Release Record, Septic Field Drain 08/14/06 Letter 8/24/06 Field9 IIIII CLASS 2 AREAS - EXCAVATED SOIL FINAL STATUS SURVEYS 12 12Cx,2 Class 2 Final Status Survey Record, Excavated Soil from Building 12/07/04 On-Site Inspection 06/13-14/06 10/9/06 Construction and Letter 1 19 19Cx,2 Class 2 Final Status Survey Record, Excavated Soil from Storm 12/02/04 On-Site Inspection 06/13-14/06 10/9/06 Drain Modification and Letter 9 Septic Field Drain survey area is contained within survey area 15(1)

Page 4 of 5

MATRIX OF BIG ROCK POINT FINAL STATUS SURVEY REPORTS SURVEY RECORD2 PACKAGE U.S. NRC PACKAGE LETTER AREA1 NUMBER SURVEY AREA DESCRIPTION SIGNOFF DATE REVIEW METHOD REVIEW DATE DATE CLASS 3 AREAS - FINAL STATUS SURVEY OF SURFACE 13 13C,3 Class 3 Final Status Survey Release Record, Shoreline East of the 08/14/06 Letter 8/24/06 13__13C_3 Industrial Site 14 14C,3 Class 3 Final Status Survey Release Record, Shoreline West of the 08/17/06 Letter 8/24/06 14___4C_3 Industrial Site 17 17C,3 Class 3 Final Status Survey Release Record, East Woods Boundary 18 18C,3 Class 3 Final Status Survey Release Record, Wooded Area West of 07/03/06"0 On-Site Inspection 06/13-14/06 10/9/06 18 _ 18C3 Industrial Site and Letter Class 3 Final Status Survey Release Record, South Woods 25 -I 25C13 Boundary 59 59C, Class 3 Final Status Survey Release Record, Soil Storage Area 07/03/06 On-Site Inspection 06/13-14/06 10/9/06 1 South of US 31 and Letter I _I 1oRevisions to packages signed after NRC review were administrative only - no changes to technical content.

Page 5 of 5

ATTACHMENT 2 CONSUMERS ENERGY BIG ROCKPOINT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION CLASS I FINAL STATUS SURVEY RELEASE RECORD, 03C 1 1, NORTH WEST PROTECTED AREA October 24, 2006 37 Pages

Class I Final Status Survey Release Record 03C1 l North West Protected Area SURVEY PACKAGE CLOSURE Final Status Survey Documentation is authorized for closure. All required reviews are complete and the evaluation of data results have satisfied the criteria established for unrestricted release.

Signed: Date: /e)/6'-'-,

/ (ESSG)

Y Signed: Date: /0-/(Df, (ES "Superintendent)

Signed: Date: /o-/*-06

/ (RP & ES Manager)

Survey Area Requirements Final Status Survey, Release Record 03C 1 1 North West Protected Area Survey Description Final Status Survey 03C 11 encompasses 1956 m2 at or below the grade elevation present during plant power operations in the north west section of the Protected Area. No materials of plant origin remain in the survey area.

History During power operations the Protected Area supported the components and systems necessary for electrical generation. The location of Survey Unit 03 is adjacent to the transport route used to move spent resin and filter media for radiological survey and offsite removal. Structures and enclosures formerly located in this area were once used for the storage of contaminated materials. A detailed review of the history and radiological characterization of Survey Unit 3 is provided in Appendix 2B and 2E of the LTP (License Termination Plan).

Current Radiological Status Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Based on operational history and former locations of radioactive systems and material transport pathways the radiological status of this survey unit is Class 1.

Post-Construction Expectations Final Status Survey 03C11 will be performed in the following activity sequence:

1. Walkdown: Environmental Services Survey Group (ESSG) personnel will perform a walkdown assessment to ensure survey area preparations are complete and confirm that the following post-construction expectations have been satisfied as applicable:

" Groundwater and Surface water control is adequate

  • All construction debris has been removed from the survey area

" The survey location status meets all applicable safety requirements

2. Survey Area Isolation and Control: Control measures will be established to ensure that any potential ongoing decommissioning activities in adjacent locations do not impact the current survey area status. Isolation and control measures include postings, barriers, access points, and the evaluation of ongoing work activities in adjacent areas.

Survey Area Requirements FSS 3C 11 Page 1 of 2

3. Survey Design and Execution: Survey design and execution will follow the Data Quality Objectives for 03Cl1 in accordance with the survey requirements established in procedures RM-76, Final Status Survey Design and RM-77, FinalStatus Survey Implementation, and LTP, Chapter 5. Survey size will be based on the statistical requirements of the Sign Test for Class 1 areas with soil samples collected in random start, systematic data point locations. Surface scanning will be performed with 100%

survey area coverage. This survey will be conducted in accordance with approved BRP procedures and follow the guidance of NUREG 1575.

4. Data Quality Assessment: Isolation and control of the survey area will be maintained until the survey Data Quality Assessment demonstrates that the regulatory requirements for unrestricted site release have been satisfied.

Survey Area Requirements FSS O3C1 Page 2 of 2

DATA QUALITY OBJECTIVES Final Status Survey, Release Record 03C11 North West Protected Area STATE THE PROBLEM The Problem:

To demonstrate that the level of residual radioactivity in Class 1 Survey Unit 03 does not exceed the release criteria of 25 mrem/year Total Effective Dose Equivalent (TEDE) as specified in the License Termination Plan (LTP).

Stakeholders:

The primary stakeholders interested in the answer to this problem are Consumers Energy Co., and the general public as represented by the Michigan Department of Environmental Quality (MDEQ), and the US Nuclear Regulatory Commission (USNRC).

The Planning Team:

The planning team consists of members of the BRP Environmental Services Survey Group (ESSG). The primary decision maker will be the Final Status Survey Supervisor.

The Final Status Survey Supervisor will obtain input from the site Construction Group and Scheduling Group for issues relating to schedule and costs.

Schedule:

Approximately five (5) working days are projected to implement the survey and to collect and analyze field data.

Resources:

The primary resources needed to determine the answer to the problem are two (2) technicians to perform fieldwork, one (1) technician to prepare the samples and conduct laboratory analyses, and two (2) survey team members to prepare and review the design, generate maps, coordinate field activities and evaluate data.

2. IDENTIFY THE DECISION Several decisions need to be defined to address the stated problem.

PrincipalStudy Question (1):

Does the mean concentration of residual radioactivity in the survey unit exceed the release criteria stated above?

Decision (1):

Determine whether the mean concentration of residual radioactivity in the survey exceeds the release criteria stated in the problem.

Actions (1):

Alternative actions include failure of the survey unit, remediation, or no action required.

Data Quality Objectives FSS 03C 1 1 Page 1 of 5

PrincipalStudy Question (2):

Do any areas of elevated activity in the survey unit exceed the release criteria?

The Decision (2):

Determine if any areas of elevated activity in the survey unit exceed the release criteria.

Actions (2):

Alternative actions include confirmation and investigation, performing the elevated measurement comparison (EMC), remediation, or no action required.

PrincipalStudy Question (3):

Is the potential dose from residual radioactivity in the survey unit ALARA as stated?

The Decision (3):

Determine if the potential dose from residual radioactivity in the survey unit is ALARA.

ALARA requirements for soil remediation are defined in Chapter 4 of the LTP.

Actions (3):

Alternative actions include remediation or no action required.

3. IDENTIFY INPUTS TO THE DECISION Information Needed:

Characterization measurements are required to define the radionuclides present and determine the extent and variability of residual radioactivity in the survey area for design and implementation of the survey. Survey area classification, ALARA analysis, potential radionuclides of interest, and site-specific DCGL values are also required inputs to the decision process. The primary information required for evaluation is the analytical results of survey measurements.

Source of the Information:

The soil sample data to be used for survey development are the radionuclide-specific measurements of representative soil samples collected for radiological characterization and excavated soil surveys conducted to determine suitability for transport of excavated soil to the SVA. The soil samples obtained were judgmentally selected as a result of multiple surveys conducted during the excavation and transport process. The ALARA analysis for potential soil remediation is provided in LTP, Section 4.4.. Site-specific DCGL values and BRP radionuclides of interest are defined in LTP Chapter 5, Table 5-1 and Procedure RM-76, Final Status Survey Design.

The survey will be conducted in accordance with applicable regulatory guidance as established in LTP Chapter 5 for Class 1 areas. Soil samples will be utilized for radionuclide-specific measurements in this evaluation.

4. BOUNDARIES OF THE STUDY Boundariesof the Survey:

The target population for this survey is the total thickness of prepared soil in the survey area of 1956 M2 .

Data Quality Objectives FSS 03Cll Page 2 of 5

Temporal Boundaries:

Scanning and sampling in this survey unit will only be performed during daylight hours under dry weather conditions. Surface soils must be free of significant snow cover and standing water prior to surface scanning. Soils must be in a non-frozen state or fragmented for collection to satisfy BRP procedural sampling requirements. The anticipated start date for the survey is September 19, 2006.

Constraints:

Cold weather or rainy conditions may effect the operation of electronic equipment.

Adverse weather conditions that include accumulations of rain or snow may limit area access and delay survey efforts.

5. DEVELOP A DECISION RULE The following decision rules have been developed to define a logical process for choosing among alternative actions for the principal study questions associated with this survey area.

Decision Rule (1):

If all reported concentrations for residual radioactivity are less than the site-specific DCGL's and the unity rule has been satisfied for each sample, then the survey unit meets release criteria. No further action is required.

Decision Rule (2):

If the mean value of activity in the survey unit is greater than the DCGL, then the survey unit fails to meet the release criteria. 1 Remediate, resurvey, and evaluate the results relative to the decision rule.

Decision Rule (3):

If the mean activity in the survey unit is less than the DCGL and any individual sample measurement exceeds this value, conduct the Sign Test and the elevated measurement comparison (EMC) per LTP, Chapter 5 and Procedure RM-76, Final Status Survey Design. If the EMC and the Sign Test have been satisfied then the survey unit meets the release Criteria and no further action is required. If the EMC or the Sign Test has not been satisfied then remediate the area(s) of elevated activity, resurvey as appropriate, and evaluate the results relative to the decision rule.

Decision Rule (4):

If the potential dose from residual radioactivity in the survey unit is ALARA, then no further action is necessary. If the potential dose from residual radioactivity in the survey unit is not ALARA, then remediate and resurvey.

6. SPECIFY TOLERABLE LIMITS ON DECISION ERRORS The Null Hypothesis:

It is assumed that residual radioactivity in the survey unit exceeds the release criterion.

1 When multiple radionuclides are present the mean activity value is determined as the average of the weighted sum. The DCGL of the weighted sum is 1.

Data Quality Objectives FSS 03C1 1 Page 3 of 5

Type I Error(a ):

The a error is the maximum probability of rejecting the null hypotheses when it is true.

Thea error is defined in the LTP at a value of 0.05 (5%) and cannot be changed to a less restrictive value unless prior approval is granted by the USNRC. The a error value of 0.05 will be used for survey planning and data assessment for this survey area.

Type ilError(,8)6 The ,8 error is the probability of accepting the null hypothesis when it is false. A value of 0.05 (5%) will be used for survey planning and data assessment for this survey area.

The Lower Bound of the Gray Region (LBGR):

The LBGR is initially set at one-half the DCGLw for this survey unit. The LBGR may be adjusted during survey design to achieve an optimum relative shift between 1.0 and 3.0.

Relative Shift (A/c):

The relative shift will be maintained within the range of 1.0 and 3.0 by adjusting the LBGR as appropriate.

7. OPTIMIZE DESIGN FOR OBTAINING DATA Statistical Test Sign Test:

Radionuclides of potential plant origin also present in soil as background activity resulting from fallout constitute only a small fraction of the DCGL. Therefore, the Sign Test will be used where applicable in the survey evaluation to determine if the survey area meets the requirements for unrestricted release.

Number of Samples Determined:

The number of samples required for this survey will be determined based on the relative shift as defined by the requirements of the Sign Test (LTP, Chapter 5.) and Procedure RM-76, Final Status Survey Design. The LBGR is initially set at one-half the DCGL, and may be adjusted as necessary for optimizing the survey design to achieve a relative shift between 1.0 and 3.0. Sample point locations are to be determined using a random start, systematic square grid spacing.

Judgmental Sampling:

Co-60 is the most limiting radionuclide for identification by surface scanning; judgmental surface and subsurface core samples will be collected in any location that exceeds the scan investigation level.

Scan Coverage:

Scanning for this survey area will provide 100% coverage.

Number of Samples for Quality Control:

A minimum of 5% of the sample population will be collected for quality evaluation.

These samples may include sample splits, sample recounts, or third party sample Data Quality Objectives FSS 03C11 Page 4 of 5

analysis. Quality analyses will be conducted as defined in LTP, Chapter 5 and Procedure RM-79, Final Status Survey Quality Control.

Additional Sample Analysis Requirements:

The area of soil excavation intersects the identified waterborne pathway for Tritium migration and shall require Tritium in soil analyses for a minimum of 10% of the sample population. Soil samples will be collected in the same random locations as those selected for QA/QC evaluation and sent to an independent laboratory for Tritium analysis. Data results will be provided in the survey package.

Investigation Levels:

Investigation levels defined in LTP, Chapter 5 and BRP Procedure RM-76, Final Status Survey Design, shall be conservatively established for this survey as shown below:

Investigation Levels for Survey 03C1 1 Scan Measurement Soil Sample Analysis

> DCGL > DCGLw The investigation levels for soil sample measurements are meant to include any individual radionuclide result greater than the site-specific DCGL or where the combined radionuclide values exceed the unity rule. Co-60 is the most limiting radionuclide for identification by surface scanning; further investigation will be initiated at any location that exceeds the Co-60 Scan DCGL of 1818 CPM above background as detailed in the survey design.

Data Quality Objectives FSS 03C1 1 Page 5 of 5

FINAL STATUS SURVEY DESIGN Release Record 03C 11 North West Protected Area Survey Unit Description Survey 03C,1 encompasses an area of 1956 m2 in the north west section of the Protected Area.

No materials of plant origin exist in this survey unit.

Soil Sample Design Scopina Data Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Input data for survey design were conservatively estimated based on supporting surveys of excavated soils resulting from subsurface structure and component removal within the Protected Area.

Table 1 Input Data for Survey Design (pCi/g)

Radionuclides Cs-137 Co-60 a* 0.524 0.255 DCGL 11.93 3.21

  • Survey data detailed in Attachment 1 Sample Requirements The number of sample data points for this survey is based on the requirements of the Sign Test.

The Unity Rule is used for the presence of multiple radionuclides. The Standard Deviation of the weighted sum is described by the following:

2 + OYCOBO 2 Cy C'sS37 DcGLcsl37) -t DCG-co6 o)

C3

,/0.524 /2 (0.255 )2 a = 0.091 Relative Shift Relative Shift = DCGLw-LBGR Relative Shift = 1-0.818 0.091 Relative Shift = 2.0 With (xand P3 error levels set at 0.05 and the relative shift of 2.0, the Sign Test requires 15 sample data points (Table 5.5 NUREG 1575).

Survey Design FSS 03C, 1 Page 1 of 7

Sample Locations Sample locations are selected in a random start, systematic square grid pattern with the southwest corner of the survey unit as origin (X=0, Y=0). Two numbers between 0 and 1 have been randomly selected and then applied to the survey unit maximum X and Y dimensions to determine the random start location as shown below:

Table 2 Random Numbers Random #, X Axis Random #, Y Axis 0.353393 0.688176 Survey Unit Dimensions: X = 40.0 meters Y = 48.9meters Random Start Location X = (0.353393)(40.0) = 14.1 meters With SW Corner Origin: Y = (0.688176)(48.9) = 33.7 meters Sample Spacing As a conservative measure sample spacing will be calculated based on 18 samples for this survey. Samples are located in a systematic square grid pattern with sample spacing determined by the following:

A nA Where: A= area of survey unit, and n = number of samples.

1956 L 95-6 10.4 meters 18 With sample spacing established at 10.4 meters, 20 data points are available for this survey.

Data point locations are identified in Attachment 2.

QA/QC Sampling A minimum of 5% of the sample population and 5% of the scan survey area are required to be selected for QA/QC verification in accordance with BRP Procedure RM-79, FinalStatus Survey Quality Control. As a conservative measure, three (3) soil samples and 10% of the scan survey area will be selected for QA/QC evaluation. Data point locations for soil samples will be determined by random number selection.

The QA/QC scan starting point and track direction are also determined by random number selection. The first random data point selected will identify the scanning start point and the second random data point will determine the direction in which the scan will track. QA/QC location results are provided in Table 3 below:

Survey Design FSS 03C11 Page 2 of 7

Table 3 Random Numbers Generated for QA/QC QA/OC Soil Random Random Samples Sample erification Scan Sample

_____sNumber Number Split Sample: 2 Start Point: 5 Sample Recount: 10 Scan Toward: 13 Sample Recount: 13 IScan Area Requirement: 196 M2 Surface Scanning The coverage requirement for surface scanning in this Class 1 area is 100%. The Scan MDC has been established at fractional values of the DCGLwfor typical background activity levels at Big Rock Point. Scan MDC values for varying backgrounds are provided in Attachment 3. The investigation level for identification of potential areas of elevated activity in this survey area will be the Scan DCGL as defined by the following:

Scan DCGL = Detector Rating CPM

  • Exposure Model uR/hr
  • DCGLw uR/hr pCi/g Scan DCGL for Co-60 = 1818 CPM Scan DCGL for Cs-137 = 3518 CPM Where: 1 Detector Rating = 1200 CPM Cs- 137 and 565 CPM Co -60 uR/hr uR/hr Exposure Model = 1.229uR/hr Cs- 13 7 and 5.029 uR/hr Co-60 5pCi/g 5 pCi/g DCGLw = 11.93 pCi/g Cs-137 and 3.21 pCi/g Co-60 The DCGLw for Co-60 is the most limiting value for scanning measurements performed to identify areas of potentially elevated activity. Scanning conducted for this survey will assume all residual radioactivity to originate from Co-60 and the instrument response at the Co-60 DCGLw (1818 cpm) will be used as the scanning investigation level for FSS 03C1 1.

1 These values established in EA-BRP-SC-0201, Nal Scanning Sensitivity for Open Land Survey.

Survey Design FSS 03ClI Page 3 of 7

Attachment 1 Design Data - FSS 03C 11 Protected Area Supporting Surveys Cs-1 37 Co-60 Survey No. Sequence Activity Activity No. (pCilg) (pCilg)

HH060705 .165388 * .26" .66 HH660705ý 1653ý9 0.06 07W6*

HH060705" 16540 i-.05 0*66

-B062805 16755 t.16 1: - ' 0.27-

,,,,-TB062805 16756 ,0.147, _ _031_ _"

VTB062805,,- 16774 0.9.3 Mean: 0.698 0.352 Std Dev: 0.524 0.255

  • Measurement system MDA - Co-60 not identified in this sample Survey Design FSS 03C11 Page 4 of 7

Attachment 2 Soil Sample Locations - Survey 03C1 1 North West Protected Area

_11U I III II-. I q-ij Y= 48.9 m 57 s o1 S30 1 91 01 11 21 33 12 8 1 81 9I O5 11 52 14 7 X=40 25 10 207 208 2D9 234

- Survey Unit 03C_1 0

i 0 5

B 6 10 S

2 Mes

  • Sample Location tiam pie spacing 15 1U.' MeiMr Survey Design FSS 03C11 Page 5 of 7

Attachment 3 Scan MDC In Varying Backgrounds Background d' j Si MDCRsurveyor Cs-1 37 Co-60 Cs-1 37 Co-60 2000 2.48 4 28.64 607.47 0.51 1.08 2.06 1.07 i 4 2;4-8

  • d:Q$ A___ 32.02: -69.I8<-**' , ý260&2130 10.5 1,20-

.2 3000 2.48 4 35.07 744.00 0.62 1.32 2.52 1.31

  • 3500 2.48 4 37.88 803.61 0.67 1.42 2.72 1.41 4000 2.48 4 40.50 859.10 0.72 1.52 2.91 1.51 4500 2.48 4 42.95 911.21 0.76 1.61 3.09 1.60 5500 2.48 4 47.49 1,007.38 0.84 1.78 3.42 1.77 6000 2.48 4 49.60 1,052.17 0.88 1.86 3.57 1.85 6500 2.48 4 51.63 1,095.14 0.91 1.94 3.71 1.93 7000 2.48 4 53.57 1,136.48 0.95 2.01 3.85 2.00 8000 2.48 4 57.27 1,214.95 1.01 2.15 4.12 2.14 8500 2.48 4 59.04 1,252.34 1.04 2.22 4.25 2.20 9000 2.48 4 60.75 1,288.65 1.07 2.28 4.37 2.27 9500 2.48 4 62.41 1,323.96 1.10 2.34 4.49 2.33 10500 2.48 4 65.61 1,391.90 1.16 2.46 4.72 2.45 11000 2.48 4 67.16 1,424.65 1.19 2.52 4.83 2.51 11500 2.48 4 68.67 1,456.67 1.21 2.58 4.94 2.56 12000 2.48 4 70.14 1,488.00 1.24 2.63. 5.04 2.62 12,'0d0 2"8 "~5 4 7.9 .8 1..2 2.659~ 516 2.6 13000 2.48 4 73.01 1,548.76 1.29 2.74 5.25 2.73 13500 2.48 4 74.40 1,578.26 1.32 2.79 5.35 2.78 14000 2.48 4 75.77 1,607.22 1.34 2.84 5.45 2.83 14500 2.48 4 77.11 1,635.67 1.36 2.89 5.55 2.88

< i 5' 740u6636 - 1 U 2.4

,Modeloo&Exposuire (uR/hr 5)-,CV-UŽ6i' Survey Design FSS 03C 1 Page 6 of 7

Attachment 4 Area Factors for Open Land Survey Evaluation Conamiae Calculated Area Factors at Time of Peak Dose Area (Mt) H-3 Mn-54 Fe-55 Co-60 Sr-90 Cs-137 Eu-152 Eu-154 Eu-155 8094 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 4047 1.00 1.01 1.00 1.01 1.00 1.02 1.02 1.01 1.02 2024 1.00 1.03 1.00 1.03 1.00 1.03 1.03 1.03 1.03 1012 1.35 1.04 1.00 1.04 1.00 1.04 1.05 1.04 1.04 506 2.91 1.09 1.98 1.08 1.98 1.13 1.07 1.07 1.06 253 6.05 1.14 3.95 1.13 3.94 1.20 1.11 1.11 1.09 126 12.4 1.20 7.93 1.20 7.87 1.29 1.17 1.16 1.14 63 24.9 1.30 15.8 1.30 15.6 1.41 1.27 1.26 1.23 32 49.2 1.49 31.2 1.49 30.5 1.62 1.44 1.45 1.39 16 98.9 1.78 62.0 1.78 59.9 1.93 1.72 1.73 1.63 8 198 2.38 123 2.38 117 2.58 2.30 2.31 2.14 4 397 3.61 243 3.62 230 3.91 3.49 3.52 3.19 2 794 5.68 473 5.75 452 6.14 5.48 5.55 4.90 1 1590 9.57 905 9.73 887 10.3 9.24 9.39 7.88 Survey Design FSS 03C 1l Page 7 of 7

RM-76 Revision 1 FINAL STATUS SURVEY DESIGN Page 19 of 19 RM-76-5 FINAL STATUS SURVEY APPROVAL AND AUTHORIZATION FOR IMPLEMENTATION Survey Code 03C, 1 Survey Area

Description:

Final Status Survey 03C,1 encompasses 1956 m 2 at or below the grade elevation present during plant power operations in the north west section of the Protected Area. No materials of plant origin remain in the survey area.

The survey area is authorized for Final Status Survey Implementation.

09 Dat by Date Technical Review by Date RM-76.doc

RM-77 Revision 2 FINAL STATUS SURVEY IMPLEMENTATION Page 8 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 1 of 3 Step Initial Date

(+)

1.0 PREPARATION FOR SURVEY (DE_ I Survey 1.1 Survey Area Status:

_ a. Final Status Survey Design has been approved for implementation (see RM-76-5, Final Status Survey Approval and Authorization for Supplementation).

1. Survey area walkdown complete
2. Survey area determined ready for FSS
3. Decommissioning activities that may impact the environmental status of the survey area have been completed.
4. Survey area environment is controlled by barriers LP and postings or other approved method to restrict SSG access.

___ b. Survey area has been turned over to the Environmental Services Survey Group (ESSG) in acceptable condition for FSS.

1.2 Field Preparation:

a. Survey unit boundaries delineated (Step 6.1.1)

_7 b. Statistical soil samples predetermined in the survey design are located and marked within the survey unit.

(Step 6.1.2)

c. Soil sample locations verified (Step 6.1.2.c)

_.Z d. Instruments and equipment have been collected and calibrated for data measurement and collection (Step 6.1.3)

  • a]LO

____ e. Field documentation is prepared (Step 6.1.4) -/SSG RM-77.doc

RM-77 Revision 2 FINAL STATUS SURVEY IMPLEMENTATION Page 9 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 2 of 3 Initial Date 2.0 DATA COLLECTION 2.1 Soil Survey:

All soil samples collected and controlled (Step 6.2.1). E*SSG 10J~

2.2 Surface Scan:

Surface Scan complete. Action response requirements have been conducted on any identified areas exceeding the investigation level (Step 6.3). LZZ- . ~4~kLo PE-S_SG 2.3' Judgmental Soil Samples:

a. Judgmental soil samples have been collected and controlled (Step 6.2.3).
b. Deep core profiles performed in areas identified to contain elevated residual activity (Step 6.2.3).

SESSG 3.0 SAMPLE PREPARATION AND LABORATORY ANALYSIS 3.1 Sample Preparation (Step 6.4.1):

a. Soil samples are homogenous Soil samples are visibly dry prior to packing
  1. _AZ b.
c. Non-soil materials have been removed from sample
d. Soil samples have been transferred to one-liter Marinelli containers and are labeled and sealed. 449 O~q 1c93Id

"'"IE

_SS G RM-77.doc

RM-77 Revision 2 FINAL STATUS SURVEY IMPLEMENTATION Page 10 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 3 of 3 Initial Date 3.2 Laboratory Analysis:

-< Isotopic analyses are complete. The spectroscopy report requires a signature of completion by the laboratory analyst and a signature of evaluation documenting that a second level review has been performed (Step 6.4.2). 'ý"-ESSG alad'ý 3.3 Sample Control and Documentation:

-Z Chain of custody documentation exhibits control of soil samples (Step 6.4.3).

T'ESSG kRe~viewed by Date RM-77.doc

RM-59 Revision 11 SAMPLING AND ANALYSIS OF OPEN LAND Page 7 of 13 AREAS FOR SITE CHARACTERIZATION SURVEYS ATTACHMENT RM-59-1 SAMPLING AND ANALYSIS REPORT Date: 09-19-2006 Time: 1600 Location: 03C011 Tech: TRS/WMH/JNS SURVEY IDENTIFICATION / DESCRIPTION Survey 03C1 1 encompasses 1956 m2 at or below the grade elevation present during plant oower woerations in the north west section of the Protected Area. No materials of plant origin remain in this area.

SURVEY TYPE Survey Type: Characterization X Scan (Motive)

Remediation X Final Scan (Static)

Trenching and Digging (use RM-59-4)

SURVEY DESIGN Sample Collection: _ Judgmental _ Random X Systematic _ Large Container Assay Scan Coverage: 100%

ANALYSIS Inst.SN/Cal Due 186201/09-30-2006 DAILY CHECK: X SAT UNSAT INIT: TRS Inst.SN/Cal Due 186194/02-08-2007 DAILY CHECK: X SAT UNSAT INIT: TRS Inst.SN/Cal Due 193709/02-21-2007 DAILY CHECK: X SAT UNSAT INIT: TRS Inst.SN/CaI Due Det.# 6 DAILY CHECK: X SAT UNSAT INIT: JP Inst.SN/Cal Due DAILY CHECK: SAT UNSAT INIT:

Investigation of Unidentified Peaks: X SAT UNSAT INIT: JLR Minimum Detectable Activity (Section 5.3.2) X SAT UNSAT INIT: JLR COMMENTS Survey 03C ,1 was performed in a random start, square grid. systematic sampling pattern with samples collected at 20 data point locations. Laboratory analyses did not identify residual radioactivity above trace levels of the DCGL value. Surface scanning identified no areas of elevated residual radioactivity. The results of the QA/QC verification scan (10%) were consistent with the findings of the primary survey scan.

Technician Sionature:i 5 Date: 94--

Second Level Review Signature: Date: l/"o /

RM-59.doc

Soil Sample Activity Summary Release Record 03C11 North West Protected Area 109 110 111 112 11i3 -4* -

Y =489 m 50 57

'1 9 128 130 131 132 133

@16 @15 i14 013 1)o 151 152 147 148 149

@Wo 912 166 167 168 169 170 171 04 e* Op 187 188 189 190 185 186 2 a3 4 40 0 X =40 m 204 205 206 207 208 209 0 5 10 20 Meters Survey Unit 03C1_1 I i I I1 S a i 0 Sample Location

Surface Scan Summary Release Record 03C11 North West Protected Area 4,3 ,

3.7 4.5 3 16 3.6 4.3 3.9 3.6 3.6 3.7

  • 14 i;3 3,8 3.5 4.E 3.5 4.9 3.1 4.9 4.1 3.6 5.0 II oil04.7 012 3.5 3.9 3,7 3.3 4.9 4.1 5.1 052 5.4 O.

3.8 3.7 3.2 3.4

.1 w 3.4

,ýI,* 3.6 3.2 w~3. ý1 3.4 0 5 10 20 MOM Survey Unit 03C1_1 I M a a i i i i
  • Sample Location RED Values are Average Mobile Scan General Area Activity (kcpm)

BLUE Values are Average Verification Scan General Area Activity (kcpm)

GREY Values are Average General Background Area Activity (kcpm) du Afoa~cq N"L 4 {

-ýj, Primary Scan : .O.  %

Tochnildin Signature: Dia:

  • _i Time:

QC Verification Scan: it  %

Technician Signature: Do 9 -199 o

RM-72 Revision 0 SAMPLE CHAIN-OF-CUSI Page 4of 5 o9- 03C11 RM-72-1 CHAIN-OF-CUSTODY RECORD Sample Number Sampling Location Date Time Final Disposition of Sample 1 Grid # 186 (3.7) (2.5) f-1.. /3.--* "O vr-,,o0z'.

2 Grid # 187 (4.1) (2.5) f-'(o,4 /9Z7-2 QASplit Grid# 187 (4.1) (2.5) f-i-,. e,,I 3 Grid # 188 (4.5) (2.5) 9-R,0--o- 13Z 5 4 Grid # 189 (4.9) (2.5) /j Z-5 Grid # 170 (4.9) (2.9) -8 /

6 Grid # 169 (4.5) (2.9) 7"(/'oe -

7 Grid # 168 (4.1) (2.9) /3..

8 Grid # 167 (3.7) (2.9) f -g-T-, i3SY 9 Grid # 148 (3.7) (3.3) 7-,-o*- .

10 (R) Grid # 149 (4.1) (3.3) '.-*f- /Ii*

11 Grid # 150 (4.5) (3.3) '.../:(,k /3i'/

12 Grid # 151 (4.9) (3.3) 9-'.-. /,.',*"

13 (R) Grid # 132 (4.9) (3.7) -o /3'i 14 Grid # 131 (4.5) (3.7) /S,,ig' 15 Grid # 130 (4.1) (3.7)  ?-&9-o0 &.19 16 Grid # 129 (3.7) (3.7) - /.?ZO 17 Grid# 53 (3.7) (4.1) f/9t-, .

18 Grid# 54 (4.1) (4.1) 9

'.*k. /3z-19 Grid # 55 (4.5) (4.1) - /5j*

20 Grid # 56 (4.9) (4.1) - /3z9 (Samples may be analyzed and stored, shipped for offsite evaluation or analyzed and disposed of.)

1.R linjUish Date Time Received in good condition by:

2. Relinquished by: 4 Date Time Received in good condition by:
3. Relinquished by: Date Time Received in good condition by:
4. Relinquished by: Date Time Received in good condition by:

RM-72.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 19 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 1 of 8 FINAL STATUS SURVEY: o3C2/

1.0 DATA VERIFICATION 1.1 Data Acceptance Review the Implementation Checklist (RM-77-1) to verify that survey isolation and control measures were executed prior to FSS and are being maintained.

Review RM-77, Final Status Survey Implementation, to verify that methods,

.techniques, and survey activities required for FSS have been applied in accordance with the appropriate procedures.

1.2 Field QC Records:

Review all assessments, Condition Reports and audits to ensure that identified issues have been resolved.

Comments:

Verify scan instrumentation was in calibration and the QC source checks were performed prior to and after surveys.

Verify daily QC source checks for Canberra gamma spectroscopy detector properly logged prior to soil sample analysis.

1.3 Review Verification:

Verify that the Data Quality Objectives are complete.

Verify that the survey design has been technically reviewed.

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 20 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 2 of 8 Verify that gamma spectroscopy results have received a technical review.

V/ Verify the Sample and Analysis Report (RM-59-1) is completed and reviewed.

Data Verification Completed: &) No Comments ec a0-i 3-be Date Assessor6 RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 21 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 3 of 8 2.0 DATA VALIDATION 2.1 Documentation Review:

Perform documentation review for quality control purposes and validate the data collected is complete and appropriate for use as defined by the survey design. Documentation includes:

§Field measurement records

.. ,* Chain-of-custody

__j Quality Control (QC) measurement records Current qualification of survey personnel Corrective Action Reports v1' Data inputs (laboratory spectroscopy)

Sample preparation techniques 2.2 Detection Limit Review:

XScan MDCs are below established site DCGLs.

Forced-count values are assigned as necessary when activity is not detected in a sample.

Minimum Detectable Concentration (MDC) values of gamma spectroscopy are below established DCGLs.

2.3 Quality Control (QC) Data Review:

  • Quality Control (QC) data results have received required reviews and are complete and consistent.

.. 1 Results of judgmental samples have been reviewed and evaluated.

.Z Review to ensure that the analytical results of judgmental samples do not impact the evaluation for unrestricted release of the survey area.

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 22 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 4 of 8 2.4 Qualification of Data:

Statistical radionuclide-specific measurements for completeness. Evaluate the survey for determination of data usability and confirm that sufficient qualified data are present for the decision process.

a. Total number of statistical samples planned for the survey: /J_ "
b. Total number of statistical samples determined as valid: Q b x120
c. Calculate % Completeness:

a QQualified data are :=400% completeness and are sufficient to support the Sign Test requirement for determination of unrestricted release.

Data Validation Completed: No Comments:

/De -?-0(

Assessor Date RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 23 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 5 of 8 3.0 DATA QUALITY ASSESSMENT 3.1 Review the DQOs and Survey Design:

_ Confirm that all inputs to the decision have been reviewed and are complete.

____ Verify that boundaries or constraints identified in the survey area have not affected the quality of the data.

__ Review the Statement of Hypothesis and confirm that it remains relevant.

z..__ Confirm that Type I and Type II error limits are consistent with DQOs.

___ Confirm that the survey design is consistent with DQOs and that the appropriate number of data points were obtained.

3.2 Preliminary Review:

3.2.1 Preliminary Evaluation:

___ Quality Assessment (QA) reports consistent with procedure RM-79, Final Status Survey Quality Control.

Survey is of sufficient intensity to satisfy classification requirement.

____ Potential trends of radioactivity levels in the survey area do not impact a decision for unrestricted release.

Comments:

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 24 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 6 of 8 3.2.2 Calculate Basic Statistical Quantities:

a. Number of qualified data points *0
b. Calculation of the Mean fL*1Jrs.#
c. Calculation of the Median /a
d. Calculation Standard Deviation ,1. 1/0 Cso)

.!L Attach graphic representation of the data if any radionuclide-specific measurements exceed 50% of the DCGL.

,jSample QA/QC measurements consistent with FSS data 3.3 Statistical Evaluation:

NOTE: If all measurement data are less than the DCGLw, statistical testing in not required and the survey unit meets the regulatory requirement for unrestricted release.

7/' All survey measurements are below the DCGLW.

3.3.1 Verify Assumptions of the Survey Design

____Review the posting plot to verify that the data exhibits spatial independence. Spatial trends must be investigated and resolved prior to further assessment.

V 7

Review to verify dispersion symmetry. The appearance of skewed data must be investigated for cause and documented prior to further assessment.

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 25 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 7 of 8

____ Review the dataset standard deviation and range for data variance.

Questionable data must be investigated for cause and documented prior to further assessment.

__ Verify that the data exhibits adequate power and confirm that the sample size is sufficient to satisfy the DQOs.

3.4 Draw Conclusions from the Data:

3.4.1 Investigation Levels and Response Actions L Determine if data resul! have exceeded any investigation level.

Document findings. 1/1a !AveJt4e-,

3.4.2 Evaluation for Unrestricted Release Select applicable conclusion:

,//. Survey area acceptance criteria met and survey area satisfies the requirements for unrestricted release:

v/j All concentrations are less than the DCGLw. The Null Hypothesis is rejected.

4 The mean concentration of the survey area is below the DCGLw but individual measurements in the survey unit exceed the DCGLw. The Sign Test and EMC evaluation are successful and the Null Hypothesis is rejected.

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 26 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 8 of 8

, Survey area acceptance criteria not met and survey area fails to satisfy the requirements for unrestricted release:

SThe mean concentration in the survey area exceeds the DCGLw. and the null hypothesis is confirmed.

.J/ The mean concentration of the survey area is below the DCGLw but individual measurements in the Unit exceed the DCGLw..

The Sign Test and EMC evaluation are unsuccessful and the null hypothesis is confirmed.

Data Quality Assessment Completed: & No Comments f/

Dat1e3-0 R Assessor Date Revie vi Te K~nicaL' e v iew /Datei-ni c l ES Superintendent Date 10 -16, -o6 RP&ES Manager Date RM-78.doc

RM-78-3, Attachment I Statistical Quantities Release Record 03C1 l North West Protected Area Sample Cs-1 37 Co-60 Weighted "Weighted Sum Number (pCi/gm) (pCi/gm) Sum (SOR) <DCGLw? DCGL-W. Sum Sign 1 0.0591 0.0023 0.0057 yes 0.9943 +1 2 0.0912 0.0288 0.0166 yes 0.9834 +1 3 0.0698 0.0118 0.0095 yes 0.9905 +1 4 0.0872 0.0012 0.0077 yes 0.9923 +1 5 0.0638 0.0073 0.0076 yes 0.9924 +1 6 0.2535 -0.0063 0.0193 yes 0.9807 +1 7 0.0529 0.0243 0.0120 yes 0.9880 +1 8 0.3983 0.0343 0.0441 yes 0.9559 +1 9 0.1171 0.0110 0.0132 yes 0.9868 +1 10 0.2412 0.0077 0.0226 yes 0.9774 +1 11 0.0677 0.0010 0.0060 yes 0.9940 +1 12 -0.0001 -0.0101 -0.0032 yes 0.9968 +1 13 0.0114 0.0117 0.0046 yes 0.9954 +1 14 0.0503 0.0210 0.0108 yes 0.9892 +1 15 0.0834 0.0175 0.0124 yes 0.9876 +1 16 0.1165 0.0552 0.0270 yes 0.9730 +1 17 0.0651 -0.0035 0.0044 yes 0.9956 +1 18 0.0558 0.0250 0.0125 yes 0.9875 +1 19 0.0458 0.0254 0.0118 yes 0.9882 +1 20 0.1818 0.0046 0.0167 yes 0.9833 +1 Std. Dev 0.0955 0.0157 0.0100 Mean 0.1056 0.0135 0.0131 Median 0.0688 0.0114 0.0119 Number of Positive Differences (S+): n/a Critical Value, k, Table 1.3 of Marssim: n/a S+ >thank?: n/a Survey Unit Pass or Fail: **Pass

  • Note: Forced-Count values are used for samples with activity levels below the MDA.
    • Note: If all measurement data are less than the DCGL ., then the Sign Test is not required.

"I .

RM-79 Revision 1 FINAL STATUS SURVEY QUALITY CONTROL Page 11 of 13 RM-79-1 FSS QUALITY CONTROL EVALUATION RESULTS FSS Package # 0'3 C4 z QC Package # 0 .& C, / -

QC Measurement Type Acceptance Criteria Met*? Reference vi1. 1. Replicate Scan No Step 5.1.3

2. Sample Recounts Step 5.1.4.1
a. In-house "e! No
b. Third party Yes / No
3. Split Samples Step 5.1.4.2

_ c. In-house e)/No

.jL d. Third party Yes / No

  • NOTE: If Acceptance Criteria is not met, completion of Attachment RM-79-2, FSS Quality Control Investigation Results, is required.

Comments: )

(D.q X,::ý A.W-4 JA / ~.z~ '

Reviews:

Evator - Date

/

-/0 -)-6 Terch'nical Review Date RM-79.doc

QA Verification Split Sample Analysis Date: 8/25/2006 QA: 03C 1l North West Protected Area Type: Split Sample Lab: In-House Resolution C= (A)10, A

< Indicatesresults less than the MDA.

  • Note Results are considered in agreement for MDA and near-MDA measurement comparisons Results fthat fail agreement must be investigatedper RM-79.

QA Verification Sample Recount Analysis 6

. Table I Date: 8125/2006 Acceptance Criteria Resolution Ratio QA: 03C 1I North West Protected Area <4 N/A 4-7 0.5-2.0 Type: Sample Recounts 8-15 0.6-1.66 16-50 0.75-1.33 Lab: In- House 51-200 0.8-1.25

>200 0.85-1.18 A B C D E F G BRP Result BRP BRP BRP Results in Acceptance Recount Comparison Agreement Radionuclide Results  % Error Ratio Recount Results Ratio Sample Below Resolution Result Compare MDA (pCi/g) (Sigma) (Table 1) Below MDA ______G Be____ow_____D (pCi/g) FI, Compare with D) 10 Co-60 0.0607 n/a n/a n/a < 0.0587 0.97 YES 10 Cs-137 0,2412 9.95 10.05 0M6-1.66 0.2059 0.85 YES 13 Co-60 < 00583 n/a n/a n/a < 0.0568 0.97 YES 13 Cs-137 < 0.0480 n/a n/a n/a < 0.0496 1.03 YES Resolution C= (AI( O

< Indicatesresults less than the MDA.

'Note Results are consideredin agreement forMDA and near-MDA measurementcomparisons Results fthat fail agreementmust be investigatedperRM-79.

,' i. V Tritium in Soil Data Results Final Status Survey 03C1 1 Sample Number r

j Tritium in Soil pCi/g 2 0.025 10 0.015 13 0.011 Mean: 0.0170 Median: 0.0150 St. Dev: 0.0072 Note: The DCGL for Tritium is 327 pCi/g.

Sample results are less than 0.2% of the DCGL

.. Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road

  • Northbrook, IL 60062-2310 ph. (847) 564-0700 - fax (847) 564-4517 Mr. David W. Parish LABORATORY REPORT NO. 8022-100-239 Big Rock Point DATE: 09-27-2006 10269 US-31 North SAMPLES RECEIVED: 09-22-2006 Charlevoix, MI 49720 PURCHASE ORDER NO:

Below are the results of the analyses for tritium on three soil samples.

Excavated Soil Survey 03C 11 Sample Collection Lab Concentration MDA Description Date Code (pCi/g of soil) (pCi/g of soil)

H-3 2 09-19-06 BRSO-6484 0.025 +/- 0.008 < 0.013 10 09-19-06 BRSO-6485 0.015 +/- 0.007 < 0.011 13 09-19-06 BRSO-6486 0.011 +/- 0.005 < 0.009 The error given is the probable counting error at 95 % confidence level. The less than, (<), value is based on 4.66 sigma counting error for background sample.

APPROVED BY

/ Tony Coorlim, Quality Assurance

ATTACHMENT 3 CONSUMERS ENERGY BIG ROCKPOINT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION CLASS 1 FINAL STATUS SURVEY RELEASE RECORD, 05C, 1 ,

CENTRAL PROTECTED AREA October 24, 2006 37 Pages

Class I Final Status Survey Release Record 05C1 l Central Protected Area SURVEY PACKAGE CLOSURE Final Status Survey Documentation is authorized for closure. All required reviews are complete and the evaluation of data results have satisfied the criteria established for unrestricted release.

Signed: Date: lo-/la- o&

f- (ESSG)

Signed: Date: /c/*6 (ERP& perintendent)

Signed: Date: /o-/~-o*

/(RP & ES Manager)

Survey Area Requirements Final Status Survey, Release Record 05C 1 1 Central Protected Area Survey Description Final Status Survey 05C 11 encompasses 1924 m2 at or below the grade elevation present during plant power operations in the central section of the Protected Area. No materials of plant origin remain in the survey area.

History During power operations the Protected Area supported the components and systems necessary for electrical generation. The location of Survey Unit 05 is adjacent to the transport route used to move spent resin and filter media for radiological survey and offsite removal. Structures and enclosures formerly located in this area were once used for the storage of contaminated materials. A detailed review of the history and radiological characterization of Survey Unit 5 is provided in Appendix 2B and 2E of the LTP (License Termination Plan).

Current Radiological Status Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Based on operational history and former locations of radioactive systems and material transport pathways the radiological status of this survey unit is Class 1.

Post-Construction Expectations Final Status Survey 05C 1 1 will be performed in the following activity sequence:

1. Walkdown: Environmental Services Survey Group (ESSG) personnel will perform a walkdown assessment to ensure survey area preparations are complete and confirm that the following post-construction expectations have been satisfied as applicable:
  • Groundwater and Surface water control is adequate
  • All construction debris has been removed from the survey area
  • The survey location status meets all applicable safety requirements
2. Survey Area Isolation and Control: Control measures will be established to ensure that any potential ongoing decommissioning activities in adjacent locations do not impact the current survey area status. Isolation and control measures include postings, barriers, access points, and the evaluation of ongoing work activities in adjacent areas.

Survey Area Requirements FSS 05C1 1 Page 1 of 2

3. Survey Design and Execution: Survey design and execution will follow the Data Quality Objectives for 05C,1 in accordance with the survey requirements established in procedures RM-76, Final Status Survey Design and RM-77, Final Status Survey Implementation, and LTP, Chapter 5. Survey size will be based on the statistical requirements of the Sign Test for Class 1 areas with soil samples collected in random start, systematic data point locations. Surface scanning will be performed with 100%

survey area coverage. This survey will be conducted in accordance with approved BRP procedures and follow the guidance of NUREG 1575.

4. Data Quality Assessment: Isolation and control of the survey area will be maintained until the survey Data Quality Assessment demonstrates that the regulatory requirements for unrestricted site release have been satisfied.

Survey Area Requirements FSS 05C 11 Page 2 of 2

DATA QUALITY OBJECTIVES Final Status Survey, Release Record 05C11 Central Protected Area STATE THE PROBLEM The Problem:

To demonstrate that the level of residual radioactivity in Class 1 Survey Unit 05 does not exceed the release criteria of 25 mrem/year Total Effective Dose Equivalent (TEDE) as specified in the License Termination Plan (LTP).

Stakeholders:

The primary stakeholders interested in the answer to this problem are Consumers Energy Co., and the general public as represented by the Michigan Department of Environmental Quality (MDEQ), and the US Nuclear Regulatory Commission (USNRC).

The Planning Team:

The planning team consists of members of the BRP Environmental Services Survey Group (ESSG). The primary decision maker will be the Final Status Survey Supervisor.

The Final Status Survey Supervisor will obtain input from the site Construction Group and Scheduling Group for issues relating to schedule and costs.

Schedule:

Approximately five (5) working days are projected to implement the survey and to collect and analyze field data.

Resources:

The primary resources needed to determine the answer to the problem are two (2) technicians to perform fieldwork, one (1) technician to prepare the samples and conduct laboratory analyses, and two (2) survey team members to prepare and review the design, generate maps, coordinate field activities and evaluate data.

2. IDENTIFY THE DECISION Several decisions need to be defined to address the stated problem.

PrincipalStudy Question (1):

Does the mean concentration of residual radioactivity in the survey unit exceed the release criteria stated above?

Decision (1):

Determine whether the mean concentration of residual radioactivity in the survey exceeds the release criteria stated in the problem.

Actions (1):

Alternative actions include failure of the survey unit, remediation, or no action required.

Data Quality Objectives FSS 05C 11 Page 1 of 5

PrincipalStudy Question (2):

Do any areas of elevated activity in the survey unit exceed the release criteria?

The Decision (2):

Determine if any areas of elevated activity in the survey unit exceed the release criteria.

Actions (2):

Alternative actions include confirmation and investigation, performing the elevated measurement comparison (EMC), remediation, or no action required.

PrincipalStudy Question (3):

Is the potential dose from residual radioactivity in the survey unit ALARA as stated?

The Decision (3):

Determine if the potential dose from residual radioactivity in the survey unit is ALARA.

ALARA requirements for soil remediation are defined in Chapter 4 of the LTP.

Actions (3):

Alternative actions include remediation or no action required.

3. IDENTIFY INPUTS TO THE DECISION Information Needed:

Characterization measurements are required to define the radionuclides present and determine the extent and variability of residual radioactivity in the survey area for design and implementation of the survey. Survey area classification, ALARA analysis, potential radionuclides of interest, and site-specific DCGL values are also required inputs to the decision process. The primary information required for evaluation is the analytical results of survey measurements.

Source of the Information:

The soil sample data to be used for survey development are the radionuclide-specific measurements of representative soil samples collected for radiological characterization and excavated soil surveys conducted to determine suitability for transport of excavated soil to the SVA. The soil samples obtained were judgmentally selected as a result of multiple surveys conducted during the excavation and transport process. The ALARA analysis for potential soil remediation is provided in LTP, Section 4.4. Site-specific DCGL values and BRP radionuclides of interest are defined in LTP Chapter 5, Table 5-1 and Procedure RM-76, Final Status Survey Design.

The survey will be conducted in accordance with applicable regulatory guidance as established in LTP Chapter 5 for Class 1 areas. Soil samples will be utilized for radionuclide-specific measurements in this evaluation.

4. BOUNDARIES OF THE STUDY Boundaries of the Survey:

The target population for this survey is the total thickness of prepared soil in the survey area of 1924 M2 .

Data Quality Objectives FSS 05C 11 Page 2 of 5

Temporal Boundaries:

Scanning and sampling in this survey unit will only be performed during daylight hours under dry weather conditions. Surface soils must be free of significant snow cover and standing water prior to surface scanning. Soils must be in a non-frozen state or fragmented for collection to satisfy BRP procedural sampling requirements. The anticipated start date for the survey is September 18, 2006.

Constraints:

Cold weather or rainy conditions may effect the operation of electronic equipment.

Adverse weather conditions that include accumulations of rain or snow may limit area access and delay survey efforts.

5. DEVELOP A DECISION RULE The following decision rules have been developed to define a logical process for choosing among alternative actions for the principal study questions associated with this survey area.

Decision Rule (1):

If all reported concentrations for residual radioactivity are less than the site-specific DCGL's and the unity rule has been satisfied for each sample, then the survey unit meets release criteria. No further action is required.

Decision Rule (2):

If the mean value of activity in the survey unit is greater than the DCGL, then the survey unit fails to meet the release criteria. 1 Remediate, resurvey, and evaluate the results relative to the decision rule.

Decision Rule (3):

If the mean activity in the survey unit is less than the DCGL and any individual sample measurement exceeds this value, conduct the Sign Test and the elevated measurement comparison (EMC) per LTP, Chapter 5 and Procedure RM-76, Final Status Survey Design. If the EMC and the Sign Test have been satisfied then the survey unit meets the release criteria and no further action is required. If the EMC or the Sign Test has not been satisfied then remediate the area(s) of elevated activity, resurvey as appropriate, and evaluate the results relative to the decision rule.

Decision Rule (4):

If the potential dose from residual radioactivity in the survey unit is ALARA, then no further action is necessary. If the potential dose from residual radioactivity in the survey unit is not ALARA, then remediate and resurvey.

6. SPECIFY TOLERABLE LIMITS ON DECISION ERRORS The Null Hypothesis:

It is assumed that residual radioactivity in the survey unit exceeds the release criterion.

'When multiple radionuclides are present the mean activity value is determined as the average of the weighted sum. The DCGL of the weighted sum is 1.

Data Quality Objectives FSS 05CO 1 Page 3 of 5

Type I Error(a):

The a error is the maximum probability of rejecting the null hypotheses when it is true.

Thea error is defined in the LTP at a value of 0.05 (5%) and cannot be changed to a less restrictive value unless prior approval is granted by the USNRC. The a error value of 0.05 will be used for survey planning and data assessment for this survey area.

Type I/ Error(,6).

The /6 error is the probability of accepting the null hypothesis when it is false. A value of 0.05 (5%) will be used for survey planning and data assessment for this survey area.

The Lower Bound of the Gray Region (LBGR):

The LBGR is initially set at one-half the DCGLW for this survey unit. The LBGR may be adjusted during survey design to achieve an optimum relative shift between 1.0 and 3.0.

Relative Shift (A/cy):

The relative shift will be maintained within the range of 1.0 and 3.0 by adjusting the LBGR as appropriate.

7. OPTIMIZE DESIGN FOR OBTAINING DATA Statistical Test Sign Test:

Radionuclides of potential plant origin also present in soil as background activity resulting from fallout constitute only a small fraction of the DCGL. Therefore, the Sign Test will be used where applicable in the survey evaluation to determine if the survey area meets the requirements for unrestricted release.

Number of Samples Determined:

The number of samples required for this survey will be determined based on the relative shift as defined by the requirements of the Sign Test (LTP, Chapter 5.) and Procedure RM-76, Final Status Survey Design. The LBGR is initially set at one-half the DCGL, and may be adjusted as necessary for optimizing the survey design to achieve a relative shift between 1.0 and 3.0. Sample point locations are to be determined using a random start, systematic square grid spacing.

Judgmental Sampling:

Co-60 is the most limiting radionuclide for identification by surface scanning; judgmental surface and subsurface core samples will be collected in any location that exceeds the scan investigation level.

Scan Coverage:

Scanning for this survey area will provide 100% coverage.

Number of Samples for Quality Control:

A minimum of 5% of the sample population will be collected for quality evaluation.

These samples may include sample splits, sample recounts, or third party sample Data Quality Objectives FSS 05C11 Page 4 of 5

analysis. Quality analyses will be conducted as defined in LTP, Chapter 5 and Procedure RM-79, Final Status Survey Quality Control.

Additional Sample Analysis Requirements:

The area of soil excavation intersects the identified waterborne pathway for Tritium migration and shall require Tritium in soil analyses for a minimum of 10% of the sample population. Soil samples will be collected in the same random locations as those selected for QA/QC evaluation and sent to an independent laboratory for Tritium analysis. Data results will be provided in the survey package.

Investigation Levels:

Investigation levels defined in LTP, Chapter 5 and BRP Procedure RM-76, Final Status Survey Design, shall be conservatively established for this survey as shown below:

Investigation Levels for Survey 05C 11 Scan Measurement Soil Sample Analysis

>DCGL > DCGLw The investigation levels for soil sample measurements are meant to include any individual radionuclide result greater than the site-specific DCGL or where the combined radionuclide values exceed the unity rule. Co-60 is the most limiting radionuclide for identification by surface scanning; further investigation will be initiated at any location that exceeds the Co-60 Scan DCGL of 1818 CPM above background as detailed in the survey design.

Data Quality Objectives FSS 05C, 1 Page 5 of 5

FINAL STATUS SURVEY DESIGN Release Record 05C11 Central Protected Area Survey Unit Description Survey 05C, 1 encompasses an area of 1924 m 2 in the central section of the Protected Area. No materials of plant origin exist in this survey unit.

Soil Sample Design Scoping Data Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Input data for survey design were conservatively estimated based on supporting surveys of excavated soils resulting from subsurface structure and component removal within the Protected Area.

Table 1 Input Data for Survey Design (pCi/g)

Radionuclides Cs-137 Co-60 O-

  • 0.524 0.255 DCGL 11.93 3.21
  • Survey data detailed in Attachment 1 Sample Requirements The number of sample data points for this survey is based on the requirements of the Sign Test.

The Unity Rule is used for the presence of multiple radionuclides. The Standard Deviation of the weighted sum is described by the following:

0= V( CS1372 +,YO02 DCGLcs137 WDC-oGo)

(= 0.091 Relative Shift Relative Shift = DCGLw- LBGR (Y

Relative Shift = 1-0.818 0.091 Relative Shift = 2.0 With ( and P3 error levels set at 0.05 and the relative shift of 2.0, the Sign Test requires 15 sample data points (Table 5.5 NUREG 1575).

Survey Design FSS 05C1 l Page 1 of 7

Sample Locations Sample locations are selected in a random start, systematic square grid pattern with the southwest corner of the survey unit as origin (X=0, Y=0). Two numbers between 0 and 1 have been randomly selected and then applied to the survey unit maximum X and Y dimensions to determine the random start location as shown below:

Table 2 Random Numbers I Random #, X Axis Random #, Y Axis 0.091956 0.994458 Survey Unit Dimensions: X = 30.3 meters Y = 70.0 meters Random Start Location X = (0.091956)(30.3) = 2.8 meters With SW Corner Origin: Y = (0.994458)(70.0) = 69.6 meters Sample Spacing As a conservative measure sample spacing will be calculated based on 18 samples for this survey. Samples are located in a systematic square grid pattern with sample spacing determined by the following:

L=A n

Where: A= area of survey unit, and n = number of samples.

1924 L= 91-2 10.3 meters 18 With sample spacing established at 10.3 meters, 19 data points are available for this survey.

Data point locations are identified in Attachment 2.

QAIQC Sampling A minimum of 5% of the sample population and 5% of the scan survey area are required to be selected for QA/QC verification in accordance with BRP Procedure RM-79, Final Status Survey Quality Control. As a conservative measure, three (3) soil samples and 10% of the scan survey area will be selected for QA/QC evaluation. Data point locations for soil samples will be determined by random number selection.

The QA/QC scan starting point and track direction are also determined by random number selection. The first random data point selected will identify the scanning start point and the second random data point will determine the direction in which the scan will track. QA/QC location results are provided in Table 3 below:

Survey Design FSS 05C 11 Page 2 of 7

Table 3 Random Numbers Generated for QA/QC SRandom Random Samples Sample Verification Scan Sample Samples Number Number Split Sample: 3 Start Point: 12 Sample Recount: 5 Scan Toward: 3 Sample Recount: 11 Scan Area Requirement: 193 M 2 Surface Scanning The coverage requirement for surface scanning in this Class 1 area is 100%. The Scan MDC has been established at fractional values of the DCGLw for typical background activity levels at Big Rock Point. Scan MDC values for varying backgrounds are provided in Attachment 3. The investigation level for identification of potential areas of elevated activity in this survey area will be the Scan DCGL as defined by the following:

Scan DCGL = Detector Rating CPM . Exposure Model uR/hr . DCGLw uR/hr pCi/g Scan DCGL for Co-60 = 1818 CPM Scan DCGL for Cs-137 = 3518 CPM Where:'

Detector Rating = 1200 CPM Cs- 137 and 565 CPM Co - 60 uR/hr uR/hr Exposure Model = 1.229 uR/hr Cs-137 and 5.029 uR/hr Co -60 5pCi/g 5 pCi/g DCGLw = 11.93 pCi/g Cs-137 and 3.21 pCi/g Co-60 The DCGLw for Co-60 is the most limiting value for scanning measurements performed to identify areas of potentially elevated activity. Scanning conducted for this survey will assume all residual radioactivity to originate from Co-60 and the instrument response at the Co-60 DCGLw (1818 cpm) will be used as the scanning investigation level for FSS 05C11.

'These values established in EA-BRP-SC-0201, Nal Scanning Sensitivity for Open Land Survey.

Survey Design FSS 05C, 1 Page 3 of 7

Attachment I Design Data - FSS 05C 1 1 Protected Area Supporting Surveys Cs-1 37 Co-60 Survey No. Sequence Activity Activity No. (pCi/g) (pCi/g)

.HH060705 16538,! ,  :.ý1.26 . 0.66 16539' ý0.06 0.06*

HH060705 "HHO60705- _ 16540- 1.050.66 TB062805 '16755 1.16 "G27,

.TB062805 16756", 0-47 . 0.1*

TB062805ý] 16774 0.19 0.31 Mean: 0.698 0.352 Std Dev: 0.524 0.255

  • Measurement system MDA - Co-60 not identified in this sample Survey Design FSS 05C11 Page 4 of 7

Attachment 2 Soil Sample Locations - Survey 05C11 Central Protected Area 89 17190 20821 191 19213 211212 21" 4

227 229231 246 250 2369 35 31639 37 328 1 X=30.3 m 340 "343

- Survey Unit 05C _1 0 i i 1 5 10 I

20 Meters I

  • Sample Location Sample spacing Is 10.3 metors Survey Design FSS 05C11 Page 5 of 7

Attachment 3 Scan MDC In Varying Backgrounds Background d' Si MDCasurveyor Cs-137 Co-60 Cs-137 Co-60 2000 2.48 4 28.64 607.47 0.51 1.08 2.06 1.07 3000 2.48 4 35.07 744.00 0.62 1.32 2.52 1.31 3500 2.48 4 37.88 803.61 0.67 1.42 2.72 1.41 4000 2.48 4 40.50 859.10 0.72 1.52 2.91 1.51 4500 2.48 4 42.95 911.21 0.76 1.61 3.09 1.60 5500 2.48 4 47.49 1,007.38 0.84 1.78 3.42 1.77 6000 2.48 4 49.60 1,052.17 0.88 1.86 3.57 1.85 6500 2.48 4 51.63 1,095.14 0.91 1.94 3.71 1.93 7000 2.48 4 53.57 1,136.48 0.95 2.01 3.85 2.00 8000 2.48 4 57.27 1,214.95 1.01 2.15 4.12 2.14 8500 2.48 4 59.04 1,252.34 1.04 2.22 4.25 2.20 9000 2.48 4 60.75 1,288.65 1.07 2.28 4.37 2.27 9500 2.48 4 62.41 1,323.96 1.10 2.34 4.49 2.33 10500 2.48 4 65.61 1,391.90 1.16 2.46 4.72 2.45 11000 2.48 4 67.16 1,424.65 1.19 2.52 4.83 2.51 11500 2.48 4 68.67 1,456.67 1.21 2.58 4.94 2.56 12000 2.48 4 70.14 1,488.00 1.24 2.63 5.04 2.62

-4 71.5 -15i68 127 26 515~* 2T 13000 2.48 4 73.01 1,548.76 1.29 2.74 5.25 2.73 13500 2.48 4 74.40 1,578.26 1.32 2.79 5.35 2.78 14000 2.48 4 75.77 1,607.22 1.34 2.84 5.45 2.83 14500 2.48 4 77.11 1,635.67 1.36 2.89 5.55 2.88 4i§7&21 re'--&4K248 ~~ 3 4 i64 64,Xi2

_______ ~~o~0' 5,Q3E+to Survey Design FSS 05C 11 Page 6 of 7

Attachment 4 Area Factors for Open Land Survey Evaluation Contaminated_ Calculated Area Factors at Time of Peak Dose Contaminated H-3 Mn-54 Fe-55 Co-60 Sr-90 Cs-137 Eu-152 Eu-154 Eu-155 Area (in 2) 8094 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 4047 1.00 1.01 1.00 1.01 1.00 1.02 1.02 1.01 1.02 2024 1.00 1.03 1.00 1.03 1.00 1.03 1.03 1.03 1.03 1012 1.35 1.04 1.00 1.04 1.00 1.04 1.05 1.04 1.04 506 2.91 1.09 1.98 1.08 1.98 1.13 1.07 1.07 1.06 253 6.05 1.14 3.95 1.13 3.94 1.20 1.11 1.11 1.09 126 12.4 1.20 7.93 1.20 7.87 1.29 1.17 1.16 1.14 63 24.9 1.30 15.8 1.30 15.6 1.41 1.27 1.26 1.23 32 49.2 1.49 31.2 1.49 30.5 1.62 1.44 1.45 1.39 16 98.9 1.78 62.0 1.78 59.9 1.93 1.72 1.73 1.63 8 198 2.38 123 2.38 117 2.58 2.30 2.31 2.14 4 397 3.61 243 3.62 230 3.91 3.49 3.52 3.19 2 794 5.68 473 5.75 452 6.14 5.48 5.55 4.90 1 1590 9.57 905 9.73 887 10.3 9.24 9.39 7.88 Survey Design FSS 05C 11 Page 7 of 7

RM-76 Revision 1 FINAL STATUS SURVEY DESIGN Page 19 of 19 RM-76-5 FINAL STATUS SURVEY APPROVAL AND AUTHORIZATION FOR IMPLEMENTATION Survey Code 05C* 1 Survey Area

Description:

Final Status Survey 05C,1 encompasses 1924 m 2 at or below the grade elevation present during plant power operations in the central section of the Protected Area. No materials of plant origin remain in the survey area.

The survey area is authorized for Final Status Survey Implementation.

629/y 9oDat 7 - [esigned by Date Tech al Review by Date RM-76.doc

RM-77 Revision 2 FINAL STATUS SURVEY IMPLEMENTATION Page 8 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 1 of 3 Step Initial Date (1) 1.0 PREPARATION FOR SURVEY survey#W 1.1 Survey Area Status:

a. Final Status Survey Design has been approved for implementation (see RM-76-5, Final Status Survey Approval and Authorization for Supplementation).
1. Survey area walkdown complete
2. Survey area determined ready for FSS
3. Decommissioning activities that may impact the environmental status of the survey area have been completed.
4. Survey area environment is controlled by barriers and postings or other approved method to restrict access.

2* b. Survey area has been turned over to the Environmental XESILj/G Services Survey Group (ESSG) in acceptable condition for FSS.

1.2 Field Preparation:

a. Survey unit boundaries delineated (Step 6.1.1)
b. Statistical soil samples predetermined in the survey design are located and marked within the survey unit.

(Step 6.1.2)

c. Soil sample locations verified (Step 6.1 .2.c)
d. Instruments and equipment have been collected and calibrated for data measurement and collection e.

(Step 6.1.3)

Field documentation is prepared (Step 6.1.4) r).,(Iz - 01 Llrzoto 67ESS-G RM-77.doc

RM-77 Revision 2 Page 9 of 12 FINAL STATUS SURVEY IMPLEMENTATION RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 2 of 3 Initial Date 2.0 DATA COLLECTION 2.1 Soil Survey:

v/ All soil samples collected and controlled (Step 6.2.1).

SESSG 0-9kio&

2.2 Surface Scan:

. Surface Scan complete. Action response requirements have been conducted on any identified areas exceeding the investigation level (Step 6.3).

uESSG 2.3 Judgmental Soil Samples:

A44 a. Judgmental soil samples have been collected and controlled (Step 6.2.3).

44 b. Deep core profiles performed in areas identified to contain elevated residual activity (Step 6.2.3).

fE_SG S

3.0 SAMPLE PREPARATION AND LABORATORY ANALYSIS 3.1 Sample Preparation (Step 6.4.1):

a. Soil samples are homogenous
b. Soil samples are visibly dry prior to packing C. Non-soil materials have been removed from sample
iz~ d. Soil samples have been transferred to one-liter Marinelli containers and are labeled and sealed. rlý 01j'pa2b4

ýtSSG RM-77.doc

RM-77 Revision 2 FINAL STATUS SURVEY IMPLEMENTATION Page 10 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 3 of 3 Initial Date 3.2 Laboratory Analysis:

7 Isotopic analyses are complete. The spectroscopy report requires a signature of completion by the laboratory analyst and a signature of evaluation documenting that a second V J, 9JO6 (0 level review has been performed (Step 6.4.2). /E! YS-'SG 3.3 Sample Control and Documentation:

z Chain of custody documentation exhibits control of soil samples (Step 6.4.3). a,,

c9 /Zyo 2c

?E S-SG Reviewed by Date RM-77.doc

RM-59 Revision 11 SAMPLING AND ANALYSIS OF OPEN LAND Page 7 of 13 AREAS FOR SITE CHARACTERIZATION SURVEYS ATTACHMENT RM-59-1 SAMPLING AND ANALYSIS REPORT Date: 09-18-2006 Time: 1600 Location: 05C1 1 Tech: TRS/WMH/JNS SURVEY IDENTIFICATION / DESCRIPTION Survey 05C01 encompasses 1924 m2 at or below the grade elevation present during plant Power operations in the central section of the Protected Area. No materials of plant origin remain in this area.

SURVEY TYPE Survey Type: Characterization X Scan (Motive)

Remediation X Final Scan (Static)

Trenching and Digging (use RM-59-4)

SURVEY DESIGN Sample Collection: _ Judgmental _ Random X Systematic _ Large Container Assay Scan Coverage: 100%

ANALYSIS Inst.SN/Cal Due 186201/09-30-2006 DAILY CHECK: X SAT UNSAT INIT: TRS Inst.SN/Cal Due 186194/02-08-2007 DAILY CHECK: X SAT UNSAT INIT: TRS Inst.SN/Cal Due 193709/02-21-2007 DAILY CHECK: X SAT UNSAT INIT: TRS Inst.SN/Cal Due Det. #6 DAILY CHECK: X SAT UNSAT INIT: Jp Inst.SN/Cal Due DAILY CHECK: SAT UNSAT INIT:

Investigation of Unidentified Peaks: X SAT UNSAT INIT: JLR Minimum Detectable Activity (Section 5.3.2) X SAT UNSAT INIT: JLR COMMENTS Survey 05C01 was performed in a random start, square arid, systematic samplina pattern with samples collected at 20 data point locations. Laboratory analyses did not identify residual radioactivity above trace levels of the DCGL value. Surface scanning identified no areas of elevated residual radioactivity. The results of the QA/QC verification scan (10%) were consistent with the scan values identified in the survey.

Technician Signature: ,,Jt , ,LL -e:

Second Level Review Signature: */(t//$f*-4/,/. Date: /01// /(

RM-59.doc

Soil Sample Activity Summary Release Record 05Cll Central Protected Area Survey Unit 05C1_1 0 4.5 9 18 Meters 1i 1 1 :1 A S Sample Location

Surface Scan Summary Release Record 05C11 Central Protected Area 3.81 17 3.2 14.0

3. 7 3- 1 4.1 5.0~ 4,1 4.3 4.14.

3.5 3. 9. 4.1 o 14A 36 1I4.4. 0 4.4 4.04f 4.5

~ ____

__ ____ ___ 4.4 I~ 4I 2

-Survey Unit 05CI_1 0 4.5 9 18 Meten S Sample Location Ili ii i ii ii RED Values are Average Mobile Scan General Area Activity (kcpm)

BLUE Values are Average Verification Scan General Area Activity (kcpm)

GREY Values are Average General Background Area Activity (kcpm)

Primary Scan : 'A"920;91WýW Technician Signature: Dats:

Time:

QC Verification Scan: ,/0  %

Technician Signature: Date: £ Time:

RM-72 Revision 0 SAMPLE CHAIN-OF-CUSTODY Page 4of 5 05C1l RM-72-1 CHAIN-OF-CUSTODY RECORD Sample Number Sampling Location Date Time Final Disposition of Sample 1 Grid#329 (2.8) (7.2) o-0g- IAqo 2 Grid#330 (3.1) (7.2) _ -__-0_ _____

3 Grid#318 (3.1) (7.6) 0 )2fo 3 QA Split Grid # 318 (3.1) (7.6) *j76 (.L*t *L 4 Grid#317 (2.8) (7.6) 5 (R) Grid # 304 (2.5) (8.0) OISCD' 6 Grid #305 (2.8) (8.0) 2SQ 7 Grid#306 (3.1) (8.0) - I)S 8 Grid#268 (3.1) (8.4) ?4-V ( O' 9 Grid#267 (2.8) (8.4) 1(/3-0(p 120 10 Grid # 266 (2.5) (8.4) c4oI 3 03 11 (R) Grid#247 (2.5) (8.8) qJ(g*fo (1300*5 12 Grid # 248 (2.8) (8.8) - -) ' ,,? O&'

13 Grid # 249 (3.1) (8.8) Nj-0 61 13to 14 Grid#230 (3.1) (9.2) 1213 15 Grid #229 (2.8) (9.2) - I 31S\

16 Grid #228 (2.5) (9.2) (

17 Grid#209 (2.5) (9.6) qit"-o-0 13P, 18 Grid #210 (2.8) (9.6) ' _

19 Grid#211 (3.1) (9.6) 7-[*gý-(, 13;3-T (Samples may be analyzed and stored, shipped for offsite evaluation or analyzed and disposed of.)

  • "/ C* t'v) Tim RReeDate e odn~c, *ito n
1. Reli quished/ :y:, I,, *, Dt Tie, y
2. Relinquishedb y: Date Time Received in good condition by:

f1LT- ra, e____ __________6__-3

3. Relinquished by: Date Time Received in good condition by:
4. Relinquished by: Date Time Received in good condition by:

RM-72.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 19 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 1 of 8 FINAL STATUS SURVEY: o5c, I 1.0 DATA VERIFICATION 1.1 Data Acceptance Review the Implementation Checklist (RM-77-1) to verify that survey isolation and control measures were executed prior to FSS and are being maintained.

Review RM-77, Final Status Survey Implementation, to verify that methods, techniques, and survey activities required for FSS have been applied in accordance with the appropriate procedures.

1.2 Field QC Records:

Review all assessments, Condition Reports and audits to ensure that identified issues have been resolved.

Comments:

.i*1 Verify scan instrumentation was in calibration and the QC source checks were performed prior to and after surveys.

Verify daily QC source checks for Canberra gamma spectroscopy detector properly logged prior to soil sample analysis.

1.3 Review Verification:

__ Verify that the Data Quality Objectives are complete.

____Verify that the survey design has been technically reviewed.

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 20 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 2 of 8 I Z. Verify that gamma spectroscopy results have received a technical review.

Verify the Sample and Analysis Report (RM-59-1) is completed and reviewed.

Data Verification Completed:

&No Comments Do O at/3-e Assesso'r Date

//

6/

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 21 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 3 of 8 2.0 DATA VALIDATION 2.1 Documentation Review:

Perform documentation review for quality control purposes and validate the data collected is complete and appropriate for use as defined by the survey design. Documentation includes:

Field measurement records Chain-of-custody Quality Control (QC) measurement records Current qualification of survey personnel Corrective Action Reports Data inputs (laboratory spectroscopy)

Sample preparation techniques 2.2 Detection Limit Review:

,__ Scan MDCs are below established site DCGLs.

/j Forced-count values are assigned as necessary when activity is not detected in a sample.

__ Minimum Detectable Concentration (MDC) values of gamma spectroscopy are below established DCGLs.

2.3 Quality Control (QC) Data Review:

,,__ Quality Control (QC) data results have received required reviews and are complete and consistent.

,_ Results of judgmental samples have been reviewed and evaluated.

__ Review to ensure that the analytical results of judgmental samples do not impact the evaluation for unrestricted release of the survey area.

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 22 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 4 of 8 2.4 Qualification of Data:

Statistical radionuclide-specific measurements for completeness. Evaluate the survey for determination of data usability and confirm that sufficient qualified data are present for the decision process.

a. Total number of statistical samples planned for the survey:
b. Total number of statistical samples determined as valid: /

b x 120 lo=

c. Calculate % Completeness: f7______

Qualified data are A 00% completeness and are sufficient to support the Sign Test requirement for determination of unrestricted release.

Data Validation Completed: O*-sNo Comments:

/0 o(?

Assessor Date RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 23 of 26 RM-78-3 DATA ASSESSMENT REPORT

.Page 5 of 8 3.0 DATA QUALITY ASSESSMENT 3.1 Review the DQOs and Survey Design:

Confirm that all inputs to the decision have been reviewed and are complete.

j/ Verify that boundaries or constraints identified in the survey area have not affected the quality of the data.

_--___ Review the Statement of Hypothesis and confirm that it remains relevant.

_ Confirm that Type I and Type IIerror limits are consistent with DQOs.

_"_" Confirm that the survey design is consistent with DQOs and that the appropriate number of data points were obtained.

3.2 Preliminary Review:.

3.2.1 Preliminary Evaluation:

Quality Assessment (QA) reports consistent with procedure RM-79, Final Status Survey Quality Control.

Survey is of sufficient intensity to satisfy classification requirement.

Z Potential trends of radioactivity levels in the survey area do not impact a decision for unrestricted release.

Comments:

RM-78.doc

I-RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 24 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 6 of 8 3.2.2 Calculate Basic Statistical Quantities:

a. Number of qualified data points /
b. Calculation of the Mean 0. 0OSI, (SOP-)
c. Calculation of the Median t9.ocLog-)
d. Calculation Standard Deviation k Attach graphic representation of the data if any radionuclide-specific measurements exceed 50% of the DCGL.

.. " Sample QA/QC measurements consistent with FSS data 3.3 Statistical Evaluation:

NOTE: If all measurement data are less than the DCGLW, statistical testing in not required and the survey unit meets the regulatory requirement for unrestricted release.

All survey measurements are below the DCGLw.

3.3.1 Verify Assumptions of the Survey Design

_ _ Review the posting plot to verify that the data exhibits spatial independence. Spatial trends must be investigated and resolved prior to further assessment.

__Review to verify dispersion symmetry. The appearance of skewed data must be investigated for cause and documented prior to further assessment.

RM-78.doc

I, RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 25 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 7 of 8

,..I* Review the dataset standard deviation and range for data variance.

Questionable data must be investigated for cause and documented prior to further assessment.

jVerify that the data exhibits adequate power and confirm that the sample size is sufficient to satisfy the DQOs.

3.4 Draw Conclusions from the Data:

3.4.1 Investigation Levels and Response Actions v__ Determine if data results have exceeded any investigation level.

Document find ings~~~k7X/A20~ ~4e~~

  • 3.4.2 Evaluation for Unrestricted Release Select applicable conclusion:

Survey area acceptance criteria met and survey area satisfies the requirements for unrestricted release:

/' All concentrations are less than the DCGLw. The Null Hypothesis is rejected.

The mean concentration of the survey area is below the DCGLw but individual measurements in the survey unit exceed the DCGLw. The Sign Test and EMC evaluation are successful and the Null Hypothesis is rejected.

RM-78.doc

I, RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 26 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 8 of 8 4,_ Survey area acceptance criteria not met and survey area fails to satisfy the requirements for unrestricted release:

,4_ The mean concentration in the survey area exceeds the DCGLw. and the null hypothesis is confirmed.

4_.The mean concentration of the survey area is below the DCGLw but individual measurements in the Unit exceed the DCGLw..

The Sign Test and EMC evaluation are unsuccessful and the null hypothesis is confirmed.

Data Quality Assessment Completed: Ye No Comments

/o-/3- O V Date Reviews:,

Date Tech i'ca fReview ES Superintendent Date RPES Manager Date RM-78.doc

RM-78-3, Attachment I Statistical Quantities Release Record 05C 11 Central Protected Area Sample Cs-137 Co-60 Weighted **Weighted Sum Number (pCi/gm) (pCilgm) Sum (SOR) <DCGLw? DCGL-W. Sum Sign.

1 0.0218 0.0120 0.0056 yes 0.9944 +1 2 0.0279 0.0173 0.0077 yes 0.9923 +1 3 0.0559 0.0106 0.0080 yes 0.9920 +1 4 0.0501 0.0002 0.0043 yes 0.9957 +1 5 0.0710 0.0404 0.0185 yes 0.9815 +1 6 0.0745 0.0144 0.0107 yes 0.9893 +1 7 0.1045 0.0059 0.0106 yes 0.9894 +1 8 0.1357 -0.0099 0.0083 yes 0.9917 +1 9 0.0861 0.0101 0.0104 yes 0.9896 +1 10 0.0462 0.0048 0.0054 yes 0.9946 +1 11 0.0124 -0.0006 0.0009 yes 0.9991 +1 12 0.0018 0.0119 0.0039 yes 0.9961 +1 13 0.0386 0.0082 0.0058 yes 0.9942 +1 14 -0.0002 -0.0108 -0.0034 yes 0.9966 +1 15 0.0390 0.0047 0.0047 yes 0.9953 +1 16 0.0208 -0.0117 -0.0019 yes 0.9981 +1 17 0.0531 -0.0152 -0.0003 yes 0.9997 +1 18 0.0384 -0.0027 0.0024 yes 0.9976 +1 19 0.0110 0.0126 0.0048 yes 0.9952 +1 Std. Dev 0.0356 0.0129 0.0051 Mean 0.0468 0.0054 0.0056 Median 0.0390 0.0059 0.0054 Number of Positive Differences (S+): n/a Critical Value, k, Table 1.3 of Marssim: n/a S+ >than k?: n/a Survey Unit Pass or Fail: **Pass

  • Note: Forced-Count values are used for samples with activity levels below the MDA.
    • Note: If all measurement data are less than the DCGL ., then the Sign Test is not required.

RM-79 Revision 1 FINAL STATUS SURVEY QUALITY CONTROL Page 11 of 13 RM-79-1 FSS QUALITY CONTROL EVALUATION RESULTS FSS Package # 5~5X2, / QC Package #

  • NOTE: If Acceptance Criteria is not met, completion of Attachment RM-79-2, FSS Quality Control Investigation Results, is required.

Comments:

14U '

/ tj Reviews:

!-/ ip060 valuato Date Technical Review Date RM-79.doc

QA Verification Split Sample Analysis Table I Date: 9/20/2006 Acceptance Criteria Resolution Ratio QA: 05C,1 Central Protected Area <4 N/A 4-7 0.5-2.0 Type: Split Sample 8-15 0.6-1.66 16-50 0.75-1.33 Lab: In-House 51-200 0.8-1.25

>200 0.85-1.18 A B C D E F BRP Results in Result BRP BRP BRP Acceptance Split Comparison Agreement Sample Radionuclide Below Results  % Error BRP Ratio Results Split Results Ratio Resolution(pi) opr Beo (pCi/g) (Sigma) (Table 1) Below MDA (pC/g) FIA Compare MDA G with D) 3 Co-60 0.0633 n/a n/a n/a < 0.0594 0.94 YES 3 Cs-137 0.0559 38.89 2.57 n/a 0.0414 0.74 YES I .4 -I- I 1 1 4 I 4 4. 4. 4- I 4 I 4 4 I 4 4- 4. 4 4-4 .4 4. 4 4 4 .4 4 4- 4 I .4 .4 4 4 4. 4 4 4

£ .4 .4 I I 4. I 4 4-L .4 _____ .4 _______ 1 ________ 1 ______ .4 _______ 1 _________

Resoltuionc (A)(B7A 0 I

< Indicatesresults less than the MDA.

  • Note Results are consideredin agreement for MDA and near-MDA measurementcomparisons Results fthat fail agreement must be investigatedper RM-79.

QA Verification I Sample Recount Analysis Table I Date: 9/20/2006 Acceptance Criteria Resolution Ratio QA: 05C,1 Central Protected Area <4 N/A 4-7 0.5-2.0 Type: Sample Recounts 8-15 0.6-1.66 16-50 0.75-1.33 Lab: In- House 51-200 0.8-1.25

>200 0.85-1.18 A B C D E F G BRP Results in BRP BRP Acceptance Recount Comparison Sample SapeRadionuclide Rdould Result eut BRe t Results  %

% EBRP Error Reouin atio Ratio Recount Reut Results RatioCopr Agreement Below Resolution Result MDA (pCi/g) (Sigma) (Table 1) Below MDA (pCi/g)sCompare F/A G with D)

___Below MDAth__D) ___D__G 5 Co-60 < 0.0731 n/a n/a n/a 0.0822 1.12 YES 5 Cs-137 0.0710 24.90 4.02 0.5-2.0 0.0426 0.60 YES 11 Co-60 < 0.0494 n/a n/a n/a 0.0607 1.23 YES 11 Cs-137 < 0.0523 n/a n/a n/a 0.0564 1.08 YES Resolution C = (A)(B 0

< Indicates results less than the MDA.

  • Note Results are consideredin agreement for MDA and near-MDA measurementcomparisons Results fthat fail agreementmust be investigatedperRM-79.

Tritium in Soil Data Results Final Status Survey 05C 1 1 Sample Tritium in Soil Number pCi/g 3 1.227 5 0.009 11 0.013 Mean: 0.4163 Median: 0.0130 St. Dev: 0.7021 Note: The DCGL for Tritium is 327 pCi/g.

Sample results are less than 0.4% of the DCGL

09/2')/200 18:09 8475644517 ý'Aor- I U / I '.ý Environmental, Inc.

Midwest Laboratory

-* 131Allegheny Teconologles Co, 700 LUnmwehr Rozd

  • Nortnbrook, IL 6006&!2310 ph. (847) 564-0700 - fax (847) 564.4517 Mr. David W. Parish LABORATORY REPORT NO. 8022-100-234 Big RocK Point DATE: 09-22-2006 10269 US-31 North SAMPLES RECEIVED: 09-20-2006 Charlevoix, MI 49720 PURCHASE ORDER NO:

Below are the results of the analyses for tritium on three soil samples.

Excavated Soil Survey 05C11 Sample Collection Lab Concentration MDA Description Date Code (pCi/g of soil) (pCi/g of soil)

H-3 3 09-18-06 BRSO-6400 1.227 +/- 0.031 < 0.018 3 09-18-06 BRSO-6401 0.980 +/-0.028 < 0.018 5 09-18-06 BRSO-6402 0.009 t 0.007 < 0.013 11 09-18-06 SRSO-6403 0.013 +/- 0.007 < 0.012 Denotes a duplicate, The error given is the probable counting error at 95 % confidence level. The less than, (<), value is based on 4.66 sigma counting error for background sample.

APPROVED BY Tony Coorlim.

Quality Assurance SEP 22 2006 18:51 8475644517 PFGE. 10

/,

ATTACHMENT 4 CONSUMERS ENERGY BIG ROCKPOINT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION CLASS 1 FINAL STATUS SURVEY RELEASE RECORD, 06C 1 1, SOUTH CENTRAL PROTECTED AREA October 24, 2006 37 Pages

Class 1 Final Status Survey Release Record 06C1 1 South Central Protected Area SURVEY PACKAGE CLOSURE Final Status Survey Documentation is authorized for closure. All required reviews are complete and the evaluation of data results have satisfied the criteria established for unrestricted release.

Signed: ýF -liný ý Date: to ---5o6 (ESSG)

Signed: Date: /d-,:9 -- o.6 TES Superintendent)

Signed: , -&E-'- e Date: /o--2-5-6o 6

,(F'Pý & ES kan-ager)

Survey Area Requirements Final Status Survey, Release Record 06C11 South Central Protected Area Survey Description Final Status Survey 06C 1 1 encompasses 1977 m 2 at or below the grade elevation present during plant power operations in the south central section of the Protected Area. No materials of plant origin remain in the survey area.

History During power operations the Protected Area supported the components and systems necessary for electrical generation. The location of Survey Unit 06 is adjacent to the transport route used to move spent resin and filter media for radiological survey and offsite removal. Structures and enclosures formerly located in this area were once used for the storage of contaminated materials. A detailed review of the history and radiological characterization of Survey Unit 06 is provided in Appendix 2B and 2E of the LTP (License Termination Plan).

Current Radiological Status Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Based on operational history and former locations of radioactive systems and material transport pathways the radiological status of this survey unit is Class 1.

Post-Construction Expectations Final Status Survey 06C, 1 will be performed in the following activity sequence:

1. Walkdown: Environmental Services Survey Group (ESSG) personnel will perform a walkdown assessment to ensure survey area preparations are complete and confirm that the following post-construction expectations have been satisfied as applicable:
  • Groundwater and Surface water control is adequate 0 All construction debris has been removed from the survey area 0 The survey location status meets all applicable safety requirements
2. Survey Area Isolation and Control: Control measures will be established to ensure that any potential ongoing decommissioning activities in adjacent locations do not impact the current survey area status. Isolation and control measures include postings, barriers, access points, and the evaluation of ongoing work activities in adjacent areas.

Survey Area Requirements FSS O6C 1 Page 1 of 2

3. Survey Design and Execution: Survey design and execution will follow the Data Quality Objectives for 06C1 1 in accordance with the survey requirements established in procedures RM-76, Final Status Survey Design and RM-77, Final Status Survey Implementation, and LTP, Chapter 5. Survey size will be based on the statistical requirements of the Sign Test for Class 1 areas with soil samples collected in random start, systematic data point locations. Surface scanning will be performed with 100%

survey area coverage. This survey will be conducted in accordance with approved BRP procedures and follow the guidance of NUREG 1575.

4. Data Quality Assessment: Isolation and control of the survey area will be maintained until the survey Data Quality Assessment demonstrates that the regulatory requirements for unrestricted site release have been satisfied.

Survey Area Requirements FSS O6C 1 Page 2 of 2

J DATA QUALITY OBJECTIVES Final Status Survey, Release Record 06C11 South Central Protected Area STATE THE PROBLEM The Problem:

To demonstrate that the level of residual radioactivity in Class 1 Survey Unit 06 does not exceed the release criteria of 25 mrem/year Total Effective Dose Equivalent (TEDE) as specified in the License Termination Plan (LTP).

Stakeholders:

The primary stakeholders interested in the answer to this problem are Consumers Energy Co., and the general public as represented by the Michigan Department of Environmental Quality (MDEQ), and the US Nuclear Regulatory Commission (USNRC).

The Planning Team:

The planning team consists of members of the BRP Environmental Services Survey Group (ESSG). The primary decision maker will be the Final Status Survey Supervisor.

The Final Status Survey Supervisor will obtain input from the site Construction Group and Scheduling Group for issues relating to schedule and costs.

Schedule:

Approximately five (5) working days are projected to implement the survey and to collect and analyze field data.

Resources:

The primary resources needed to determine the answer to the problem are two (2) technicians to perform fieldwork, one (1) technician to prepare the samples and conduct laboratory analyses, and two (2) survey team members to prepare and review the design, generate maps, coordinate field activities and evaluate data.

2. IDENTIFY THE DECISION Several decisions need to be defined to address the stated problem.

PrincipalStudy Question (1):

Does the mean concentration of residual radioactivity in the survey unit exceed the release criteria stated above?

Decision (1):

Determine whether the mean concentration of residual radioactivity in the survey exceeds the release criteria stated in the problem.

Actions (1):

Alternative actions include failure of the survey unit, remediation, or no action required.

Data Quality Objectives FSS 06C 1I Page 1 of 5

PrincipalStudy Question (2):

Do any areas of elevated activity in the survey unit exceed the release criteria?

The Decision (2):

Determine if any areas of elevated activity in the survey unit exceed the release criteria.

Actions (2):

Alternative actions include confirmation and investigation, performing the elevated measurement comparison (EMC), remediation, or no action required.

PrincipalStudy Question (3):

Is the potential dose from residual radioactivity in the survey unit ALARA as stated?

The Decision (3):

Determine if the potential dose from residual radioactivity in the survey unit is ALARA.

ALARA requirements for soil remediation are defined in Chapter 4 of the LTP.

Actions (3):

Alternative actions include remediation or no action required.

3. IDENTIFY INPUTS TO THE DECISION Information Needed:

Characterization measurements are required to define the radionuclides present and determine the extent and variability of residual radioactivity in the survey area for design and implementation of the survey. Survey area classification, ALARA analysis, potential radionuclides of interest, and site-specific DCGL values are also required inputs to the decision process. The primary information required for evaluation is the analytical results of survey measurements.

Source of the Information:

The soil sample data to be used for survey development are the radionuclide-specific measurements of representative soil samples collected for radiological characterization and excavated soil surveys conducted to determine suitability for transport of excavated soil to the SVA. The soil samples obtained were judgmentally selected as a result of multiple surveys conducted during the excavation and transport process. The ALARA analysis for potential soil remediation is provided in LTP, Section 4.4. Site-specific DCGL values and BRP radionuclides of interest are defined in LTP Chapter 5, Table 5-1 and Procedure RM-76, Final Status Survey Design.

The survey will be conducted in accordance with applicable regulatory guidance as established in LTP Chapter 5 for Class 1 areas. Soil samples will be utilized for radionuclide-specific measurements in this evaluation.

4. BOUNDARIES OF THE STUDY Boundariesof the Survey:

The target population for this survey is the total thickness of prepared soil in the survey area of 1977 M2 .

Data Quality Objectives FSS 06C,1 Page 2 of 5

Temporal Boundaries:

Scanning and sampling in this survey unit will only be performed during daylight hours under dry weather conditions. Surface soils must be free of significant snow cover and standing water prior to surface scanning. Soils must be in a non-frozen state or fragmented for collection to satisfy BRP procedural sampling requirements. The anticipated start date for the survey is September 14, 2006.

Constraints:

Cold weather or rainy conditions may effect the operation of electronic equipment.

Adverse weather conditions that include accumulations of rain or snow may limit area access and delay survey efforts.

5. DEVELOP A DECISION RULE The following decision rules have been developed to define a logical process for choosing among alternative actions for the principal study questions associated with this survey area.

Decision Rule (1):

If all reported concentrations for residual radioactivity are less than the site-specific DCGL's and the unity rule has been satisfied for each sample, then the survey unit meets release criteria. No further action is required.

Decision Rule (2):

If the mean value of activity in the survey unit is greater than the DCGL, then the survey unit fails to meet the release criteria. 1 Remediate, resurvey, and evaluate the results relative to the decision rule.

Decision Rule (3):

If the mean activity in the survey unit is less than the DCGL and any individual sample measurement exceeds this value, conduct the Sign Test and the elevated measurement comparison (EMC) per LTP, Chapter 5 and Procedure RM-76, Final Status Survey Design. If the EMC and the Sign Test have been satisfied then the survey unit meets the release criteria and no further action is required. If the EMC or the Sign Test has not been satisfied then remediate the area(s) of elevated activity, resurvey as appropriate, and evaluate the results relative to the decision rule.

Decision Rule (4):

If the potential dose from residual radioactivity in the survey unit is ALARA, then no further action is necessary. If the potential dose from residual radioactivity in the survey unit is not ALARA, then remediate and resurvey.

6. SPECIFY TOLERABLE LIMITS ON DECISION ERRORS The Null Hypothesis:

It is assumed that residual radioactivity in the survey unit exceeds the release criterion.

When multiple radionuclides are present the mean activity value is determined as the average of the weighted sum. The DCGL of the weighted sum is 1.

Data Quality Objectives FSS 06C 11 Page 3 of 5

Type I Error(a):

The a error is the maximum probability of rejecting the null hypotheses when it is true.

Thea error is defined in the LTP at a value of 0.05 (5%) and cannot be changed to a less restrictive value unless prior approval is granted by the USNRC. The a error value of 0.05 will be used for survey planning and data assessment for this survey area.

Type II Error(,B):

The f8 error is the probability of accepting the null hypothesis when it is false. A value of 0.05 (5%) will be used for survey planning and data assessment for this survey area.

The Lower Bound of the Gray Region (LBGR):

The LBGR is initially set at one-half the DCGLW for this survey unit. The LBGR may be adjusted during survey design to achieve an optimum relative shift between 1.0 and 3.0.

Relative Shift (A/a):

The relative shift will be maintained within the range of 1.0 and 3.0 by adjusting the LBGR as appropriate.

7. OPTIMIZE DESIGN FOR OBTAINING DATA Statistical Test Sign Test:

Radionuclides of potential plant origin also present in soil as background activity resulting from fallout constitute only a small fraction of the DCGL. Therefore, the Sign Test will be used where applicable in the survey evaluation to determine if the survey area meets the requirements for unrestricted release.

Number of Samples Determined:

The number of samples required for this survey will be determined based on the relative shift as defined by the requirements of the Sign Test (LTP, Chapter 5.) and Procedure RM-76, Final Status Survey Design. The LBGR is initially set at one-half the DCGL and may be adjusted as necessary for optimizing the survey design to achieve a relative shift between 1.0 and 3.0. Sample point locations are to be determined using a random start, systematic square grid spacing.

Judgmental Sampling:

Co-60 is the most limiting radionuclide for identification by surface scanning; judgmental surface and subsurface core samples will be collected in any location that exceeds the scan investigation level.

Scan Coverage:

Scanning for this survey area will provide 100% coverage.

Number of Samples for Quality Control:

A minimum of 5% of the sample population will be collected for quality evaluation.

These samples may include sample splits, sample recounts, or third party sample Data Quality Objectives FSS 06C1 1 Page 4 of 5

analysis. Quality analyses will be conducted as defined in LTP, Chapter 5 and Procedure RM-79, Final Status Survey Quality Control.

Additional Sample Analysis Requirements:

The area of soil excavation intersects the identified waterborne pathway for Tritium migration and shall require Tritium in soil analyses for a minimum of 10% of the sample population. Soil samples will be collected in the same random locations as those selected for QA/QC evaluation and sent to an independent laboratory for Tritium analysis. Data results will be provided in the survey package.

Investigation Levels:

Investigation levels defined in LTP, Chapter 5 and BRP Procedure RM-76, Final Status Survey Design, shall be conservatively established for this survey as shown below:

Investigation Levels for Survey 06C1 1 Classification Scan Measurement Soil Sample Analysis Class 1 > DCGL > DCGLw The investigation levels for soil sample measurements are meant to include any individual radionuclide result greater than the site-specific DCGL or where the combined radionuclide values exceed the unity rule. Co-60 is the most limiting radionuclide for identification by surface scanning; further investigation will be initiated at any location that exceeds the Co-60 Scan DCGL of 1818 CPM above background as detailed in the survey design.

Data Quality Objectives FSS 06C11 Page 5 of 5

FINAL STATUS SURVEY DESIGN Release Record 06C11 South Central Protected Area Survey Unit Description Survey 06C11 encompasses an area of 1977 m2 in the south central section of the Protected Area. No materials of plant origin exist in this survey unit.

Soil Sample Design Scoping Data Scoping measurements and supporting surveys performed in the Protected Area following removal of subsurface components and demolition debris do not indicate the presence of elevated levels of residual radioactivity in this survey area. Input data for survey design were conservatively estimated based on supporting surveys of excavated soils resulting from subsurface structure and component removal within the Protected Area.

Table 1 Input Data for Survey Design (pCi/g)

Radionuclides I Cs-137 I Co-60 O"*

DCGL

  • Survey data detailed in Attachment 1 0.524 11.93 0.255 3.21 I Sample Requirements The number of sample data points for this survey is based on the requirements of the Sign Test.

The Unity Rule is used for the presence of multiple radionuclides. The Standard Deviation of the weighted sum is described by the following:

JG CCS137 DCGLcsl37 )

2 GCOSO

+DCGLcoeo) 2 Cy 0.ý524 +2(0.2515ý y= 0.091 Relative Shift Relative Shift = DCGLw-LBGR Relative Shift = 1-0.818 0.091 Relative Shift = 2.0 With ca and [3 error levels set at 0.05 and the relative shift of 2.0, the Sign Test requires 15 sample data points (Table 5.5 NUREG 1575).

Survey Design FSS 06C,1 Page 1 of 7

Sample Locations Sample locations are selected in a random start, systematic square grid pattern with the southwest corner of the survey unit as origin (X=0, Y=0). Two numbers between 0 and 1 have been randomly selected and then applied to the survey unit maximum X and Y dimensions to determine the random start location as shown below:

Table 2 Random Numbers Random #, X Axis Random #, Y Axis 0.803882 0.025830 Survey Unit Dimensions: X = 60.0 meters Y = 39.3 meters Random Start Location X = (0.803882)(60.0) = 48.2 meters With SW Corner Origin: Y = (0.025830)(39.3) = 1.0 meters Sample Spacing As a conservative measure sample spacing will be calculated based on 18 samples for this survey. Samples are located in a systematic square grid pattern with sample spacing determined by the following:

L=A n

Where: A= area of survey unit, and n = number of samples.

L 1977 1- 10.4 meters 18 With sample spacing established at 10.4 meters, 20 data points are available for this survey.

Data point locations are identified in Attachment 2.

QAIQC Sampling A minimum of 5% of the sample population and 5% of the scan survey area are required to be selected for QA/QC verification in accordance with BRP Procedure RM-79, Final Status Survey Quality Control. As a conservative measure, three (3) soil samples and 10% of the scan survey area will be selected for QA/QC evaluation. Data point locations for soil samples will be determined by random number selection.

The QA/QC scan starting point and track direction are also determined by random number selection. The first random data point selected will identify the scanning start point and the second random data point will determine the direction in which the scan will track. QA/QC location results are provided in Table 3 below:

Survey Design FSS 06C1 l Page 2 of 7

Table 3 Random Numbers Generated for QA/QC Random Random QA/QC Soil Sample Verification Scan Sample Samples Number ,Number Split Sample: 12 Start Point: 11 Sample Recount: 14 Scan Toward: 17 Sample Recount: 16 IMinimum Scan Area Requirement: 198 m 2 Surface Scanning The coverage requirement for surface scanning in this Class 1 area is 100%. The Scan MDC has been established at fractional values of the DCGLwfor typical background activity levels at Big Rock Point. Scan MDC values for varying backgrounds are provided in Attachment 3. The investigation level for identification of potential areas of elevated activity in this survey area will be the Scan DCGL as defined by the following:

Scan DCGL = Detector Rating CPM . Exposure Model uR/hr . DCGLw uR/hr pCi/g Scan DCGL for Co-60 = 1818 CPM Scan DCGL for Cs-137 = 3518 CPM Where:1 Detector Rating = 1200 CPMCs -137 and 565 CPM Co -60 uR/hr uR/hr Exposure Model = 1.229uR/hr Cs- 137 and 5.029uR/hr Co-60 5pCi/g 5 pCi/g DCGLw = 11.93 pCi/g Cs-137 and 3.21 pCi/g Co-60 The DCGLw for Co-60 is the most limiting value for scanning measurements performed to identify areas of potentially elevated activity. Scanning conducted for this survey will assume all residual radioactivity to originate from Co-60 and the instrument response at the Co-60 DCGLw (1818 cpm) will be used as the scanning investigation level for FSS 06C, 1.

'These values established in EA-BRP-SC-0201, Nal Scanning Sensitivity for Open Land Survey.

Survey Design FSS 06C 11 Page 3 of 7

Attachment I Design Data - FSS 06C1 l Protected Area Supporting Surveys Cs-1 37 Co-60 Survey No. Sequence Activity Activity No. (pCi/g) (pcilg) 1111060705 *16588  :-.:26t, 0.m66'

,HH0607051ý 16539., 0i.'062 06

ý,HH06075 '16540, ~1.05 j0.6&11 TB062AQ5 '16755 1 16 0.27

~TB062405 16756 0,47 '0.15*

TB062805 16774 0.1903 Mean: 0.698 0.352 Std Dev: 0.524 0.255

  • Measurement system MDA - Co-60 not identified in this sample Survey Design FSS 06C1 I Page 4 of 7

Attachment 2 Soil Sample Locations - Survey 06C11 South central Protected Area 31 U al 2 19 (17 2I 1 0 5 10 2 Meters SurveyUnit06C1

. Sample Location Survey Design FSS 06C11 Page 5 of 7

Attachment 3 Scan MDC In Varying Backgrounds Background d' i Si MDCRsurvevor Cs-137 Co-60 Cs-137 Co-60 2000 2.48 4 28.64 607.47 0.51 1.08 2.06 1.07 25,00~ 2.48 ~4 2.27 b >67ý,~ > 57,, >!,-1,U2O 2__30_ 1.20 3000 2.48 4 35.07 744.00 0.62 1.32 2.52 1.31 3500 2.48 4 37.88 803.61 0.67 1.42 2.72 1.41 4000 2.48 4 40.50 859.10 0.72 1.52 2.91 1.51 4500 2.48 4 42.95 911.21 0.76 1.61 3.09 1.60 5500 2.48 4 47.49 1,007.38 0.84 1.78 3.42 1.77 6000 2.48 4 49.60 1,052.17 0.88 1.86 3.57 1.85 6500 2.48 4 51.63 1,095.14 0.91 1.94 3.71 1.93 7000 2.48 4 53.57 1,136.48 0.95 2.01 3.85 2.00 8000 2.48 4 57.27 1,214.95 1.01 2.15 4.12 2.14 8500 2.48 4 59.04 1,252.34 1.04 2.22 4.25 2.20 9000 2.48 4 60.75 1,288.65 1.07 2.28 4.37 2.27 9500 2.48 4 62.41 1,323.96 1.10 2.34 4.49 2.33

-1ii 2A-4 "1 11" `4403 4.5&5 2.".4:____

10500 2.48 4 65.61 1,391.90 1.16 2.46 4.72 2.45 11000 2.48 4 67.16 1,424.65 1.19 2.52 4.83 2.51 11500 2.48 4 68.67 1,456.67 1.21 2.58 4.94 2.56 12000 2.48 4 70.14 1,488.00 1.24 2.63 5.04 2.62 2$ ~2.4ýZ ~> 7.9" 8 j15:8~6~~"1.7 .9 62 13000 2.48 4 73.01 1,548.76 1.29 2.74 5.25 2.73 13500 2.48 4 74.40 1,578.26 1.32 2.79 5.35 2.78 14000 2.48 4 75.77 1,607.22 1.34 2.84 5.45 2.83 14500 2.48 4 77.11 1,635.67 1.36 2.89 5.55 2.88

~ 24 Ai4 Z84~K 5Yi663.63 19 5.4 2 M~de ______ _ _____ _______

I

_______________ i~~~~~1~23'~0 _______ ______

Survey Design FSS 06C 11 Page 6 of 7

Attachment 4 Area Factors for Open Land Survey Evaluation Contaminated

_Calculated Area Factors at Time of Peak Dose Area (M2) H-3 Mn-54 Fe-55 Co-60 Sr-90 Cs-137 Eu-152 Eu-154 Eu-155 8094 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 4047 1.00 1.01 1.00 1.01 1.00 1.02 1.02 1.01 1.02 2024 1.00 1.03 1.00 1.03 1.00 1.03 1.03 1.03 1.03 1012 1.35 1.04 1.00 1.04 1.00 1.04 1.05 1.04 1.04 506 2.91 1.09 1.98 1.08 1.98 1.13 1.07 1.07 1.06 253 6.05 1.14 3.95 1.13 3.94 1.20 1.11 1.11 1.09 126 12.4 1.20 7.93 1.20 7.87 1.29 1.17 1.16 1.14 63 24.9 1.30 15.8 1.30 15.6 1.41 1.27 1.26 1.23

.32 49.2 1.49 31.2 1.49 30.5 1.62 1.44 1.45 1.39 16 98.9 1.78 62.0 1.78 59.9 1.93 1.72 1.73 1.63 8 198 2.38 123 2.38 117 2.58 2.30 2.31 2.14 4 397 3.61 243 3.62 230 3.91 3.49 3.52 3.19 2 794 5.68 473 5.75 452 6.14 5.48 5.55 4.90 1 1590 9.57 905 9.73 887 10.3 9.24 9.39 7.88 Survey Design FSS 06Cl Page 7 of 7

RM-76 Revision 1 FINAL STATUS SURVEY DESIGN Page 19 of 19 RM-76-5 FINAL STATUS SURVEY APPROVAL AND AUTHORIZATION FOR IMPLEMENTATION Survey Code 06Cl1 Survey Area

Description:

Final Status Survey 06C, 1 encompasses 1977 m 2 at or below the grade elevation present during plant power operations in the south central section of the Protected Area. No materials of plant oriain remain in the survey area.

The survey area is authorized for Final Status Survey Implementation.

T esigned by Date

  • Technical Review by Date RM-76.doc

RM-77 Revision 2 FINAL STATUS SURVEY IMPLEMENTATION Page 8 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 1 of 3

(+) Initial Date 1.0 PREPARATION FOR SURVEY Survey #

1.1 Survey Area Status:

_ a. Final Status Survey Design has been approved for implementation (see RM-76-5, Final Status Survey Approval and Authorization for Supplementation).

1. Survey area walkdown complete
2. Survey area determined ready for FSS
3. Decommissioning activities that may impact the environmental status of the survey area have been completed.
4. Survey area environment is controlled by barriers ILIJA 0 and postings or other approved method to restrict eE5SG access.

_-,Z b. Survey area has been turned over to the Environmental Services Survey Group (ESSG) in acceptable condition for FSS. ,2L4O 4 (

1.2 Field Preparation:

/ a. Survey unit boundaries delineated (Step 6.1.1)

b. Statistical soil samples predetermined in the survey

/-7 design are located and marked within the survey unit.

(Step 6.1.2)

c. Soil sample locations verified (Step 6.1.2.c)
d. Instruments and equipment have been collected and calibrated for data measurement and collection e.

(Step 6.1.3)

Field documentation is prepared (Step 6.1.4) azzz

(/LSSG RM-77.doc

RM-77 Revision 2 Page FINAL STATUS SURVEY IMPLEMENTATION 9 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 2 of 3 Initial Date 2.0 DATA COLLECTION 2.1 Soil Survey:

.Z All soil samples collected and controlled (Step 6.2.1). 01,40 2.2 Surface Scan:

,/ Surface Scan complete. Action response requirements have been conducted on any identified areas exceeding the investigation level (Step 6.3). 2ý_44/ma tSýSG 2.3 Judgmental Soil Samples:

P/A a. Judgmental soil samples have been collected and controlled (Step 6.2.3).

b. Deep core profiles performed in areas identified to contain elevated residual activity (Step 6.2.3). 6j11{4 3.0 SAMPLE PREPARATION AND LABORATORY ANALYSIS 3.1 Sample Preparation (Step 6.4.1):

7 a. Soil samples are homogenous

-7" b. Soil samples are visibly dry prior to packing C. Non-soil materials have been removed from sample

d. Soil samples have been transferred to one-liter Marinelli containers and are labeled and sealed.

"ESSG RM-77.doc

RM-59 Revision 11 SAMPLING AND ANALYSIS OF OPEN LAND Page 7 of 13 AREAS FOR SITE CHARACTERIZATION SURVEYS ATTACHMENT RM-59-1 SAMPLING AND ANALYSIS REPORT Date: 09-14-2006 T Time: 1600 Location: 06C, 1 Tech:

TSSO/JHW/LED/JNS SURVEY IDENTIFICATION / DESCRIPTION Survey 06CI1 encompasses 1977 m 2 at or below the grade elevation present during plant power operations in the south central section of the Protected Area. No materials of plant ori-gin remain in this area.

SURVEY TYPE Survey Type: Characterization X Scan (Motive)

___ Remediation X Final Scan (Static)

Trenching and Digging (use RM-59-4)

SURVEY DESIGN Sample Collection: _ Judgmental _ Random X Systematic Large Container Assay Scan Coverage: 100%

ANALYSIS Inst.SN/Cal Due 201195/02-10-2007 DAILY CHECK: X SAT UNSAT INIT: sso Inst.SN/Cal Due 186185/09-23-2006 DAILY CHECK: X SAT UNSAT INIT: LED Inst.SN/Cal Due 193709/02-21-2007 DAILY CHECK: X SAT UNSAT INIT: TRS Inst.SN/Cal Due 189086/01-26-2007 DAILY CHECK: X SAT UNSAT INIT: JHW Inst.SN/Cal Due Det. # 6 DAILY CHECK: X SAT UNSAT INIT: Jp Investigation of Unidentified Peaks: X SAT _ UNSAT INIT: JLR Minimum Detectable Activity (Section 5.3.2) X SAT UNSAT INIT: JLR COMMENTS Survey 06C,1 was performed in a random start, square grid, systematic sampling pattern with samples collected at 20 data point locations. Laboratory analyses did not identify residual radioactivity above trace levels of the DCGL value. Surface scanninq identified no areas of elevated residual radioactivity. The results of the QA/QC verification scan (10%) were consistent with the findings of the primary survey scan.

-I m

Date: /p -ZZ-II OC( I RM-59.doc

RM-77 Revision 2 FINAL STATUS SURVEY IMPLEMENTATION Page 10 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 3 of 3 Initial Date 3.2 Laboratory Analysis:

L/ Isotopic analyses are complete. The spectroscopy report requires a signature of completion by the laboratory analyst and a signature of evaluation documenting that a second level review has been performed (Step 6.4.2). ý, týS-G-192 AI/W 3.3 Sample Control and Documentation:

/ Chain of custody documentation exhibits control of soil samples (Step 6.4.3).

(/ESSG 0-ýZoea

( -I ý,ý/ /i2(1 9 ý-Zj Date RM-77.doc

Soil Sample Activity Summary Release Record 06011 South Central Protected Area 304 305 30/ 309 310 290 316 291 328 ý34 292 340 293 352 3,M8 294 X=I 60.0 m 364 365 366 369 370 295

= Survey Unit 06C1_1 0I .

5I .

10 I

20 Meters 0 Sample Location

Surface Scan Summary Release Record 06C 11 South Central Protected Area

= Survey Unit 06C1_1 0 5 10 20 Motors

! l  ; , I = i r I

  • Sample Location RED Values are Average Mobile Scan General Area Activity (kcpm)

BLUE Values are Average Verification Scan General Area Activity (kcpm)

GREY Values are Average General Background Area Activity (kcpm)

V, Primary Scan:

Technician Signature: Date: '1-A. 0 Time: '400 QC Verification Scan: /0  %

Technician Signature: ' JA Date: 9*.14-o(o Time: 1l400

RM-72 Revision 0 SAMPLE CHAIN-OF-CUSTODY Page 4of 5 06C1 1 RM-72-1 CHAIN-OF-CUSTODY RECORD Sample Number Sampling Location Date Time Final Disposition of Sample 1 Grid #353 (6.6) (1.0) u HT'o* "-

2 Grid # 354 (7.0) (1.0) - - .O 17-4-D 3 Grid#355 (7.4) (1.0) 0('-i.( 13, 4 Grid#356 (7.8) (1.0) 5I.I*-(do \2ifi 5 Grid #357 (8.2) (1.0) *,l -.o0 IS' 6 Grid # 358 (8.6) (1.0) .Iq'ot*

7 Grid#346 (8.6) (1.4) . I.5" 8 Grid #345 (8.2) (1.4) 9.- ,IUS0 12 1L 9 Grid #344 (7.8) (1.4) 9.1Llr

  • 10 Grid # 343 (7.4) (1.4) -i"(z-0I9 3m 11 Grid # 342 (7.0) (1.4) 5L. +/--D ý,-

12 Grid #341 (6.6) (1.4) jlH.(O .ZLA1e 12 QASplit Grid#341 (6.6) (1.4) Iq.t-o( \I-LI(p 13 Grid # 331 (7.4) (1.8) q,, V- M.Q 14 (R) Grid # 332 (7.8) (1.8) ".ILb 0 4 , I.,%,L 15 Grid #333 (8.2) (1.8) .9. jLLf.(I \7CQS 16 (R) Grid #334 (8.6) (1.8) q.IL*o.o( I SOt /

17 Grid # 322 (8.6) (2.2) 9. 1&I.oeC ID,(4 18 Grid#321 (8.2) (2.2) ,I-O(* \ )

19 Grid#320 (7.8) (2.2) --

  • 20 Grid#319 (7.4) (2.2) _0.O(_ _ _ __'_

(Samples may be analyzed and stored, shipped for offsite evaluation or analyzed and disposed of.)

',1 ¢-WeI, I. l,

2. elnqishd y:Date . Time Received in good condition by:
2. Relinquished by: e Date Time Received in good condition by:
3. Relinquished by: Date Time Received in good condition by:
4. Relinquished by: Date Time Received in good condition by:

RM-72.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 19 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 1 of 8 FINAL STATUS SURVEY: O& (,//

1.0 DATA VERIFICATION 1.1 Data Acceptance

.. ~i,, Review and the Implementation Checklist (RM-77-1) to verify that survey isolation control measures were executed prior to FSS and are being maintained.

Review RM-77, Final Status Survey Implementation, to verify that methods, techniques, and survey activities required for FSS have been applied in accordance with the appropriate procedures.

1.2 Field QC Records:

Review all assessments, Condition Reports and audits to ensure that identified issues have been resolved.

Comments:

,/1 Verify scan instrumentation was in calibration and the QC source checks were performed prior to and after surveys.

7 Verify daily QC source checks for Canberra gamma spectroscopy detector properly logged prior to soil sample analysis.

1.3 Review Verification:

v/" Verify that the Data Quality Objectives are complete.

" Verify that the survey design has been technically reviewed.

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 20 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 2 of 8 V Verify that gamma spectroscopy results have received a technical review.

Verify the Sample and Analysis Report (RM-59-1) is completed and reviewed.

Data Verification Completed: YosN o Comments Assessor Date RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 21 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 3 of 8 2.0 DATA VALIDATION 2.1 Documentation Review:

Perform documentation review for quality control purposes and validate the data collected is complete and appropriate for use as defined by the survey design. Documentation includes:

IField measurement records SChain-of-custody Quality Control (QC) measurement records Current qualification of survey personnel Corrective Action Reports

.* Data inputs (laboratory spectroscopy)

Sample preparation techniques 2.2: Detection Limit Review:

X Scan MDCs are below established site DCGLs.

7/ Forced-count values are assigned as necessary when activity is not detected in a sample.

7Minimum Detectable Concentration (MDC) values of gamma spectroscopy are below established DCGLs.

2.3 Quality Control (QC) Data Review:

Quality Control (QC) data results have received required reviews and are complete and consistent.

4* Results of judgmental samples have been reviewed and evaluated.

_* Review to ensure that the analytical results of judgmental samples do not impact the evaluation for unrestricted release of the survey area.

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 22 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 4 of 8 2.4 Qualification of Data:

Statistical radionuclide-specific measurements for completeness. Evaluate the survey for determination of data usability and confirm that sufficient qualified data are present for the decision process.

a. Total number of statistical samples planned for the survey: j*"j
b. Total number of statistical samples determined as valid: c,2 D b x120_
c. Calculate % Completeness:

a

_ Qualified data are J00% completeness and are sufficient to support the Sign Test requirement for determination of unrestricted release.

Data Validation Completed: 2 No Comments:

Assessor Date RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 23 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 5 of 8 3.0 DATA QUALITY ASSESSMENT 3.1 Review the DQOs and Survey Design:

__ Confirm that all inputs to the decision have been reviewed and are complete.

__j Verify that boundaries or constraints identified in the survey area have not affected the quality of the data.

j Review the Statement of Hypothesis and confirm that it remains relevant.

___ Confirm that Type I and Type II error limits are consistent with DQOs.

ZConfirm that the survey design is consistent with DQOs and that the appropriate number of data points were obtained.

3.2 Preliminary Review:

3.2.1 Preliminary Evaluation:

  • Quality Assessment (QA) reports consistent with procedure RM-79, Final Status Survey Quality Control.

SSurvey is of sufficient intensity to satisfy classification requirement.

7 Potential trends of radioactivity levels in the survey area do not impact a decision for unrestricted release.

Comments:

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 24 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 6 of 8 3.2.2 Calculate Basic Statistical Quantities:

a. Number of qualified data points 0-9
b. Calculation of the Mean P,,1a-.00.1
c. Calculation of the Median .
d. Calculation Standard Deviation Co iP. o'7"2 COW il& Attach graphic representation of the data if any radionuclide-specific measurements exceed 50% of the DCGL.

.JL Sample QA/QC measurements consistent with FSS data 3.3 Statistical Evaluation:

NOTE: If all measurement data are less than the DCGLw, statistical testing in not required and the survey unit meets the regulatory requirement for unrestricted release.

____All survey measurements are below the DCGLw.

3.3.1 Verify Assumptions of the Survey Design

____ Review the posting plot to verify that the data exhibits spatial independence. Spatial trends must be investigated and resolved prior to further assessment.

Review to verify dispersion symmetry. The appearance of skewed data must be investigated for cause and documented prior to further assessment.

RM-78.doc

I RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 25 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 7 of 8

___ Review the dataset standard deviation and range for data variance.

Questionable data. must be investigated for cause and documented prior to further assessment.

Verify that the data exhibits adequate power and confirm that the sample size is sufficient to satisfy the DQOs.

3.4 Draw Conclusions from the Data:

3.4.1 Investigation Levels and Response Actions

_*. Determine if data results have exceeded any investigation level.

Document findings. > . '&-'-J-y/

3.4.2 Evaluation for Unrestricted Release Select applicable conclusion:

j Survey area acceptance criteria met and survey area satisfies the requirements for unrestricted release:

_ All concentrations are less than the DCGLW. The Null Hypothesis is rejected.

_Ap The mean concentration of the survey area is below the DCGLw but individual measurements in the survey unit exceed the DCGLw. The Sign Test and EMC evaluation are successful and the Null Hypothesis is rejected.

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 26 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 8 of 8

.4 Survey area acceptance criteria not met and survey area fails to satisfy the requirements for unrestricted release:

,d The mean concentration in the survey area exceeds the DCGLw. and the null hypothesis is confirmed.

A2ý, The mean concentration of the survey area is below the DCGLw but individual measurements in the Unit exceed the DCGLw..

The Sign Test and EMC evaluation are unsuccessful and the null hypothesis is confirmed.

Data Quality Assessment Completed: No Comments 7 Assessor Date Reviews:

Ot Da(Z-3 Technical R iew Date ES Superintendent 'Date RPr&-ES Manager Date RM-78.doc

RM-78-3, Attachment 1 Statistical Quantities Release Record 06C11 South Central Protected Area Sample Cs-1 37 Co-60 Weighted **Weighted Sum Number (pCi/gm) (pCi/gm) Sum (SOR) <DCGLw? DCGL-W. Sum Sign 1 0.0547 0.0319 0.0145 yes 0.9855 +1 2 0.0490 -0.0036 0.0030 yes 0.9970 +1 3 0.0472 -0.0083 0.0014 yes 0.9986 +1 4 0.0853 0.0471 0.0218 yes 0.9782 +1 5 0.0331 0.0291 0.0118 yes 0.9882 +1 6 0.0902 -0.0150 0.0029 yes 0.9971 +1 7 0.0581 0.0132 0.0090 yes 0.9910 +1 8 0.0044 0.0023 0.0011 yes 0.9989 +1 9 0.0667 0.0566 0.0232 yes 0.9768 +1 10 0.0918 0.0369 0.0192 yes 0.9808 +1 11 0.0468 0.0323 0.0140 yes 0.9860 +1 12 0.0324 -0.0009 0.0024 yes 0.9976 +1 13 0.0624 0.0013 0.0056 yes 0.9944 +1 14 0.0417 0.0030 0.0044 yes 0.9956 +1 15 0.0364 0.0474 0.0178 yes 0.9822 +1 16 0.0213 0.0110 0.0052 yes 0.9948 +1 17 0.0613 0.0049 0.0067 yes 0.9933 +1 18 0.0422 0.0084 0.0062 yes 0.9938 +1 19 0.0287 0.0119 0.0061 yes 0.9939 +1 20 0.0524 0.0422 0.0175 yes 0.9825 +1 Std. Dev 0.0224 0.0210 0.0072 Mean 0.0503 0.0176 0.0097 Median 0.0481 0.0115 0.0064 Number of Positive Differences (S+): n/a Critical Value, k, Table 1.3 of Marssim: n/a S+ >thank?: n/a Survey Unit Pass or Fail: **Pass

  • Note: Forced-Countvalues are used for samples with activity levels below the MDA.
    • Note: If all measurement data are less than the DCGL ., then the Sign Test is not required.

I t RM-79 Revision 1 FINAL STATUS SURVEY QUALITY CONTROL Page 11 of 13 RM-79-1 FSS QUALITY CONTROL EVALUATION RESULTS FSS Package # 0(a C' I QC Package # o (c2Co /

QC Measurement Type Acceptance Criteria Met*? Reference

1. Replicate Scan (2 No Step 5.1.3.
2. Sample Recounts Step 5.1.4.1

_ _ a. In-house No 2/yL b. Third party Yes / No

3. Split Samples Step 5.1.4.2
c. In-house No
d. Third party Yes I No
  • NOTE: If Acceptance Criteria is not met, completion of Attachment RM-79-2, FSS Quality Control Investigation Results, is required.

Comments:~

-wý 4 AA F t -

Reviews:

TEvaluator Date Technical Review Die RM-79.doc

QA Verification Split Sample Analysis Table I Date: 9/14/2006 Acceptance Criteria Resolution Ratio QA: 06C,1 South Central Protected Area <4 N/A 4-7 0.5-2.0 Type: Split Sample 8-15 0.6-1.66 16-50 0.75-1.33 Lab: In-House 51-200 0.8-1.25

>200 0.85-1.18 A B C D E F (3 BRP BRP BRP Results in Sample Radionuclide Result Results  % Error BRP Ratio Results ResltsRatioSplit Results Rati Comparison Agreement Below Resolution (pCi/g) Compare MDA (pCi/g) (Sigma) (Table 1) Below MDA F/A G with D) 12 Co-60 < 0.0624 n/a n/a n/a < 0.0638 1.02 YES 12 Cs-137 < 0.0612 n/a n/a n/a < 0.0622 1.02 YES A"

Resolution C = -

(A)( IB I

< Indicates results less than the MDA.

  • Note Results are considered in agreement for MDA and near-MDA measurementcomparisons Results fthat fail agreement must be investigated per RM-79.

QA Verification Sample Recount Analysis Table 1 Date: 9/14/2006 Acceptance Criteria Resolution Ratio QA: 06C,1 South Central Protected Area <4 N/A 4-7 0.5-2.0 Type: Sample Recounts 8-15 0.6-1.66 16-50 0.75-1.33 Lab: In- House 51-200 0.8-1.25

>200 0.85-1.18 A B C DE F G BRP BRP BRP Acceptance Recount Recount Comparison Agreement Sample Radionuclide Result Below Results  % Error RReonAgemt Ratio Resolution Result Results Ratio Compare S (pCi/g) (Sigma) ( Table 1) el (pCi/g) F/A Compare MDA pg, Iga(Tbe Below MDA G with D) 14 Co-60 < 0.0639 n/a n/a n/a < 0.0749 1.17 YES 14 Cs-137 0.0417 38.44 2.60 n/a 0.0671 1.61 YES 16 Co-60 < 0.0612 n/a n/a n/a < 0.0479 0.78 YES 16 Cs-137 < 0.0598 n/a n/a n/a 0.0506 0.85 YES Resolution C= (Al OO

< Indicates results less than the MDA.

  • Note Results are considered in agreement for MDA and near-MDA measurement comparisons Results flhat fail agreement must be investigatedper RM-79.

.4 if Tritium in Soil Data Results Final Status Survey 06C 1 1 Sample Tritium in Soil Number pCi/g 12 0.007 14 0.015 16 0.024 Mean: 0.0153 Median: 0.0150 St. Dev: 0.0085 Note: The DCGL for Tritium is 327 pCi/g.

Sample results are less than 0.02% of the DCGL

-

  • Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road - Northbrook, IL 60062-2310 ph. (847) 564-0700

  • fax (847) 564-4517 Mr. David W. Parish LABORATORY REPORT NO. 8022-100-230 Big Rock Point DATE: 09-22-2006 10269 US-31 North SAMPLES RECEIVED: 09-19-2006 Charlevoix, MI 49720 PURCHASE ORDER NO:

Below are the results of the analyses for tritium on three soil samples.

Excavated Soil Survey 06C1 l Sample Collection Lab Concentration MDA Description Date Code (pCi/g of soil) (pCi/g of soil)

H-3 12 09-14-06 BRSO-6372 0.007 +/- 0.006 <0.011 14 09-14-06 BRSO-6373 0.015 +/- 0.008 < 0.014 16 09-14-06 BRSO-6374 0.024 +/- 0.007 < 0.013 The error given is the probable counting error at 95 % confidence level. The less than, (<), value is based on 4.66 sigma counting error for background sample.

APPROVED BY- J-0ý4//& A Tony Coorlim, Quality Assurance

  • t~

ATTACHMENT 5 CONSUMERS ENERGY BIG ROCKPOINT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION CLASS I RELOCATED SOIL RELEASE RECORD, TBCx1 51, RELOCATED SOILS FROM TURBINE BUILDING/CONTAINMENT DEMOLITION October 24, 2006 38 Pages

Supporting Survey, Relocated Soil Release Record TBCx151 Relocated Soils From Turbine Building/Containment Demolition SURVEY PACKAGE CLOSURE Final Status Survey Documentation is authorized for closure. All required reviews are complete and the evaluation of data results have satisfied the criteria established for unrestricted release and onsite use for excavation backfill.

Sianedýý' -ý5 -5sy-ýý Date: io(Z.5 (ESSG Supervisor) '

z/ /

Signed: Date:

'S Superintendent)

Signed: Date:

(RP & ES Manager)

I-,

Survey Requirements Release Record TBCx51 l Relocated Soils From Turbine Building/Containment Demolition Area Survey Description Supporting survey TBCX15 1 consists of soils excavated during Turbine/Containment demolition and the removal of subsurface piping components. The excavated soil was transported to the soil verification area (SVA) and graded to maximum depth of 1.0 meter. The physical size of the survey area is 1800 square meters.

The evaluation of excavated soil will be performed in accordance with procedure RM-76, Final Status Survey Design. Sample locations will be established by random start, systematic square grid pattern over the graded area. Each soil sample will be a full core homogenized composite that is representative of total soil thickness. Surface scanning will be conducted over 100% of the survey area.

History The soil for survey evaluation originated from a Class 1 area that was excavated to remove concrete and piping components in the Turbine Building/Containment demolition area. Soil remediation efforts were required for some areas associated with subsurface component removal.

Current Radiological Status Based on post remediation analyses and supporting surveys the residual radioactivity in this excavated soil is not expected to exceed DCGL concentration values. Survey documentation is maintained in the 10 CFR 50.75(g) files. Input for this evaluation includes the following survey data:

Turbine Building Demolition Supporting Surveys for Soil Transport and Evaluation TB051005 SB040405 SB042905 TB062805 HH060705 TB052405 SB040605 SB050205 HH050505 TB060905 TB052505 SB040705 SB051705 HH051705 TB080805 TB052605 SB041205 SB051805 HH051905 TB080905 TB060105 SB041905 HH042705 HH041905 Survey Requirements TBC.isI Page 1 of 2

40ý i Post-Construction Expectations Survey TBCx151 will be performed in the following activity sequence:

1. Walkdown: Environmental Services Survey Group (ESSG) personnel will perform a walkdown assessment to ensure survey area preparations are complete and confirm that the following post-construction expectations have been satisfied as applicable:

0 Groundwater and Surface water control is adequate 0 All construction debris has been removed from the survey area 0 The survey location status meets all applicable safety requirements

2. Survey Area Isolation and Control: Control measures will be established to ensure that any potential ongoing decommissioning activities in adjacent locations do not impact the current survey area status. Isolation and control measures include postings, barriers, access points, and the evaluation of ongoing work activities in adjacent areas.
3. Survey Design and Execution: Survey design and execution will follow the Data Quality Objectives for TBCxl 51 in accordance with the survey requirements established in procedures RM-76, Final Status Survey Design and RM-77, Final Status Survey Implementation, and LTP, Chapter 5. Survey size will be based on the statistical requirements of the Sign Test for Class 1 areas with soil samples collected in random start, systematic data point locations. Surface scanning will be performed with 100%

survey area coverage. This survey will be conducted in accordance with approved BRP procedures and follow the guidance of NUREG 1575.

4. Data Quality Assessment: Isolation and control of the survey area will be maintained until the survey Data Quality Assessment demonstrates that the regulatory requirements for unrestricted site release have been satisfied.

Survey Requirements TBCX1 51 Page 2 of 2

DATA QUALITY OBJECTIVES Survey TBCx15 1 Relocated Soils From Turbine Building/Containment Demolition Area STATE THE PROBLEM The Problem:

To demonstrate that the level of residual radioactivity in soils excavated from the Turbine Building/Containment demolition area does not exceed the release criteria of 25 mrem/year Total Effective Dose Equivalent (TEDE) as specified in the License Termination Plan (LTP). This soil has been relocated to the soil verification area (SVA) and is to be prepared for survey by grading out to a depth of one (1) meter or less. The excavated soil for evaluation is to be designated as a Class 1 survey area. It must be demonstrated that soils in this survey area satisfy the criteria established for unrestricted release prior to disposition as fill material for onsite usage.

Stakeholders:

The primary stakeholders interested in the answer to this problem are Consumers Energy Co., and the general public as represented by the Michigan Department of Environmental Quality (MDEQ), and the US Nuclear Regulatory Commission (USNRC).

The Planning Team:

The planning team consists of members of the BRP Environmental Services Survey Group (ESSG). The primary decision maker will be the Final Status Survey Supervisor.

The Final Status Survey Supervisor will obtain input from the site Construction Group and Scheduling Group for issues relating to schedule and costs.

Schedule:

Approximately five (5) working days are projected to implement the survey and to collect and analyze field data.

Resources:

The primary resources needed to determine the answer to the problem are two (2) technicians to perform fieldwork, one (1) technician to prepare the samples and conduct laboratory analyses, and two (2) survey team members to prepare and review the design, generate maps, coordinate field activities and evaluate data.

2. IDENTIFY THE DECISION Several decisions need to be defined to address the stated problem.

PrincipalStudy Question (1):

Does the mean concentration of residual radioactivity in the survey unit exceed the release criteria stated above?

Data Quality Objectives TBC,15 1 Page 1 of 5

Decision (1):

Determine whether the mean concentration of residual radioactivity in the survey exceeds the release criteria stated in the problem.

Actions (1):

Alternative actions include failure of the survey unit, remediation, or no action required.

PrincipalStudy Question (2):

Do any areas of elevated activity in the survey unit exceed the release criteria?

The Decision (2):

Determine if any areas of elevated activity in the survey unit exceed the release criteria.

Actions (2):

Alternative actions include confirmation and investigation, performing the elevated measurement comparison (EMC), remediation, or no action required.

PrincipalStudy Question (3):

Is the potential dose from residual radioactivity in the survey unit ALARA as stated?

The Decision (3):

Determine if the potential dose from residual radioactivity in the survey unit is ALARA.

ALARA requirements for soil remediation are defined in Chapter 4 of the LTP.

Actions (3):

Alternative actions include remediation or no action required.

3. IDENTIFY INPUTS TO THE DECISION Information Needed:

Characterization measurements are required to define the radionuclides present and determine the extent and variability of residual radioactivity in the survey area for design and implementation of the survey. Survey area classification, ALARA analysis, potential radionuclides of interest, and site-specific DCGL values are also required inputs to the decision process. The primary information required for evaluation is the analytical results of survey measurements.

Source of the Information:

The soil sample data to be used for survey development are the radionuclide-specific measurements of representative soil samples collected for characterization to determine suitability for transport to the SVA. The soil samples obtained were judgmentally selected as a result of multiple surveys conducted during the excavation and transport process. The ALARA analysis for potential soil remediation is provided in LTP, Section 4.4. Site-specific DCGL values and BRP radionuclides of interest are defined in LTP Chapter 5, Table 5-1 and Procedure RM-76, Final Status Survey Design.

The survey will be conducted in accordance with applicable regulatory guidance as established in LTP Chapter 5 for Class 1 areas. Soil samples will be utilized for radionuclide-specific measurements in this evaluation.

Data Quality Objectives TBC, 15 1 Page 2 of 5

4. BOUNDARIES OF THE STUDY Boundaries of the Survey:

The target population for this survey is the total thickness of prepared soil in the survey area of 1800 M2 .

Temporal Boundaries:

Scanning and sampling in this survey unit will only be performed during daylight hours under dry weather conditions. Surface soils must be free of significant snow cover and standing water prior to surface scanning. Soils must be in a non-frozen state or fragmented for collection to satisfy BRP procedural sampling requirements. The anticipated start date for the survey is September 22, 2006.

Constraints:

Cold weather or rainy conditions may effect the operation of electronic equipment.

Adverse weather conditions that include accumulations of rain or snow may limit area access and delay survey efforts.

5. DEVELOP A DECISION RULE The following decision rules have been developed to define a logical process for choosing among alternative actions for the principal study questions associated with this survey area.

Decision Rule (1):

If all reported concentrations for residual radioactivity are less than the site-specific DCGL's and the unity rule has been satisfied for each sample, then the survey unit meets release criteria. No further action is required.

Decision Rule (2):

If the mean value of activity in the survey unit is greater than the DCGL, then the survey unit fails to meet the release criteria.' Remediate, resurvey, and evaluate the results relative to the decision rule.

Decision Rule (3):

If the mean activity in the survey unit is less than the DCGL and any individual sample measurement exceeds this value, conduct the Sign Test and the elevated measurement comparison (EMC) per LTP, Chapter 5 and Procedure RM-76, Final Status Survey Design. If the EMC and the Sign Test have been satisfied then the survey unit meets the release criteria and no further action is required. If the EMC or the Sign Test has not been satisfied then remediate the area(s) of elevated activity, resurvey as appropriate, and evaluate the results relative to the decision rule.

When multiple radionuclides are present the mean activity value is determined as the average of the weighted sum. The DCGL of the weighted sum is 1.

Data Quality Objectives TBCx151 Page 3 of 5

Decision Rule (4):

If the potential dose from residual radioactivity in the survey unit is ALARA, then no further action is necessary. If the potential dose from residual radioactivity in the survey unit is not ALARA, then remediate and resurvey.

6. SPECIFY TOLERABLE LIMITS ON DECISION ERRORS The Null Hypothesis:

It is assumed that residual radioactivity in the survey unit exceeds the release criterion.

Type I Error(a ):

The a error is the maximum probability of rejecting the null hypotheses when it is true.

Thea error is defined in the LTP at a value of 0.05 (5%) and cannot be changed to a less restrictive value unless prior approval is granted by the USNRC. The a error value of 0.05 will be used for survey planning and data assessment for this survey area.

Type II Error(/3):

The ,8 error is the probability of accepting the null hypothesis when it is false. A value of 0.05 (5%) will be used for survey planning and data assessment for this survey area.

The Lower Bound of the Gray Region (LBGR):

The LBGR is initially set at one-half the DCGLw for this survey unit. The LBGR may be adjusted during survey design to achieve an optimum relative shift between 1.0 and 3.0.

Relative Shift (A/a):

The relative shift will be maintained within the range of 1.0 and 3.0 by adjusting the LBGR as appropriate.

7. OPTIMIZE DESIGN FOR OBTAINING DATA Statistical Test Sign Test:

Radionuclides of potential plant origin also present in soil as background activity resulting from fallout constitute only a small fraction of the DCGL. Therefore, the Sign Test will be used where applicable in the survey evaluation to determine if the survey area meets the requirements for unrestricted release.

Number of Samples Determined:

The number of samples required for this survey will be determined based on the relative shift as defined by the requirements of the Sign Test (LTP, Chapter 5.) and Procedure RM-76, FinalStatus Survey Design. The LBGR is initially set at one-half the DCGLw and may be adjusted as necessary for optimizing the survey design to achieve a relative shift between 1.0 and 3.0. Sample point locations are to be determined using a random start, systematic square grid spacing.

Data Quality Objectives TBC 1 51 Page 4 of 5

Judgmental Sampling:

Co-60 is the most limiting radionuclide for identification by surface scanning; judgmental surface and subsurface core samples will be collected in any location that exceeds the scan investigation level.

Scan Coverage:

Scanning for this survey area will provide 100% coverage.

Number of Samples for Quality Control:

A minimum of 5% of the sample population will be collected for quality evaluation.

These samples may include sample splits, sample recounts, or third party sample analysis. Quality analyses will be conducted as defined in LTP, Chapter 5 and Procedure RM-79, Final Status Survey Quality Control.

Additional Sample Analysis Requirements:

The area of soil excavation intersects the identified waterborne pathway for Tritium migration and shall require Tritium in soil analyses for a minimum of 10% of the sample population. Soil samples will be collected in the same random locations as those selected for QA/QC evaluation and sent to an independent laboratory for Tritium analysis. Data results will be provided in the survey package.

Investigation Levels:

Investigation levels defined in LTP, Chapter 5 and BRP Procedure RM-76, Final Status Survey Design, shall be conservatively established for this survey as shown below:

Investigation Levels for Survey TBCx1 51 Scan Measurement Soil Sample Analysis

> DCGL > DCGLW The investigation levels for soil sample measurements are meant to include any individual radionuclide result greater than the site-specific DCGL or where the combined radionuclide values exceed the unity rule. Co-60 is the most limiting radionuclide for identification by surface scanning; further investigation will be initiated at any location that exceeds the Co-60 Scan DCGL of 1818 CPM above background as detailed in the survey design.

Data Quality Objectives TBC, 15 1 Page 5 of 5

SURVEY DESIGN Survey TBCx 5sl Survey Design Relocated Soils from Turbine Building/Containment Demolition Area Survey Unit Description Survey TBCx15 1 consists of excavated soils that have been removed from the Turbine Building/Containment demolition area for subsurface structure and component removal. Areas of excavation include the Containment foundation and the following subsurface piping and components:

  • Underground diesel storage tank (heating boiler),
  • Condenser cooling water piping,
  • East side storm drain, and
  • Radwaste effluent piping in Survey Units 8, 9, and 10.

The soil has been graded out to a maximum thickness of one (1) meter over a total area of 1800 M2. Soil sample locations for this survey will be determined using a random start, systematic, square-grid pattern over the graded area. Each soil sample will be a homogenized composite representative of the total thickness of soil. Surface scanning will be conducted over 100% of the graded area.

Soil Sample Design Scoping Data Sample measurements obtained to determine suitability for soil transport to the designated survey area have not identified residual radioactivity above fractional concentrations of the DCGL value. Input data for survey design were conservatively estimated based on supporting surveys for transport suitability obtained in the Turbine Building demolition area.

Table 1 Input Data for Survey Design (pCi/g)

Radionuclides Cs-137 Co-60 a

  • 0.524 0.255 DCGL 11.93 3.21
  • Survey data detailed in Attachment 1 Sample Requirements The number of sample data points for this survey is based on the requirements of the Sign Test.

The Unity Rule is used for the presence of multiple radionuclides. The Standard Deviation of the weighted sum is described by the following:

= ICDCG~cs1

37) +C~o Survey Design TBCx151 Page 1 of 8

,/0.524 '2 (f0.255'2

(= 0.091 Relative Shift Relative Shift = DCGLw-LBGR G

Relative Shift = 1-0.818 0.091 Relative Shift = 2.0 With cc and P3 error levels set at 0.05 and the relative shift of 2.0, the Sign Test requires 15 sample data points (Table 5.5 NUREG 1575).

Sample Locations Sample locations are selected in a random start, systematic square grid pattern with the southwest corner of the survey unit as origin (X=0, Y=0). Two numbers between 0 and 1 have been randomly selected and then applied to the survey unit maximum X and Y dimensions to determine the random start location as shown below:

Table 2 Random Numbers Random #, X Axis 0.341663 +/- Random #, Y Axis 0.184214 Survey Unit Dimensions: X = 150 meters Y = 12 meters Random Start Location X = (0.341663)(150) = 51.2 meters With SW Corner Origin: Y = (0.184214)(12) = 2.2 meters Sample Spacing As a conservative measure sample spacing will be calculated based on 18 samples for this survey. Samples are located in a systematic square grid pattern with sample spacing determined by the following:

L=A!n where A= area of survey unit, and n = number of samples.

L, 18 = 10 meters

= 180 Survey Design TBCý15 1 Page 2 of 8

With sample spacing established at 10 meters, 15 data points are available for this survey.

Data point locations are identified in Attachment 2.

QAJQC Sampling A minimum of 5% of the sample population and 5% of the scan survey area are required to be selected for QA/QC verification in accordance with BRP Procedure RM-79, FinalStatus Survey Quality Control. As a conservative measure, three (3) soil samples and 10% of the scan survey area will be selected for QA/QC evaluation. Data point locations for soil samples will be determined by random number selection.

The QA/QC scan starting point and track direction are also determined by random number selection. The first random data point selected will identify the scanning start point and the second random data point will determine the direction in which the scan will track. QA/QC location results are provided in Table 3 below:

Table 3 Random Numbers Generated for QA/QC Random Random QA/QC Soil Sample Verification Scan Sample Samples Number Number Split Sample: 2 Start Point: 8 Sample Recount: 4 Scan Toward: 2 Sample Recount: 7 Minimum Scan Area Requirement: 180 M 2 Surface Scanning The coverage requirement for surface scanning in this Class 1 area is 100%. The Scan MDc has been established at fractional values of the DCGLwfor typical background activity levels at Big Rock Point. Scan MDc values for varying backgrounds are provided in Attachment 3. The investigation level for identification of potential areas of elevated activity in this survey area will be the Scan DCGL as defined by the following:

Scan DCGL = Detector Rating CPM

  • Exposure Model uR/hr , DCGLw uR/hr pCi/g Scan DCGL for Co-60 = 1818 CPM Scan DCGL for Cs-137 = 3518 CPM Where:1 Detector Rating = 1200 CPM Cs-137 and 565 CPM Co- 60 uR/hr uR/hr Exposure Model = 1.229uR/hr Cs-1 37 and 5.029 uR/hr Co_-60 5pCi/g 5 pCi/g DCGLw = 11.93 pCi/g Cs-137 and 3.21 pCi/g Co-60 These values established in EA-BRP-SC-0201, Nal Scanning Sensitivity for Open Land Survey.

Survey Design TBC 15 1 Page 3 of 8

The DCGLw for Co-60 is the most limiting value for scanning measurements performed to identify areas of potentially elevated activity. Scanning conducted for this survey will assume all residual radioactivity to originate from Co-60 and the instrument response at the Co-60 DCGLw (1818 cpm) will be used as the scanning investigation level for Survey TBCx15 1.

Survey Design TBC,151 Page 4 of 8

Attachment 1 Design Data - Survey TBCx,1 5 Relocated Soils From Turbine Building Demolition Area Cs-I 37 Co-60 Survey No. Sequence Activity Activity No. (pCi/g) (pCi/g)

H H060705, 1'6538 :126 0,66'

-HH06070'5r 1653;9 0.06 0.06*

HH675 16540 1.05 0ý66 TB062805t -16755& 11 0.27 TB062805, C11617665 ý4ý7*, 5ý*

oTB062805 1"6774 019 03 Mean: 0.698 0.352 Std Dev: 0.524 0.255

  • Measurement system MDA - Co-60 not identified in this sample Survey Design TBCx15 1 Page 5 of 8

Attachment 2 Soil Sample Locations - Survey TBC, 151 Relocated Soils From Containment/Turbine Building Demolition Area V=IV)

=

X= 150 M

- Sol Pise 0 5 10 20 Motors 0 8an~e Location 1L+/-.- LL.-

Sample no. 6 Is the random start location Sample spacing Is 10.0 meters Survey Design TBCxist Page 6 of 8

Attachment 3 Scan MDC In Varying Backgrounds Background d' _ Si MDCRsurveyor Cs-137 Co-60 Cs-137 Co-60 2000 2.48 4 28.64 607.47 0.51 1.08 2.06 1.07 3000 2.48 4 35.07 744.00 0.62 1.32 2.52 1.31 3500 2.48 4 37.88 803.61. 0.67 1.42 2.72 1.41 4000 2.48 4 40.50 859.10 0.72 1.52 2.91 1.51 4500 2.48 4 42.95 911.21 0.76 1.61 3.09 1.60

______2.480 - 4 4.8 -, 960.5,0 >0ý18O< ~1A7d 32~~ 1 5500 2.48 4 47.49 1,007.38 0.84 1.78 3.42 1.77 6000 2.48 4 49.60 1,052.17 0.88 1.86 3.57 1.85 6500 2.48 4 51.63 1,095.14 0.91 1.94 3.71 1.93 7000 2.48 4 53.57 1,136.48 0.95 2.01 3.85 2.00 8000 2.48 4 57.27 1,214.95 1.01 2.15 4.12 2.14 8500 2.48 4 59.04 1,252.34 1.04 2.22 4.25 2.20 9000 2.48 4 60.75 1,288.65 1.07 2.28 4.37 2.27 9500 2.48 4 62.41 1,323.96 1.10 2.34 4.49 2.33 10500 2.48 4 65.61 1,391.90 1.16 2.46 4.72 2.45 11000 2.48 4 67.16 1,424.65 1.19 2.52 4.83 2.51 11500 2.48 4 68.67 1,456.67 1.21 2.58 4.94 2.56 12000 2.48 4 70.14 1,488.00 1.24 2.63 5.04 2.62 1240,0 U4 7.859

71. -i586 1.27 12:9 5. 1;5 i2.67 13000 2.48 4 73.01 1,548.76 1.29 2.74 5.25 2.73 13500 2.48 4 74.40 1,578.26 1.32 2.79 5.35 2.78 14000 2.48 4 75.77 1,607.22 1.34 2.84 5.45 2.83 14500 2.48 4 77.11 1,635.67 1.36 2.89 5.55 2.88 Sxpsr
  • 5" ý:(iR/hrfl5p)i~j.

5,03Ej00

ýC4$151;23E+OO,_____

Survey Design TBC, 151 Page 7 of 8

Attachment 4 Area Factors for Open Land Survey Evaluation Calculated Area Factors at Time of Peak Dose Area (Mt) H-3 Mn-54 Fe-55 Co-60 Sr-90 Cs-137 Eu-152 Eu-154 Eu-155 8094 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 4047 1.00 1.01 1.00 1.01 1.00 1.02 1.02 1.01 1.02 2024 1.00 1.03 1.00 1.03 1.00 1.03 1.03 1.03 1.03 1012 1.35 1.04 1.00 1.04 1.00 1.04 1.05 1.04 1.04 506 2.91 1.09 1.98 1.08 1.98 1.13 1.07 1.07 1.06 253 6.05 1.14 3.95 1.13 3.94 1.20 1.11 1.11 1.09 126 12.4 1.20 7.93 1.20 7.87 1.29 1.17 1.16 1.14 63 24.9 1.30 15.8 1.30 15.6 1.41 1.27 1.26 1.23 32 49.2 1.49 31.2 1.49 30.5 1.62 1.44 1.45 1.39 16 98.9 1.78 62.0 1.78 59.9 1.93 1.72 1.73 1.63 8 198 2.38 123 2.38 117 2.58 2.30 2.31 2.14 4 397 3.61 243 3.62 230 3.91 3.49 3.52 3.19 2 794 5.68 473 5.75 452 6.14 5.48 5.55 4.90 1 1590 9.57 905 9.73 887 10.3 9.24 9.39 7.88 Survey Design TBC. 151 Page 8 of 8

RM-76 Revision 1 FINAL STATUS SURVEY DESIGN Page 19 of 19 RM-76-5 FINAL STATUS SURVEY APPROVAL AND AUTHORIZATION FOR IMPLEMENTATION Survey Code TBC,,isl Survey Area

Description:

Survey TBCx15 1 is the final status evaluation of soil that was excavated from the Turbine Buildingq/Containment demolition area. The soil has been relocated to the SVA and prepared for survey by -gradingq to a maximum depth of 1 meter over an area of 1800 square meters.

The survey area is authorized for Final Status Survey Implementation.

...2-/D-ate o Designed by Date on- I*-'*Im~o Technical Review by Date RM-76.doc

RM-77 Revision 2 FINAL STATUS SURVEY IMPLEMENTATION Page 8 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 1 of 3 Step Initial Date

(+)

1.0 PREPARATION FOR SURVEY Survey #

1.1 Survey Area Status:

Z a. Final Status Survey Design has been approved for implementation (see RM-76-5, Final Status Survey Approval and Authorization for Supplementation).

1. Survey area walkdown complete
2. Survey area determined ready for FSS
3. Decommissioning activities that may impact the environmental status of the survey area have been completed.
4. Survey area environment is controlled by barriers and postings or other approved method to restrict ,ESSG access.

/ b. Survey area has been turned over to the Environmental Services Survey Group (ESSG) in acceptable condition for FSS. 4ý-Iw(a 1.2 Field Preparation:

+ a.

b.

Survey unit boundaries delineated (Step 6.1.1)

Statistical soil samples predetermined in the survey design are located and marked within the survey unit.

(Step 6.1.2)

c. Soil sample locations verified (Step 6.1.2.c)
d. Instruments and equipment have been collected and calibrated for data measurement and collection (Step 6.1.3)

/ e. Field documentation is prepared (Step 6.1.4) (/ESSG RM-77.doc

RM-77 Revision 2 FINAL STATUS SURVEY IMPLEMENTATION Page 9 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 2 of 3 Initial Date 2.0 DATA COLLECTION 2.1 Soil Survey:

All soil samples collected and controlled (Step 6.2.1).

EdSSG_

OIL4,ýrlo &

2.2 Surface Scan:

Surface Scan complete. Action response requirements have been conducted on any identified areas exceeding the investigation level (Step 6.3).

62;ý 2.3 Judgmental Soil Samples:

4 a. Judgmental soil samples have been collected and controlled (Step 6.2.3).

b. Deep core profiles performed in areas identified to contain elevated residual activity (Step 6.2.3).

XES-SG 3.0 SAMPLE PREPARATION AND LABORATORY ANALYSIS 3.1 Sample Preparation (Step 6.4.1):

/ a. Soil samples are homogenous

b. Soil samples are visibly dry prior to packing
c. Non-soil materials have been removed from sample
d. Soil samples have been transferred to one-liter Marinelli containers and are labeled and sealed. d4z ,22Zzs1-(;(0 JESSG RM-77.doc

RM-77 Revision 2 FINAL STATUS SURVEY IMPLEMENTATION Page 10 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 3 of 3 Initial Date 3.2 Laboratory Analysis:

Isotopic analyses are complete. The spectroscopy report requires a signature of completion by the laboratory analyst and a signature of evaluation documenting that a second level review has been performed (Step 6.4.2). SSG 3.3 Sample Control and Documentation:

Chain of custody documentation exhibits control of soil samples (Step 6.4.3). d&

eME8SG bý Date Reviewed 7

RM-77.doc

RM-59 Revision 11 SAMPLING AND ANALYSIS OF OPEN LAND Page 7 of 13 AREAS FOR SITE CHARACTERIZATION SURVEYS ATTACHMENT RM-59-1 SAMPLING AND ANALYSIS REPORT Date: 09-22-06 Time: 1600 I Location: TBC. 15 1 Tech:WMHILED/JHW/JNS SURVEY IDENTIFICATION I DESCRIPTION 1

Survey TBC x15 consists of excavated soils removed from the Turbine/ Containment Building demolition area and the removal of subsurface Dinino and components. The phvsical size of the survey prep is ISMlfl SURVEY TYPE Survey Type: Characterization X Scan (Motive)

Remediation Scan (Static)

X Final Trenching and Digging (use RM-59-4)

SURVEY DESIGN Sample Collection: _ Judgmental _ Random X Systematic Large Container Assay Scan Coverage: 100  %

ANALYSIS Inst.SN/Cal Due 186194/02-08-2007 DAILY CHECK: X SAT UNSAT INIT: WMH Inst.SN/Cal Due 186192/03-14-2007 DAILY CHECK: X SAT UNSAT INIT: WMH Inst.SN/Cal Due 201195/02-10-2007 DAILY CHECK: X SAT UNSAT INIT: WMH Inst.SN/Cal Due 189086/01-26-2007 DAILY CHECK: X SAT UNSAT INIT: WMH Inst.SN/Cal Due Det #6 DAILY CHECK: X SAT UNSAT INIT: JP Investigation of Unidentified Peaks: X SAT UNSAT INIT: JLR Minimum Detectable Activity (Section 5.3.2) X SAT UNSAT INIT: JLR COMMENTS Survey TBC 15 1 was performed in a random start, square grid, systematic sampling pattern with samples Collected at 15 data point locations. Laboratory analyses did not identify residual radioactivity above trace Levels of the DCGL value. Surface scannina at 100% coveraae identified no areas of elevated residual Radioactivity. The results of QA/QC verification scanning (10% coverage) were consistent with the scan values identified in the survey.

A PJ Technician Signature: Date: ______i_____

Second Level Review Signature: _6 4 Date: /Z2-O0 RM-59.doc

Soil Sample Activity Summary Release Record TBCx1 51 Relocated Soil from Containment/Turbine Building Demolition Area Y= 12m X = 150 m

- Soil Pile 0 5 10 20 I I i I I I I I Meters S Sample Location Prorcea-count values Coordinate location relative to SW comer of survey unit where X=O m. and Y=O m.

Surface Scan Summary Release Record TBCx1 51 Relocated Soil from Containment/Turbine Building Demolition Area 4.2 4.5 4.3 4.4 4.2 4,2 4.0 4.4 4.0 3.8 4.3 4.0 4,2 4.1 4 .2 0Soil Pile 0 5 10 20

  • Sample Location I 1 i i I 1 , 1 IMeters RED Values are Average Mobile Scan General Area Activity (kcpm)

BLUE Values are Average Verification Scan General Area Activity (kcpm)

GREY Values are Average General Background Area Activity (kcpm)

Primary Scan: / * %_xwo TechnIcian Signature: Date: 2-:t-O; Time: Mlop QC Verification Scan: 10  %

Technician Signature: Date: * *?.-

  • Time: IS'"

RM-72 Revision 0 SAMPLE CHAIN-OF-CUSTODY Page 4of 5 TBCx151 RM-72-1 CHAIN-OF-CUSTODY RECORD Sample Number Sampling Location Date Time Final Disposition of Sample 1 (1.2)(2.2) q-*-o6 / 3a* e_* *.y,'-v ro.

2 (11.2)(2.2) " -

23 QASplit (11.2)(2.2) 7-7 gsj0j/L(130 25"o-9~cl, 3 (21.2)(2.2) I L- 1-15'o4 4 .. (R) (31.2)(2.2) ýS-c6/3 /

5 (41.2)(2.2) -'061 £ t 3 2" 6 (51.2)(2.2) 7- d'-e6 1/ 3 11" 7 (1) (61.2)(2.2) -,-*5-od; ! 3 d/

8 (71.2)(2.2) 7-.-5,01 132j 3 9 (81.2)(2.2) cI-,5"o6 1 39*-S 10 (91.2)(2.2) 7- 0 OK 3d7o 11 (101.2)(2.2) I 3"c""° d,

12 (111.2)(2.2) 7"o5'O6 /3 A 13 (121.2)(2.2) 9"O 1330 14 (131.2)(2.2) -"A.S'o6 13 3A 15 (141.2)(2.2) ', ;5-06 1 33_ _ _ _ _ _ _ _

(Samples may be analyzed and stored, shipped for offsite evaluation or analyzed and disposed of.)

1. Relinquis, d by: *-4/*o1*. Date Time Received in go condition by:
3. Relinquished by Date Time Received in good condition by:
3. Relinquished by: Date Time Received in good condition by:
4. Relinquished by: Date Time Received in good condition by:

RM-72.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 19 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 1 of 8 FINAL STATUS SURVEY: "1' w/

1.0 DATA VERIFICATION 1.1 Data Acceptance X Review the Implementation Checklist (RM-77-1) to verify that survey isolation and control measures were executed prior to FSS and are being maintained.

X Review RM-77, Final Status Survey Implementation, to verify that methods, techniques, and survey activities required for FSS have been applied in accordance with the appropriate procedures.

1.2 Field QC Records:

X Review all assessments, Condition Reports and audits to ensure that identified issues have been resolved.

Comments:

____ Verify scan instrumentation was in calibration and the QC source checks were performed prior to and after surveys.

_Verify daily QC source checks for Canberra gamma spectroscopy detector properly logged prior to soil sample analysis.

1.3 Review Verification:

7' Verify that the Data Quality Objectives are complete.

  • .. Verify that the survey design has been technically reviewed.

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 20 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 2 of 8 Verify that gamma spectroscopy results have received a technical review.

Verify the Sample and Analysis Report (RM-59-1) is completed and reviewed.

Data Verilfication Completed: No Comments Assessor Dafe RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 21 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 3 of 8 2.0 DATA VALIDATION 2.1 Documentation Review:

Perform documentation review for quality control purposes and validate the data collected is complete and appropriate for use as defined by the survey design. Documentation includes:

Field measurement records Chain-of-custody Quality Control (QC) measurement records Current qualification of survey personnel Corrective Action Reports Data inputs (laboratory spectroscopy)

Sample preparation techniques 2.2 Detection Limit Review:

___ Scan MDCs are below established site DCGLs.

X/ Forced-count values are assigned as necessary when activity is not detected in a sample.

ffi Minimum Detectable Concentration (MDC) values of gamma spectroscopy are below established DCGLs.

2.3 Quality Control (QC) Data Review:

Quality Control (QC) data results have received required reviews and are complete and consistent.

4 Results of judgmental samples have been reviewed and evaluated.

4* Review to ensure that the analytical results of judgmental samples do not impact the evaluation for unrestricted release of the survey area.

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 22 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 4 of 8 2.4 Qualification of Data:

Statistical radionuclide-specific measurements for completeness. Evaluate the survey for determination of data usability and confirm that sufficient qualified data are present for the decision process.

a. Total number of statistical samples planned for the survey:
b. Total number of statistical samples determined as valid: /

b x120

c. Calculate % Completeness: -/,-" ()ý0 --

a

_zQualified data are A 00% completeness and are sufficient to support the Sign Test requirement for determination of unrestricted release.

Data Validation Completed: No Comments:

A~s'ses'so r Date RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 23 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 5 of 8 3.0 DATA QUALITY ASSESSMENT 3.1 Review the DQOs and Survey Design:

X1 Confirm that all inputs to the decision have been reviewed and are complete.

Z1* Verify that boundaries or constraints identified in the survey area have not affected the quality of the data.

Review the Statement of Hypothesis and confirm that it remains relevant.

__ Confirm that Type I and Type IIerror limits are consistent with DQOs.

J Confirm that the survey design is consistent with DQOs and that the appropriate number of data points were obtained.

3.2 Preliminary Review:

3.2.1 Preliminary Evaluation:

Quality Assessment (QA) reports consistent with procedure RM-79, Final Status Survey Quality Control.

v/ Survey is of sufficient intensity to satisfy classification requirement.

__ Potential trends of radioactivity levels in the survey area do not impact a decision for unrestricted release.

Comments:

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 24 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 6 of 8 3.2.2 Calculate Basic Statistical Quantities:

a. Number of qualified data points
b. Calculation of the Mean O2ocOV
c. Calculation of the Median
d. Calculation Standard Deviation Attach graphic representation of the data if any radionuclide-specific measurements exceed 50% of the DCGL.

Sample QA/QC measurements consistent with FSS data 3.3 Statistical Evaluation:

NOTE: If all measurement data are less than the DCGLw, statistical testing in not required and the survey unit meets the regulatory requirement for unrestricted release.

.wj" All survey measurements are below the DCGLw.

3.3.1 Verify Assumptions of the Survey Design

-__ Review the posting plot to verify that the data exhibits spatial independence. Spatial trends must be investigated and resolved prior to further assessment.

_ Review to verify dispersion symmetry. The appearance of skewed data must be investigated for cause and documented prior to further assessment.

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 25 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 7 of 8 X/ Review the dataset standard deviation and range for data variance.

Questionable data must be investigated for cause and documented prior to further assessment.

_ Verify that the data exhibits adequate power and confirm that the sample size is sufficient to satisfy the DQOs.

3.4 Draw Conclusions from the Data:

3.4.1 Investigation Levels and Response Actions Determine if data results have exceeded any inyestiation level.

Document findings.

3.4.2 Evaluation for Unrestricted Release Select applicable conclusion:

Survey area acceptance criteria met and survey area satisfies the requirements for unrestricted release:

___ All concentrations are less than the DCGLw. The Null Hypothesis is rejected.

The mean concentration of the survey area is below the DCGLw but individual measurements in the survey unit exceed the DCGLw. The Sign Test and EMC evaluation are successful and the Null Hypothesis is rejected.

RM-78.doc

RM-78 Revision 2 FINAL STATUS SURVEY ASSESSMENT Page 26 of 26 RM-78-3 DATA ASSESSMENT REPORT Page 8 of 8

_A4L Survey area acceptance criteria not met and survey area fails to satisfy the requirements for unrestricted release:

4. The mean concentration in the survey area exceeds the DCGLw. and the null hypothesis is confirmed.

The mean concentration of the survey area is below the DCGLw but individual measurements in the Unit exceed the DCGLw..

The Sign Test and EMC evaluation are unsuccessful and the null hypothesis is confirmed.

Data Quality Assessment Completed: O*No W)

Comments Assessor Date Reviews:

Technical Oview bate ES Superintendent Date RlM&ES Manager Date RM-78.doc

RM-78-3, Attachment I Statistical Quantities Release Record TBCx1 51 Relocated Soil from Containment/Turbine Building Demolition Area Sample Cs-I 37 Co-60 Weighted **Weighted Sum Number (pCi/gm) (pCi/gm) Sum (SOR) <DCGLw? DCGL-W. Sum Sign 1 0.0694 0.0121 0.0096 yes 0.9904 +1 2 0.0431 0.0065 0.0056 yes 0.9944 +1 3 0.0391 0.0283 0.0121 yes 0.9879 +1 4 0.0299 -0.0181 -0.0031 yes 0.9969 +1 5 0.0190 -0.0144 -0.0029 yes 0.9971 +1 6 0.0256 0.0002 0.0022 yes 0.9978 +1 7 0.0332 0.0000 0.0028 yes 0.9972 +1 8 0.0442 -0.0209 -0.0028 yes 0.9972 +1 9 0.0183 0.0151 0.0062 yes 0.9938 +1 10 -0.0020 -0.0016 -0.0007 yes 0.9993 +1 11 0.0212 0.0003 0.0019 yes 0.9981 +1 12 0.0312 0.0206 0.0090 yes 0.9910 +1 13 0.0706 0.0144 0.0104 yes 0.9896 +1 14 0.0427 0.0319 0.0135 yes 0.9865 +1 15 0.0458 -0.0087 0.0011 yes 0.9989 +1 Std. Dev 0.0189 0.0161 0.0056 Mean 0.0354 0.0044 0.0043 Median 0.0332 0.0003 0.0028 Number of Positive Differences (S+): n/a Critical Value, k, Table 1.3 of Marssim: n/a S+ >thank?: n/a Survey Unit Pass or Fail:

    • Pass
  • Note: Forced-Count values are used for samples with activity levels below the MDA.
    • Note: If all measurement data are less than the DCGL w, then the Sign Test is not required.

I. .

RM-79 Revision I FINAL STATUS SURVEY QUALITY CONTROL Page 11 of 13 RM-79-1 FSS QUALITY CONTROL EVALUATION RESULTS FSS Package # - QC Package #

QC Measurement Type Acceptance Criteria Met*? Reference

1. Replicate Scan --;/ No Step 5.1.3
2. Sample Recounts Step 5.1.4.1
a. In-house
  • No

, b. Third party Yes / No

3. Split Samples Step 5.1.4.2
c. In-house No 4,.,L/A d. Third party Yes / No
  • NOTE: IfAcceptance Criteria is not met, completion of Attachment RM-79-2, FSS Quality Control Investigation Results, is required.

Comments: Q A 44q - 4,4 1

_-i

/

Reviews:

Date

,Evaluator Technical Review Date RM-79.doc

QA Verification Split Sample Analysis Table 1 Date: 9/25/2006 Acceptance Criteria Resolution Ratio QA: TBC.,gl Excavated Soil from Contain. Bldg. Area <4 N/A 4-7 0.5-2.0 Type: Split Sample 8-15 0.6-1.66 16-50 0.75-1.33 Lab: In- House 51-200 0.8-1.25

>200 0.85-1.18 A B C D E F G RP BResults in Sample Radionuclide Result Below Results  % Error BRP Resolution Acceptancetio Recount Recount Comparison Agreement Result Compare MDA (pCi/g) (Sigma) (Table 1) Belo (pCi/g) F/A CowphrD MABelow MDA G with D) 2 Co-60 < 0.0754 n/a n/a n/a < 0.0588 0.78 YES 2 Cs-137 0.0431 46.17 2.17 n/a < 0.0605 1.40 YES Resolution C=()t Indicates results less than the MDA.

  • Note Results are consideredin agreement for MDA and near-MDA measurementcomparisons Results fihat fail agreement must be investigatedper RM-79.

QA Verification Sample Recount Analysis Table I Date: 9/25/2006 Acceptance Criteria Resolution Ratio QA: TBC,,.l Excavated Soil from Contain. Bldg. Area <4 N/A 4-7 0.5-2.0 Type: Sample Recounts 8-15 0.6-1.66 16-50 0.75-1.33 Lab: In- House 51-200 0.8-1.25

>200 0.85-1.18

~t A B C D E F G RP BResults in Sample Radionuclide Result Results  % Error BRP Ratio Recount Results Ratio Agreement Below (Sigma) Resolution 1' Result (pCi/g) F/A Compare MDA Below MDA G with D) 4 Co-60 < 0.0387 n/a n/a n/a < 0.0641 1.66 YES 4 Cs-137 < 0.0568 n/a n/a n/a < 0.0568 1.00 YES 7 Co-60 < 0.0541 n/a n/a n/a < 0.0442 0.82 YES 7 Cs-137 0.0332 44.44 2.25 n/a < 0.0547 1.65 YES Resolution C A)(aZ O

<Indicates results less than the MDA.

  • Note Results are consideredin agreement for MDA and near-MDA measurementcomparisons Results Ithat fail agreementmust be investigatedper RM-79.

n S -, 5'-

Tritium in Soil Data Results Final Status SurveyTBC, 15 1 Sample Tritium in Soil Number pCi/g 2 0.007 4 0.006 7 0.004 Mean: 0.0060 Median: 0.0060 St. Dev: 0.0010 Note: The DCGL for Tritium is 327 pCi/g.

Sample results are less than 0.2% of the DCGL

-Environmental, Inc.

Midwest Laboratory an Aliegheny Technologies Co.

700 Landwehr Road

  • Northbrook, IL60062-2310 ph. (847) 564-0700 . fax (847) 564-4517 Mr. David W. Parish LABORATORY REPORT NO. 8022-100-243 Big Rock Point DATE: 10-02-2006 10269 US-31 North SAMPLES RECEIVED: 09-27-2006 Charlevoix, MI 49720 PURCHASE ORDER NO:

Below are the results of the analyses for tritium on three soil samples.

Excavated Soil Survey TBCx1 5-1 Sample Collection Lab Concentration MDA Description Date Code (pCi/g of soil) (pCi/g of soil)

H-3 2 09-25-06 BRSO-6591 0.007 +/- 0.006 < 0.011 4 09-25-06 BRSO-6592 0.006 +/- 0.006 < 0.010 7 09-25-06 BRSO-6593 0.004 +/- 0.005 < 0.010 The error given is the probable counting error at 95 % confidence level. The less than, (<), value is based on 4.66 sigma counting error for background sample.

Sincerely, Bronia Grob, Laboratory Manager

-x APPROVED BY Tony Coorlim, Quality Assurance

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