ML070590446

Submittal of Final Status Survey Report for the University of Washington More Hall Annex Decommissioning Project

ML070590446
Person / Time
Site:	05000139
Issue date:	02/26/2007
From:	Addison S J Univ of Washington
To:	Alexander Adams NRC/NRR/ADRA/DPR
References
TAC MD2586
Download: ML070590446 (327)

Text

Q UN I V ER SIT Y OF ENVIRONMENTAL HEALTH AND SAFETY 1ITWASLHLI1N1GTON 201 Hall Health Center Box 354400* Seattle, Washington 98195-4400 Phone 206.543.0463 FAX 206.543.3351 www.ehs.washington.edu February 26, 2007 Alexander Adams US Nuclear Regulatory Commission Mail Stop O G -15 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Re: Termination of NRC License # R-73

Dear Alexander:

The University is pleased to submit the revised Final Status Survey Report for the University of Washington More Hall Annex Decommissioning Project. We believe the enclosed controlled copy demonstrates that the conditions and requirements of 10CFR 50.82 B6 have been met, and addresses the NRC Request for Additional Information dated February 7, 2007. The responses to your questions of February 7, 2007, along with necessary back-up documentation, are attached to this letter and, where appropriate, corresponding changes to the Final Status Survey are indicated with a vertical bar in the left hand margin.We believe the final status survey process has established that the More Hall Annex is now suitable for release from radiological controls.

The enclosed revised Final Status Survey Report provides the necessary documentation demonstrating the radiological condition of the facility and responds to the NRC review comments.

This document also supports the conclusion that the University of Washington has complied with NRC decommissioning requirements.

Based on this, the University of Washington is now requesting termination of United States Nuclear Commission License number R-73. Please contact me with any questions about this request.Sincerely, Stanley J. Addison, M.S.UW Radiation Safety Officer I declare under penalty of perjury that, to the best of my knowledge, the forgoing is true and correct. Executed 2/26/07 Copy: Marty Howlett, Project Manager, Capital Projects Office Jeff Angeley, Associate Construction Manager, Capital Projects Office REQUEST FOR ADDITIONAL INFORMATION UNIVERSITY OF WASHINGTON RESEARCH REACTOR FINAL STATUS SURVEY REPORT DOCKET NO. 50-139 1. The cited nominal efficiency values for Alpha Gas Proportional detectors in Tables 5-1 and 5-2 and the text in Section 5.3.1.1 are inconsistent.

The nominal efficiency values should be consistent in the document, and the associated Minimum Detectable Activities (and Probabilities of Detection) should be calculated using the same efficiency value for a given instrument combination/measurement type. Please update this information to be consistent.

2. Section 5.3.2, Instrument Calibration, does not include a discussion of calibration sources (isotope, material, and geometry) and source-to-detector distance for each type of radiation measurement (alpha, beta, gamma). Please provide this information.

3. Section 7.1.3.3 describes the use of a 50 cm 2 air proportional detector for assessing total alpha activity inside the fuel storage tubes (10 cm diameter).

Table 7-2 describes three elevated alpha activity results and the associated weighted average. Please provide the source-to-detector distance and the method of determining the net results in dpm/100 cm 2 (e.g., was the measurement result doubled since the detector is 50 cm 2 in area?). Discuss if the source-to-detector distance results in an underestimation or overestimation in the efficiency and results.4. Section 4.3.2 of the Decommissioning Plan states that "For direct methods of surface monitoring, the scanning speed will be slow enough to ensure a source detectionr probability of at least 25% of the guideline level." The calculated scan MDC for beta surface activity, as specified in Table 3-3 of the Final Site Survey Plan (FSSP), is less than 25% of the release criteria for gas proportional detectors, but is not less than 25%of the release criteria for beta friskers.

Furthermore, the scan MDC for alpha surface activity specified in Table 3-3 of the FSSP is 160 dpm/100 cm 2 , which is not less than 25% of the release criteria.

Standard final site survey instrumentation is typically not capable of detecting radioactivity at 25% of the Regulatory Guide 1.86 release criteria when utilized for scanning, nor is there a regulatory requirement that scanning instrumentation should be capable of detecting radioactivity at these levels. Please develop and submit a technical basis to justify the deviation from the requirements of the DP or revise the DP accordingly.

If you revise the DP, please submit a copy of the revision paperwork.

5. Because of your revision to release criteria that occurred after NRC's site visit to account for tritium, please collect and submit additional measurements around two locations of interest on the bioshield floor (grid location B, 1) and bioshield interior south wall (grid location E,-1), to verify that the square-meter average is less than the modified average beta contamination limit of 1,700 dpm/100 cm 2.The individual measurement results for these locations were 3,700 and 1,800 dpm/100 cm 2 , respectively.

)

UW More Hall Annex Decommissioning Project Document Comments Form F Services, Inc.Document Final Status Survey Report Document No.: UW-MCP-OP-13 Rev. 1 Commenter(s)

NRC Docket # 50-139 RAI (February 7, 2007) Document Date: December 6, 2006 Project Number 10492 Comment Section/ Comments Responses No. Page 1 5.3.1.1 The cited nominal efficiencies for Alpha Gas Proportional The text contained in Section 5.3.1.1 has been detectors in Tables 5-1 and 5-2 and the text in Section 5.3.1.1 modified to provide a consistent instrument efficiency are inconsistent.

The nominal efficiency values should be and a discussion of the probability of detection consistent in the document, and the associated Minimum formula from the MARSSIM.Detectable Activities (and Probabilities of Detection) should be calculated using the same efficiency value for a given instrument combination/measurement type.2 5.3.2 ORISE recommends the section 5.3.2, Instrument Calibration, A short description of the daily response checks and include a discussion of calibration sources (isotope, material, the associated sources has been added to Section and geometry) and source-to-detector distance for each type of 5.3.2 of the FSS report.radiation measurement (alpha, beta, gamma).3 7.1.3.3 Section 7.1.3.3 describes the use of a 50 cm' air proportional A discussion has been added to Section 7.1.3.3 of the detector for assessing total alpha activity inside the fuel FSSR on the use of the 50-cm 2 detector in the fuel storage tubes (10 cm diameter).

Table 7-2 describes three storage tubes.elevated alpha activity results and the associated weighted average. ORISE recommends including additional information Section 6.2 of the FSSR details the data conversion in the report that describes

1) the source-to-detector distance process which includes detector area correction for all and 2) the method of determining net results in dpm/100 cm 2 measurements based upon the detector utilized.(e.g. was the measurement result doubled since the detector is 50 cm 2 in area?). The additional information should support the premise that the source-to-detector distance did not result in an overestimation in the efficiency, and therefore underestimation of the result.I Document I Final Status Survey Report Document No.: UW-MCP-OP-13 Rev. 1 Commenter(s)

NRC Docket # 50-139 RAI (February 7, 2007) Document Date: December 6, 2006___Project Number 10492 Comment Section/ Comments Responses No. Page 4 DP Section 4.3.2 of the Decommissioning Plan states that "For A 50.59-type change has been drafted ,reviewed and direct methods of surface monitoring, the scanning speed will approved by the University Technical Safety be slow enough to ensure a source detection probability of at committee to modify the Decommissioning Plan least 25% of the guideline level." The calculated scan MDC requirement of alpha scan MDC's below 25% of the for beta surface activity, as specified in Table 3-3 of the Final guideline levels. A copy of this change request has Site Survey Plan (FSSP), is less than 25% of the release been included as an attachment to this Project criteria for gas proportional detectors, but is not less than 25% Document Comment Form. The requirement has of the release criteria for beta friskers.

Furthermore, the scan been modified to ensure that alpha scans be MDC for alpha surface activity specified in Table 3-3 of the performed slow enough to ensure that the scan MDC FSSP is 160 dpm/100cm 2 , which is not less than 25% of the is below the EMC criteria, in this case 300 release criteria.

Standard final site survey instrumentation is dpm/1 00cm 2.typically not capable of detecting radioactivity at 25% of the Regulatory Guide 1.86 release criteria when utilized for Beta frisker instrumentation was used to collect FSS scanning, nor is there a regulatory requirement that scanning evaluated data in localized areas where gas instrumentation should be capable of detecting radioactivity at proportional probes were to large. In all cases, the these levels. Please develop and submit a technical basis to beta scan MDC was below the EMC value of 15,000 2 justify the deviation from the requirements of the DP or revise dpm/1 00cm2.the DP accordingly.

If you revise the DP, please submit a copy of the revision paperwork.

5 N/A Because your revision to the release criteria that occurred after Material was collected from these two locations the NRC's site visit to account for tritium, please collect and immediately following the completion of the final submit additional measurements around two locations of NRC site inspection.

This material was sampled and interest on the bioshield floor (grid location B,1) and bioshield analyzed to develop the Hard To Detect nuclide interior south wall (grid location E, -1), to verify that the fraction and revised release criteria.

These locations square-meter average is less than the modified average beta were immediately resurveyed and the results were contamination limit of 1,700 dpm/100cm

2. The individual included as part of the evaluated FSS data in UW measurement results for these locations were 3,700 and 1,800 MCP-OP-13 Rev 1. The final beta value for floor dpr/1 0Ocm 2 , respectively.

location B,1 is 413 dpm/100cm 2 and the final value for wall location E,-1 is 617 dpm/100cm 2.2 UN VE R S ITY OF WASH! NGTON UW 10492 More Hall Annex Decontamination and Decommissioning

1. Purpose ,The NRC letter dated 1/31106 (Re: Authority to Make Changes to the Decommissioning Plan)establishes the conditions under which the licensee may make changes to the facility, decommissioning plan or related procedures without NRC approval.

The More Hall Annex Decomnmissioning Plan has been approved by the NRC. During the decommissioning process it may be subject to modifications to accommodate alternate contractor methods, address unforeseen site conditions or safety considerations.

This procedure provides the means for the University of Washington, as licensee, to evaluate and accept changes to the facility or procedures, methods of performing or controlling in accordance with the NRC letter dated 1131/06 and thereby without obtaining NRC approval.2. Applicability 2.1 This procedure is not intended to modify aspects of the Decommissioning Plan related to the DECON decommissioning option such as: 2.1.1 The criteria for unrestricted release of the facility and the site, 2.1.2 The Technical Safety Committee 2.1.3 Radiation exposure limits as required under 10 CFR Part 20.Therefore, the following sections of the Decommissioning Plan are specifically exempt from this modification procedure and will require NRC approval prior to modification.

Reference Topic 1.3.1 Selected Method 1.3.7.1 Surface contamination shall be below the limits specified in Table 1, "Acceptable Surface Contaminations Levels," of USNRC Regulatory Guide 1.86, "Termination of Operating Licenses for Nuclear Reactors." 13.7.2 Residual radioactivity shall not cause area dose levels to exceed 5 urem/hr above background at 1 meter above the surface of the radioactive materials.

2.1 Decommissioning

Alternative

2.3.2 Technical

and Safety Committee 2.6 Radioactive Materials Unrestricted Release Criteria 3.2.2 Occupational Radiation Exposure Limits 2.2 In accordance with paragraph I 0.0(b)(1) of the Decommissioning Plan (as amended), the University may make changes in the facility or in procedures as described in the Decommissioning Plan where: 2.2.1' A change to the technical specification as incorporated in the license is not required and 2.2.2 .None of the conditions in paragraph

2.3.1 through

2.3.6 listed below will result.2.3 In accordance with paragraph 10.0(b)(2) of the Decommissioning Plan (as amended), the University must obtain NRC approval prior to implementing a proposed change where the change may result in any of the following conditions:

2.3.1 Results

in more than a minimal increase in the frequency of occurrence of an-accident previously evaluated in the Decommissioning Plan 1 of(4

2.3.2 Result

in more than a minimal increase in the likelihood of occurrence ora malfunction of a structure, system, or component (SSC) important to safety previously evaluated in the Decommissioning Plan.2.3.3 Result in more than a minimal increase in the consequences of an accident previously evaluated in the Decommissioning Plan, 2.3.4 Result in more than a minimal increase in the consequences ofa malfunction of an SSC important to safety previously evaluated in the Decommissioning Plan.2.3.5 Create a possibility for an accident of a different type than any previously evaluated in the Decormnissioning Plan-2.3.6 Result in a departure from a method of evaluation described in the Decommissioning Plan used in establishing the design bases or in the safety analyses.2.4 In accordance with paragraph I0.0(a)(1) of the Decommissioning Plan (as amended), a change to the Decommissioning Plan will refer to: 2.4.1 A modification or addition to, or removal from, the facility or procedures that affect a design function, method of performing or controlling the function, or an evaluation that demonstrates that intended functions will be accomplished.

2.4.2 Departure

from a method of evaluation described in the Decommissioning Plan (as amended) used in establishing the design basis or in the safety analysis will mean: i. Changing any, of the elements of the method(s) described in the Decommissioning Plan (as amended) unless the result of the analysis are conservative or essentially the same.ii. Change to a method described in the Decommissioning Plan (as amended) to another method, unless that proposed method has been approved by the NRC) for the intended application.

3. Evaluation Process 3.1 The Safety Evaluation form found in Appendix A of this procedure shall be completed to address the applicable criteria.3.2 Appendix A Part A must clearly define the proposed change, citing the existing document and substitution.

3.3 Applicability

of the NRC letter dated 1/31106 is determined by Part B of the evaluation form.A "Yes" answer to any of the questions in Part B invalidates the use of this procedure for Decommissioning Plan change approval.3.4 Once it is detennined that a given activity meets the evaluation criteria under this procedure, Part C will be reviewed for acceptance by the licensee Technical Safety Committee.

4. Recordkeeping

a. The University will submit, as specified in 10 CFR 50.4 and in accordance with the paragraph 10.0(c)(2) of the Decommissioning Plan (as amended), a report containing a brief description of any changes that are adopted, including a summary of the evaluation of each. A report will be submitted to the NRC at intervals not to exceed 24 months.b. The University will maintain records of all changes in the facility or procedures as adopted under this procedure.

The records will be maintained until termination of facility license R-73 has been issued by the NRC or at least 5 years, whichever is longer.2 otC4 APPENDIX A MORE HALL REACTOR DECOMMISSIONING PL-N CHANGE EVALUAT.[ON FOiM I NSTRIUC.TIONS:

The requestor will compleic this checklist.

For each question, sufficient information must he provided to substantiate the response.

This inforination must be provided on a separate form and attached to 1his checklist.

PART A DESCRIPTION OF PROPOSED C..H-ANGE SICATURE: " ".'ITLE, "-SS COORDINATOR DATE. lU/t19!2t0016 PROPOSED CHANGE DESCRUPTION (ATTACH ADDITIONAL L -NT I OAS/DECE$SARY:

CHANGE SECTFON 4.3.2 PARAGRA' i 2 SENTENCE 2 TO READ ASNOLLOWS SY"FOR D1IRECT METHODS OF srLrlBFACE mO.NiTORINC, THE SCANN-G SPEVED W LL BE SLOW ENOUM11TO ENSURE A SOURCE DETEC7iTION PROBABILITY OF AT LEAST 250/% OF TRlE GUIDELINE LEVEL FOR BETA EMITTERS AND LESS TIAN TEIE UPPER GUIDELIJNE LEVEL FOR ALPHA E.,MITT'ERS." I DISCUSsION SUPPORTING THIS C-4-NGE REQUEST 1S ATTACHED.PART B APPLICABILITY 1 I. Will the change result in more than a minimal increase in the frequency of occurrence of an '1 Yes accident previously evaluated in the Decommissioning Plan? X No 2. Will the change result in more than a minimial increase in the likelihood of occurTence Ora 1 0 Yes malfunction of a structure, system or component important to safety previously evaluated in I X No f the Decommissioning Plan? r___XNo 3. Will the change result in more than a minimal increase in the consequences of an accident [0 Yes previously evaluated in the Decomniissioning Plan? X No) 4. Will the change result in more than a minimal increase in the consequences of a malfunction C0 Yes L of a structiure, system or component important to safety as previously evaluated in the X No 4 L Decommissioning Plan?_PART C CRITERIA FORACCEPTANCE

1. Will the proposed change require a change to the Fi l. Status Survey Pl.an 1?Yes IX No 2. Will the proposed change involve the potential to have an adverse effect on the 0 Yes environmen.?l_

_x _ )3. Does the proposed change increase the potential radioactive dose to facility Personnel?

0 Yes.Irso, protective measures and dose calculations must be provided ftir evaluntion.

X No 4. Does the proposed change increase the potenti-al radioactive dose to the public? If so, 1-0 Yes protective measures and dose calculation must be provided for evaluation.

X No 5. Does the proposed change require revisions to the contractor Work Plan? 0 Yes If so, provide revisions.

X No 6. Does the proposed change require revisions to the contractor Sife Healh and Saf.ty Pn Yes (SH.4,519?

If so. provide revisions-to the S-HASP addressing the changes. X to1'0 ECHNICA. S .OMMITTEE DATE A.I)VISING HEALTH PHYSICIST DATE"! C." 4 DISCUSSION IN SUPPORT OF THE CHANGE REQUEST For the radionuclides of concern present at UWNR, Regulatory Guide 1.86 establishes guideline criteria as follows: Emitter Average Static Activity Maximum Static Activity Removable Type Activity.Alpha 100 dpmn/100cm' 300 dpm/I 00cmP 20 (over not more than I-rn) (over not more than 100-cm') dpilrl00cm2 Beta 5,000 dpm/100cin 15,000 dpni 100cm 2 1,000-(over not more than 1-n 2) (over not more than I -n 2) dpm/100cm' Alpha-emission detecting field instrumentation does not exist that is capable of meeting a Minimum Detectable Activity (MDA) of <25% of the average guideline criteria (25 dpm/l00cm2) during scanning evolutions.

The nuclear industry standard is to meet a scan MDA for beta emitters of 25% and less than the upper guideline limit (300 dpm/100cm 2) for alpha emitters.

This change would bring the Decommissioning Plan into accordance with typical industry standards and eliminate a situation where the DP requirements are not capable of being met.Oak Ridge Institute for Science and Education (ORISE), the independent verification contractor employed by the US Nuclear Regulatory Commission (NRC), concurs with this position and has stated in their report from the August in-process inspection:

-) "ORISE recognizes that standard FSS instrumentation is not capable of detecting radioactivity at 25% of the Regulatory Guide 1-86 release criteria when utilized for scanning, nor is there a regulatory requirement that scanning instrumentation should be capable of detecting radioactivity at these levels." The final status survey for alpha affected areas consisted of alpha scans, beta/gamma scans, alpha static and beta/gamma static measurements.

The scan MDA of <25% was met for beta/gamma measurements.

The alpha activity limit for facility license termination is not affected since the release limit is based on the static measurements.

The MDA for the static measurements also met the Decommissioning plan criteria.Therefore the final level of radioactivity remaining in the UWNR facility meets the release criteria of the Decommissioning Plan, Regulatory Guide 1.86 and the regulatory requirement from IOCFR20.4 of 4 REVISED FINAL STATUS SURVEY REPORT UNIVERSITY OF WASHINGTON NUCLEAR REACTOR NRC LICENSE NUMBER R-73 UW-MCP-OP-13 Rev. 2 February 22, 2007 Prepared for the University of Washington by: ENERCON Services, Inc.4499 Old William Penn Highway Murrysville, PA 15668 Richard Moss, Executive Engineer Energy Solutions 143 West Street New Milford, CT 06776 University of Washington Project #10492 4 ...UNITED STATES,NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 7, 2007 SE.CE:iVE Dr. Stanley Addison, Radiation Safety Officer Environmental Health and Safety University of Washington 223 Hall Health Center Mail Stop 354400 Seattle, Washington 98195-4400

SUBJECT:

UNIVERSITY OF WASHINGTON-REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE TERMINATION (TAC NO. MD2586)

Dear Dr. Addison:

We are continuing our review of your request for termination of Facility License No. R-73 for the University of Washington Research Reactor which you submitted on December 13, 2006.During our review of your Final Status Survey Report, questions have arisen for which we require additional information and clarification.

Please provide responses to the enclosed request for additional information within 30 days of the date of this letter. In accordance with 10 CFR 50.30(b), your response must be executed in a signed original under oath or affirmation.

Following receipt of the additional information, we will continue our evaluation of your request.If you have any questions regarding this review, please contact me at (301) 415-1127.Sincerely, Alexander Adams, ir.Anior Project Manager Research and Testt'eactors Branch A Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-139 License No. R-73

Enclosure:

As stated cc w/enclosure:

See next page 0 University of Washington Docket No. 5D-139 p cc: Dr. M. Carette, Assistant to the Dean College of Engineering University of Washington Box 352180 Seattle, WA 98195-2180 Stanley Addison, Radiation Safety Officer Environmental Health and Safety University of Washington Hall Health Center Box 354400 Seattle, WA 98195-4400 Elizabeth Kane, Project Manager Capital Projects Office University of Washington University Facilities Annex 2 Box 352205 Seattle, WA 98195-2205 Dr. Mani Soma, Acting Dean College of Engineering University of Washington P.O. Box 352180 Seattle, WA 98195-2180 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611 0 REQUEST FOR ADDITIONAL INFORMATION UNIVERSITY OF WASHINGTON RESEARCH REACTOR FINAL STATUS SURVEY REPORT DOCKET NO. 50-139 1. The cited nominal efficiency values for Alpha Gas Proportional detectors in Tables 5-1 and 5-2 and the text in Section 5.3.1.1 are inconsistent.

The nominal efficiency values should be consistent in the document, and the associated Minimum Detectable Activities (and Probabilities of Detection) should be calculated using the same efficiency value for a given instrument combination/measurement type. Please update this information to be consistent.

2. Section 5.3.2, Instrument Calibration, does not include a discussion of calibration sources (isotope, material, and geometry) and source-to-detector distance for each type of radiation measurement (alpha, beta, gamma). Please provide this information.

3. Section 7.1.3.3 describes the use of a 50 cm 2 air proportional detector for assessing total alpha activity inside the fuel storage tubes (10 cm diameter).

Table 7-2 describes three elevated alpha activity results and the associated weighted average. Please provide the source-to-detector distance and the method of determining the net results in dpm/100 cm 2 (e.g., was the measurement result doubled since the detector is 50 cm 2 in area?). Discuss if the source-to-detector distance results in an underestimation or overestimation in the efficiency and results.4. Section 4.3.2 of the Decommissioning Plan states that "For direct methods of surface monitoring, the scanning speed will be slow enough to ensure a source detection probability of at least 25% of the guideline level." The calculated scan MDC for beta surface activity, as specified in Table 3-3 of the Final Site Survey Plan (FSSP), is less than 25% of the release criteria for gas proportional detectors, but is not less than 25%of the release criteria for beta friskers.

Furthermore, the scan MDC for alpha surface activity specified in Table 3-3 of the FSSP is 160 dpm/1 00 cm 2 , which is not less than 25% of the release criteria.

Standard final site survey instrumentation is typically not capable of detecting radioactivity at 25% of the Regulatory Guide 1.86 release criteria when utilized for scanning, nor is there a regulatory requirement that scanning instrumentation should be capable of detecting radioactivity at these levels. Please develop and submit a technical basis to justify the deviation from the requirements of the DP or revise the DP accordingly.

If you revise the DP, please submit a copy of the revision paperwork.

5. Because of your revision to release criteria that occurred after NRC's site visit to account for tritium, please collect and submit additional measurements around two locations of interest on the bioshield floor (grid location B, 1) and bioshield interior south wall (grid location E,-1), to verify that the square-meter average is less than the modified average beta contamination limit of 1,700 dpm/100 cm 2.The individual measurement results for these locations were 3,700 and 1,800 dpm/1 00 cm 2 , respectively.

0 UW More Hall Annex Decommissioning Project Document Comments Form 0 ENERCON Services, Inc.5ERV/-,CES5' Document Final Status Survey Report Document No.: UW-MCP-OP-13 Rev. 1 Commenter(s)

NRC Docket # 50-139 RAI (February 7, 2007) Document Date: December 6, 2006 Project Number 10492 Comment Section/ Comments Responses No. Page 1 5.3.1.1 The cited nominal efficiencies for Alpha Gas Proportional The text contained in Section 5.3.1.1 has been detectors in Tables 5-1 and 5-2 and the text in Section 5.3.1.1 modified to provide a consistent instrument efficiency are inconsistent.

The nominal efficiency values should be and a discussion of the probability of detection consistent in the document, and the associated Minimum formula from the MARS SIM.Detectable Activities (and Probabilities of Detection) should be calculated using the same efficiency value for a given instrument combination/measurement type.2 5.3.2 ORISE recommends the section 5.3.2, Instrument Calibration, A short description of the daily response checks and include a discussion of calibration sources (isotope, material, the associated sources has been added to Section and geometry) and source-to-detector distance for each type of 5.3.2 of the FSS report.radiation measurement (alpha, beta, gamma).3 7.1.3.3 Section 7.1.3.3 describes the use of a 50 cm 2 air proportional A discussion has been added to Section 7.1.3.3 of the detector for assessing total alpha activity inside the fuel FSSR on the use of the 50-cm 2 detector in the fuel storage tubes (10 cm diameter).

Table 7-2 describes three storage tubes.elevated alpha activity results and the associated weighted average. ORISE recommends including additional information Section 6.2 of the FSSR details the data conversion in the report that describes

1) the source-to-detector distance process which includes detector area correction for all and 2) the method of determining net results in dpm/100 cm 2 measurements based upon the detector utilized.(e.g. was the measurement result doubled since the detector is 50 cm2 in area?). The additional information should support the premise that the source-to-detector distance did not result in an overestimation in the efficiency, and therefore underestimation of the result.1 0 * *Document Final Status Survey Report Document No.: UW-MCP-OP-13 Rev. 1 Commenter(s)

NRC Docket # 50-139 RAI (February 7, 2007) Document Date: December 6, 2006 Project Number 10492 Comment Section/ Comments Responses No. Page 4 DP Section 4.3.2 of the Decommissioning Plan states that "For A 50.59-type change has been drafted ,reviewed and direct methods of surface monitoring, the scanning speed will approved by the University Technical Safety be slow enough to ensure a source detection probability of at committee to modify the Decommissioning Plan least 25% of the guideline level." The calculated scan MDC requirement of alpha scan MDC's below 25% of the for beta surface activity, as specified in Table 3-3 of the Final guideline levels. A copy of this change request has Site Survey Plan (FSSP), is less than 25% of the release been included as an attachment to this Project criteria for gas proportional detectors, but is not less than 25% Document Comment Form. The requirement has of the release criteria for beta friskers.

Furthermore, the scan been modified to ensure that alpha scans be MDC for alpha surface activity specified in Table 3-3 of the performed slow enough to ensure that the scan MDC FSSP is 160 dpm/100cm 2 , which is not less than 25% of the is below the EMC criteria, in this case 300 release criteria.

Standard final site survey instrumentation is dpm/100cm2.

typically not capable of detecting radioactivity at 25% of the Regulatory Guide 1.86 release criteria when utilized for Beta frisker instrumentation was used to collect FSS scanning, nor is there a regulatory requirement that scanning evaluated data in localized areas where gas instrumentation should be capable of detecting radioactivity at proportional probes were to large. In all cases, the these levels. Please develop and submit a technical basis to beta scan MDC was below the EMC value of 15,000 justify the deviation from the requirements of the DP or revise dpm/100cm 2.the DP accordingly.

If you revise the DP, please submit a copy of the revision paperwork.

5 N/A Because your revision to the release criteria that occurred after Material was collected from these two locations the NRC's site visit to account for tritium, please collect and immediately following the completion of the final submit additional measurements around two locations of NRC site inspection.

This material was sampled and interest on the bioshield floor (grid location B,1) and bioshield analyzed to develop the Hard To Detect nuclide interior south wall (grid location E, -1), to verify that the fraction and revised release criteria.

These locations square-meter average is less than the modified average beta were immediately resurveyed and the results were 2 contamination limit of 1,700 dpm/I00cm

.The individual included as part of the evaluated FSS data in UW measurement results for these locations were 3,700 and 1,800 MCP-OP-13 Rev 1. The final beta value for floor dpm/100cm 2 , respectively.

location B,1 is 413 dpm/100cm 2 and the final value for wall location E,-1 is 617 dpm/100cm 2.2 U N IVE R S ITY OF 1WASHINGTON UW 10492 More Hall Annex Decontamination and Decommissioning

1. Purpose The NRC letter dated 1/31/06 (Re: Authority to Make Changes to the Decommissioning Plan)establishes the conditions under which the licensee may make changes to the facility, decommissioning plan or relatcd procedures without NRC approval.

The More Hall Annex Decommissioning Plan has been approved by the NRC. During the decommissioning process it may be subject to modifications to accommodate alternate contractor methods, address unforeseen site conditions or safety considerations.

This procedure provides the means for the University of Washington, as licensee, to evaluate and accept changes to the facility or procedures, methods of performing or controlling in accordance with the NRC letter dated 1/31/06 and thereby without obtaining NRC approval.2. Applicability 2.1 This procedure is not intended to modify aspects of the Decommissioning Plan related to the DECON decommissioning option such as: 2.1.1 The criteria for unrestricted release of the facility and the site, 2.1.2 The Technical Safety Committee 2.1.3 Radiation exposure limits as required under 10 CFR Part 20.Therefore, the following sections of the Decommissioning Plan are specifically exempt from this modification procedure and will require NRC approval prior to modification.

Reference Topic 1.3.1 Selected Method 1.3.7.1 Surface contamination shall be below the limits specified in Table I, "Acceptable Surface Contaminations Levels," of USNRC Regulatory Guide 1.86, "Termination of Operating Licenses for Nuclear Reactors." 1.3.7.2 Residual radioactivity shall not cause area dose levels to exceed 5 urem/hr above background at I meter above the surface of'the radioactive materials.

2.1 Decommissioning

Alternative

2.3.2 Technical

and Safety Committee 2.6 Radioactive Materials Unrestricted Release Criteria 3.2.2 Occupational Radiation Exposure Limits 2.2 In accordance with paragraph 10.0(b)(1) of the Decommissioning Plan (as amended), the University may make changes in the facility or in procedures as described in the Decommissioning Plan where: 2.2.1 A change to the technical specification as incorporated in the license is not required and 2.2.2 None of the conditions in paragraph

2.3.1 through

2.3.6 listed below will result.2.3 In accordance with paragraph 10.0(b)(2) of the Decommissioning Plan (as amended), the University must obtain NRC approval prior to implementing a proposed change where the change may result in any of the following conditions:

2.3.1 Results

in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the Decommissioning Plan 1 44

2.3.2 Result

in more than a minimal increase in the likelihood of occurrence of a malfunction of a stnicture, system, or component (SSC) important to safcty previously evaluated in the Decommnissioning Plan.2.3.3 Result in more than a minimal increase in the consequences of an accident previously evaluated in the Decommissioning Plan.2.3.4 Result in more than a minimal increase in the consequences of a malfunction of an SSC important to safety previously evaluated in the Decommissioning Plan.2.3.5 Create a possibility for an accident of a different type than any previously evaluated in the Decomnnissioning Plan-2.3.6 Result in a departure from a method of evaluation described in the Decommissioning Plan used in establishing the design bases or in the safety analyses.2.4 In accordance with paragraph I0.0(a)(l) of the Decommissioning Plan (as amended), a change to the Decommissioning Plan will refer to: 2.4.1 A modification or addition to, or removal from, the facility or procedures that affect a design function, method of performing or controlling the function, or an evaluation that demonstrates that intended functions will be accomplished.

2.4.2 Departure

from a method of evaluation described in the Decommissioning Plan (as amended) used in establishing the design basis or in the safety analysis will mean: i. Changing any of the elements of the method(s) described in the Decommissioning Plan (as amended) unless the result of the analysis are conservative or essentially the same.ii. Change to a method described in the Decommissioning Plan (as amended) to another method, unless that proposed method has been approved by the NRC for the intended application.

3. Evaluation Process 3.1 The Safety Evaluation form found in Appendix A of this procedure shall be completed to address the applicable criteria.3.2 Appendix A Part A must clearly define the proposed change, citing the existing document and substitution.

3.3 Applicability

of the NRC letter dated 1/31/06 is determined by Part B of the evaluation form.A "Yes" answer to any of the questions in Part B invalidates the use of this procedure for Decommissioning Plan change approval.3.4 Once it is detennined that a given activity meets the evaluation criteria under this procedure, Part C will be reviewed for acceptance by the licensee Technical Safety Committee.

4. Recordkeeping

a. The University will submit, as specified in 10 CFR 50.4 and in accordance with the paragraph 10.0(c)(2) of the Decommissioning Plan (as amended), a report containing a brief description of any changes that are adopted, including a summary of the evaluation of each. A report will be submitted to the NRC at intervals not to exceed 24 months.b. The University will maintain records of all changes in the facility or procedures as adopted under this procedure.

The records will be maintained until termination of facility license R-73 has been issued by the NRC or at least 5 years, whichever is longer.2 of 4 APPENDIX A NIORE HALL REACTOR DECOMIVIISSIONiNG PILAN CILANCE EVALUATION FO1i.1 Mil'rUiCTI ONS: The requestor will complele this checklist.

For each q,,uestion, sufficient information must be provided to substanliate "Le response.

This information must be provided on a .eparate fornm alnd attached to this checklist.

PiART A DESCRIPTION OF PROPOSED C.HANGE SICNATURE:

TITLE: FISS COORDINATOR DATE: 1l/99/2OO6 PROPOSED CHANGE DESCRTPTJON (ATTACH ADDITIONAL INTFOCRM1.TION AS NECESSARY:

CHANGE SECTuON 4.3.2 PARAGRAPIH 2 SENTENCE 2 TO READ AS FOLLOWS: I"FOR DIRECT METHODS OF SULRFACE MIONITORNC, THE SCANNDING SPEED WITILL BE SLOW ENOUGH TO ENSUIRE A SOURCE DETECTION PROBA.BLITY OF AT LEAST 25% OF THE IGUIDELINE.

LEVEL, FOR BETA EMITTERS AND LESS THAN THE UPPER GUIDELU{E.

LEVEL FOR ALPHA EMITTERS."1 DiscussioN SUPPORTING THIS CHAUNGE REQUEST 1S ATTACHED, PAPT R AP~I.ICArni.1TV

1. Will the change result in more than a minimal increase in the frequency of occurrence of an 0 Yes accident previously evaluated in the Decommissionimn Plan? XNo 2. Will the change result in rnore than a minimal increase in the likelihood or'occurrence ol'a 0 Yes malfunction of a structure, system or component important to safety previously evaluated in X No the Decommissioning Plan? _3. Will the change result in more than a minimal increase in the consequences of an accident J 0 Yes previously evaluated in the Decommissioning, Plan? X No 4. Will the change result in more than a minimal increase in the consequences of a malfunction 01 Yes of a structure, system or component important to safety as previously evaluated in the X No L Decommissioning Plan?PART C CRITERIA FOR ACCEPTANCE_

'1. Wi'l the proposed change requhe a change to the Fincal Status 7WVcyC a-5 Yes SX 'No 2. Will the proposed change involve the potential to have an adverse effect on the Yes environment?

_.___ _ __\3. Does the proposed change increase the potential radioactive dose to facility personnel?

I ED Yes If so, protective measures and dose calculations must be provided for evaluation.

I X No 4. Does the proposed change increase the potential radioactive dose to the public? If so, 0 0 Yes I protective measures and dose calculation must be provided for evaluation.

j X No 5. Does the proposed change require revisions to the. contractor J'ork Plan? 0 Yes S If so, provide revisions.

__x N,,0 6. Does the proposed change rcquirc revisions to the contractor Site Health andeSafr, Plan (SHASP)? Ifs(. provide revisions-to the SHASP addressing the changes.0 Yes N No TElHI2HNCA l ,S AýTi CONFITTEVE

/( ~2J/2e'O6 DATE O.DATE A-.,l)VISLG HEALrq I HYSICIST DATE I o`,

DISCUSSION IN SUPPORT OF THE CHANGE REQUEST For the radionuclides of concern present at UWNR, Regulatory Guide 1.86 establishes guideline criteria as follows: Emitter Average Static Activity Maximuni Static Activity Removable Type Activity 100 dpnI 00cm 2 300 dprm/l 00cm' 20 Alpha (over not more than I-n 2) (over not more than 100-cm 2) dprn/l00cm 2 Beta 5,000 dpm/100cmi 15,000 dpin/100cm 2 1,000__eta _ , (over not more than I-2) -(over not more than 1-m 2) dpm/100cm 2 Alpha-emission detecting field instrumentation does not exist that is capable of meeting a Minimum Detectable Activity (MDA) of <25% of the average guideline criteria (25 dpm/100cm 2) during scanning evolutions.

The nuclear industry standard is to meet a scan MDA for beta emitters of 25% and less than the upper guideline limit (300 dpm/100cm 2) for alpha emitters.

This change would bring the Decommissioning Plan into accordance with typical industry standards and eliminate a situation where the DP requirements are not capable of being met.Oak Ridge Institute for Science and Education (ORISE), the independent verification contractor employed by the US Nuclear Regulatory Commission (NRC), concurs with this position and has stated in their report from the August in-process inspection:"ORISE recognizes that standard FSS instrumentation is not capable of detecting radioactivity at 25% of the Regulatory Guide 1.86 release criteria when utilized for scanning, nor is there a regulatory requirement that scanning instrumentation should be capable of detecting radioactivity at these levels." The final status survey for alpha affected areas consisted of alpha scans, beta/gamma scans, alpha static and beta/gamma static measurements.

The scan MDA of <25% was met for beta/gamma measurements.

The alpha activity limit for facility license termination is not affected since the release limit is based on the static measurements.

The MDA for the static measurements also met the Decommissioning plan criteria.Therefore the final level of radioactivity remaining in the UWNR facility meets the release criteria of the Decommissioning Plan, Regulatory Guide 1.86 and the regulatory requirement from IOCFR20.0 4 of 4 REVISED FINAL STATUS SURVEY REPORT UNIVERSITY OF WASHINGTON NUCLEAR REACTOR NRC LICENSE NUMBER R-73 UW-MCP-OP-13 Rev. 2 February 22, 2007 Prepared for the University of Washington by: ENERCON Services, Inc.4499 Old William Penn Highway Murrysville, PA 15668 Richard Moss, Executive Engineer Energy Solutions 143 West Street New Milford, CT 06776 University of Washington Project #10492 Final Status Survey Report for the University of Washington More Hall Annex D&D Project UW-MCP-OP-13 Rev. 2 February 22, 2007 Prepared by: Reviewed by: Reviewed by: Reviewed by: Approved by: Todd Brautigam FSS Coordinator Corey E. DeWitt Safety & Compliance Manager Daniel Jordan Radiation Safety Officer Scott LaBuy Project Engineer David Cronshaw Project Manager Executive Engineer Approval University of Washington More Hall Annex D&D, Project 10492 Final Status Survey Report

SUMMARY

OF CHANGES This Final Status Survey Report is issued as a controlled document.

Revisions to this plan will be tracked and revisions or addenda will be issued to controlled copyholders.

Changed sections will be identified by special demarcation in the margin. A summary description of each revision or addenda will be noted in the following table.Revision Number Date Comments Rev. 0 10/18/2006 Original Issue Rev. 1 12/06/2006 Addresses UW comments Rev. 2 02/22/2007 Addresses NRC comments UW-MCP-OP-13 Rev. 2 ii UW-MCP-OP-13 Rev. 2 ii University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 TABLE OF CONTENTS INTRODUCTION

............................................................................................................................

1 1.1 Project Overview .........................................................................................................

1 1.2 Ownership and Licensing

....................................................................................................

1 1.3 Object and Scope .................................................................................................................

1 2 SITE INFORM ATION .........................................................................................................

2 2.1 Facility Location ........................................................................................................

2 2.2 Facility Operating History ..............................................................................................

4 2.3 Facility Radiological History .........................................................................................

4 2.4 Facility Description

.......................................................................................................

4 2.4.1 Reactor Room ..............

.................................

5 2.4.2 Unrestricted Area -First Floor ..........................................................................

7 2.4.3 Unrestricted Area -Second Floor ........................................................................

7 2.4.4 Underground Utilities

..........................................................................................

7 2.4.5 Exterior Building Features -Retention Tanks ...................................................

7 3 DECOM M ISSIONIN G ACTIVITIES

.......................................................................................

8 3.1 Site Area Identification

..................................................................................................

8 3.2 Decontam ination and Decomm issioning Activities

........................................................

8 3.2.1 Facility M odifications

........................................................................................

8 3.2.2 Rem oval of Shield Blocks ...................................................................................

8 3.2.3 Reactor M onolith .................................................................................................

9 3.2.4 Fuel Storage Pit ..................................................................................................

9 3.2.5 Process Pit ......................................................................................................

9 3.2.6 Reactor Room ...................................................................................................

10 UW-MCP-OP-13 Rev. 2 111 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 3.2.7 Overhead Crane ................................................................................................

10 3.2.8 Rem oval of W all and Floor Coatings ..............................................................

10 3.2.9 Peripheral Room s ..............................................................................................

10 3.2.10 Retention Tanks ....................................................................................................

11 3.2.11 Investigation and Rem oval of Underground Drainlines

.................................

11 3.2.12 Confirmatory Soil Sampling ..........................................................................

11 3.3 Decontam ination M ethods ............................................................................................

12 3.3.1 HEPA Vacuum ................................................................................................

12 3.3.2 Chem ical Cleaning ............................................................................................

12 3.3.3 Grinding/Scarifying

..........................................................................................

12 3.3.4 Demolition

.......................................................................................................

12 4 PROJECT RADIATION PROTECTION PROGRAM RESULTS ..........................................

13 5 FINAL STATUS SURVEY OVERVIEW .................................................................................

14 5.1 Decontam ination and FSS Objectives

..........................................................................

14 5.2 M anagem ent Approach ................................................................................................

14 5.3 Instrum entation .................................................................................................................

14 5.3.2 Instrum ent Calibration

.....................................................................................

17 5.3.3 Pre-Operational Checks ..................................................................................

17 5.3.4 M inimum Detectable Activity (M DA) Calculation

..........................................

18 5.3.5 Instrument Efficiency

.......................................................................................

18 5.3.6 Instrument M odels ............................................................................................

19 5.4 Radionuclides of Concern ............................................................................................

20 5.5 Release Guideline Criteria ...........................................................................................

21 5.5.1 Area Classification

...........................................................................................

22 5.5.2 Survey Requirem ents ........................................................................................

23 5.5.3 Reference Grids ................................................................................................

24 UW-MCP-OP-13 Rev. 2 iv University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 5.6 Background Level Determ ination ................................................................................

25 5.7 FSS Survey M ethods ...................................................................................................

26 5.7.1 Static measurement

..........................................................................................

26 5.7.2 Scan .......................................................................................................................

26 5.7.3 Removable Activity W ipe ................................................................................

26 5.7.4 M icroR Exposure Rate .....................................................................................

26 5.7.5 Building and Equipment Surfaces ...................................................................

26 5.7.6 Floor Drains and Embedded Pipe .....................................................................

28 5.7.7 Excavations

.......................................................................................................

28 6 FINAL STATUS SURVEY EVALUATION

..........................................................................

30 6.1 Statistical Analysis .......................................................................................................

30 6.2 Data Preparation

..........................................................................................................

30 7 FINAL STATUS SURVEY RESULTS ...................................................................................

32 7.1 Survey Units ......................................................................................................................

32 7.1.1 Unit 1-1 Counting Room ...................................................................................

32 7.1.2 Unit 1-2 Experiment Room ..............................................................................

32 7.1.3 Unit 1-3 Reactor Room .....................................................................................

33 7.1.4 Unit 1-4 Crystal Spectroscopy Room ..............................................................

39 7.1.5 Unit 1-5 Radiochemistry Lab ............................................................................

39 7.1.6 Unit 1-6 Robotics Laboratory

..........................................................................

39 7.1.7 Unit 1-7 Offices, Restroom s, and Hallway ......................................................

40 7.1.8 Unit 2-1 Control Room .....................................................................................

40 7.1.9 Unit 2-2 Lecture Briefing Room ......................................................................

41 7.1.10 Unit 2-3 Stairs, 2nd Floor Foyer, Fan Room, and Mechanical Room .............

41 7.1.11 Unit 3-1 Building Exterior ..............................................................................

42 7.1.12 Unit 3-2 Retention Tanks and Valve Gallery ................................................

42 UW-MCP-OP-13 Rev. 2 v University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 8 FSS QUALITY ASSURANCE

.................................................................................................

43 8.1 P roject O bjective .......................................................................................

.......................

43 8.2 Q uality O bjectives

.......................................................................................................

43 8.3 Criteria for Measurement Data .....................................................................................

43 8.4 Special Training Requirements/Certification

...............................................................

43 8.5 Documentation and Records .......................................................................................

43 8.6 Instrument Calibration and Frequency

........................................................................

43 8.7 Assessments and Response Actions ............................................................................

44 8.7.1 QA/QC Assessment Checklist

..........................................................................

44 8.8 QA/QC Verification Surveys .......................................................................................

45 8.9 D ata Entry and R eview ................................................................................................

45 8.10 Com pleteness R eview ..................................................................................................

46 8.11 D ata A nalysis ....................................................................................................................

46 9 R E FE R E N C E S ...............................................................................................................................

4 7 10 SITE M A P D RA W IN G S ...............................................................................................................

48 11 ATTACHMENTS

..........................................................................

Error! Bookmark not defined.Attachment 1 -Unit 1-1 Counting Room Attachment 2 -Sub-Unit 1-2-1 Experiment Room Ceiling, East and North Walls Attachment 3 -Sub-Unit 1-2-2 Experiment Room Floor, South and West Walls Attachment 4 -Sub-Unit 1-3-1 Overhead Crane Attachment 5 -Sub-Unit 1-3-2 Fuel and Process Pit Blocks Attachment 6 -Sub-Unit 1-3-3 Fuel Storage Tubes Attachment 7 -Fuel Storage Pit Liquid Scintillation Analytical Results Attachment 8 -Sub-Unit 1-3-7 Reactor Room North Wall 0 To 4-m Attachment 9 -Sub-Unit 1-3-8 Reactor Room North Wall 5 To 9-m Attachment 10 -Sub-Unit 1-3-9 Reactor Room South Wall 0 To 4-m UW-MCP-OP-13 Rev. 2 vi University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 Attachment 1 -Sub-Unit 1-3-10 Reactor Room South Wall 5 To 9-m Attachment 12 Sub-Unit 1-3-11 Reactor Room West Ceiling Grids A-D Including Beams Attachment 13 -Sub-Unit 1-3-12 Reactor Room Center Ceiling Grids E-H Including Beams Attachment 14 -Sub-Unit 1-3-13 Reactor Room East Ceiling Grids I-L Including Beams Attachment 15 -Sub-Unit 1-3-14 Reactor Room West Wall Attachment 16 -Sub-Unit 1-3-15 Reactor Room East Wall 0 To 4-m Attachment 17 -Sub-Unit 1-3-16 Reactor Room East Wall 5 To 9-m Attachment 18 -Sub-Unit 1-3-20 Bioshield North Wall Including Beam Ports Attachment 19 -Sub-Unit 1-3-21 Bioshield South Wall Including Beam Ports Attachment 20 -Sub-Unit 1-3-30 Process Pit Attachment 21 -Sub-Unit 1-3-40 Reactor Room Floor West Grids A-G Attachment 22 -Sub-Unit 1-3-41 Reactor Room Floor East Grids H-N Attachment 23 -Sub-Unit 1-4-1 Crystal Spectroscopy Room Ceiling, East, North, and West #2 Walls Attachment 24 -Sub-Unit 1-4-2, Crystal Spectroscopy Room Floor, West and South Walls Attachment 25 -Sub-Unit 1-4-3 Crystal Spectroscopy Overhead Piping Attachment 26 -Unit 1-5 Radiochemistry Lab Attachment 27 -Sub-Unit 1-6-1 Robotics Lab Floor Attachment 28 -Sub-Unit 1-6-2 Robotics Lab West and South Walls Including Transformer Room South Wall Attachment 29 -Sub-Unit 1-6-3 Robotics Lab East and North Walls Including Transformer Room East, West, and North Walls Attachment 30 -Sub-Unit 1-6-4 Robotics Lab Ceiling Attachment 31 -Unit 1-7 Offices, Restrooms, and Hallway Attachment 32 -Sub-Unit 2-1-1 Control Room Ceiling, East, and North Walls Attachment 33 -Sub-Unit 2-1-2 Control Room Floor, South, and West Walls Attachment 34 -Sub-Unit 2-2-1 Lecture Briefing Room Ceiling, East, and North Walls Attachment 35 -Sub-Unit 2-2-2 Lecture Briefing Room Floor, South, and West Walls UW-MCP-OP-13 Rev. 2 vii University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 Attachment 36 -Unit 2-3 Stairs, 2nd Floor Foyer, Fan Room, and Mechanical Room Attachment 37 -Unit 3-1 Building Exterior Attachment 38 -Unit 3-2 Retention Tanks and Valve Gallery Attachment 39 -Excavation Soil Sample Radiochemistry Analytical Results Attachment 40 -Bioshield Concrete Characterization Analytical Results Attachment 41 -Final Bioshield Analysis for Hard to Detect Radionuclides Attachment 42 -Summary of Air Sample Results Tables Table 3-1 -A ssigned Section N um bers ........................................................................

8 Table 5-1 -Summary of Instrumentation Used for Final Status Survey .............................

15 Table 5-2 -Alpha Scan Probability of Detection

.......................................................

16 Table 5-3 -Potential Isotopes at The UWNR ...........................................................

20 Table 5-4 -UWNR Decommissioning Release Criteria ...............................................

21 Table 5-5 -UWNR Survey Requirements

..............................................................

23 Table 5-6 -Soil Sample Radiochemistry Results ......................................................

28 Table 7-1 -Survey Unit Identification

......................................................................

31 Table 7-2 -Elevated Activity Evaluation.......................................33 UW-MCP-OP-13 Rev. 2 viii UW-MCP-OP-13 Rev. 2 Vill University of Washington More Hall Annex D&D, Project 10492 Final Status Survey Report ABBREVIATIONS AND ACRONYMS AA ACM ALARA CCE CFM CFR CR-5849 D&D DAC DCGL DPM DQOs EE ENERCON FSS GA HEPA LLRW LVI MARSSIM MDA MDC NIST NORM Alpha Affected Asbestos Containing Material As Low As Reasonably Achievable Contamination Control Envelope Cubic Feet per Minute Code of Federal Regulations Draft NUREG/CR-5849

'Manual for Conducting Radiological Surveys in Support of License Termination' Decontaminate and Decommission Derived Air Concentration Derived Concentration Guideline Level Disintegrations Per Minute Data Quality Objectives Executive Engineer ENERCON Services, Inc.Final Status Survey General Affected High Efficiency Particulate Air Low Level Radioactive Waste LVI Environmental Services, Inc.NRC NUREG-1575

'Multi-Agency Radiation Survey and Site Investigation Manual'Minimum Detectable Activity Minimum Detectable Concentration National Institute for Standards and Technology Naturally Occurring Radioactive Material UW-MCP-OP-13 Rev. 2 ix UW-MCP-OP-13 Rev. 2 ix University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 ABBREVIATIONS AND ACRONYMS NRC Nuclear Regulatory Commission NVLAP National Voluntary Laboratory Accreditation Program pCi/g PicoCuries per Gram RCA Radiologically Controlled Area RCT Radiological Control Technician REM Roentgen Equivalent Man RSO Radiation Safety Officer RWP Radiological Work Permit TLD Thermo-Luminescent Dosimeter UN Unaffected UW University of Washington UW-MHA University of Washington More Hall Annex UWNR University of Washington Nuclear Reactor UW-MCP-OP-13 Rev. 2 x UW-MCP-OP-13 Rev. 2 X University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 1 INTRODUCTION

1.1 Project

Overview During the calendar year 2006, the University of Washington Nuclear Reactor (UWNR) underwent full decontamination and decommissioning (D&D) activities to support the termination of United States Nuclear Regulatory Commission (NRC) license R-73. D&D activities were conducted by LVI Services, Inc. (LVI) and its partner ENERCON Services, Inc. (ENERCON) in accordance with the NRC approved UWNR Decommissioning Plan (NES, 1994). The LVI team began project planning in January 2006 with the development of all plans and procedures needed to perform the decommissioning activities.

Following owner review and approval of the plans and procedures, the LVI team mobilized personnel to prepare the site for D&D activities.

Radiological D&D activities began in early April 2006 and were conducted through the summer of 2006. The D&D activities resulted in the generation of 1677 cubic feet of Low Level Radioactive Waste and 32 cubic feet of Mixed Waste which were disposed at U.S. Ecology in Hanford, Washington and Energy Solutions in Clive, Utah, respectively.

Final Status Surveys (FSS) in support of license termination commenced in August 2006 and were completed in the beginning of October 2006. FSS was planned and conducted in accordance with methodologies established in NUREG/CR-5849.

1.2 Ownership

and Licensing The UWNR is wholly owned and operated by the University of Washington under NRC License Number R-73.1.3 Object and Scope The objective and scope of this report is to document the relevant D&D activities conducted at the UWNR and to provide the FSS data results to support the request for NRC license termination.

FSS data is included as Attachments 1-39. Attachments 40 and 41 present characterization sample results for the activated portions of the bioshield.

Attachment 42 summarizes air sample collection results gathered during the course of remediation activities.

UW-MCP-OP-13 Rev. 2 1 UW-MCP-OP-13 Rev. 2 I University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 2 SITE INFORMATION A historical description of the site has been developed based on radiological survey findings and a review of historical documents and drawings.

The historical information presented is not all-inclusive.

However, it provides the best available reconstruction of activities from the data available.

2.1 Facility

Location The UWNR is located within the More Hall Annex (Annex) (Figure 1) on the main campus of the University of Washington (UW) in Seattle, Washington.

The Annex is located west and adjacent to the intersection of Jefferson and Mason Roads (Figure 2). The UW campus is located approximately 10 miles north of the center of the city of Seattle, Washington.

Figure 1 -More Hall Annex UW-MCP-OP-13 Rev. 2 2 UW-MCP-OP-13 Rev. 2 2 University of Washington More Hall Annex D&D, Project 10492 Final Status Survey Report Figure 2 -Site Aerial View UW-MCP-OP-13 Rev. 2 3 UW-MCP-OP-13 Rev. 2 3 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 2.2 Facility Operating History The UWNR was an ARGONAUT type training and research reactor. It began operation in April 1961 with an initial power output of 10 kilowatts.

Following 6 years of intermittent use, the power was increased to 100 kilowatts in 1967. The reactor operated for training and research purposes until June 30, 1988 when critical operations were permanently shut down. During its operational years, the reactor generated a total of 303,443 kilowatt hours.Following its shutdown, all fuel was removed and sent to Idaho National Labs outside of Idaho Falls, ID for disposal.

Radiological characterization activities in support of decommissioning planning began in 1993 by NES, Inc. Following the characterization, NES, Inc. prepared the UWNR Decommissioning Plan which was approved by the NRC in 1994.2.3 Facility Radiological History The only radiological incident of historical note was a failed plutonium oscillator experiment on June 13, 1972 whereby plutonium contamination was dispersed throughout the Reactor Room. Decontamination efforts removed most of the contamination in the weeks following the incident, but characterization activities identified small amounts of alpha contamination in areas of the Reactor Room including the ventilation ductwork and overhead crane. Following the incident, the floor of the Reactor Room was painted and covered with composite tile to prevent transfer of any residual contamination.

The walls of the Reactor Room were also painted and temporary wall partitions erected at some point following the plutonium incident.During its operational years, various radiological experiments were conducted in the reactor and in the adjacent rooms. Various experiments with short-lived isotopes and irradiated materials were prepared, conducted and analyzed in the Radiochemistry, Counting and Experiment Rooms. Other than the plutonium incident, no experiments using longer lived isotopes have been identified that could have deposited residual radioactivity at the site. Historically, waste disposal has occurred offsite at approved disposal facilities for all radiological materials, i.e., no onsite burial of radiological materials has occurred.

Previous characterizations have not indicated the presence of any radiological contamination outside of the Reactor Room other than the retention tanks.2.4 Facility Description The More Hall Annex is divided into two sections, the restricted and the unrestricted areas. The restricted area is located in the western half of the facility and is comprised of the Reactor Room and associated facilities.

The unrestricted area is located in the eastern half of the facility and is comprised of three story structure previously used for classroom, supervisory offices, graduate study rooms, the reactor control room, fan loft and the mechanical equipment room. These building layouts are depicted in Drawings 1-3 which are located in Section 10 -Site Map Drawings.

These areas outside of the Reactor Room have been generally kept free from activities involving radiological materials and have been historically maintained as unrestricted areas. The restricted and unrestricted areas are separated by a 20-cm concrete wall.UW-MCP-OP-13 Rev. 2 4 UW-MCP-OP-13 Rev. 2 4 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 2.4.1 Reactor Room The Reactor Room and associated facilities are contained in an area approximately 14 meters in width by 21 meters in length. The Reactor Room measures approximately 14 meters long by 10 meters wide and is three stories high with an average height of 10.5 meters. Adjacent to the Reactor Room are four separate smaller rooms which include the Radiochemistry Laboratory (4 meters x 4.5 meters) and Crystal Spectroscopy Room (10 meters x 4 meters) to the south and the Counting (4 meters x 4 meters) and Experiment (6 meters x 5 meters) Rooms to the north. Each of these side rooms are approximately 3 meters in height. The floor and walls of the Reactor Room are poured concrete.

The floors are between 15-cm and 45-cm thick and were poured over undisturbed earth. The exterior walls are 25-cm thick to a height of 4 meters above the floor. The upper surfaces of the Reactor Room are supported by a concrete column and beam structure and contain glass windows midway between the floor and ceiling. The north, west and south walls of the Reactor Room are below grade as the Annex is built into the side of a hill.The Reactor Room is isolated from the unrestricted areas of the building by a 20-cm concrete wall. Two doorways along the eastern wall provide access to Reactor Room; a single door from the control office, and a double door from the Robotics Laboratory.

Direct access to Reactor Room is also available through a hatchway from the Mechanical Equipment Room, and two emergency egress hatchways located on the north Wall of the Experiment Room and the south wall of the Crystal Spectroscopy Room.The Reactor Room contains four distinct features:

the reactor monolith, the process pit, the fuel storage pit and the overhead bridge crane.2.4.1.1 Reactor Monolith The reactor monolith is situated in the center of the Reactor Room. The concrete monolith is comprised of two concrete biological shields (bioshields), spaced 1.5 meters apart (Figure 3). Each bioshield is approximately 6 meters in length, 1-3 meters in width, and 3.5 meters in height. The reactor core, graphite moderator and associated components were located in this space between the bioshields.

UW-MCP-OP-13 Rev. 2 5 University of Washington More Hall Annex D&D, Project 10492 Final Status Survey Report Figure 3 -Reactor Monolith 2.4.1.2 Process Pit The process pit is located directly to the south of the reactor bioshield.

It is located below grade and is 2 meters wide, 4 meters long and 1.5 meters deep. Before D&D activities, it contained a sump, sump pump, reactor coolant pump, heat exchanger, waste lines, and a storage tank. Reactor coolant lines and associated lines ran from underneath the reactor to the north side of the process pit. Seven solid concrete covers are placed over the pit. The top of the concrete covers are level with the finished floor of the Reactor Room.2.4.1.3 Fuel Storage Pit The fuel storage pit is located in the southwest comer of the Reactor Room. It contains fifty-four, 10-cm diameter steel lined storage tubes. Each tube is approximately

1.5 meters

deep and was lined with plastic sleeves. Each tube contained an iron encased concrete shield plug that locked into place following placement of the fuel rods for storage. Three solid concrete covers are placed over the pit. The top of the concrete covers are level with the finished floor of the Reactor Room.2.4.1.4 Reactor Room Ventilation Systems Ventilation systems in the Reactor Room and Crystal Spectroscopy Room provided air circulation and reactor exhaust. The ductwork in the Reactor Room was typical box and frame construction located 3 UW-MCP-OP-13 Rev. 2 6 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 meters above floor level and below the windows. This ductwork transported recirculated air from filters in the Crystal Cpectroscopy Room. The reactor's 250 CFM blower transported exhaust air to a 10,000 CFM dilution fan in the Fan Loft located above the Control Room via a 12 cm diameter line along the walls of the Reactor Room. Radiological characterization activities identified the reactor ventilation ductwork as potentially contaminated due to the plutonium incident.2.4.1.5 Overhead Bridge Crane The Reactor Room is serviced by a 3-ton capacity bridge crane. The crane has historically been used to move shield blocks into various positions about the reactor monolith and heavier objects around the reactor room. The crane spans the Reactor Room and is constructed of one large I-beam approximately 10 meters in length.2.4.2 Unrestricted Area -First Floor The unrestricted area of the first floor is located east of the Reactor Room. This area is comprised of the Robotics Lab, Directors Office, Control Office, Calculating Room, Graduate Room and restrooms.

2.4.3 Unrestricted

Area -Second Floor The second floor area is an unrestricted area located adjacent to the upper surfaces of the Reactor Room.It is comprised of the Lecture Briefing Room and the Control Room. Located above these rooms are the Mechanical Equipment Room and the Fan Loft. These areas housed the air handling systems for various building systems.2.4.4 Underground Utilities Various underground lines are located throughout the UWNR. An investigation into the design and operating history of the facility identified various lines which transported waste liquid, potable water, steam, and electrical services.

There were two drainlines identified beneath the floor of the Reactor Room that had potential for radiological contamination.

These lines ran from the sink and emergency shower in the southeast corner of the Experiment Room and process pit to the Radiochemistry Lab where it tied together and drained outside the building to the retention tanks. These lines connected to a drain on the northeast corner of the bioshield and two sink drains located in the Radiochemistry Lab. Drawing 4 depicts the location of these drain lines. Drawing 4 is located in Section 10 -Site Map Drawings.2.4.5 Exterior Building Features -Retention Tanks Two retention tanks and a valve gallery are located outside the Annex, directly south of the Radiochemistry Lab. The retention tanks were used to store overflow water from the process pit and drain lines located in the restricted areas of the building.

Each retention tank is approximately 2 meters wide by 2 meters long by 2 meters deep and are constructed of sealed concrete approximately 10-cm thick. The valve gallery is located between the tanks and housed the pumps, level controls and water lines which distributed the liquids between each tank. Incoming liquids were received into the valve gallery through a 2-in cast-iron line which exited the Annex from underneath the south wall of the Radiochemistry Laboratory.

Drawing 1 depicts the location of the retention tanks. Drawing 1 is located in Section 10 -Site Map Drawings.UW-MCP-OP-13 Rev. 2 7 University of Washington More Hall Annex D&D, Project 10492 Final Status Survey Report 3 DECOMMISSIONING ACTIVITIES 3.1 Site Area Identification Drawings 1, 2 and 3 (Section 10) depict all site areas involved in the decommissioning process. Drawing 1 depicts first floor survey areas, and Drawing 2 depicts second floor survey areas. Drawing 3 depicts the Fan Loft and Mechanical Equipment Room. Building areas involved in the decommissioning process are identified on the drawings by section and survey unit, for example, a plant area identified as 3-1 would refer to Section 3, Unit 1. Sub-unit numbers are assigned as necessary to meet final status survey size requirements for affected areas so that 3-1-1 would refer to Section 3, Unit 1, Sub-Unit 1.Section numbers were assigned to various areas based on distinguishing features such as floor level and survey classification; survey unit and sub-unit designations are associated with the final status survey phase of the decommissioning process.Section numbers were assigned as follows: Table 3-1: Assigned Section Numbers Survey Section Location/Description Distinguishing Features 1 First Floor Reactor Room and other restricted areas 2 Second Floor Control and Lecture Briefing Rooms 3 Building Exterior Retention Tanks 3.2 Decontamination and Decommissioning Activities Upon mobilization, various activities were conducted to prepare the site for D&D activities.

Miscellaneous equipment and materials were surveyed, released and disposed to facilitate D&D activities.

3.2.1 Facility

Modifications Upon mobilization, some facility modifications were necessary to provide increased access to the Reactor Room. These modifications included removal of the walls separating the Crystal Spectroscopy Room and Experiment Room from the Reactor Room. The drywall corridor between the Control Office doorway and Experiment Room was also removed, surveyed and free released.

No other walls were removed from the restricted areas. Emergency egress hatchways were modified to accommodate HEPA ventilation units and make up air supply.3.2.2 Removal of Shield Blocks Concrete shield blocks were used during reactor operation to provide increased shielding around the reactor bioshield.

These shield blocks were surveyed, decontaminated as necessary and released.

Any UW-MCP-OP-13 Rev. 2 8 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 shield block material that could not be released was packaged and disposed as radiological waste. One remediated shield block was surveyed to FSS standards and left within the Reactor Room.3.2.3 Reactor Monolith The reactor monolith consisted of two reinforced concrete bioshields on the north and south. The reactor core box, lead and graphite shielding and associated reactor systems were contained in the center of the monolith between a shield tank to the east and concrete shield blocks to the west. The shield blocks and shield tank were removed and surveyed.

Any portions of the shield tank or shield blocks that could not be released were packaged and disposed as radiological waste. A contamination control envelope (CCE)was installed over the top and west side of the monolith with HEPA ventilation installed on the east side of the monolith.The graphite moderator and lead shielding blocks were removed, packaged and disposed as radiological and mixed waste. After access to the core box was available, surveys were conducted to assess the radiological conditions of the core. The core box was removed, packaged and disposed as radiological waste.After the core box and the remainder of the lead and graphite were removed, demolition commenced on the activated concrete contained within the monolith using a Brokk remote demolition tool and hand tools. As the demolition progressed, periodic surveys were conducted to identify surfaces requiring additional demolition to meet the acceptance criteria.

Concurrent with the demolition activities, the six steel beam tubes were cut and removed from the monolith as well as any remaining peripheral equipment.

3.2.4 Fuel Storage Pit The fuel storage pit is located in the southwest comer of the Reactor Room and consists of fifty-four steel-lined tubes which are embedded in concrete.

Each tube contained removable shield plugs and plastic liners. The shield plugs and liners were removed, surveyed and released or disposed as radiological waste as necessary.

Each tube was surveyed according to the survey protocol established in the Decommissioning Plan. Each tube was surveyed via 100% scan for beta-gamma and alpha activity.Additionally, five static readings, two gross alpha and beta-gamma wipes and one liquid scintillation wipe, which was counted for low energy beta activity (H 3), were taken in each tube. Decontamination activities involved removing the paint from the top of the fuel storage pits. Tube A2-9 was identified as having alpha activity greater than the guideline limit and was remediated.

A map showing the location of this tube is available in Attachment 6.3.2.5 Process Pit The process pit contained a sump, sump pump, reactor coolant pump, heat exchanger, holding tank and waste lines. The equipment was removed from the pit and disposed as either clean waste or radiological waste based on total contamination surveys. The pit walls, floor, and sump were wiped down and surveyed.

Areas with elevated activity were remediated in preparation for final status surveys.UW-MCP-OP-13 Rev. 2 9 UW-MCP-OP-13 Rev. 2 9 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 3.2.6 Reactor Room The Reactor Room housed the reactor monolith, process pit, fuel storage pit, overhead bridge crane, and Reactor Room ventilation systems. There was ventilation ductwork which encompassed the entire room, and was mounted to the walls just under the windows. All supply and return ductwork in the Reactor Room were entirely removed, including the 12 cm diameter line transporting reactor exhaust air to the dilution fan, and disposed based on the survey results.3.2.7 Overhead Crane D&D activities identified low levels of alpha contamination on the overhead bridge crane. These areas were remediated using abrasive measures and wiped down. Portions of the overhead crane including the catwalk, motor, and pulley system could not be surveyed due to inaccessibility and were consequently removed and disposed as Low Level Radioactive Waste (LLRW).3.2.8 Removal of Wall and Floor Coatings During D&D activities, various wall and floor coatings were identified that either were or could have been applied after the reactor began operation.

While the potential for contamination of these areas from reactor operations was low, any coatings in the Reactor Room that were applied after the plutonium incident were removed. Residual floor paint, applied to fix contamination from the plutonium incident, was removed by grinding.

A layer of lead based paint, applied to the top surface of each bioshields after the plutonium incident, was removed and disposed as mixed waste. During building construction, a layer of asbestos skimcoat was applied to the lower walls of the Reactor Room and the four adjacent rooms.Through discussions with operation staff, it was determined that a layer of paint was applied over the top of the skimcoat after the plutonium incident, which required the paint on all of the walls of the Reactor Room and side rooms to be removed. Containments were constructed and all outer wall paint was removed with grinders from the Reactor Room floor to the ceiling. This material was disposed as Asbestos Containing Materials (ACM) contaminated LLRW. In effect, all wall coatings in the Reactor Room and adjacent rooms were removed, including original surfaces applied before operations began.3.2.9 Peripheral Rooms There are four peripheral rooms within the Radiologically Controlled Area (RCA) adjacent to the reactor room. These are the:* Counting Room* Experiment Room* Radiochemistry Laboratory

• Crystal Spectroscopy Room These rooms contained support equipment and systems such as the secondary cooling system, fume hoods and sinks, and drain lines. All of the fixed and loose equipment in these rooms was removed with the exception of piping in the overhead of the Crystal Spectroscopy Room. The materials were surveyed and disposed according to the survey results. The overhead piping was left in place because it consisted of hot and cold water supply and did not transport process water. A diagram and photograph depicted the overhead piping configuration are included in Attachment

25. Additional decontamination was performed in the Crystal Spectroscopy Room on the floor. Other discreet areas identified as having elevated activity were remediated and surveyed.UW-MCP-OP-13 Rev. 2 10 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 3.2.10 Retention Tanks The retention tanks are located outside the south end of the More Hall Annex. Scoping surveys identified low levels of discrete elevated activity within the tanks. Hand wiping successfully removed the elevated activity and the tanks were cleaned in preparation for FSS.The center section between the tanks is the valve gallery which contained piping, a pump and valves to control the tank levels. Much of the piping and valves were removed to facilitate FSS. Equipment and materials were surveyed and disposed based on the survey results.3.2.11 Investigation and Removal of Underground Drainlines The presence of detectable radiological activity in the retention tanks required an investigation of the upstream drain lines which fed into the retention tanks. Drawing 4 presents the layout of the underground drain line system. The drain line which entered the retention tanks system was excavated and removed to its junction with the south wall of the More Hall Annex. A lxi Nal probe was attached to a pipe snake and used to survey the interior of the upstream sections of drainline in the radiochemistry lab. This survey indicated the presence of elevated gamma activity at a few spots inside the pipe beneath the radiochemistry lab. Consequently, the drain lines in the radiochemistry lab were excavated and disposed as LLRW. Both sink drains were also removed. Two sections of drain line ran into the radiochemistry lab: one from the process pit and the other from the sink and emergency shower in the southeast corner of the Experiment Room. The entire section of drainline between the process pit and the Radiochemistry Lab could not be adequately surveyed due to bends and obstructions, therefore, it was excavated and removed.Inaccessible portions of drainline between the Experiment Room and Radiochemistry Lab were also removed. The drain located on the northeast corner of the reactor monolith was also removed. A twenty-eight foot straight section of drainline on the eastern side of the Reactor Room was left in place because it had no visual breakages and no drain line tie-ins. No detectable activity was found inside this section of pipe.3.2.12 Confirmatory Soil Sampling Following drain line removal, soil samples were collected beneath the excavated pipes at elbows and couplings and analyzed for gamma emitting radionuclides to determine if any leaks had occurred which could have contaminated the underlying soils. Drawing 5 presents the layout of the underground drain line system and the locations where soil samples were collected.

Samples results indicate that no detectable radionuclides other than Naturally Occurring Radiological Materials (NORM) were present in soils located beneath the drainlines within the building footprint.

Two samples, SS-1 and SS-11, were collected from soils outside the building and indicated low levels of Cs-137 which are consistent with background concentrations identified in the Radiological Characterization Report. Attachment 39 presents the results of the soils sample analysis.

From this data, it has been concluded that soils beneath the UWNR drain lines were not radiologically impacted from reactor operations.

UW-MCP-OP-13 Rev. 2 11*UW-MCP-OP-13 Rev. 2 I1I University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 3.3 Decontamination Methods A variety of safe and effective decontamination methods were used to meet unrestricted use criteria.

The decontamination techniques employed are widely used in the decommissioning industry and do not pose unusual, or significant, health and safety concerns.3.3.1 HEPA Vacuum High Efficiency Particulate Air (HEPA) vacuuming was used to collect dirt and larger particle debris that were contaminated with radioactive material.

Although not generally effective as an initial decontamination technique, HEPA vacuuming is extremely effective in conjunction with any of the more aggressive methods of decontamination.

3.3.2 Chemical

Cleaning Commercially available chemical agents were used when non-destructive decontamination was desired.These agents work by loosening or dissolving the host material and/or the contaminant.

Chemical agents were used when it was reasonably assured the radioactive waste could be significantly reduced by removal of the residual contamination.

3.3.3 Grinding/Scarifying Grinding and scarifying incorporates a high-speed wheel made of stone or steel that aggressively abrades the surface to remove residual radioactive material.

This method was used successfully on floors and walls where the aesthetics of the remaining surface was not a concern. A close-capture HEPA vacuum or enclosure was used with this method to capture airborne particulates for dust and airborne radioactive material exposure control. Water was also used to limit dust and maintain contamination control.3.3.4 Demolition Demolition is often the most cost-effective solution when radioactive disposal rates are reasonable.

Demolition of certain building components was used in areas where decontamination was not effective, proved to be cost prohibitive, or involved remediation of volumetrically contaminated media (e.g. the inner portions of the bioshields).

Demolition was also required in certain areas to allow access to original building surfaces for survey purposes.

Demolition was limited to non-load bearing building components.

IJW-MCP-OP-13 Rev. 2 12 UW-MCP-OP-13 Rev. 2 12 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 4 PROJECT RADIATION PROTECTION PROGRAM RESULTS 4.1 Radiation Exposure Monitoring Over the course of this project, D&D personnel with the potential for radiological exposure were monitored using external and internal means. All work evolutions with the potential to generate airborne radioactivity were monitored with air sampling equipment.

Air samples collected over the course of the project were analyzed and the results demonstrated that average airborne activity was kept to less than 2%of the federal regulatory limit. A summary of air sampling data from project work evolutions is available in Attachment 42 -Summary of Air Sample Results. All site radiation workers were monitored with external dosimetry.

The Decommissioning Plan estimated the minimum and maximum collective dose to be 4.93 and 6.02 person Roentgen Equivalent Man (REM) respectively.

The total collective dose for the project was 1.491 person REM or 30% of the minimum estimate.

The highest individual dose for the duration of the project was 0.323 REM. The monitoring was performed from April 1, 2006 through September 12, 2006. In addition, project personnel with potential for internal exposures were monitored through in vivo (bioassay) and/or in vitro (Whole Body Counting) means.UW-MCP-OP-13 Rev. 2 13 UW-MCP-OP-13 Rev. 2 13 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 5 FINAL STATUS SURVEY OVERVIEW 5.1 Decontamination and FSS Objectives The purpose of the FSS activities is to demonstrate that the radiological conditions at the UWNR satisfy the USNRC guidelines and the UWNR can, therefore, be released from USNRC license Number R-73 for future use without radiological controls.

For the purpose of this demonstration, each survey unit is independently evaluated.

The objective of the survey is to demonstrate at a 95% minimum level of confidence that the license release conditions have been met.5.2 Management Approach The present day management at the UWNR has fully supported efforts by the contractor to remediate known areas of residual contamination.

Radiological Control Staff at the UWNR maintained overall responsibility and authority for the remediation activities.

Qualified LVI remediation workers and ENERCON radiological control technician (RCTs) worked under the direction of the LVI/ENERCON management staff. Cooperative discussions between the associated parties resulted in a cost efficient approach to decommissioning while adhering to all applicable health, safety and radiation protection guidelines.

Guidance documentation issued by the NRC was utilized as a basis for development of the final survey methodology and associated documentation.

All survey methods and QA/QC activities have been and continue to be subject to review by the University staff that maintains final approval, authority and responsibility for work conducted under this license.5.3 Instrumentation Instruments were selected that provided an adequate response to radionuclides of concern presented in Section 5.4. Minimum detectable activity (MDA) was calculated for each model. The MDA was calculated using formulae contained within the Multi Agency Radiation Survey and Site Investigation Manual (MARSSIM) and shown in Section 4.5.3. The MARSSIM contains the most current guidance on recommended methods of calculating survey instrument MDA. The background rate and detector efficiency used in the MDA are averages calculated from the daily operational check of each instrument.

Table 4-1 shows the instrument models selected and summarizes the typical observed background counts in counts per minute (cpm), typical observed detector efficiency, and a typical observed MDA in disintegration per minute (dpm/100 cm 2) for each instrument model. Other objectives in selecting instruments included special features such as digital displays to provide a more accurate reading than conventional analog displays.UW-MCP-OP-13 Rev. 2 14 University of Washington More Hall Annex D&D, Project 10492 Final Status Survey Report Table 5-1: Summary of Instrumentation Used For Final Status Survey Ratemeter Instrument Background Probe Efficiency Static MIDA MDA Scan MIDA Model Rate Area (cm 2) (%) o (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm 2)Ludlum Model 2221 w/43-44 Air Proportional detector 0.1 CPM 50 1.3 50(2) 110 150(3)Ludlum Model 2221 w/44-9 Geiger Mueller Detector 150 CPM 17.5 13.0 1850 8150 11500 Ludlum Model 3 or 12 w/44-9 Geiger Mueller Detector (Beta Frisker) 40 CPM 17.5 13.5 N/A 4000 5700 Ludlum Model 2 360 w/43-68 Gas Proportional Detector (Alpha) 2 CPM 126 10.5 40(2) 110 160(3)Ludlum Model 2360 w/43-68 Gas Proportional Detector (Beta) 123 CPM 126 26.4 120(2) 520 740(4)Ludlum Model 19 MicroR 9 microR/hr N/A N/A N/A N/A N/A Ludlum Model 2929 Wipe Counter (Alpha) 0.1 CPM 100 25.6 16 N/A N/A Ludlum Model 2929 Wipe Counter (Beta) 46 CPM 100 22.6 153 N/A N/A (1) Detector area-corrected to 100-cm 2 using the formula in section 6.2.(2) Based on a 2-minute count (3) Based on 1/3 probe width per second scan rate (4) Based on one probe width per second scan rate 5.3.1.1 Alpha and Beta Scans Surface scans were performed at a rate of 1 probe-width per second in the General Affected areas. Surface scans were performed over 100% of the surface area in the General Affected and Alpha Affected areas.Alpha and Beta scan surveys were performed at a probe to surface distance as close as practical, not to exceed 1-cm (-1/2/2 inch).In the Alpha Affected areas, scanning differed from that of beta and gamma emitters in that the typical background count rate was usually very close to zero. Therefore the scan MDA for alpha activity is typically presented as a probability that a given contamination level is detectable at a given scan rate.UW-MCP-OP-13 Rev. 2 15 University of Washington More Hall Annex D&D, Project 10492 Final Status Survey Report Table 5-2 provides a summary of the alpha detection probability using formula 6-12 presented in Section 6.7.2.2 of the MARSSIM. The formula is:-GEd P(n >_ 1)= 1-e 60v Detection Probability (6-12)Where P(n>1) = the probability of detecting a single count G = Contamination activity (DPM)E = Detector efficiency d = Width of detector in the direction of the scan v = Scan speed (cm/s)Table 5-2 Alpha Scan Probability of Detection Probability of Detecting Total Probe Dimension in 300 DPMI100cm 2 Detector Type Efficiency Direction of Scan Scan Rate (Table 4-1)Alpha Gas Proportional 10.5% 9-cm (1/3 3-cm/s 79%___________________

__________

_____________

(1/3_ probe/sec)_____________

Alpha Gas Proportional 10.5% 9-cm ( 4.5-cm/s 65%__________________

________ _________________

(1/2 probe/sec)

____________

The formula above is more conservative than that presented in the MARSSIM which uses a 4-pi detector efficiency that is not adjusted for surface efficiency.

Using the more conservative total efficiency, discussed in Section 5.3.5, the probability of detection is exceeds 67% which is listed in Draft ANSI Standard N13.12 (1978) when scanning for alpha emitters.

The data evaluation supports the premise that this detection probability is unrealistically low as evidenced by the numerous detections of alpha activity less than 300 dpm/1OOcm 2 demonstrated during the FSS evolution.

The higher desired probability (90%) stated in the MARSSIM is also a result of the non-parametric basis of that survey approach, which results in far fewer static survey locations when compared to a NUREG/CR-5849 license termination method.Using the 4-pi efficiency, as recommended in the MARSSIM, the results indicate a scan speed of 1/3 probe width per second is sufficient to achieve the MARSSIM recommended 90% probability of detection.

A single count detected during a scan is cause for the surveyor to pause until the probability of achieving another count has reached 90%. This time interval may be calculated using formula 6-13 from the MARSSIM as presented below.Time Interval Probability (6-13)13800 tC-CAE Where UW-MCP-OP-13 Rev. 2 16 UW-MCP-OP-13 Rev. 2 16 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 C = Maximum guideline criteria (300 dpm/I00-cm 2)A = Detector Area (124-cm 2)E = Detector Efficiency (10.5%)Using this formula, a pause of 3 seconds was sufficient to achieve a 90% probability of detection.

If no additional count was detected during the 3 second pause, then no elevated activity was found and the scan survey continued.

5.3.2 Instrument

Calibration ENERCON (or another qualified vendor) calibrated all field instrumentation using approved procedures.

At a minimum, the survey instruments were calibrated semi-annually.

Instrument calibrations were performed with a source to detector distance no greater than 1-cm. A source holding 'jig' is commonly used during the calibration process to ensure a consistent geometry.

ENERCON maintaineds original instrument calibration data and certificates for the calibration sources at the calibration lab and provided copies to file on-site. Instrument calibrations followed NUREG-1507 and ISO 7503-1 guidance.At a minimum, response checks were performed prior to use each day and upon completion of an FSS survey during the day. Response checks were performed on a flat desktop maintaining the source to detector distance as close to contact as possible.

The radiological check sources that were used for each of the instruments are as follows:* Alpha instruments:

Th 2 3 0 47-mm electroplated disk* Beta instruments:

Tc 9 9 47-mm electroplated disk* Gamma instruments:

Cs137 encapsulated button ISO-7503 recommends a surface efficiency correction for Tc 9 9 of 0.25, however a surface efficiency correction factor of 0.5 has been utilized in all calculations because the Tc 9 9 is not a radionuclide of interest, but is merely the best available calibration standard for the instrumentation used. In all cases, the check sources listed above provides a conservative response in comparison to the potential isotopes present at the facility due to relative isotope energies and would tend to overestimate the actual activity present.5.3.3 Pre-Operational Checks All background readings for counting instruments were conducted daily during instrument use. Any instrument that used a battery had a daily battery check performed before instrument operation.

If a battery check failed, an equivalent size battery was installed and the instrument was rechecked before operation.

An appropriate initial source response, as determined by a comparison to calibration information, to the appropriate on-site check source was obtained prior to the instrument being placed in service for the project.Each day an instrument was used, the instrument received an operational check that consisted of a background reading (observed CPM for ratemeters or 10-minute static count for scalers) and a count of a known check source (observed CPM for ratemeters; i-minute static count for scalers) with the detector in contact with the source in its' holder to provide a consistent source to detector distance.

If at any UW-MCP-OP-13 Rev. 2 17 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 time an instrument exceeded its calibration due date or fell outside of the +/-10 percent of the established initial source check, the instrument was recalibrated, and a new initial source check was performed.

An inappropriate response resulted in the instrument being taken out of service and sent for calibration and/or maintenance.

This information was recorded on a Daily Instrument Pre-Operational Check form.Additionally, at the conclusion of each FSS survey, the survey instrument received a response check.This response check entailed exposing the detector to an appropriate check source and verifying an acceptable count rate was obtained (i.e. within +10% of the initial source count). The result of this response check was documented on a survey instrument response check log.5.3.4 Minimum Detectable Activity (MDA) Calculation Background readings and calibration efficiencies were used to evaluate the MDA for each instrument model. The formulae and/or functions used in the spreadsheet are detailed in the following sections.3 +4.65 BrT6 Static Count MDA MDA = 60 T, *.E,* A 60 100 MDCR Scan MDA ScanMDA =100cm 2 MDCR MDCR = s 60 Where: C = Conversion factor from counts to concentration Br = Background rate in CPM T, = Sample count time in seconds A = Effective probe size in cm2 p = Surveyor efficiency Ei Instrument efficiency E, Surface efficiency si= Minimum detectable net source counts per interval i= Observed time interval 5.3.5 Instrument Efficiency The efficiency of the detection capabilities for each applicable instrument was calculated using the following formula: Instrument Efficiency (E 1) Ei -S UW-MCP-OP-13 Rev. 2 18 UW-MCP-OP-13 Rev. 2 18 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 Where: C, = Measured source count in CPM Cb = Measured background count in CPM S = 2 pi source value in DPM Total Efficiency (E,) E, = El

• Es Where: Ei = Instrument efficiency E, = Surface efficiency (Alpha emitters = 0.25, Beta emitters = 0.5)The total instrument efficiency (Et) is a product of the instrument detection efficiency (E 1) and the source detection efficiency (E,) and is used to convert the raw instrument counts into the standardized unit of disintegrations per minute (DPM). The source efficiency utilized for the UWNR follows the recommendations in ISO-7503-1 which makes recommendations for default source efficiencies.

A source 60 efficiency of 0.5 is recommended for beta emitters with maximum energies above 0.4 MeV, such as Co Eu152 and Eu 1 5 4.Alpha emitters and beta emitters with maximum beta energies between 0.15 and 0.4 MeV have a recommended source efficiency of 0.25, such as Pu239 .As such, beta measurements use an E, of 0.5 and alpha measurements use an E, of 0.25.5.3.6 Instrument Models The instrument models used are listed below and are typical of each instrument class.5.3.6.1 Ludlum Model 2221 with 43-44 Air Proportional Detector This is a scaler/ratemeter instrument with a 50-cm2 air proportional detector.

This instrument was used for interior alpha surveys (scans and static locations) of pipes or other areas where the larger detectors can not be used.5.3.6.2 Ludlum Model 2221 with 44-9 GM Tube Detector This is a scaler/ratemeter instrument with a 17.5-cm 2 Geiger-Mueller (GM) tube detector that was used for interior beta-gamma surveys (scans and static locations) of pipes or other areas where the larger detectors can not be used. The MDA calculations are based upon beta background and efficiency data.5.3.6.3 Ludlum Model 2221/2241/2360 with 43-68 Gas Proportional Detector These are scaler/ratemeter instruments with a 126-cm 2 gas proportional detector that were used for all types of surveys. The Model 2221 may be dual-calibrated for alpha and beta detection while Models 2241 and 2360 are capable of discriminating between alpha and beta activity.

For FSS surveys, specific meter/detector combinations were dedicated for either alpha and/or beta applications.

UW-MCP-OP-13 Rev. 2 19 UW-MCP-OP-13 Rev. 2 19 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 5.3.6.4 Ludlum Model 2929 with 43-10-1 Scintillation Detector This is a scaler instrument used for counting wipe samples. This instrument was used for all analysis of removable activity wipes. A 47-mm diameter cloth wipe is used to wipe over an area of 100-cm2 to collect a sample of removable activity.

A wiping efficiency of 90% is used compensate for the inability of the wiping cloth to collect all the material that may be present on the surface. This instrument is capable of discriminating between alpha and beta activity.5.3.6.5 Ludlum Model 19 MicroR This is a ratemeter instrument that was used for exposure rate surveys. It is generally accepted throughout the nuclear industry that the MDA of this instrument is equivalent to the background readings.5.4 Radionuclides of Concern Radionuclides of concern at the UWNR are those that have been previously reported or are anticipated based upon knowledge of historical site operations.

Based upon historical site assessment, potential radiological contaminants could be present from neutron activation due to reactor operations and/or radiological spills. In the 1993 Characterization Report, activation products were identified as potential radiological contaminants in the biological shield and reactor core components.

The types and inventories of these radionuclides were based upon activation analysis and similar findings during the decommissioning of the UCLA Boelter Research Reactor. These radionuclides are listed in Table 5-3.The Radiological Characterization Report for the UWNR also identified Pu-239/240 and Pu-241 resulting from the June 1972 failure of a plutonium foil experiment in the Reactor Room. Although the majority of the contamination was decontaminated immediately following the event, small amounts of alpha activity were identified in the characterization of the facility.

This report also identified Cs-137 as potential radiological contaminant in the Radiochemistry Lab sink drain and retention tanks.Before the current reactor demolition activities began, concrete samples were collected from activated regions of the biological shield and analyzed for gamma emitting radionuclides, H-3 and C-14. As expected, these analyses identified Co-60, Eu-152, Eu-154, H-3 and C-14. Analytical results for these samples are available in Attachment 40 -Bioshield Concrete Characterization Analytical Results. During the initial D&D activities, wet smears were collected on shield blocks and various surfaces of the Reactor Room to determine if C-14 of H-3 had migrated outside .the reactor core to other areas of the Reactor Room. These wet smears were analyzed on a QuantaSmart 1.31 liquid scintillation counter and no detectable activity was observed.The radiological surface release criteria for the UWNR are established in Table I of U.S. NRC Reg.Guide 1.86, "Termination of Operating Licenses for Nuclear Reactors" (U.S. NRC, 1974). Specifically, beta-gamma emitting radionuclides must not exceed 5000 disintegrations per minute (dpm)/100 cm 2 average fixed plus removable activity.

Removable activity must not exceed 1000 dpm/100 cm 2.The guidance also established alpha release criteria of 100 dpm/100 cm 2 average fixed plus removable and 20 dpm/100 cm 2 removable.

Some beta emitting radionuclides have a more restrictive release limit of 1000 dpm/100 cm 2 , but none of these radionuclides are present in the UWNR. The only radionuclide from this list which would be resultant from fission would be Sr-90. There is no indication that any fuel ever leaked at the UWNR, therefore, Sr-90 was not identified as a radionuclide of concern at the UWNR.For areas of facility which possess residual tritium activity in addition to fission products, i.e., inner surfaces of the bioshield, a modified survey protocol was necessary to adequately account for all residual radioactivity.

In this case, the beta-gamma survey results were used as a surrogate nuclide for tritium. A UW-MCP-OP-13 Rev. 2 20 University of Washington More Hall Annex D&D, Project 10492 Final Status Survey Report composite sample of concrete from areas within the remediated portions of the bioshield was collected at the completion of FSS activities and analyzed for gamma emitters, tritium and C-14. Analysis of this sample indicated a 1.86:1 ratio of tritium to Co-60 and Eu-152. No C-14 was detected in the analysis.Data from this analysis is presented in Attachment 41 -"Final Bioshield Analysis for Hard to Detect Radionuclides".

Using the ratio above, the beta-gamma DCGL for the bioshield data analysis was reduced to 1700 dpm/100cm 2 to account for the presence of tritium. This surrogate assures tritium activity to be less than an limit of 5000 dpm/100cm 2 established for beta emitters in the Decommissioning Plan. Additional discussion of the affect of tritium on the final data analysis is included in Section 7.1.3.16.Table 5-3 Potential Isotopes at the UWNR Component Isotope Mean Life Principle Decay Modes Metallic Parts Mn 5 4 450 days EC, y Fe 5 5 3.9 years EC Co 6 0 7.6 years [V, Y Zn 6 5 352 days EC, y Graphite Co 6 0 7.6 years [3, y Eu 1 5 2 19.3 years E3, , BC, y Eu 1 5 4 12.3 years [3-, y H 3 17.8 years [3 C 1 4 8268 years Lead Ag 1 0 8 190 years EC, y Ag 1 0 360 days [V, Y Magnetite Concrete Mn54 450 days EC, y Co 6 0 7.6 years Y- y CS 1 3 4 3.0 years [3-, y Eu 1 5 2 19.3 years E3, [3+, EC, y Eu 1 5 4 12.3 years [- 'H 3 17.8 years C 1 4 8268 years [3 5.5 Release Guideline Criteria Release guideline criteria for materials and building surfaces are based on NRC Regulatory Guide 1.86,"Termination of Operating Licenses for Nuclear Reactors".

NRC has stated that beta-gamma and alpha surveys should be conducted in the Reactor Room to account for Pu-241 beta decay and the alpha decay of Pu-239 and Am-241. Based upon this requirement and the list of potential radionuclides, the Reg.Guide 1.86 limits of 100 dpm/100 cm 2 alpha and 5,000 dpm/100 cm 2 beta-gamma activities are deemed suitable for the UWNR. The beta limit of 1,000 dpm/1OOcm2 is not appropriate for this facility because, as established above, Sr-90 should not be present at the UWNR. For areas of the facility that contain tritium, i.e., the inner bioshield surfaces, a modified release limit of 1700 dpm/1OOcm 2 average beta-gamma will be used. Table 5-2, "Potential Isotopes at the UWNR", provides the isotope list contained in the University of Washington Nuclear Reactor Decommissioning Plan. The remaining isotope of concern UW-MCP-OP-13 Rev. 2 21 University of Washington More Hall Annex D&D, Project 10492 Final Status Survey Report is Plutonium-241 as stated in the NRC position letter in Attachment B of the radiological Characterization Report. The release criteria are summarized in Table 5-4, "UWNR Decommissioning Release Criteria".

Table 5-4 UWNR Decommissioning Release Criteria Emitter Average Static Maximum Static Removable_TypeII Alpha 100 dpm IOOcm 2 300 dpm/100cm 2 20 (over not more than 1-m 2) (over not more than 100-cm) dpm/100cm 2 Beta 5000 dpm/100cm 2 15,000 dpm!l OOcm 2 1000 (over not more than 1-m 2) (over not more than 1-m 2) dpm/I10cm 2 Gamma Net result _< 5 microRem/hr at (Interior) 1-m (average over I 00-M 2) 5 microRem/hr at 1-m N/A Static measurements that indicate an area of activity above the decommissioning release criteria, but less than the maximum decommissioning release criteria were evaluated for average activity over the area (not to exceed 1-M 2) in which the elevated measurement is present. This was accomplished by performing surveys of at least three additional static measurements within the one square meter area and calculating a weighted average activity as described in NUREG/CR-5849.

If the weighted average activity over 1-m2 is less than the guideline limit, the area meets unrestricted release criteria.

If the 1-m 2 weighted average was greater than the guideline limit, further decontamination was necessary.

This report verifies that unrestricted release criteria have been met for the facility.

Building surfaces have been evaluated against the following unrestricted release criteria:* Fixed alpha activity does not exceed an average of 100 dpm/100 cm 2 above background when averaged over 1-M 2.* Fixed beta/gamma activity does not exceed an average of 5,000 dpm/100 cm 2 above background when averaged over 1 m2.* Removable alpha activity does not exceed 20 dpm/100 cm 2 above background at any location.* Removable beta/gamma activity does not exceed 1,000 dpml100 cm 2 above background at any location.* Gamma exposure rate of 5-microrem per hour (itR/hr) above background at 1 meter from a surface averaged over a 100 m 2 for inside floor surfaces. (Walls and ceilings were not surveyed for gamma exposure)5.5.1 Area Classification Area classification was performed considering that all areas of the site did not have the same potential for residual contamination and did not need the same level of survey coverage to achieve the established UW-MCP-OP-13 Rev. 2 22 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 release criteria.

Classification required areas with higher potential for contamination to receive a higher degree of survey effort. For purposes of establishing the sampling and measurement frequency and pattern, NUREG/CR-5849 uses two classifications, affected and unaffected.

Due to the Plutonium foil incident, it was determined that only specific areas were suspect for alpha contamination.

Therefore, the affected classification was further divided into alpha affected and general affected.Affected areas are areas with potential or known radioactive contamination based on plant operating history or preliminary radiological surveys. This included areas.where radioactive materials were used and/or stored, where spills or unusual occurrences may have resulted in the spread of contamination and areas immediately surrounding or adjacent to these locations.

Affected and Unaffected areas are discussed in further detail below.5.5.1.1 Affected Areas Affected areas are defined by NUREG/CR-5849 as "areas that have potential radioactive contamination (based on plant operating history) or known radioactive contamination (based on past or preliminary radiological surveillance)." NUREG/CR-5849 goes on to further define those areas directly adjacent to affected areas as affected based on potential contamination migration.

Adjacent areas may be classified as unaffected if a physical, impermeable barrier is currently in place and was present during operations.

An example would be a concrete or brick wall structure.

The maximum size for a survey unit classified as affected is I 00-M 2.There are two sub-divisions of affected for the UWNR Decommissioning project, which depend upon the relationship of the area to the plutonium foil incident.

Areas that were impacted by the reactor operation, but not by the foil incident are classified as "general affected".

Areas that were identified during the characterization surveys to have alpha contamination in excess of 25% of the established release criteria or that were directly impacted by the plutonium foil incident were classified as"alpha affected.5.5.1.2 Unaffected Areas Unaffected areas are defined by NUREG/CR-5849 as "All areas not classified as affected".

At a minimum, all areas adjacent to an affected area were also classified as affected unless separated by a permanent barrier, when they were classified as unaffected.

Upper surfaces within an affected area were classified as unaffected barring a reason to be classified as affected.

Areas separated from an affected area by an unaffected area were defined as unaffected and not requiring survey. There is no maximum size for an unaffected area.5.5.2 Survey Requirements Survey requirements for each area was determined by the classification, as defined above. Table 5-5,"UW-MHA Survey Requirements' summarizes the survey types and density given for each classification.

UW-MCP-OP-13 Rev. 2 23 UW-MCP-OP-13 Rev. 2 23 University of Washington More Hall Annex D&D, Project 10492 Final Status Survey Report Table 5-5 UWNR Survey Requirements Classification Unaffected (No maximum size)General Affected (Maximum 100-m 2)Alpha Affected (Maximum 100-m 2)Survey Type 1 per 1-m 2 Alpha static None required None required MDA 100 dpm/1 00cm 2 100% surface area 1/3 probe width per Alpha scan None required None required second upon positive detection 1 per 50-m2 1 per 42M2 I per 1-m2 Beta static MDA_<1,250 dpm/10 MDA_<1,250 MDA_<1,250 Minimum 30 locations per dpm/100cm2 dpm/100cm 2 survey area 1-m area around static 100% surface area 100% surface area Beta scan point 1 probe width per 1 probe width per 1 probe width per second second second 100% of the floor 100% of the floor Gamma scan 0% of ter surfac surface surface 0.25 m per second 0.25 m per second Removable One 100-cm 2 wipe per One 100-cm 2 wipe per One 100-cm 2 wipe per alpha activity static location static location static location wipe MDA <15 dem/100cm 2 MDA 15 dpm/I100cm 2 MDA 15 dem/10O0cm 2 Removable beta One 100-cm' wipe per One 100-cm2 wipe per One 100-cm wipe per static location static location static location aciiywipe2 MDA 50 dpm/100cm MDA <50 dpm/100cm 2 MDA <50 dpm/100cm 2 Exposure rate None per 4-mi 1 per 4-m 2 Exposure_

I rate None(floor surfaces only) (floor surfaces only)5.5.3 Reference Grids Grid pattern were established at the site to facilitate systematic selection of measuring/sampling locations; to provide a mechanism for referencing a measurement/sample back to a specific location so that the same survey point can be relocated and to provide a convenient means for determining average activity levels.A grid consists of a system of intersecting lines, referenced to a fixed site location or benchmark.

Typically, the grid lines are arranged in a perpendicular pattern, dividing the survey location into squares of equal area.Grid patterns were identified using a Cartesian Alpha-Numeric coordinate system (XY) where AO is the southwest-most corner of the floor for each unit or subunit and the lower left-hand corner of any wall in a unit or subunit. On floors, the x-axis runs east-west and the y-axis runs north-south.

On walls, the axes match the grid established for the floor resulting in the floor grid wrapping onto the walls. All measurements are in meters. Ceiling surfaces utilized a superimposition of the floor grid system to readily identify survey locations.

For example, grid location B2 on the ceiling was directly above grid location B2 on the floor.UW-MCP-OP-13 Rev. 2 24 UW-MCP-OP-13 Rev. 2 24 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 Partial grids, i.e. grids less than 1-m in at least one direction, are evaluated individually.

Normally an area less than 0.5-m is attached to the previous grid block and one greater than 0.5-m is designated as a new grid block.To facilitate survey design and assure that the number of survey data points from an area was sufficient to enable statistical evaluation, areas were divided into survey units or sub-units (as appropriate) that have common history, other common characteristics, or are naturally distinguishable from other portions of the site. Survey units could combine adjacent rooms or areas that have the same contamination potential.

To account for the possibility of combining adjacent rooms or areas into a unit, subunit designations are used. A subunit is the smallest unique area of a unit having the same potential for contamination.

Typically, a subunit is a room within a survey unit that has a distinct grid system.The location of any grid can be located by identifying the Section number, Unit number, and Sub-unit number for that grid. Typical nomenclature is as follows: Section # -Survey Unit # -Sub-unit #Where: Section Number = 1 through 3 as identified above Survey Unit Number = 1 through x (where x varies by section)Sub-unit Number = 1 through y (where y varies by unit)For example, Grid 3-13-2 is in Section 3, in Unit 13 in Sub-unit 2.Instances where the sub-unit is absent is an indication that the unit is sufficiently small to be evaluated in its' entirety.5.5.3.1 Lower Surfaces Lower surfaces are defined as floors and walls up to 2-meter height. This would include structural supports, doors, windows, and any other item or structural member present within that 2-meter area.5.5.3.2 Upper Surfaces Upper surfaces are defined as those surfaces above 2-meter height. In general, upper surfaces within an unaffected area are exempt from survey requirements.

Upper surfaces within an affected area may be classified as either affected or unaffected depending on the contamination potential.

For project purposes, any upper surface within an affected area will be considered unaffected unless survey results or process knowledge indicate a need for reclassification.

Data set analysis for some affected surfaces show that the surface area exceeds 100-M2, the maximum allowable by NUREG-5849.

In these areas, the data sets are further delineated using sub-unit designators and individually analyzed for compliance with the requirements of NUREG-5849 and the license release criteria.5.6 Background Level Determination Instrument background readings were taken each day and are used to adjust the final status survey data in order to provide a net activity.UW-MCP-OP-13 Rev. 2 25 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 5.7 FSS Survey Methods A description of each of the FSS survey methods is presented below.5.7.1 Static measurement A two-minute fixed point measurement was collected for total alpha and/or beta-gamma activity at each selected location.

For this survey type, the probe was placed on the selected surface and left in place while the instrument collected count data for the pre-set time of two minutes at which point the instrument signaled completion of the data collection with an audible tone.5.7.2 Scan This consisted of a slow scan of the selected area or item for total alpha and/or beta-gamma activity with the detector as close as practical to the surface. Scan rates were dependent on the type of survey being performed.

A scan for alpha and beta-gamma emitters was performed at 1/3 probe-width per second. A scan for only beta-gamma emitters was done at one probe-width per second. Scan rates were calculated based upon the formula presented into Section 5.3.3.5.7.3 Removable Activity Wipe Removable activity wipes were collected at each location with a 47-mm diameter cloth wipe and was analyzed on-site using the Ludlum Model 2929 counters.

To perform the wipe test for FSS, the 100-cm 2 area which received the static measurement was wiped with the cloth using moderate pressure.Removable activity wipes were collected to assess the activity of the low energy beta emitters C-14 and H-3. To perform the wipe test, a 100-cm 2 area was wiped with the scintillation wipe using moderate pressure.

The wipe was dissolved in a scintillation cocktail and counted using a QuantaSmartTM liquid scintillation counter.5.7.4 MicroR Exposure Rate Floors received a microR exposure rate survey taken at waist height of the technician.

Exposure rate surveys of walls, ceilings, and other surfaces were not required.5.7.5 Building and Equipment Surfaces To assure a consistent survey method, common building and equipment surfaces received FSS surveys consisting of static surface measurements, surface activity scans, and gamma exposure rate surveys using the procedure described below.1. Survey floors, walls, ceilings, and larger miscellaneous equipment/items on separate survey forms.UW-MCP-OP-13 Rev. 2 26 UW-MCP-OP-13 Rev. 2 26 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 2. Acquire a survey serial number from the Final Status Survey logbook. This number shall begin with FSS- and progress sequentially starting with 001. Be sure to fill in all requested information in the Final Status Survey logbook.3. Completely fill in all requested preliminary information on the "Final Status Survey Form".If an item does not apply, enter "N/A" in that location.4. Begin with a scan of the 1-meter area bounded by the grid location (i.e. A-i) at 1-probe width per second for general affected areas or 1/3-probe width per second in alpha affected areas.5. Note whether the location has physical features in the comment section of the survey form (i.e. doors, windows, columns, etc.).6. Make note of any area(s) that appear(s) elevated.7. Record the minimum and maximum counts-per-minute (CPM) of the scan on the Final Status Survey Form in the appropriate blocks.8. Perform a static count at the most elevated area within the one-meter square. If no area appears to be elevated, perform the count at the lower left comer of the one-meter square.9. Record the static count in the appropriate block on the Final Status Survey Form.10. If the static count is 100 dpm!1OOcm 2 alpha and <5,000 dpm!1OOcm 2 beta, go to step 16.11. If the static count is >100 dpm/100cm 2 alpha and/or 5,000 dpm/100cm 2 beta, scan the area around the hot spot to determine to size of the elevated area.12. Document the estimated size and static count on the "Elevated Area Survey Form".13. If the elevated area is >300 dpm/1OOcm 2 alpha; >15,000 dpm/100cm 2 beta; or >100cm 2 , document the size of the area and its activity on the Elevated Area Survey (EAS) Form and go to step 15.14. If the activity of the elevated area is 300 dpm/100cm 2 alpha and <15,000 dpm/1OOcm2 beta, and its' size is 100-cm 2 , perform at least 3 additional static measurements at random locations within the 1 meter block, and record these measurements in their approximate locations on the Elevated Area Survey Form.15. If there are multiple Elevated Areas (EA) within the 1-mi 2 block, document all of the EAS on one EAS form.16. Take a wipe sample (100-cm 2) at the location of the most elevated static count as identified in the above section UW-MCP-OP-13 Rev. 2 27 University of Washington More Hall Annex D&D, Project 10492 Final Status Survey Report 17. Record a gross exposure rate at 1-meter from the surface and document the reading on the Final Status Survey Form.18. Analyze the wipe sample, and record the result in the appropriate field of the form.19. Assure all requested information is completed on the survey forms and put the forms together in the order: a) Final Status Survey Form b) Elevated Area Survey Form(s) (if necessary) c) Miscellaneous additional documentation (i.e. maps, drawings, comments, etc.)20. Scan or photocopy the survey package and staple each package together.21. Proceed to the next survey.5.7.6 Floor Drains and Embedded Pipe Floor drains and portions of embedded pipe which remained following remediation were surveyed using a procedure equivalent to that used at the UCLA Boelter Reactor decommissioning.

Specifically, direct measurements, scans, and removable activity wipes were collected at each access point using appropriate FSS instrumentation.

Interior surfaces were swabbed using an absorbent cloth and counted using field instruments and with the wipe counters.

All measurement results were less than the guideline limits.5.7.7 Excavations When a drainline was excavated, soil samples and/or direct gross gamma scan measurements were conducted in the open excavation.

All gamma scan results corresponded to background levels. Eleven soil samples were collected from selected areas beneath the removed drainlines for volumetric analysis.

There is no applicable release guideline limits established for either the gross gamma measurements or the volumetric samples, but the information was collected to provide a substantial indication that the drainline did not have any leaks throughout its operational lifespan.

The table below summarizes the analyses of the primary radionuclides of concern from those listed in Section 5.4 for the collected soils samples. The full radiochemistry analysis results are provided in Attachment 39.Table 5-6 Soil Sample Radiochemistry Results Co-60 Cs-137 Eu-152 Eu-154 Sample Result MDC Result MDC Result MDC Result MDC ID Location (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi /) 0Ci/ (pCi/g)Process pit /Radiochemistry west lab sink Wl+l junction <MDC 4.74E-02 <MDC 6.55E-02 <MDC 1.40E-01 <MDC 1.04E-01 North bioshield W2+2 branch <MDC 8.68E-02 <MDC 7.19E-02 <MDC 2.12E-01 <MDC 2.05E-01 UW-MCP-OP-13 Rev. 2 28 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 Co-60 Cs-137 Eu-152 Eu-154 Sample Result MDC Result MDC Result MDC Result MDC ID Location (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)Process pit /S+3 mainline junction <MDC 1.08E-01 <MDC 1.07E-01 <MDC 2.25E-01 <MDC 1.94E-01 Bioshield

/N-2 mainline junction <MDC 9.49E-02 <MDC 1.06E-01 <MDC 2.79E-01 <MDC 1.89E-01 Process pit elbow in Crystal Spectroscopy W1+5 Room <MDC 5.92E-02 <MDC 7.96E-02 <MDC 2.17E-01 <MDC 1.53E-01 Radiochemistry Lab / east lab sink S+2 junction <MDC 6.64E-02 <MDC 6.88E-02 <MDC 2.42E-01 <MDC 1.68E-01 Mainline exit from 1.72E-01 SSI building <MDC 1.23E-01 +/-7.76E-02

<MDC 3.17E-01 <MDC 1.95E-01 Emergency shower/ sink junction in SS1O Experiment Room <MDC 7.70E-02 <MDC 7.48E-02 <MDC 2.23 E-01 <MDC 1.67E-01 Retention tank 2.95E-01 SS11 outlet <MDC 1.05E-01 +/-1.34E-01

<MDC 2.97E-01 <MDC 2.25E-01 Elbow outside SS4 building <MDC 1.19E-01 <MDC 9.08E-02 <MDC 2.43E-01 <MDC 1.78E-01 Sink in Experiment SS8 Room <MDC 6.48E-02 <MDC 8.67E-02 <MDC 3.19e-01 <MDC 2.04E-0I UW-MCP-OP-13 Rev. 2 29 UW-MCP-OP-13 Rev. 2 29 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 6 FINAL STATUS SURVEY EVALUATION

6.1 Statistical

Analysis FSS data was evaluated relative to conditions established for unrestricted release in USNRC License R-73. This included organization of collected data into data sets, and analysis of each data set using methods described in NUREG/CR-5849.

For comparison to guideline values, the FSS data was organized into units, taking into consideration physical location, size, and classification to meet criteria described in NUREG/CR-5849.

Each data set from each unit was evaluated using three statistical tests. An area that passed the three statistical tests is considered to have met the unrestricted release criteria for the facility.In the first test, the size of the data set was checked to determine if it was of sufficient size to demonstrate compliance.

The number of data points required was determined using the formula 8-21 in NUREG/CR-5849 along with the guideline value, the data set mean value, and the standard deviation.

If the number of data points was less than required, then additional measurements would be required to demonstrate compliance.

The second test compared individual measurements directly against the appropriate guideline value. If the elevated activity of an area was between the guideline value and the allowed maximum value, additional testing would be required to assure that the average surface activity level within the contiguous 1-im 2 area containing the elevated area is less than the guideline value. Residual activity exceeding the maximum value limit would require remediation and follow-up surveys.Finally, a test was performed to confirm that the data met the guidelines at the 95% confidence level. For this test the means and standard deviations of each data set were determined for each radiological parameter.

These values were used along with the actual number of individual measurements, a false positive probability of 5%, and a false negative value of 10%, to determine a value of Jta according to formula 8-13 in NUREG/CR-5849.

This value was then compared to the guideline value and if it was less than the guideline, the area tested met the guideline at a 95% confidence level.An additional test was performed for unaffected areas. For these areas, all individual measurements were checked to determine if the values were less than 25% of the guideline.

Any unaffected area that exceeded the 25% value would be reclassified as affected.When the data sets for a unit were determined to pass each of these statistical tests, the unit met the release criteria.

If the data set failed to pass the statistical tests, the cause of the failure would be evaluated.

6.2 Data Preparation Prior to performing any statistical analysis on the collected survey data, it must first be converted into standardized units over a standardized area. Typically this is to net disintegrations per minute per 100 square centimeters (DPM/100cm 2). This is a straight-forward conversion following industry standard techniques done by utilizing the total efficiency formula in Section 5.3.4 and correcting for the detection area of the instrument probe. Therefore, the completed formula for handheld field instruments is: UW-MCP-OP-13 Rev. 2 30 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 Net DPM/100cm 2-C, -Cb E, A Where: Cr = Instrument Counts per One Minute Cb = Instrument Daily Background Counts per One Minute Et = Total instrument efficiency A = Probe detection area in cm2 Removable activity counters utilize only the source efficiency from Section 5.3.4, but account for a wiping efficiency of 90% using the formula: Net DPMIOOcm 2 = Cr Cb E, 0.9 Where: Cr = Instrument Counts per One Minute Cb = Instrument Daily Background Counts per One Minute E, = Instrument source efficiency UW-MCP-OP-13 Rev. 2 31 UW-MCP-OP-13 Rev. 2 31 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 7 FINAL STATUS SURVEY RESULTS This section provides detailed descriptions of the results of the Final Status Survey activities for each unit.A release status determination was made for each survey unit based on a review of available data and the results of statistical analyses described in the previous sections.

Statistical analyses were performed in accordance with guidelines provided in NUJREG/CR-5849.

Attachments 1 through 38 contain information such as relevant drawings, unit location and description, statistical analyses, and the FSS data. Figures and information associated with drain lines and excavations are included in Section 10, analytical results of collected volumetric soil samples are included in Attachment 39.7.1 Survey Units Table 7-1 below provides a summary of the unit identifier, location, and classification for each of the survey units.Table 7-1 Survey Unit Identification Unit ID Location Class 1-1 Counting Room AA 1-2 Experiment Room AA 1-3 Reactor Room AA 1-4 Crystal Spectroscopy Room AA 1-5 Radiochemistry Laboratory AA 1-6 Robotics Laboratory GA 1-7 Offices, restrooms, and hallway UN 2-1 Control Room GA 2-2 Lecture Briefing Room GA 2-3 Stairs, 2nd Floor Foyer, Fan Loft, and Mechanical Equipment Room UN 3-1 Building Exterior UN 3-2 Retention Tanks and Valve Gallery AA 7.1.1 Unit 1-1 Counting Room The Counting Room is located on the ground floor in the northwest comer of the building and was classified as alpha affected.

It is a windowless room approximately 4-m by 4-m in size. A unique feature is an approximately 1-m x 1-m x 1-m 'cave' located in the north wall. The cave was constructed with a shielded door and was used to store highly radioactive sources. As part of the remediation and in preparation for FSS, the shield door and lead bricks were removed. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 1.7.1.2 Unit 1-2 Experiment Room The Experiment Room is located on the ground floor along the north side of the building and was classified as alpha affected.

It is a windowless room approximately 6-m by 5-m in size with an emergency escape hatchway in the northeast comer. As part of the remediation and in preparation for FSS, the south partition wall separating the Experiment Room from the Reactor Room was removed, leaving only the UW-MCP-OP-13 Rev. 2 32 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 original concrete archway. This unit was divided into two sub-units in order to meet size restrictions for an affected area.7.1.2,1 Sub-Unit 1-2-1 Experiment Room Ceiling, East and North Walls The Experiment Room ceiling, east and north walls were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 63-mi 2 in surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 2.7.1.2.2 Sub-Unit 1-2-2 Experiment Room Floor, South and West Walls The Experiment Room floor, south and west walls were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 55-mr 2 in surface area. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 3.7.1.3 Unit 1-3 Reactor Room The Reactor Room is located on the ground floor in the center of the building and was classified as alpha affected.

It is the largest room in the facility and measures approximately 14-m by 10-m in size and is approximately 10.5-m high. As part of the remediation and in preparation for FSS, the north partition wall separating the Experiment Room from the Reactor Room and the south partition wall separating the Reactor Room from the Crystal Spectroscopy Room were removed, leaving only the original concrete archways.

This unit was divided into 18 sub-units in order to meet the 1 00-M2 size restriction for an affected area.7.1.3.1 Sub-Unit 1-3-1 Overhead Crane The portions of the overhead crane remaining after remediation were grouped together as a sub-unit for statistical analysis.

Fifty-two survey locations were identified on all of the crane surfaces which included the fixed travel rails on the north and south ends of the Reactor Room and the mobile bridge that spanned the travel rails. The movable lifting trolley was removed as part of the remediation.

All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 4.7.1.3.2 Sub-Unit 1-3-2 Fuel and Process Pit Blocks Reinforced concrete blocks were used to cover the process pit and the fuel storage pits. These were grouped together as a sub-unit along with a portion of one remaining reactor shield block for statistical analysis.

There were 27 survey locations for this sub-unit.

Four exposure rate measurements were taken on the reactor shield block. The remaining exposure rate measurements were collected as part of the corresponding floor survey once the process pit and fuel storage pit blocks were returned to their normal positions.

All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 5.7.1.3.3 Sub-Unit 1-3-3 Fuel Storage Tubes The fuel storage pit contains 54 steel lined tubes 1.5 meters in depth embedded in concrete and recessed approximately 20 cm below the Reactor Room floor surface. Each tube is 10 cm in diameter.

Each tube UW-MCP-OP-13 Rev. 2 33 University of Washington More Hall Annex D&D, Project 10492 Final Status Survey Report yielded 0.6-M 2 of internal surface area. Three reinforced concrete blocks were normally in place over the storage pits.As per the Decommissioning Plan, each tube received 5 alpha and beta-gamma static counts, two alpha and beta-gamma removable surveys, one gamma exposure survey and one liquid scintillation wipe for hard to detect radionuclides.

Total alpha activity for the sides of the tubes was measured with an air proportional 50-cm 2 detector.

Total beta-gamma activity was collected with a 17.5-cm 2 Geiger-Mueller detector.

Each tube was also scanned for total alpha and total beta-gamma activity.

This scan was used to select the five locations for fixed point static measurement.

A total of five locations exceeded their respective guidelines limits, but were less than the maximum guideline limits. Three locations exceeded the total alpha activity guideline of 100 dpm/100-cm 2 and two locations exceeded the total beta-gamma activity guideline of 5,000 dpm/100-cm

.The activity scans indicate that each area of elevated activity is less than 100-cm2 in area. The elevated areas subsequently were evaluated for weighted average activity over the internal area of the tube. In each case, the weighted average activity was deemed to meet criteria.Table 7-2 provides a summary of the elevated result and the weighted average result by location.

In no case were there two elevated areas within one tube.Table 7-2 Elevated Activity Evaluation Location ID Elevated Result Weighted Average A2 :8 147 dpm/IOOcm 2 total Measurements equal alpha activity background B2: 7 201 dpmr/OOcm 2 total 19 dpm/IOOcm 2 total alpha activity alpha activity B2: 8 124 dpm/1OOcm 2 total 9 dpm/1OOcm 2 total alpha activity alpha activity BO: 6 5,278 dpm/100cm 2 total Measurements equal beta-gamma activity background A2: 3 6,500 dpm100cm 2 total Measurements equal beta-gamma activity background All other survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 6, liquid scintillation analytical results for the fuel storage tubes are provided in Attachment 7.The 50-cm 2 air proportional alpha detector provided the best resource for meeting the source-to-detector distance required by the instrument use procedures (i.e. no greater than 1-cm) when used on the curved surface within the fuel storage tubes. With the detector edges in contact with the tube wall, the maximum detector distance from the detector face to the apex of the tube wall was calculated to be 1.2-cm. This means the average source-to-detector distance was 0.6-cm, thereby meeting the procedural requirement of a distance no greater than 1-cm.UW-MCP-OP-13 Rev. 2 34 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 During the data evaluation phase, the total efficiency is area-corrected to reflect the size of the 50-cm 2 detector using the formula: Net DPM/100cm 2 -Cr -Cb Et *( A1 Where: Cr = Instrument Counts per One Minute Cb = Instrument Daily Background Counts per One Minute Et = Total instrument efficiency A = Probe detection area in cm 2 7.1.3A4 Sub-Units 1-3-4 through 1-3-6 These Sub-Unit numbers were not utilized due to data management planning methodologies.

7.1.3,5 Sub-Unit 1-3-7 Reactor Room North Wall 0 To 4-m The lower portions (up to 4-m above the floor surface) of the Reactor Room north wall were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 55-mr 2 in surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 8.7.1.3.6 Sub-Unit 1-3-8 Reactor Room North Wall 5 To 9-m The upper portions (5-m above the floor surface and beyond) of the Reactor Room north wall were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 67-M 2 in surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 9.7.1.3.7 Sub-Unit 1-3-9 Reactor Room South Wall 0 To 4-m The lower portions (up to 4-m above the floor surface) of the Reactor Room south wall were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 58-M 2 in surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 10.7.1.3.8 Sub-Unit 1-3-10 Reactor Room South Wall 5 To 9-m The upper portions (5-m above the floor surface and beyond) of the Reactor Room north wall were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 67-M2 in surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. All UW-MCP-OP-13 Rev. 2 35 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 11.7.1.3.9 Sub-Unit 1-3-11 Reactor Room West Ceiling Grids A-D Including Beams The western third of the Reactor Room ceiling was grouped together as a sub-unit for statistical analysis.This sub-unit is approximately 88-M 2 in surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. The ceiling construction includes 0.5 meters deep x 15 cm wide beams with a flat surface approximately 1 meter between. For simplicity, each 1-meter long section of flat surface was surveyed as one square meter and each 1-meter long section of beam was surveyed as one-square meter. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 12.7.1.3.10 Sub-Unit 1-3-12 Reactor Room Center Ceiling Grids E-H Including Beams The center third of the Reactor Room ceiling was grouped together as a sub-unit for statistical analysis.This sub-unit is approximately 88-M 2 in surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. The ceiling construction includes 0.5 meters deep x 15 cm wide beams with a flat surface approximately 1 meter between. For simplicity, each 1-meter long section of flat surface was surveyed as one square meter and each i-meter long section of beam was surveyed as one-square meter. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 13.7.1.3.11 Sub-Unit 1-3-13 Reactor Room East Ceiling Grids I-L Including Beams The center third of the Reactor Room ceiling was grouped together as a sub-unit for statistical analysis.This sub-unit is approximately 77-mi 2 in surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. The ceiling construction includes 1.5 meter deep x 15 cm wide beams with a flat surface approximately 1 meter between. For simplicity, each 1-meter long section of flat surface was surveyed as one square meter and each 1-meter long section of beam was surveyed as one-square meter. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 14.7.1.3.12 Sub-Unit 1-3-14 Reactor Room West Wall The western wall survey locations of the Reactor Room were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 91-mi 2 in surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 15.7.1.3.13 Sub-Unit 1-3-15 Reactor Room East Wall 0 To 4-m The lower portions (up to 4-m above the floor surface) of the Reactor Room east wall were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 60-mi 2 in surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 16.UW-MCP-OP-13 Rev. 2 36 UW-MCP-OP-13 Rev. 2 36 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 7.1.3.14 Sub-Unit 1-3-16 Reactor Room East Wall 5 To 9-m The upper portions (5-m above the floor surface and beyond) of the Reactor Room east wall were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 59-rM 2 in surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 17.7.1.3.15 Sub-Units 1-3-17 through 1-3-19 These Sub-Unit numbers were not utilized due to data management planning methodologies.

7.1.3.16 Sub-Unit 1-3-20 Bioshield North Wall Including Beam Ports The surfaces of the northern half of the remaining portion of the bioshield and the floor of the bioshield interior were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 81-rm 2 in surface area. While this sub-unit is classified as alpha affected, heavily remediated portions of the bioshield interior and the beam ports received surveys as general affected.

Sufficient material was removed during remediation to eliminate concern of any of the plutonium incident residual activity remaining attached to the surfaces and volumetric samples of the bioshield indicated a lack of alpha emitting nuclides in the concrete.

Three beam port penetrations were surveyed independently for beta-gamma and removable activity.Rough surfaces within the remediated portions of the bioshield interior may have had an adverse effect on the detection efficiencies during FSS. Assurance is provided that detection efficiency was not affected by a resurvey of select locations using a smaller 17.5-cm2 Ludlum model 44-9 Geiger-Mueller detector capable of maintaining a surface to detector distance of no greater than 1-cm. During this survey, measurement results are consistent with those obtained with the larger gas proportional Ludlum 43-68 detectors.

The beta-gamma release criteria for this sub-unit and sub-unit 1-3-21 (the south bioshield) were reduced to 1700 dpm/100cm 2 for total surface activity and 340 dpm/1OOcm 2 for removable surface activity to account for the potential presence of tritium in the bioshield concrete.

Using a 1.86:1 ratio of tritium to beta-gamma emitters, the beta-gamma limit of 1700 dpm/100cm 2 , would equate to 3160 dpm/100 cm 2 tritium, which is below the release criteria for tritium in the Decommissioning Plan of 5000 dpm/100cm 2.Use of this criteria, which is for removable activity, is conservative in that the volumetric analysis was performed for total activity.

Additional conservatism is provided through the application of the unity rule.The unity calculation is performed to assure that differing release criteria for multiple radionuclides do not result in a total contamination above release levels. This is accomplished by formula 4-3 from the MARSSIM: Unity C 1 + C2 C, DCGL 1 DCGL 2 DCGLn Where: C = radionuclide concentration DCGL = appropriate radionuclide release limit Applying this calculation to the release limits for beta-gamma emitters (1700 dpmrlOOcm2 ) and tritium (5000 dpm/1OOcm 2) results in a unity value of 0.97, thereby assuring that a beta-gamma survey value that UW-MCP-OP-13 Rev. 2 37 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 is equal to the reduced criteria results in true compliance to all release criteria.

The calculations for the modified release criteria and unity rule are provided in Attachment

41. As a result, all survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 18.7.1.3.17 Sub-Unit 1-3-21 Bioshield South Wall Including Beam Ports The surfaces of the southern half of the remaining portion of the bioshield were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 68-M 2 in surface area. While this sub-unit is classified as alpha affected, heavily remediated portions of the bioshield interior and the beam ports received surveys as general affected.

Sufficient material was removed during remediation to eliminate concern of any of the plutonium incident residual activity remaining attached to the surfaces and volumetric samples of the bioshield indicated a lack of alpha emitting nuclides in the concrete.

Three beam port penetrations were surveyed independently for beta-gamma and removable activity.

The beta-gamma release limit for this sub-unit was also reduced to 1700 dpm/100 cm2 to account for the presence of tritium. Select locations within the remediated portions of the bioshield were surveyed with a smaller detector as was described in the above section to verify the detection efficiency was not adversely affected by the rough surfaces.

All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 19.7.1.3.18 Sub-Unit 1-3-22 through 1-3-29 These Sub-Unit numbers were not utilized due to data management planning methodologies.

7.1.3.19 Sub-Unit 1-3-30 Process Pit All surfaces of the process pit were grouped together as a sub-unit for statistical analysis.

This included removable activity surveys of all penetrations into the process pit, such as drain lines from the reactor core and electrical conduits.

All penetrations were swabbed and analyzed for removable activity.

This included 4 penetrations on the east wall, one penetration on each the south and west walls, and 7 penetrations on the north wall. One pipe penetration, NPP-5, was large enough to survey directly with a GM detector, therefore, a direct scan of the penetration interior for total beta-gamma activity was performed.

This sub-unit is approximately 68-mi 2 in surface area. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 20.7.1.3.20 Sub-Unit 1-3-31 through 1-3-39 These Sub-Unit numbers were not utilized due to data management planning methodologies.

7.1.3.21 Sub-Unit 1-3-40 Reactor Room Floor West Grids A-G The survey locations of the western half of the Reactor Room floor were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 65-mi 2 in surface area. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 21.7.1.3.22 Sub-Unit 1-3-41 Reactor Room Floor East Grids H-N The survey locations of the eastern half of the Reactor Room floor were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 57-mr 2 in surface area and included utility trenches.UW-MCP-OP-13 Rev. 2 38 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 Portions of the floor were removed during drain line remediation.

All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 22.7.1.4 Unit 1-4 Crystal Spectroscopy Room The Crystal Spectroscopy Room is located on the ground floor in the southwest comer of the building and was classified as alpha affected.

It is a windowless room approximately 10-m by 4-m in size with an emergency escape hatchway in the southeast comer. As part of the remediation and in preparation for FSS, the north partition wall separating the Crystal Spectroscopy Room from the Reactor Room was removed, leaving only the original concrete archway. The Crystal Spectroscopy Room housed the air handling and coolant systems for the restricted areas. This unit was divided into three sub-units in order to meet size restrictions for an affected area.7.1.4.1 Sub-Unit 1-4-1 Crystal Spectroscopy Room Ceiling, East, North, and West #2 Walls The survey locations for the ceiling, east wall, north wall, and a partial wall attached to the north wall were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 87-M 2 in surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken.All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 23.7.1.4.2 Sub-Unit 1-4-2 Crystal Spectroscopy Room Floor, West and South Walls The survey locations for the floor, west wall, and south wall were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 96-mr 2 in surface area. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 24.7.1.4.3 Sub-Unit 1-4-3 Crystal Spectroscopy Overhead Piping A total of 32 survey locations associated with sealed overhead piping which carried supply water to and from the restricted area coolant systems was grouped together as a sub-unit for statistical analysis.

Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. The pipes were surveyed and grid coordinates applied based upon the overhead ceiling grid coordinate in which the pipe was located. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 25.7.1.5 Unit 1-5 Radiochemistry Lab The survey locations contained within the Radiochemistry Laboratory were grouped together as a subýunit for statistical analysis as an alpha affected unit. The Radiochemistry Lab dimensions are approximately 4-m x 4.5-m with approximately 87-mr 2 in total surface area. Portions of the floor were removed during drain line remediation.

All survey results in this unit are less than the guideline limits.FSS results and a statistical summary are provided in Attachment 26.7.1.6 Unit 1-6 Robotics Laboratory The Robotics Laboratory is located on the ground floor in the southeast comer of the building.

The room dimensions are approximately 8-m x 9-m. Due to limited space in the facility, the room was used during UW-MCP-OP-13 Rev. 2 39 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 D&D activities to store full waste boxes prior to shipment.

The waste boxes received a complete release survey prior to removal from the restricted area to ensure no removable activity was present on the exterior surfaces of the box. This unit is classified as a general affected unit. A small electrical equipment room (aka Transformer Room) is located in the southwest comer of the Robotics Laboratory and was included in this unit. This unit was divided into four sub-units in order to meet size restrictions for an affected area.7.1.6.1 Sub-Unit 1-6-1 Robotics Lab Floor The survey locations for the floor were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 80-M 2 in total surface area. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 27.7.1.6.2 Sub-Unit 1-6-2 Robotics Lab West and South Walls The survey locations for the west and south walls and were grouped together with locations in the Transformer Room as a sub-unit for statistical analysis.

This sub-unit is approximately 96-r 2 in total surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken.All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 28.7.1.6.3 Sub-Unit 1-6-3 Robotics Lab East and North Walls The survey locations for the east and north walls were grouped as a sub-unit for statistical analysis.

This sub-unit is approximately 88-M 2 in total surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. All survey results in this unit are less than the guideline limits.FSS results and a statistical summary are provided in Attachment 29.7.1.6.4 Sub-Unit 1-6-4 Robotics Lab Ceiling The survey locations for the Robotics Lab ceiling were grouped as a sub-unit for statistical analysis.

This sub-unit is approximately 88-mi 2 in total surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. All survey results in this unit are less than the guideline limits.FSS results and a statistical summary are provided in Attachment 30.7.1.7 Unit 1-7 Offices, Restrooms, and Hallway The remaining portions of the first floor were identified during review of the Characterization Report as unaffected and were grouped together as a unit for statistical analysis.

Thirty randomly selected locations received surveys. The survey results underwent the standard FSS statistical analysis and were also evaluated to ensure no individual measurement exceeded 25% of the appropriate criteria.

All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 31.7.1.8 Unit 2-1 Control Room The Control Room is located in the center of the 2 nd floor with an overlooking view of the Reactor Room.This room was identified during a review of the Characterization Report as a general affected area. The UW-MCP-OP-13 Rev. 2 40 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 dimensions are approximately 7-m x 4-m. This unit was divided into two sub-units in order to meet size restrictions for an affected area.7.1.8.1 Sub-Unit 2-1-1 Control Room Ceiling, East, and North Walls The Control Room ceiling, east and north walls were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 80-mi 2 in surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 32.7.1.8.2 Sub-Unit 2-1-2 Control Room Floor, South, and West Walls The Control Room floor, south and west walls were grouped together as a sub-unit for statistical analysis.This sub-unit is approximately 68-m 2 in surface area. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 33.7.1.9 Unit 2-2 Lecture Briefing Room The Lecture Briefing Room is located in the southeast comer of the 2 nd floor with an overlooking view of the Reactor Room. This room was identified during a review of the Characterization Report as a general affected area. The dimensions are approximately 5-m x 5-m. This unit was divided into two sub-units in order to meet size restrictions for an affected area.7.1.9.1 Sub-Unit 2-2-1 Lecture Briefing Room Ceiling, East, and North Walls The Lecture Briefing Room ceiling, east and north walls were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 64-mr 2 in surface area. Since no floor surfaces are within this sub-unit, no exposure rate measurements were taken. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 34.7.1.9.2 Sub-Unit 2-2-2 Lecture Briefing Room Floor, South, and West Walls The Lecture Briefing Room floor, south and west walls were grouped together as a sub-unit for statistical analysis.

This sub-unit is approximately 60-mr 2 in surface area. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 35.7.1.10 Unit 2-3 Stairs, 2nd Floor Foyer, Fan Room, and Mechanical Room The remaining portions of the second floor were identified during review of the Characterization Report as unaffected and were grouped together as a unit for statistical analysis.

Thirty randomly selected locations received surveys. The survey results underwent the standard FSS statistical analysis and were also evaluated to ensure no individual measurement exceeded 25% of the appropriate criteria.

All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 36.UW-MCP-OP-13 Rev. 2 41 UW-MCP-OP-13 Rev. 2 41 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 7.1.11 Unit 3-1 Building Exterior The exterior surfaces of the building were grouped as a survey unit for statistical analysis as an unaffected area. A total of random 36 survey locations were chosen covering all external surfaces, including walls, roof, and the patio area surrounding the second floor. The survey results underwent the standard FSS statistical analysis and were also evaluated to ensure no individual measurement exceeded 25% of the appropriate criteria.

All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 37.7.1.12 Unit 3-2 Retention Tanks and Valve Gallery Two retention tanks and an associated central control valve gallery are located at and below ground level approximately 5-m south of the building.

Each tank is approximately 2-m x 2-m x 2-m in size and the valve gallery is approximately 2-m x 1-rn x 2-m in size. This unit was classified as an alpha affected area due to elevated alpha activity found during characterization verification surveys following the clean out of the tanks. All survey results in this unit are less than the guideline limits. FSS results and a statistical summary are provided in Attachment 38.UW-MCP-OP-13 Rev. 2 42 UW-MCP-OP-13 Rev. 2 42 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 8 FSS QUALITY ASSURANCE 8.1 Project Objective The objective of the FSS Quality Assurance section is to provide a description of the policies and procedures utilized to assure data quality in support of the decommissioning of the UWNR.8.2 Quality Objectives The methods described in this document were utilized to ensure that the data collection and analysis achieved the Data Quality Objectives (DQOs) set forth for the UW-MHA Decommissioning.

The methods employed to ensure such quality were:* Careful planning and design of methods and procedures;

• Selection of qualified personnel and thorough training of the personnel to the procedures

• Audits and reviews of collected data to verify accuracy;* Identification and correction of problems or uncertainties as they arise.8.3 Criteria for Measurement Data The decommissioning release criteria for measurement data is based upon Regulatory Guide 1.86'Termination of Operating Licenses for Nuclear Reactors'.

8.4 Special

Training Requirements/Certification Prior to beginning work on the project, each Radiation Control Technician (RCT) received training on all pertinent project procedures.

This training included, at a minimum, review of the operation of each radiological survey instrument, discussion of the QA/QC expectations, and review of the data collection and documentation procedures.

The Safety and Compliance Manager documented the training on an attendance roster and retained the documentation on-site.8.5 Documentation and Records All documentation pertinent to the final status of the UW-MHA decommissioning project was maintained on-site by the Safety and Compliance Manager.8.6 Instrument Calibration and Frequency At a minimum, radiological instruments were calibrated:

UW-MCP-OP-13 Rev. 2 43 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492* Semi-Annually

• Following any repair that may affect the calibration

• When the pre-operational source check is greater than +/-10% difference from the initial source response 8.7 Assessments and Response Actions 8.7.1 QA/QC Assessment Checklist Quality Assurance and Quality Control (QA/QC) checklists provided a method for assuring survey accuracy and provided a manner in which to identify and correct discrepancies.

The following is the general guidance provided to the QA/QC manager to verify the proper completion of QA/QC Assessment Checklist for the UWNR decommissioning project.1. Begin with an appropriate blank QA/QC Checklist.

2. Each checklist has a review information section that contains at a minimum QA/QC reviewer, review date, item reviewed, and an approval/rejection indicator.

Ensure each of these blocks is complete, if an item does not apply, enter "N/A" in that block.3. A section is present on each checklist that is specific to the information being examined.

This section will contain block-columns for "Y", "N", "Item", and "Corrective Action / Comments" 4. In all cases, a definitive mark placed in the "Y" block-column indicates an acceptable item condition and a definitive mark in the "N" block-column indicates a deficiency condition that requires corrective action for that item.5. Any mark placed in the acknowledgement section should be definitive in that it should not cross block boundaries and it should positively indicate which block is selected.

A suggested mark would be an. "X" placed within one block.6. The "Item" block-column describes that which the reviewer is to examine and determine the acceptance or rejection thereof. In most cases, this item is strictly "Yes" or "No" and is not subject to outside conditions or reviewer opinion.7. The "Corrective Action / Comments" block-column provides space for the reviewer to provide a suggested course of corrective action or it may be used to call attention to a potential future condition to be examined (i.e. "Numbers '1' and '7' appear similar on the datasheet").

8. If each line item has been satisfied (only "Y" acknowledgement blocks are marked), the checklist is approved and should receive an appropriate indicator in the approval area of the QA/QC Review Information section.UW-MCP-OP-13 Rev. 2 44 UW-MCP-OP-13 Rev. 2 44 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 9. If corrective action is necessary, complete a new checklist once all action items have been satisfied and attach the new checklist to the original.

Repeat as necessary until the checklist receives an"Approved" mark.10. File all "Approved" checklists in the UWNR QA/QC file.8.8 QA/QC Verification Surveys QA/QC verification surveys were performed once a survey unit FSS was completed.

At a minimum, one QA/QC Verification survey was performed for each survey unit as a standard practice.

This was done to provide an early indication of potential problems with final status survey procedures/guidelines, instrumentation, and/or possible cross-contamination from ongoing site decontamination activities.

All verification surveys were performed in accordance with the UWNR FSS Plan. Verification of final status surveys included the investigation of documentation, survey protocol, instrument calibration, and any practice associated with the collection of survey data. Verification surveys were completed by the Safety and Compliance Manager or, at the discretion of the Safety and Compliance Manager, by a different technician than performed the original survey.QA/QC verification surveys were performed on at least 5% of each survey unit. All requested information was verified complete on the surveys and all instruments were verified to be properly available for use, i.e., each instrument had received a valid daily pre-operational check. Locations within a survey unit were randomly selected for verification.

The verification survey followed the same survey protocol utilized for FSS surveys. Upon completion of the verification survey, each verification location was directly compared against the original FSS location.

If the QA/QC survey result was less than the final status survey result, no action was necessary.

If there was a net difference within +25%, no action was required.If the net QA/QC survey result was +25% or greater, the net count differential was added to the net QA/QC survey result to calculate an adjusted net QA/QC value. If this adjusted net QA/QC value was less than unrestricted release criteria appropriate to the survey, no further action was required.

If the adjusted net QA/QC result was greater than the unrestricted release criteria appropriate to the survey,"Invalid" was written on the Final Status Survey copy and in the appropriate entry of the Final Status Survey logbook along with the QA/QC reviewers' initials and date and designate locations on that survey to be resurveyed.

All QA/QC verification surveys indicated the original FSS surveys to be valid and no corrective action and/or resurveys were necessary.

8.9 Data Entry and Review During data entry, all survey forms were reviewed for completeness and legibility, and survey instrumentation were reviewed to ensure a valid calibration.

Any discrepancies or missing information necessitated direct communication with the originating technician for correction.

If the originating technician was not available, clarification was obtained from the Safety and Compliance Manager, the on-site RSO, or the survey data was recollected.

QA of the data entry was performed once the handwritten surveys had been entered into electronic versions of the form. The data entry review was performed on at least 5% of the survey records and included the following items:* Survey Information (serial numbers, dates, unit, etc.) all corresponded to the survey original UW-MCP-OP-13 Rev. 2 45 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492* The surface type (wall, floor, ceiling, etc.) was valid* The grid (X, Y) represented on the survey form was present and valid* Each reading (static measurements, scans, removable activity, etc.) on the electronic copy corresponded to the original survey* Comments corresponded to the original survey 8.10 Completeness Review Prior to performance of the FSS statistical analysis, a completeness review was performed to verify that each surface of each survey unit had been adequately surveyed to meet density requirements set in the FSS Plan. This was accomplished by directly comparing the accumulated survey data against prepared survey maps. Any discrepancies were related to the Safety and Compliance Manager and/or the site RSO for investigation or additional survey as appropriate.

8.11 Data Analysis Data analysis was performed utilizing data spreadsheets and analysis routines developed by ENERCON specifically for the evaluation of NUREG/CR-5849 survey data. These spreadsheets have been utilized for many projects and the formulae and analysis routines have received numerous verification and validation reviews.A master database was created to manage the FSS survey data. This database provided the data source for the individual unit or sub-unit statistical analysis.

Only the required survey data was placed into the spreadsheets for analysis.

Survey data that was not required, such as alpha survey data collected in an unaffected area or exposure rates collected for a wall surface, was discarded from the analytical sheets, but has been retained in the master database.UW-MCP-OP-13 Rev. 2 46 UW-MCP-OP-13 Rev. 2 46 University of Washington Final Status Survey Report More Hall Annex D&D, Project 10492 9 REFERENCES

• United States Nuclear Regulatory License R-73* "Standard Format and Content of Decommissioning Plans for Licenses", Regulatory Guide 3.65, U.S. Nuclear Regulatory Commission, August 1989* "Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material", Regulatory Guide 1.86, U.S. Nuclear Regulatory Commission, April 1993" "Manual for Conducting Radiological Surveys in Support of License Termination", NUREG/CR-5849, U. S. Nuclear Regulatory Commission, 1992* "NMSS Decommissioning Standard Review Plan", NUREG-1727, U.S. Nuclear Regulatory Commission, 2000" "Residual Radiation Contamination from Decommissioning", NUREG/CR-5512, Volume 1, US Nuclear Regulatory Commission, 1992* "Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions", NUREG-1507, U.S. Nuclear Regulatory Commission, 1997* "Decommissioning of a University Research Reactor", Abelquist et al., 1994" "Evaluation of Surface Contamination

-Part 1: Beta Emitters and Alpha Emitters", ISO-7503-1, International Standards Organization, Geneva, Switzerland, 1988" University of Washington Nuclear Reactor Decommissioning Project; Investigation and Analysis Phase; Radiological Characterization Plan, November 1993* University of Washington Nuclear Reactor Decommissioning Plan, 1994" Draft ANSI Standard N13.12 (1978), "Control of Radioactive Surface Contamination on Materials, Equipment, and Facilities to be Released for Uncontrolled Use", ANSI 1978 UW-MCP-OP-13 Rev. 2 47 UW-MCP-OP-13 Rev. 2 47 University of Washington More Hall Annex D&D, Project 10492 Final Status Survey Report 10 SITE MAP DRAWINGS UW-MCP-OP-13, Rev. 2 UNIVERSITY OF WASHINGTON NUCLEAR REACTOR DECOMMISSIONING FIRST FLOOR LAYOUT OPEN TO REACTOR ROOM SUDING DOOR/SLATE CHALKBOARD CONTROL ROOM (2-1)LECTURE ROOM (2-2)2 N FLOOR STNRS HALLWAY (2-3)UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS PROJECT REACTOR DECOMMISSIONING Drawn by: DM.DRAWING SECOND FLOOR LAYOUT DRAWING 2 Enercon Services I UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS PROJECT REACTOR DECOMMISSIONING Drawn by: DM DRAWING THIRD FLOOR LAYOUT DRAWING 3 Enercon Services

!::ES' L 'OkM&EXPE7F --N^*N Rc~~1 RAL,%hJATE

!RE-ACTOR K/ North>O5~3/4~d Bn-j~leld---- ------ROB ()T'ý G ROw R SDrainline section left in place-w Drainline section removed UNIVERSITY OF WASHINGTON NUCLEAR REACTOR DECOMMISSIONING UNDERGROUND DRAIN LINES LOCATION MAP Drainline section left in place Drainline section removed UNIVERSITY OF WASHINGTON NUCLEAR REACTOR DECOMMISSIONING UNDERGROUND DRAINLINES LOCATION MAP SOIL SAMPLE LOCATIONS University of Washington More Hall Annex D&D, Project 10492 Final Status Survey Report 11 ATTACHMENTS UW-MCP-OP-13, Rev. 2 University of Washington More Hall Annex D&D, Project 10492 Attachment 1 -Unit 1-1 Counting Room FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-1 (Counting room)I Location

Description:

I counting room I'- I + I _ _ __ Ir f Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpml/00cm

2) (dpm/100cm

2) (pRr)Number of measurements:

87 87 87 87 19 Number of measurements needed : 9 9 9 9 N/A Maximum value of results: 45 12 3155 70 0 Mean value of results: 6 1 157 9 0 Standard Deviation ofresults:

10 2 341 18 0 Degree of Freedom (2): 1.665 1.665 1.665 1.665 1.734value: 8 1 218 12 0 Guideline level: 100 20 5000 1000 5 Are there sufficient measurements?

Yes Yes Yes Yes Yes Is the max value < guideline level? Yes Yes Yes Yes Yes Is pt,, < guideline?

Yes Yes Yes Yes Yes Does survey unit pass? Yes Yes Yes Yes Yes as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-i for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-1 (Counting room)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta BetaScan BetaScan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpin) (cpat) DPM (cpm) (cpmn) DPM DPM 022 08/21/06 AA i W Wall A 0 3 ND ND 380 0 160 4 29 4m2 West Wall 022 08/21/06 AA I W Wall A 2 0 ND ND 106 0 160 0 0 2m2 West Wall 022 08/21/06 AA I W Wall C 0 14 ND ND 159 0 160 0 33 4m2 West Wall 022 08/21/06 AA I W Wall C 2 3 ND ND 143 0 180 0 29 2m2 West Wall 022 08/21/06 AA I W Wall E 0 20 ND ND 151 0 160 0 19 2rn2 West Wall 023 08/21/06 AA 1 S Wall A 0 14 ND ND 131 0 160 0 38 4m2 South Wall 023 08/21/06 AA I S Wall A 2 14 ND ND 86 0 160 0 0 2m2 South Wall 023 08/21/06 AA I S Wall C 0 3 ND ND 111 0 160 0 0 4m2 South Wall 023 08/21/06 AA I S Wall C 2 14 ND ND 133 0 180 0 70 2na2 South Wall 024 08/23/06 AA I Floor A 0 11 0 I 127 0 180 0 0 0 4m2 024 08/23/06 AA I Floor A 2 0 0 2 143 0 160 0 0 0 4mss2 024 08/23/06 AA 1 Floor C 0 22 0 I 161 0 160 0 0 0 4m2 024 08/23/06 AA I Floor C 2 22 0 2 105 0 880 0 38 0 4tn2 024 08/23/06 AA I Floor B 4 45 0 2 107 0 180 0 0 0 hIn2 025 08/24/06 AA I Floor B 4 33 0 ND 263 0 500 0 0 0 4m2 Comipletion ofFSS-024 026 08/20/06 AA I N Wall A 0 0 0 4 0 100 105 0 0 026 08/20/06 AA I N Wall A 1 0 0 0 0 80 125 0 0 026 08/20/06 AA I N Wall A 2 0 0 0 0 800 127 0 0 026 08/20/06 1AA I IN Wall B 0 0 0 0 0 800 105 0 0 N. Wall of'Penetration 026 08/20/06 AA I N Wall B- 1 0 0 0 0 110 187 0 0 026 08/20/06 AA I N Wall B 2 0 0 0 0 1o0 126 0 0 026 08/20/06 AA I N Wall C 0 0 0 0 0 100 130 0 0 026 08/20/06 AA I N Wall C 1 0 0 0 0 60o 120 4 0 026 08/20/06 AA I N Wall C 2 0 0 4 0 100 142 0 0 026 08/20/06 AA I N Wall D 0 0 0 3 0 100 114 0 0 026 08/20/06 AA I N Wail D 1 0 0 1 0 80 130 0 0 026 08/20/06 AA I N Wall D 2 0 0 0 0 100 128 0 0 027 08/24/06 AA I Ceiling A 0 5 0 0 0 60 80 0 0 027 08/24/06 AA I Ceiling A 1 0 0 2 0 60 t00 0 0 027 08/24/06 AA I Ceiling A 2 5 0 4 0 60 80 0 6 027 08/24/06 AA I Ceiling 3 0 0 2 0 60 200 0 0 027 08/24/06 AA I Ceiling D 0 0 0 0 0 60 800 0 0 027 08/24/06 AA I Ceiling B 1 0 0 3 0 60 100 4 0 027 08/24/06 AA I Ceiling B 2 0 0 3 0 60 100 0 0 027 08/24/06 AA I Ceiling 3 0 0 0 0 60 100 0 0 027 08/24/06 AA I Ceiling C 0 0 0 2 0 860 -0 0 027 08/24/06 AA I Ceiling C 1 0 0 0 0 60 100 0 2 027 08/24/06 AA I CeaII C 2 0 ND 0 16 200 0 0 027 08/24/06 AA 1 Ceiling C 3 0 N 0 0 60 820 0 0 027 08/24/06 AA I Ceiling D 0 0 0 1 0 60 800 0 0 027 08/24/06 -AA 1- Ceiling D 1 0 0 2 0 60 100 0 11 027 08124/06 AA I Ceiling D 2 0 0 3 0O 60 i00 10 0 027 08/24106 AA I Ceiling; D 3 0 0 1 0 60 120 0 21 030 08/28/06 AA I W Wall A 0 0 2 0 160 030 09/28/06 AA I W Wait A 1 0 ND NiD 186 0 160 12 2 030 108/28/06 AA I W Wall A 2 ND ND 0 160 030 08/28/06 AA 8 W Wall B 01 0 ND ND 164 0 160 0 0 030 08/28/06 AA I W Wall B 1 5 ND ND 137 0 160 0 0 030 08/28/06_

AA I W Wall g 0 0 2 0 160 030 08/28/06 AA I W Well C 1 0 ND ND 133 0 1 160 0 0 030 08/28/06 AA 1 W Wall C 2 ND ND 0 160 030 08/28/06 AA I W Wall D 0 0 ND ND 152 860 0 8 ENERCON Serices, ie.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-1 (Counting room)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta BetaScan BetaScan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpii) (cpm) DPM (cprm) (cpu) DPM DPM 030 08/28/06 AA I W Wall D 1 12 0 2 182 0 160 0 2 030 08/28/06 AA I W Wall D 2 ND ND 0 160 030 08/28/06 AA I W Wall E 0 ND ND 0 160 030 08/28/06 AA I W Wall B 2 ND ND 0 160 0 17 031 08/28/06 AA I IE Wall A 0 0 1 0 0 031 08/28/06 AA I E Wall A 1 0 1 0 0 031 08/28/06 AA I E Wall A 2 0 1 0 0 03 [ 08/28/06 AA 1 E Wall B 0 19 0 1 89 0 12 031 01/32/06 AA I E Wall B 1 19 0 1 51 0 0 032 08/28/06 AA 1 E Wall B 2 0 0 1 156 0 0 031 08/28/06 AA I E Wall C 0 0 1 4 2 031 08/28/06 AA I E Wall C 2 39 0 1 101 0 0 031 08/28/06 AA I E Wall C 2 0 0 1 71 0 0 031 08/28/06 AA I EWall D 0 0 N 0 1 170 0 32 031 08/28/06 AA I S Wall D 1 12 0 1 212 0 0 031 081/281/06 AA I E Wall D 2 12 0 3 246 0 0 031 08/28/06 AA I E Wall E 0 0 1 0 0 031 08/28/06 AA I E Wall E 1 0 0 1 202, 0 0 031 08/28/06 AA I E Wall E 2 0 1 0 2 032 08/31/06 AA I S Wall A 1 25 ND ND 225 0 300 0 0 hln^2 032 08/31/06 AA I S Wall B 0 15 ND ND 204 0 300 0 41 0 ha^2 032 08/31/06 AA I S Wall B 1 2 ND ND 128 0 320 0 62 hai^2 032 08/3 1/06 AA I S Wall B 2 ll ND ND 277 1 0 300 1 0 0 hn^2 032 08/31/06 AA I S Wall C 1 0 0 2 31 3 0 220 0 0 10R F^2 032 08/31/06 AA I S Wall D 0 11 ND ND 292 0 320 0 0 11^2 032 08/31/06 AA I ISWall D 1 25 ND ND 242 0 340 0 21 h n^2 032 08/31/06 AA I S Wall D 2 20 ND ND 372 0 300 0- 62 1mn^2 034 08/31/06 AA I Floor A 11 ND ND 237 0 320 0 52 0 hnn2 034 08/31/06 AA I Floor B 0 2 ND ND 366 0 300 0 67 0 lm^2 034 08/31/06 AA I Floor B 1 11 ND ND 214 0 340 0 67 0 ha^2 034 08/31/06 AA I Floor B 2 6 ND ND 185 0 400 0 0 0 1 m^2 034 08/31/06 AA I Floor B 3 0 ND ND 116 0 300 4 0 0 1 m^__2 034 08/31/06 AA I Floor B 4 11 ND N D 3155 1 0 480 1 0 31 0 h A^2 034 08/31/06 AA I Floor C 1 6 ND ND 239 100 260 4 0 0 a2 034 08/31/06 AA I FWllor D 0 0 ND ND 246 0 300 0 26 0 1 ma2 034 08/3[106 AA L Floor D 1 25 ND N D 166 0 240 0 0 0 Wal2 034 08/31/06 AA 1 Floor D 2 11 ND ND 258 0 280 0 0 0 1hn^2 034 08/3 t/06 AA I Floor D 3 6 ND ND 267 0 260 4 6 0 1I m^2 141 10/02/06 AA I Floor A 3 1 0 0 2 50 120 200 0 0 0 Count Roomi Floor 141 10/02/06 AA I Floor C 3 0 0 2 193 100 220 0 0 0 Count Roomi Floor 147 10/02/06 AA 1 W Wall A I 100 240 147 10/02/06 AA I W Wall B 0 1 80 200 147 10/02/06 AA I W Wall B 1 120 220 147 10/02/06 AA I W Wall B 2 0 0 2 216 100 24U 147 10102/06 AA I W Wail D 0 too 220 147 10/02/06 AA I 1W Wall D 1 120 220 147 10/02/06 AA I W Wall D 2 0 0 2 171 100 220 4 0 147 10/02/06 AA I W Wall C I1 2 0 2 235 100 2401 148 10/02/06 AA 1 EWall Aý 0 0 0 2 110 too 200 East Wall in cave 148 10/02/06 AA I JE Wall 1 0 120 240 East Wall 148 10/02/06 AA I JE Wall B 1 100 1 220 jEast Well 148 10/02/0 AA 1 Ewall B 2 80--F 200 East Wall ENERCON Services, ic.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-1 (Counting room)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Mtn. Scan Max. Direct Min. Max. Wipe Wipe DPIVI (cpms) (cpHI) DPM (cpul) (cplu) DPM DPM 148 10/02/06 AA I E Wall C 0 0 0 2 223 100 200 East Wall 148 10/02/06 AA I E Wall C I 100 220 East Wall 148 10/02/06 AA I E Wall C 2 120 220 East Wall 148 10/02/06 AA I E Wall D 0 100 200 East Wall 148 10/02/06 AA I E Wall D 1 120 240 East Wall 148 10/02/06 AA I E Wall D 2 100 220 East Wall 148 10/02/06 AA I E Wall E 0 0 0 2 141 100 200 1 _ East Wall 148 10/02/06 _6A _ I EWall E 1 100 220 East Wall 148 10/02/06 AA I E Wall E 2 0 0 2 166 100 200 1 lEast Wall 148 10/02/06 AA I E Wall E 1 120 220 East Wall 148 10/02/06 AA I E Wall E 2 0 0 2 196 100 200 East Wall ENERCON Services, inc.

University of Washington More Hall Annex D&D, Project 10492 Attachment 2 -Sub-Unit 1-2-1 Experiment Room Ceiling, East and North Walls FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-2-1 (Experiment room ceiling, east and north walls).. ... ....Unit Designator:.._

1- Class: AA Certainty[ Location

Description:

Experiment room ceiling, east and north walls Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm), (pR/hr)Number of measurements:

63 63 63 63 N/A Number of measurements needed (1)" 9 9 9 9 N/A Maximum value of results: 38 8 331 64 N/A Mean value of results: 4 0 82 12 N/A Standard Deviation of results: 9 1 110 19 N/A Degree of Freedom (2).: 1.671, 1.671 1.671 1.671 N/Avalue: 6 1 105 16 N/A Guideline level: 100 20 5000 1 000 N/A Are there sufficient measurements?

Yes Yes Yes Yes N/A Is the max value < guideline level? Yes Yes Yes Yes N/A Is ýt, < guideline?

Yes Yes Yes Yes N/A Does survey unit pass? Yes Yes Yes Yes N/A (1) as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-2-1 (Experiment room ceiling, east and north walls)FSS0# 0ate Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta2Scan Alpha Beta Net 0 R Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (0p2) (cpA) DPM (cpC) (cpm) DPM DPM 028 08/23/06 AA 1 Ceiling A 0 1 ND ND 29 100 140 0 0 028 08/23/06 AA 1 ,Ceiling 1 0 ND ND 35 80 120 0 0 028 08/23/06 AA I lCeiling A 2. 0 ND ND 0 100 140 0 0 028 08/23/06 AA I lCeiling A 3 0 ND ND 31 100 140 0 0 028 08/23/06 AA I ICeilina A 4 0 ND ND 0 100 160 0 28 028 08/23/06 AA 1 Ceiling B 0 0 ND ND 10 60 140 0 0 028 08/23/06 AA 1 Ceiling B I 0 ND ND 0 60 160 0 61 028 08/23/06 AA I Ceiling B 2 0 ND ND 0 60 120 0 0 028 08/23/06 AA I Ceiling B 3 0 ND ND 0 80 160 0 0 028 08/23/06 AA 1 Ceiling B 4 0 ND ND 0 60 140 0 61 028 08/23/06 AA I Ceiling C 0 0 ND ND 3 80 140 0 38 028 08/23/06 AA 1 Ceiling C 1 15 ND ND 7 100 180 0 0 028 08/23/06 AA I Ceiling C 2 0 ND ND 0 10 140 2 0 51 028 08/23/06 AA I Ceiling C 3 0 ND ND 37 80 180 0 0 028 08/23/06 AA I Ceiling C 4 2 ND ND 29 80 180 0 14 028 08/23/06 AA I Ceiling D 0 0 ND ND 105 80 160 0 0 028 08/23/06 AA I Ceiling D 1 0 ND ND 7 80 120 0 51 028 08/23/06 AA 1 Ceiling D 2 0 ND ND 19 100 180 3 52 028 08/23/06 AA I Ceiling D 3 0 ND ND 0 60 180 0 56 028 08/23/06 AA I Ceiling D 4 1 ND ND 5 60 160 0 19 028 08/23/06 AA I Ceiling E 0 29 ND ND 105 0 160 3 0 028 08/23/06 AA I Ceiling E 1 29 ND ND 145 0 140 0 0 028 08/23/06 AA I Ceiling E 2 .0 ND ND 31 0 140 3 0 028 08/23/06 AA I Ceiling E 3 0 ND ND 127 0 220 0 28 028 08/23/06 AA 1 Ceiling E 4 22 ND ND 2 0 180 0 0 028 08/23/06 AA I Ceiling F 0 8 IND ND 109 0 160 0 511 028 08/23/06 AA I Ceiling F 1 -8 ND ND 137 0 180 1 0 0 028 08/23/06 AA I Ceiling F 2 0 ND ND 109 0 160 0 28 028 08/23/06 AA I Ceiling F 3 8 ND IND 113 0 180 0 0 028 08/23/06 AA I Ceiling F 4 -- I ND ND 101 0 200 0 0 029 08/24/06 AA I E Wall A 0 24 ND ND 248 160 200 0 30 02 82/6 AA 1 E1 Wall A I I ND ND 200 160 200 0 0 029 08/24/06 AA 1 1E Wall A 2 17 ND ND 1 272 160 180 0 0 2Z29 0822 / AA I E W all B 0 0D ND 2 180 260 0 20 029 09/214/006 AA Il E Wall B 1 38 ND ND 1 272 160 220 8 5 029 08/24/06 AA I I E Wall 029 08/24/06 AA I I [E Wall 029 08/24/061 AA I E Wall 029 08/24/06 1 AA I I IE Wall B 1 2 0 0 0 ND ND ND ND ND 298 160 200 0 10 ND 302 180 200 0 1 0 C 1 2 029 08/24/061 AA 1 I IEWall D 0 3 ND ND 150 160 220 1 0 1 0 029 1 D I I 1 10 ND ND 1 226 160 200 1 0 1 0 1)3 ND 286 1 160 1 200 1 0 1 10 029 08/24/06 AA I I lBWall E 029 1 08/24/06 1 AA I I IlE Wall E I I 1 17 029 08/24/06 IAA I I lB Wall E 1 2. 1 10 ND 160 200 1 0 5 036 A.0 1 0 0 ND 0 0 200 1 4 18 036 A A 036 09/01/06 1 AA 1 1 IN Wall ND ND ND ND 0 0 1 200 1 0 1 0 036 109/01/061 AA I I IN Wall I B.0 0 036 036 036 09101/061 AA 1 1 IN Wall B 11 0 0 0 220 1 0 1 64 B 1 -2 0 ND 1 0 1 0 1 220 1 0 1 0 ___ 1______________________

C 0 0 1 ND 1 0 1 0 1 200 1 0 1 41 1__ 1 _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ENERCON Se-ake, ie..

University of Washington More Hall Annex Final Status Survey Results -Unit 1-2-1 (Experiment room ceiling, east and nortlh Walls)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpin) DPM (cpm) (cpm) DPM DPM 036 09/01/06 AA 1 N Wall C 1 0 0 ND 0 0 200 0 0 036 09/01/06 AA I N Wall C 2 0 0 ND 0 0 200 0 0 036 09/01/06 AA I N Wall D "0 0 0 ND 0 0 200 0 0 036 09/01/06 AA I N Wall D 1 0 0 -ND 0 0 200 0 0 036 09/01/06 AA 1 N Wall D 2 0 0 ND 0 0 200 0 0 036 09/01/06 AA 1 N Wall E 2 0 0 ND 0 0 200 0 0 036 09/01/06 AA I N Wall E 1 0 0 ND 0 0 220 0 4 Hatch iu EI, E2 036 09/01/06 AA 1 N Wall E 2 0 0 ND 0 0 200 4 0 F1,F2 036 09/01/06 AA 1 N Wall F 0 0 0 ND 0 0 200 0 4 036 09/01/06 AA 1 N Wall F I 0 0 ND 0 0 200 0 0 036 09/01/06 AA 1 N Wall F 2 0 0 ND 0 0 200 0 8 ENERCON Services, inc.

University of Washington More Hall Annex D&D, Project 10492 Attachment 3 -Sub-Unit 1-2-2 Experiment Room Floor, South and West Walls FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-2-2 (Experiment room floor, south and west walls)I Location

Description:

IExperiment room floor, south and west walls I~i4V1~. -Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results. Results Beta Results Results All Surfaces (dpmIl0Ocm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (JIR/hr)Number of measurements:

55 55 55 55 33 Number of measurements needed (1 9 9 9 9 N/A Maximum value of results: 22 8 840 111 2 Mean value of results: 5 1 224 16 1 Standard Deviation of results: 7 2 163 22 1 Degree of Freedom (2) 1.674 1.674 1.674 1.674 1.694 g value: 7 1 260 21 1 Guideline level: 100 20 5000 1000 5 Are there sufficient measurements?

Yes Yes Yes Yes Yes Is the max value < guideline level? Yes Yes Yes Yes Yes Is Jita < guideline?

Yes Yes Yes Yes Yes Does survey unit pass? Yes Yes Yes Yes Yes (1) as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-2-2 (Experiment room floor, south and west walls)FSS # Date Class Floor Surface X Y Aipha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 017 08/18/06 AA I Floor E 0 0 ND ND 715 0 200 4 0 0 FSS Dooe Prior To Rcmoving 017 08/18/06 AA 1 Floor F 0 0 ND ND 131 0 140 0 14 0 Shower Drain 017 08/18/06 AA I Floor F 1 0 ND ND 152 0 160 0 0 0 040 09/05/06 AA I Floor A 0 0 0 3 285 0 240 0 0 1 040 09/05/06 AA I Floor A I 11 0 3 356 0 280 0 41 1 040 09/05/06 AA I Floor A 2 17 0 3 153 0 280 4 0 2 040 09/05/06 AA I Floor A 3 5 0 2 292 0 320 0 18 2 040 09/05/06 AA I Floor A 4 0 0 1 270 0 320 4 0 1 040 09/05/06 AA 1 Floor B 0 11 0 3 305 0 380 4 0 1 040 09/05/06 AA I Floor B 1 0 0 1 454 0 320 0 0 2 040 09/05/06 AA I Floor B 2 22 0 3 292 0 310 0 0 2 040 09/05/06 AA I Floor B 3 17 0 4 249 0 280 0 45 2 040 09/05/06 AA I Floor B 4 0 0 1 268 0 210 0 4 2 040 09/05/06 AA I Floor C 0 5 0 2 532 0 320 0 45 2 040 09/05/06 AA I Floor C 1 17 0 2 367 0 310 0 8 2 040 09/05/06 AA I Floor C 2 0 0 1 357 0 290 0 27 2 040 09/05/06 AA I Floor C 3 0 0 1 335 0 260 0 0 2 040 09/05/06 AA -1 Floor 040 09/05/06 AA I Floor 040 09/05/06 AA I Floor 040 09/05/06 AA I Floor C 14 17 0 2 283 0 260 0 0 2 0 22 0 3 840 0 360 0 18 2.[ I 0 [ 0 1 426 340 I U D 2 5 0 2 411 340T u 2Ii 041 09/05/06 AA I S Wall 041 09/05/06 AA I S Wall 041 09/05/06 AA I S Wall 041 09/05/06 AA I S Wall A 0 0 1 ND I ND 1 66 120 1 220 1 8 1 0 A I1 6 ND ND 1 0 A. [2[01 ND 140 220 0 0 80 180 0 0 80 140 0 41 B T 2 I I I ND r'oencItraljo exists 041 09/05/06 1 AA 1 S Wall C 1 2 1 0 1 ND ND 1 0 100 1 200 1 0 0 1 S Wall D 1 2 1 0 1 ND ND 41 1 100 0 1 0 Dartial penetration exist 1 S Wall 200 041 109/05/061 AA I S Wall F P 0 ND NID I 100 S 0 i15 ND 1 1 223 042 1 09/05/06 1 AA I 1 IW Wall 120 22 0 120 24 0 042 09/05/06 AA 042 09/05/06 AA 042 09/05/06 AA 042 09/05/06 AA I W Wall I W Wall 1 W Wall I W Wall A I I ND A 2 10 ND B 0 0 ND B I 0 ND B 2 .15 ND 1 254 69 I 210 140 I 00 I 60 221 1 178 1 194 21 21 9 §218 042 1 09/05/06 1 AA I 1 IW Wall 042 09/05/06 AA 042 09/05/06 AA 042 09/05/06 AA 042 09/05/06 AA 042 09/05/06 AA I W Wall I C 1 0 1 0 1 ND 1 1 225 1 110 1 180 1 0 1 0 I W Wall I W Wall 1 W Wall 1 W Wall C I C 1 6 ND 10 1ND 187 1 120 200 0 19 245 1 110 1 180 go 01 37 1 0 0 [ ND 1_J-9 D I 1 151 ND F 1 042 09/05/061 AA I W Wall 042 09/05/06 [ AA I W Wall 042 09/05/06 AA I W Wall 042 [09/05/06 AA I W Wall 044 09/05/061 AA I Floor 0 0 ND 1 189 1 120 1 200 0 1 5 1 176 140 172 100 200 1 0 11ill 1i60-T 0 0T 22 321 0 1[Dirt Floor F 0 044 1 09/05/06 044 [09/05/06 F__ _ F___ ___ F 2 11 1 ND I ND 1 123 1 120 1 220 4 1 26 1 0 IConcrete Floor 044 09/05/06 AA I Floor 044 09/05/06 AA I Floor 044 09/05/06 AA I Floor 044 09/05/06 1 AA I Floor 044 09/05/06 AA I Floor F 3 F 4 O- -f 0 0 [Coocrrete Floor S 0 0 u [Corete Floor___0 1 ND I ND 1 91 1 100 1 200 0 1 41T 0 1Concrete Floor E ND ND 336 140 300 0 0 0 [Concre Floor END J ND 153 140 260 0 26 0 Concrete Floor E 2 0 ND ND 148 140 220 1 0 16 0 Concrete Floor ENERCON Services, ioe.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-2-2 (Experiment room floor, south and west walls)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpn) DPM DPM 044 09/05/06 AA I Floor E 3 0 ND ND 96 140 240 0 6 0 Concrete Floor 044 09/05/06 AA I Floor E 4 6 ND ND 83 140 220 0 0 0 Concrete Floor 044 09/05/06 AA I Floor D 4 6 ND ND 98 120 220 0 11 0 Concrete Floor 044 09/05/06 AA 1 Floor D 3 0 ND ND 70 120 220 0 36 0 Concrete Floor EN ERCON koir , ix-.

WEST WALL EO DO CO BO A2 Al AO NORTH WALL A2 Al AO BO CO DO EQ FO A4 A3 A2 Al AO BO CO DO EQ FE EAST WALL AO Al A2 BO CO DO EQ FO NOT SURVEYED.

Concrete removed dunng drainine excavoaon.

AO Al SOUTH WALL F2 E2 D2 C2 B2 A2r- I LIrt. 11 U_ _ ......... --__ _ _ _ _ _ _ _ ------AO BO CO DO EQ FE Al A2 A3 L A4 UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS PROJECT REACTOR DECOMMISSIONING Drawn by: DM DRAWING EXPERIMENT ROOM DRAWING 7 SURVEY UNIT 1-2 Enercon Services University of Washington More Hall Annex D&D, Project 10492 Attachment 4 -Sub-Unit 1-3-1 Overhead Crane FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-3-1 (Overhead crane)I Location

Description:

Overhead crane I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/lOOcm

2) (dpm/lOOcm

2) (dpm/lOOcm

2) (dpm/lOOcm

2) (RR/hr)Number of measurements:

38 38 38 38 N/A Number of measurements needed (1): 9 9 9 9 N/A Maximum value of results: 70 16 262 104 N/A Mean value of results: 25 1 150 21 N/A Standard Deviation of results: 16 3 80 28 N/A Degree of Freedom (2): 1.687 1.687 1.687 1.687 N/A lta value: 29 2 172 29 N/A Guideline level: 100 20 5000 1000 N/A Are there sufficient measurements?

Yes Yes Yes Yes N/A Is the max value < guideline level? Yes Yes Yes Yes N/A Is pi < guideline?

Yes Yes Yes Yes N/A Does survey unit pass? Yes Yes Yes Yes N/A as interpolated from NUREG/CR-5 849 Table B-2 (2) from NUREG/CR-5 849 Table B-I for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-1 (Overhead crane)FSS# Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (epin) DPM DPM 033 08/31/06 AA f South Crane Rail A 0 6 ND ND 0 0 240 0 62 lra^2 033 08/31/06 AA I South Crane Rail A 1 11 ND ND 111 0 260 0 36 lm^2 033 08/31/06 AA I South Crane Rail A 2 11 ND ND 151 0 260 0 0 lm^2 033 08/31/06 AA I South Crane Rail A 3 15 ND ND 74 0 280 0 0 1nm^2 033 08/31/06 AA I South Crane Rail A 4 6 ND ND 103 0 300 B 0 lm^2 033 08/31/06 AA I South Crane Rail A 5 11 ND ND 57 0 280 0 26 1ra^2 033 08/31/06 AA I South Crane Rail A 6 15 ND ND 15 0 240 0 72 Iai^2 033 08/31/06 AA I South Crane Rail A 7 25 ND ND 63 0 320 0 1 n^A2 033 08/31/06 AA I South Crane Rail A 8 25 ND ND 115 0 300 0 31 lm^2 033 08/31/06 AA I South Crane Rail A 9 29 ND ND 109 0 260 0 0 IraA2 033 08/31/06 AA I South Crane Rail A 10 2 ND ND 0 0 400 0 1 1 mA2 102 09/23/06 AA 1 Crane Bridge C 0 13 0 1 122 80 200 0 68 Includes South Support 102 09/23/06 AA I Crane Bridge C 1 13 0 1 112 80 220 4 43 Beam 102 09/23/06 AA 1 Crane Bridge C 2 43 0 3 126 80 200 0 58 Beanm 102 09/23/06 AA 1 Crane Bridge C 3 13 0 1 87 80 220 4 0 Beam 102 09/23/06 AA I Crane Bridge C 4 43 0 3 62 80 240 0 13 Beam 102 09/23/06 AA 1 Crane Bridge C 5 13 0 3 142 80 260 0 104 Beam 102 09/23/06 AA I Crane Bridge C 6 48 0 3 114 80 220 0 43 Beam 102 09/23/06 AA I Crane Bridge C 7 59 0 5 138 80 200 0 18 Beam 102 09/23/06 AA 1 Crane Bridge C 8 43 0 3 138 80 240 16 48 Beam 102 09/23/06 AA I Crane Bridge C 9 13 0 3 52 80 240 Includes North Support 117 09/28/06 AA I Crane Bridge C 9 0 73 Post-decon 127 09/30/06 AA I North Crane Rail B 0 42 0 4 258 80 280 0 20 Crane Rail North 127 09/30/06 AA I North Crane Rail B 1 37 0 4 244 80 260 12 0 Crane Rail North 127 09/30/06 AA 1 North Crane Rail B 2 19 0 5 76 80 240 0 0 Crane Rail North 127 09/30/06 AA I North Crane Rail B 3 33 0 4 231 80 260 4 0 Crane Rail North 127 09/30/06 AA I North Crane Rail B 4 19 0 4 214 80 240 0 0 Crane Rail North 127 09/30106 AA I North Crane Rail B 5 14 0 3 212 80 240 4 0 Crane Rail North 127 09/30/06 AA 1 North Crane Rail B 6 14 0 3 262 80 260 0 30 Crane Rail North 127 09/30/06 AA I North Crane Rail B 7 14 0 3 240 80 240 0 0 Crane Rail North 127 09/30/06 AA 1 North Crane Rail B 8 70 0 5 239 80 260 0 0 Crane Rail North 127 09/30/06 AA I North Crane Rail B 9 33 0 4 214 80 240 0 0 Crane Rail North 127 09/30/06 AA I North Crane Rail B 10 14 0 4 210 80 260 0 0 Crane Rail North 127 09/30/06 AA I North Crane Rail B 11 42 0 5 219 80 240 0 0 Crane Rail North 127 09/30/06 AA I North Crane Rail B 12 14 0 4 237 80 260 0 40 Crane Rail North 127 09/30/06 AA I North Crane Rail B 13 28 0 4 262 80 240 0 30 Crane Rail North 128 09/30/06 AA I South Crane Rail A 11 33 0 4 217 80 280 0 0 Crane Rail South 128 09/30/06 AA I Sooth Crane Rail A 12 23 0 4 239 80 260 0 0 Crane Rail South 128 09/30/06 AA I South Crane Rail A 13 33 0 4 242 80 260 0 0 Crane Rail South ENERCON leeires, inu.

University of Washington More Hall Annex D&D, Project 10492 Attachment 5 -Sub-Unit 1-3-2 Fuel and Process Pit Blocks FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-3-2 (Fuel and process pit blocks)I Location

Description:

IFuel and process pit blocks I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm100cm 2) (pR/hr)Number of measurements:

27 27 27 27 4 Number of measurements needed (1). 9 9 9 9 N/A Maximum value of results: 69 13 431 91 1 Mean value of results: 16 2 211 16 1 Standard Deviation of results: 18 3 75 24 0 Degree of Freedom (2): 1.706 1.706 1.706 1.706 2.353 l value: 22 3 236 24 1 Guideline level: 100 20 5000 1000 5 Are there sufficient measurements?

Yes Yes Yes Yes Yes Is the max value < guideline level? Yes Yes Yes Yes Yes Is ýta < guideline?

Yes Yes Yes Yes Yes Does survey unit pass? Yes Yes Yes Yes Yes as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-2 (Fuel and process pit blocks)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM q35 08131/0 AA I Puoces pih block NIA NIA 1 1D 164 1I0 20M0 0 D Block 035 08/31/06 AA I Process pit block N/A N/A 0 0 ND 144 100 200 0 41 Block 1 035 08/31/06 AA I Process pit block N/A N/A 0 0 ND 171 100 180 0 0 Block 2-3 035 08/31/06 AA I Process pit block N/A N/A 5 0 ND 160 100 200 4 21 Block 2-4 035 08/31/06 AA I Process pit block N/A N/A 5 0 ND 205 100 160 0 0 Block 3-5 035 08/31/06 AA 1 Process pit block N/A N/A 37 0 ND 208 100 140 0 36 Block 3-6 035 08/31/06 AA 1 Process pit block N/A N/A 0 0 ND 201 100 260 0 36 Block 4-7 035 08/31/06 AA I Process pit block N/A N/A 24 0 ND 199 100 200 0 62 Block 4-8 035 08/31/06 AA 1 Process pit block N/A N/A 24 0 ND 183 100 180 0 0 Block 5-9 035 08/31/06 AA I Process pit block N/A N/A 11 0 ND 230 100 180 0 0 Block 5-10 035 08/31/06 AA I Process pit block N/A N/A 31 0 ND 173 100 180 0 0 Block 6-11 035 08/31/06 AA I Process pit block N/A N/A 24 0 ND 229 100 200 0 0 Block 6-12 035 08/31/06 AA 1 Process pit block N/A N/A 0 0 ND 253 100 220 4 0 Block 7-13 035 08/31/06 AA I Process pit block N/A N/A 18 0 ND 247 100 200 4 21 Block 7-14 043 08/31/06 AA I Fuel storage block N/A N/A 11 ND ND 230 0 200 0 0 Block 1-I 043 08/31/06 AA I Fuel storage block N/A N/A 24 ND ND 227 0 200 4 0 Block 1-2 043 08/31/06 AA I Fuel storage block N/A N/A 11 ND ND 227 0 220 13 10 Block 2-1 043 08/31/06 AA I Fuel storage block N/A N/A 5 ND ND 247 0 220 0 0 Block 2-2 043 08/31/06 AA 1 Fuel storage block N/A N/A 56 ND ND 282 0 200 0 43 Block 3-1 043 08/31/06 AA I Fuel storage block N/A N/A 69 ND ND 289 0 200 4 1 Block 3-2 043 08/31/06 AA I Fuel storage block N/A N/A 0 ND ND 85 0 180 0 0 Block I Sides 043 08/31/06 AA I Fuel storage block N/A N/A 31 ND ND 92 0 180 0 47 Block 2 Sides 043 08/31/06 AA I Fuel storage block N/A N/A 24 ND ND 127 0 200 0 10 Block 3 Sides 111 09/27/06 AA I Shield block A 1 6 0 1 170 80 300 4 0 1 to ri-ht 111 09/27/06 AA 1 Shield block A 2 1 0 I 153 80 300 4 10 1 to left Ill 09/27/06 AA I Shield block A 3 6 0 1 375 80 400 0 91 1 bottom ri ht 11 09/27/06 AA I Shield block A 4 1 0 1 431 80 400 0 0 1 bottom leW1 ENERCON Service, or.

University of Washington More Hall Annex D&D, Project 10492 Attachment 6 -Sub-Unit 1-3-3 Fuel Storage Tubes FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 0 Final Status Decision Summary for Unit 1-3-3 (Fuel storage tubes -AO, Al)I1 I Location

Description:

IFuel storage tubes -AO, Al Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (gRlhr)Number of measurements:

270 108 270 108 54 Number of measurements needed " 9 9 9 9 N/A Maximum value of results: 85 13 3667 63 0 Mean value of results: 3 1 146 4 0 Standard Deviation of results: 11 3 564 11 0 Degree of Freedom (2) 1.653 1.661 1.653 1.661 1.675 p.a value: 4 2 202 6 0 Guideline level: 100 20 5000 1000 5 Are there sufficient measurements?

Yes Yes Yes Yes Yes Is the max value < guideline level? Yes Yes Yes Yes Yes Is ýta < guideline?

Yes Yes Yes Yes Yes Does survey unit pass? Yes Yes Yes Yes Yes (1) as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5 849 Table B-1 for the listed certainty

%ENERCON Services, inc.

FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 081 09/13/06 AA 1 Fuel Pits A0: 1-1 0 0 1 0 14 18 4 0 0 081 09/13/06 AA 1 Fuel Pits AO: 1-2 0 0 1 0 220 310 0 0 081 09/13/06 AA I Fuel Pits AO: 1-3 0 0 0 0 180 320 081 09/13/06 AA I Fuel Pits AO: 1-4 0 0 1 0 250 410 081 09/13/06 AA I Fuel Pits AO: 1-5 0 0 1 0 260 340 081 09/13/06 AA I Fuel Pits AO: 2-1 0 0 0 0 18 16 0 0 0 081 09/13/06 AA 1 Fuel Pits A0: 2-2 0 0 1 0 240 370 0 1 081 09/13/06 AA I Fuel Pits A :2-3 0 0 1 0 210 350 081 09/13/06 AA I Fuel Pits AO : 2-4 0 0 1 0 200 400 081 09/13/06 AA I Fuel Pits AO : 2-5 0 1 1 1389 180 460 081 09/13/06 AA 1 Fuel Pits A0:3-1 39 1 2 0 14 20 0 15 0 081 09/13/06 AA I Fuel Pits AO: 3-2 39 0 0 0 200 400 0 34 081 081 081 081 09/13/06 09/13/06 09/13/06 09/13/06 1 Fuel Pits AO: 3-3 0 0 0 0 Fuel Pits 1 Fuel AO: 3-4 A0:3-5 AO: 4-1 AO :4-2 39 0 0 39 0 0 0 0 AA l Fuel 0 T T 0 0-0 0-0-0 0 200 200 14 240 180 480 380 19 400 340 0 Fuel Pits 081 081 081 081 09/13/06 09/13/06 09/13/06 09/13/06 AA AO :4-2 0 0 1 Fuel Pits AO :4-4 AO :4-5 AO: 5-1 AO: 5-2 0 0 0 0 220 480 AA 01 0 0 1 0 010 0 0 T 0 0 0_0 0 260 140 200 200 440 18 460 380 AA 1 Fuel Pits 081 09/13/06 AA 1 Fuel Pits Fuel Pits Fuel Pits Fuel Pits AO: 5-3 0 0 AU: 5-4 A: 5-: 0 C T 0 0_0_0_0 0 0 0 06 722 0-0-0 220 240 14 200 400 480 21 380 AA AO:6-1 081 081 09/13/06 09/13/06 09/13/06 09/13/06 AA AA AAýAA T T T I Fuel Pits Fuel Pits Fuel Pits Fuel Pits AO: 6-2 0 0 AO: 6-2 AD 6-4 A0 :6-0 70 0-77-_0 0 0 0 1-0 0-0 0 0_0 0_0_0_0_0 0 260 2140T 200-14T i220 T220 480 560 440 30 420 500 081 081 081 081 081 081 081 081 09/13/06 09/13/06 09/13/06 09/13/06 09/13/06 09/13/06 09/13/06 09/13/06 AA AA AA AA AA AA AA AA I T I T I I I 1 T 1-1 I-UT8 081 081 081 081 081 082 U~l l i/US 09/13/06 09/13/06 09/13/06 09/13/06 AA AA AA AA AA-AA AA AA AT Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits AO:7-1 AO: 7-2 AO: 7-3 AO: 7-4 AO: 7-5 AM:8-1 AM0: 8-2 AO: 8-3 AýO : 8-4 A0 :.8-5 AO:9-1 AO: 9-2 AO: 9-3 AG :9-4 A0:9-5 BO: 1-t BO:I-2 B0:I-3 B0:1-4 0 0 0.0 0-0-0 0 0_0_0 0_0_0 0 0 0 0 0 0 0 0 o 0_0_0 0-0 0_0-0 0 0-0-0 0 1_0-1 0_0 0-0 0 0_0-0-0 0 0-0 0-0 260 120-iw--16-0 1-6 200 140-160-10 TWO 440 360 480 400 32 500 340 480 500 22 400 0 0 0 160 460 0 T 0 T 0 T T 180 420 13 0 15 0 0 0 0-0 I T 0 -0 I 082 09/13/06-1 39 1 2 350 17 .23 1 4 0 0-2 1 0 1 0 1. 0 1 2222 240 500 -0 o 0 1 University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-3 (Fuel storage tubes -AO, Al)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Cooed. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DP'M (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 082 09/13/06 AA 1 Fuel Pits B0: 2-3 0 0 0 0 200 560 082 09/13/06 AA I Fuel.Pits BO: 2-4 0 0 1 278 240 520 082 09/13/06 AA I Fuel Pits B0 : 2-5 0 0 0 0 200 480 082 09/13/06 AA I Fuel Pits BO: 3-1 0 0 1 50 10 26 0 0 0 082 09/13/06 AA I Fuel Pits B0: 3-2 0 0 0 0 260 600 0 0 082 09/13/06 AA I Fuel Pits B0: 3-3 0 0 1 0 240 460 082 09/13/06 AA 1 Fuel Pits O : 3-4 0 0 0 3667 160 580 082 09/13/06 AA I Fuel Pits B0 : 3-5 0 0 1 0 220 480 082 09/13/06 AA I Fuel Pits BO: 4-1 0 0 1 0 12 20 0 1 0 082 09/13/06 AA 1 Fuel Pits BO: 4-2 0 0 0 0 220 400 0 0 082 09/13/06 AA I Fuel Pits 80 : 4-3 0 0 1 0 180 480 082 09/13/06 AA I Fuel Pits B0: 4-4 0 1 1 0 160 480 082 09/13/06 AA I Fuel Pits Bt : 4-5 0 0 0 0 140 360 082 09/13/06 AA I Fuel Pits B0: 5-1 0 0 1 0 9 15 0 0 0 082 09/13/06 AA I Fuel Pits B0: 5-2 0 0 1 0 120 300 0 25 082 09/13/06 AA 1 Fuel Pits BO : 5-3 0 0 0 0 180 360 082 09/13/06 AA I Fuel Pits BO : 5-4 0 0 0 0 160 400 082 09/13/06 AA I Fuel Pits O : 5-5 0 0 0 1000 200 480 082 09/13/06 AA I Fuel Pits B0: 6-1 0 0 1 300 14 33 0 0 0 082 09/13/06 AA 1 Fuel Pits B0 : 6-2 0 0 0 0 200 420 0 0 082 09/13/06 AA I Fuel Pits BO: 6-3 0 0 0 0 240 460 082 09/13106 AA I Fuel Pits O : 6-4 0 0 1 111 180 480 082 09/13/06 AA I Fuel Pits BO : 6-5 0 0 0 0 240 460 Beta averaged via EAS 082 09/13/06 AA I Fuel Pits 80: 7-1 0 0 1 150 12 29 0 0 0 082 09/13/06 AA 1 Fuel Pits BO :7-2 0 0 1 0 180 480 0 0 082 09/13/06 AA 1 Fuel Pits BO :7-3 0 0 0 3444 220 520 082 09/13/06 AA I Fuel Pits BO: 7-4 1 0 0 0 0 200 500 082 09/13/06 AA I Fuel Pits BO: 7-5 0 0 0 0 180 460 082 09/13/06 AA 1 Fuel Pits BO: 8-1 0 0 1 0 14 30 0 0 0 082 09/13/06 AA I Fuel Pits l : 8-2 0 0 0 0 160 480 0 0 082 09/13/06 AA I Fuel Pits B : 8-3 0 0 0 00 20 520 082 09/13/06 AA I Fuel Pits l : 8-4 0 0 0 0 220 460 082 09/13/06 AA I Fuel Pits B0: 8-5 0 0 1 0 180 5400 082 09/13/06 AA I Fuel Pits BA: 9-1 39 0 1 250 10 28 11 0 082 09/13/06 AA 1 Fuel Pits B : 9-2 0 0 0 0 180 480 0 0 082 09/13/06 AA I Fuel Pits B : 9-3 0 0 1 0 200 440 082 09/13/06 AA I Fuel Pits BA : 9-4 0 0 0 0 240 460 082 09/13/06 AA I Fuel Pits BA: 9-5 0 0 1 0 200 500 083 09/13/06 AA I Fuel Pits Al :3-1 0 0 1 250 15 20 0 8 0 083 09/13/06 AA I Fuel Pits AI: -2 0 0 1 0 160 440 0 8 083 09/13/06 AA I Fuel Pits Al :3-3 l0 0 0 0 160 360 083 09/13/06 AA I Fuel Pits A : 1-4 0 0 1 0 180 460 083 09/13/06 AA I I Fuel Pits A [ 0 0 1 0 200 4001 083 09/13/06 AA 1 Fuel Pits At 2-1 0 0 1 0 10 22 0 0 0 083 09/13/06 AA I Fuel Pits Al : 2-2 0 0 1 0 240 460 0 0 083 09/13/06 AA I Fuel Pits A t : 2-3 0 0 0 0 160 310 083 09/13/06 AA I Fuel Pits At : 2-4 0 0 0 0 180 380"083 09/13/06 AA 1 Fuel Pits At : 0 0 0 0 180 400 083 09/13/06 AA I Fuel Pits Al : 3-1 39 0 1 0 16 22 0 0 0 083 09/13/06 AA I Fuel Pits T1 0 0 0 0 240 440 0 3 083 09/13/06 A At I Fuel Pits AI : 3-3 0 2 6 8 083 09/13/06 1AA I I Fuel Pits A l : 3-4I 0 1 0 0 180 360 ENERCON Sn'icea, inc.

FSS N Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Courd. Coord. Direct Scan MIn. Scan Max. Direct MIn. Max. Wipe Wipe DPM (cpm) (cpm) DPM (epm) (cpm) DPM DPM 083 09/13/06 AA I Fuel Pits Al :3-5 0 0 0 0 220 420 083 09/13/06 AA I Fuel Pits AI :4-1 0 0 0 0 12 20 0 0 0 083 09/13/06 AA I Fuel Pits At: 4-2 0 0 1 0 200 380 0 0 083 09/13/06 AA I Fuel Pits Al: 4-3 0 0 0 0 220 440 083 09/13/06 AA 1 Fuel Pits Al: 4-4 0 0 0 9 260 500 083 09/13/06 AA I Fuel Pits Al :4-5 0 0 0 0 240 480 083 09/13/06 AA t Fuel Pits Al :5-1 0 0 0 250 14 30 0 13 0 083 09/13/06 AA I Fuel Pits Al :5-2 0 0 0 0 200 420 0 63 083 09/13/06 AA I Fuel Pits Al : 5-3 0 0 1 0 160 380 083 09/13/06 AA I Fuel Pits At: 5-4 0 0 0 0 200 480 083 09/13/06 AA I Fuel Pits Al : 5-5 0 0 00 160 380 083 09/13/06 AA I Fuel Pits AI :6-1 0 0 I 1 t6 26 0 33 0 083 09/13/06 AA 083 09/13/06 A[083 09/13/06 A)I T Fuel Pits Fuel Pits Fuel Pits Fuel Pits Al :6-2 At :6-3 At :6-4 At : 6-5 0 0 0 0 200 440 0 0 0 0 1 0 160 380 0 0 1 0 1 0 220 420 083 09/13/06 AA 0 0 0 0 160 380 083 09/13/06 AA 083 09/13/06 083 [09/t3/06L I 1 I Fuel Pits Fuel Pits Fuel Pits Fuel Pits At: 7-I 0 0 1 0 0 0 At: 7-2 At :7-3 0 0 0 0 0 0 0 1 0 240 160 180 240 460 380 380 0 0 At : 7-4 083 09/13/06 AA I 1 Fuel Pits Fuel Pits Fuel Pits Fuel Pits At: 7-5 0 1 Al:8-1 At :8-2 AlX:8-3 Al1:8-4 0_0 0_0 0 0 0 0 0 T o 0 16 28 0 58 0 0 260 480 0 0 1 0 160 360 083 09113/06 AA 1 Fuel Pits 0 380 083 083 083 083 083 083 085 085 085 09/13/06 AA 09/13/06 AA 09/13/06 AA 09/13/06 AA 09/13/06 AA 09/13/06 AA 09/15/06 AA 09/15906 AA 09/15/06 AA 1~1~1 1 Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits At:8-5 0 0 0 I Fuel Pits I Fuel Pits I Fuel Pits At :9-1 Al :9-2 Al :9-4 Al :9-5 BI :-2 BI :1-2 BI1:--3 BI:1-4 BI:I-5-0_0 0 0 0-0 0 0 0 0 0 1 0 1 0 0 0 5ý6-0 0 0 0 0 0 0 0 T 0 T 0 0 0-0 0-0 0 0 250 0 085 09/15/06 085 09/15/06 085 085 09/15/06 AA 09/15/06 AA I 1 I I 1 I I T T Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits 11 160 160 200 240 11 200 t180 200 160 13 220 240 260 220 10 220 28 380 340 400 420 27 481 440 400 380 21 460 500 540 480 22 500 0-0 0 0 0-ii 0 0 7 0 18 0 0 0 06-085 09/15/06 AA 085 09/15/06 AA B1:2-3 B1:2-4 B1:2-5 B11:3-1 B1:3-2 91:3-3 0_0 0 0-0 31 0 0 0 0 0 1-0-0 0 2389 2500 0 0 085 085 09/15/06 1 AA 09/15/06 09/15/06 09/15/06 09/15/06 AA AA AA:3-51 1 0 L 0 1 0 1 0 2611 180 1 460 1 1 0 1 1 0 1 10 1 31 1 4 1 8 0 FSS N Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. CooNd. Direct Scan MIn. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 085 09/15106 AA I Fuel Pits B1 : 5-2 0 0 I 0 200 340 0 0 085 09/15/06 AA 1 Fuel Pits BI :5-3 0 0 0 0 160 380 085 085 085 085 09/15/06 AA I T T T I Fuel Pits BI :5-4 0 0 0 0 240 420 Fuel Pits Fuel Pits Fuel Pits Fuel Pits BI:5-5 BiN: 6-1 BI :6-2 5I: 6-3 0-0 0 0 0 0 0 0 200 460 0 0 09/15/06 FAA 1 944 085 09/15/06 1 AA 0 0 10 160 220 T6 0 22 360 380 420 it 0 085 09/15/06 1 AA I 085 09/15/06 AA I 085 09/15/06 AA Fuel Pits Fuel Pits Fuel Pits Fuel Pits BI :6-4 B1-6-5 Hi :7-1 Bi:7-2 0-0 0 0 0 0 0 0 T 0 0 1 280 160 2F600 540 17 360 500 1 085 09/15/06 1 AA 6 085 l 09/15/06 AA 085 085 085 085 085 085 085 085 086 086 086 086 086 086 086 086 086 09/15/06 AA 09/15/06 AA 09/15/06 AA 09/15/06 AA 09/15/06 AA 09/15/06 AA 09/15/06 AA 09/15/06 AA 09/15/06 AA 09/15/06 AA 09/15/06 AA 09/15/06 AA 09/15/06 AA 09/15/06 AA 09/15/06 AA 09/15/06 AA 09/15/06 AA I 1 T T T I I T T I T T T I T I T T T Fuel Pits BI :7-3 Fuel Pits Fuel Pits Fuel PNs Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits BI :7-4 Ni-:7-5 BI : 8-1 BI :8-2 BI: 8-3 BI :8-4 BI :8-5 BI: 9-1 B1: 9-2 BI : 9-3 BI 9-4 BI : 9-5 A2: 1-1 A2: I-2 A2 1-3 A2: -4 A2: 1-5 A2 : 2-1 A2 : 2-2 A2:2-3-A2:2-4 A2 :2-5 A2: 3-1 A2: 3-2 A2 : 3-3 A2 :34 A2 : 3-5 A2 :4-1 0 0 0 0 0 0 0 31 0 0 0 0 0 0 0 0 0 0 0_0 0-0 0 0 0 0 0 0 0 0 0 0 0 0 0 T--6-0 0 0 0-6-0 0 0-6-0-?F 0 0_0_0 0-0 0 0 0 0 0 0 0 180 0 0-1 1 0 1 1 7i 0 0 0 0 0 0 0 0 0_0 160-9 160 180 T6-0 200 110 160 240 14 1F40-0 400 0 0 360 14 400 360 440 380 23 400 480 460 500 28 420 0 0 0 0 0 0-0 1 0 0 200 480 0 0 220 520 0 1 0 1 220 520 1__086 109/15/06 AA I I ]Fuel Pits 086 09/t5/06 AA I Fuel Pits 086 09/15/06 AA i Fuel Pits 086 09/15/06 LA.A i Fuel Pits 0 1-1 1 0 0 t_0-1 0-1 0 0 0 244, 033 0 0 08S-0 0_0 13 140 180 220 260 12 160 200 160 140 14 20 380 420 400 30 3-80-440 2 6-0 0 0 49 0 0 0 0-0 086 09/15/06 1 AA I t 086 09/15/06 AA 086 09/15/06 [ AA i 086 09/15/06 AA I Fuel Pits Fuel Pits Fuel Pits Fuel Pits Fuel Pits Beta aversaed via EAS 0 0 086 09/15/06 AA 086 09/15/06 AA 086 09/15/06 AA 086 09/15/06 AA 086 09/15/06 A.A 086 09/15/06 AA 086 09/15/06 AA University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-3 (Fuel storage tubes -AO, Al)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 086 09/15/06 AA I Fuel Pits A2; 6-4 0 0 0 0 160 340 086 09/15/06 AA I Fuel Pits A2: 6-5 0 0 1 0 220 480 086 09/15/06 AA I Fuel Pits A2 :7-1 31 1 1 0 13 28 0 0 0 086 09/15/06 AA 1 Fuel Pits A2: 7-2 0 0 1 278 200 440 4 0 086 09/15/06 AA 1 Fuel Pits A2 :7-3 0 0 1 0 180 480 086 09/15/06 AA 1 Fuel Pits A2: 7-4 0 0 0 0 220 400 086 09/15/06 AA I Fuel Pits A2 :7-5 0 0 I 167 140 380 086 09/15/06 AA I Fuel Pits A2 : 0-1 0 0 1 0 13 26 0 17 0 086 09/15/06 AA I Fuel Pits A2 : 8-2 0 1 2 0 220 480 8 0 Alpha Averaged via EAS 086 09/15/06 AA 1 Fuel Pits A2 : 8-3 0 0 1 0 240 460 086 09/15/06 AA I Fuel Pits A2: 8-4 0 0 I 0 180 400 086 09/15/06 AA 1 Fuel Pits A2 :8-5 0 0 0 0 180 340 086 09/15/06 AA I Fuel Pits A2 :9-1 _ 0 0 1 0 14 41 4 0 0 086 09/15/06 AA I Fuel Pits A2 : 9-2 0 0 1 0 160 380 0 0 086 09/15/06 AA I Fuel Pits A2 : 9-3 0 1 1 0 200 480 086 09/15/06 AA 1 Fuel Pits A2 : 9-4 0 1 1 0 220 420 086 09/15/06 AA I Fuel Pits A2 : 9-5 0 0 1 0 200 440 091 09/18/06 AA I Fuel Pits B2: 1-1 0 0 0 0 12 20 0 0 0 091 09/18/06 AA I Fuel Pits B2 : 1-2 0 0 0 0 140 360 8 0 091 09/18/06 AA I I Fuel Pits B2: 1-3 8 0 1 0 180 420 091 09/18/06 AA I Fuel Pits B2 : 1-4 0 0 0 0 200 400 091 109/18/06 AA 1 Fuel Pits B2 : 1-51 8

• 0 1 1 0 16ý0- 440 091 09/18/06 AAý I Fuel Pits B2 : 2-11 0 0 0 0 6 15 0 0 0 091 09/18/06 AAt I Fuel Pits .B2 : 2-21 a 0 1 0 180 460 8 0 091 09/18/06 AA I Fuel Pits B2 : 2-31 0 0 0 0 160 340 091 09/18/06 AA I Fuel Pits B2 : 2-4 8 0 1 0 1 240 460 091 09/18/06 AA 1 Fuel Pits B2 : 2-5 0 0 0 0 220 540 091 09/18/06 AA 1 Fuel Pits B2 : 3-1 8 0 1 0 9 29 0 0 0 091 09/18/06 AA I 1 Fuel Pits B2 : 3-2 0 0 0 0 200 400 0 0 091 09/18/06 AA I I Fuel Pits B2 : 3-3 1 0 0 0 0 240 460 -091 109118/06 AA I1 Fuel Pits B2 : 3-4 1 8 0 1 0 200 440 091 109/18/06 AA I IFuel Pits B2 : 3-5 1 8 0 1 1000 180 420 091 09/18/06 AX 1 I-FuelPits B2:4-1 0 0 0 0 8 19 4 0 0 091 09/18/06 AA I1 Fuel Pits B2 :4-2 8 0 I 0 160 1_460 8 0 091 09/18/06 AA I Fuel Pits B2:4-3 8 0 I .0 1 180 360 091 09/18/06 AA I Fuel Pits B2 : 4-4 0 0 0 0 200 440 091 09/18/06 AA 1 Fuel Pits B2 : 4-5 8 0 1 0 160 L80 091 09/18/06 AA I Fuel Pits B2 : 5-1 8 0 1 420 20 32 0 o o 091 09/18/06 AA I Fuel Pits B2g :-2 8 0 1 0 160 380 0 0 091 109/18/06 AA I Fuel Pits B2:5_318 1 0 200 1 360 091 09/18/06 AA I Fuel Pits B2: 5-4 0 0 0 0 240 1 480 091 Fuel Pits Fuel Pits Fuel Pits Fuel Pits 091 09/18/06 1AA B2: 5-5 B2: 6-1 B2 : 6-2 B2: 6-3 B2: 6-4 0 0 0 3167 1 0 0 0 0 0 0 0 9 24 0 0 180 340 091 1 09/18/06 1 AA 1_0-1 0 0 0_0 0 220 160 160 240 480 1 4 0 091 09/18/06 1 AA 091 ((I T 1 T Fuel Pits 8 Fuel Pits 091 Fuel Pits B2: 6-5 B2:7-1 B2 :7-2 B2 : 7-3 0 0 85 8 0 520 0 0 091 09/18/06 1 AA Fuel Pits 1 ] I 0-0 0_0 14 180 160 T8-0 27 400 380 340 4 0 0 091 1 09/18/06 AA 1 Fuel Pits 0 AA I Fuel Pits B2: 74 8 0 AA 1 I Fuel Pits B2 : 7-51 19 11i 21 0 240 1 460 I t TAlptha Averaged via EAS ENERCON Servises, ine.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-3 (Fuel storage tubes -AO, Al)FSS# Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net VR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 091 09/18/06 AA I Fuel Pits B2 :8-1 0 0 0 0 11 33 0 0 0 091 09/18/06 AA 1 Fuel Pits B2: 8-2 8 0 1 0 224 440 0 0 091 09/18/06 AA I Fuel Pits B2: 8-3 9 1 2 111 260 520 Alpha Averaged via EAS 091 09/18/06 AA 1 Fuel Pits B2 : 8-4 85 0 1 0 200 380 091 09/18/06 AA 1 Fuei Pits 12: 8-5 0 0 0 0 220 400 091 09/18/06 AA 1 Fuel Pits B2: 9-I 0 0 0 0 12 26 4 0 0 091 09/18/06 AA I Fuel Pits B2: 9-2 8 0 1 0 180 360 0 0 091 09/18/06 AA 1 Fuel Pits B2: 9-3 0 0 0 0 160 380 091 09/18/06 AA 1 Fuel Pits B2 : 9-4 8 0 I 0 220 420 091 09/18/06 AA I Fuel Pits B2: 9-5 8 0 1 0 240 500 ENERCON Sevices, inc.

A25 A2-9 Al-E 1 1 9 E E 1AV2 Al5 1 812- B F 818 Al1l Ai-4 A1 -l 81- 1-l7, I~ D- -_7-.4 N r_Individual Fuel Storage Tube UNIVERSITY OF WASHINGTON NUCLEAR REACTOR DECOMMISSIONING FUEL STORAGE PIT LAYOUT SURVEY UNIT 1-3 University of Washington More Hall Annex D&D, Project 10492 Attachment 7 -Fuel Storage Pit Liquid Scintillation Analytical Results UW-MCP-OP-13, Rev. 2 Fuel Storage Pit Liquid Scintillation Results Background Gross Net Location Date DPM DPM DPM Fuel Storage Pit -A0-1 9/14/2006 42 50 8 Fuel Storage Pit -AO-2 9/14/2006 42 49 7 Fuel Storage Pit -AO-3 9/14/2006 42 44 2 Fuel Storage Pit -A0-4 9/14/2006 42 45 3 Fuel Storage Pit -A0-5 9/14/2006 42 59 17 Fuel Storage Pit -A0-6 9/14/2006 42 35 0 Fuel Storage Pit -AO-7 9/14/2006 42 54 12 Fuel Storage Pit -AO-8 9/14/2006 42 52 10 Fuel Storage Pit -AO-9 9/14/2006 42 61 19 Fuel Storage Pit -Al-i 9/14/2006 42 56 14 Fuel Storage Pit -Al-2 9/14/2006 42 40 0 Fuel Storage Pit -A1-3 9/14/2006 42 58 16 Fuel Storage Pit -Al-4 9/14/2006 42 42 0 Fuel Storage Pit -A1-5 9/14/2006 42 37 0 Fuel Storage Pit -A1-6 9/14/2006 42 43 1 Fuel Storage Pit -A1-7 9/14/2006 42 59 17 Fuel Storage Pit -A1-8 9/14/2006 42 34 0 Fuel Storage Pit -AI-9 9/14/2006 42 42 0 Fuel Storage Pit -A2-1 9/14/2006 42 38 0 Fuel Storage Pit -A2-2 9/14/2006 42 53 11 Fuel Storage Pit -A2-3 9/14/2006 42 44 2 Fuel Storage Pit -A2-4 9/14/2006 42 62 20 Fuel Storage Pit -A2-5 9/14/2006 42 57 15 Fuel Storage Pit -A2-6 9/14/2006 42 41 0 Fuel Storage Pit -A2-7 9/14/2006 42 58 16 Fuel Storage Pit -A2-8 9/14/2006 42 54 12 Fuel Storage Pit -A2-9 9/14/2006 42 45 3 Fuel Storage Pit -BO-1 9/14/2006 42 59 17 Fuel Storage Pit -BO-2 9/14/2006 42 51 9 Fuel Storage Pit -BO-3 9/14/2006 42 66 24 Fuel Storage Pit -B04 9/14/2006 42 54 12 Fuel Storage Pit -BO-5 9/14/2006 42 47 5 Fuel Storage Pit -BO-6 9/14/2006 42 57 15 Fuel Storage Pit -BO-7 9/14/2006 42 50 8 Fuel Storage Pit -BO-8 9/14/2006 42 42 0 Fuel Storage Pit -BO-9 9/14/2006 42 26 0 Fuel Storage Pit -B1-1 9/14/2006 42 66 24 Fuel Storage Pit -B1-2 9/14/2006 42 49 7 Fuel Storage Pit -B1-3 9/14/2006 42 39 0 Fuel Storage Pit -B1-4 9/14/2006 42 56 14 Fuel Storage Pit -BI-5 9/14/2006 42 50 8 Fuel Storage Pit -B1-6 9/14/2006 42 35 0 Page 1 of 2 Fuel Storage Pit Liquid Scintillation Results Background Gross Net Location Date DPM DPM DPM Fuel Storage Pit -B1-7 9/14/2006 42 46 4 Fuel Storage Pit -Bl-8 9/14/2006 42 44 2 Fuel Storage Pit -B1-9 9/14/2006 42 60 18 Fuel Storage Pit -B2-1 9/14/2006 42 49 7 Fuel Storage Pit -B2-2 9/14/2006 42 45 3 Fuel Storage Pit -B2-3 9/14/2006 42 53 11 Fuel Storage Pit -B2-4 9/14/2006 42 49 7 Fuel Storage Pit -B2-5 9/14/2006 42 51 9 Fuel Storage Pit -B2-6 9/14/2006 42 51 9 Fuel Storage Pit -B2-7 9/14/2006 42 40 0 Fuel Storage Pit -B2-8 9/14/2006 42 55 13 Fuel Storage Pit -B2-9 9/14/2006 42 47 5 Page 2 of 2 University of Washington More Hall Annex D&D, Project 10492 Attachment 8 -Sub-Unit 1-3-7 Reactor Room North Wall 0 To 4-m FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2

• Final Status Decision Summary for Unit 1-3-7 (Reactor room north wall 0 to 4-m)I Location

Description:

IReactor room north wall 0 to 4-m I I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/lOOcm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (j+/-R/hr)Number of measurements:

55 55 55 55 N/A Number of measurements needed (1): 9 9 9 9 N/A Maximum value of results: 29 8 220 91 N/A Mean value of results: 7 1 100 23 N/A Standard Deviation of results: 8 2 60 25 N/A Degree of Freedom (2): 1.674 1.674 1.674 1.674 N/A 4 value: 9 1 113 28 N/A Guideline level: 100 20 5000 1000 N/A Are there sufficient measurements?

Yes Yes Yes Yes N/A Is the max value < guideline level? Yes Yes Yes Yes N/A Is p, < guideline?

Yes Yes Yes Yes N/A Does survey unit pass? Yes Yes Yes Yes N/A (1) as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

0 University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-7 (Reactor room north wall 0 to 4-m)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct MIn. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 095 09/20/06 AA I N Wall L 0 0 0 0 120 150 250 0 0 095 09/20/06 AA I N Wall M 0 0 0 1 147 120 200 0 0 095 09/20/06 AA I N Wall N 0 0 0 0 158 too 200 0 1 095 09/20/06 AA I N Wall L T 0 0 1 162 100 180 0 86 095 09/20/06 AA 1 N Wall M 1 3 0 1 182 100 220 0 11 095 09/20/06 AA I N Wall N I 22 1 1 165 120 240 0 36 095 09/20/06 AA I N Wall L 2 8 0 1 131 100 200 0 21 095 09/20/06 AA 1 N Wall M 1 2 0 1 0 0 136 t00 260 0 11 095 09/20/06 AA I N Wall N ]2 0 1 0 0 123 100 200 0 41 095 09/20/06 095 09/20/06 095 09/20/06 095 09/20/06 AA I I IN Wall LI 31 3 0 173 100 1 220 0 71 AA I IN Wall M 3 3 AA a AA 3 0 0 0 0 0 1 1 76 1 100 200 0 1 0 114 1 120 200 1 0 21 1 095 109/20/06 1 AA I IN Wall M 4 18 1 095 09/20/06 AA I N Wall 095 09/20/06 AA 1 N Wall 095 09/20/06 AA I N Wall 095 09/20/06 AA I N Wall N 14 3 1 0 1 80 1 180 1 0 1 66 K 0 K I K 2 1 3 0 22 3 3 0 1 0 0 1 2-1 1 165 175 147 164 100 120 140 240 0 26 200 0 41 110 0 6 240 0 91 1 095 09/20/06 AA I N Wall 095 09/20/06 AA I N Wall 095 09/20/06 AA I I IN Wall 095 09/20/06 AA 1 N Wall 1'3 3 4 4 095 1 09/20/06 1 AA I N Wall J 1 N1 Wall K 4 0 8 3 0 T-0-0 6 0 0 1-2 1IN We Wal 098 09/21/06 AA 098 09/21/06 AA 098 09/21/06 AA 098 09/21/06 AA 098 09/21/06 AA 1 N Wall 0 0 0 0 0 0 0 0 127 100 280 0 36 240 0 21 240 0 26 1 0 0 80 1 140 1 0 1 21 1 643 100 1 160_ 1__ 0 1___41____1___1_

0 1 36 1100 1610 014 11 1 _~_ __ _ _80 160 1 0 1 41 I N Wall A 1 2 1 N Wall B 0 B 1 B 2 C 0 C 11 AA I I N Wall 11 20 6 15 11 1 0 1 1-2-1 098 09/21/06 AA 098 09/21/06 AA 098 09/21/06 AA 098 09/21/06 AA.I N Vall 1 N Vall 1 N Wall I N Wall 0 0 05 0 I 1 106 136 143 51 51-142-162 153 160 99 108 129 69 84 135 22308 120 1 200 4 36 120 240 0 11 D [ 6 DP 2 11 098 09/21/06 AA 1 N all 098 09/21/06 AA I N Wall 098 09/21/06 AA I N Wall E 0 E 1 E 2 A 3 2 0 0-0 0 0 0 0 1 t-I 0 1 1 2 1 120 1O00 T220 100 80 140o-160 098 09/21/06 AA 098 09/21/06 AA 098 09/21/06 AA I 1 N Wall C D 3 A 1 4 B 1 4 098 109/21/061 AA I I IN Wall 2 2-i4-i 2 2 11 15 11 6-29 2 11 0 1 200 0 11 180 0 0 240 0 6 180 0 0 200 0 0 220 6 0 0 240 0 0 180 0 46 220 4 36 220 8 51 098 09/21/06 A/_________

C_________

D___________

E F 4 4 3 3 0 0 0 0 0 2-1 41 100 30 I 80 0 80 140 78 140 220 143 100 240 4 1 1 .098 098 098 098 09/21/06 AA 09/21/06 AA 09/21/6 AA 09/21/06 AA 1 T I N Wall I N Wall 1 N Wall G 1 3 E 4 29 2 3 90 140 240 1 4 36 F 4 29 1 3 0 120 200 4 36 ENERCON Se-ixes, ia.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-7 (Reactor room north wall 0 to 4-m)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta BetaScan BetaScan Alpha Beta Net Ipn Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 098 09/21/06 AA I N Wall G 4 15 0 1 82 140 220 4 0 140 10/02/06 AA I N Wall H 3 11 0 2 0 100 180 0 65 North Wall Reactor Room 140 10/02/06 AA I N Wall H 4 0 0 2 0 100 200 0 0 North Wall Reactor Room ENERCON Services, in.

University of Washington More Hall Annex D&D, Project 10492 Attachment 9 -Sub-Unit 1-3-8 Reactor Room North Wall 5 To 9-m FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-3-8 (Reactor room north wall 5 to 9-m)I Location

Description:

IReactor room north wall 5 to 9-m I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpmi/100cm ) (dpmlOOcim) (dpm100cm 2) (PgR/hr)Number of measurements:

67 67 67 67 N/A Number of measurements needed (1)" 9 9 9 9 N/A Maximum value of results: 58 12 255 122 N/A Mean value of results: 18 1 113 30 N/A Standard Deviation of results: 17 2 71 28 N/A Degree of Freedom (2): 1.670 1.670 1.670 1.670 N/A value: 21 1 128 35 N/A Guideline level: 100 20 5000 1000 N/A Are there sufficient measurements?

Yes Yes Yes Yes N/A Is the max value < guideline level? Yes Yes Yes Yes N/A Is lta < guideline?

Yes Yes Yes Yes N/A Does survey unit pass? Yes Yes Yes Yes N/A as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

... ....................... ... --..... ....FSS # I Date I Class Floor Comments Wipe DPM 8 1 095 09/20/06 095 09/20/06 AA I IN Wall 0 1 54 120 220 0 66 AA I I INWall L 6 3 0 1 095 M-iT L M 6 7-7 8 8 13 8 1 1 21 0 151f 1 100 240 0 6 1 4-095 1 09/20/06 1 AA I I IN Wall 0 I 095 1 09/20/06 1 AA 1 I IN Wall N 7 8 1 1 095 1 09/20/06 1 AA I I N Wall'ail A/'all L W-L Mf 8 3 0 I 8 1 0 0 1 8 0 01-1 095 1 09/20/06 1 AA I I IN Wall 9-9 0 3 0 0 1 T 158-78-123 56-92 0 39-0 100 120 095 095 095 095 140 09/20/06 1 AA I I IN Wall (I N Na1 9N19 0 0 .1 I 1 NWall 1 1 5 1 0 1 0 l 09/20/061 AA I I IN Wall J K-1 5 5-6 095 09/20/06 1AA I I IN Wall AA AA N Wal 4 Wal 095 095 095 095 095 095 095 098 09/20/06 AA I N Wall 09/20/06 AA I N Wall 09/20/06 AA 1 N Wall 09/20/06 AA 1 N Wall 09/20/06 AA 1 N Wall 1-T-J B iT-1-K 1 J K A B C D 7 7 T 8 8 8 9 0 37-27 27 18 13-13-0 8 is 3 8 2 1 2 0 2 2 1-2-3 1-1 1 0 1 0 0 1 0 0 1-1-0-0-1 1 T 2 1 1 2 1 1 T T 1 0 2 T o-2 28 131 158 178 114 145 118 85 167 140 112 132 0 4 120 140 160 120 80 140 120 140 120 100 120 140 160 100 120 120 260 180 .220 200 240 240 180 140 200 220 260 180 200 240 220 280 200 200 180 160 240 0 0-0 0 0 0 51 16 26 0 0 86 11 122 0-5 0 76 0 41 0 6 0 36 0 36 0 86 0 56 0 0 0 26 7 36 0 0 090 09/21/06 AA 1 N Wall 090 09/21/06 AA I N Wall 5 2 1 0 5 15 5 20 6 2 0 4 6 AA 100 098 09/21/06 AA IN Wall 090 09/21/061 AA I I N Wall 6-6 6-5 0 49 120 220 99 [140 260 U uvt 0 1 4 0 100 109/22/06 AA I I IN Wall 100 09/22/06 1AA I I N Wall 161 120 [ 200 1 0 0____ ____ __ ________ 4 J-~-4 4 4-L ing, grids A9, B9, C9 are not present ing, grids A9, B9, C9 are not present ing, grids A9, B9, C9 ate not present ing, grids A9, B9, C9 are not present ing, grids A9, B9, C9 are no t present ing, grids A9, B9, C9 are not present ing, grids A9, 89, C9 are not present ing, grids A9, B9, C9 are not present 8 1 39 1 2 8 1 5 0 0 University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-8 (Reactor room north wall 5 to 9-mn)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta BetaScan BetaScan Alpha Beta Net PR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cps) (cpm) DPM (cpm) (epm) DPM DPM 100 09/22/06 AA I N Wall 0 8 29 1 2 152 140 200 0 54 Due to sloping ceiling, grids A9, B9, C9 are not present 100 09/22106 AA i N Wall H 8 39 1 2 199 120 240 0 0 Due to sloping ceiling, grids A9, B9, C9 are not present 100 09/22/06 AA I N Wall E 9 5 0 1 140 80 160 12 0 Due to sloping ceiling, grids A9, B9, C9 are not present 100 09/22/06 AA I N Wall F 9 44 1 2 225 120 200 0 0 Due to sloping ceiling, grids A9, B9, C9 are Lint present 100 09/22/06 AA I N Wall G 9 34 1 2 231 140 200 0 0 Due to sloping ceiling, grids A9, B9, C9 are not present 100 09/22/06 AA I N Wall H 9 29 1 1 16 100 160 0 79 _ Due to sloping ceiling, grids A9, B9, C9 are sot present 100 09/22/06 AA I N Wall A 7 44 1 2 161 140 220 0 0 Due to sloping ceiling, grids A9, B9, C9 are not present 100 09/22/06 AA I N Wall B 7 44 2 3 118 100 180 0 54 Due to sloping ceiling, grids A9, B9, C9 are n0t present 100 09/22/06 AA I N Wall C 7 5 0 1 140 120 200 0 0 Due to sloping ceiling, grids A9, B9, C9 are not present 100 09/22/06 AA I N Wall D 7 24 1 2 159 120 220 0 24 Due to sloping ceiling, grids A9, B9, C9 are not present 100 09/22/06 AA I N Wall A 8 49 2 4 195 140 260 0 44 Due to sloping ceiling, grids A9, B9, C9 are not present 100 09/22/06 AA I -N Wall B -39 2 3 202 120 260 0 0 Due to sloping ceiling, grids A9, B9, C9 are not present 100 09/22/06 AA I N Wall C 8 39 2 2 169 100 240 0 24 Due to sloping ceiling, grids A9, B9, C9 are not present 100 09/22/06 AA 1 N Wall D 8 39 1 2 155 120 200 0 0 Due to sloping ceiling, grids A9, B9, C9 are not present 100 09/22/06 AA I N Wall D 9 44 2 3 253 160 260 4 0 _ Due to sloping ceiling, grids A9, B9, C9 are not present ENERCON Servires, i.u.

University of Washington More Hall Annex D&D, Project 10492 Attachment 10 -Sub-Unit 1-3-9 Reactor Room South Wall 0 To 4-m FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-3-9 (Reactor room south wall 0 to 4-m)I Location

Description:

Reactor room south wall 0 to 4-r Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cmZ) (qR/hr)Number of measurements:

58 60 58 60 N/A Number of measurements needed (1): 9 9 9 9 N/A Maximum value of results: 71 13 1228 78 N/A Mean value of results: 25 2 .175 17 N/A Standard Deviation of results: 20 3 211 22 N/A Degree of Freedom (2): 1.672 1.671 1.672 1.671 N/A li,, value: 29 2 222 22 N/A Guideline level: 100 20 5000 1000 N/A Are there sufficient measurements?

Yes Yes Yes Yes N/A Is the max value < guideline level? Yes Yes Yes Yes N/A Is [.t, < guideline?

Yes Yes Yes Yes N/A Does survey unit pass? Yes Yes Yes Yes N/A (I) as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5 849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-9 (Reactor room south wall 0 to 4-in)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta BetaScan BetaScan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Mn. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DP'M 054 08/30/06 GA I Pipe A 28 88 144 4 23 Survey ofmain drainline (1.5") left in reactor room fl -2811 054 08/30/06 GA 1 Pipe A 0 88 144 0 9 Survey of main drainline (1.5") left it reactor room fl -2811 099 09/21/06 AA I S Wall A 0 16 0 2 165 40 320 0 42 099 09/21/06 AA I S Wall A I 16 0 1 195 40 400 0 0 099 09/21/06 AA I S Wall A 2 1 0 1 203 40 400 0 0 099 09/21/06 AA I S Wall B 0 6 0 1 276 40 400 4 19 Void Space 099 09/21/06 AA 1 S Wall B 1 11 0 2 209 40 380 0 19 1 099 09/21/06 AA 1 S Wall B 2 6 0 1 192 40 380 0 51 099 09/21/06 AA 1 S Wall C 0 11 0 1 126 40 310 0 0 Void Space 099 09/21/06 AA I S Well C 1 1 0 1 93 40 300 4 0 099 09/21/06 AA I S Wall C 2 16 0 1 42 40 300 0 0 099 09/21/06 AA I S Wall D 0 21 0 1 128 40 310 0 0 099 09/21/06 AA I S Wall D I 27 0 1 1228 40 480 0 0 099 09/21/06 AA I S Wall D 2 0 0 0 95 40 310 0 70 099 09/21/06 AA I S Wall E 0 32 0 2 86 40 310 0 0 099 09/21/06 AA S Wall E 1 11 0 1 120 40 310 1 0 14 099 09/21/06 AA 1 SWall E 2 1 0 1 126 40 310 0 0 Void Sp ace 099 09/21/06 AA I S Wall K 0 6 0 1 76 40 300 4 47 099 09/21/06 AA I S Wall K 1 52 0 3 234 40 400 4 42 099 09/21/06 AA I S Wall K 2 11 0 I 86 40 310 0 0 099 09/21/06 AA 1 S Wall 099 09/21/06 AA I S Wall 099 09/21/06 AA I S Wall 099 09/21/06 AA I S Wall L 0 32 0 153 40 320 0 0 Doorway___ __H 27 0 0 T 1 1 1090 1 40 1 500 0 1 0 M 0 Doorway Doorway 099 109/21/061 AA I 1 S Wall I M 1 16 107 40 310 0 0 099 099 09/22/06 AA I1 09/22/06 AA I 09/22/06 AA I 09/22/06 AA I S Wall M 1 2 1 20 0 1 153 1 40 320 0 1 13 S Wall N 0 10 099 S Wall [ N -1 0 0 0 0 1 122 40 40O 40 40ýO 310 0 1 0 099 S Wall NT 2 310 4 1 69 1 1CaePower Box 300 _0 1 0 1__ 1_____________________

300 1 0 1 31 1 1 099 09/22/06 1 AA 1 1 S Wall N 13 40 2 140 099 c C S Wall N 14 35 0 2 3 40 400 1 0 1 13 099 ISWall M 1 4 1 71 0 4 0 7 099 109/22/061 AA I S Wall LI 3 45 0 3 54 0 Voided snace 099 099 099 099 09/22/06 AA I S Wall 09/22/06 AA I S Wall 09/22/06 AA ! S Wall 09/22/06 AA 1 S Wall L 1 4 1 40 K 4 35 0 0 0 0 0 0_0 099 09/22/06 AA 1 S Wall 099 09/22/06 AA 1 S Wall 099 09/23/06 AA I S Wall 099 09/23/06 AA IS Wall J 13 55 7 1 099 09/23/06 AA I1 099 09/23/06 AA I 099 09/23/06 AA I 101 09/23/06 AA I 101 09/23/06 AA 1 101 09/23/06 AA 1 S Wall 1 3 65 2-1 3 2.-2-I-i~2 3 2-1-2 3 2 1 2 553 44 40 500 13 78 40 300 13 31 153 40 310 9 4 146 1 40 380 0 0 19 40 260 0 54 4 54 0 3 0 4 40 310 0 81 1] 40 [400 4I I 13 1__ _ _ _ _ _ _ _:1 so S Wall 1 1 2 65 0 06 120 1 40 r 300 S Wall H 1 4 S Wall S Wall§ Wall A 3 101 101 101 101 09/23/06 1 AA I S Wall I D 1 3 39 45 54 50 25 35 40 30 40 290 243 290 256 273 120 200 140 260 120 240 100 240 140 1 220 0 8 0 1 40 1 260 8 0 0 0 0 38 0 13 0 0 Due to sloping ceiling grids A9, B9, and C9 not present Due to sloping ceiling grids A9, B9, and C9 not present Due to sloping ceiling grids A9, B9, and C9 not present Due to sloping ceiling grids A9, B9, and C9 not present Due to sloping ceiling grids A9, B9, and C9 not present Due to sloping ceiling grids A9, B9, and C9 not present 09/23/06 AA 09/23/06 AA 09/23/06 AA 1 S Wall A C D5-4-4 4-4 0 1 1_0 180 1 80 1 180 0 0 187 100 160 [12 1 _18 tDue to sloping ceiling grids A9, B9, and C9 nuot present 144 80 1 180 0 33 IDue to sloping ceiling grids A9, B9. and C9 sot present 101 1 09/23/06 1 AA I IS Wall ENERCON Serices, ias.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-9 (Reactor room south wall 0 to 4-m)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comminents Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 107 09/25/06 AA 1 S Wall E 4 6 0 1 43 100 180 3 0 107 09/25/06 AA 1 S Wall F 4 1 0 1 0 80 140 0 0 1 107 09/25/06 AA I S WaII G 4 6 0 1 0 100 180 0 26 107 09/25/06 AA I S Wall E 3 6 0 1 155 120 240 0 46 107 09/25/06 AA I S Wall F 3 0 0 0 102 140 200 0 0 107 09/25/06 AA I S Wall G 3 1 0 1 186 140 220 3 31 107 09/25/06 AA I S Wall 11 3 6 1 1 140 120 260 0 62 107 09/25/06 AA 1 S Wall J 4 0 0 0 60 100 180 0 -1 ENERCON Serices, in-.

-1 0 0 0 CD (0 D9 Rising ceifing slope Begins 09 -N9 UNIVERSITY OF WASHINGTON NUCLEAR REACTOR DECOMMISSIONING REACTOR ROOM SOUTH WALL SURVEY UNIT 1-3 University of Washington More Hall Annex D&D, Project 10492 Attachment 11 -Sub-Unit 1-3-10 Reactor Room South Wall 5 To 9-m FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-3-10 (Reactor room south wall 5 to 9-m)I Location

Description:

IoReactor room south wall 5 to 9-m I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/lOOcm

2) (dpm/100cm

2) (dpm/100cm

2) (VR/hr)Number of measurements:

67 67 67 67 N/A Number of measurements needed (1): 9 9 .9 9 N/A Maximum value of results: 76 12 442 101 N/A Mean value of results: 37 1 168 21 N/A Standard Deviation of results: 19 3 104 25 N/A Degree of Freedom (2): 1.670 1.670 1.670 1.670 N/A p. value: 40 2 189 26 N/A Guideline level: 100 20 5000 1000 N/A Are there sufficient measurements?

Yes Yes Yes Yes N/A Is the max value < guideline level? Yes Yes Yes Yes N/A Is [t,, < guideline?

Yes Yes Yes. Yes N/A Does survey unit pass? Yes Yes Yes Yes N/A as interpolated from NUtREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-I for the listed certainty

%ENERCON Services, inc.

0 University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-10 (Reactor room south wall 5 to 9-m)FSS# Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan BetaScan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 099 09/22/06 AA I S Wall N 5 20 0 1 0 40 380 4 13 099 09/22/06 AA I S Wall N 6 45 0 3 83 40 380 0 0 099 09/22/06 AA I S Wall N 7 60 0 4 146 40 290 0 18 099 09/22/06 AA 1 S Wall M 7 35 0 2 52 40 250 0 0 099 09/22/06 AA I S Wall M 6 45 0 3 169 40 360 0 69 099 09/22/06 AA I S Wall M 5 30 0 2 0 40 360 0 101 099 09/22/06 AA 1 S Wall L 5 25 0 1 17 40 300 4 69 099 09/22/06 AA 1 S Wall L 6 40 0 1 0 40 300 0 4 099 09/22/06 AA I S Wall L 7 40 0 1 101 40 310 0 0 099 09/22/06 AA 1 S Wall K 7 76 0 3 77 40 300 4 73 099 09/22/06 AA 1 S Wall K 6 5 0 1 62 40 300 0 18 099 09/22/06 AA I S Wall K 5 20 0 l 73 40 300 9 59 099 09/23/06 AA 1 S Wall J 5 39 0 3 49 40 300 8 7 099 09/23/06 AA 1 S Wall J 6 33 0 2 442 40 490 0 26 099 09/23/06 AA 1 S Wall J 7 39 0 2 93 40 300 8 21 099 09/23/06 AA I S Wall 1 7 60 0 3 142 40 300 0 3 099 09/23/06 AA I S Wall 1 6 49 0 2 147 40 300 0 12 099 09/23/06 AA I S Wall 1 5 44 0 2 93 40 300 0 0 099 09/23/06 AA I S Wall H 5 49 0 2 34 40 300 0 3 099 09/23/06 AA I S Wall H 6 28 0 2 169 40 320 0 40 099 09/23/06 AA I S Well H 7 23 0 1 32 40 230 0 0 099 09/23/06 AA I S Wall G 7 70 0 3 151 40 330 0 0 099 09/23/06 AA I S Wall G 6 28 0 2 233 40 400 4 35 099 09/23/06 AA I S Wall G 5 65 0 3 0 40 200 0 68 101 09/23/06 AA I S Wall A 5 50 2 2 236 120 240 0 0 Due to sloping ceiling gridsA9, B9, and C9 not present l01 09/23/06 AA I S Wall B 5 30 1 1 139 80 140 8 28 Due to sloping ceiling grids A9, B9, and C9 not present 101 09/23/06 AA I S Wall C 5 45 0 2 154 100 140 0 18 Due to sloping ceiling grids A9, 89, and C9 not present 101 09/23/06 AA I S Wall D 5 11 0 0 170 120 200 12 53 Due to sloping ceiling grids A9, B9, and C9 not present 101 09/23/06 AA I S Wall A 6 54 2 3 217 140 260 4 3 Due to slopiug ceiling grids A9, B9, and C9 not present 101 09/23/06 AA I S Wall B -6 54 1 2 293 140 260 0 0 Due to sloping ceiling grids A9, B9, and C9 not present 101 09/23/06 AA 1 S Wall C 6 25 0 1 202 120 220 0 0 Due to sloping ceiling grids A9, B9, and C9 not present 101 09/23/06 AA I S Wall P 1 35 1 2 228 140 260 0 3 Due to sloping ceiling grids A9, B9, and C9 not present 101 09/23/06 AA I S Wall A 7 30 1 I 301 160 280 0 0 Due to sloping ceiling grids A9 139, and C9 not present 101 09/23/06 AA I S Wall B1 7 50 2 3 224 120 240 4 13 Due to sloping ceiling grids A9, B9, aud C9 not present 101 1 09/23/06 AA I S Wall l2! 09/23/06 AA I S Wall 101 09/23/06 AA 1 S Wall 101 1 09/23/06 AA I S Wall Cl 7 I 5 71 I tn Ifi a I -, 271 1 140 260 1 0 1 28.--- .......D 7 40 A 1 0 0 2 249 120 260 0 0 Due to sloping ceiling grids A9, B9, and C9 not present 228 B 256 140 120 100 140 260 0 46 Due to sloping ceiling grids A9, B9, and C9 not present 0) 1 3 101 09/23/06 101 09/23/06 101 09/23/06 11 09/23/06 AA I I ISWall 8 1 16 1 230 D I C ti-g a inn ai AA 1 S Wall AA IS Wall AA IllS Wall D 8 30 1 1 2 228 220 1 0 21 t!", 8 50 35 25 25 2 1 3 T 1 2 247 286 297 213 140 160 140 100 260 0 240 0 260 0 220 0 6 Due to sloping ceiling grids A9, B9, aid C9 not present 31 Due to slopitng ceiling grids A9, B9, and C9 not present 101 109/23/061 AA I I S Wall L 1 8 0 16 Due to sloping ceiling grids A9, 139, nad C9 notI 101 1 09/23/06 1 AA I I IS Wall N 19 0 26 Due to slopin2 ceilinp nrids A9. B9. and C9 not u M 9_________ -L T 50 45 59-59 2-2-2-3 3 224 140 240 1 0 a 0 -p g 0 "0 Due to.1 f3. t piinnordeAO Ino , r'o ..n 303 120 0 Due to sloping ceiling grids A9, B9, and C9 not present 101 1 09/23/06 1 AA I I IS Wall K 226 101 109/23/061 AA I I S Wall I J 8 3 223 0 0 101 1 09/23/061 AA I I IS Wall 1 1 8 1 54 1 2 2 1 342 160 1 280 1 0 1 21 Due to sloping ceiling grids A9, B9, and C9 not present Due to sloping ceiling grids A9, B9, and C9 nut present lt 101 101 09/23/06 AA I S Wall 09/23/06 AA 1 S Wall 09/23/06 AA 1 S Wall K 19 40 1 1 1 2 1 219 1 120 1 200 1 0 1 0 230 100 1 220 0 0 1 Due to sloping ceiling grids A9, B9, and C9 not present 258 1 140 1 240 1 0 1 6 1 IDue to sloping ceiling grids A9, B9, and C9 stot present ENERCON Services, inn.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-10 (Reactor room south wall 5 to 9-m)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta BetaScan BetaScan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 101 09/23/06 AA 1 S Wall i1 8 50 -1 2 273 140 260 0 31 Due to sloping ceiling grids A9, B9, and C9 not present 101 09/23/06 AA 1 S Wall G 8 30 0 2 254 100 220 0 0 Due to sloping ceiling grids A9, B9, and C9 not present 10t 09123/06 AA I S Wall F 8 35 1 2 273 120 240 0 21 Due to sloping ceiling grids A9, B9, and C9 not present 101 09/23/06 AA I S Wall H 9 64 3 4 286 160 260 3 46 Due to sloping ceiling grids A9, B9, and C9 not present 101 09/23/06 AA I S Wall a 9 69 3 4 237 100 220 0 62 Due to sloping ceiling grids A9, B9, and C9 not present 101 09/23/06 AA I S Wall F 9 59 2 3 284 120 240 3 36 Due to sloping ceiling grids A9, B9, and C9 not present 107 09125/06 AA I S Wall D 9 1 0 1 0 too 160 0 1 107 09/25/06 AA I S Wall E 9 15 1 1 0 80 180 3 0 107 09/25/06 AA I S Wall E 8 24 1 2 62 100 220 0 6 107 09/25/06 AA I S Wll E 7 1 0 1 11 120 240 0 1 107 09/25/06 AA I SWall F 7 1 0 1 84 140 220 0 0 107 09/25/06 AA I S Wall E 6 19 I 2 87 120 240 0 21 107 09/25/06 AA I S Wall F 6 10 0 I 170 160 280 0 52 107 09/25/06 AA 1 S Wall E 5 15 I 1 43 120 240 1 3 41 107 09/25/06 AA I SWall F 5 1 0 1 1 80 11.0 0 26 ENERCON Services, hi..

NO N9 Mo TT LO KO-n 0 0 J3 t 3 Ii ii LD CD H33' fT DO I CO BO B1 AO Al A2 A3 A4 A5 A6 A7 A8-D9 Rising ceiling slope Begins D9 -Ng Crane rail UNIVERSITY OF WASHINGTON NUCLEAR REACTOR DECOMMISSIONING REACTOR ROOM SOUTH WALL SURVEY UNIT 1-3 University of Washington More Hall Annex D&D, Project 10492 Attachment 12 Sub-Unit 1-3-11 Reactor Room West Ceiling Grids A-D Including Beams FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-3-11 (Reactor room west ceiling grids A-D including beams)I Location

Description:

IReactor room west ceiling grids A-D including beams I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) ( LR/hr)Number of measurements:

88 88 88 88 N/A Number of measurements needed (1: 9 9 9 9 N/A Maximum value of results: 32 4 266 53 N/A Mean value of results: 8 0 112 7 N/A Standard Deviation of results: 8 1 74 13 N/A Degree of Freedom (2): 1.665 1.665 1.665 1.665 N/A g value: 9 0 125 9 N/A Guideline level: 100 20 5000 1000 N/A Are there sufficient measurements?

Yes Yes Yes Yes N/A Is the max value < guideline level? Yes Yes Yes Yes N/A Is ýtý < guideline?

Yes Yes Yes Yes N/A Does survey unit pass? Yes Yes Yes Yes N/A () as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-11 (Reactor room west ceiling grids A-D including beams)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan BetaScan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DIM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 067 09/09/06 AA 1 Ceiling A 0 8 0 0 243 120 180 0 33 067 09/09/06 AA I Ceiling A 1 25 1 2 212 120 200 0 0 067 09/09/06 AA 1 Ceiling A 2 0 0 1 189 120 160 0 8 067 09/09/06 AA I Ceiling A 3 30 0 1 170 120 160 0 0 067 09/09/06 AA I Ceiling A 4 21 1 2 202 140 220 0 0 067 09/09/06 AA I Ceiling A 5 17 0 2 191 120 220 0 0 067 09/09/06 AA I Ceiling A 6 17 0 I 197 120 240 0 0 067 09/09/06 AA I Ceiling A 7 25 1 2 177 120 220 0 8 067 09/09/06 AA I Ceiling A 8 0 0 1 160 120 200 0 8 067 09/09/06 AA I Ceiling A 9 12 0 1 114 120 200 0 0 067 09/09/06 AA I Ceiling A 10 3 0 1 156 120 200 0 13 067 09/09/06 AA 1 Ceiling B 0 3 0 1 139 120 180 0 0 067 09/09/06 AA I Ceiling B 1 12 1 2 139 120 200 0 43 067 09/09/06 AA I Ceiling B 2 21 1 2 87 120 180 0 28 067 09/09/06 AA I Ceilin B 3 21 2 2 107 120 220 0 0 067 09/09/06 AA I Ceiling B 4 8 0 1 89 120 200 0 0 067 09/09/06 AA I Ceiling B 5 0 0 1 85 120 180 0 0 067 09/09/06 AA I Ceiling B 6 12 1 2 128 120 200 0 0 067 09/09/06 AA I Ceiling B 7 8 0 1 85 120 180 0 0 067 09/09/06 AA I Ceiling B 8 0 0 1 59 120 180 0 28 067 09/09/06 AA I Ceiling B 9 17 1 2 189 120 220 0 8 067 09/09/06 AA I Ceiling B 10 12 I 1 87 120 200 0 13 068 09/09/06 AA I Beam A 0 9 0 0 0 40 160 0 0 Concrete Ceiling Beams 068 09/09/06 AA I I eanm A I 0 0 1 2 40 220 3 3 1 Concrete Ceiling Beams 068 09/09/06 AA I Ream A 2 9 0 1 0 40 200 0 0 Concrete Ceiling Beams 068 09/09/06 AA I Beam A 3 13 0 1 21 40 240 0 0 Concrete Ceiling Beams 068 09/09/06 AA I Beam A 4 4 0 1 49 40 260 0 0 Concrete Ceiling Beams 068 09109106 AA 1 Beam A 5 13 0 1 11 40 220 0 53 Concrete Ceiling Beams 068 09/09/06 AA I Beamn A 6 9 0 1 0 40 190 0 0 Concrete Ceiling Beams 068 09/09/06 AA I Beam A 7 0 0 l 0 40 180 3 18 Concrete Ceiling Beams 068 09/09/06 AA 1 Beam A 8 0 0 1 0 40 180 0 38 Concrete Ceiling Beams 068 09109106 AA I Beam A 9 0 0 1 0 40 160 0 3 Concrete Ceiling Beams 068 09/09/06 AA I Beam A 10 0 0 1 0 40 220 0 13 Conerete Ceiling Beams 068 09/09/06 AA I Beam B 0 0 0 1 0 40 180 0 0 Concrete Ceiling Beams 068 09/09/06 AA I Beam B 1 -0 0 1 0 40 160 0 0 Concrete Ceiling Beams 068 09/09/06 AA I Bearn B 2 0 0 1 0 40 200 0 0 Concrete Ceiling Beams 068 09/09/06 AA 1 Beam B 3 0 0 1 0 40 200 0 8 Concrete Ceiling Beams 068 09/09/06 AA I Beam B 4 0 0 0 0 40 200 0 0 Cncrete Ceiling Beams 068 09/09/06 AA 1 Beam B 5 0 0 I 0 40 170 0 0 Concrete Ceiling Beams 068 09109/06 AA 1 Beam B 6 0 0 1 0 40 160 0 0 Concrete Ceiling Beanms 068 09/09/06 AA I Beam B 7 0 0 1 0 40 110 0 0 Concrete Ceiling Beams 068 09/09/06 AA 1 Benis B S 0 0 1 0 40 130 0 0 Cncrete Celing Beams 068 09/09/06 AA I Beam B 9 0 0 1 0 40 200 0 0 Concrete Ceiling Beams 068 09/09/06 AA I Beamn B 10 0 0 1 0 40 190 0 28 Concrete Ceiling Beams 069 09/09/06 AA I Ceiling C 0 0 0 1 116 100 200 0 53 069 09/09/06 AA I Ceiling C 1 5 0 2 94 100 200 0 7 069 09/09/06 AA I Ceiling C 2 0 ND ND 128 100 200 0 35 069 09/09/06 AA I Ceiling C 3 0 0 1 122 100 200 0 0 069 09/09/06 AA I Ceiling C 4 5 0 2 133 100 200 0 44 069 09/09/06 AA I Ceiling C 5 10 1 3 200 100 200 0 0 069 09/09/06 AA I Ceiling D 0 10 I 3 164 100 200 0 0 069 09/09/06 AA 1 Ceiling D I 5 0 2 141 100 200 0 21 ENERCON Servi-c, i.n.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-11 (Reactor room west ceiling grids A-D including beams)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net eR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpmn) (cpm) DPM (epmn) (cpm) DPM DPM 069 09/09/06 AA I Ceilina D 2 5 0 2 156 100 200 0 0 069 09/09/06 AA 1 Ceiting D 3 19 " 2 3 230 100 200 0 0 069 091091/06 AA I Ceiling D 4 0 ND ND 124 100 200 0 0 069 09/09/06 AA 1 Ceiling D 5 10 1 3 168 100 200 0 0 069 09/11/06 AA I Beam C 0 4 1 2 142 100 200 4 0 1Bams 069 09/09/06 AA I Iearn C 1 19 2 3 126 100 200 4 0 Beams 0691 09/09/06 AA 1 CBeam C 2 0 N N1 115 100 200 0 0 Beams 0691 09/09/06 AA I Beam C .3 9 2 3 75 100 200 0 0 Beams 069 09/09/06 AA I Beam C 4 10 1 3 145 100 200 0 0 Beams 069 09/091/06 AA I Beam C 5 19 2 3N 171 120 200 0 2 Beams 071 09/11/06 AA 1 Ceiling C 6 32 4 8 155 100 200 0 21 071 09/11/06 AA I Ceiling C 7 9 1 3 180 100 220 0 0 071 09/11/06 AA I Ceiling C 8 4 0 2 142 100 200 0 16 B 071 09/11/06 AA I Ceiling C 9 109 2 3 127 100 200 0 0 071 09/11/06 AA I Ceiling C 10 0 ND ND 266 180 200 0 0 071 09/11/06 AA I Ceilina D 9 1 3 197 100 200 0 0 071 09/11/06 AA I Ceaming D 7 0 0 1 167 100 220 0 0 071 09/11/06 AA 1 Ceiling D .8 0 ND ND 157 [20 200 0 0 071 09/11/06 AA I Ceiling D 9 9 2 3 125 100 180 0 0 071 09/11/06 AA I Ceiling D 10 13 2 3 146 100 200 0 0 071 09/11/06 AA I Beam C 6 4 0 2 238 100 200 0 0 Beams 071 09/14/06 AA I Beam C 7 18 2 4 185 100 200 0 0 Beams 071 09/11/06 AA I Beam C 8 9 1 3 165 100 200 0 0 Beams 071 09/11/06 AA I Beam C 9 9 1 3 178 100 200 0 21 Beams 071 09/11/06 AA I Beam C to 0 0 1 174 too 200 0 0 Beams 071 09/11/06 AA I Beam D 8 0 0 1 148 120 220 0 0 Beams 071 109/11/06 AA I Beam D 9 18i 2 4 118 100 200 0 0 Beams 071 09/11/06 AA I Beam D 10 0 0 1 134 100 200 0 0 Beams 089 09/14/06 AA I Beam D 0 23 0 ND 149 140 180 04 -0 Beams 089 09/14/06 AA 1 Beam D 1 27 0- ND 21 140 200 4 0 Beams 089 09/14/06 AA- I Beam D 9 0 ND 151 160 200 0 0Beams 089 09/14/06 AA I Beam D 9 0 ND 1 144 180 200 0 7 1 _Beams_089 09/14/06 AA I Beam D 4 0 0 ND 19 10 10 0 1 em 089 09114106 AA I Beam D 5 0 0 ND 14 40 20 0 0 Beams 090 09/18/06 AA I Beam D 6 9- 3 113 100 200 0 0 IBeams 090 09/18/06 AA I Beam D 7 4 1 3 163 100 200 0 0 1 Beams ENERCON Service, in.

NOTE b denotes concrete beam UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS REACTOR DECOMMISSIONING Drawn by: DM REACTOR ROOM CEILING DRAWING 12 SURVEY UNIT 1-3 Enercon Services University of Washington More Hall Annex D&D, Project 10492 Attachment 13 -Sub-Unit 1-3-12 Reactor Room Center Ceiling Grids E-H Including Beams FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-3-12 (Reactor room center ceiling grids E-H including beams)I Location

Description:

IReactor room center ceiling grids E-H including beams I h* 'I *~~,*j ..~Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (IiR/hr)Number of measurements:

88 88 88 88 N/A Number of measurements needed M: 9 9 9 9 N/A Maximum value of results: 46 9 257 97 N/A Mean value of results: 13 1 164 12 N/A Standard Deviation of results: 12 2 39 23 N/A Degree of Freedom (2): 1.665 1.665 1.665 1.665 N/A Jta value: 15 1 171 16 N/A Guideline level: 100 20 5000 1000 N/A Are there sufficient measurements?

Yes Yes Yes Yes N/A Is the max value < guideline level? Yes Yes Yes Yes N/A Is j.+/- < guideline?

Yes Yes Yes Yes N/A Does survey unit pass? Yes Yes Yes Yes N/A (1) as interpolated from NUTREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-12 (Reactor room center ceiling grids E-H including beams)FSS # Date I Class Floor Surface X I Y Coord. Coord.Alpha Alpha Alpha Direct Scan Min. Scan Max.Beta Beta Scan Beta Scan Direct Min. Max.DPM (cpm) (cpm)Alpha Wipe DPM Beta Net pR Wipe DPM Comments DPM (cpm) (cpus)071 09/11/061 AA 1 !Ceiling E 1 8 9 1 3 1j 38 100 071 09/11/06 AA I ICeiling I E 9 32 1 4 8 J 199 80 071 1 09/11/061 AA 1 Ceiling E I 10 0 0 1 229 100 1 180 1 0 16 1 Ceiling F 8 1 Ceiling F 0 TY 4 4 0 1 157 100 200 0 0 071 109/11/061 AA 1 [Ceilina 100 200 0 0 100 200 0 0 100 200 0 0 120 180 0 0 071 1 09/11/061 AA 1 1 Ceiling G 19 0 1 2 197 071 09/11/061 AA 1 1 Ceiling H 18 9 3 229 H 19 0 0 0-2 2 1 161 100 200 0 0 2 153 80 200 0 0 071 09/11/061 AA 1 1 Beam Beams Beams Beams Beams 071 09/11/06 AA II Beam F 8 18 AA I I Beam 2 4 178 100 200 0 0 G 8 0 Beams 0 1 127 072 09/12/06 GA I I Beam 22 0 101 ____ jeass 2?00 20 J2 ___lBeams 200 1 0 1 0 1__ Ilemus 072 09/12/06 GA I Beam H 9 I Ceiling 1 E El 2 217 240 0 3 089 09/14/06 089 09/14/06 089 09/14/06 089 09/14/06 E 3 173 8:110 , 183 1 160 I AA 1 Ceiling E 5 46 0 ND 121 089 09/14/06 AA I jBeam 089 09/14/06 AA I Beam 089 09/14/06 AA I Beam 089 09/14/06 AA I Beam 089 09/14/06 AA I I IBeam 089 09/14/06 AA I JCeiling 32 0 ND E 2 E 3 E 4 E 5 F 0 F t 23 9 5 0 0 0 ND 199 160 240 0 0 ND 144 180 200 0 7 ND 178 180 220 0 0 Beams Beams Beams Beams Beams Bennis 37 0~~41 32 089 09/14/06 089 09/14/06 089 09/14/06 089 09/14/06 AA I j Beam AA II Beas F I 1 1 14 4/06 AA I Ceiling 4/06 AA I I Ceiling 089 09/14/06 089 09/14/06 AA I Beam AA I Ceilini AA 1 Beam F 2~-F 3 F -0 F 4 F 4 F- -5 I- 5 G 0 G 0 G I G I G 2 G 2 G 3 G 3 G 4 0 27 14 9 5 14 5 27 0 0 0 0 0 0 0 0 0 0_0 0 0 0 0 0 0 0 0 0 0 ND 203 ND I 162 ND 140 160 220? 0 0 ND 167 180 220 0 I0 ND 101 160 1 200 1 0 1 0 Beams Beams Beams 180 260 0 0 089 109/14/061 AA 1 0 0 72 0 I 1 I Ceiling Beam Ceiling Beam Ceiling Beam ND ND ND ND ND ND ND ND ND ND ND 165 255 139 157 198 164 162 160 200 , Beams -See GO comment-140 240 0 0 0 0 0 D 0 0 BF:4 0 1 0 1 0 1 RpnmQ gpp fqdh mnmmpnlQ 160 200 0 9 9 0 IBcams, See G4b connmnents 49 I 089 1 09/14/06 1 AA ND 151 160 220 0 26 1 _ Beams, East side needs surveyem ND 171 180 I 220 I 0 a 171 180 220 0 0 ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-12 (Reactor room center ceiling grids E-H including beams)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net tR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 089 09/14/06 AA I Beam a 5 5 0 ND 165 140 180 0 40 Beams, East face needs surveyed, static smear 090 09/18/06 AA 1 Ceiling 6 6 31 3 6 129 100 200 0 23 090 09/18/06 AA I Ceiling B 7 13 2 4 152 120 220 0 0 090 09/18/06 AA I Beam E *6 0 0 2 174 100 200 0 0 Beams 090 09/18/06 AA F Beam B 7 22 3 5 160 100 200 0 0 Beams 090 09/18/06 AA I Ceiling F 6 13 2 3 120 120 200 0 51 090 09/18/06 AA I Ceiling F 7 0 0 2 248 100 220 0 28 090 09/18/06 AA I I Ceiling H 0 22 3 4 181 100 220 0 0 090 109/18/061 AA I 1 Ceiling H 1 4 l 3 140 100 200 0 0 H 2 1 0 0 2 149 100 200 0 0 H 3 172 100 20 l l__ __________

___I 102 t00 180 4~ F O __ _____________

090 1 09/18/06 1 AA I I ICeiling I 1 4 090 109/18/061 AA I Ceiling H 5 9 1 4 113 100 200 4 0 I Beam H 1 0 9 I 3 163 100 1 200 1 0 1 32 Beams l Beam 090 109/18/061 AA I Beam 0 0 18 3 36 I 3 2 5 4 96 100 1 180 1 0 1 0 Beams 093 1 09/19/06 1 AA I Beam F 16 I Ceiling 1 B~eam 01 6 26 3 194 100 200 1 9 1 0 2 093 1 09/19/06 1 AA I Ceiling 3 4 T L 1 144 100 204 100 200 100 148 100 180 0 13 200 0 8 200 0 0 200 9 17 Beams 093 1 09/19/06 1 AA I Beam 1 1-1 1 3 2 0 Beams I Beam 1 1-1 4 2 0 Beams I Beam 106 1 09/25/06 1 AA I I Ream H E F F 5 10 10 10 106 09/25/06 AA 1 106 09/25/06 AA I Ceiling Beam l Ceiling 1 Beam 1 Ceiling 106 1 09/25/06 I AA 106 09125/06 1AA 1 Enam 106 09/25/06 AA 1 Ceiling 1i 10 F 7 0 7 G 7 H 7 H 7 H 6 H 10 0 10 ti in 21 8 3 8 8 0 17 0 17 3 0 3 3 2 0-3 1 161 1 100 180 1 0 1 0 0 1 1 1 151 I 80 300 1 0 1 26 0 3 0 3 0 3 0 5 0 3 122 80 340 0 57 113 80 340 i0 67 1 162 1 80 280 1 0 1 36 Beams Beam Ceiling Beam Ceiling Beam Ceiling Beam Ceiling Beam Beam Beam 106 09/25/06 AA 106 09/25/06 AA qea 156 80 11 0 106 09/25/06 AA 1 Beam 106 09/25/06 AA I Beam 106 I09/25/06 IAA JIt eiliam, 0 1 170 80 0 3 194 _ 80 300 1 3 300 1 0 26 n"1 80 Il+ 111 106 1 09/25/06 AA I I lCeiling 11 10 3 0 3 ENERCON Seics, in.

University of Washington More Hall Annex D&D, Project 10492 Attachment 14 -Sub-Unit 1-3-13 Reactor Room East Ceiling Grids I-L Including Beams FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-3-13 (Reactor room east ceiling grids I-L including beams)Unit Designator:

I 3-13 i I Location

Description:

IReactor room east ceiling grids I-L including beams I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/lOOcm

2) (p.R/hr)Number of measurements:

77 77 77 77 N/A Number of measurements needed (1): 9 9 9 9 N/A Maximum value of results: 45 9 226 112 N/A Mean value of results: 10 1 164 24 N/A Standard Deviation of results: 10 2 31 26 N/A Degree of Freedom (2)': 1.667 1.667 1.667 1.667 N/A Va value: 12 1 170 29 N/A Guideline level: 100 20 5000 1000 N/A Are there sufficient measurements?

Yes Yes Yes Yes N/A Is the max value < guideline level? Yes Yes Yes Yes N/A Is ýta < guideline?

Yes Yes Yes Yes N/A Does survey unit pass? Yes Yes Yes Yes N/A as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

0 University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-13 (Reactor room east ceiling grids I-L including beams)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (epm) (cpm) DPM (cpm) (cpm) DPM DPM 072 09/12/06 AA I Ceiling 1 8 3 0 3 119 100 200 0 2 072 09/12/06 AA 1 Ceiling 2 9 13 1 3 152 100 220 0 0 090 09/18/06 AA I Ceiling 1 0 0 0 2 161 100 200 0 32 090 09/18/06 AA I Ceiling 1 1 22 3 4 185 100 220 0 19 090 09/18/06 AA I CeiBing 1 2 13 2 3 145 100 200 0 0 090 09/18/06 AA I Ceaming 4 3 7 1 3 226 100 220 0 1 093 09/19/06 AA 1 Ceiling a 4 26 3 4 140 100 200 0 0 093 09/19/06 AA I Ceiling 1 5 16 2 3 170 100 200 0 13 093 09/19/06 AA I Beam 1 0 12 1 3 161 100 200 0 31 Beams 093 09/19/06 AA I Beam 1 1 26 2 4 178 100 180 0 0 Beams 093 09/19/06 AA 1 Beam 1 2 7 0 2 170 100 200 0 0 Beams 093 09/19/06 AA I Beam 1 3 12 1 3 185 100 220 0 31 Beams 093 09/19/06 AA 1 Beam 1 4 45 4 6 193 100 200 0 8 Beams 093 09/19/06 AA I Beam J 5 71 0 2 206 120 200 0 17 Beams 093 09/19/06 AA I Ceiling J 0 2 168 100 200 4 8 093 09/19/06 AA I Ceiling 1 21 2 3 164 110 200 0 0 093 09/19/06 AA I Ceiling K 2 2 0 1 166 100 200 0 0 093 09/19/06 AA I Ceiling 1 3 16 2 3 157 800 200 0 13 093 09/19/06 AA I Ceiling 1 4 31 3 5 129 10 0 0 9 C 093 09/19/06 AA 1 Ceiling a 5 16 2 3 226 100 220 0 31 093 09/19/06 AA I Ceiling J 6 2 0 1 129 100 200 0 0 093 09/19/06 AA 1 Ceiling I 7 16 2 3 187 100 340 0 0-093 109/19/06 1AA I1 Beam 1 0 26 2 4 168 120 200 0 0 Beams 093 09/29/06 AA 1 Beam 1 1 7 0 2 164 100 200 0 0 Beams 093 09/19/06 AA I Beanm 1 2 7 0 2 166 100 200 0 31 Beams 093 09/19/06 AA I Beam J 3 36 3 5 157 100 200 0 0 Beams 093 09/19/06 AA I Beam -4 16 2 3 129 10 30 0 4 0 Beams 093 09/19/06 AA I Beam J 5 12 I 3 149 100O 200 0 45 1 Beams 093 09/19/06 AA- I Beam J 6 7 0 2 159 100 1 200 0 0 1 Beams 093 09/19/06 --AA I Beam J 7 12 1 3 204 120 1 220 4 0 Be13ams 093 09/19/06 AA I K 0 12 1 3 142 100 200' 0 0 West and bottom scanned a: 0-6 cpm /B I10U-200 cpm 093 109/19/06 1AA I ICefling K 1 12 2 3- 215 100 220 0 0 West and bottom scanned a: 0-6 cpm /B 100-200 cam 093 09/19/06 AA I Ceiling K 2 26 3 4 193 too 200 0 0 West and bottom scanned a: 0-6 cinn/B 100-200 cpni 093 09/19/06 -AA I Ceiling K 3 1 16 1 4 178 100 200 0 0 West and bottom scanned a: 0-6 cpm /B 100-200 cpm 093 09/19/06 AA 1 K 4 21 2 4 157 100 200 0 17 West and bottom scanned a; 0-6 cpm /B 100-200 cpm 093 09/19/06 AA I Ceiling K 5 26 2 4 198 120 200 0 0 096 09/20/06 AA I Ceiling J 10 0 0 0 83 140 260 0 6 096 09/20/06 AA 1-- Ceiling J 9 18 -1 2 187 140 280 0 26 096 09/20/06 AA 1 Ceiling K to 13 1 1 167 160 280 0 161 096 09/20/06 AA I Ceiling K 9 22 I 2 180 140 300 0 26 097 109/20/06 1AA I1 Beam 1 10 13 1 2 167 180 280 0 46 Beams 097 09/20/06 AA I ]Beam J 9 0 0 1 1 118 160 300 0 "0 Beams 097 09/20/06 AA 1 1Beam K 1 0 1 22 1 1. 2 165 180 320 0 21 Beamns 097 09/20/06 AA I Beam K 9 1 3 0 1 1 164 140 280 3 66 Beamns 106 09/25/06 AA I Ceiling 1 7 1 0 0 1 3 187 80 280 0 36 Ceiling 106 09/25/06 AA I Ceiling 1 6 0 0 3 202 80 300 0 41 Ceiling I0 92/6 A Beam 1 6 22 0 l 128 80 340 0 36 Beam 16 09/25/06 AA I Beam 1 7 8 0 3 185 80 30 0 1Ba 106 09/25/06 AA I Be in 1 8 8 0 3_ 162 80 320 0 16 B1eam IN6 9/ 5/06 AA I Beam 1 9 0 0 3 171 80 320 0 41 Beam 106 09T/253/06 AA 1 Beam 1 10 3 t 5 192 80 340 0 36 jBeam 106 09/25/06 AA I Ceifing 1 10 0 0 3 98 80 300 0 3 ela ENERCON Servi-es, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-13 (Reactor room east ceiling grids I-L including beams)FSS N Date Class Floor Surface X Y Alpha Alpha Alpha Beta BetaScan Beta Scan Alpha Beta Net JJR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 106 09/25/06 AA I Beam 1 8 8 0 3 156 80 320 0 41 Beam 106 09/25/06 AA 1 Ceiling K 8 17 0 5 79 t0 300 0 62 Ceiling 106 09/25/06 AA 1 Beam K 8 17 0 3 105 10 300 0 57 Beam 106 09/25/06 AA I Ceiling K 7 0 0 4 117 80 320 0 67 Ceiling 106 09/25/06 AA I Beam K 7 0 0 1 2 209 80 280 0 36 Beam 106 09/25/06 AA 1 Ceiling K 6 3 0 5 117 80 320 0 0 Ceiling 106 09/25/06 AA 1 Beam K 6 0 0 4 141 80 280 0 46 Beam 106 09/25/06 AA I Beam K 0 8 0 5 183 80 320 0 112 Beam 106 09/25/06 AA I Ceiling L 0 8 0 4 177 80 300 0 102 Ceiling 106 09/25/06 AA I Beam K 1 0 0 3 194 80 300 3 16 Beam 106 09/25/06 AA I Ceiling L 1 0 0 3 170 80 300 0 0 Ceiling 106 09/25/06 AA I Beam K 2 0 0 3 162 80 320 3 21 Beam 106 09/25/06 AA I Beam K 3 3 0 3 154 80 280 0 36 Beam 106 09/25/06 AA 1 Ceiling L 2 3 0 3 141 80 320 0 26 Ceiling 106 09/25/06 AA I Ceiling L 3 17 0 3 187 80 340 0 36 Ceiling 106 09/25/06 AA I Beam K 4 8 0 5 162 80 320 0 77 IBeanm 106 09/25/06 AA I Beam K 5 3 0 4 156 80 320 0 36 Beam 106 09/25/06 AA I Ceiling L 4 0 0 3 192 80 320 0 41 Ceiling 106 09/25/06 AA I Ceiling L 5 3 0 3 196 80 320 0 16 Ceiling 106 09/25/06 AA I Ceiling L 6 8 0 3 207 80 320 0 77 Ceiling 106 09/25/06 AA 1 Ceiling L 7 3 0 3 204 80 320 -7 82 Ceiling 106 09/25/06 AA 1 Ceiling L 8 0 0 5 137 80 300 0 57 Ceiling 106 09/25/06 AA 1 Ceiling L 9 0 0 3 147 80 300 7 31 Ceiling 106 09/25/06 AA I Ceiling L 10 0 0 4 109 80 320 0 41 Ceiling 106 09/25/06 AA 1 T Ceiling 1 8 8 0 3 141 80 320 0 26 Ceilhlg ENERCON Servce, in-.

University of Washington More Hall Annex D&D, Project 10492 Attachment 15 -Sub-Unit 1-3-14 Reactor Room West Wall FSS Statistical Summary and Survey Data UW-MCP-OP--13, Rev. 2 Final Status Decision Summary for Unit 1-3-14 (Reactor room west wall)Location

Description:

lReactor room west wall I I I I Direct Alpha Removable Direct Beta Removable Gamma-Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm) (gR/hr)Number of measurements:

91 91 91 91 N/A Number of measurements needed (: 9 9 9 9 N/A Maximum value of results: 56 8 294 92 N/A Mean value of results: 6 1 90 10 N/A Standard Deviation of results: 10 2 96 20 N/A Degree of Freedom (2) : 1.664 1.664 1.664ý 1.664 N/A 4L value: 8 1 107 14 N/A Guideline level: 100 20 5000 1000 N/A Are there sufficient measurements?

Yes Yes Yes Yes N/A Is the max value < guideline level? Yes Yes. Yes Yes N/A is [tc < guideline?

Yes Yes Yes Yes N/A Does survey unit pass? Yes Yes Yes Yes N/A I as interpolated from NUREG/CR-5849 Table B-2 (-) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-14 (Reactor room west wall)FSS # Date Clss Floor Surface X Y Alpha Alpha Alpha Beta Beta Sca0 Beta Scan Alpha Beta Net PR Comments Coord. Chord. Direct Scan Min. Scan Max. Direct MIn Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpmu) (epm) DPM DPM 045 08/29/06 AA I W Wall 1 8 0 0 0 0 100 140 0 0 10" lip right end & face 045 08/29/06 AA I W Wall 1 7 3 0 0 0 0 20 0 8 0 face 2nd meter from right 045 08/29/06 AA I W Wall H 7 10 0 0 0 0 220 0 41 face 3rd meter fromr right 045 08/29/06 AA I W Wall H 8 0 0 0 0 0 180 0 16 3rd window meter from right & lip 045 08/29/06 AA I W Wall H 9 3 0 0 0 0 240 8 6 3rd meter from right up to ceiling 045 08/29/06 AA I W Wall 1 9 0 0 0 0 0 220 0 1 2nd meter from right up to ceiling 045 08/29/06 AA I W Wall G 9 0 0 0 0 0 260 0 0 4th meter from right top to ceiling 045 08/29/06 AA I W Wall G 8 30 0 0 0 0 200 0 0 4th meter from right, window & lip 045 08/29/06 AA I W Wall G 7 6 0 0 0 0 0 260 0 0 44i meter from right face 045 08/29/06 AA I W Wall F 9 16 0 0 0 0 220 4 0 51h meter from right-top 045 08/29/06 AA I W Wall F 5 0 0 0 0 0 220 0 36 5th meter from right window & lip 045 08/29/06 AA I W Wall F 7 0 0 0 0 0 200 0 0 5th meter from right face 045 08/29/06 AA I W Wall E 9 3 0 0 0 0 180 4 16 6th meter from right top 045 08/29/06 AA I W Wall E 8 0 0 0 0 0 220 0 0 6th meter from right window & lip 045 08/29/06 AA I W Wall E 7 3 0 0 0 0 180 0 0 64h meter from right floor 045 08/29/06 AA I W Wall G 6 0 0 0 0 0 180 4 6 045 08/29/06 AA I W Wall F 6 0 0 0 0 0 200 0 0 045 08/29/06 AA I W Wall F 5 16 0 0 0 0 160 0 0 045 08/29/06 AA 1 W Wall F 4 0 0 0 0 1 0 180 0 31 045 08/29/06 AA 1 W Wall F 3 0 0 0 0 0 200 0 26 045 08/29/06 AA I W Wall B 6 3 0 ND 20 0 220 0 6 045 08/29/06 AA I W Wall C 6 16 ND 19 0 200 4 0 045 08/29/06 AA I W Wall D 6 23 0 N6 0 0 200 4 36 046 08/29/06 AA I W Wall A 1 3 0 ND 188 0 180 0 0 046 08/29/06 AA I W Wall B 1 0 1 ND 164 0 300 0 0 046 08/29/06 AA I W Wall C 9 3 0 ND 238 0 220 0 0 0 046 08/29/06 AA I W Wall D 1 10 0 ND 184 0 200 0 0 046 08/291/06 AA I W Wall E 1 0 0 ND 242 0 180 0 0 _046 08/29/06 AA I W Wall F 1 3 0 ND 247 0 200 0 0 046 08/29/06 AA I W Wall A 9. 10 0 ND 0 0 260 0 27 046 08/29/06 AA I W Wall B 9 5 0 ND 0 0 240 4 82 046 08/29/06 AA I W Wall C 9 33 0N ND 0 0 380 0 4 046 08/29/06 AA 1 W Wall D 9 10 0 ND 0 0 300 0 0 046 08/29/06 AA I W Wall D 8 1 0 ND 294 0 340 0 31 046 08/29/06 AA I W Wall C 8 56 0 ND 252 0 380 0 27 046 08/29/06 [AA I W Wall B 8 1 0 ND 188 1 0 360 0 411 046 08/29/06 AA I W Wall A 8 1 0 ND III1 0 400 0 0 046 08/29/06 AA I 1 W Wall A 7 1 0 ND 0 0 320 0 69 046 08/9106 AA I1 W Wall B 7 0 0 7 0 0 360 4 4 046 08/29/06 AA I1 W Wall C 7 0 0 N D 0 0 320 0 0 046 08/29106 AA I1 W Wall D 7 0 0 ND 0 0 300 4 0 046 08/29/06 AA I W Wall A 6 1 0 ND 0 0 300 4 8 047 108/31/06 AA I W Wall 1 9 18 ND ND 59 0 220 8 0 047 08131/06 AA 1 W Wall J 8 5 ND ND 39 0 200 8 0 047 08/31/06 AA I W Wall 1 7 5 ND ND 205 0 300 0 0 047 08/31/06 AA 1 W Wall 1 6 50 ND ND 7 0 180 0 26 1 047 08/31/06 AA I W Wall 1 5 0 ND ND 101 0 280 0 0 047 08/31/06 AA- I W Wall 1 4 is NO ND 208 0- ISO 0 0 047 08/31/06 AA I W Wall -J 3 18 ND ND- 195 0- 160 0 -0 047 08/31/06 AA I W Wall 1 6 24 ND ND 122 0 180 0 0 047 08/31/06 AA I al1 5 0 ND ND 35 0 180 4 0 047 108/31/06 AA I W Wall 1 4 5 ND I ND 197 1 0 180 0 0 ENERCON S-nvcaa, i.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-14 (Reactor room west wall)FSS N Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 047 08/31/06 AA i W Wall 1 3 5 ND ND 76 0 200 0 6 047 08/31/06 AA i W Wall H 5 11 ND ND 98 0 160 0 0 047 08/31/06 AA 1 W Wall H 4 5 ND ND 219 0 180 0 92 047 08/31/06 AA I W Wall H 3 0 ND ND 221 0 180 0 a 047 08/31/06 AA I W Wall G 5 0 ND ND 100 0 160 4 0 047 08/31/06 AA I W Wall G 4 5 ND ND 179 0 200 0 0 047 08/31/06 AA I W Wall G 3 5 ND ND 236 0 200 0 31 047 08/31/06 AA I W Wall E 3 18 ND ND 184 0 200 0 6 047 08/31/06 AA I W Wall H 6 5 ND ND 103 0 200 8 77 047 08/31/06 AA I W Wall E 5 0 0 ND 0 0 160 0 0 047 08/31/06 AA 1 W Wall E 6 0 0 ND 0 0 180 0 0 048 09/01/06 AA t WWall D 5 11 0 11 164 0 240 0 0 048 1 09/01/06 1 AA I I W Wall C 5 0 0 ND 148 a 0 1/ Wall B I Wall A 5-5 4 4 0 0 5 69 5 0 -v 0 280 0 260 0 300 0 240 04 40_0 16 0 0 1 1 048 1 09/01/06 1 AA IW Wall A 0'ND 048 1 09/01/06 1 AA I I W Wall B 11 1 0 185 i Wall C TWal DI 048 1 09/01/06 1 AA I I W Wall E 4 4 0 5 5 5 0 ND 0 0 ND 18N 100 0 l N!DL 229 1 0 1 300 0 01 7 ND 217 L 0 200 4 36 ND 171 1 0 200 0 0_ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _0 200 0 048 09/01/06 048 09/01/06 048 09/01/06 048 09/01/06 AA I I W Wall A AA I1 W Wall B 1 3 AA iw )WnaI A A~ I -I 17 5 0 0 ND 90 ND 234 0 220 0 0 0 048 1 09/01/06 1 AA I 1 W Wall E 1 3 048 109/01/06 AA 1 W Wail 048 09/01/06 AA I W Wail 048 09/01/06 AA 1

• W Wall 048 1 09/01/06 1 AA I I W Wall A 2 B. 2 C 2 D 2 5 0 ND 1 206 1 0 220 0 1 0 It 0 0 0 0 ND 1 224 0 0-6-240 0 0 I1 048 109/01/06 AA 1 W Wall 048 109/01/06 AA I W Wall 040 09/01/06 AA I W Wall E 1 2 23 ND 1 180 21 0 I 1 0 I1 0 0 ND 1 187 0 0 0 0 220 200 200 200.180 180 220 0 31 048 09/01/06 048 09/01/06 048 09/01/06 048 09/01/06 040 09/01/06 048 09/01/06 048 09/01/06 146 10/02/06 AA I I W Wall AA AA AA AA AA AA AA 1 W Wall.1 W Wall 1 W Wall 1 W Wall I WWall G H 1 ND I ND 1 0 0 1 2 I 2 0 ND ND ND 0 1 0 200 0 0 220 0 16 0 0 Dj0 0 220 E00 0 JI 2 0 ND I ND 0 200 0 0______ 3 3 0 j ND j ND J 2 ___ 2 g 0 0~ ~ j__________________

ENERCON Services, inc.

A9 A8 A7 A6 A5 A4 A3 A2 A1 B1 C1 D1 El F1 G1 H1 I1 J1 Note: Wall was inadvertently labeled Al to A9 during FSS survey instead of AO to AB.)6-UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS REACTOR DECOMMISSIONING Drawn by: DM REACTOR ROOM WEST WALL DRAWING 13 SURVEY UNIT 1-3 Enercon Services University of Washington More Hall Annex D&D, Project 10492 Attachment 16 -Sub-Unit 1-3-15 Reactor Room East Wall 0 To 4-m FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-3-15 (Reactor room east wall 0 to 4-m).Unit Designator:

......1-3-15 Clss AA CetitI: 9 Location

Description:

Reactor room east wall 0 to 4-m Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (gR/hr)Number of measurements:

60 60 60 60 N/A Number of measurements needed M: 9 9 9 9 N/A Maximum value of results: 74 8 980 102 N/A Mean value of results: 12 1 201 17 N/A Standard Deviation of results: 16 2 172 25 N/A Degree of Freedom (2) 1.671 1.671 1.67i 1.671 N/A tc, value: 15 1 238 22 N/A Guideline level: 100 20 5000 1000 N/A Are there sufficient measurements?

Yes Yes Yes Yes N/A Is the max value < guideline level? Yes Yes Yes Yes N/A Is ýLe < guideline?

Yes Yes Yes Yes N/A Does survey unit pass? Yes Yes Yes Yes N/A (1) as interpolated from NUREG/CR-5849 Table B-2 (') from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-15 (Reactor room east wall 0 to 4-m)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cp-) DPM (cpm) (cpm) DPM DPM 094 09/19/06 AA I E Wall C 0 74 0 4 132 40 220 0 0 094 09/19/06 AA I E Wall C 1 21 0 2 190 40 280 0 36 094 09/19/06 AA I E Wall D 0 29 0 2 205 40 300 4 45 094 09/19/06 AA I E Wall D 1 0 0 1 181 40 280 4 0 094 09/19/06 AA I E Wall E 0 14 0 1 179 40 260 0 0 094 09/19/06 AA I EWall E 1 14 0 1 181 40 260 0 0 094 09/19/06 AA I E Wall F 0 44 0 3 205 40 280 0 31 Door 094 09/19/06 AA I E Wall F I 0 0 1 204 40 280 0 26 Door 094 09/19/06 AA I E Wall G 0 14 0 2 245 40 300 0 0 Door 094 09/t9/06 AA I E Wall G 1 29 0 3 381 40 360 0 8 Door 094 09/19/06 AA I E Wall H 0 0 0 1 413 40 400 0 22 094 09/19/06 AA I E Wall H 1 0 0 1 407 40 380 0 40 094 09/19/06 AA 1 E Wall 1 0 0 0 1 311 40 300 0 0 094 09/19/06 AA 1 E Wall 1 1 6 0 1 339 40 300 0 0 094 09/19/06 AA I E Wall 3 0 0 0 1 283 40 300 0 22 094 09/19/06 AA I E Wall J 1 0 0 1 343 40 300 0 0 094 09/19/06 AA I E Wall K 0 0 0 1 432 40 360 0 0 094 09/19/06 AA I EWali K 1 0 0 0 519 40 360 4 0 094 09/19/06 AA 1 E WaIl L 0 0 0 0 338 40 320 0 0 094 09/19/06 AA I EWall L 1 0 0 1 385 40 360 0 0 094 09/20/06 AA I E Wall A 3 0 0 0 129 40 280 0 0 094 09/20/06 AA I E Wall A "4 0 0 1 307 40 400 8 96 094 09/20/06 AA I E Wall B 3 13 0 1 135 40 280 0 31 094 09/20/06 AA I E Wall B 4 0 0 1 0 40 200 0 0 094 09/20/06 AA I E Wall C 3 13 0 1 149 40 310 0 0 094 09/20/06 AA 1 E Wall C 4 8 0 1 0 40 220 0 40 094 09/20/06 AA 1 E Wall D 3 8 0 1 89 40 310 0 0 Partial grid, not full meter 094 09/20/06 AA I E Wall D 4 3 0 0 0 40 300 8 0 Partial grid, not full meter 094 09/20/06 AA 1 E Wall E 3 3 0 1 106 40 300 4 3 094 09/20/06 AA I E Wall E 4 13 0 4 539 40 460 0 8 094 09/20/06 AA 1 E Wall F 3 3 0 1 311 40 400 4 0 094 09/20/06 AA 1 E Wall F 4 8 0 1 329 40 400 0 1 094 09/20/06 AA I E Wall B 3 8 0 2 50 40 300 0 0 094 09/20/06 AA I EWall G 4 13 0 1 0 40 240 04 0 094 09/20/06 AA I EWall H 3 273 0 1 69 40 300 0 0 Partial grid, not full meter 094 09/20/06 AA I E Wall D4 8 0 1 87 40 300 0 0 8artial arid, not full meter 094 09/21/06 AA I EWall 1 3 11 0 1 67 40 300 0 6 Partial grid, not full meter 224 ý09/2 '/06 AA I E Wall 1 4 1 0 0 0 40 200 S 46 Partial grid, not full meter 094 09/21/06 AA I EWall A 0 21 0 2 161 40 310 0 41 Door 094 09/21/06 AA I E Wall A 1 67 0 4 93 40 310 0 6 Door 094 09/21/06 AA I EWall A 2 6 0 1 218 40 290 0 0 094 09/21/06 AA I E Wall B 0 11 0 2 295 40 420 0 16 Door 094 09/21/06 AA M 1 E W a II B 1 32 0 3 434 40 480 0 41 Door 094 09/21/06 AA I E Wall B " "2 11 0 2 126 40 320 0 141 094 09/21/06 AA 1 E Wall C 2 27 0 2 118 40 310 0 1 36 094 09/21/06 AA I E Wall D 2 1 0 1 153 310 O 81 094 09/21/06 AA I E Wall E 2 32 0 2 149 40 310 0 6 094 079/ 1'/06 AA I E Wall F 2 27 0 2 151 .40 310 0 0 094 09/21/06 AA I E Wall 0 2 21 0 2 138 40 290 0 0 094 09/21/06 AA 1 E Wall H 2 7 0 3 92 40 310 0 11 094 09/21/06 AA I E Wall 1 2 27 0 2 188 40 390 0 76 094 09/21/06 AA I EWall 1 2 16 0 2 122 40 310 0 102 ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-15 (Reactor room east wall 0 to 4-m)FSS N Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpus) (cps) DPM (cps) (cpm) DPM DPM 094 09/21/06 AA 1 E Wall K 2 1 0 0 190 40 380 0 6 094 09/21/06 AA I E Wall L 2 16 0 2 980 40 500 0 0 116 09/28/06 AA I E Wall J 3 0 0 1 0 80 220 4 0 116 09/28/06 AA I EWall J 4 0 0 3 9 80 200 4 15 116 09/28/06 AA 1 E Wall K 3 0 0 3 47 80 200 0 0 116 09/28/06 AA I EWaII K 4 0 0 3 110 80 220 0 10 116 09/28/06 AA I EWall L 3 0 0 3 40 80 240 0 0_116 09/28/06 AA I E Wall L 4 0 0 3 7 80 220 0 30 ENERCON Su-ic-, in.

Column 101H0 Column DO through 12/1H2. through D2.Small grids Small grids continued to continued to ceiling for ceiling for consistency.

consistency.

-.9K UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS PROJECT REACTOR DECOMMISSIONING Drawn by: DM DRAWING REACTOR ROOM EAST WALL DRAWING 14 SURVEY UNIT 1-3 Enercon Services University of Washington More Hall Annex D&D, Project 10492 Attachment 17 -Sub-Unit 1-3-16 Reactor Room East Wall 5 To 9-m FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-3-16 (Reactor room east wall 5 to 9m)Location

Description:

Reactor room east wall 5 to 9m I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results. Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (jpR/hr)Number of measurements:

59 59 59 59 N/A Number of measurements needed (1). 9 9 9 9 N/A Maximum value of results: 41 8 489 86 N/A Mean value of results: 9 1 110 11 N/A Standard Deviation of results: 9 2 110 21 N/A Degree of Freedom (2): 1.672 1.672 1.672 1.672 N/A ga value: 10 1 133 16 N/A Guideline level: 100 20 5000 1000 N/A Are there sufficient measurements?

Yes Yes Yes Yes N/A Is the max value < guideline level? Yes Yes Yes Yes N/A Is g' < guideline?

Yes Yes Yes Yes N/A Does survey unit pass? Yes Yes Yes Yes N/A (1) as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-16 (Reactor room east wall 5 to 9m)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct MIn, Max. Wipe Wipe DPM (cpm) (cpni) DPM (cpm) (cpm) DPM DPM 094 09/20/06 AA I E Wall A 5 3 0 1 0 40 240 4 0 094 09/20/06 AA I E Wall A 6 0 0 1 0 40 240 0 0 094 09/20/06 AA 1 E Wall A 7 3 0 1 137 40 320 0 0 094 09/20/06 AA 1 E Wall B 5 8 0 1 0 40 210 0 0 094 09/20/06 AA 1 EWall B 6 3 0 1 0 40 210 0 0 094 09/20/06 AA I E Wall B 7 13 0 t 116 40 300 0 3 094 09/20/06 AA I E Will C 5 34 0 3 0 40 240 4 0 094 09/20/06 AA 1 E Wall C 6 13 0 1 0 40 210 4 54 094 09/20/06 AA I E Wall C 7 3 0 1 489 40 460 4 3 094 09/20/06 AA I E Wall D 5 8 0 1 0 40 240 0 31 Partial grid, nut full meter 094 09/20/06 AA I E Wall D 6 13 0 1 408 40 450 8 68 Partial grid, not full meter 094 09/20/06 AA I E Wall D 7 8 0 I 149 40 310 0 0 Partial grid, not full meter 094 09/20/06 AA 1 E Wall E 5 0 0 0 0 40 200 0 0 094 09/20/06 AA 1 E Wall E 6 1 8 0 1 0 40 210 0 3 094 09/20/06 AA I E Wall E 7 3 0 I 40 40 300 0 0 094 09/20/06 AA I E Wall F 5 3 0 l 0 40 210 0 8 094 09/20/06 AA I E WaIl F & 13 0 2 73 40 300 0 0 094 09/20/06 AA 1 E Wall F 7 0 0 0 79 40 320 0 3 094 09/20/06 AA I E Wall 0 5 3 0 1 193 40 380 0 0 094 09/20/06 AA I E Wall 0 6 3 0 1 0 40 220 4 0 094 09/20/06 AA I E Wall G 7 8 0 I 106 40 310 0 0 094 09/20/06 AA I E Wall 11 5 8 0 1 0 40 220 0 8 Partial grid, not full meter 094 09/20/06 AA E1E Wall H 6 1 8 0 0 40 220 0 0 Partial grid, not full meter 094 09/21/06 AA I E Wall 1 5 11 0 2 0 40 200 4 0 Partial grid, not full meter 094 09/21/06 AA I E Wall 1 6 6 0 16 -0 40 200 0 71 Partial grid, not full meter 108 09/25/06 AA 1 E Wall A 8 8 0 1 162 80 280 0 6 108 09/25/06 AA I E Wall A 9 3 0 1 119 80 300 0 1 108 09/25/06 AA 1 E Wall B 8 8 0 3 130 80 300 0 0 B-8 Surveyed to ceiling. No B-9 because ofopen rhole itn wall It5 09/28/06 AA 1 EWall C 8 0 0 1 225 80 280 0 0 1 115 09/28/06 AA 1 EWall C 9 9 0 1 190 80 300 4 5 1 115 09/28/06 AA I E Wall D 8 41 0 3 283 80 300 0 10 115 09/28/06 AA I E Wall D 9 22 0 3 144 80 320 0 20 115 09/28/06 AA I E Wall E 8 0 0 2 194 80 320 0 71 115 09/28/06 AA 1 E Wall E 9 0 0 3 173 80 340 0 0 115 09/28/06 AA I E Wall F 8 9 0 3 205 80 320 0 0 115 09/28/06 AA I E Wall F 9 9 0 3 210 80 340 4 0 115 09/28/06 AA 1 E Wall G 8 15 0 3 153 80 340 4 15 115 09/28/06 AA 1 E Wall 0 9 22 0 2 227 80 340 0 40 115 09/28/06 AA I E Wall H 8 9 0 2 177 80 320 0 45 115 09/28/06 AA I E Wall 11 9 9 0 3 192 80 340 0 5 115 09/28/06 AA I E Wall 1 8 15 0 3 236 80 320 0 0 115 09/28/06 AA 1 E Wall 1 9 22 0 3 166 80 320 0 10 115 09/28/06 AA 1 E Wall J 8 22 0 1 220 80 340 _0 30 115 09/28/06 AA 1 EWall J 9 15 0 3 168 80 320 0 0 115 09/28/06 AA I E Wall K 8 9 0 3 216 80 340 0 0 115 09/28/06 AA -T EWaIl K 9 22 0 I 177 80 320 0 0 115 09/28/06 AA I EWall L 8 22 0 I 218 80 340 0 0 115 09/28/06 AA 1EWalt L 9 22 0 2 220 80 340 4 0A 116 091/28/06 AA 116 09/28/06 AA S(E Wall I 7 0 0 l 0 1 80 240 1 0 1 0 I IEWoII[ 5 1 0 0 3 1 70 80 1 220 1 0 1 0 116 09/28/06 1AA I E Wall) I 0 116 09/28/061 AA I I E Wall K I I 0 ENERCON Servies, ino.

0 University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-16 (Reactor room east wall 5 to 9m)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta BetaScan Bela Scan Alpha Beta Net pR Comments Coord. Coard. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 116 09/28/06 AA I E Wall K 5 0 0 3 0 80 220 0 0 116 09/28/06 AA I E Wall K 6 0 0 2 44 80 200 0 0 116 09/28/06 AA I E Wall K 7 0 0 2 27 80 240 4 0 116 09/28/06 AA t E Wall L 5 0 -0 3 12 80 220 0 35 Includes Vent 116 09/28/06 AA 2 EWall L 6 0 0 I 27 80 220 0 0 Includes Vent 116 09/28/06 AA I EWall L 7 0 0 3 0 80 200 0 86 142 10/02/06 AA I EWall 1H 7 6 0 2 39 100 240 4 25 East Wall Reactor Room ENERCON Services, ic.

A9 HOLE A8 A7 A6 A5 A4 A3 LO KO JO 10 HO GO A2 Al A0 7/Column DO through D2.Small grids continued to ceiling for consistency.

Column 10fHO through 12/H2.Small grids continued to ceiling for consistency.

-.9K UNIVERSITY OF WASHINGTON NUCLEAR REACTOR DECOMMISSIONING REACTOR ROOM EAST WALL SURVEY UNIT 1-3 University of Washington More Hall Annex D&D, Project 10492 Attachment 18 -Sub-Unit 1-3-20 Bioshield North Wall Including Beam Ports FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-3-20 (Bioshield north wall and floor including beam ports)I Location Desciption:l Bioshield north wall and floor including beam portsI Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (pR/hr)Number of measurements:

85 86 96 86 52 Number of measurements needed (1). 9 9 9 9 N/A Maximum value of results: 70 13 893 107 5 Mean value of results: 22 1 235 30 1 Standard Deviation of results: 21 3 174 30 2 Degree of Freedom (2): 1.666 1.665 1.663 1.665 1.676 ti, value: 26 2 265 35 2 Guideline level: 100 20 1700 340 5 Are there sufficient measurements?

Yes Yes Yes Yes Yes Is the max value < guideline level? Yes Yes Yes Yes Yes Is jta < guideline?

Yes Yes Yes Yes Yes Does survey unit pass? Yes Yes Yes Yes Yes () as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

O -~0 University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-20 (Bioshield north wall and floor including beam ports)FSS #f Date Class Floor Surface f [X Y Alpha TAlpha Alpha Beta BetaScan BetaScan Alpha Beta Net iJR Comments-s[.i~1 ICoord. Cnord. Direct Scan Min. Scan Max. Direct Mn. Max. WIpe Wipe DPM (cps) (cpm) DPM (cpm u) ] DPM1DPM 103 1 09/23/06 1 AA I Exterior N BioShield A 0 49 0 1 0 Bioshield Northwall, Exterior -Pipes in wall/shield 4 BioShield A 1 70 0 2 303 L 40 1 400 0 1 49 q BioShield A 2 60 0 2 0 103 1 09/23/06 1 AA 11 Exterior N BioShield B 1 0 70 0 3 86 Biosideld Northwall.

Exterior Al g'l An I 2f0u n fi 0 63 40 1 300 1 8 1 68 Bihild Eti .Exterior N BioShield-, -B 2 39 0 l_E ]xeror N BioShield

[C 0~P 70lz 103 109/23/061 AA 1 Exterior N BioShield I C I I 60 BioshieidNoetliwall, Exterior -Hole Biosield Northwall, Exterior Bioshield Northwoll, Exterior Bioshield Northwall, Exterior Bioshield Northwall, Exterior 103 1 09/23/06 1 AA I I Exterior N BioShicld C 1 2 1 70 0 3 248 1 40 400 1 4 1 105 103 09/23/06 1 AA I I Exterior N BioShield C 1 3 1 33 0 2 103 D 0 39 0 1 104~[D 1KI 202 40 380 0 12 96 40 260 0 68 40 260 0 Bioshield Nortliwali, Exterior Bioshiield Northwall, Exterior Biosisield Northwa I, Exterior Bioshield Nortliwall.

Exterior 104 09/25/06 1 AA 1 1 1Exterior N BioShield D 2 104 1 09/25/06 1 AA 1 A I 0 223 1 40 300__,_1 I Exterior N BioShieldr oiU E 0 14 E 1 19 E 2 70 E 3 0 104 109/25/061 AA I I1 Exterior N Biol 0 1 0 3 0 Bioshield Northwall, Exterior 104 [09/25/06 AA 1 Exterior N BioS 104 109/25/06 AA 1 j.Exterior N BioS 156 40 300 0 36 177 40 300 3 0 204 40 300 0 0 198 40 300 3 11 Bioshield Northwall, Exterior -Hole Bioshield Northwall, Exterior Bioshield Northwall, Exterior Biosltield Northwall.

Exterior 0 1 0 1 I Exterior N BioShield F 2 0 0 0 225 1 40 1 310 1 0 0 Bioshield Northwall, Exterior I Exte 34 0 2 104 1 09/25/06 1AA F Exte 4 [I~IIZ Exterior N BioShield G 12 70 104 09/25/06 AA 104 09/25/06 AA 104 09/25/06 AA 104 09/25/06 AA 0 0 209 40 1 300 0 62 1 142 40 300 0 26 209 40 300 0 36 246 40 300 3 36 777 ASS 200 fl Bioshield Northwall, Exterior Bioshield Northwall, Exterior -Bioslideld Northwall, Exterior Bioshield Northwall, Exterior 1 1 Exterior N BioSIhield I Exterior N BioShield 1 Exterior N BioShield H 1 0 1 65-3 227 40 1 300 Bioshield Northwall Exterior 0 2 0 1 259 40 310 3 97 225 40 300 0 107 297 40 350 0 1 238 40 310 0 21 Biosltield Northwall, Exterior O"1-, -I I ., .. I I I 1 0 3 104 09/25/06 AA I Exterior N BioShield 104 09/25/06 AA I Exterior N PinShield 104 09/25/06 AA -Exterior N BinShield 104 09/25/06 AA I Exterior N BioShield I18 09/28/06 AA I Interior N BioShield 118 09/28/06 AA 1 Interior N BinShield 118 09/28/06 AA I Interior N BioShield I1 0 I I 1 2 1 3 14 0 1 3r 9 0 9 0 914 1 0 179 40 300 0 87 Bp osield Notthwall, Exterior 184 40 j 300 0 102 Bioshield Northwall, Exterior 269 40 300 [3 46 ioshield Northwall, Exterior 96 1 80 1 120 1 0 1 37 1 0 lInterior A 1 0 2 0_0 A B B I 31 0 0 1 0-1 16-1 0 0 35 2-4 2 2 4 2 4 I1 I 1 1 Interior N BioShield hIterior N BioShield Interior N BioShield C 0 0 0 JmI II 187 80 140 0 17 0 Interior 266 100 160 0 17 0 Interior 439 200 300 0 22 2 Interior 677 200 320 0 37 4 Interior 893 300 400 4 0 4 Interior 275 100 220 4 0 4 Interior 158 100 140 0 22 1 Interior 167 100 150 0 17 1 Interior 118 09/28/06 AA I I Interior N Bion D-I 2 118 09/28/06 AA 118 09/28/06 AA 118 09/28/06 AA I Interior N BioShield 1 Interior N BioShield Interior N BioShield Interior N BioShield E -1 2 F 0 16 F 11 2 B 2 1 7 0 0 0 0-0_0 0 4 2 T 2 2Y 2Y 143 1 100 1 160 1 4 1 0 0 Interior 119 109/29/06 AA I t19 09/29/06 AA I 119 1 09/29/06 AA I 250 480 140 0 _[ 2 1 D 1 1 23 467 160 1 240 1 0 7 5 D I[I______ _________________

______ _______ ______ _______ I "~ .1 '~'~ _______________________________________________

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-20 (Bioshield north wall and floor including beam ports)FSS # Date Class Floor Surface x Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net PR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (epm) (cpm) DPM (epm) (cpm) DPM DPM 119 09/29/06 AA I Interior N BioShield F 2 7 0 2 149 80 140 0 22 0 Interior 120 09/29/06 AA I Interior N BioShield A 2 01 2 166 80 140 0 2 0 Interior 120 09/29/06 AA I Interior BioShield Floor A 0 35 0 2 333 100 180 0 0 1 North Bioshield Interior 120 09/29/06 AA I Interior BioShield Floor A B 0 2 410 100 200 0 0 1 North Bioshield Interior 120 09/29/06 AA 1 Interior BioShield Floor B 0 7 0 2 427 100 300 4 0 3 Northi Bioshield Interior 120 09/29/6 A 1 Interior BioShield Floor D 0 12 0 2 440 100 200 8 7 4 INorth Bioshield Interior 120 09/29/06 AA I Interior BioShield Floor K D I is 0 4 736 100 260 4 12 3 North Bioshield Interior 120 09129/06 AA I Interior BioShiield Floor E o 0 2 392 80 220 0 22 3 North BioshiekldInterior 120 09/29106 AA I Interior BioShield Floor E 1 18 0 6 0 20 0 22 1 lNorlt Bioshield Interior 120 09/29/06 AA I Interior BioShcied Floor B 1 2 120 09/29/06 AA 1 Interior BioShield Floor C 0 5 120 09/29/06 AA 1 120 09/29/06 AA 1 120 09/29/06 AA 1 122 09/29/06 AA 1 122 09/29/06 AA I Interior BioShield Floor C 1 3 F 0 1 1 A 0 10 0 122 09/29/06 AA I N BioShield Top 122 09/29/06 AA I N BioShield To 122 09/29/06 AA I N BioShield Top 122 09/29/06 AA I N BioShield Too B I 1 0 2 1 269 120 1 200 0 1 22 0 Top North Bioshield A 1 16 0 2 231 100 1 200 0 42 0 Top North Bioshield B 2 0 E 0 182 100 200 0 320 100 200 0 (A 2 5 0 t 122 1 09/29/06 1 AA I N BioShield Top B 3 0 0 2 1 295 1 100 1 200 1 4 1 12 1 0 Too North Bioshield 1 I N N NT 122 1 09/29/06 1 AA I BioShield Top BioShield Top BioShield Top BioShield Top BioShield Top A 3 B 4 A 4 B 5 C 5 p 1 2 1 189 1 80 1 220 1 0 1 17 1 0 ITo North Bioshield 0t 5 0 2 1 301 1 100 1 200 4 1 27 0 Top North Bioshield 9 I 1~Q I 00 I 990 I 0 17 I A IT~,,N-,0IR~ht~.td 0 0 122 09/29/06 AA 1 N.122 09/29/06 AA I N.122 09/29/06 AA I N ]145 09/30/06 GA I Be 145 09/30/06 GA I Be 145 09/30/06 GA I Be 145 09/30/06 GA I Be 145 09/30/06 GA I Be 5 0 A 1 5 5 0 2 199 1 100 1 240 1 0 1 12 1 0 Too North Bioshield 1 0 0 N 8 I N 1 8 1 1 2 291 140 1 240 1 0 7 68 1 0 [Tot North Bioshield 0 1 100 1 300 1 0 70 1 1Jf ioshield exterior 0 1 100 1 300 1__ 1 1__ J ___ jdpoint am port 8 am port 7 am oort 7 N 8 0 1 100 1 300 Midpoiot 7 0 100 1 300 1 0 1 0 1 I 1Bioshield exterior 7 0 145 09/30/06 145 09/30/06 145 09/30/06 145 09/30/06 GA I I IBeam port 7 N 7 0 GA I I Beam port 7 N 17 0 100 1 300 1 0 1 5 3 IBioshield interior GA GA I N §i4 1 6 1 N 1 6 1 592 1 100 1 300 1 0 1 0 1 0 IBioshield exterior 0 100 1 300 I\lidpoitrt 145 1 09/30/061 GA I Beam port 6 Bsidpoint 145 09/30/06 GA 1 Beam port 6 150 11/08/06 AA I Interior BioShield Floor I50 1/08/06 AA 1 Interior BioShield Floor 150 11/08/06 AA I Interior BioShield Floor N 6 I i 1 45 1 ND ND 1 413 1 M 1 200 1 0 [ 421 39 ND ND 1 221 1 100 1 t80 1 0 1 53 3ioohield interior Resurvey of FSS-l20 Resrvey of FSS-120 Resurvey of FSS-120 Resurvey of FSS-120 Resurvey of FSS-120 150 11/08/06 AA 1 I 150 11/08/06 AA 1 I interior Bin]LW 28 F 0 22 ND ND 50 1 100 1 160 1 0 1 22 Interior BioShield Floor I F 1 33 T22 435 629 100 1 220 4 63 100 260 L 0 99 151 111/08/06 1 AA 1 lExterior N BioShield I F 1 0 ND 170 100 160 1 4 1 63 1 _ Bioshield Northwall, Exterior 151 11/08/06 AA 1 152 11/08/06 AA I 153 11/08/06 GA I 153 11/08/06 GA I 153 11/08/06 GA I 153 11/08/06 GA I Exterior N BioShield Interior N BioShield G 10 39 1 ND ND 110 I00 t60 0 [ 53 D 1 51 Nq 1 22 ND I ND 384 1 100 200 4 1 63 1 Bioshield Northwall, Exterior Resurvey of FSS-I119 Resurvey of FSS-145 Midpoint 0 1 100 140 Beam Port 8 Beam Port 7 Beam port 6 N 1 8 N 1 7 33 28 588 10 tO 220 1 1 -esurvey of FSS- 145 Interior ND I ND 0 100 1 140 Resurvey of FSS-145 Midpoint N I 6 33 ND t NDS I 500 I AO 33 Resurve ofFSS-145 Mid oint , ND I ND 2 100 1 140 p ENERCON Seroiom, too.

SOUTH BIOSHIELD EXTERIOR VIEW A2 A Beam Po 2 Beam Ph t 3 Beam F ar14 A0 BO CO DO EO FO GO HO 10 NORTH BIOSHIELD INTERIOR VIEW SOUTH BIOSHIELD INTERIOR VIEW Pipe penetrations between bioshield Intenor and process pit Labeled NPP 1-7 on Drawing 17 UNIVERSITY OF WASHINGTON NUCLEAR REACTOR DECOMMISSIONING BIOSHIELD WALLS SURVEY UNIT 1-3

Bioshield Liquid Scintillation Results Background Gross Net Location Date DPM DPM DPM South BioShield Interior -Beam Port 6 9/28/2006 59 71 12 South BioShield Interior -Beam Port 8 9/28/2006 59 42 0 South BioShield Interior -BO 9/28/2006 59 43 0 South BioShield Interior -CO 9/28/2006 59 33 0 South BioShield Interior -C -1 9/28/2006 59 51 0 South BioShield Interior -D 0 9/28/2006 59 50 0 South BioShield Interior -D-1 9/28/2006 59 39 0 North BioShield Interior -Beam Port 2 9/28/2006 59 55 0 North BioShield Interior -Beam Port 3 9/28/2006 59 31 0 North BioShield Interior -BO 9/28/2006 59 35 0 North BioShield Interior -CO 9/28/2006 59 54 0 North BioShield Interior -C -1 9/28/2006 59 57 0 North BioShield Interior -D 0 9/28/2006 59 57 0 North BioShield Interior -D- 1 9/28/2006 59 51 0 South BioShield Pipe -NPP 1 9/28/2006 59 58 0 South BioShield Pipe -NPP 2 9/28/2006 59 42 0 South BioShield Pipe -NPP 3 9/28/2006 59 59 0 South BioShield Pipe -NPP 4 9/28/2006 59 166 107 South BioShield Pipe -NPP 5 9/28/2006 59 47 0 South BioShield Pipe -NPP 6 9/28/2006 59 49 0 BioShield Floor -CO 9/28/2006 59 61 2 BioShield Floor -C 1 9/28/2006 59 42 0 BioShield Floor -DO 9/28/2006 59 52 0 BioShield Floor -D1 9/28/2006 59 51 0 Page 1 of I University of Washington More Hall Annex D&D, Project 10492 Attachment 19 -Sub-Unit 1-3-21 Bioshield South Wall Including Beam Ports FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-3-21 (Bioshield south wall including beam ports)I Location

Description:

I Bioshield south wall includin beam ports Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (.R/br)Number of measurements:

69 73 83 73 40 Number of measurements needed (1) 9 9 9 9 N/A Maximum value of results: 68 8 769 97 4 Mean value of results: 17 1 161 14 1 Standard Deviation of results: 16 2 131 26 1 Degree of Freedom (2) 1.669 1.668 1.666 1.668 1.684 it value: 20 1 185 19 1 Guideline level: 100 20 1700 340 5 Are there sufficient measurements?

Yes Yes Yes Yes Yes Is the max value < guideline level? Yes Yes Yes Yes Yes Is g.- < guideline?

Yes Yes Yes Yes Yes Does survey unit pass? Yes Yes Yes Yes Yes (1) as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min, Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 110 09/27/06 AA I Exterior S BioShield A 0 29 0 2 96 40 200 4 0 Exterior 110 09/27/06 AA I Exterior S BioShield A 1 0 0 1 89 40 200 0 0 Exterior 110 09/27/06 AA I Exterior S BioShield A 2 6 0 1 128 40 200 0 0 Exterior 110 09/27/06 AA I Exterior S BioSiield B 0 48 0 3 32 40 200 0 0 Exterior 110 09/27/06 AA 1 Exterior S BioShield B I 20 0 1 67 40 200 0 0 Exterior 110 09/27/06 AA 1 Exterior S BioSiteld B 2 11 0 1 60 40 200 0 45 Exterior 110 09/27/06 AA I Exterior S BioShield C 0 16 0 1 55 40 200 0 0 Exterior 110 09/27/06 AA 1 Exterior S BioShield C 1 0 0 1 92 40 200 0 5 Exterior 110 09/27/06 AA I Exterior S BioShield C 2 16 0 1 158 40 300 0 10 Exterior 110 09/27/06 AA I Exterior S BioShield D 0 .6 0 1 69 40 200 0 0 Exterior 110 09/27/06 AA I Exterior S BioShield D 1 16 0 1 28 40 200 0 15 Exterior 110 09/27/06 AA I Exterior S BioShield D P2 38 0 2 105 40 200 0 0 Exterior 110 09/27/06 AA I Exterior S BioShield D 3 38 0 2 228 40 300 -0 0 Exterior 110 09/27/06 AA 1 Exterior S BioShield E 0 0 0 1 99 40 200 0 40 Exterior 110 09/27/06 AA 1 Exterior S BioShield E 1 2 0 1 78 40 200 0 0 Exterior 110 09/27/06 AA I Exterior S BioShield E 2 2 0 1 185 40 300 0 0 Exterior 110 09/27/06 AA 1 Exterior S BioShield E 3 61 0 4 107 40 200 0 0 lExterior 110 09/27/06 1 Exterior S BioShield F S10 ]09/27/06 AA Exterior S Bion 110 09/27/06 AA Exterior S Bio!0 1.2 3 20 0 2 Exterior 0 1 o 1 67 187 12-4 40 40-4-0 4W 200 300-30-0 2;4-0 0 0-T 0 Exterior Exterior Exterior Exterior 110 09/27/06 AA I F 61 0 4 110 1 09/27/06 AA 110 09/27/06 AA i10 1 09/27/06 AA 110 1 09/27/06 AA 1 I I I G 0 20 0 1 10 Exterior S BioShield G.Exterior S BioSield a G Exterior S BioShield I 3 1 2 3 0 43 16 0 0-0 0 2-1 1-1 240 0 0 Exterior 131 153 108 128 40 40 40 40 240 300 240 250 0 0 Exterior 040 0 45 Exterior 240 0 35 Exterior It1O ri / 7fl70 A A I FTtprinr 14 110 09/27/06 AA 0 52 0 Exterior S BiriShild H 110 09/27/06 AA I Exterior S BioShield 110 09/27/06 AA 1 Ext 110 1 09/27/061 AA 1 Ext 110 1 09/27/06 AA I I Ext 1-H 1 l 2 0 0 0 Exterior 38 0 21 I 1 0.0 11 0 1-2-1 121 110 117 856 40 40 40 40 240 1 0 1 45j 1_ JExterior 250 0 0 Exterior 110 09/27/06 AA 110 09/27/06 AA 110 1 09/27/06 AA 123 09/29/06 AA Exterior S BioShield ExteriorS BioShield Exterior S BioShield S BioShield Too 1 1 20 0 240 0 Exterior 1 2 16 S 3 _20 0 0 0 0 1 2-2-2 0 0 Exterior I A 10 85 210 325 12-1 40 100 210 220 200 F8-0 0 T 0 T 0 0 7 T Exterior 123 1 09/29/06 1 AA I S BioSltield Top B 0 16 1 S BioShield Top A I I S BioShield Top B 10 5_0 0 0 0 2 I I S BioShield Too A 2 2 2 2 160 0 22 0 rop South Bioshield 123 ADf/O9/06 AA 1 xt.Rin'ildTan l:l 3'291 140 265 100 299 1 140 123 09/29/06 AA 0-I 220 300 320 0 4 0 0 0 0 Top South Bioshield 58 1 1"oo South Bioshield 123 09/29/06 AA S BioSltield Top 123 1 09/29/06 AA I S BinShield Ton 123 1 09/29/06 AA i 1 S BioSlteld To 1 A 13 A B7 3 3 4 0 5 0 10 0 123 1 09/29/06 AA I 0-1dT-4 2 2-2 2 231 100 240 0 21 212 160 12 0 0 320 140 30 AA I S Bi-Sld, 32 0 88 0 1!0 0 0 Top South Bioshield Top South Bioshield Tooo South Bioshield AA B 6 146 800 200 1 0 20 In ltterior 204 100 220 1 0 1 1 11 Interior C -1 5___I -5I 267 1i20 220 I_0 1 0 L 2 Interior 316 J 100 1 220 4 1 0[ 3 Intterior University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-21 (Bioshield south wall including beam ports)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpn) (cpm) DPM (cpm) (cpm) DPM DPM 124 09/29/06 AA I Interior S BioShield D 0 16 0 4 316 100 220 0 26 3 Interior 124 09129/06 AA 1 Interior S BioShield D -1 5 0 2 363 120 240 0 62 3 Interior 124 09/29/06 AA 1 Interior S BioShield E 0 5 0 2 180 100 220 4 0 2 Interior 124 09/29/06 AA I Interior S BioShield E -1 1 Interior 124 09/29/06 AA 124 09/29/06 AA 124 09/29/06 AA 124 09/29/06 1 AA I 1 1 I Interior S BioShield Interior S BioShield Interior S BioShield Interior S BioShield F 0 0 0 2 170 100 1 220 0 0 1 nterior 1 10 5 5 5 0 2 T 2 2 140 80 200 4 0 B 2 0 0-1 0 1 nterior[nterior Interior nterior Iterior t deonA.l 124 09/29/06 AA 1 Interior S BioShield C 1 0 104 124 09/29/06 1 AA 1 Interior S BioShield 124 09/29/06 AA " I Interior 124 09/29/06 AA 1 Interior D D-I Eff 1 2 1-21 26 10 10 0 2 202 100 1 260 1 4 87 0 2[2 124 09/29/06 124 09/29/06 124 09/29/06 124 09/29/06 AA I Interior S BioShield 110 127 123 195 120 1 200 0 8 0-0 67 97 11 0-0 T 1-1 Interior hiterior Iterior interior 0 2 AA I Interior S BioShield F 2 16 0 2 100 200 AA I hItterior A 2 5 0 2 AA I Interior C 2 5 153 99 415 0 100 100 100 100 200 200 300 300 0 0 0 Interior Interior -p Bioshield, Midpoint 130 09/30/06 GA I Beam port 2 S 2 GA I Beam port 2] GA- 1Beam po S S S 2 2 130 1 09/30/06 GA Beam Do 2 130 1 09/30/06 GA I Beam port 2 130 130 130 130 09/30/06 GA 09/30/06 GA 09/30/06 GA 09/30/06 GA I Beam port 3 I Beam port 3 I Beam port 3 I Beam Dort 3 S S 2 3 3 3 3 4 4 0 0 0 0 327 0 0 130 1 09/30/06 1 GA I I 300 I00-300 Midpoint Midpoint Beam Port 4 100 100 100 100 100 100 100 100.100 300 1 4 0 4 300 1 0 5 3 B i oshield i Midpoint 1 t I [Midpoint 130 1 09/30/06 130 09/30/06 130 09/30/06 130 09/30/06 GA GA I earn port 4 I Beam port 4 S Bioshield interior Bioshield exterior Midpoint Midpoint Midpoint S 4 GA II Beam S 4 0 150 769 GA I 1 Beam r S -300 0 154 1 11/08/061 GA Beam Port 3 S ND 81 25 3 Biosltield interior 155 I 1100100 AA I-t*tO MFt KfFt 155 1 11/08/06 interior S BioShield E 1 39 ND ENERCON Servicm. ino.

NORTH BIOSHIELD EXTERIOR VIEW A2 Beam Pc rt 6 Beam Po 7 Beam P( rt 8 Al 10 HO GO FO EO DO CO BO AO SOUTH BIOSHIELD EXTERIOR VIEW A2 Beam Port 2 Beam P rt 3 Beam F art AO BO CO DO EO FO GO HO 10 NORTH BIOSHIELD INTERIOR VIEW SOUTH BIOSHIELD INTERIOR VIEW A2 A2 A1 Beam Port E Beam Jrtr7 3eam Port 6 AO BO CO DO EO FO Beam Port 4 Beam ort 3 B. rPort 2 Al FO EO DO CO BO AO B-i C-1 D-1 E-l1 E-1 Pipe penetrations between bioshield interior and process pt- Labeled NPP 1-7 on Drawing 17 B-l UNIVERSITY OF WASHINGTON NUCLEAR REACTOR DECOMMISSIONING BIOSHIELD WALLS SURVEY UNIT 1-3

Bioshield Liquid Scintillation Results Background Gross Net Location Date DPM DPM DPM South BioShield Interior -Beam Port 6 9/28/2006 59 71 12 South BioShield Interior -Beam Port 8 9/28/2006 59 42 0 South BioShield Interior -BO 9/28/2006 59 43 0 South BioShield Interior -CO 9/28/2006 59 33 0 South BioShield Interior -C -1 9/28/2006 59 51 0 South BioShield Interior -D 0 9/28/2006 59 50 0 South BioShield Interior -D-1 9/28/2006 59 39 0 North BioShield Interior -Beam Port 2 9/28/2006 59 55 0 North BioSbield Interior -Beam Port 3 9/28/2006 59 31 0 North BioShield Interior -BO 9/28/2006 59 35 0 North BioShield Interior -CO 9/28/2006 59 54 0 North BioShield Interior -C -1 9/28/2006 59 57 0 North BioShield Interior -D 0 9/28/2006 59 57 0 North BioShield Interior -D-1 9/28/2006 59 51 0 South BioShield Pipe -NPP 1 9/28/2006 59 58 0 South BioShield Pipe -NPP 2 9/28/2006 59 42 0 South BioShield Pipe -NPP 3 9/28/2006 59 59 0 South BioShield Pipe -NPP 4 9/28/2006 59 166 107 South BioShield Pipe -NPP 5 9/28/2006 59 47 0 South BioShield Pipe -NPP 6 9/28/2006 59 49 0 BioShield Floor -CO 9/28/2006 59 61 2 BioShield Floor -C 1 9/28/2006 59 42 0 BioShield Floor -DO 9/28/2006 59 52 0 BioShield Floor -D1 9/28/2006 59 51 0 Page 1 of 1 University of Washington More Hall Annex D&D, Project 10492 Attachment.20

-Sub-Unit 1-3-30 Process Pit FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-3-30 (Process pit)I Location

Description:

IProcess pit I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm7) (dpm/100cm2) (dpm/100cm) (dpm/100cm) (g.R/hr)Number of measurements:

38 51 51 51 14 Number of measurements needed (1): 9 9 9 9 N/A Maximum value of results: 40 17 1667 76 1 Mean value of results: 12 1 117 7 0 Standard Deviation of results: 10 3 271 16 1 Degree of Freedom (2): 1.687 1.677 1.677 1.677 1.771 g, value: 15 2 181 11 1 Guideline level: 100 20 5000 1000 5 Are there sufficient measurements?

Yes Yes Yes Yes Yes Is the max value < guideline level? Yes Yes Yes Yes Yes Is j.+/-, < guideline?

Yes Yes Yes Yes Yes Does survey unit pass? Yes Yes Yes Yes Yes as interpolated from NUREG/CR-5 849 Table B-2 (-) from NUREG/CR-5849 Table B-I for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-30 (Process pit)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Mln. Scan Max. Direct Min. Max. Wipe Wipe I DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 037 09/01/06 AA 1 Pipe NPP 1 0 50 50 0 0 Penetration internals to Stop 037 09/01/06 AA I Pipe NPP 2 0 50 50 0 0 Penetration internals to stop 037 09/01/06 AA I Pipe NPP 3 0 50 50 17 0 Penetration interuals to stop 037 09/01/06 AA 1- Pipe NPP 4 0 50 50 8 48 Penetration internals to stop 037 09/01/06 AA I Pipe NPP 5 0 76 Penetration internals to stop 037 09/01/06 AA 1 T Pipe NPP 6 0 50 50 0 -0 Penetration internals to stop 037 09/01/06 AA I Pipe NPP 7 0 50 50 0 20 Penetration internals to stop 037 09/01/06 AA I Pipe EPP 1 0 50 50 0 0 Penetration internals to stop 037 09/01/06 AA I Pipe EPP 2 0 50 50 0 0 Penetration internals to stop 037 09/01/06 AA 1 Pi e EPP 3 0 50 50 0 0 Penetration internals to stop 037 09/01/06 AA I Pipe EPP 6 0 50 50 0 0 Penetration internals to stop 037 09/01/06 AA 1 Pipe SPP 1 0 50 50 0 6 Penetration internals to stop 037 09/01/06 AA I Pipe WPP I 0 50 50 0 0 Penetration internals to stop 038 09/01/06 AA t -Wall A 0 26 ND ND 122 0 300 4 30 1 m^2 E wall -Process Pit 03? 09/01/06 AA I E Wall A 1 12 ND ND 114 0 280 0 0 1 m^2 E wall -Process Pit 038 09/01/06 AA I IF Wall B 0 35 ND ND 74 0 280 0 0 11 m^2 E wall -Process Pit 0381 09/01/06 AA I fE Watt B 1 12 ND ND 17 0 400 0 34 11 m^2 E wall -Process Pit 0381 09/01/06 AA 1 I Floor 038 09/01/06 AA I I FIoor 038 09/Ot/06 AA [ Floor 038 09/01/06 AA I Floor A 0 7 ND ND 0 0 360 0 0 0 1 ra^2 floor -Process pit 3 ND 21 ND 17 ND ND 124 0 320 4 0 0 I m^2 floor -Process pit 188 0 320 0 0 137 0 340 0 0 r-]r-]B .1 038 109/01/061 AA I I Floor C 1 0 12 ND I ND D 207 0 1 60 1 0 1 21 0 Tm^2 floor -Process oit Floor C 1 3 1 ND I ND 1 99 1 0 1 380 1 0 1 0 1 0 1 rI^2 floor -Process pit Flto 0 17 N I ND 1 156 1 0 1 800 1 0 1 0 1 0 1 m^2 floor -Process pit 038 109/01/061 AA I Flooj EI 1 12 1~ 194 1 0 300 1 _0 ~ 0 '2 f~l~oor -Proceasspit 1 29 1 0O 300 1 4 J0 1 __ J Iý MA2 N Wall -Process pit 039 109/01/06 1 AA I i N Wall A 0 0 039 109/01/061 AA 1 1 4 Wall A 1 17 [ ND I ND 135 0 340 0 11 1 ra^2 N Wall -Process oit 039 039 N yWall IN Wall B 1 01 3 1 NDl t'J fl I O I 0 NO NO 0 1 0 280 0 0 p j aTiA2 N Wall -Process it I I ^ N Wall niI ND ND 17 0 360 0 44 1 mn2 N Wall -Process pit 039 109/01/061 AA 1 1 ND 0 300 0 0 I m^2 N Watt -Process pit -039 1 09/01/06 1 AA I I IN Wall C 11 7 ND 0 600 0 0 1 ron2 N 039 039 D 2 3 1D _I 1 12 ND ND ND ND ND 21 1 0 300 0 0 1 rn^2 N N D 36 039 1 09/01/06 1 AA I t IW Wall AT 0 0 0 0 280 0 0 320 0 0 260 0 0 300 4 0 I m^2 N Wall -Process pit 1 m^2 W Wall -Process pit 1 Ma2 W Wall -Process pit 1 m^2 W Wall -Process pit 039 109/01/061 AA 1 1 W Wall A 1 0 I1 1 W Wall B 0 12 1 ND ND 31 t W Wall B ND ND 135 1 0 1 260 1 0 1 30 039 109/01/061 AA I S Wall 039 1 09/01/061 AA I I S Wall I A I 0 0 3 ND ND ND 0 0 I 039 09/01/06 AA I S Wall 039 09/01/06 AA 1 IS Wall 039 09/01/06 AA I S Wall 039 09/01/06 AA I S Wall B ND 78 1 0 1 300 1 0 0 1 12 0 40 ND ND ND ND 0 324 0 240 1 0 1 0 I m^2 W Wall -Process pit Im"2 S Wall -Process pit I m^2 S Wall -Process pit I in2 S Wall -Process pit 1 m^2 S Wall -Process pit 1m2 S Wall -Process pit Imrn^2 S Wall -Process pit I m^2 S Wall -Process pit I ro2 S Walt -Process pit Penetration istemals -Post decon 0 1 300 1 0 1 0 C 1 26[ 61 _ 0 039 09/01/06 AA I1 039 09/01/06 AA 051 09/06/06 AA 11 070 09/09/06 AA I S Wall I D 1 0 30 1 ND ND 0 0 S Wall Pipe Sumo D NPP A A 1 1 12 ND ND 1 101 0 1 300 1 0 1 0 10 0 0 1667 40 80 1 1 60 60 1 310 1 0 1 43 1 1 IWest Side -After decon/paint removal 070 [09/09/06 AA 1 umrp 070 [09/09/06 AA I Sump 070 1 09/09/06 AA I Sump 0 4 A 0z 30 A 20 13 0 0 0-5 3 1 iast Side -Artel 119 60 320 0 18 1 outh Side -After decon/paint removal?Rn fl OF a I a~or- ]rrenlnil pn 070 09/09/06 AA I Sui 070 09/09/06 [AA I Su.I nn 01 fin 91 280 1 20 1 10- 1 11 1'Floor -Aflcr decon/aint removal A 1 0 1 1 1 0 1 1 0 1 260 1 3 1 0 1 1 ILid -Afler decou/paint removal ENERCON Services, isa.

NORTH WALL Pipe penetratons between bioshield interior and process pit WEST WALL BO B1 Al AO NPP-- le.t to right 000 C0 000 Al B1 C1 D1 AO BO CO DO FLOOR EAST WALL Al AO0 r=PP-,@EPP-2 EPP-3 BO QE4PP4 B 1 SOUTH WALL DO CO BO AO D1 C1 B1 Al 0SPP-0 Pipe penetration UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS REACTOR DECOMMISSIONING Drawn by: DM REACTOR ROOM PROCESS PIT Drawing 17 SURVEY UNIT 1-3 Enercon Services _

University of Washington More Hall Annex D&D, Project 10492 Attachment 21 -Sub-Unit 1-3-40 Reactor Room Floor West Grids A-G FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2

• Final Status Decision Summary for Unit 1-3-40 (Reactor room floor west grids A-G)Class:I AA I Certainty

%I Location

Description:

lReactor room floor west eids A-G I I.F W J.~Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results Al Surfaces (dpm/lOOcm2) (dpm/lOOcm

2) (dpm/lOOcm

1) (j+/-R/hr)Number of measurements:

65 65 65 65 4 Number of measurements needed (1). 9 9 9 9 N/A Maximum value of results: 34 7 1087 85 0 Mean value of results: 13 1 152 14 0 Standard Deviation of results: 9 2 203 20 0 Degree of Freedom (2) 1.670 1.670 1.670 1.670 2.353ýt, value: 14 1 194 18 0 Guideline level: 100 20 5000 1000 5 Are there sufficient measurements?

Yes Yes Yes Yes Yes Is the max value < guideline level? Yes Yes Yes Yes Yes Is ýt < guideline?.

Yes Yes Yes Yes Yes Does survey unit pass? Yes Yes Yes Yes Yes as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-40 (Reactor room floor west grids A-G)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta BetaScan BetaScan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (rpm) DPM (cpm) (cpm) DPM DPM-7105 09/25106 AA I Floor A 0 34 0 2 445 40 320 0 0 0 FSS Done Prior To Removing -105 09/25/06 AA I Floor A 1 9 0 1 238 40 300 0 0 105 09/25/06 AA I Floor A 2 19 0 1 280 40 380 3 52 0 Dirt Floor 105 09/25/06 AA I Floor A 3 34 0 2 257 40 380 3 1 0 Concrete Floor 105 09/25/06 AA I Floor A 4 19 0 2 282 40 380 0 62 0 Concrte Floor 105 09/25/06 AA 1 Floor A 5 19 0 1 341 40 400 0 6 105 09/25/06 AA 1 Floor B 0 24 0 1 514 40 460 0 6 105 09/25/06 AA I Floor B 1 4 0 1 630 40 500 0 36 105 09/25/06 AA I Floor B 2 14 0 1 263 40 360 3 0 105 09t25106 AA I Floor B 3 9 0 1 345 40 400 0 52 105 09/25/06 AA 1 Floor C 0 0 0 0 301 40 310 0 0 105 09/25/06 AA I Floor C 1 4 0 1 339 40 380 3 0 105 09/25/06 AA I Floor C 2 4 0 1 292 40 310 0 41 105 09/25/06 AA I Floor C 3 14 0 I 253 40 310 0 26 105 09/25/06 AA I Floor C 4 0 0 1 246 40 310 3 57 105 09/25/06 AA I Floor D 0 19 0 1 311 40 380 0 6 105 09/25/06 AA I Floor D I 14 0 1 282 40 380 0 1 109 09/26/06 AA 1 Floor A 6 27 0 3 107 40 300 0 0 109 09/26/06 AA 1 Floor A 7 22 0 2 78 40 300 0 20 109 09/26/06 AA I Floor A 8 0 0 1 842 40 600 3 11 109 09/26/06 AA I Floor A 9 22 0 1 23 40 280 0 0 109 09/26/06 AA 1 Floor A 10 13 0 1 0 40 260 0 0 109 1 09/26/06 AA I Floor B 4 18 0 1 74 40 300 0 0 109 09/26/06 AA I Floor B 5 4 0 1 153 40 300 3 39 109 09/26/06 AA I Floor B 6 13 0 1 94 40 300 0 62 109 09/26/06 AA I Floor B 7 13 0 1 1087 40 450 0 11 109 09/26/06 AA I Floor B 8 18 0 1 56 40 300 0 25 109 09/26/06 AA I Floor B 9 9 0 1 34 40 300 0 39 109 09/26/06 AA I Floor B 10 13 0 1 44 40 280 0 0 109 09/26/06 AA I Floor C 5 9 0 1 28 40 260 0 30 109 09/26/06 AA I Floor C 6 22 0 2 1 40 260 0 0 109 09/26/06 AA I Floor C 7 22 0 1 34 40 260 3 0 109 1 09/26/06 AA 1 Floor C 8 12 0 1 113 40 300 3 34 109 09/26/06 AA 1 Floor C 9 31 0 2 96 40 300 0 0 109 09/26/06 AA i Floor C 10 0 -0 1 7 40 260 3 39 -109 09/26/06 AA I Floor D 2 13 0 I 34 40 280 0 0 109 09/26/06 AA 1 Floor D3 3 18 0 I 30 40 280 0 20 10909/26/06 AA 3 Floor D 4 0 0 1 30 40 280 0 0 109 09/26/06 AA 1 Floor 1 5 18 0 2 56 40 300 0 30 109 09/26/06 AA 1 Floor D 6 9 0 1 11 40 260 0 0 log 92/6 AA 1 ForD 7 8 4 280 3 0 109 09/26/06 AA I Floor D 10 0 0 1 5 40 260 3 85 109 09/26/06 AA 1 Fioor E 7 9 0 1 42 40 300 0 16 109 092/6AA 1 ForE I 3 0 1 0 40 2600 0 109 09/26/06 AA I Floor D 2 13 0 1 345 40 2830 0 0 109 09/26/06 AA I Floor D 3 08 0 1 30 40 280 0 20 109 09126/06 AA I Floor D 4 08 0 1 30 40 280 0 0 109 09/26/06 AA I Floor D 5 is1 0 21 5633 40 300 0 30 109 09/26/06 AA I Floor D to 0 0 1 0 40 260 3 05 109 09/26/06 AA 1 Floor E 0 9 0 1 19 40 300 0 016 ENERCON Services, no.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-40 (Reactor room floor west grids A-G)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta BetaScan BetaScan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpn) (cpm) DPM DPM 109 09/26/06 AA I Floor E 8 22 0 2 56 40 300 3 0 109 09/26/06 AA I Floor E 9 13 0 1 80 40 300 3 0 109 09/26/06 AA t Floor E 10 0 0 1 115 40 300 7 0 109 09/26/06 AA 1 Floor F 8 0 0 1 17 40 260 0 20 109 09/26/06 AA I Floor F 9 18 0 1 68 40 300 0 0 109 09/26/06 AA I Floor F 10 0 0 1 113 40 310 0 2 109 09/26/06 AA I Floor G 8 9 0 1 0 40 240 0 0 109 09/26/06 AA I Floor G 9 18 0 1 26 40 280 0 0 109 09/26/06 AA I Floor G 10 18 0 1 100 40 300 0 0 109 09/26/06 AA I Floor F a 4 0 1 52 40 280 3 0 109 09/26/06 AA I Floor F 1 0 0 1 15 40 280 3 0 109 09/26/06 AA I Floor G 0 22 0 3 0 40 240 3 16 109 09/26/06 AA 1 Floor G 1 0 0 1 0 40 240 0 0 121 09/29/06 AA I Floor A 0 121 09/29/06 AA I Floor A I__._1F21 09/29/06 AA I Floor A 2 121 09/29/06 AA I Floor A 3 21 09/29/06 A 1 ForA 4 121 09/29/06 AA I Floor A 4 121 092/6 AA 1 Floor A 5 121 09/29/06 AA 1 Floor B 0 121 09/29/06 AA I Floor B I 121 09/29106 1A Floor B 2 121 09/29/06 AA I Floor B 3 121 109/29/06 1AA I IFloor C 0 121 09/29/06 AA I Floor C I 121 09/29106 AA I Flour C 2 12[ ]9/29/06 AA I Floor C 3 121 09/29/06 AA I Floor D 0 121 09/29/06 AA I Floor D L ENERCON Services i

University of Washington More Hall Annex D&D, Project 10492 Attachment 22 -Sub-Unit 1-3-41 Reactor Room Floor East Grids H-N FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-3-41 (Reactor room floor east grids H-N)I >~I Unit Designator:

1-3-41 1 .Class: AA I .Certainty

L iJ Location

Description:

Reactor room floor east grids H-N Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (jR/hr)Number of measurements:

57 57 57 57 57 Number of measurements needed (1): 9 9 9 9 N/A Maximum value of results: 29 4 347 71 1 Mean value of results: 5 0 182 9 1 Standard Deviation of results: 7 1 73 18 0 Degree of Freedom (2): 1.673 1.673 1.673 1.673 1.673 4c, value: 7 0 198 13 1 Guideline level: 100 20 5000 1000 5 Are there sufficient measurements?

Yes Yes Yes Yes Yes Is the max value < guideline level? Yes Yes Yes Yes Yes Is J.+/- < guideline?

Yes Yes Yes Yes Yes Does .survey unit pass? Yes Yes Yes Yes Yes (1) as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-I for the listed certainty

%ENERCON Services.

inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-41 (Reactor room floor east grids H-N)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 109 09/26/06 AA 1 Floor H 8 0 0 1 34 40 300 3 0 0 Pipe 109 09/26/06 AA 1 Floor H 9 9 0 1 26 40 280 0 0 0 109 09/26/06 AA I Floor H 10 0 0 1 15 40 260 0 0 0 109 09/26/06 AA I Floor 1 8 0 0 1 34 40 300 0 2 0 109 09/26/06 AA I Floor 1 9 9 0 1 88 40 300 3 0 0 109 09/26/06 AA I Floor H 10 4 0 1 155 40 310 3 2 10 113 09/28/06 AA 1 Floor H 0 0 0 1 243 40 300 0 35 1 113 09/28/06 AA 1 Floor 1 1 0 0 1 126 40 240 0 5 1 113 09/28/06 AA 1 Floor 1 0 0 0 I 171 40 280 0 0 1 113 09/28/06 AA 1 Floor I 1 0 0 1 137 40 210 0 45 1 113 09/28/06 AA I Floor J 0 3 0 1 156 40 220 0 0 1 113 09/28/06 AA t Floor J 1 7 0 2 173 40 280 0 0 1 113 09/28/06 AA I Floor K 2 0 0 1 200 40 300 0 0 1 113 09/28/06 AA I Floor K 0 3 0 2 184 40 300 4 0 1 113 09/28/06 AA I Floor K 1 3 0 2 234 40 240 0 0 1 113 09/28/06 AA I Floor K 2 20 0 3 151 40 200 0 0 1 113 09/28/06 AA I Floor K 3 3 0 1 93 40 240 0 15 1 113 09/28/06 AA 1 Floor L 0 7 0 1 144 40 280 0 0 1 113 09/28/06 AA I Floor L 1 3 0 1 171 40 280 0 0 1 113 09/28/06 AA I Floor L 2 0 0 1 182 40. 200 0 0 1 113 09/28/06 AA I Floor L 3 0 0 1 131 40 280 0 0 1 113 09/28/06 AA I Floor M 0 3 0 1 175 40 240 0 0 1 113 09/28/06 AA I Floor M 1 3 0 1 151 40 300 0 0 1 113 09/28/06 AA I Floor M 2 3 0 1 189 40 300 0 5 1 113 09/28/06 AA I Floor M 3 24 0 2 216 40 300 0 35 1 113 09/28/06 AA I Floor N 0 0 0 1 173 40 300 0 10 1 113 09/28/06 AA I Floor J 8 0 0 1 158 40 240 0 0 1 113 09/28/06 AA I Floor 1 9 7 0 1 131 40 240 0 0 1 113 09/28/06 AA I Floor 1 10 7 0 1 193 40 280 0 40 1 1 13 09/28/06 AA I Floor K 7 0 0 1 184 40 280 0 71 1 113 09/28/06 AA I Floor K 8 0 0 1 182 40 280 0 0 1 113 09/28/06 AA I Floor K 9 0 0 1 173 1 40 260 10 71 11 113 09/28/06 AA I 1 IFloor K 10 T 0 1 234 40 300 10 0 1 113 09/29/06 AA I Floor L 9 3 0 1 247 40 310 1 0 0 1 113 09/28/06 AA I Floor L 10 3 0 2 211 40 300 0 0 1 113 09/28/06 AA I Floor M 8 20 0 2 281 40 320 0 0 1 113 09/28/06 AA I Floor M 9 29 0 3 153 40_ 240 0 0 1 113 09/28/06 AA I Floor M 10 1 3 0 1 1 241 40 300 0 0 1 113 09/28/06 AA- I Floor N 8 3 0 1 180 40 K 300 0 5 1 113 09/28/06 AA I Floor N 9 3 0 1 1 198 40 300 0 0 1 1 113 09/28/06 AA I Floor N 10 0 0 1 "162 1 40 260 0 51 1 113 09/28/06 AA I I Flo1or N 1 7 0 1 229 40 300 0 0 1 113 09/28/06 AA I Floor N 2- 3 0 1 234 40 300 1 0 0 1 13 09/28/06 AA I F our N 4 0 0 1 104 40 200 0 35 1 E113 09/28/06 AA I [Floor N 4 0 0 1 126 40 210 0 35 1 1 13 09/28/06 AA I IFlour N 5 0 0 1 54 40 -200 0 0 1 1 25 09/29/06 AA I IFloor L 4 s 09 2_ 267 100 300 0 30 1 125 09/29/06 AA I1 Floor L 5 1 2 261 100 320 0 10 1 125 1 09/29/06 AA I Floor L 16 12 0 2 201 100 1 320 1 0 1 0 1 1 125 I IFloor I L 1 7 12 0 1 1 1 229 1 100 1 300 1 0 1 0 1 125 IIFloor I 125 1 09/29/06 1 AA I Floor 4 ENERCON S-rvi.., in.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-3-41 (Reactor room floor east grids H-N)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta BetaScan Beta Scan Alpha Beta Net pJR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 125 09/29/06 AA I Floor M 5 20 0 3 293 100 320 0 0 1 125 09/29/06 AA I Floor M 6 20 0 2 347 100 300 0 0 _125 09/29/06 AA I Floor M 7 0 0 3 203 100 300 0 0 1 125 09/29/06 AA I Floor N 6 8 0 2 237 100 320 4 35 1 125 09/29/06 AA I Floor N 7 20 0 2 347 100 320 0 0 1 __I ENERCON Srvices, ic.

University of Washington More Hall Annex D&D, Project 10492 Attachment 23 -Sub-Unit 1-4-1 Crystal Spectroscopy Room Ceiling, East, North, and West #2 Walls FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-4-1 (Crystal spectroscopy room ceiling, east, north, and west #2 walls)I Location

Description:

ICrystal spectroscopy room ceiling, east, north, and west #2 walls I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (IjR/hr)Number of measurements:

87 87 87 87 N/A Number of measurements needed (1): 9 9 9 9 N/A Maximum value of results: 36 4 262 88 N/A Mean value of results: 9 0 144 15 N/A Standard Deviation of results: 9 1 53 21 N/A (2)Degree of Freedom : 1.665 1.665 1.665 1.665 N/A ga value: 10 1 153 19 N/A Guideline level: 100 20 5000 1000 N/A Are there sufficient measurements?

Yes Yes Yes Yes N/A Is the max value < guideline level? Yes Yes Yes Yes Ný/A Is ýt, < guideline?

Yes Yes Yes Yes N/A Does survey unit pass? Yes Yes Yes Yes N/A () as interpolated from NURREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-4-1 (Crystal spectroscopy room ceiling, east, north, and west #2 walls)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta BetaScan BetaScan Alpha Beta Net pR Comments Conrd. Coord. Direct Scan Mn. Sean Max. Direct Min. Max. Wipe Wipe DPM (cpm) (epni) DPM (cpin) (epm) DPM DPM 074 09/12/06 AA I Ceiling A 0 0 0 I 99 40 200 4 16 Ceiling tiles 074 09/12/06 AA I Ceiling A 1 8 0 2 134 40 260 0 0 Ceiling tiles 074 09/12/06 AA I Ceiling A 2 4 0 1 89 40 240 0 0 CCeiling tiles 074 09/12/06 AA I Ceiling A 3 26 0 4 160 40 280 0 25 Ceiling tiles 074 09/12/06 AA I ]Ceiling B 0 12 0 2 180 40 300 0 25 Ceiling tiles 074 09/12/06 AA I Ceiling B 1 26 0 4 119 40 260 0 7 Ceiling tiles 074 09/12/06 AA I Ceiling B 2 8 0 1 193 40 300 0 7 Ceiling tiles 074 09/12/06 AA I Ceiling B 3 0 0 1 106 40 240 0 39 Ceiling tiles 074 09/12/06 AA I Ceiling C 10 0 0 1 84 40 210 0 21 Ceiling tiles 074 09/12/06 AA I Ceiling C 1 0 0 1 193 40 300 0 7 Ceiling tiles 074 09/12/06 AA 1 Ceiling C 2 8 0 2 163 40 300 0 49 Ceilin tiles 074 09/12/06 AA 1 Ceiling C 3 0 0 1 174 40 300 0 76 Ceiling tiles 075 09/12/06 AA I E Wall A 0 8 1 2 141 10O 200 0 44 075 09/12/06 AA I E Wall A 1 3 0 1 121 100 200 0 49 075 09/12/06 AA 1 E Wall A 2 3 0 1 117 100 200 0 63 075 09/12/06 AA I E Wall B 0 3 0 1 108 100 200 0 21 075 09/12/06 AA I E Wall B 1 13 1 3 143 100 200 0 0 075 09/12/06 AA I E Wall B 2 3 0 1 132 100 200 0 7 1/10 grid obstructed 075 09/12/06 AA I E Wall C 0 13 1 3 121 100 200 0 0 3/4 grid obstructed (obstruction surveyed)075 09/12/06 AA 1 E Wall C 1 17 2 4 148 100 200 4 0 3/4 grid obstructed (obstruction surveyed)075 09/12/06 AA I EWall C 2 3 1 1 132 100 200 4 35 075 09/12/06 AA I E Wall D 0 8 1 2 104 100 200 0 35 075 09/12/06 AA I E Wall D 1 8 1 2 88 100 200 0 2 075 09/12/06 AA 1 E Wall D 2 3 0 1 137 100 200 0 39 075 09/12/06 AA I EWall E 0 13 I 3 148 100 200 0 2 075 09/12/06 AA 1 EWall E 1 3 0 1 117 too 180 0 7 075 09/12/06 AA 1 E Wall E 2 8 1 2 106 100 200 0 86 078 09/13/06 AA I Ceiling D 0 7 0 2 60 40 280 0 0 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling D 1 0 0 1 196 40 320 0 0 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling D 2 3 0 1 76 40 280 0 0 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling D 3 12 0 2 119 40 300 0 0 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA --Ceiling E 0 0 0 1 0 40 200 0 38 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA 1 Ceiling E 1 0 0 1 13 40 210 0 0 Ceiling tiles all accessible surfnces onceiling 078 09/13/06 AA I Ceiling E 2 0 0 1 19 40 260 0 3 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling E 3 3 0 1 156 40 30 0 0 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA 1 Ceiling F 0 12 0 2 221 46 320 0 0 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling F 1 7 0 2 188 40 310 0 0 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling F 2 0 0 1 176 40 310 0 88 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling F 3 21 0 3 162 40 340 0 18 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling G 0 3 0 1 213 40 340 0 53 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling G 1 0 0 1 243 40 340 0 8 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA 1 Ceiling 0 2 0 0 0 211 40 340 0 0 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling G 3 12 0 3 239 40 350 0 53 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling H 0 21 0 4 186 40 340 0 0 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I -Ceiling H 1 21 0 1 3 262 40 350 0 3 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling 1-1 2 17 0 2 192 40 340 0 0 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling H 3 12 0 2 231 40 350 0 8 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA 1 Ceiling 1 0 26 0 4 231 40 320 0 33 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling 1 1 0 0 1 215 40 300 0 0 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling 1 2 12 0 2 211 40 300 4 0 Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling 1 3 17 0 3 192 40 300 0 0 I Ceiling tiles all accessible surfaces on ceiling 078 09/13/06 AA I Ceiling J 0 0 a 0 I 217 40 300 0 8 Ceiling tiles all accessible surfaces on ceilitig ENERCON Services, ine.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-4-1 (Crystal spectroscopy room ceiling, east, north, and west #2 walls)FSS # Date Class 1 Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Coord. Coord.1 Direct 1 Scan Min. IScan Max.1 Direct Min. Max.Comments Wipe DPM DPM (cpm)(cpm)DPM 078 09/13/06 AA 1 ~eiling J I 0 1 0 1 1 233 40 300 1 0 I 8 078 09/13/06 AA I e2 0 R0 1 58 40 300 1 0 143 AA 1 Ceilng AA I IN Wall 084 09/15/06 AA 1 j Wall 3 T 2-0 0 T T 2 1 1-4 4 084 09/15/06 AA A 0 AA I IN Wall 084 09/15/06 AA t__ N Wall 084 109/15/06 1AA I I IN Wall B-B B C 0 T 2 T 0 1 T-4 3 147 100 200 1 120 100 200 207 100 220 99 100 1 180 084 1 09/15/06 1 AA I I IN Wall 10 1 2 4 084 084 09/15/06 AA I N Wall 09/15/06 AA X N Wall 09/15/06 AA I N Wall 09/15/06 AA I N Wall C 1 16 3 4 084 084 09/15/06 084 09/15/06 084 09/15/06 084 09/15106 AA I I IN Wall AA I AA I AA I N Wall N Well N Wall C D D D E E-E F G H I-J A A A 2 T T 0 T T 2 2 2 T T 2~0 1 T T 4 2 4 23 3j 6 2 3 4 23 1 4 10 2 084 09/15/06 AA I N Wall 084 09/15/06 AA I N Wall 084 09/15/06 AA 1 N Wall 087 09/15/06 AA I I B Wall 2 087 09/15/06 AA I I Wall 2 4 0-0-4 10 4 2 2-2-2 2 3 5-3-3 5 6-5 4 3 3 3-3-3-4 3 4-3 3-5-5-4 3 133 148 126 165 124 150 158 too 100 100 100 200 200 100 200 4 0 100 200 0 200 o00 200 00 0 160 100 200 4 200 0 66 4 17 100 180 0 Penetration Surveyed Penetration Surveyed Penetration Surveyed Penetration Surveyed 2-m wide partition attached to north wall of crystal spec room 128 60 124 105 200 1 0 1 0 180 0 0 200 1 0 5 I -]f___ 2-m wide partition attachet 087 09/1.5/06 087 09/15/06 AA I AA 1~E Wall 2 F Wall 2 100 200 0 o 2-m wide partition attached Nr 101 100 180 01 10 to I 2-m wide partition attached 087 09/15/06 t AA 1 E Wal 1 4 2 105 100 1 200 1 0 0 087 09/15/06 088 09/15/06 088 09115/06 088 09/15/06 088 09/15/06 AA 1 2 0 AA AA AA AA I WWaII2 I W Wall 2 I W Wall 2 I W Wall 2 A 0 23 23 1-3-3 A I .2-m wide partition attached to north wall of crystal spec room 2-m wide partition attached to north wall of crystal spec room 2-m wide partition attached to north wall of crystal spec room 2-m wide partition attaclhed to north wall of crystal spec room 2-m wide partition attached to north wall of crystal spec room 2-m wide partition attached to north wall of crystal spec room 2-m wide partition attached to north wall of cystal spec toom A 2, 10 2 AA 1 W YWall 2 AA Il W Wall 2 B 0 B 1 B 7 23 0 23'4 1 113 100 200 0 122 100 200 0 105 1 100 200 4-5 2 ide atiti tthd t th llf tl ENERCON Service-, ine.

0 NORTH WALL E2 I E=Z G2 1 H21-~ J A2 Al AO LCO DO WEST WALL 1 EQ DO0 FLOOR EAST WALL 1 iF A4_J__ __LiI ~~ Q__A3 1 DO CO A2 CO BO Al BO A2 Al AO AO BO CO DO EQ FO GO HO 10 JO( AO Al WEST WALL 2 SOUTH WALL EAST WALL 2 BO AO BO CO DO EQ F GO HO 10 JO BO AO1A NlAO : Al AOtAl CEILING NCER_-__K]

REACO BO CO DO EQO E GO HO 10 JO Al A2 A3 NOTE: A3 through J3 oorrtin the s'lt areas that were surveyed separately as A4 through J4 for the floor of the Crystal Spectroscopy Room.UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS PROJECT REACTOR DECOMMISSIONING LDrawn by: DM CRYSTAL SPECTROSCOPY ROOM D7 DRAWING DRAWNG 19 SURVEY UNIT 1-4 Enercon Services University of Washington More Hall Annex D&D, Project 10492 Attachment 24 -Sub-Unit 1-4-2 Crystal Spectroscopy Room Floor, West and South Walls FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-4-2 (Crystal spectroscopy room floor, west and south walls)I Location

Description:

ICrystal spectroscopy room floor, west and south walls I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/IOOcm

2) (dpm/100cm

2) (i+/-R/hr)Number of measurements:

96 96 96 96 51 Number of measurements needed (1): 9 9 9 9 N/A Maximum value of results: 68 9 279 94 0 Mean value of results: 11 1 145 15 0 Standard Deviation of results: 12 2 41 21 0 Degree of Freedom (2): 1.663 1.663 1.663 1.663 1.677 gc value: 13 1 152 18 0 Guideline level: 100 20 5000 1000 5 Are there sufficient measurements?

Yes Yes Yes Yes Yes Is the max value < guideline level? Yes Yes Yes Yes Yes Is [t, < guideline?

Yes Yes Yes Yes Yes Does survey unit pass? Yes Yes Yes Yes Yes m (1) as interpolated from NUTREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-I for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-4-2 (Crystal spectroscopy room floor, west and south walls)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (rpm) (cpm) DPM (cpm) (cpm) DPM DPM 073 09/12/06 AA I W Wall A 0 0 ND ND 101 100 200 0 0 073 09/12/06 AA I W Wall A 1 8 0 2 148 100 200 0 0 073 09/12/06 AA I W Wall A 2 22 2 4 143 100 200 4 39 073 09/12/06 AA I W Wall B 0 0 ND ND 132 100 200 0 12 073 09/12/06 AA I W Walit B 1 0 ND I ND 139 100 200 0 35 073 09/12/06 AA I W Wall B 2 8 0 2 143 100 200 0 53 073 09/12/06 AA t W Wall C 0 0 ND ND 110 100 200 0 44 073 09/12/06 AA I W Wall C 1 0 ND ND 112 100 200 0 67 073 09/12/06 AA I W Wall C 2 3 0 1 135 100 200 0 0 073 09/12/06 AA I W Wall D 0 27 3 5 205 100 220 0 30 073 09/12/06 AA I W Wall D 1 8 0 2 88 100 180 0 0 073 09/12/06 AA I W Wall E 0 13 1 3 119 100 200 4 0 073 09/12/06 AA I W Wall E 1 3 0 I 128 100 200 0 0 073 09/12/06 AA I W Wall E 2 3 0 I 159 100 200 0 90 073 09/12/06 AA I 076 09/13/06 AA 1 076 09/13/06 AA I W Wall S Wall S Wall S Wall D 2 13 3 166 1 100 200 4 1 7 0 10 0 131 123 167-14-2 too 200 0 0 100 076 109/13/061 AA I A 2 10 100 076 1 09/13/06 1 AA I I IS Wall B 0 5 2 100 0 1 94 L B 1 34 1___ ___ B 2L 4 2 1 T 6-3 2-2 155 138 156 116 100 200 0 1 0 1 100 200 0 is -______________________

1 100 200 T-___________________

076 1 09/13/061 AA I I IS Wall C 0 076 1 09/13/061 AA I I IS Wall C 1 5 100 1 200 0 0 C C D D D 2 T T T 0 5--5 ND ND-2 ND-2 145 1 100 1 200 0 0 131 100 1 200 0 1 0 076 1 09/13/061 AA I I IS Wall N 129 0 076 109/13/061 AA I S Wall 1 129 1 076 09/13/06 AA 076 09/13/06 AA 076 09/13/06 AA 076 09/13/06 AA I I I S Wall S Wall S Wall S Wall S Wall S Wall S Wall E 0 T 2 5 10i 0 NID 076 I 09/13/06 AA I 1 T 076 1 09/13/06 1 AA I I IS Wall 076 09/13/06 AA I 076 09/13/06 AA _S Wall S Wall F F F G G G-7 H H H if 1 I 1 2-6-I T 1 2 T 2 0 5 15 5 0 15 15 5 5 5 10 5 0 10 1 2 1 2 2 1 1 1 1-1 0 1 2-3 ND-2 3-2-iD 3 3-2 2 2 167 T4-4 199 1 100 127 1 100 1 200 1 0 1 25 100 1 180 140 125 109 10-7 100 200 0 0 100 180 0 38 100 200 0 11 100 200 0 11 0 10 100 1 200 1 0 1 20?1200 L 20 L 138I _ __________

200 1 0 1~ 6 '1 1 076 1 09/13/06 AA 298 100 200 19 100 1200 0 100 220 0 1 43 076 09/13/06 1 Wall 076 09/13/06 [ 1 S Wall 076 109/13/061 AA I I S Wall 10[ 1 0 II 0 [ ___- 1 __ _ _ _ __ _ _ _1 3 127 156 100 200 4 1 0 076 091/13106[

AA I 1 076 09/13/06 1 AA I I S Wal 1 0 ND 2 1 0 1 0 1 0 93 079 09/14/06 079 09/14/06 079 09/14/06 079 09/14/06 079 09/14/06 079 09/14/06 079 09/14/06 AA I Floor AA 1 Floor AA I Floor AA 1 Floor AA I Floor AA 1 Floor AA I Floor A 0 A I 1 15 1F 0 1 U A 1 3 1 131 231 T7-1-183 100 200 0 220 0 11 0 29 0 A 14 20 2 4 DET0o_ 01 100 1 220 0 20 0 RB I 25 3 25..... 3 1 _ _ _ __ _ENERCON Serie, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-4-2 (Crystal spectroscopy room floor, west and south walls)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net hR Comments Coord. Cuord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpmn) DPM (epm) (cpm) DPM DPi 079 09/14/06 AA I Floor B .2 6 0 2 " 148 100 200 4 20 0 079 09/14106 AA 1 Floor B 3 6 0 2 171 100 200 0 0 0 079 09/14/06 AA I Floor B 4 15 2 4 102 100 200 9 0 0 079 09/14/06 AA I Floor- C 0 10 1 3 160 too 200 0 0 0 079 09/14/06 AA IIl Floor C 1 39 4 6 206 100 200 0 0 10 I7 9 1 /0 A l F lo o r C , 2 2 5 2 4 13 1 to o 18 0 0 00 079 09/14/06 A l Foor C 3 6 0 2:: 223 100 220 0 15 079 09/14/06 AA 1 Floor 1C 4 15 1 3 171 100 200 0 6 0 079 09/14/06 AA 1 Floor D 1 0 39 4 6 142 100 200 0 29 0 079 109/14/061 AA 1 Floor D 4 10 1 3 194 1 100 1 200 0 1 11 0 lFtoor J 0 0 0 ND 47 1 140 1 180 0 1 0 3 113 1 140 1 180 0 1 38 080 109/13/061 AA I 080 109/13/061 AA I Floor J 3 16.0 Trench tltu it 12" wide 080 010 09/13/06 AA I Floor 09/13/06 AA I Floor 09/13/06 AA 1 Floor 09/13/06 AA 1 Floor J 4 0 0 ND 1 77 1 140 1 160 1 0 1 0 080 1 4 1 1 2 0 0 N 139 120 180 4 1 0 1 0 ND 157 120 180 0 1 15 FTrench thru it 12" wide 0 ND 1 223 140 220 0 0 080 080 109/13/061 AA I Floor I 1 1 21 0 ND 1 191 1 160 17200 1 0 1 0 Floor 1 0 1 0 0 ND 1 236 1 140 1 180 1 0 1 0 080 1 09/13/06 1AA 11 20 8 0 Hj l 38 o ND 1 90 1 140 1 180 1 0 1 25 0 A 080 1 09/13/06 1 AA 1 Floor I H 2 1 29 0 0 1 080 09/13/06 1 AA 1 I Floor HI 3 0 0 ND 1 119 1 180 1 220 1 0 1 66 Trench thru it 12" wide 00 HI 4 8 0 ND 1 173 140 1 180 1 0 1 15 080--4 1 0 1 0 I G 1 3 1 3 1 0 187 160 200 0 1 52 L1 080 09/13/06 1 AA I t Floor 1 200 0 Trench thru i 080 09/13/06 AA 080 09/13/06 AA 080 09/13/06 AA 080 09/13/06 AA l Floor I Floor G 121 3 G 1 0 0 0 0 ND 0 180 0 11 0 0 ND 1 204 1 160 I Flo.FIH.j 8[ 010 ND I 139 10 200 0 _ 0 1__ 1___________________________

ND 1 158 1 180 1 200 1 0 1 0 1 1 080 09/13/06 080 09/13/06 AA 11 AA 11 Floor F I 16 0 Floor F 2 16 Floor Floor Floor Floor F '3 8 0 0 01 ND 1 171 1 100 1 160 1 4 1 52 rrench thru it 12" wide rrench tluu it 12" wide 080 09/13/06 1 AA 1 1 ND 178 ND 121 120 180 0 0 160 20 4 0 E 4 38 E 3 38 080 09/13/06 AA I 080 09/13/06 AA I 080 09/13/06 AA 1 080 09/13/06 AA I 080 09/13/06 1AA I 1 115L 1- 00 0 11 1 -B7 1t Floor E 1 2 12 ND 185 160 1 200 1 0 0 Floor Floor Floor ED I 21 8 0 ND 1 184 1 120 1 240 1 4 1 0 0 1 ND 279 1 120 1 240 1 0 68 Z 25 29 080 1 09/13/06 1 AA 1 Floor_______ D 1 ~0 0 122 84 167 120 240 0 120 200 0 140 200 0 Remediated See FSS-079 080 1 09/13/06 AA I I Floor 0 0 080 09/13/06 AA ND ND 149 10/03/06 149 10/03/L06 AA 1 Floor AA 1 Floor D2 3 12 1 0 S 0 J I l 191 120 200 0 0 0 I I I 1 0 149 10/03/06 AA I 149 10/03/06 AA I 149 10/03/06 AA 1 149 10/03/06 AA 1 149 10/03/06 AA I Flonr I 1 2 Fl~oor 1 Floor 1 3 1 4 0 0 0 0 0 IFloor 1 3 1 2 149 10/03/061 AA I 1 Floor ENERCON Serices, ine.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-4-2 (Crystal spectroscopy room floor, west and south walls)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net PR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 149 I0WQ3106 &A I Fklao 1 t 0 149 10/03/06 AA I Floor 1 0 0 149 10/03/06 AA 1 Floor H 0 0 149 10/03/06 AA I Floor H I 0 149 10/03/06 AA 1 Floor H 2 0 149 10/03/06 AA I Floor H 3 0 149 10/03/06 AA 1 Floor 11 4 0 149 10/03/06 AA 1 Floor G 4 0 149 10/03/06 AA I Floor G 3 0 149 10/03/06 AA I Floor G 2 0 149 10/03/06 AA 1 Floor G I 0 149 10/03/06 AA I Floor 3 0 0 149 10/03/06 AA 1 Floor F 0 0 149 10/03/06 AA 1 Floor F I 0 149 10/03/06 AA 1 Floor F 2 0 149 10/03/06 AA 1 Floor F 3 0 149 10/03/06 AA I Floor F 4 1 0 149 10/03/06 AA I Floor E 4 0 149 10/03/06 AA I Floor E 3 0 149 10/03/06 AA I Floor E 2 0 149 10/03/06 AA I Floor E I 0 149 10/03/06 AA 9 Floor E 0 0 149 10/03/06 AA 1 Floor D 0 0 149 10/03/06 AA I Floor D I 0 149 10/03/06 AA I Floor D 3 0 14 9 10/03/06 1AA I I Floor D 3 10 ENERCON Servicn, inc.

NORTH WALL A2 ~E2 G2 H2Jj Al~AO CO DO 1 WEST WALL 1 FLOOR EAST WALL 1 EQ A4 EO DO A3 DO CO A2 CO BO Al BO A2 Al AO AO BO CO DO EO FO GO HO 10 JO EAO Al A2.. ..... .....I B .........WEST WALL 2 SOUTH WALL EAST WALL 2 KO Al BO CO DO EO FO GO HO 10 AO ABJO=A2 CEILING AO BO CO DO EO FO GO HO 10 JO Al A2 A3 NOTE: A3 through .13 contain the smarn areas that were suveyed separately as A4 through .14 for the floor of the Crystal Spectroscopy Room.UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS PROJECT REACTOR DECOMMISSIONING Drawn by: DM DRAWING CRYSTAL SPECTROSCOPY ROOM DRAWING 19 SURVEY UNIT 1-4 Enercon Services University of Washington More Hall Annex D&D, Project 10492 Attachment 25 -Sub-Unit 1-4-3 Crystal Spectroscopy Overhead Piping FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-4-3 (Crystal spectroscopy overhead piping)I Location

Description:

ICrystal spectroscopy overhead piping I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (pR/hr)Number of measurements:

32 32 32 32 N/A Number of measurements needed (1): 9 9 9 9 N/A Maximum value of results: 74 8 253 61 N/A Mean value of results: 23 0 113 12 N/A Standard Deviation of results: 21 2 74 17 N/A Degree of Freedom (2): 1.696 1.696 1.696 1.696 N/A 4 value: 29 1 135 17 N/A Guideline level: 100 20 5000 1000 N/A Are there sufficient measurements?

Yes Yes Yes Yes N/A Is the max value < guideline level? Yes Yes Yes Yes N/A Is gu < guideline?

Yes Yes Yes Yes N/A Does survey unit pass? Yes Yes Yes Yes N/A as interpolated from NUREG/CR-5 849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

0 University of Washington More Hall Annex Final Status Survey Results -Unit 1-4-3 (Crystal spectroscopy overhead piping)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct ScanMIn. ScanMax. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 092 09/19/06 AA I lpe A 3 59 0 3 24 40 180 0 15 11es and insolation exteriors, scanned all accessible areas.092 09/19/06 AA 1 [e B 0 6 0 1 11 40 180 0 45 1pes and insulation exteriors, scanned all accessible areas.092 09/19/06 AA 1 e B 1 0 0 0 79 40 200 0 0 lpes and insulation exteriors, scanned all accessible areas.092 09/19/06 AA I lpe B 2 6 0 1 173 40 220 0 0 [Des and insulation exteriors, scanned all accessible areas.092 09/19/06 AA* I [e B 3 1 14 0 2 249 40 300 0 61 lpes and insulation exteriors, scanned all accessible areas.092 09/19/06 AA 1 ie C 0 6 0 1 253 40 300 0 0 lpes and insulation exteriors, scanned all accessible areas.092 09/19/06 AA I e C -e1 14 0 2 37 40 200 0 0 lpes and insulation exteriors, scanned all accessible areas.092 09/19/06 AA I e C 2 0 0 -1 188 40 280 0 0 lIPes and insulation exteriors, scalned all accessible areas.092 09/19/06 AA I pe C 3 1 21 0 3 "75 40 1 200 0 0 40 1 loes and insulation exteriors, scanned all accessible areas.092 1 09/19/06 AA 1 Ipe 092 1 09/19/061 AsA 1 je__ _092 1 09/19/06 1 AsA I I' _____D 0 D .1 D 2 D 3 29 0 51 0 21 0 29 0 173 1 40 1 260 0 1 15 lbes and insulation exteriors, scanned all accessible areas.4 49 1 40 1 200 0 1 25 3 t lpes and insulation exteriors, scanned all accessible areas.Iles and insulation exteriors, scanned all accessible areas.lbes and insulation exteriors, scanned alt accessible areas.092 1 09/19/06 1 AA 1 1l[be 4 092 1 09/19/06 1 AA I I I roe E 10 0 0 1 132 1 40 210 0 1 0 ltes and insulation exteriors.

scanned all accessible areas.E 11 0 0 E 12 44 1-4 2 1 45 1 40 1 200 1 0 1 0 lbes and insulation exteriors, scanned all accessible areas.20 40 200 1 0 1 25 1 j.!es and insulation exteriors, scassed all accessible areas.200 40 280 1 0 1 0 1 les and insulation exteriors, scanned all accessible areas.092 1 09/19/06 1 AA 1 1 The E 3 14 092 109/19/06 1 AA I I tle 092~i 1 09/19/06 1 AsA 1- I~e___092 1 09/19/06 1AAt -I j.pe____F 0 F I1 F 2 G 1 0 29 0 215 40 300 0 0 Ihes and insulation exteriors.

scanned all accessible areas.44 0 3 83 40 260 0 10 Ibes and insulation exteriors, scanned all accessible areas.21 0 2 092 09/19/06 1 AA I I I[e 66 1 0 4 092 1 09/19/06 1 AA I I I [e G I 1 1 44 1 0 3 124 40 280 0 0 I bes and insulation exteriors, scanned all accessible areas.G 1 2 1 29 1 0 I 3 1 51 40 240 0 5 [Pes and insulation exteriors, scanned all accessible areas.188 40 280 1 0 1 30 1 lIles and insulation exteriors, scanned all accessible areas.092 1 09/19/06 1 AA I I I[e_205 1 40 092 1 09/19/06 1 AA I I Th~e H 2 I 0 0 1 0 40 tel 092 109/19/061 AA I[ibe.1 10 1 0 0 132 40 1 260 0 115 1 1 lbes and insulation exteriors,.

scanned all accessible areas.ilpe I I 1 1 21 0 1 2 1 100 1 40 1 220 1 0 1 40 1lbes and insulation exteriors, scanned all accessible areas.2 21 1 0 092 1 09/19/06 FAA 1 110 14 2 1-3 2 28 J 40 200 4 1 0 lges and insulation exteriors, scanned all accessible areas.139 40 I 260 81 0 les and insulation exteriors, scanned all accessible areas.092 109/19/061 AA I ibe J 36 092 09/19/061 AA I I I be I J 12 1 14 0 ENFRCON Services, is.

PIPE LAYOUT ON CEILING AO BO CO DO EO FO GO HO 10 JO M Irr A2 --"-- --~-b--m-A2 ~ ~- j..........____

_____Figure 4 PROJECT UNIVERSITY OF WASHINGTON NUCLEAR REACTOR DECOMMISSIONING DRAWING CRYSTAL SPECTROSCOPY ROOM PIPES SURVEY UNIT 1-4 University of Washington More Hall Annex D&D, Project 10492 Attachment 26 -Unit 1-5 Radiochemistry Lab FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-5 (Radiochemistry lab)I Location

Description:

IRadiochemistry lab I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm.) (pRhr)Number of measurements:

87 87 87 87 18 Number of measurements needed (1): 9 9 9 9 N/A Maximum value of results: 45 4 285 54 0 Mean value of results: 9 0 149 7 0 Standard Deviation of results: 11 1 52 14 0 Degree of Freedom (2) : 1.665 1.665 1.665 1.665 1.740 gc. value: 11 1 158 9 0 Guideline level: 1 00 20 5000 1 000 5 Are there sufficient measurements?

Yes Yes Yes Yes Yes Is the max value < guideline level? Yes Yes Yes Yes Yes Is g < guideline?

Yes Yes Yes Yes Yes Does survey unit pass? Yes Yes Yes Yes Yes (1 as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-5 (Radioc.i.nistry lab)FSS# Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Ird Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cps) DPM (cpm) (cpm) DPM DPM 053 09/070 ' A 1 ceiting 053 09107/06 AA 1Celn 053 09/07/061 AA 1 1 eln 053 09/07/06 1AA Celn A I fl I A.7I loft n 0 A 1) 45 4 7 272 100 1 200 0 0 ...... ._A 1 0 0 1 49 100 200 0 0 hktially inaccessible (pipes)A 2 3 103 100 200 0 54 A 3 ND 103 100 200 0[-E 053 09/07/06 AA I 053 09/07106 AA 1 053 09/07/06 AA I 033 09/07/06 AA 1 Ceiling A 4 0 ND ND 164 100 220 0 1 Ceiling B 0 0 0 0 1 64 100 200 0 0 Ceiling Ceilina 7 T 1 59 100 200 0 0 Static on insulation partially inaccessible (pipes)1 0 053 09/07/06 AA I I Ceilint 0 053 1 09/07/06 1 AA I I Ceiling I B 1 4 157 1 100 1180 1 0 0 053 09/07/06 1 AA I I...... a C 0 31 4 5 59 1 100 t 200 1 0 1 7 Ceiling Ceiling C 1 16 3 4 2 7 1 2 4 053 09/07/06 AA 053 1 09/07/06 AA 1 ICeiling D 1 0 W3 09/07/06 AA [Ceiling 053 09/07/06 AA 1 Ceilin 057 09/07/06 AA 1 N Wall 0 Ts 7 A1 3 I_ A 1 01_21 A 11 A 1 2 057 057 057 09/07/06 1 AA I I IN Wall B 0 Bi~ -0 0 0 16 0 0 0 0 0-4 1 1 1 0 0-F ND 0 0 0 3 T 1 7 T-3 2 1-2 IN 12,02 :ý:2ý0O ý O 4'0 Removed door most ofrid 112 100 200 0 0 144 100 180 0 0 153 100 200 0 3 176 too 200 0 0 90 100 200 0 0 129 100 200 0 12 146 100 200 4 49 185 100 200 0 0 77d t on f dO Rpnvddl ,nlnr mn t n oi 057 1 09/07/06 1 AA I 1 N Wall N Wall N Wall C 1 2 057 109/07/06 1 AA o 0 1 0 057 060 060 09/07/06 AA I N Wall 09/08/06 AA I W Wall 09/08/06 AA I W Wall D 2 A 0 A I A 2 B 0 B 1 0 0 1 0 6 060 09/08/06 1 AA I W Wall 060 09/08/06 AA 1 W Wall 060 09/08/06 AA I W Wall 060 09/08/06 AA 1 W Wall 060 09/09/06 AA I W Wall 060 09/08/06 AA I W Wall 0 0-ND 0_0 1 2-2 1 2 0 2 1 0 0 0 5 ND 1 2 2 1 2-D-1 2 3 3 2 5 1 3 2 1 1 1 278 100 200 0 0 192 100 200 0 7 200 100 220 0 0 202 100 220 0 0 214 100 200 0 12 Removed door most of grid 7 0 20 0 21 48 1 220 0 9 om pp____urveed_

203 12020 2020 __ 9 __ IS.sme pipes (surveyed) 174 100 200 0 51 Some pipes (surveyed)

Includes penetration 285 111 100 180 0 0 C 2 1 D) 0 20 060 060 156 100 200 0 0 163 100 200 3 0 103 100 220 0 0 208 100 200 0 51 172 100 200 0 32 1 1 W Wall E I 064 09/08/06 1 AA 1 S Walil 064 09/08/06 AA I S Wall 064 09/08/06 AA I S Wall 064 09/08/06 AA I S Wall 064 09/08/06 AA & S Wall 064 09/08/06 AA I S Wall 064 09/08/06 AA I S Wall S 260 1 3 100 200 0 0 A 1 6 A 2 B 0 B I B 2 C 0 16 I-F1 1-1 1 0 T T 1 82891 10022 220 0 9 2018 100 220 0 0 3 3 3 0 1 0 0 i EN ERCON Seri-ej..

University of Washington More Hall Annex Final Status Survey Results -Unit 1-5 (Radiochemistry lab)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net hR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (epm) (cpm) DPM (cpm) (cpm) DPM DPM 064 09/08/06 AA 1 S Wall C 1 1 0 1 172 100 200 0 23 064 09/08/06 AA I S Wall C 2 20 2 3 206 100 220 3 0 064 09/08/06 AA I S Wall D 0 1 0 L 204 100 200 3 9 064 09/08/06 AA I S Wall D I 1 0 1 118 100 180 0 14 064 09/08/06 AA I SWaII D 2 6 1 2 154 100 200 0 23 065 09/08/06 AA l E Wall A 0 4 1 2 132 40 300 0 0 Concrete Wall, lpes 065 09/08/06 AA 1 JE Wall 065 09/08/06 AA I E Wall 065 09/08/06 1 AA 1 1 JE Wall A 1 0 1 2 111 40 290 1 3 1 0 Concrete Wall. Ibes 1 4 159 40 360 0 0 1 3 132 [Concrete Wall, lpea Concrete Wall, Thes Concrete Wall, lpes Concrete Wall. lbes 065 109/08/061 AA I I IE Wall B l 4 1 2 165 I 065 09/08/06 AA I 1 EWall B 2 14 065 109/08/06 AA I E Wall C 0 39 06 109/08/06 AA 1 E Wall C I 9 4 196 40 390 0 1 0 115 1 Is 1 5 59 40 310 0 1 0 Concrete Wall roes, Concrete Concrete Wood. Concrete 065 1 09108/061 AA I I lBWall C 1 2 29 065 109/08/06 1 AA I I E Wall D 0 9 1 4 201 40 380 0 1 0 H Wall 1 EWalr 1 Floor DI I 9 0 TO T9 1 1 3 190 40 300 3 0 Wood. Concrete 1 148 40 280 0 0 Concrete 066 109/09/061 AA I 3 066 09(09/06 066 09/09/06 AA I Floor A I 4 AA I I Floor A 1. 2 0 0 1 166 100 I 220 I 4 I 0 I 0 I A 3 A 29 10 5 0 3 i 3 ~ ~ ~ 4 5~ 122 10 20..1..10

......trnc 17 I 10 on 00OI i f t fl a IOcrtial t reh l 3 066 1 09/09/06 1 AA I I Floor B 0 2 115 113 128 10-9 100 200 4 1 0 1 0 066 09/09/06 066 09/09/06 066 09/09/06 066 09/09/06 AA I I IFloor B 1 2 ND I ND AA I Floor B 1 3 5 0 2 100 1 200 1 0 1 0 1 0 1rtial trench AA B 1 4 C 066 1 09/09/06 AA I Floor 066 09/09/06 AA I 066 09/09/06 AA I 066 09/09/06 AA I 066 09/09/06 AA 1 066 09/09/06 AA 1 066 09/09/06 AA 1 066 09/09/06 AA I Floor Floor Floor Floor Floor C 2 C 3 B 0 C 0 I 5 14 2f9 24 10 14 1 3 4 5 3 1 5 101 164 96 0 7 0 4-I; Ion I an n O i n Io~nh 100 200 0 1 0 J 0 1_________________________

100- 200 0 12 J 0 ________________________

100 200 0 1 25 0 ________________________

100 200 __0 0 I 0 ________________________

1 D 0 10 [3 4 3 4 21 7 __ 100 220, 4- 0l0-I-

-.........

7 100 200 0 0 1 0 I6'rtial trench D 11 0 0 2 8[ 100 18 I 0 Ii 1 0 1 -0_I_ _ _ _ _ _ _D 2I 19 TT 103 100 200 0 1 0 1 0.... ..... ... ... i I it I____5___ 152 10 200__ 0 1__0_1 0 ENERCON Seric-es, oi.

University of Washington More Hall Annex D&D, Project 10492 Attachment 27 -Sub-Unit 1-6-1 Robotics Lab Floor FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-6-1 (Robotics lab floor)~ I -~->7. -__ ~I Location

Description:

Robotics lab floor.-'Thj~.~4'.

~~ ~. ~ ~ ~ _ U Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (hR/br)Number of measurements:

N/A 20 20 20 20 Number of measurements needed (1): N/A 9 9 9 N/A Maximum value of results: N/A 4 251 38 0 Mean value of results: N/A 1 171 14 0 Standard Deviation of results: N/A 1 44 14 0 Degree of Freedom (2): N/A 1.729 1.729 1.729 1.729 pvalue: N/A 1 188 20 0 Guideline level: N/A 20 5000 1000 5 Are there sufficient measurements?

N/A Yes Yes Yes Yes Is the max value < guideline level? N/A Yes Yes Yes Yes Is ýit < guideline?

N/A Yes Yes Yes Yes Does survey unit pass? N/A Yes Yes Yes Yes (1) as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services.

inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-6-1 (Robotics lab floor)-r r-~rT ,~, C -r C --r -C -rr r C FSS # I Date I Class I Floor Surface X Y Cor.Coord.

Alpha Direct DPM Alpha Alpha Beta Scan Mn. Scan Max. Direct (cpm) (cpm) DPM Beta Scan Min.(cpm)Max.(cpm)Alpha Wipe DPM Beta Wipe DPM Net pR Comments 134 1 1001/06061 GA I Floor 134 10/01/06 GA I IFloor 1 198 t00 134 10/01/06 GA I Floor E 0 220 220 T8-0 0 0 Transformer I 134 10/01/06 GA I Floor G 0 182 80 0 0 134 134 134 134 10/01/06 10/01/06 10/01/06 10/01/06 10/01/06 GA GA GA GA GA I~1 I Floor Floor Floor Floor 1 0 142 o00 23 0 A C-E G 1 7 82 100 I 1lo 13 0 Rnom 2 82 100 1 180 13 0 Transformer Room 2 142-180 251 152 100 220 100 200 120 J 240 13 38-23 0 0 0 0 0 134 I Floor 134 134 134 134 10/01/06 10101/06 10/01/06 10/01/06 10/01/06 GA I Floor 2 100 200o-GA GA GA GA I Floor Floor Floor Floor A 4 148 1 100 220 8 0 134 I 134 134 134 134 134 T3 4 10/01/06 10/01/06 10/01/06 10/01/06 10/01/06 GA GA I I Floor Floor GA I1I Floor GA GA I I 160 11/08/06 160 11/08/06 160 11108/06 GA I I GA GA GA GA GA 160 160 I I T T T T T T T T 1 T T 1 1 I Floor Floor Floor Floor Floor Floor Floor Floor Floor Floor Floor Floor Floor Floor Floor Floor Floor Floor Floor Floor Floor Floor Floor C E A C E G-1 A C-E G-1 4 4 T 4 6 6 1(M 202 92 208 60 80 100 220 100 200 120 180 200 2600 170 1 100 1' 2R15 150 80 1 200 160 160 33 is-3 18 0_0 0 1F3 0 0 0 11/08/06 GA 11/08/06 GA 11/08/06 GA 11/08/06 GA 11/08/06 GA 11/08/06 GA E 6 T 1 G IK A B E 0 0 0 0 0 0 0 0 2 2 2 2-2 4 4 4 4 4 6 6 6 6-i 0 0 4 0 0 0 0 0 4 4 0 0 0 0 0 0 160 160 1 1/08/06 1 GA 160 1108/06 GA n_____ --~___ __1 ____ .____.1 __ __1 __ __ L .I I.........6 ENERCON Senioes, TRANSFORMER ROOM -SEE DRAWING 23 SOUTH WALL A2 Ao BO CO DO EO FO GO HO NORTH WALL AO Al A2 BO CO DO EO FO GO HO WALL- SEE FIGURE 22 FOR SURVEY MAP)6ý-UNIVERSITY OF WASHINGTON NUCLEAR REACTOR DECOMMISSIONING ROBOTICS LABORATORY SURVEY UNIT 1-6 University of Washington More Hall Annex D&D, Project 10492 Attachment 28 -Sub-Unit 1-6-2 Robotics Lab West and South Walls Including Transformer Room South Wall FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-6-2 (Robotics lab west and south walls)Unit Designator:

1-6-2 Class: GA I9Certainty

%: 5I Location

Description:

Robotics lab west and south walls Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpmnl00cm

2) (pR/hr)Number of measurements:

N/A 25 21 21 18 Number of measurements needed M: N/A 9 9 9 N/A Maximum value of results: N/A 4 419 59 0 Mean value of results: N/A 0 121 8 0 Standard Deviation of results: N/A 1 122 15 0 Degree of Freedom (2): N/A 1.711 1.725 1.725 1.740 g value: N/A 1 167 14 0 Guideline level: N/A 20 5000 1000 5 Are there sufficient measurements?

N/A Yes Yes Yes Yes Is the max value < guideline level? N/A Yes Yes Yes Yes Is [t, < guideline?

N/A Yes Yes Yes Yes Does survey unit pass? N/A Yes Yes Yes Yes () as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-6-2 (Robotics lab west and south walls)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 129 09/29/06 GA I S Wall A 0 119 60 160 0 0 0 129 09/29/06 GA I S Wall C 0 42 80 200 0 0 0 129 09/29/06_

GA I S Wall E 0 0 o80 180 0 8 0 129 129 09/29/06 GA 09/29/06 GA 09/29/06 GA 09/29/06 GA 1 S Wait I S Wall I SWall 1 S Wall G H A C 0 T 2 55 60 160 0 33 0 129 223 0 80 60 60&o 200 T8-0 160o T8-0 0 0-0 23 59-0 0_0--0 129 129 129 129 131 09/29/06 09/29/06 09/29/06 09/30/06 GA I IS Wall E 2 GA GA GA 1IS j W ell S Wall G H A C 2 0 0 0 60 180 0 0 0 272 WWall 80 100 too 100 220 280 260 200 0 0-0_0_0 0_0 0_0 131 09/30/06 GA I W Wall 131 131 131 131 09/30/06 1 GA I W Wall W Wall W Wall W Wall E 0 158 I G A C E 0 2 2V 43 60 180 3 0 296 09/30/06 1 GA I1 346 80 100 80 80 220 220 200 21600 8 23-0 0 0 0 131 09/30/06 1 GA I W Wall 123 0 131 09/30/06 1 GA 135 10/01/1 I T 1 T W Wall SWe S Wall s wait G 2 110 0 37 80 180 0 18 pipe in trans room west wall 136 10/01/1 30 136 10/01/06 1 GA 100 180 100 200 0 Transformer room -South wall, wire mesh Transformer room -Southl wall wire mesh 156 156 156 156 156 156 156 156 162 162 162 162 162 162 11/08/06 1 GA I 1 W Wall W Wall W Wall W Wall W Wall 11/08/06 1GA II 11/08/061 GA I 11/08/06 GA 1 W Wall 11/08/06 GA W W Wall 11/08/06 GA I W Wall 11/08/06 GA 1 S Wall A-C E G A C E A-C C 0 0 0 0 T T T T 0 T 4 0iI 0_0 11/08/06 11/08/06 11/08/06 11108/06 11/08/06 GA GA GA GA GA I 1 1 T 1 S Wall W Wall W Wall W Wall W Wall S Wall S Wall W Wall W Wall 4 Wl 4-!!Wal_____~~~~~

1 __)y_ fv~ I_______I~

I___{~ : ENERCON Services, ina.

TRANSFORMER ROOM -SEE DRAWING 23 SOUTH WALL A2 Al A0 BO Co DO EQ FO GO HO NORTH WALL AO Al A2 BO CO DO EO FO GO HO WALL -SEE FIGURE 22 FOR SURVEY MAP EAST WALL AO BO CO DO E0 FO Al Ho A2 UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS PROJECT REACTOR DECOMMISSIONING Drawn by-. DM DRAWING ROBOTICS LABORATORY DRAWING 22 SURVEY UNIT 1-6 Enercon Services SOUTH WALL 2 CEILING A2 B2 C2 D2 E2 NORTH WALL 2 F2 G2 HO Hi H2 HO GO FO EO DO CO BO B1 B2 B3 B4 B5 B6 B7)6-A4 A5 A6 A7 A4 A6 A7 A5 UNIVERSITY OF WASHINGTON NUCLEAR scale: NTS REACTOR DECOMMISSIONING Drawn by: DM ROBOTICS LABORATORY DRAWING 23 SURVEY UNIT 1-6 Enercon Services SOUTH WALL A li AO WEST WALL A2 Al~A0 BO Co DO: FLOOR SECTiON EXTENDS INTO W ALL AO Al A2 A3 BO EAST WALL AO BO Go DO Al A2 CEILING Al B0 ..... .C0 _DO I___ BO 1 CO DO_AO DO....NORTH WALL A AlH UNIVERSITY OF WASHINGTON NUCLEAR scale: WTS PROJECT REACTOR DECOMMISSIONING Drawn by: DM TRANSFORMER ROOM DRAWING 24 SURVEY UNIT 1-6 Enercon Services University of Washington More Hall Annex D&D, Project 10492 Attachment 29 -Sub-Unit 1-6-3 Robotics Lab East and North Walls Including Transformer Room East, West, and North Walls FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-6-3 (Robotics lab east and north walls)Unit Designator.

1-6-3 Class:] GA Certainty

%: I Location

Description:

jRobotics lab east and north walls Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/O00cm

2) (dpm/100cm

2) (gR/hr)Number of measurements:

N/A 22 26 26 16 Number of measurements needed (1): N/A 9 9 9 N/A Maximum value of results: N/A 4 354 59 0 Mean value of results: N/A 0 145 13 0 Standard Deviation of results: N/A 1 115 16 0 Degree of Freedom (2): N/A 1.721 1.708 1.708 1.753 g,, value: N/A 1 183 19 0 Guideline level: N/A 20 5000 1000 5 Are there sufficient measurements?

N/A Yes Yes Yes Yes Is the max value < guideline level? N/A Yes Yes Yes Yes Is gIt < guideline?

N/A Yes Yes Yes Yes Does survey unit pass? N/A Yes Yes Yes Yes () as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-6-3 (Robotics lab east and north walls)FSS N Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coard. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cp m) (cpm) DPM DPM 132 09/30/06 GA I E Wall A 0 120 80 200 0 0 132 09/30/06 GA 1 E Wall C 0 160 100 240 0 0 132 09/30/06 GA I E Wall E 0 100 80 220 0 0 132 09/30/06 GA I E Wall G 0 0 80 200 3 0 132 09/30/06 GA I E Wall A 2 1 0 80 180 0 0 132 09/30/06 GA I E Wall C 2 87 80 200 3 0 132 09/30/06 GA I E Wall E 2 35 80 180 28 0 132 09/30/06 GA 1 E Wall G 2 1 60 180 13 0 133 09/30/06 GA 1 N Wall A 0 24. 100 220 33 0 133 09/30/06 GA I N Wall C 0 275 120 260 8 0 133 09/30/06 GA I N Wall E 0 308 120 240 38 0 133 09/30/06 GA I N Wall G 0 286 100 240 0 0 133 09/30/06 GA I N Wall A 2 309 120 260 0 0 133 09/30/06 GA I N Wall C 2 242 100 220 13 0 1 133 09/30/06 GA I N Wall E 2 338 80 240 0 0 133 09/30/06 GA 1 N Wall G 2 354 120 260 0 0 136 10/01/06 GA 1 W Wall A 0 195 120 200 0 Transformer room -West wall 136 10/01/06 GA I W Wall C 0 165 100 200 3 Transformer room -West wall 136 10/01/06 GA I W Wall A 2 112 120 220 0 Transformer room -West wall 136 10/01/06 GA I W wait C 2 75 too 180 13 Transformer room -West wall 136 10/01/06 GA I N Wall A 0 0 100 100 23 Transformer room -North wall0 door 136 10/01/06 GA I N Wall A 2 60 80 180 33 Transformer room -North wall 136 10/01/06 GA I E Wall A 0 178 too 200 59 2ransformer room -East wall 136 10/01/06 GA I IE Wall C 0 191 80 200 18 2ransformer room -East wall 136 10/01/06 GA I E Wall A 2 97 100 200 38 Transformer room -East wall 136 1 0/01/06 CA 1 E Wall C 2 45 100 220 .13 Transformer room -East wall 158 11/08/06 GA 1 E Wall A 0 0 158 11/08/06 GA 1 E Wall C 0 0 158 11/08/06 GA 1 E Wall E 0 0 158 11/08/06 GA I E Wall G 0 0 158 11/08/06 GA I E Wall A 2 0 158 11/08/06 GA I E Wall C 2 0 158 11/08/06 GA I E Wall E 2 0 156 11/08/06 GA I E Wall G 2 0 159 11/08/06 GA I N Wall A 0 4 162 11/08/06 GA 1 E Wail A 0 0EaI 162 11/08/06 G A 1 NEW ai l C 0 4 0_ _ ~ I 1 6 2 1 1 / 0 8 / 0 6 G A 1 NEW a lI A 2 0 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 0 N_ _ _ _ E W a l l 1 6 2 1 1 / 0 8 / 0 6 G A I E W a l l C 2 0__ _ _ _ _ _ _ _ _ _ _ _ _ _ E W a l l ENERCON Services, inc.

TRANSFORMER ROOM -SEE DRAWING 23 SOUTH WALL A2 A G O BO CO DO EO FO GO HO NORTH WALL AO Al A2 BO CO DO EO FO GO HO WALL -SEE FIGURE 22 FOR SURVEY MAP UNIVERSITY OF WASHINGTON NUCLEAR REACTOR DECOMMISSIONING ROBOTICS LABORATORY SURVEY UNIT 1-6 SOUTH WALL 2 CEILING NH2 G2 F2 E2 D2 C2 B2_SA2 B2 C2 D2 E2 NORTH WALL 2 F2 G2 HOIH1 H)6-UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS REACTOR DECOMMISSIONING Drawn by. DM ROBOTICS LABORATORY DRAWING 23 SURVEY UNIT 1-6 Enercon Services WEST WALL A2 Al AO BO CO DO FLOOR SOUTH WALL Al AO SECTION EXTENDS INTO WALL EAST WALL AO BO DO Al>A2 _ _ _)6ý-UNIVERSITY OF WASHINGTON NUCLEAR scale: NTS PROJECT REACTOR DECOMMISSIONING Dram byr. DM DRAWING TRANSFORMER ROOM DRAWING 24 SURVEY UNIT 1-6 Enercon Services _

University of Washington More Hall Annex D&D, Project 10492 Attachment 30 -Sub-Unit 1-6-4 Robotics Lab Ceiling FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 1-6-4 (Robotics lab ceiling)Location

Description:

I Robotics lab ceiling-r I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm]100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

1) (giR/hr)Number of measurements:

N/A 29 29 29 N/A Number of measurements needed (): N/A 9 9 9 N/A Maximum value of results: N/A 4 496 54 N/A Mean value of results: N/A 1 108 6 N/A Standard Deviation of results: N/A 1 86 13 N/A Degree of Freedom (2): N/A 1.701 1.701 1.701 N/A 4,value: N/A 1 135 10 N/A Guideline level: N/A 20 5000 1000 N/A Are there sufficient measurements?

N/A Yes Yes Yes N/A Is the max value < guideline level? N/A Yes Yes Yes N/A Is ýta < guideline?

N/A Yes Yes Yes N/A Does survey unit pass? N/A Yes Yes Yes N/A 6) as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-I for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-6-4 (Robotics lab ceiling)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta BetaScan BetaScan Alpha Beta Net hR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 135 10/01/06 GA I Ceiling A 0 54 100 180 0 FTransformer Room 135 10/01/06 GA 1 Ceiling C 0 129 100 200 0 135 10/01/06 GA I Ceiling E 0 187 80 220 0 135 10/01/06 GA I Ceiling 0 0 105 80 200 0 135 10/01/06 GA 1 Ceiling 1 0 155 100 200 0 135 10/01/06 GA 1 Ceiling A 2 58 100 180 8 Transformer Room 135 10/01/06 GA I Ceiling C 2 77 80 200 0 135 10/01/06 GA I Ceiling E 2 49 100 180 0 135 10/01/06 GA I Ceiling G 2 45 100 200 13 135 10/01/06 GA I Ceiling 1 2 71 80 180 0 135 10/01/06 GA 1 Ceiling A 4 94 100 200 0 135 10/01/06 GA I Ceiling C 4 41 100 160 18 135 10/01/06 GA -Ceiling E 4 92 80 200 0 135 10/01/06 GA I Ceiling E 4 142 100 220 0 135 10/01/06 GA I Ceiling G 4 79 80 220 13 135 10/01/06 GA I Ceiling A 6 139 100 220 3 135 10/01/06 GA 1 -Ceiling C 6 127 80 200 0 135 10/01/06 GA I Ceiling E 6 496 1oo 200 0 135 10/01/06 GA I Ceiling G 6 75 80 200 43 135 10/01/06 GA I Ceiling 1 6 94 too 220 18 137 10/01/06 GA I Ceiling A 0 64 100 200 0 North side of beam 137 10/01/06 GA I Ceiling A 2 75 80 220 0 North side of beam 137 10/01/06 GA I Ceiling C 2 51 100 200 0 North side of beam 137 10/01/06 GA I Ceiling E 2 86 80 220 0 North side of beam 137 10/01/06 GA I Ceiling G 2 45 100 200 8 North side of beam 137 10/01/06 GA I Ceiling A 2 73 too 200 0 South side of beam 137 10/01/06 CA I Ceiling C 2 161 120 220 54 South side of beam 137 10/01/06 GA 1 Ceiling E 2 170 100 200 0 South side of beam 137 10/01/06 GA I Ceiling G 2 137 too 180 0 South side of beam 161 11/08/06 GA I Ceiling A 0 0 161 11/08/06 GA I Ceiling C 0 0 161 111/08/061 GA_ I Ceiling E 0 0 161 11/08/06 GA 1 ICeiling G 0 0 161 11/08/06 GA I Ceiling 1 0 0 161 11/08/06 GA I Ceiling A 2 0 1 61 11/08/06 GA I Ceiling C 2 4 16t 11/08/06 GA 1 Ceiling E 2 0 161 11/08/06 GA I Ceiling G 2 0 161 11/08/06 GA I Ceiling 1 2 0 161 11/08/06 GA I Ceiling A 4 0 161 1 11/08/06 1GA I Ceiling C 4 4 161 11108/06 GA I Ceiling E 4 0 161 11/08/06 GA I Ceiling G 4 0 161 11/08/06 GA I Ceiling 1 4 0 161 11/08/06 GA 1 Ceiling A 6 0 161 11/08/06 GA I Ceiling C 60 61 11/08/06 GA I CeilingE 60 161 11/08/06 GA I Ceiling G 64 161 ll1/08/06 GA 1 Ceiling 1 6 0 163 111/08/06 GA I Ceiling, A 13 ta 1 Ceiling A 2 ___ IN side of beam I ICeiling C 12 0 1JN side ofbean ENERCON Sermices, ne.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-6-4 (Robotics lab ceiling)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 163 11/08/06 GA I Ceiling E 2 0 N side of beam 163 11/08/06 GA I Ceiling G 2 0 N side of beam 163 11/08/06 GA I Ceiling A 2 4 S side of beam 163 11/08/06 GA I Ceiling C 2 0 S side of beam 163 11/08/06 GA I Ceiling E 2 0 S side of beam 163 11/08/06 GA 1 Ceiling G 2 0 S side of beam ENERCON Se-i-, in.

SOUTH WALL 2 CEILING H2 G2 F2 E2 D2 C2 B2 A2A9A A2 B2 C2 D2~E2 NORTH WALL 2 F2 G2~HO Hi H2 HO GO FO EO DO CO BO BI B2 B3 B4 B5 B6 B7)6-A4 A5 A6 A7 A4 A5 A6 A7 POET UNIVERSITY OF WASHINGTON NUCLEAR Scae: NTS REACTOR DECOMMISSIONING -Dr by: DM DRAWING ROBOTICS LABORATORY DRAWING 23 SURVEY UNIT 1-6 Enercon Services ,

University of Washington More Hall Annex D&D, Project 10492 Attachment 31 -Unit 1-7 Offices, Restrooms, and Hallway FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2

• Final Status Decision Summary for Unit 1-7 (Offices, restrooms, and hallway)I Location

Description:

Offices, restrooms, and hallway I I I~Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (gR/hr)Number of measurements:

N/A 30 30 30 30 Number of measurements needed (1): N/A 9 9 9 N/A Maximum value of results: N/A 4 417 38 0 Mean value of results: N/A 1 188 8 0 Standard Deviation of results: N/A 2 105 12 0 Degree of Freedom (2): N/A 1.699 1.699 1.699 1.699 pt value: N/A 1 220 11 0 Guideline level: N/A 20 5000 1000 5 Are there sufficient measurements?

N/A Yes Yes Yes Yes Is the max value < guideline level? N/A Yes Yes Yes Yes Is gt < guideline?

N/A Yes Yes Yes Yes Does survey unit pass? N/A Yes Yes Yes Yes (1) as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 1-7 (Offices, restrooms, and hallway)FSS # Date Class Flor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net IJR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 114 09/28/06 UN I Floor F 1 184 80 140 0 0 Grad Room 1 114 09/28/06 UN 1 Floor F 2 77 60 120 8 0 Grad Room 2 114 09/28/06 UN I Floor F 3 90 80 180 0 0 Grad Room 3 114 09/28/06 UN I Floor F 4 12 60 100 3 0 Grad Room 4 114 09/28/06 UN 1 Floor F 5 96 60 120 0 0 Grad Room 5 114 09/28/06 UN 1 Floor F 6 88 100 140 0 0 Grad Room 6 114 09/28/06 UN I Floor F 7 109 60 140 0 0 Grad Room 7 114 09/28/06 UN I Floor F 8 74 80 120 0 0 Grad Room 8 114 09/28/06 UN I Floor F 9 52 60 120 0 0 Grad Room 9 114 09/28/06 UN I Floor F 10 56 60 I00 33 0 Grad Room 10 114 09/28/06 UN i Floor F 11 417 120 220 23 0 Womano room 11 114 09/28/06 UN I Floor F 12 152 80 160 0 0 Woman6 room 12 114 09/28/06 UN I Floor F 13 337 100 160 0 0 Meob room 13 114 09/28/06 UN I Floor F 14 105 80 180 28 0 Me, room 14 1i4 09/28/06 UN 1 Floor F 15 83 100 180 0 0 W1 15 114 09/28/06 UN 1 Floor F 16 114 80 120 8 0 1l 16 114 09/28/06 UN I Floor F 17 158 100 140 0 0 I1 17 138 10/01/06 UN 1 Floor F 38 219 180 260 0 0 1829 Dr 138 10/01/06 UN I Floor F 39 266 120 280 3 0 1930 hr 138 10/01/06 UN I Floor F 20 247 120 260 33 0 20 hal I 138 10/01/06 UN I Floor F 21 212 120 260 0 0 20 Rall 138 10/01/06 UN I Floor FF 22 294 140 260 0 0 22 hall 138 11/01/06 UN I Floor F 23 247 120 240 8 0 23 hall 138 1 1/01/06 UN I Floor F 24 313 120 240 23 0 24 4al[138 10/01/06 UN I Floor F 25 217 120 220 38 0 25 Calroom 138 10/01/06 UN I Floor F :26 242 100 220 0 0 26 Cael roomn 138 10/01/06 UN I Floor F 27 258 120 240 18 0 27 Calc room 138 10/01/06 UN I Floor F 28 1309 160 240 0 0 28 Director off 138 10/01/06 UN I Floor F 29 322 160 240 0 0 29 Director off 138 10/01/06 UN i Floor F 30 281 160 260 0 0 30 Director off 157 1 1/08/06 UN I Floor F 1 0 Grad Room 1 157 11/08/06 UN 1 Floor F 2 0 Grad Room 2 157 11/08/06 UN 1 ,Floor F 3 0 G rad Room 3 157 11/08/06 =UN I Floor F 4 0Grad Room 4 157 11i/08/06 UNT iFloor F 5 4Grad Room 5 157 11/08/06 1 UN I 157 11/I Floor Floor Floor Floor F F___ 6 0I ~ 4 4-1 I t~ ___________________

fi n F 7 157 Sl/I(4 4 0 0 Grad Room 7 Grad Room 8 Grad Room 9 Grad Room 10 157 11/08/06 1 UN I 157 157 157 157 11/08/06 11/08/06 11/08/06 11/08/06 UN I Floor F to 1 T Floor Floor Floor Floor F II 0I nm thr n I I F 11 0I Imr ro 11~'!~F 12 FE '3]___ I .: 0 0 0 T Woman§ room 12 Menl room 13 MenM room 14 lill 15 157 11/08/06 UN F 14 157 157 11/08/06 11/08/06 11/08/06 11/08/06 UN UN UN UN I-1 1 Floor Floor Floor Floor F 15 157 F T F T 16 17 18 19 0 11 16 164 164 164 164 164 11/08/06 11/08/06 11/08/06 11/08/06 UN I Floor 0 I bi -1119 UN II Floor F 20 4 M1 20 1 _ _ _ _ 1 1_ _ Id:l 6212 1___ 1112 ENERCON Soe,.i, b..

0 University of Washington More Hall Annex Final Status Survey Results -Unit 1-7 (Offices, restrooms, and hallway)FSS N Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (rpm) DPM DPM 164 11/08/06 UN I Floor F 23 4 IM123 164 11/08/06 UN 1 Floor F 24 0 fil1l24 164 11/08/06 UN I Floor F 25 0 Calc Room 25 164 11/08/06 UN I Floor F 26 0 Calc Room 26 164 11/08/06 UN 1 Floor F 27 0 Calc Room 27 164 11/08/06 UN 1 Floor F 28- -Directors room 28 164 11/08/06 UNl I Floor -F 29 0 1 Directors roomn 29 164 11/08/06 UN II Floor F 30 1 1 1 0 1 Directors room 30 ENERCON Servies, h..

WEST WALL NORTH WALL FLOOR EAST WALL SOUTH WALL CEILING UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS REACTOR DECOMMISSIONING Drawn by: DM GRADUATE ROOM DRAWING 26 SURVEY UNIT 1-7 Enercon Services NORTH WALL FLOOR SOUTH WALL CEILING UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS PROJECT REACTOR DECOMMISSIONING Drawn by: DM DRAWING DIRECTOR'S ROOM D DRAWIN UNDRAWING 27 SURVEY UNIT 1-7 Enercon Services_____

WEST WALL FLOOR EAST WALL 7.......SOUTH WALL CEILING UNIVERSITY OF WASHINGTON NUCLEAR REACTOR DECOMMISSIONING CALCULATING ROOM SURVEY UNIT 1-7 T WALL SOUTH WALL NORTH WALL CEILING)6-UNIVERSITY OF WASHINGTON NUCLEAR REACTOR DECOMMISSIONING CONTROL OFFICE SURVEY UNIT 1-7 University of Washington More Hall Annex D&D, Project 10492 Attachment 32 -Sub-Unit 2-1-1 Control Room Ceiling, East, and North Walls FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status-Decision Summary for Unit 2-1-1 (Control room ceiling, east, and north walls)I Location

Description:

IControl room ceiling, east, and north walls I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) 0/r Number of measurements:

20 20 20 20 N/A Number of measurements needed 9 9 9 9 N/A Maximum value of results: 65 4 183 44 N/A Mean value of results: 9 0 38 9 N/A Standard Deviation of results: 16 1 52 14 N/A Degree of Freedom (2): 1.729 1.729 1.729 1.729 N/A ga value: 16 0 58 15 N/A Guideline level: 100 20 5000 1000 N/A Are there sufficient measurements?

Yes Yes Yes Yes N/A Is the max value < guideline level? Yes Yes Yes Yes N/A Is jt1 < guideline?

Yes Yes Yes Yes N/A Does survey unit pass? Yes Yes Yes Yes N/A () as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-I for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 2-1-1 (Control room ceiling, east, and north walls)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (rpm) DPM DPM 005 08/11/06 GA 2 Northern E Wall A 0 4 ND ND 0 0 120 0 0 4m2 area Includes vent duct 005 08/11/06 GA 2 Northern E Wall A *2 0 ND ND 0 0 120 0 44 4n2 area 005 08/11/06 GA 2 Northern E Wall C 0 8 ND ND 67 0 140 0 0 4m2 area 005 08/11/06 GA 2 Northern E Wall C 2 0 ND ND 54 0 140 0 2 4n2 area 006 08/11/06 GA 2 Southern E Wall A 0 0 ND ND 0 0 100 0 20 4m2 area 006 08/11/06 GA 2 Southern E Wall A 2 8 ND ND 0 0 100 4 30 4m2 area 006 08/11/06 GA 2 Southern E Wall C 0 4 ND ND 0 0 100 0 0 4n2 area 006 08/11/06 GA 2 Southern E Wall C 2 0 ND ND 0 0 100 0 2 4n2 area 008 08/12/06 GA 2 N Wall A 0 0 ND ND 57 0 120 0 29 4m2 area includes drainline 008 08/12/06 GA 2 N Wall A 2 0 ND ND 183 0 100 0 38 4m2 area includes drainliue 008 08/12/06 GA 2 N Wall C 0 0 ND ND 158 0 100 0 0 4m2area Oil 08/12/06 GA 2 Ceiling A 0 15 ND ND 0 0 140 0 0 4m2 oil 08/12/06 GA 2 Ceiling A 2 30 ND ND 62 0 120 0 1 4rn2 OIl 08/12/06 GA 2 Ceiling A 4 15 ND ND 17 0 120 0 0 4m2 011 08/12/06 GA 2 Ceiling C 0 10 ND ND 44 0 140 0 6 4m2 011 08/12/06 GA 2 Ceiling C 2 0 ND ND 30 0 140 0 0 4m2 Oil 08/12/06 GA 2 Ceiling C 4 0 ND ND 26 0 120 0 10 4m2 Oil 108/12/06 GA 2 Ceiling E I 30 ND ND 8 0 100 0 0 4m2 011I 08/12/06 GA 2 Ceiling E 4 0 ND ND 0 0 120 0 6 4mi2 011i 08/12/06 GA 2 COiling E 2 65 ND ND 64 0 120 0 1 4m2 ENERCON Sevisa, inc.

University of Washington More Hall Annex D&D, Project 10492 Attachment 33 -Sub-Unit 2-1-2 Control Room Floor, South, and West Walls FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 2-1-2 (Control room floor, south, and west walls)I Location

Description:

I Control room floor, south, and west walls I I h Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (gR/hr)Number of measurements:

17 17 17 17 6 Number of measurements needed (" 9 9 9 9 N/A Maximum value of results: 6 0 53 39 0 Mean value of results: 1 0 8 7 0 Standard Deviation of results: 2 0 18 12 0 Degree of Freedom (2): 1.746 1.746 1.746 1.746 2.015 ji value: 2 0 16 12 0 Guideline level: 100 20 5000 1000 5 Are there sufficient measurements?

Yes Yes Yes Yes Yes Is the max value < guideline level? Yes Yes Yes Yes Yes Is gie < guideline?

Yes Yes Yes Yes Yes Does survey unit pass? Yes Yes Yes Yes Yes (1) as interpolated from NUJREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-i for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 2-1-2 (Control room floor, south, and west walls)FSS # Date Class Floor Sorface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net jJR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpn) (cpm) DPM DPM 002 08/11/06 GA 2 Floor C 0 0 ND ND 0 0 100 0 2 0 44m2 area 002 08/11/06 GA 2 Floor C 2 4 ND ND 0 0 100 0 11 0 4m2 area 002 08/11/06 GA 2 Floor C 4 4 ND ND 0 0 100 0 0 0 4m2 area 003 08/11/06 GA 2 Floor A 0 0 ND ND 0 0 60 0 0 0 4nm2 area 003 08/11/06 GA 2 Floor A 2 0 ND ND 0 0 80 0 0 0 4i2 area 003 08/11/06 GA 2 Floor A 4 0 ND ND 0 0 80 0 34 0 4m2 area 004 08/11/06 GA 2 W Wall A 0 0 ND ND 0 0 80 0 0 4un2 area 004 08/11/06 GA 2 W Wall A 2 0 ND ND 0 0 100 0 0 1mn2 area 004 00/11/06 GA 2 W Wall C 0 5 ND ND 0 0 80 0 0 4m2 area 004 08/11/06 GA 2 WVWall C 2 0 ND ND 0 0 80 0 39 4m2 area 004 08/11/06 GA 2 W Wall E 0 0 ND ND 0 0 80 0 2 4un2 area 004 08/11/06 GA 2 W Wall E 2 0 ND ND 0 0 80 0 0 4m2 area 004 08/11/06 GA 2 W Wall G 0 0 ND ND 0 0 80 0 0 4m2 area 009 08/12/06 GA 2 S Wall A 0 1 ND ND 53 0 100 0 15 4m2 area 009 0/12/06 GA 2 S Wall A 2 6 ND ND 51 0 120 0 15 4m2 area 009 08112/06 GA 2 SWaII C 0 0 ND ND 21 0 100 0 0 4m2area 009 08/12/06 GA 2 S Wall C 2 0 ND ND 14 0 120 0 0 4m2 area ENERCON Service, i6.

University of Washington More Hall Annex D&D, Project 10492 Attachment 34 -Sub-Unit 2-2-1 Lecture Briefing Room Ceiling, East, and North Walls FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2

• Final Status Decision Summary for Unit 2-2-1 (Lecture briefing room ceiling, east, and north walls)Unit Designator:

1 2-2-1 I I Location

Description:

ILecture briefing room ceiling, east, and north walls I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm100cm 2) (dpm/100cm

2) (dpm/100cm

2) (dpm100cm 2) (iR/hr)Number of measurements:

16 16 16 16 5 Number of measurements needed (1): 9 9 9 9 N/A Maximum value of results: 39 3 443 69 2 Mean value of results: 16 0 71 9 1 Standard Deviation of results: 13 1 123 20 1 Degree of Freedom (2) 1.753 1.753 1.753 1.753 2.132 gvalue: 22 1 125 17 2 Guideline level: 100 20 5000 1000 5 Are there sufficient measurements?

Yes Yes Yes Yes Yes Is the max value < guideline level? Yes Yes Yes Yes Yes Is ýi < guideline?

Yes Yes Yes Yes Yes Does survey unit pass? Yes Yes Yes Yes Yes (1) as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 2-2-1 (Lecture briefing room ceiling, east, and north walls)FSS # Date Class Flour Surface X Y Alpha Alpha Alpha Beta Beta Scan BetaScan Alpha Beta Net pR Comments Coord. Coard. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 007 08/12/06 GA 2 Ceiling A 0 25 ND ND 0 0 100 0 0 4m2 area 007 08/12/06 GA 2 Ceiling A 2 5 ND ND 0 0 100 0 0 4m2 area 007 08/12/06 GA 2 Ceiling A 4 25 ND ND 0 0 100 0 0 4m2 area 007 08/12/06 GA 2 Ceiling C 0 0 ND ND 0 0 120 0 1 4m2 area 007 08/12/06 GA 2 Ceiling C 2 5 ND ND 15 0 120 0 10 4m2 area 007 08/12/06 GA 2 Ceiling C 4 10 ND ND 24 0 100 0 1 4m2 area 059 09/07/06 GA 2 E Wall A 0 17 222 40 200 0 0 1 East Wall, khter 059 09/07/06 GA 2 E Wall A 2 24 142 40 180 0 0 1 East Wall, Windows 059 09/07/06 GA 2 E Wall C 0 36 443 40 280 0 0 2 East Wall, khter 059 09/07/06 GA 2 E Wall C 2 36 161 40 220 0 0 1 East Wall, Windows 059 09/07/06 GA 2 E Wall E 0 5 121 40 180 0 0 2 East Wall, Eliter, Windows 061 09/08/06 GA 2 N Wall A 0 39 0 40 240 0 69 N. Wall, Blackboard 061 09/08/06 GA 2 N Wall A 2 9 12 40 280 3 46 B. Board, Window, Wall 061 09/08/06 GA 2 N Wall C 0 14 0 40 260 0 0 B. Board 061 09/08/06 GA 2 N Wall C 2 4 0 40 260 0 0 B. Board, Window, Door 061 09/08/06 GA 2 N Wall E 0 0 0 40 220 3 1 9 Door. Window, B. Board ENERCON S-rices, inc.

NORTH WALL SLATE CHALKBOARD WEST WALL E0 DO CO BO A2 Al AO CEIILING~FLOOR A4 A3 A2 Al AO BO CO DO EQ EAST WALL EO DO CO BO AO Al A2 AO BO CO DO EO Al A2 A3 A4 PROJECT UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS REACTOR DECOMMISSIONING Drawn by: DM DRAWING LECTURE ROOM DRAWING 31 SURVEY UNIT 2-2 Enercon Services University of Washington More Hall Annex D&D, Project 10492 Attachment 35 -Sub-Unit 2-2-2 Lecture Briefing Room Floor, South, and West Walls FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 2-2-2 (Lecture briefing room floor, south, and west walls)I Location

Description:

ILecture briefing room floor, south, and west walls I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cm

2) (dpmIOOcm 2) (pIR/hr)Number of measurements:

15 15 15 15 10 Number of measurements needed (1): 9 9 9 9 N/A Maximum value of results: 42 4 198 63 2 Mean value of results: 10 1 87 6 2 Standard Deviation of results: 13 2 57 18 0 Degree of Freedom (2): 1.761 1.761 1.761 1.761 1.833 g, value: 16 2 112 14 2 Guideline level: 100 20 5000 1000 5 Are there sufficient measurements?

Yes Yes Yes Yes Yes Is the max value < guideline level? Yes Yes Yes Yes Yes Is gci < guideline?

Yes Yes Yes Yes Yes Does survey unit pass? Yes Yes Yes Yes Yes (1) as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 2-2-2 (Lecture briefing room floor, south, and west walls)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net PR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (epm) (epm) DPM (cpm) (cpm) DPM DPM 055 09/07/06 GA 2 Floor A 0 5 82 40 180 0 0 2 055 09/07/06 GA 2 Floor A 2 11 78 40 200 0 0 2 055 09/07/06 GA 2 Floor C 0 0 80 40 200 0 0 2 055 09/07/06 GA 2 Floor C 2 11 41 40 160 4 0 2 055 09/07/06 GA .2 Floor E 0 0 126 40 200 4 0 2 058 09/07/06 GA 2 S Wall A 0 .0 -82 40 210 0 0 1 South Wall, Blackboard 058 09/07/06 GA 2 S Wall A 2* 0 179 40 220 10 0 1 Blackboard, Window 058 09/07/06 GA 2 S Wall C 0 36 198 40 260 4 63 2 Blackboard, Wall 058 09/07/06 GA 2 S Wall C 2 42 136 40 210 4 0 1 Blackboard, Window 058 09/07/06 GA 2 S Wall E 0 11 113 40 200 0 0 2 S. Wall, B.B. Window 062 09/08/06 GA 2 W Wall A 0 0 59 40 280 0 0 West Wall, Window 062 09/08/06 GA 2 W Wall A 2 14 0 40 210 0 0 West Wall, Window 062 09/08/06 GA 2 W Wall C 0 14 77 40 280 0 31 West Wall, Window 062 09/08/06 GA 2 W Wall C 2 4 0 40 220 0 0 West Wall, Window 062 09/08/06 GA 2 W Wall E 0 0 48 40 240 0 0 West Wall, Window 063 09/08/06 GA 2 Floor A 0 4800 6400 Gamma Scans Over Floor, 100%063 09/08/06 GA 2 Floor B 0 5000 6500 Gamma Scans Over Floor, 100%063 09/08/06 GA 2 Floor C 0 4900 6500 N/A 063 09/08/06 GA 2 Floor D 0 5200 6700 N/A 063 09/08/06 GA 2 Floor E 0 5200 6800 N/A ENERCON Seroices, i.o.

University of Washington More Hall Annex D&D, Project 10492 Attachment 36 -Unit 2-3 Stairs, 2nd Floor Foyer, Fan Room, and Mechanical Room FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2

• Final Status Decision Summary for Unit 2-3 (Stairs, 2nd floor foyer, fan room, mechanical room)Unit Designator:

1 2-3 I Class: 1 UN Certainty

'X I Location

Description:

Stairs, 2nd floor foyer, fan room, mechanical room I Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm/100cm

2) (dpm/100cm

2) (dpm/100cmZ) (dpm/100cm

2) (pR/hr)Number of measurements:

N/A 57 56 57 52 Number of measurements needed (1): N/A 9 9 9 N/A Maximum value of results: N/A 8 401 123 0 Mean value of results: N/A 1 141 17 0 Standard Deviation of results: N/A 2 82 24 0 Degree of Freedom (2).: N/A 1.673 1.674 1.673 1.676 g,, value: N/A 2 159 22 0 Guideline level: N/A 20 5000 1 000 5 Are there sufficient measurements?

N/A Yes Yes Yes Yes Is the max value < guideline level? N/A Yes Yes Yes Yes Is < guideline?

N/A Yes Yes Yes Yes Does survey unit pass? N/A Yes Yes Yes Yes () as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 2-3 (Stairs, 2nd floor foyer, fan room, mechanical room)FSS N Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net VR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 010 08/12/06 UN 2 Floor A 0 1 ND ND 154 0 160 0 6 0 Floor SW Comer 010 08/12/06 UN 2 W Wall A 1 0 127 0 61 0 Pipe End W Wall 010 08112/06 UN 2 Floor A 2 1 ND ND 156 0 120 0 0 0 Floor NW Comer 010 08/12/06 UN 2 SW Wall A 3 15 ND ND 94 0 140 0 0 0 Inside Vent Duct SW Wall 010 08/12/06 UN 2 W Wall A 4 15 ND ND 142 0 120 0 0 0 W Wall 010 08/12/06 UN 2 Floor A 5 6 ND ND 144 0 240 0 29 0 Floor Center 010 08/12/06 UN 2 Floor A 6 1 ND ND 111 0 120 0 10 0 Floor NE Comer 010 1 08/12/061 UN 1 2 Floor A 17 15 ND ND 179 0 1 160 0 I10 0 Floor SE Comer G II ND ND 97 1 0 140 140 120 120 T20 0 1 0 0 IN Wall 4 010 1 08/12/061 UN 1 2 IS Wall IAK 1 10 107 0 010 08/12/061 UN 2 IE Wall A I I1 11 ND I ND 111 1 0 0 0 1 0 Inside Vent Duc E Wall 010 (f 014 2 E Wall 2 Vent 2 Vent 2 Vent A 12 M N/A M N/A M NIA 8 1 24 0 Smear Too of Vent E Wall 0 014 08/15/06 UN 1 0 90 74 014 1 08/15/06 UN 7 220 0 300 0 200 8 350 0 0 0 Ventilation exhaust in South fan loft -South inside 0 0 Ventilation exhaust in South fan loft -South outside 0 0 Ventilation exhaust in South fan loft -East Inside 23 0 Ventilation exhaust in South fan loft -East outside 0 014 j08/15/061 UN 1 2 Vent M I N/A 0 0 178 1 90 Vent M IVent L m I 014 1 08115/061 UN 1 2 Vent-N/A N/A N/A N/A 3 20 3-3 0 0 T 01 1 0 2 0 90 220 300 220 250 4 13 0 Ventilation exhaust in South fan loft -Top inside 0 0 0 Ventilatjio exhaust in South fas loft -North Inside 0 32 0 Ventilation exhaust in South fan loft -North outside 0 0 0 Ventilation exhaust in South fan loft -West Inside 187 90 1 350 0 1 0 1 0 IVentilation exhaust in South fas leoft -Top outside 014 1 08/15/061 UN 1 2 1Verit M 014 08115/06 UN 2 Vent 112 09/28/06 UN 2 Floor 112 09/28/06 UN 2 Floor 112 09/28/06 UN 2 Floor 112 09/20/06 UN 2 Floor M N/A F 1 F 2 F 3 F 4 F 5 F 6 3 0 6 90 143 1 80 1 120 1 0 1 27 1 0 IN1 loft near fan room 176 60 140 0 0 0 I2 loft near h20 tanks 112 09/28/06 UN 2 112 09/28/06 UN 2 112 09/28/06 UN 2 ?I 112 09/28/06 UN1 2 Floor Floor Floor Floor 143 T 100 63 2 0 #5 loft near h20 mssain 0 #6 loft airduct 61 216 242 134 171 61 80 To0o 120 150 200 4 4 123 0 #7loftnearAiXC 8 017 0 #8 loft near HVAE 112 09/28/06 UN 112. 09/28/06 UN 2 Wall 2 Wall W 1 9 W I 1t 100 140 0 0 0 #9 loft wall near cir Im 60 120 0 42 1 0 610 loft wall sear 100 140 0 58 1 0 Ul Iloft wall N 2 lWail 112 09/28/06 1 UN 2 Floor 94 10t0 140 0 1 0 0 1#12 loft 3Rd step down 112 09/28/06 UN 2 112 09/20/06 UN 2 112 09/28/06 UN 2 112 09/28/06 UN 2 Floor Floor Floor Floor Floor F 13 1 F 14 F 15 F 16 F 17 F 18 F 19 F 20 109 1 120 160 4 0 0 52 1 100 180 0 1 37 107 1 100 160 1 0 1 32 0-0-0'th step down loor hall lor sall#1 207-297-171 211 100 1 200 1 0 1 47# 16 2nd floor wall 112 09/28/06 UN 112 09/28/06 UN 2 Floor 2 Floor 0 0 181I 2nd floor St. well 112 112 09/28/06 UN 2 Floor 09/28/06 UN 2 Floor 112 1 09/28/061 UN 1 2 Floor Floor Floor Floor Floor Floor F 23 F 24 F 25 F 26 F 27 F 28 F 29 F 30 286 100 160 0 27 0 #21 2nd floor 5th step down 182 100 150 0 0 0 #22 2nd floor St. well 251 100 160 0 22 0 #23 2nd floor St. well 268 120 200 0 58 0 #24 2nd floor 9th step 401 100 180 0 7 0 625 2nd floor l2th step 165 100 160 0 12 0 #26 2nd floor St. well 275 10 140 0 7 0 627 2nd floor St. well 107 80 130 0 58 0 #28 2nd floor St. well 76 60 130 87 0 # 29 2ud floor St. well 88 60 120 1 7 0 #30 2nd floor St. well 21 st ENERCON Servic,, i-o.112 109/28/061 UN 2 112 1 09/28/061 UN 1 2 Floor University of Washington More Hall Annex Final Status Survey Results -Unit 2-3 (Stairs, 2nd floor foyer, fan room, mechanical room)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta BetaScan BetaScan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct MIn. Max. Wipe Wipe DPM (cpmn) (cpru) DPM (cpm) (cpm) DPM DPM 139 10/02/06 UN 2 Vent M 1 110 100 200 0 1 P fresh air intake 139 10/02/06 UN 2 Vent M 2 96 100 180 0 2 HVAC 020301 139 10/02/06 UN 2 Vent M 3 175 100 180 0 3 HVAC 020202 139 10/02/06 UN 2 Vent M 4 56 80 160. 0 4 HVAC 020201 139 10/02/06 UN *2 _Vent M 5 75 100 180 0 5 fresh air intake 165 11/00/06 UN I Floor F -0 Fresh air intake I 165 11/08/06 UN I Floor F 2 4 21iVAC 020301 165 11/08/06 UN I Floor F 3 4 3 HVAC 020202 165 11/08/06 UN 1 Floor F 4 0 4 HVAC 020201 165 11/0t/06 UN I Floor F 5 14 5 Frsh air intake ENERCON Serviem, ito.

WEST WALL SOUTH WALL F LO0OR NORTH WALL....~~~~t St.....air

......Opening EAST WALL CEILING UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS PROJECT REACTOR DECOMMISSIONING Drawn by: DM DRAWING HALLWAY -2 ND FLOOR DRAWING 32 SURVEY UNIT 2-3 Enercon Services University of Washington More Hall Annex D&D, Project 10492 Attachment 37 -Unit 3-1 Building Exterior FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 3-1 (Building exterior)Location

Description:

Building exterior Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces. (dpml/00cm2) (dpm/100cm2) (dpm/100cm) (dpm/100cm

2) (piRhr)Number of measurements:

N/A 36 36 36 36 Number of measurements needed : N/A 9 9 9 N/A Maximum value of results: N/A 4 875 20 1 Mean value of results: N/A 0 256 1 0 Standard Deviation of results: N/A 1 133 5 0 Degree of Freedom (2): N/A 1.690 1.690 1.690 1.690 4 value: N/A 0 294 2 0 Guideline level: N/A 20 5000 1000 5 Are there sufficient measurements?

N/A Yes Yes Yes Yes Is the max value < guideline level? N/A Yes Yes Yes Yes is g, < guideline?

N/A Yes Yes Yes Yes Does survey unit pass? N/A Yes Yes Yes Yes as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

FSS # ýDate assFloor Surface X Y Alpha Alpha. Alpha Beta Beta Scan Be~taSan Alph~a Beta Net pR Commnents Coord. Coord. Direct Scan Mln Scan max Direct Mi.. Ma. Wipe Wipe DPM (cpH) (cpm) DPM (cpm) (cpm) DPM DPM 001 06/07/06 UN Ext Ext Ext Ext B Wall N Wall N Wall N Wall I N/A 0 0 E wall 2 N/A 3[~i N/A __0 T 0 0 0 0 0 0 N wall N wall N wall N deck 4 N/A 001 06/07106 UN Ext Floor 5 6 7 8 N/A N/A N/A N/A 0 0 0 0 0 0 0 1 E wall E deck Ewall S wall 9 NIA UN Ext Floor UN Exi 001 06/07/06 UN Exi 001 06/07/06 001 06/07/06 UN UN 001 001 06/07/06 UN 06107/06 UN Ext Ext Ext Ext Ext Ext Ext Effxt Floor Floor E Wall Floor E Wall EWall N Wall Exterior N Wall N Wall Exterior N Wall 001 06/07/06 001 06/07/06 UN U-ON 10 II 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 A A A A A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 1 2 3 4 0 0 0 0_0 0 0 0 0 0 0 0 0 0 0 S wall Deck SE drain Deck SSE draic E wall Loading dock E wall 0 0 S deck S wall S wa[001 001 001 001 001 001 001 001 021 021 021 021 021 06/07/06 UN Ext 06/07/06 UN Ext 06/07/06 UN 06/07/06 UN 06107106 UN 06/07/06 UN 06/07/06 UN 06/07/06 UN 08/19/06 UN 08119/06 UN 08/19106 UN 08/19/06 UN 08/19/06 UN Ext Ext Ext Ext Ext Ext Ext Ext Ext Ext Ext Ext Ext Ext Ext-at-Ext 0 0 0 0 0_0-0 0 4 0 0 0 0 0 0_0_0_0 0 0w Asphalt N N wall N wall DoorwayF N wall S wall S wall S wall wall Hatch S S Wall S Wall Exterior Roof Roof Roof ND 1 44 0 1 175 1 0 2 1 11 m2 Ontop North Ret Tnk ND 227 0 200 0 0 1 1 lm2 Ontop North Ret Tuk 8 16 ND ND Nnl 598 a~x 0 0l 420 0 al 20 1 1hn2 Ontop South Ret Tak ND ND 875 0 220 0 0 1 ND 126 09/30/06 UN 126 09/30/06 UN 126 09/30/06 UN Roof E Wall N Wall N Wall N Wall Floor 235 365 233 306 0-0 80 160 280 220 0 0 1 1am2 Under South Ret T.lc 1am2 Under North Ret Tok Smears taken on survey FSS-0 Smears taken on survey FSS-(3 T 5 6 i 10 ------stke nsuvyFS-0~0 1 Smears taken on survey F55-001 OIIJ UN Ext IFloor 217 80 240 [ t Smears taken on survey FSS-001 219 1 80 260 1 1 11 0 ISmnears taken on survey FSS-001 0 0 University of Washington More Hall Annex Final Status Survey Results -Unit 3-1 (Building exterior)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan BetaScan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpn) (cpn) DPM (cpm) (epm) DPM DPM 126 09/30/06 UN Ext Floor 17 239 80 220 0 -Smears taken on survey FSS-001 126 09130106 UN Ext E Wall 18 237 80 240 0 Smears taken on survey FSS-001 126 09/30/06 UN Ext E Wall 19 221 80 260 0 1 Smears taken on survey FSS-001 126 09/30/06 UN Ext N Wall 20 229 80 240 0 Smears taken on survey FSS-001 126 09/30/06 UN Ext Exterior 21 258 80 240 0 Smears taken on survey FSS-001 126 09/30/06 UN Ext N Wall 22 244 80 260 0 Smears taken on survey FSS-001 126 09/30/06 UN Ext N Wall 23 76 80 240 0 Smears taken on survey FSS-001 126 09/30/06 UN Ext Exterior 24 231 80 220 0 Smears taken osi survey FSS-001 126 09/30/06 UN Ext N Wall 25 214 80 240 0 Smears taken on survey FSS-001 126 09/30/06 UN Ext S Wall 26 212 80 240 0 Smears taken on survey FSS-001 126 09/30/06 UN Ext S Wall 27 262 80 260 0 Smears taken on survey FSS-001 126 09/30/06 UN Ext S Wall 28 240 80 240 0 Ssears taken on survey FSS-001 126 09/30/06 UN Ext S Wall 29 239 80 220 -0 m Snsears taken on survey FSS-001 126 09/30/06 UN Ext Exterior 30 1 214 80 240 0 Smears takenoun survey FSS-001 ENERCON Srri ies, us.

University of Washington More Hall Annex D&D, Project 10492 Attachment 38 -Unit 3-2 Retention Tanks and Valve Gallery FSS Statistical Summary and Survey Data UW-MCP-OP-13, Rev. 2 Final Status Decision Summary for Unit 3-2 (Retention tanks and valve gallery)Location

Description:

[Retention tanks and valve alleryI Direct Alpha Removable Direct Beta Removable Gamma Results Alpha Results Results Beta Results Results All Surfaces (dpm]100cm

2) (dpm/100cm

2) (dpm/100cmZ) (dpm/100cm

2) (iRlhr)Number of measurements:

63 69 63 69 23 Number of measurements needed (1): 9 9 9 9 N/A Maximum value of results: 79 8 878 70 2 Mean value of results: 6 0 168 9 0 Standard Deviation of results: 12 1 124 15 1 Degree of Freedom (2): 1.671 1.669 1.671 1.669 1.717 g,,, value: 9 1 194 12 1 Guideline level: 100 20 5000 1000 5 Are there sufficient measurements?

Yes Yes Yes Yes Yes Is the max value < guideline level? Yes Yes Yes Yes Yes Is gh < guideline?

Yes Yes Yes Yes Yes Does survey unit pass? Yes Yes Yes Yes Yes as interpolated from NUREG/CR-5849 Table B-2 (2) from NUREG/CR-5849 Table B-1 for the listed certainty

%ENERCON Services, inc.

University of Washington More Hall Annex Final Status Survey Results -Unit 3-2 (Retention tankand valve gallery)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan MIn. Scan Max. Direct Min. Max. Wipe Wipe DPM (cpm) (cpm) DPM (cpm) (cpm) DPM DPM 015 08/16/06 AA Ext W Wall A 0 0 ND ND 0 0 140 0 70 Im2 W Wail S Retension Tank 015 08/16/06 AA Ext W Wall A 1 10 ND ND 117 0 120 2 0 lm2 W Wall S Retension Tank 015 08/16/06 AA Ext W Wall B 0 0 ND ND 154 0 140 2 0 1m2 W Wall S Retension Tank 015 08/16/06 AA Ext W Wall B 1 2 ND ND 412 0 140 0 0 1m2 W WallS Retension Tank 015 08/16/06 AA Ext N Wall A 0 22 ND ND 174 0 140 0 0 a1m2 N Wall S Retension Tank 015 08/16/06 AA Ext N Wall A 1 0 ND ND 101 0 140 0 5 hln2 N Wall S Retension Tank 015 08/16/06 AA Ext N Wall B 0 2 ND ND 128 0 160 2 0 lm2 N Wall S Retension Tank 015 08/16/06 AA Ext N Wall B 1 0 ND ND 181 0 140 0 0 Im2 N Wall S Retension Tank 015 08/16/06 AA Ext S Wall A 0 6 ND ND 457 0 160 0 0 Im2 S Wall S Retension Tank 015 08/16/06 AA Ext S Wall A 1 0 ND ND 161 0 180 0 19 lm2 S Wall S Retension Tank 015 08/16/06 AA Ext S Wall B 0 0 ND ND 130 0 180 0 38 lm2 S Wall S Retensiou Tank 015 08/16/061 AA I Ext IS Wall R I nt Nfl Nfl I 570-I4a O U I.,,? C Wall C nppcll TnL-B 1t~ 0 ND-- II--- ND 10l2 SWl SRFnnTn 015 08/16 015 08/16 A 0 A 1 B 0 B 1 2 0 0 0 ND ND ND ND ND ND ND ND 170 0 140 0 19 1m2 E Wall S Retention tank Ilm2 E WallIS Retention tank 015 08/16/06 1 AA I Ext IE Wall E Wall S Retention tank 015 08/16/06 016 08/17/06 016 08/17/06 016 08/17/06 AA I Ext I E Wall 110 0 140 E Wall S Retention tank AA I Ext Floor A I 0 7?Nfl I Nf 147 tt I 0Of It It I Ir9Iln r n hn lnin m l A 0 22 ND ND 147 0 200 0 1 0 1 2 11 m2 Floor -South Retention tank Al A 1 B 0 B 1 A 0 9 26 17 5 ND ND ND ND ND ND ND ND 156 878 195 337 0 T 0 140 0 0 2 1lm2 Floor -South Retention tank 2 1nm2 Floor -South Retention tank 016 08/17/06 AA I Ext Floor 2 1lm2 Floor -South Retention tank 016 016 08/17/061 AA IExt ICeiling 08/17/06Aý Ext Ceiling b8/17/061 IA Et Ceiin 08/17/06 1AA IExt Ciling!140 0 0 lm2 Ceilin -South retention tanI 016 A I1 B 0 B 1 A 0 5 1 17 0 ND I ND l101 0 19*1 O I Ut.v 0-120 0 0 lm2 Ceilin- -Sut etnto .u In,? fl~ilino -Cn,,lh rptwntinn Imnn 0 140 0 0 016 Im2 Ceiling -South retention tank 1m2 Ceiling -South retention tank lh2 W Wall -North retention tanl lm2 W Wall -North retention tan]018 08/18/06 1 AA Ext IW Wall ND ND Ext W Wall A 1 Ext W Wal 0 9 0 0 ND ND 105 0 140 0 0 ND ND 135 0 200 0 23 018 1 08/18/061 AA Ext W Wal ND 018 08/18/06 AA 018 08/18/06 AA 018 08/18/06 AA 018 08/18/06 AA Ext N Wall Ext IN Wall A 1 B-1 0 1 0 1 018 08/18/06 AA Ext S Wall 018 08/18/061 AA I Ext S Wall 0 0 0 0 4 0 0 0 4 ND ND ND ND ND ND ND ND ND ND 39 0 140 4 0 118 0 140 0 0 ND 111 0 1 140 0 0 97 0 140 0 [ha2 W Wall -North retention tank lIr2 W Wall -North retention tank lm2 N Wall -North retention tank 1hn2 N Wall -North retention tank lIr2 N Wall -North retention tank 1n2 N Wall -North retention tank hm2 S Wall -North retention tank lIr2 S Wall -North retention tank lm2 S Wall -North retention tank ln2 S Wall -North retention tank lm2 E Wall -North retention tank Im2 E Wall -North retention tank Im2 E Wall -North retention tank 147 0 140 4 018 08/18/06 AA Ext S Wall 018 08/18/06 AA Eat S Wall 018 08/18/06 AA Ext E Wall 018 08/18/06 AA Ext E Wall 018 08/18/06 AA Ext E Wall 018 08/18/06 AA Ext E Wall 019 08/18/06 AA Ext S Wall 019 08/18/06 AA Ext S Wall 019 08/18/06 AA Ext S Wall 019 08/18/06 AA Ext S Wall 019 08/18/06 AA Ext S Wall 019 08/18/06 AA Ext S Wall B 0 B 1 A 0 A I ND ND 128 0 120 0 1 ND ND 145 150 T24 A45 0 0-6-6-120 140 160 140 0 1 0 B 1 0 1 9 0 1 28 1 B 1 B 1 B 1 B 1 A 0 A 0 4 0 32 0 Penetration

1. 1 S Wall -North retention tank Penetration

1. 2 S Wall -North retention tank S23 _ Penetratio 0 0 1 1 1 2 1 22 2j I Penetration

1. 4 S Wall -North retention tank Penetration

1. 5 S Wall -North retention tank Penetration

1. 6 5 Wall -North retention tank lm2 Floor -North Retention tank 020 08/19/06 AA Ext 020 08/19/06 AA Ext 020 08/19/06 A6 Ext 020 08/19/06 AA Ext Floor Floor A I1 8 ND ND ND 0 1 0 I o2 Floor -North Retention tari ND 231 0 0 lm2 Floor -North Retention tarl 1 187 1 0 110 0 16 0 lm2 Floor -North Retention tan)D 59 0 120 0 0 lm2 Ceiling -North retention lank AA I Ext Ceilina D 40 [ 0 120 1.0 0 1 .lm2 Ceiling -North retention tank ENERCON Services, in,.

University of Washington More Hall Annex Final Status Survey Results -Unit 3-2 (Retention tankand valve gallery)FSS # Date Class Floor Surface X Y Alpha Alpha Alpha Beta Beta Scan Beta Scan Alpha Beta Net pR Comments Coord. Coord. Direct Scan Min. Scan Max. Direct Mlin. Max. Wipe Wipe DPM (rpm) (cpm) DPM (cpm) (cpm) DPM DPM 020 08/19/06 AA Ext Ceiling B 0 3 ND ND 0 0 120 0 6 lm2 Ceiling -North reterlion tank 020 08/19/06 AA Ext Ceiling B 1 0 ND ND 39 0 120 0 57 lin2 Ceiling -North retention tank 077 09/12/06 AA Ext Floor A 0 2 0 0 234 150 240 0 0 0 Valve Gallery -Floor 077 09/12/06 AA Ext Floor B 0 6 0 0 205 160 220 0 3 0 Valve Gallery 077 09/12/06 AA Ext W Wall A 0 6 0 0 207 140 260 0 0 0 Valve Gallery -West Wall 077 09/12/06 AA Ext W Wall A 1 11 0 0 231 140 200 0 13 0 Valve Gallery 077 09/12/06 AA Ext N Wall A 0 2 0 0 212 120 180 0 0 0 Valve Gallery -North Wall 077 09/12/06 AA Ext N Wall A 1 2 0 0 42 100 140 0 0 0 Valve Gallery 077 09/12/06 AA Ext N Wall B 0 2 0 0 210 140 180 0 0 0 Valve Gallery 077 09/12/06 AA Ext N Wall B 1 6 0 0 157 120 180 0 0 0 Valve Gallery 077 09/12/06 AA Ext E Wall A 0 79 0 I 185 120 240 0 0 0 Valve Gallery -East Wall Includes Ladder 077 09/12/06 AA Ext E Wall A 1 2 0 0 172 120 180 0 18 0 Valve Gallery -Includes Ladder 077 09/12/06 AA Ext S Wall A 0 2 0 0 240 120 240 0 0 0 Valve Gallery -South Wall 077 09/12/06 AA Ext S Wall A 1 2 0 0 141 120 200 0 0 0 Valve Gallery 077 09/12/06 AA Ext S Wall B 0 20 0 0 238 140 210 0 0 0 Valve Gallery 077 09/12/06 AA Ext S Wall B 1 34 0 0 302 140 240 0 0 0 Valve Gallery 077 09/12/06 AA Ext S Wall A 0 29 0 0 253 100 240 0 13 0 Valve Gallery -Sunp 077 09/12/06 AA Ext Floor A 0 7800 0500 Valve Gallery -Gansina Scans Over Floor, 100%077 09/12/06 AA Ext Floor B 0 7850 8300 Valve Gallery -Gamma Scans Over Floor, 100%ENERCON Services, inc.

Layout of Valve Galery Located between N &S Retention Tanks SOUTH WALL Al A0 131 BO AWEST WALL Al FLOOR NORTH WALL OAO Al BOBO B13 ESW J AO F-iEAST WALL Al Pipe Penetretio PROJECT UNIVERSITY OF WASHINGTON NUCLEAR Scale: NTS REACTOR DECOMMISSIONING Drawn by: DM DRAWING VALVE GALLERY/RETENTION TANKS ' DRAWING 33 SURVEY UNIT 3-4 Enercon Services University of Washington More Hall Annex D&D, Project 10492 Attachment 39 -Excavation Soil Sample Radiochemistry Analytical Results UW-MCP-OP-13, Rev. 2 5 Mk TELEDYNE BROWN ENGINEERING, INC.A Teedyne Technrlgles Company 2508 Quality Lane Knoxville,TN.

37931-3133 Cory DeWitt Enercon 4499 Old William Penn Highway Murnysville PA 15668, Report of Analysis/Certificate of Conformance 09/29/2006 LIMS #,: L29888 Project ID#- EN005-3EREG-06 Received' 09114/2006 DeiverY Date: 09/28/2006.

P.O. #: MCILVI001 Release #: SDG #: This is to certify that Teledyne Brown Engineering

-Environmental Services located at 2508 Quality Lane, Knoxville, Tennessee, 3793 1, has analyzed, tested and documented-samples as specified in the applicable purchase order.This also certifies that requirements of applicable codes, standards and specifications have been fully met and that any quality assurance documentation which verified conformance to the purchase order is on file and may be examined upon .request.I herebycertify that the above statements are true and correct.K th Jeter Operations Manager

,MqM TELEDYNE A BROWN ENGINEERING, INC.Aleledyne Tezhno ngies.Company 25089 Quality Lane K0oxville, TN 37931-3133 Cory DeWitt Enercon 4499 Old William Penn Highway Murrysville PA 15668.LIMS'# L29888 Project ID#: EN005-3EREG-06 Received, 09/14/2006 Delivery bate:- 0912812006MCIL VIO01 SDG #: Cross Refe ence Table.Cliebt ID Labboratory ID. Station.ID(if applicable):

-wir I L29888-1I

....W2,2 L2988"8-.2 S 3 L2 9888-3 *N I L29888-4 N l [ 821 .. ... -L29888-5

__........

sW .L298886 _ _! ss]_o_ _______ ...-. L29888&9 j .........__ ...SS91 1-29888-10,_

_SS41 1,29988:41 I_____________

SS4 "L29888-l8 I ........55... .s8 j'L29888-12}

"________

ýý- ;j -Report of Analysis BWN TELEDYNE 09I!R/6 15.1 BROWN ENGINEEBING, INC..09/29/06 15:17 Tmotocirpi L29888 Enercon Cory DeWitt ENOO5-31ERtG-06 Sample ID- W1 ] Collect Start 08/29/2006 12-00 Matrix:. Soil (S)Station: Collect Stop: Volume:

Description:

Receive Date: 09/14/2006

% Moisture:

6.44 LIMS Nurmber.:

L29888-1[ Activity :Uncertainty " Run i Aliquot I Aliquot 4 Reference

! Count .1Count Count Radionoclide SOP# Cone 2 Sigmi D is # Volume Units Date Date I Time Units Flag Values BE-7 2007 4 5.12E41 pCi/g Dry ____ 397.18 1 gdry '08/29/06 12a00 t 09/20/061 1800 See 1 U iT NoT K-SI T 2007 i 6.70E+00 I 1.38E+00 I _ pCigDry 1 1 397.18 1 gdry 08/29/06 12:00 1 09/20/064.

1800 T Se&i F- I Yes.CR-51 _ _ 2007 1 < _ I 7.77E-01 1 pCi/gDry i 1 397.18 1 gdxy 408/29/0612:00 09/20/061 1800 1 See 1 U I [No 1 MN-54 2007 I < ' _ _ _ 5.68E-02 I pCi/gDry 1 1 397.18 1 gdry 1.08/29/06 12:00 1 09/20/064 1800 1 Sec I U I Noo CO-57 4 2007 F < [ 5.20E-02 pCi/gDry 1I 397.18 1 gdry 108/29/06 12:001 09/20/061 1800 T Sec r U 7[NO-T C0-58 2007 <r 6.46F_-02 pCi/gDry 397.18 4 gdry I08/29/06 12:00 1 09120/061 1800 FSec i U j No i 4 FE-59 2007 1 < 1 _ 1.63",.1 , pCj/gDry j 397.18 J gdry Fn/29106 12.900 1 0M06118 0 1 Sec I U i No -1 CO-60 2007 , < 4.74F_-2 jpCi/gfry 1 397.18 gdry 08/29/06 12:00 p 09/20/06i 1800 1 See U i No"65 [2007 I < } 1.69,,.01 f pCi/gDry ;397.18 4 gdry 08/29/06 t2:00i 09/20/06!

1800 T Sec U 1. No___9 ___ 2007 1 < ___ 1.69E01 {-0 pCi/gDry _ 397.18 [ gdry 08/29/06 12:00-i 09/20/06i 1800 1 Se I U 1 N N-2007 i < 1 6.ASE4102 1 pCi/gDry 397.18 ' gdry 108/2910612:00

! 09/20/061.

1800 [ Se I U 4 No .~tR-103 T 2007 t < I !_6_E.2E-01 2 pCilgDry 1 i 397.18 gdry 408/29/06 12:00409/20/0618001 Sec U ! _ 1 No pRU-I069=J 2007 4 < I __ _ 1.291+-,-02 4 pCilgDry i 397.18 1 gdry I 08/29/06 12:00 1 09/20/061 1800 1 Sec [ U No ZRA- T5 2007 1 < I I 6.125-02 I pCi/gDry .397.8 gdsy 408/29/0612:00 " 09/20/064 1800 1 Sdc [ U 1 1 No RU SB-124 4: 2007 _______ 4 _ _ 52911-/02 pC/gDry I I '397.18 [ gdxy 408/29/0612:00 09/20/06 1800 g See 1=9 /No 1!SB-125M 4 2007 ____< ...J _ 6.158.-021 pCi/gDry g" 39718 4 gdry 108/29/06 12:00 1 09/20/064 1800 1 Sec [ U 1 No SB-]312 [. 2007 j, I < _F 3.41-01 pCifgDry ! .... 397.18 gd0y 108/29/062100[

09/20/06!

1800 1Se U i No S-134 i 2007 < "i 65.E-02 1 pC'g-Dry .1 397.18 "'dry 108/29/06 12:00.. 09/20/061 1800 1 Sec 1 U 1 No I1R-137 1 2007 1_" < I 3.91E-01 T pCi/gDry II 397.18 1 gdry f08/29/06 12:00 1 09/20/061 1800 See I U I I No I$CS-t4 I i 2007 _ _< i ._.....__

5.6151-02 1 pCi/gDry I 3 97.18. 1 gdry 108/29/06 12:00 1 09/20/06i 1800 I Sec I U I No I I SB-124 2007 1 <_.... _ 2.59E1-01 2 pCi/gDry 3 297.18i 1 gdry 108/29/06.12:00 j 09/20/06!

1800 1 Sec U I No:iESt-125 2007 1 < _ 1.658-01 pCi/g Dry { 397.18 1 gdry 108/29/06 12:00 T 09/20/061 1800 1 Sec I U 1 No '1LA-143 2007 ! < 43.41E-01 PCi/gDty 1 1 397.18 1 gdry 108/29/06 1200 ! 09/20/061 1800 1 Sec U 4 .No I -EB-1402 2007 5 1.68E--01 pCi/gDry 1 .397.18 4 gdry 108,29/0612:00 1 09/20/064 1800 4 Scc : U 1 1 No I ,EU-14 2007 I < _ 1.5421-0!

I pCi/gDry 1 1 397.18 1 gdry 108/29/061200 1 09/20/061 1800 1 Sec U I I No I la5E-02 -07 I____ ____ .0.i pCi/g Dry 4f 397.18 g gdry .308/2910612:00 4 09/20/064 1800 1 Sec iU 1 4No4 ICE- ___144 2007 1 _____ I____ 3.52E-01 1: pCi/g Dry I~ 397.18 g gdry 108/29/06 1200o 09/20/6,-

1800 ISec U1 1 1.No 4'RA-226 i 2007 < 4 1-39L+00 pCi/gDry I" 397.18 4 gdsy! 08/29/0612:00 109/20/064 1800 i Sen U No_ _.*_ _

• _ _ _ _ _ ......... I _ _ _ _ ....._ _:_ ....._ _ _ _ _ _,__ _ _ .L [ .. __. .......L....Flag Values U -Compound/Anadyte not deteted or lessthan 3 sigmia No Peak not identified in garmmaspwtkum

-Activity coneentration eteeds MDC and 3 signa; peak identified(gamma only) Yes =Peak identified in gamnna spectrum U" -. Com.pound/Analyt1enot detfcte4 Peak not identified, but forced activity concentration exceeds MDC and 3 sigma ... Results arexreportednan aos reeived basis High -Activity concentration nxoesds customer reporting value unless otherwise noted Spec -MDC.exceds csismner technical specficati-n L -MDC -MiniLonw Dct/stable Concentration H, -High recovery Page 1 of 22.Bolded text indicates reportable value.

Report of Analysis.09/29106 15:17 L29888 Enercon EN 005-3 EREG-06 ABRO WN ýENGINEERING, INC.A Tedyn.Teehn~ogimo Ceepary Cory DeWitt SampleiD::

WI I Collect Start; 08/29/2006 12:00 Matric Soil (S)Station: ColleatrStop:

Volume:

Description:

Receive Date: 091142006

% Moisture:

6.44 LIMS.Number L29888-1 3Activity Uncertainty 1Run Aliquot IAliquot I Reference Count I Count .1Count Radionuclide SOP# Conc 2 Sigma MfDC Units Volume flnits Date .Date Time 'Units Flag Values TH-228 2007 2.05F-01 8.54E-02 pCi/p Dry 397.18 g dry 08/29106 12:00 09/20/06 1800 Sec + Yes ITH-232 I 2007 J < < 3.55E-01 I pCilgDry I 1 397.18 I gdry 08P/29/0612:00

.1 09/20/061 1800 I Sed U I I No I Flag Values U = ComporndiAsalyte not detected or less than 3 sigma+ = Activity concentration excceds MDC and 3 sigma; peak onsy)Uti -Compound/Analyte not detected.

Peak not idonti flied, bt forted activity concentratign excceds MDC and 3 sigma ffigb -Activity concentralin er-ceeds customer reparlingvnlue Spec = MDC exceeds customc technical specification L -Low recovery H I-TighrecveIy Page 2 of 22 Bolded text indicates reportable value.No = Peaknot identified in gamma speitrum Yes = Peak- identfijed in gamma spectrum Resulits are r-ported on an as received basis auless otlervwise noted MDC -Minimum Delectable Concentration Report of Analysis 09/29/06 15:17 L29888 Enercon ENOO5-3EREG-06 BROWN ENGINEERING, INC.AmTelady, T.hn.l&gin Cma.ry Cory DeWitt Sample ID: W2 2 Collect Start 08/29/2006 12:00 Matrix: Soil (S)Station: Collect Stop: Volume:

Description:

Receive Date: 09/14/2006

% Moisture:

7.59[ LIMS Number= L29888-2 Activity Ucertainty Run Aliquot -Aliquot Reference ICount .1Count ICount Radionuclide SOP# Conc 2 Sigma MDC Units Volume Units Date 1 Date rTime Units lagValue 13E-7 .... 2007 < ....i 1.00r-00O I pCi/g Dry "] 386.99 1 gdry "108/29/D6 12:001[ 09120/061 1800 1 "See U 1. r 1 K-40 !2007 1 .7.76E+001 1.67E+-007 1 pCi/g~r 5i .. -i 86.99 I g dr'y 08/29/06 12:00 J 09n201061 t800. ~~ Ys tCR'51 ...I 2071 .1.HE-H00 I pCi/g Dry .1" 386.99 1 g dry 108/29/06 12:00 1 09/20/061 1800 1 see 1 U I I No I_.MN _54. _ 2007 _ < 9.1 9.O5E-02 I pCi/g Dry 1 386.99 1 gdry 108/29/06 12:00 1 09/20/061 1800 1 Set i U I I No 1 CO-57 2007 < 9.4302 .pCi/g Dry 1. j 386.9 g dry 108/29/061 2:00 1 09/20/061 1800 Sec I I Yeao-1-CO-58 1 2007 I < I _ _ 1.21_ E01 pCi/gDry 1i 386.99T gdry i08/29/06 12:00 1 09/20/061 1800 ' Sec ! U I I No FE-54. i2007 1 <. 2 ..." Iý 2.15.-1 pCi/g Dry I 386.99 g dry t 08/29/0612:00 1 09/20/06i 1800 .See , U J i No I IC0-5N 2007 ._ < 8 8.68E-021 pCi/g Dry i 386.99 t g dy 08/29/06 12:00 i 09/20/06i 1800 Sec IU u I No _5, 2007 < 1.61E-01 f pCi/gDry [ 386.99 gdry 08/29/06 12:00 1 09/20/06; 1800 S S ! U .. No-- 2007 i < _ 9.32,E-0221 pCi/g Dry -386.99 g dy 08/29/0612:00 1 09/20/06]

1800 1 Sec Uo C 2007 T < , 1.8F,0- pCi/g Dry I i 386.99 I2g dry 08129/061:00 19M21061 1800 ! See I U No_ZR'95 I 2007 .< I 1.98E-01 1 pCig Dry i1 386-99: 1 g dry 108/29/06 12:00 1 09/20/061 1800 Sec U 1 No MO-99 1 2007 1 < L99E+02. pCi/gDry 1 386.99 J. gdry 108/29/0612:00 0 09/20/061 1800 See U I Nol j 2007R [ < 9_ _ 9.1IE-0l & pCi/gpry 1 1 386.99 1t gdry 101/29/06 12:00 :1 09/20/061 1800 S See I U I No I 1RU__I06 [_ 2007 i < I 8 8.97E-01.

pCi/gDry 1 T 386.99 1 gdry 108/29/0612:00 1 09/20/061 1800 1 Se9c U 1 " '1 No'MAG-I1OM 2007 < L8.95E+02 F pCi/gDry I i 386.99 I gdry 108/29/0612:00 1 09/20/061 1800 1 S=c i U 1 1 No I USB-124- 2007 < I ".01E-0 pCi/gDry 1 ? .1 386.99 1 d 08/29/0612:00 f 09/20/061 1800 1 See 1 U " 1 No I i R 2_E-01 .pCi/g Dry 3. 9 g dry 1 08/29/06 12:00 .09/20/061 1800 ecN IS-125 2007 ! < ' 8.55E-01 pCi/gDry 1 386.99 " gdry 108/29/0612:00 09/20/06 1800 Se U I No I 1B-131 2007 _ < I 5.40E,-01 i pCi/g Dry i .1 386.99 i gdry 108/29/06 12:00 09/20/06i 1800 I See ! U i No J C-134 2007 T <.58_2 pi/g Dry l...... 386.99. 1 g dr~ d 0&29/0612:00 f 09/20/1061 1800 See .U No 1C-1:37- 2007 < I I 7.19E-02 T' pCi/gDry 1 386.99 } 1 08/29/06:12:00

]" 09/20/061 1800 1 Sec U I J No j t CS- 134 2007 < _ .... .. 58E,02 I pCi/g Dry I ' 386.99 I gdry -08/29/0612:00 109/20/06 1800 Sec U No i i[CS-.:74 1 !..2007 T < I ....:_ 7.19E-02 I pCilg Dry I 386.99 gdry i 08/29/0612:001 09/20/061 1800 [ Sec U I No 1: SA-144 2007 < -_ j1.23F,,,4 1 pCi/gDry I 386.99 gdry -108/29/0612:00 T 09/20/061 1800 1 See U T 1I4NOT 1 IJCE4 200 I____ _____126E.1Ip/gr F 369 gdy 0890620T92/61 1800-, F§Th r FI- TN-oT IE-Id L4 2007.I 1.2911+0 1 pCi/g Dry 1I 1 38&.99 J.,dry 108/29/06 12:00 1 09/20/061 180ISc 1Ur Io EU-152I 2007 1 i " 2.12E-01 1: pCi/g Dry F I 386.99 I gdry .08/29/0612:00

1. 09/20/061 1800 I Sec I U I I No '.EU-154 ' 2007 1 < 2.05"E-1 [ pCi/g Dry 3869 gdry 108/29/06 12:00 09/20/061 1800 i See I U N i o 1RA-226 I 2007 < I 271E+D0o I pCilgDry F " 386.99 1 gdry 08/29/06 12:00 1 09/201061 1800 j See i U I No iTH-228 2007 1 < 1.62E-01 I pCi/gDry i 386.99 I gdry 108/29/0612:00 09/20/061 1800 F See I U.1 Yes i_ _ _ _ _ _ _ _ _ ...... ..I I _ _._ _ _ _ _ .... ._ _._ _ ,- _ _ _ _ .. _* _ .Flag Valuae U = CompoundlAnalytesot detdctid or less than 3 sigma Activity concentration exceeds MDC and 3.sigma; peak idenitiled(ganmua only)U* Compound/Analyte nol detected.

Peak.not identified, bat forced activity concmnxartion M.DC and 3 sigma High = Activity concetraation exceeds customer reporting value Spec = MDC exceeds customer technical apecificat!on L = Low recovery H = High recovery Page .oF 22 Bolded text indicates reportable valIue.No. = Peakhot idenitiied in gamma spectrum Yes =Pcakidenlified in gamma

• Resulis am rcporled on fin awt received basis unless otherwis noted MDC -Minimum Detectable Concentration Report of Analysis 09/29106 15:17 L29888 Enercon EN005-3EREG-06

.,,- .TELEDYNE BROWN ENGINEERING, INC.A T.y.!enhnaoaiaa Canpqn Cory DeWitt Sample ID: W2 2 Collect Start: 08/29/2006 12:00 Matrix: Sodl (S)Station: Collect Stop: Volutme.Description:

Receive Date: 0911412006

% Moisture:

7-59 LIMS lumber. L29888-2 i Activity jUncertainty, Run Aliquot Aliquot Reference I Count :Count Count Radionuclide SOP# Cone 1 2Sigma IDC Units. volume Units te I Time 1 Units FlagValues ,ado en .Sm n. ne TH]-232 2007 < 5-.9E-01 pCilg Dry 386.99 g dry 08/29/0612:00 09120/06 1800 Sec U _ No Flag Values U = Compound/Analyte not detected or less than 3 sigma+ = Activity concentration exceeds MDC and 3 sigma; peak idcntified(garimem only)U. = Compound/Analyte not detected.

Peak n0ot identified, but forced activity concentration exceeds MDC and 3 sigma High = Activity-concentration exceeds customer reporting value Spec, zf- MDC exceeds customer technical sptcification L LoW recovery H = High rcTovety Pe 4 of 22 Bolded .text indicates reportable value.No -Peak not identified in gamma spectrum Yes -Peak identified in gamma spectrumrn

• • +* Results ore reported oe an asreceived basis Rnlcsýsotherwisc noted MDC -Minimum Detectable Concentration Report of Analysis ~al R p1r BROWN ENGINEERING, INC.09/29/06 15:17 A T -7.0 Cm pa .L29889 Enercon Cory.DeWitt EN005-3EREG-06 Sample 1D: S3 Collect Start: 08/2/006 12:00 Matrix: Soil (S)Station: CollectStop,:

Volume-.Description:

Receive Date: 09/1412006

% Moisture:

6.84 LIMS Number: L29888-3S Activity Unetit u Aliquot Reference Count Count Cun. t SOP#ue d so Cone Unetinty MDC ui, I ..°.u'Radonulid SOP#_ CIn 2 im. nt i# Vl Uis Dt Datel Timse Unit PingValues I BE-7 2007 I < _ " 1 9.39<E-01 1 pCi/gDry I I 401.64 l gdry .08/28/0612:00D1 09/206i61 1800 1 Sec I U.) I No1{.1 2007 I 7.64E+00 I .795+0) I I pCi/g Dry 1 40164 gdry 08/28/06 12:0 J 09/20/061 1800 1 Sec i1 Yes I C5-S 1 2007 c < _ i .nE+oo T pCi'gDry rr 401.64, 1 gdr-y 08/20612:00 1 09/2/o061 1800 Io Se I u No I IMN54 2007 __< .... _ .1.145-01 T pCigDry 1T 401.64 Cgry 108/28/06 12:00 1 09/20/061 1800 F Sec U I I No l ICD-57 2007 j! < _ _ 9.40E-02 T pCi/gDry J 401.64 1 gddry. 8/2/06 12:001 09/20/061 1800 1 See I U: 1 j No J CD-58 I 2007 I. < _ _ I.2z.-o] T pCi/g Dry. 1 j 401.64 1 gdry 08/28/0612:00 I.09/20/061 100 j Sec I U : I No j FE_59 ......__2_07 _....< I " ___7.-__ pCi/g Dry J 401.64 .gdry 08/2/06 12:00 1 09/20106, 1800 1 Sec 1 U 1ý INo 1;CO-60 I 2007 .< I 1 1.08-01 pCt/gDry j 401.64 J gdry 08/28/06 12:00 j 09/20/06" 18E0 1 Sec IU I No i _" 2007 I < _ _ _ 2.34--01 :1 pCi/gDry I I 401.64 I gdry 108/28/0612+:00 1 09/20/061 18001:..1:

Sec 1 U I No I-94 1 2007 1 < .8.29-02 V: pCi/gDry 401.64 gdry 108/29/0612:00 1 09120/01 1800 T See I I I Nio M.-95 1: 2007 1 < _ I 1.43101 1 pCi/gDry f 1 40164 .F gdry 08/281/0612:00 709/201061 1800 1 See I U I_ I No I ZR-95 1 2007 I < Ti .785-Ol I pCi/gDry 1 401.64 I gdy 108/28/0612:00 1 09/20/061 1800 I Sec FiiI 1 .tNo 17 MO91 2007 1 < 12.0+02 I pCrg Dry 1 40164 F gdry 108/28/0612:00 09/20/06i 100 T8e i U, I No]RU-103 i 2007 ! < _ _ 1.38E-01 I pCi/gDry 1 40164 1 gdry I08/2/0612:001 09/20/061 1800 .Se F I 1 .-No J IRU-106 2007 1: < 7.015-01 I pC1/gDry 401.64 gdry 08/28/06 12:00 1 09/20/061 1800 See U : I No .1 IAG-I.1OM 2007 7 !_ _ 9.55E-,0'2 1 p~i/gI i 401.64. g dry j108128106 12:00i 09/20/06N 1800 1 See 1U I No 0i.SB-124 2007 < [ 1 9.54M-02 1 pCi/gDry 1 401.64- g dry j0&28/06 12:00 1 09/20/061 1800- .1 Sec 06 ... No 1 i SB-125 2007 i < 1 1 2.32E-01 1 pCi/g.Dry 1 1 401.64 F g dry 08/28/0612:00 1 09/20/061 1800 ) Sec U 1 No 1 j]-131 T 2007 <: !. _ 6.68E-01 pCi/gDry 1 401.64 1 gdiy 108/28/0612:00.

1 09/20/06i 1800 1 See I U F No' 1 1 CS-134 2007 1 < I_ I 7.49E-02 I pCi/gDry 1 I 401.64: 1 g dry 108/28/06.12:00 1 09/201061 1800 I Sec 1 U I No..ICS-137 2007 J < _____ 1.07E.-01 I pCi/gDry 1 1 401.64 1 g:dry .08/28/0612:00

[ 09/20/061 1800 1 See U I Nor.BA-140 " -2007 .. < 8.67E-01 1 pCi/gDry I ' 401L64 f gdry 08/28/0612:00 1 09/20/061 1800 Se -ti I No __-LA-140 i. 2007 ;1 < 1 ! 4.27E-01 1 pCi/gDry I 401.64 1 gdry 08/28/06 12:00 1 092001061 1800 Sep U I No <jCE-1 41 f 2007 F < _ i 2.41E-01 : pCi/gDry 11 401.64 ! gdry I 0828/0612:00 1 09/20/06 1800 Sec l U F--- " I No I ICE-144 1 2007 .< i 7.43E-01 I pCi/gDry 1 401.64 f gdry 108/28/0612:00'F 09/20/06!

1800 ! See I: UI No i iEU-152 F 2007 1 _ _ _ _ 2.25E-01 1 pCi/gDry I I 401.64 1 gdry 108/28/0612,00 F 09/20/06f 180 Sec !U I No EU3154 F 2007 F < I .... 1.94E-01 i pCi/gDry 1 401.64 1 g dry 108/28/0612.M00 09/20/061 1800 See i U : No lRA-226. ..2007 < I .2.46E÷00 I pCi/g Dry 1 I 401.64 1 g dry 108/8/06 12:00 109/201061, 1800. Sec I U I No___________ , L ____i ._________".

____ L 1. , '_._'_' A 1 U = Compound/Analyte not detected or less than 3 sigma No =Peak not identified in gamma spectrum+ -Activity concentration exeeds MDCand 3 sigma; peakidcntificd(gamma only) Yes m Pek identified in ganmra spectrum.U. CompoandlAnalytc not.detected.

Pe4a not identified, but forced activity concenlration exceeds MDC and 3 sigma ** Results are reported on an as Teceived basis, Hfigh ActiVity concentration exceeds customer reporting value unless otherwise eoted Spe- = MDC exceeds custor 'ehnical spceification L = Low recoveryPa 5of2 L = Low 3. MDC -Minimutm Detectable Conc,/illtion Boded text High ndicovtery reo:baue Bohlded text indicates reportable valie.

Report of Analysis 09129106 15:17 L29888 Enercon ENO5-3EPEG-06 STELEDYNE BROWN ENGINEERING, INC, ATatutim, T.&dai..Cnpo Cory DeWitt Sample ID: S3 Coilecd Start 08/128/006 12:00 Matrix; Soil (S)Station: Coilet Stop: Volume:

Description:

Receive Date: 09/14/2006.

% Moisture:

6.84 L/MS Number: L29888-3 Activity 4Uncertainty Run Aliquot Aliquot I Reference Count 1Countý Count Radionuclide SOP# I COne 2 Sigma MDC Units I Volume Units Date Date T Time Units Flag Values I .. Ie TH-228 2007 < 1.73E- pCi/gDry 401.64 g dry 08/28/06 12:00 09/20/06 1800 Sec U Yes TTH-232 -< 1 ! 6.30E-01 I pCi/gDry D ; 401.64 1 gdry 08/28/06 12:00 1 09/20/061 1800 1 Sec U 1 Yes I Sample ID: N I Collect Start: 08/28/2006 12:00 Matrix: Soil (S)Station: Collect Stop: Volume.Descriptioir Receive Date: 09/14/2006

% Moisture: LIMS Number- 1_29888-4 id cl*de Activity Uncertainty

' r. Run j Aliquot Aliquot: Reference Count. Count Count I Cone .! " " MDC Unitst # iDate j Date Time Units Fla Values TLE 4s < I NA 1 A I I .l IUI I Flag Values U -Compound/Analyte not detected or less than 3 sigma+ -. Activity concentration exeends MDC and 3 sigma; peak identifiLed(gammna oniy)L" = CompoundlAnalyte not detected.

Peak not identified, liut forced activity concentration exceeds MDC and 3 sigma 1-ig -Activity concentration exceeds custonme reporting value Spec MD i=exceeds customer technical spicification L L.w'ecovery HI Higtrecovery Page 6 of 22 Bold ed teitindicates reportable value, No = Peak ,notidentified in gamma spectrum Yes =Peak identified in gamma spectrum** Resuliý eortedr onan as received basis unless otherwise noted MDC -Minimum Detectable Concentration Report of Analysis 09/29/06 15:17 L29888 Enercon FNfOrl5-3EREG-o6 VR1 BROWN ENGINEERINB, INC.Cory DeWitt Sample ID; N 2 Coflect-Slart:

08=282006 12:00 Matrix:: Soil (S)Station: Collect Stop: Volume:

Description:

Receive Date: 09/A412006

% Moisture:;

5.52 LIMS Number L29888-5 I Activity Uncertainty Run Aliqnot. Aliquot IReferene Count Count Count Radionuclide SOP#f Cone 1 2 Sigma MDC i it ] Volume jtiUnits Date Date Time Un'ti Flag Values 1BE-7 ".2007 .1 < l 8.98&-01 1 pCi/gDry 1 1 382.24 1 gdry 1 08/206 12:00 -09/20/061 1800 Sec I U I I No I i K-40 1 2007 8.12E1+001 1.83£+00 i. 1 pCi/gDry 1 382.24 1 gdry 108/28106 12:00 1 09/201061 1800 1 Sec.1+ 1 Yes } I.I ,CR- 51 2007 .1 cj 1.25E+05 i pCi/gDry 1 1 382.24 1 gdry 108/28/06 12:00 i 09/201061 1800 j Sec j U i I No 1 1 IMN-54 2007 F < 01.07E--01 pCi/gDry 1 38224 i g dry 08/28/0612:00 1 09/20/06:

1800 See U __ No -CO-57 2 2007 , 9.12E&02 pCi/gD,-ry 1 392.24 i g dry 08/28/06 12:00 1 09120/061 1800 l S ec, UI NoI CO-S8 2007 j "< ! _ 1.32E<01 pCi/g~ry 1 1 38224 1 gdry F08/28/06 12:00ý j 09/20106 1800 1 Sea I U 1 1 No 1.FE-59 1 2007 .... < I _ ' 1.86E-0' 0 pCiOg Dry I 382.24 I gdry 08128/06 12:00 1 09/20/061 1800 :1 Sec 1 U i " No I ICO-60 1 2007 _ < _ _ _ 9.49E-02 I pCbgDry 11 382.24I igdry o0/28/0612'00 1 09/20/061 1800 1 Sec FU 1 F No U O 2007 I < 1 _ _ 2.285_01 1. pCi/tg~ry 1 ] 382.24 1 gdry F0828/0612:00 09120/06j.

1800 1 Sec J 1. No J 1N'4. ~2007 1 < I I 9.292-02l F. pCi/gry 1 382.24 1 g dry I0180 120 F 092/6 10 .e ll IN 94 200 I I____ 9.92E-0 J: pCi/gDry 'I I 382.24 1g dry 108129/06 12:00 1 09M2/061 1800 1 Sec I U I No I 7Z0R-95 1 2007 < i 1 1.48E-01 1 pCi/gDry 1 .382.24 1 gdry 0I8/28/06 12:00 F 09/20/061 1800 1 Sec I U 1 1 No I IMZ-99 2007 < I 1.48E-+02 pCi/gDry 11 38224 gdry 08/28/06 12:00 09120/061.

1800 1 Sec I U 4 1 No I RU-103 2007. < I 1 3.08F.01 J pCi/g Dry 1 1 382.24 .gdry 108/28/06 12-00 1 09120/06; 1800 1. Sec JU 1. .t1N I I RU-106 2007 I < i 1 691F--01 j pCi/gDry I i 382.24 ik dry 08/28/06.12:00 j 09/20/061 1800 Sec U No i AG-Il0M 2007 < *. 8.1IF-02 F pCi/g1ry i I 382724 .1 g dry 108/28/06 12:00 F 0 9/2 0/0 6; 1800 1 See U 1 No. Ff iSB-t24 2007 1 < 1 1 1.05&-01 l pCi/gDry xi 382.24 gdry I08/28/06 12:00 i 09/20/06i 1800 1 Sec FW _ I No e1 FSB-125 1. 2007 1 < I 2.59X-01 ( pCi/gory i1 38224 gdry 108/28/06 12:00 1.09120/061 1800 1 Sec I ___ N / o 1]1-13 2007 T < F [ 6.84E-01 1 pCi/goy i 382.24 rdry 1 08/28/0612:00 1 09/20/061 1800 1 Sec i.U I N"'.CS 134 I 2007 T < :i _I 8.63E-02 pCi/gDry i. 38224 F gduy 108/2870612:00

09/20/o61 1800 1 Ser U I No 1 CS137 2007 j < _ i1 1.06"-0! 1 pCi/gDry 1 .382.24 1 gdry: 108/2810612:00 P09/20/06j 1800 1 Sec T.U i No I iA BA140 ..... [2007 1[ "___ < ______ .I.II*+00 I pCi/g~ry 1 J 362.24 I .gryD [08/"28/06 12:00. 09/.20/06l 1800 iSec U I ____oI No TLA- 140 .E02007 i "_<__. .22-01 T pCi/g.Dry 1 382.24 gdry 08/28/06 12:00 ! 09/20/061 1800 FSecTUj No F CE-t41 ,2007 1 < .2.57F-1 1 pCi/gDry ] .382;24 .g1ry 08/28/06 12:00 < 09/20/061 1800 1 Sec U i. I No 2CE-2144 2007 I 6.8701 I pCi/gDry i 1 382.24 F g dry 09/20/061 1800DI Sec I U I INo EU-152. 2007 1 < _ 1 2.79E-01 I pCi/gDry F. 382.24 1 gdry 08/2810612:00

.09/20/06" 1800 Sec U No I CU-154 2007 i < 1 i 1.897-01 1 pCi/g Dry I I 3g2.24 I gdry 108-28/0612:001 09/20/061 1800 1 Sec I U I iNo i RA-226 1 2007 1 < 1 _ 21845+00 1. pCi/gDry .. " 382.241 j r.!08/2810612.00 1 09/20/061 1800 6 Se I IU" F No I-lag Values- , .;a.'5 U. Compotmd/Anslyte rot detectedorless than 3 sigma+ Activity concentration exeeids MDC and 3 sigmna ;peak iddrltified(garnrna only)U.* .Compouand/Anlyte not detected.

Peak.oot identifierS, but forced activity concentration exceeds MDC anu 3 sigma High z Activity concentration exceeds customer reporting value Spec MDC exceeds.custorner technical specification L ow recovery Page 7 of 22 oH ttighdecovere Bolded text indicates reportable value.YeS = Peik idetifed he gamria spectrum-Results am reportedon an as recived.basis unless otherwise noted MDC-- Minimum Detctbhe Concentration Report of Analysis 09/29/06 15:17 L29888 Enercon ENOO5-3EREcG-06 I BROWN ENGINEERING, INC.A Teledy.e Ts:chinimogir Cimpeny CoTyDeWiStt Sample ID: N 2 Collect Start 08/28/2006 12:00 Matrix: Soil (5)Station: Collect Stop: Volume:

Description:

Receive Date: 09114/2006:

% Moisture:

5.52 LIMS Number: L29888-5-.Activity Uner-tainty Run Aliquot Aliquot Reference j Count Count Count Radi nuclide SOi Voum U~~t Inetit U ISOP Cn 2USigna MDC Units ii nits Date Date Time Units Flag Values T14-228 2007 4.79E-01 2.11E-0I pCi/gDry 382.24 g dry 08/28/06 12-00 09/20/06 1800 Sec + Yes TH-232 2007 I 3.40E-01 L,73E-01 1pCi/gDry 382.24 1 gdry t08/28/06 12:00 1 09/20/061 1800 i Sec + i Yes j Flag Values.U = Compoand/Analyte not detectedor less than 3 sigma+ = Activity concentration exceeds MDC and 3 sigma~peak4identified, gamma only)U!, = Compound/Analytc not detected.

Peak not identified, but.forced activity concentration exceeds MDC and 3 sigma.High = Activity concentration exceeds customer reporting value;Sped = MDC exceeds customer technical spocificatlon L = Low recovery Page 8, of 22 Bi t 1igi recoverty Boided text indicates reportable value.No =,P eak not identified in gamma spectnru Yes = Pea& identified in gamma spectrum:****Results are reported on an as received basis unless otherwise naoted MDC -Minimrnum.Dtectable Concentration

-.2 Report of Analysis TELEOYIE 0929/06 15:1 BROWN ENGINEERING, INC.A Tdiloynteu=ai6go

i. ýL29888 Enercon Cory DeWitt EN005-3EREG-06 Sample ID: WI-S Collect 08/29/2006 12:00 Matrix: Soil (S)Station: Collect Stop: Volume.Description:

Receive Date: 09Z14/2006

% Moisture.

4.78 LIMS.Number L29888-6 Raincie-Activity iUncertainty iRun *Aliquiot Alqo Reference Con Count Count R SOP# Cone 2 Sigma MDC units Volume Units Date Date Imoe Units Flag Values BE-7 2007 1 < " I _ 7.75E-0, 1 pCi/gDry I "464.97 i gdry 08/29/0612:00 09/21/06[

1800 { See U I IND 4.K-40 1 2007 I 710E÷00 1.45E+00 .pCigDry 464.97 I g dry 1 08/29/06 12:00 1 09/21/06!

1 80a I See + I IYesa I ICR-53 I 2007 1 7;20E+00 I_1.45_0 1.E0- I pCi/gDry ! 464.97 gdry 08/29/06t2:00 09/21/061 1800 1 Sec -U- I Nn I MN-54 1 2007 1 < i I 7.E-02 E pCi/g Dry T 464.97 1 g dry 08/29/0612:00 1 09/21/061 1800 1 See U I. No I CO751 2007 _ < _, __ 7.67E-02 pCi/gDry i 464.97 gdry 108/29/0612:00 i 09061 1800- See U No I CO'58 2007 < _ _" " 9.95E-02 I pCi/g.Dry

i. j 464.97 I gdry F08/29/06 12:00 1:09/211061 1800 i See.'"U 1 No I IFE-59 .i 2007 < .1.85&0-l I pCi/gDry I I 464.97 1 gdry j08/29/06 12:00 I .09/21/061 1800 See IU :_ 1 No I -ICO-60 I 2007 1 <: I I 5.92.-02 1 pCi/gDry 1 I 1 464.97 1 .gdry 108/2910612:00 1 09/21/061 1800 1 Sc i .j I No II T 2007 t < .1.62&-01 1 pCi/g Dry i 1 464.97 1 g dry: 08/29/0612:00 1 09/21/061 1800 See I U I I No 1: 42007 < 5.81I-02 pCi/g Dry Ti 464.97 d 1 08)29/06 12:00 09/2)/061 1.800 1See I U I I No 95 I 2007 1 < _ 1.06"-01 pCi/gDry T 46497 1 g try [0829/06 12:00 1 09/21/061 1800 1 See 1U R No lZR-95 T 2007 < i L70E"-1 pCi/gDry 1 .464.97 1 gdry i 08/29/06 12:00 1 09/211061 1800 1 Sec I U 1. I No I'M0-991 11 2007 1 < 1.61E+02 pCi/gDry ! 464.97 ; g diy 108/29/0612:00 1 09/21/061 1800 See U 1 ' 1 No. F RU-]03 2007 < 1 9.186-02 1 pCVgDry 464.97 1 gdry 08/29/0612:00 09/21/061 1800 See I U I 1 No -1.RU-106 2007 < ._ _ 5.64&-01 pCi/g Dry 1 464.97 .gd 08/29/06 12:00 091211061 1800 I Sec 1 U 1 No 1AG-IOM I 2007 f < 6.74E-02 pCi/gDry T1 464.97 ! gdry ,i 08/29106.12-00 1 09/21/061 1800 i See U i No 'ISB-124 " 2007 ! < _ _ _I 8.08F..-02 I pCi/gDry .464.97 J g dry 08/290612:00 1 09/21/061 1800 :Se U J I No I S.-1T25 2007 1 ' < _ _ _ 1.95-0 1 pCi/gDry 1I 464.97 1 gdry 108/29/0612:00 1 09/21/061 1800 I .Sec I U 1 I No 1 1-t3. 1 2007 I 1.9.1 pCi/gDy 4.89-0 464.97 1 gdry 108/29/06 12:00 1 09/21/061 1800 1 See I1 I I NU -ýCS-134 T 2007 < ' 6.82<-42 1 pJ4i/gD .464.97 1 g dry 08/29/06 12:00 I 09/21/061:

1800 1 See I ' No ,CS?137 _ 2007 i < 1 F 7.96F-02.

I pCi/gDr0 1 464.97 j gdry j08/29/0612:00 1 09/211061 1800 I Se1 I U I i No I 1 BA-140 " .... 2007' I _ .7.82.-01 1 pCi/gDry 1 T 464.97 1 g dry 08/29/06 12:00 F 09/21/06 1800 See Ur I No ILA-140 .... 2007 j < 1 3.64E-01 J1 pCi/gDry 464.97 gdry i 08/29/0612:00 1.091i/06' 1800.1 See .U No i CE-141 2007 J < 1 " 2.09E-01 pCi/g Dry 464.97 g dry i0/29/06 12:00.] 09/21/06j 1800 See !,. I INo CE-144 1: 2007 j <_ _ 6.38E-01.

I pCi/g Dry -464.97 g dry 08/29/0612:00 1 09/21/061 1800 See .U I No t* EU-152ý 2007 : I 2.17E-01 i pCi/gDry I .464.97_71 gdry 108/29/06 12:00 :1 09/21/061 1800 F Sec I U __ No I EU-154 1 2007 I _ I _________

3E-01. I pci/g Dry 1. *464.97 1 g dry 108/29/0612:00 I 09/21/061 1800 0 Sec 2 U 2 No -RA-226 1 2007 1 < i 1.835+00.

F pCi/gDry 1 1 464.97 1 g dry 108/29/06 12:00 T 09/21/061 1800 Se2 Uf 1 .._ _ _...._ , _ ... ._ _ _ , _ _ _ .*. i -_ _... I I , I ...A )Flag Values U, = Comrpound/Ahalytenot detected or less than 3 sigma*No = Pek not identifie in gemiaSpectrum

+ = Activity concentration exceeds MDC and 3 sigma; peak identified(gamma only) Yes = Peak identifiedin gamma spectrum U* = Compound/Analyte nm detected.

Peak not identified, but forced activity concentration exceeds MDC and 3 sigma: c Results are reported on an us received basis High -Activity concentration exceeds customer.reporting value. unlest otherwise noled Spec = MDC exceeds customer fecuhica]

specification L i Low recovery MDC -Minimum Concentaition H -Highnicoavery Page 9 of 22 Bolded text in dicates reportable value.

Report of Analysis 09129106 l5:17 L29888 Enercon EN005-3EREG-06

~BROWNENGINEERING, HI[C.A T.ldy..TeuhngIqies toapun Cory DeWitt Sample ID: WI 5 CollectStart 08/29/2006 12:00 Matrix: Soil (S)Station: Collect Stop: Volume,

Description:

Receive Date: 09/14/2006

% Moisture:

4.78 LIMS Number: U.9898-6 j Activity -Uncertainty Run. Aliquot Aliquot Reference C ountj Count Count Radionudide SOPH Cone 2 Sigmas MDC Units # Volume Units Date Date .Time Unit, Flag ValuesýTI-228 2007 4.00E-01 1.73E-01 pCi/gDry 4-64.97 g dry 08/29/0612:00 09/21/06 1800 Sr + Yes 232I 2007 1. 4.04E-01I 1-23E-01 1 I pCi/gDry 464.97 I gdry 108/29/06 12-00 09/21/061 1800 ! Sec 4- 1 I Yes.Flag Values U = Compoond/Analytt not detected or less than 3 sigma+ Activity cont6ctration exceeds MDC and 3 sigea; peak identified(gamma only)U* = -CompoUnd/Analyte not detected.

Peak not identified, but forced activity concentration exceeds MDC and 3 sigrisa High = Activity concentration exceeds customer reporting value Spec = MDC:exceeds, customer technical specificafion Boulded text indicates reportable value.No = Peak not identified in g8anma spectrum Yes =Peak ident Mit gammaspoetrum

.*.. Results are reported on an as received basis unless otherWise noted MDC Minimuim Concentration Report of Analysis 09/29106 15:17 L29888 Enercon EN005-3ERBG-06,TELEDYNE:

BROWNENGINEERING, INC.ATe edy.reT.r.aotgtes Compary Cory DeWitt Sample ID: S 2 Collect Start 08/28/2006 12:00 Matrix: Soil (S)Station: Collect Stop: Volume:

Description:

Receive Date. 09/14/2006

% Moisture:

3.80 LIMS Number. L29888-7 Activity Uncertainty Run Aliquot Aliquot Reference Count Count Count i SOP# Cone Igma MDC , Units i Volume Units De Date Timt Units Rlag Values BE-7 2007 1 < 1 8.41F-01 pCi/gDry 1 4 414.73 1 9dry i0828/06 12:00 09121/061 100 i Sec U JiNo 1 F O 1 2007 i 8.07E+00 I 1.55E+00 I .pCi/gDry T 414.73 1: gdry F08128/06 1-00 1 09/2/060 1800 1 Sec I + I I Yes ICR-51 12007 ___ < .I 1.16E÷00 1 pCi/gDry 1 414.73 1 gdry 108/28/06 12:00 1 09/211061 1800, Scc I U i 1 No I.2007 < I " 8.60E-02 I pCi/g Dry 1 .1 414.73 I gdry 108/28/0612:00 1 09/21/061 1800 T Sec I U] I No 1 CO-57 F 2007 i < I_ _ 8.04E-02 j pCilgDry 1 ] 414.73 1 g dry 108/28106 12:00 1 09/21/06F 1800 1 Sec I U 1 No. I fCO-58 1 2007 .< 1 I 9.77E-02 1 pCi/gDry.

I 1 414.73 j gdry 108/28/06 12:00 i 09/21/061 1800 1 Sec U I .. No I i FE-59 12007 1 < I .L87E,-01 I pCi/gDry 1 1 414.73 gdry 08/28/06 12:00 1 09/211061 1800 j Sec I U I1 No 1 j(O-60 ..... o 20071T < i 6.64E-&02 JpCi/g Dry 414.73 t g dry 50/28/06 12:00 1 09/21/061 1800 : Se U, I No zN65..........

2007 I _________

i_ 1 1.51E-0 1 ipCi/gDry 1 414.73 F gdry 08/28/06 12:00 1 09/21/061:

1800 1 Sec U, i No I'13_94 2007 1 _ -I 8.21&E02 1 pCi/gD-ry i 1 414.73 -gdry 108/28/0612=00 1 09/21/061 1800 .See i U 1 1No 1 3 2007 1 < _ _ 1.04E-01 JpCigPry T 414.73 gdry to8/28/06 12-00 i9/21/06ý1 10 s ec I U 1 No I W14 -95 2007 < i 1.68E-0:1 oCitgDry F 1 414.73 1gdry 10828/06 12:00. 109/2106; 1800 1 Sec U-99 1 2007 71 F < .I 1.93E+02 I pCi/gD ry 1 414.73 1 gdry 108/28/06 12:00, 09/21/06[

1800 Se e I U 1 1 No 1 RU-103 1 2007 i < 7 1 414,73_800 1 1.24E-01 .pCi/gDry I 414.73 ] gdry, 08/28/06 12:00 1 09/21/061 1800 1 Sec No IRU-106 1 2007 i < I _ 7.86E-01 I pCi/gDry F i 414.73 F gdry 108/28/06 12:00 i 09/21/061 1800 See T .T .. I AG-IIOM 1 2007 < < I :} 5.96E-02 1 pCi/gDry .414.73 1 gdry 108/28/0612:00 1 09/21/061 1800 1 .Sec I TU _ No I SIS-124 .2007 1 < f _ 9.09E-02 I pCi/g Dry i 414.73 i gdry 108/28/06 12:00 1 09/21/061 1800 See 7 U 1: 1 No , SB-125 2007 1 < I-C 2.OOE-01 1 pCi/gDry i 414.73 g dry i08/28/06"12:00 1 09/17/061 1800 1 Sc -i U i I No 1-131 .72007 " < 4.69E-01 1 pCi/g Dry 1 r 414.73 gdry 08/28/06 12:00 09/21/061 1800 j1 Sec ; U _i -No I{CS--34 2007 __< __.......

1 -7.58E-02 J. pCi/gDry I 1 414.73 7 gdry 08/28/06.12:00 912/061 1800 I Sec I U FI No CS-137 1 2007 1 < ... ___... 6.88E-02 ý. pCi/gDry I 414.73 g dry' 1028/06 12.00 F 09/21/061 18001- Sec I U I No I BA-140; 1 2007 1 < _ I 8.74E-01 1. pCi/gDry.

T 414.73 1 gdry I08/28/06 12:00 1 09/211061 1800 1 See I U _ 1 No I LA-140 1 2007 I 1 2.95E.-01

.1 pCi/g Dry. I I 414.73 1. g.dry 108/28/06 12:00 F 09121/061 1800 ;1 Sec I U I I No I j CE-141. 1 2007 __< _ _ '_ 2.9101 1 pCi/gDry1 I 414.73 -gdry 108/28/0612:00 1 09/21/061 1800 1 Se IU Q 1 No I 1CE-144 i 2007 < 1 [ 6.11E-01 1 pCi/g Dry ,00 < ! 414.731 T .gdry 108/28/0612:00 6 09/21/061 1800 1 Sec I U No I: EU-152 2007 < 1 1 2.42E-01 pCi/g Dry j 414.73 1 g dry i08/28/0612:00 j 09/21/06 1800 Sec I U No I'EU-154 1 2007 < 1 1.68E-01 1 pCi/gDry I 414.73 1 gdy 108/28/06 12:00RF 09/21/06 ' 1800 I Sec U I 1 No 1 iRA-226 1 2007 < _ _ ? 2.03E+00 pCi/gDry 1 414.73 1 gdry 108/28/0612:001 09/21/061 1800 1 Sec i U 1 No_ _ _ _ _. ......__. _ _ _ _ _ _ _ _ ._ _ _ _ _ _Flag Valuces Tj .Compound/Analyte not dcetectcd or less than 3 sigma+ -Activity concennration exceeds MDCand 3 sigrna peak identiified(gamma only)U* = Compound/Analyte not dctctn. PPek not idmnified, but foreed activity:eoncentratinnoxceedsMDC and I sigmna High -ActiviLcy concentration excreds customer reporting value Spec = MDC exceeds customertechnical specification L -Low ecovey Page II of 22 H = High recovery Bolded text Indicates reportable value.N6 = Pe.ek not identified in gamma spectrum Yes = Peak identified in ganuna spectrun Results m'r reported on an as received basis unless otherwise noted MDC -Minimum Detectable Concentration Report of Analysis 09/29/06 15:17 L29888 Enercon EN005-3EREG-06-arT-BROWN ENGINEERING, INC.A T.1.yr. T-h..14. C-openy Cory DeWitt Sample ID: S 2 Collect Start 02O/2&O6 12:00 Matix: Soil (S)Station: Collect Stop: Volume:

Description:

Receive Date: 09/1412006

% Moisture:

3.80 LIMS Number: L29888-7 Activity Uncertainty Run Aiiqoot Aliquot Reference Count 1 Count CountI Radionuclide SOP# Cone 21 .ga MDC 1 Units # u Units , Date Date I. Time Units Flag Values TH-228 2007 2.08E-01 1.0413-0t pC1i/gDry 414.73 g dry 08/28/06 12:00 09/21/06 1800 Sec + Yes TI1-232 2007 I 3.03E-01 I I..30E-01 I I pCi/g Dry I I g dry 1 08/28106 12:00 1 09121/061 1800 1 Sec I -.. Yes Rag Values U -Componnd/AnalyLte not detected or less than 3 sigma+ -Activity concentration exceeds MDC and 3 sigma; peak identified(gamma only)U* = Compound/Ananyte not detected.

Peak not identified, but forced activity coneentrationexceeds MDC and 3 sigmai HIgh = Activity concentralion.exceeds customer reporing value Spc = MDC exceeds customcr technical specification L = Low recovery page I2 of 22 H = High recovery Bolded text indicates reportable value.No = Peak not identified in gamma spectrumti Yes -Peak identified in gamma spectrum Results am reported on an as received basis unless noted: MDC -Minimum Detectable Concentration Report of Analysis 09/29106 15:17 L29888 Enercon.TELEDYNE low BROWN ENGINEERING, INCG Canpiny Cory DeWitt ENt05-3EREG-06 Sample ID: SS1 Collect Star 08/21/2006 12:00 Matrix: Soil (S)Station: Collect Stop: Volume:

Receive Date: 09/14/2006

% Moisture:

6.59 LIMS Number-b L29888-4 Activity j Run Aliquot Aliquot Reference tI R adionuclide, So n # } C ~ e 2 i m M D C U nits V me u n ts 1),a e D t i e'; nt Cone 2 Sigma MC nt VohiaU is Dta Pate ITie~ Units Flag Values IBE-7 2007 _ <_ , _ 1.02E+00 i pCi/gDry 366.69 7 gdry 108/21/06 12:00] 09/22/061 1800 Sec 1 U [1K-40 2007 7.16E+O00 1.75E+00 1 '_ pCi/gDry I 366.69 i .gdry 08/21/0612:00.1 09/22/061 1800 ; Sec + I +Yes FCRN51 -2007 1 < 1 _ 1.565+00 1 pCi/gDry T / 366.69._!

gdry 1, R8/21/06 12-00 1 09/22/06 1800 1 Sc I [U I No 20,MN-54 2007 1 < I _ 7.53F-02 1 pCi/gDry, I ' 366.69 :1 gdry 108/21/0612:00

.1 09/22/061 1800 1,Sec UT No LCO-57: 2007 1 < I _ _ 1.02E-01 1 pCi/gDry 1i 366.69 1 gdry '08/21/06 12:00 1 09/22/06!

1800 1 Sec I U [ [ NoT CO-Sg F 2007 1 <_ __ _ 1.7_-01 < pCi/gDry.

T 1 366.69 f g dry' 08R.1/0612:00 1 09/22/061 1800 1 Sec -! U I No rnn FE-59 2007 ...[<: 1 3.25F-01 I pCi/gDry j. 1 366.69 1 gdry 108/2110612:00 1 061 1800 i Sec -W -7 U 1 -No T 1 2007! < 1. 1.231-01 1 pCi/gDry I j 366.69 ; g d1' .1 0812 1116 12:00 1 :09/22J06i 1800 I Sec k.U i I No I t-65 2007 1 < i_ ... i 2.07E-01 pCi/gDry 366.69 1 gdry, 108/21206 12.00 1 09/-2/06 1800 I See , U1. INO 2007' I 7.63E-02 pC/gD 2 1 366.69 1 gdry 108/21/06 12:00 j 09/22/061 1800 ID T U .: No7 11.9 2007 1 < i " 1.51E-01 j pCifgDry j I 366.69 gry j:08/21/06 12:00"1 09/22/06!

1800 1Sec" U 1 No I _ýZMR_95. " 2007 1 < 1 " { 2.35"-0.-

1 pCi/gDry T 1 366&69 gdry 108121/06 12-00 i 09/22/06!

1800 I Sec U OI No't________ 2007 1 < 1. _ _ 2-00E+03 1: pCi/gDry I1 366.69 I gdry .08/21/0622:00 1 09/22/06!

1806 1 1 Se1c T INn ! J iR-10 F" : 2007 1 _<, 1506E101 1. pCi/gDry TI 36669' gdry j108/21/06 1200 [ /61 1800 I Sec U I No I RI--106 1 2007 j < 1 1 8.68E-01 [ pCi/gfDry I 1 366.69 T gdry 108/21/06 12.00 i 09/22/061 1800 t Sec I UF1 No= *.I_A_-I!0M_

_ 1 2007 I < 1 I 9.74E-02 pCi/gDry :1 1 366.69 gdry 08/2t/06.t2:00 1 09/22/06!

1800 j Sec U f [ T No 1$B-124 2007 < I _ I 1.32E-01 I pCilgDPry 1, 366.69 1 gdry '08/21/06 12:00 1 09/22/06!

1800 U Sec. U V No I[$125 122007 .I <___" 2.5SE-01 pCi/g Dry 1. j 366.69 T gdr 108/21/0612:00 1'09/22/061 1800 i Sec IU " N 1-131 T 2007 .< 1.44L+00 pCi/gD T 1 366.69 I g dry .08/21/06 12:00.. 09/22/06!

1800 Sec U [No [ICS-134 T 2007 1 < i ' 1.08.-01 J pCi/gDry 366.69 1 gIdry 08/21/0612.00D.

09/22/06!

1800 Sec Ui NoD 1 iCS-137 T 2007 1 1.72E--0i I 7 76E-02 ! i pCi/gDry 1 366.69r gdry 108/21/0612:00 T 09/22/06!

1800 F Sec ! + I Yes i BA-140 i 2007 -...._..__ 2.04E+00G pCi/gDry ...366.69 1 gdry 08/21/06 12:00 1 09122/061 1800 1 Sec T U No I LA-140 1 2007 r .. O 7 < 1 _ 7.34F-01 I pCi/gflry I 366.69 1 & dry 108&21/06 12:00 1 09/22/061 1800 Bo Sec I U No I CE-141 1 2007 1 < i _ 3.S2E-01 .pCi/g Dry ! 7 366.69. 1 gdry 108/21/06 12:00 1 09/22/061..800 i See 1 U I T.No 1:!CE-144 {- 2007 F ! < .______ 8.80E-01 F pCi/gDry i [ 366.69 .gdry 108/21/06 12:00 1 09/22/06!

1800 1 See i UI I No I7 EU-132 .2007 1 < F _ 3.17E-01 F pCi/gDry .1 '366.69 I gAry 108/21/0612:00 1 09/22/06!

1800 1 Sec I U i , TNo I EU-.154 1 2007 1 1.95E-01 I pCi/g Dry, i 366.69 1 gdry 108/21/06.12:00 1 09/22061 1800 1 S... U I Nsr'RA-226 i 2007 _ _ < __ .... 2.50E+00 pCi/gOry 366.69 g dry 08/21106 12:00 09/22/06 1800, Sec Fj I No-_____ ..____ .... r '.. ______" __ :" ..... i ;Rlag Vlues U = Compound/Anrlyte not detected or less than 3 sigma+ -. Activity conceniration exceeds MDC and 3 sigma; pak id'ntified(garrimaonly)

U* = Comrpound/Anatyte not deacted. Peak not idetified, but forced astlyity concentration excee ds MDC and 3 signma High = Activity concarration exceeds customer reporting value Spec = MDC exceeds cusiomuncrichnieri specilicaion L Low recovery Page 13 of 22 H t Hightecovery Ilolded taXtindicates reportable value.No = Peak not gamma spectruom Yes -Peak identified in gamana spectrum* Results are.reported onan as received basis unless otherwise noled MDC -Minimum Detectable Conccnt-ation Report of Analysis 09/29/06:15:17 L29888 Enetcon EN005-3EREG-b6 STELMYEi]!E BROWN ENGINEERING, INC.ATeedyne 7er.hnelogiZ-cnp.y Cory DeWitt Sample ID: SSI Collect Start 08/21/2006 12:00 Matrix: Soil (S)Stado.o: Collect Stop: Volume:

Description:

Receive Dae: 09/14/2006

% Mojsture:

6.59 LIMS "Number. L29888-8 RadiuSOP#id Activity Uncertainty Run. Aliquot Aliquot Reference Count Count Count i RadS Cclideon 2 Sigma MDC Units Volume units Date Date Time FlagValues TH-228 2007 < 1.65E-01I pCi/g Dry 366.69 g dry 08/21/06 12:00 09/22/06.

1800 Sec. U Yes TH-232 1 2007 1 1 < 5.85E-01.

I pCi/g Dry J. 366.69 I gdry 108/21106 12:00 09/22t061 1800 j Sec j U J 7N I 1" Flag Values U = CompoundlAnalytc not-detvcind or less than 3 sigma+ -Activity concentration exceeds MDC and 3 sigma; peak idestified(gamma only)= Cornpound/Anilyte not detected-Peak notidentified, but forced activity concentration exceeds MDC and 3 sigma High -Activity conccenration exceeds ucMtoone=

reporting vaJue Spec -MDC exceeds customer technical specification L Low recovery H = High recovery Page 14 of 22.Bolded text indicates reportaible value;No = Peak not identified in gamma spectrum Yes = Peak identihicd in gamma spectrum*xa* Results are reported on an as received basis unless otherwise noted MDC -Mininuis Detectable Concentration Report of Analysis 09/29/06 15:17 L29888 Enercon EN005-3EREG-06 TELEDYNE'¶ BROWN ENGINEERING, INC.AT,.iot Tee eaje Cuntan Cory DeWitt Sample ID: SSIO Collect Start; 08/2,1/2006 12:00 Matrix: Soil (S)Station: Collect Stop: Volume:

Description:

Receive Date- 09/14/2006

% Moisture:

4.00 LIMS Number L29888-9 SO41Activity

[Uncertainty Ru Alquot Aliquot Reference JCout Count Coun Radionuclde

'SO Cone 2 Sigma, MDC Units Volume Units Dat Date Time Unite Flag Values I__ _ _ _I I ....BE-7 1 2007 1 < _ _ 1 _ 1 1;27400 0 pCi/gDry 1 1 434.25 ] g dry 108/21/06 12:00 1 09/2/06! -1800 1 Sec j U I [No I K-40 7 2007 1 7.61E+00 1.56E+00 i- pCi/g Dry 1 T 434.25 1 gdry T08/2110612:00

.1 0922/061 1800 1 Sec I -. yes I CR-.51 2007 1 < _ _ ! 1.36E+00 1 pCi/gDry 1ý 434.25 1 gdry 08/21/06 12:00 7 09/22/061 1800 1 Sec. U 1 1. No I MN-54 1 2007 _< ; _ 1L.08E-01 pQ~ggDry [ T 434.25 1 gdry 08/21/0612:00 09/22/061 1800 Sec.i U I I No :l CO-57 .2007 1 < i 1 8.76F-02 j pCi/gDry 1T 43425 1 gdcry 108/21/06 12:00 1 09/221061 1800T Sec .1 U i 1 No 1, CO.-58 T 2007 _ !'C<" __ 6.80E-02 ipCi/gDry J. _434-25 1 gdry 108/21/0612:00 1 09/22/061 1800 1 Sc 1 U I I No 'I fE-59 i 2007 <._____ < _ i 3.03R-01 I pCi/gDry 1 434.25 1 gdry 108/21/06 12:00 1 09/221061 1800 1 Sec -1U i I No I jCO6.-60 2007, 1 < I 7.70E-02 1 pCi/gDry 1 1 434.25 j gdry [08/21/06 12:00 1 09n22061 1800 T Sec [Ui U i No I A 94"-65 1 2007 1 < 1 I 1.57E-01 [. pCi/gDry ] [ 434.25 1 gdry 108/21/0612:00 1 09/22/061 1800 T. Se I U .No ,94 1 2007 1 < _ 8.72E-02 1ý pCi/gDry [ 43425 gdry !.08/21/06 12:00 1 09/22/061 1800: 1 Sec U I U No 1 NW -95 2007 7 T 1.08-1 7 pCi/gDr, fT 43425 gdry ![08/2110612:00 1 09/22/06!

1800 T Sec L__-_____-95

_ _ 2007. < _ _ 2.05,-01 1 pCt/g Dry i 434.25 g dry 08/21106 12:00 7 09/22/061 1800 ! Sec U i No 1 MO-99 i. 2007 1 < " 1.88E+03 pCi/gDry 1 1 434.25.i gdry 108/21/06.12:00i 09/22/061 1800 I Sec U I 1No RU-103 1 2007 I ..... < 1.38E-01 1 pCi/gDry 1 1 434.25 : g dry 08/21/06.12:00 I 09/22/061 1800. j Sec. [ U j 1 No I Fi -106 2007 1 < I_ _ (_ .8.49E,-011 pCi/gDry 434.25 i g dry 08/21/06 12:00 09/2Z'06!

1800 2 Sc i U 1 T! No -..AG-Ib0M 1 2007 I < I I 6.20E-02 1 pCi/gDry.

1 434.25 1 gdry [08/21/06 12:00 1 09/22/061 1800 1 Se t UI TNo I SB-124 1 2007 1 <. 1 _ I.1E-01 I pCi/gDry T i. 43425 I gdry 108/21/06 12:00 1 09/22061 1.800 1 Sec U 1 I No " SB-125 2007 1 < ___" 1.84E-01 1 pCi/g1Dr T 43425 1 g.dry 08/21/06 12:00 1 09/22/06!

1800 1 Sec I U. i' No 1ý 13.1 2007 l4< __,, 1.26E+0 0 pCi/gDry .1i. 434.25 gdry [08/21/06 F2:00 09=02/01 1800 1 Sac i " NoI T§-t34 i 2007 1 < .I 8.491-02 I pqtgDDy, I 434-25 .gdry I08/21106 12:00 1 09/22/06!

1800 ! Sec j U I No V CS-137 2007 ! < 1 7.48E-D2 !. pC'lgDry I 43425 1 gdry 0&/21/06 12:00 ) 09/22/06!

1800 i Sec j U 0 No 1 IBA-140. i 2007 I < 1 1.69E+00 pCi/ggDry I I 4342, £ dry [08/21/06 12:00 09/22/06!

1800 I Sec I U I No i LA-140 2007 .._____ .5.63F-01 pCi/gDr 434.25 1 gdry 108/21/0612:00 1 09/22/061 1800 Scc U I No jCE1. 2007 _ < i 2.90&101 1 pCi/g Dry 1 43425 gdry 108/21/0612:00 j 09/22/06!

1800 I Sec i U i No I CE-144 2007 I < _ __ 7.35F-01 pCi/gDry 1 L 4325 I5 g dry [08/21/0612-00 I 09/22/061 1800 ! Sec 1 U I No i iEU-152 : 2007 1 < " 2.23E-01 pCi/g Dry 4 43425 I g dry 108/21/06 12:00 1 09/22/061 1800 i Sec i U i No IEU-154 2007 I 1.6711-01 pCi/gDry I 43425 i gdry 08/21/06 12:00 1 .09/22/061 1800 S ec U I No RA-226 1 2007 : < i I 2.16E+00 I pCi/gDry 1 1 434.25 1 g dry [08/21/0612:001 09/22/06j 1800 Sec .1 U I[.. i No [...........

_ _ _ I. _ _ ._ _ _ _ _ _ _ _ ... .. I 7 _ _ _ +,It _ _ I. ,l -Flag Values U -Compound/Analyte not detected or less than 3 sigma+ Activity concentraton cxe,-eds MDC and3 sigma; peak identilied(gamma only)U. Compoand/Analyte not detected.

Peakmnot identified, but forced activity conentration enxctds.MDC and 3 sigma High -Activity cenceatration exeedsg ustomerr reporting value, Spec = MDC exceedscustomer technical specificadon L Low recovery Page 15 ef 22 H High recovery Bolded text indicates reportable valuc.No =Pea not ideatificdin garmmaspectrrm Yes = Peak identified in gamma spectrum sean Results are reported on an as received basis unless otherwise noted MDC -lMinimme DetectableCncentration.

Report of Analysis 09429106 15:17 L29898 Eatecon EN005-3EREG-06 BROWN ENGINEERING, INC.Altedyna Tohnologles Cempany Cory DeWitt Sample ID: SSI0. Collect Start: 08/21/2006 12:00 Matrix: Soil (S)Station: Collect Stop: Volume:

Description:

Receive Date: 09114/2006

%Moisture:

4.00 LIMS Number: L29888-9 e Activity Uncertainty I Run Aliquot Aliquot Refernce Count I Count Count Radionuclide Coe 2 Sig MDC U Volu Units Date Date .Time Units. Flog Values STH-228 2007 < 1.63E-01 pCi/g Dry 434.25 gdry 08/21/06 12:00 09/22106 1800 Sec U Yes 1TH-232 I 2007 I< 1 4.83&01 1 pCi/g Dry 1 434.25 1 g dry i08/2106 12100 :1 09/22/061 1800 .Sec U i I No I Flag Values U = Compound/Analyte not detected or less than 3. sigma+ = Activity concentration exceeds MDC and 3 sigma; peak identified(gansmna only)U* = Compound/Anatyte not detecte& Peak not identified, but forced activity concentration cxccs MDC and 3 sigma High -Activity concentration exceeds cnstomer reporting vadlue Spec = MDC exceeds customer technical spQcifitation L -Low recovery Page 16 of 22 H = High recovery Dolded text indicates reportable value.No = Peak not idcntified'in gamma spectrum Yes = Peak identified in gamma spectrum**Results are reported on an at mcceived basis unless otherwvise noted MDC -Mininmu Detectable Coocentration Report of Analysis 09729/06 15:17 L29888 Enercon EN005-3EREG-06 O q TELEDYNEBROWN ENGINEERING, INC.ATel4e.tne TW-Iagiss C-pany Cory DeWitt Samplel D: SS11 Collect Start 08/21Y200612:00 Matrix: Soil (S)Station:.

Collect Stop: Volume: Description-Receive Date: 09114/2006

% Moisture, 4.19 LIMS Number L29888-10.

Activity Uncertainty

.Run 1 Aliquot gi Reference 20 C Count Count Raincld O Conc i Sigmax MDC Uit # Voue Iunits Date Date ITime Units Fa8ale BE-5 i 2007 < I 1.49B+00 1 pCi/gDry 1 ' 298.89 i gdry. 08/21/06 12:00 1 09/22/061 1800 Sec .U 1 FT No .K-40 2007 1 9.60E+00 I 2.12E+00 I. pCi/gDry T298.89 gdy 108/21/0612:00 09/22/061 1800 Sec 1. 1 Yes I{COI 2007 [ 2.60E,-01 pCi/gDy 298.89 1 g dry 108/21/06 12:00 0922/061 1800 1 Sec +U Ye MNFE594. "12007 ! < F ___ _ 4.046E-.01 1 pti/gDry F 298.89 gdry 108/21/06 12:00] 09t6..2/06[180

[IBO See iUF [ NWFJ C-CO51 .2007 1 < ._.. _ __ i .1.0E+0-01 I pCi/gDry , .298.89 j gdry 108/21/06 12:001 09/22/061 1800 I Sec 1 U NO INo j:C58F2007

< ' i F 11___ .111-01t pCi/g Dry -T 298.89 1 Zgdry j108/fi 2 ./6126 t -09F22-/09F1-0 IgOOT Sec ii -No I M F-7 1 2007 1 < I _____T 4.0E-.01 I pCi/g Dry FT 298.89 r. gy 108&21/06 12;001 09/22/061 1800 1. Sec I IT No It:CO-50 2007 <___ _____ 1.60E-01 (pCi/g Dry 1 299.89 g gdry 108/21/06 12:00 109/22/061

.1800 T Sec U T __ I No I C.O65 2007 < T 3.53-01. 1, pCi/g Dry F -'.298.89 1 gdry 08/21/0612.00 1 09/22/06!

1800 1, Sec I i No I.)4 2007 I < 9.49r-2 pCi/g Dry 1 29889 g dry 08/21/06.12:00 1 D9/22/06 1800 Sec .U I No 95 2007 < i L48E-_01 pCi/gDry 298.89 g dry .08/21/06 12:00 09/22/061 1800 Seac T 1 FNoI-R-95 "2007 : < t T 3.01E-01 1pCi/g1ry 1 298.89 i gdry 108/21/0612:00 1 09/2 2061 1800 -Sec i U " No M-99 12007 < T .... T 2.65+03 1 pCi/gDry.

1 298.89 Dr gy y 08/21/0612:00 1 09/22/06 1800 Sec i .J F No 1 RU___I03 ____ .2007 1 '< ,T ..........

T 1.70E1 1 pCT/gDry F 298.89 1 gdry 108/21/06 12:00 t 09/22/061.

1800 Sec I U 1 No MU _106 .... 1 2007 j < 2 1.33E+03 1 pCi/gDry FI 298.89 1 gdry 108/21/0612:00109/22/061 1800 1 Sec I Ui 1Fo.[AG-110M 2007 1 ..T 1 t.370E-01 1 pCi/gDry T 1 298.89 1_ g dry 108/21/06 12:00 1 09/22/061 18-0 1 See I U 1 T No.1 SB-124 .1. 2007 1 < 91.82-01 1 pCi/g1ry T 298.89 gdry 08/21/062:00 1 09/22/061.

1800 1 Sec F U INoI iSB-25 12007 I < 3.03F-,01 1 pCi/g Dry 1i 298.89 -gdryI 08/21/0612:00 09/22/06' 1800I Sec ] U " No .1-131 1 2007 1 < I 1.47E+00 pCi/gDry I " 29.89 g dry I 08/21/0612:00 1 09/22/061 1800 1See U 1 ' T No IS*CS-1104 2007 < 1.I.0538E-01 1 pCi/gDry 1 .298.89 1. gdry .1 08/21/06 12:00 09t22/061 1800 1 Sec U I No.I S-137 2007 I 2.955-0 1 1.348-0 E1 pCi/gDry 1.i .298.89 1 gdry I 08/21/06 12:00 1 09/22/061 1800 1 Sec + i UYes I IBA-1I40 " ....1 2007 1: .2.18E+00 pti/gDry.1

___ 1 2"98.89 g dry '08/21/06 12:00 .... I0/'206l 1800 Sec U [ No .l.AI =140 }= 2007 ___<'_ 1 I6.425-11 I pCi/g~ry i 1 298.89 F 8gdry i08/'21/0612:00 F 09/22/061 1800 I .Sec U I 1 o SB.-1415i 2007 < 1< 1 3.83E-01 F pCi/gDty I 1 298.89 F gdry 108/21/06 12:00 ! 09/22/06j 1800 5 ..Sec I. U I No ._1-13-1 ____ 2007 F < _ _ 9.77F_01.

pCi/g1ry 11 298.89 F gdry F08/21/0612:00 F 09/22/a061 1800 1 Sec I U No I I EU-I.52 I 2007 i 1 ________ 2.975-01 F pCi/g Dry i. 298.89 i gdry 08/21/06 12:00 Vo9/22/06.1800 1 Sec U F I No -j EU-154 I 2007 < " < F 2.251-01 I pCi/g Dry ." 298.89 .g dry 08/21/06 12:00 F 09/22/061.

1800 I Sec 1 U F 1 No F RA-22,6= I 2007 _____< _ 1 '. _ 3.365+00 F pCi/g Dry l I -2.98.89 8 dry 08/21/06 12:00 I 09P-V061 1800 G Sec I U F No F I________PR

ý _ __ [__ 2.18E+ 1 298._ 1 _ g .dry_ 082M 12:00_ 1 19V6 80j , N Flag Values U = Compound.Analyte not detected or less than 3 .sigma+ Activity concentration MDC and 3 sigma; peak identified(ginra only)U* Cocpound/Analyte noit detected.

Peak notiderntifed, but forced activity concentration exceeds MDCand 3. sigma High Activity concentration exceeds cumsme reporting value Spec MDC exceeds castomer tecbnipea]

spacificatioa L = Lighrecovery u High t eovte y Pago 17 rf 22 Bold'ed text indicates reportable" value..No = Peak hat identiied in gamma spectrun Ye = Peak identified in gamma spectrum"* Results am reported en an asreceived basis unless othenrviseoted MDC -Minimum Detectable Concentration Report of Analysis 09/29106 15:17 L29888 Enercon EN005-3EREG-06 BROWN ENGINEERING, INC.A Tetlyot Tar nolugino Cmpany Cory DeWitt Sample ED: SSll 08/21/2006 12:00 Matrix Soil (S)SDacrion:

Collect Stop: Volume:: DescripSion:

Receive Date: 09/14/2006

% Moisture:

4.19 LIMS Numbr-: L29888-10 Activity *,Untertainty RUB Aliquot Aliquot Reference Count Count Count 1 Radionuclide SOP# Coote Sigma. MCnisDt te Te 1 Units Flag Values. Iso j c~0 i s,-2 MDC #oo Volume UnlOit Date Time' Ti-228 2007 3.21 E-01 2.08E-01 pCi/g Dry 298.89 g dry 0M/21/06 12:00 09/22/06 1800 See + Yes TH-232 2007 1 < I 7.41E-01 pCi/gDry 1 298.89 gdry [08/21/06 12:00 i 09/22/061 1800 Sec 1 U i I No 1 Hag Values U = Compousd/rAnrlyte nao detected or less than 3 sigma .+ Activity concentration exceeds MDC and 3 sigma; peals ideonfified(ganuna only)U* Compound/Analyte not detected.

Peak not identified, but forced activity concentratian exceeds MDC and 3 sigma High Activity concantration exceeds customer reporting value Spec = MDC exceeds customer tcchnical spacification L, = tow recovery L -Low , recovery Page l8 of 22 H = Hign recovery Bolded text indieatus reportable value.No = Peak not identified

in gamma spectnrum Yes Peak identifiedin gamma spectrim are reported on a as received basis un)ess ot*Fwjse noted MDC -Minimum Detestable Concentration

-.,L.Report of Analysis 09/29/06 15:17 L29888 Enercon EN005-31EREG-m06 WBROWN ENGINEERING.

INC.AT.ke"4w~hv.ogiaa epae Cory DeWitt Sample ID: SS4 Collect Start 08/21/2006 12:00 Matrix: Soil (S)Station: Collect Stop: Volume:

Description:

Receive.Date:

09114/2006

% Moisture:

2O00 LAIMS Number; L29888-1 I I Activity !Uncertainty Run Aliquot Airjuot IReference Count ICount count Radionuclide SOP# I Cone 2 Siga UDC Units u Volume A Units Dat Date Time Units Flag Values BE-7 17 < ' I 8.54E-01 pCiSgDry 467.55 1 g dry 108/21/06 12:00 09/22/061 1800 I Se= I U .No F_K-40 12007 8.86E+00 I 1.62E+00 1 C pC/gDrz T I 467.55 1 gdry 108/21/06 12:00 1 09/22/06" 1800 1 See + i I Yes -: 4CR-5l 1 2007 1 < F _ 1.41E+00 1 pCi/gDry...

1 467.55 1 gdry ;08/21/06 12:00 i 09/22/061 1800

• Sec V 1U No I M-54 .2007 1 < 1 9.57&-02' pCi/gDry T 467.55 I gdry 108/21106 12:00 1 09/22/06!

1800 F See U v 1 No I'CO-57 1 2007 1 < _" I &74E-O01 1 pCi/gDry i 467.55 i gdry !08/21/0612:00

-, 09/22/061 1800 F Sec U I I No CO-58 2007 1 < t. 120E-01 I pCi/gDry; 1 467.55 g dry 108/21/0612:00 09/22/06' 1800 Sec 4 U No FE-59 F 2007 3 " 3 2.43E-01.

pCilg Dry 1 467.55 ' g dry 08/21/06 12:00 .: 09/22J06], 1800 Sec U I No ,CO-60 2007 < i 1.19"01. pCi/gDry I 467.55 gdry 108/21/0612:00 09/22/061 1800 See U 1 1 No 1'65 2007 1 < I 1T 2.46F-01 I pCi/gDry 1 467.55 1 gdry j 08/21/06 12:00 09)22/06!

1800 T Sec i U .1 i No O 2007 1 <: 1 1 7.58,-02 tpCigDry 1 1 6.755 I gdry 08/21/0612:00 09/22/061 18 1 Sec I U 1 No I 95 2007 1 1.30-01 1 pCi/gDryT

.467.55 I gdry 08/21/0612:00 09/22/061 1800 3 See .-U I I No i ZR-95 F 2007 i <' 7 ._ 1.558E-1 I pCi/g<Dry T 467.55 ! gdry 108/21/0612-00.

F 09/22/063 1800 l See U U 1 No I MO-99 2007 1 < i__. _ 1.90E+03 1 pCidgDry T 1; 467.55 1 gdry 108/21/06 12:00 7 09/22/061 1800 1 See ! U I NoTl RU-103 1 2007 1 < -..1.3,-01 Dry T -467.55r g dry 108/21/0612:00 1 09/22/061 1800z I See U i No i R.U-106 1 2007 3 < 1 7.57-01I pCi/gDry.

1 467.55:. gdry 108/21/06.12:00 j 09/22/061 1800 I Sec I U I I No i AG-ITOM 2007 r < _ _ _ 8.031-02 pCi/g Dry 3 467.55 1 gdry 108/21/0612:00 1 09/22/06!

1800 See U 3 No 3 SBOB124 2007 < 1 1.04E-01 i: pCi/g Dry 1 467.55 11 gdry 08/21/06 12:00 ! 09/22/06i 1800, Sec U I I No '3 SB-125 2007 1 < " 2.31E-01 1ý pCi/gDr-y 1 467.55, F gdiry 108121/06.12:00 1 09122/061 1800 1 Sec U 1No IF 1-131 3 2007 I < j 1.23E+00 pCi/gDry .1 467.55 j g'dry 1 08/21/0612:00 1 09/22/061 1800 3 Sec U I F 1 No F1 .2007 1 < 1 7.558-02 1 pCt/gDry 1 467.55 1 gdry ;08/21/0612:00 1 09/22/06i 1800 1 Sec T4 U No I:.CS-13--

F 20"07 .T < i9.08--2 I pCi/gDry 1 1 467.55. F gdry 108/21/0612:00 1 09/22=06 1800 1 Sec .. U7] ] No 1F 2007 1 < 1.79E+001..f pCi/gDry I 1 467-55 F gdry 308/21/0612:00 09/22/061 1800 3 See i U 1NT LA-140 2007 1 < j 3 3.985-01 D pCi/gfry 1 1 467.55 F gdry 108/21/0612:001 09/22/061 1800 See I U NoI CE-141 i 2007 ! 4< I I 2.96F_01 1 pCi/gDry 1 1 467.55 1 gdry 108/2t/Q6]2:00 T 09/22/061 1800 1 See !U I No I77 CE-144 3 2007 1 < 3 ! 6.881-01 F pCilgDry' 467.55 IN gdry 08/21/0612:00 3 09/22/061 1800 1Sec 1 U No .EU-152 2007 ! < I _ 2.435-01 pCi/gDry i 467.5 5 gdry i08/2106 12:00J 09122/06) 1800 iSe U 1No ,EIU1 4 1 2007" ! <1 1.78-0i1" I pCi/gDry 467.55 g dry !08/21/06 12:00 1 09/22/063 1800 I Sec 1U3 i No I RA-226 i .2007 I < i " 2.54E+00 3 pCi/gDry " 467.55 gdry.. 08/21/06 12:00 1 09/22/06' 1800, 1 See i U i No Flag Values U = Compound/Analyte not detected or less than.3 sigma+ = Activity concenla-Jon exceeds MDC and 3 signa; peak only)U- = Compound/Analyte not detected.

Peal; not identified,'but forced activity concentmtion excecds MDCand.3 sigma.High -Activity concentration exceeds cuslomer repbiting value Spec = MDC exceeds customer technicalfspecifiestion.

• L = Low recovcry Page 19 of 22 H1 High recdverp Bolded txext indicates reportable value.No. =Peak not identified In gammaspectrim, Yes = Peak identified in gamma spectrum*C** Results are reported on an as received basis unless otherwise noted M4DC -Minimum Detecrable Concentration

.-:L.Report of Analysis 09/29/06 15:17 L29888 Enercon ENO05-3EREG-06 SHOWN ENGINEERI NG, INC.A TdIje.cpýheo.orio teOpOy Cory DeWitt SampleID:

SS4 Collect Start 08/21/2006 12:00 Soil (S)Station: Collect Stop: Volume"

Description:

Receive Date: 09/14/2006:

% Moistire:

2.00 LIMS Number-. L29888AI1 Activity .Uncertainty I Run Aliquot, Aliquot Reference Count Count Count nRadionuclide SOP# Cne 2 Sigma MDC Units Volume Units I Date Date Time Units Flag Values TH-228 2007 2.41E-01 1.28E-01 pCi/g Dry 467.55 g dry. %)8/21/06 12:00 09/22W06 1800 Sec + Yes-T14-232 ' 2007 1 < .4.65E-01 I pCi/gDty " 467.55 1 g dry 108/21/0612:00 I 09/22/061 i800 I See U 1.. No 1 Flag Values U Comnpound/Analytt not detected or less than 3 sigma+ = Activity conceentratiowxceeds MDC and 3.sigma; peak identified(gamma only)U* CompoundlAnalyte not detected.

Peak not identified, but oromed activity concentration exceeds MDC and 3 sigma High f Activity concentration exceeds customer reporting value Spec, = MDC exceeds:ciistomcr technical specification L = LOW, recovery Page 20 of 21 H = Highr.mcovyry Bolded text indicates reportable value.No P=encak not identified in gamma spectrum Yes identified in gamma spectrum Results armc-portedion an as.received basis unless otherwise noted MDC -Minimum Detectable Concentration

---

.Report of Analysis 09/29/06 15:17 L29888 Enercon ENoo5-muEG-o6 BROWN ENGINEERING, INC.A Teladyna TehntoVian C-npany Cory DeWitt Sample ID.: S8 Collect Start 08121120106 12:00 Matrix: Soil (S)Station: Collect Stop: Volume:

Description:

Receive Date.: 09/14/2006

% Moisture:

4.70 LIMS Number L29888-12 Ativty Uncertainty Run I Aliquot Aliquot Reference Count Count Count Radionulidone ia MDC Unis Units Date; Date Time Units nag Values 2007 : _ " .I# Volum r __ ___2do0i 1.04E40 1y4E+0 pCl gDry 1 383.71 gdry 10821106"12:00

__09122J061 100 _S.. _ U J No ]K-40 .2007 6.85E+00 i 1.80E+00 i p:i/gDry I i 383.71. 1 gdry... 108/21/0612:00 1 09/221061 1800 1 Sec + Yes',/'-OR-51

2. 2007 " < I .L5IE+00 I pCi/g Dry f 383.71 g dry. 1 0821/06 12:00 09/22/061 1800 1 Sec U. j: No I lMNvt54 2007 _ < -.07E-01 pCi/gDrY 1 383.71 gdry 1.08/21/06 12:00 09/22/061 1800 Sec. U I No C0-57 -2007 _ < [ 1.02F,,-01 I pCi/g.Dry

{ 383.71 1 gdry 108/21/06 12:00 109/22/061 1800 Sec r U .No i.CO-58 2007 1 < i 1.41E-01 1 pCi/gDry -383171 1 gdry !08121/0612:00 i 09/22/061 1800 1 Sec U I No FE-59 i 2007 1 <_ _ _ _ 3.47E-01.I pCi/g Dry 1 383.71 gdry 08121/0612:00 1 09/22/061 1800 1 Sec t u1 F 1 No I CO-60 1 2007 T < I I 6.481r-02 1 pCi/g Dry 1 383.71 1 gdry 08/21/06512:00 I 09/22/061 1800: :i; See 1 1U 1 1 No I 55 2007 * < i I L83F-01 I pCi/gDry 1 1 383.71 I gdry 108/21/0612:00 1 09/221061

.1800 1 Sec ! U I I No 4. 2007 1 < [ 1_ 7.96E-02 I pCi/g Dry 1 " 383.71 i gdry .108/21/0612.00 09/22/061 1800 1Sec 1U No 1 1 2007 < F 1.78E1-01 pCi/gDry 1. 383.71 1 g dry 108/21/0612:00 1 09/22/061 1800 i Sec I U I No I ZR-99 2007 1 < _ .... 72.1E03 pCi/gDry 1. 1 383.71 gdry 108/21/0612:00-1 09/22/061 1800 -Sec U I I No MO-99 .2007 < 1 1 2.81E+03 1 ' pCi/g Dry .383.71 g dry 108/21/0612:00

-09/221061 1800 i Sec :I U i No 1: RU106 2007 < .3F-01 1 pCi/g Dry 1 1 383.71 j g dry 1 08/2110612:00 09/22/061 1800 1 Seo 1U I No 1 RUG-110M6 2007 I D39" < T8.87F,20 pCi/g Dry -383.71 gdiy 108/21/06 12:00 T 09/22061 1800 ý pSec i U " No RB-106 2007 1 1 _._1__ 0- 1 pCi/gDry 1 i 383.71 1 gdry 108/21/0612:00 T 09/221061 1800 1 See i U I No 1 B--125_ 2007 < : 8.87E&-01 1 pCi/gDry i 1 383.71 1 g dry 108/21/0612:001 09/22/061 1800 I Sec I U F No I S~1- OM 2007 1 < _ 1.2iE+00 .pCi/g~ry I 383.71 1 gd R 108/21/0612:00.

09/221061 1800 i Sec 1 U I I No I.-134 1 2007 1 < _ 6.68-10E I pCi/gDry 1. 383.71 g dry 108/21/06 12:00 09/22/061 1800 I See U I I No I CS-13. 2007 I _ _ _ _ _ 6.68.7-02 pCilgDry 1F 383.71 1 g dry 108/21/06 12:001 1 09/22/061 1800 1 See UT No 1 SB-140 2007 1 .2.18E-00 I pCi/gDry 383.71 -gdr, 08/21/061200 09/22/061 1800 I Sec U No I 1-1431 2007 < .... I ........ 1.12E,+00 I pCi/gDry.

I. 383.71 gdry 1 0 8/2 1/0 6 12:00 1 09/221061 1800 " See I U 1 1 No I:CE-14 20071 < 3.23E-01 pCi/gDry 1. 1 383.71 g dry 108/21/0612:00 I 09/22/061 1800 F Sec 1 U 1 1 No I SEU-I44 2 2007: < .1Z 8 -01 pCi/gDry FI 383.71 I g dry 108121/0612:00 1 09/22/061 1800 Sec I U No 1 I EU-t52 2007 < .2.18E_0- pCi/gDry I t 383.71 gdry 108/21/0612-00 I 09/221061 1800 i See j U I No i______________

2007_ < ____ I 8.01E-01 I pCi/g Dry 17 383.71 1 g dry 108/21/06 1200 ;' 09/22/061 1800 1Sec I U 1 1 No I EU-152 200 3. _____ 1927E+01 i pCi/g~ry 1. 383.71 1 g dry 108/2110612:00 1 09122/061 1800 Sec I U. 1 INol1_RA-226 12_007 ' < i _2.73E+00 I pCgDry _38_3_.7_

g& dry 108_21/06_12:00 1 0922/061 180_0 _See i u_ I No 1:_T14-228 1 2007 1 3,011 f 1.5213-01 1 1 pCi/g Dry F 383.71 gdry.' 108/21/0612:00 1 09/22/061 1800 1 Sec i + YC*ye_ -_- _ ... , ._ I i _ _ _ I ... .L I i 1 _1 _, I _. .i Flag Values U = Compound/Ahalyte not detected or less than 3 sigma+ Activity.

concentration excceds MDC and 3 sigma; peak identified(gamma only)U- Compound/Analyte not detected.

Peak not idcntifiedl but forced activity concentration exceeds MDC and 3 sigma Hig, = Activity concentrationexceeds customer reporting value Spec. = MDC ex'eeds customer technical specification L -Low recovery H = High.recovery Pag 21 of 22 Bolded text indicates reportable value.No = Peak not identified in gamma spectrum Yes = Peak identified in gamma speqtrum kasults ae reporfd on an as-received basis unleas otherwise noted-MDC -Minimum Detectable Caocentration Report of Analysis 09/29/06 15:17 L29888 Enercon EN005-ý3EREG-06 eBRO 3 WNENGINEERING, INC.A Tdtdy.. SeT eata*.r.p.ny Cory DeWitt Sample ID,. SSS Collect Start 08/21/2006 12:00 Matrix: Soil (S)Station: Collect Stop: Volume:

Description:

Receive Date: 09/1412006

% Moisture:

4.70 LIMS'Number:

L29888-12 Activit2 Uncertainty I Run Aliquot Aliquot Reference Coy1t I0 Count Count Se Radionuclide SOP#f Cone 2 Sigma MDC Units Volume Uts Date Date Tine. Units riag ValIe.TH-232 2007 < 5.36E-,01 pCilg Dry 383.71 g dry 08/21/06 12:-00 09/22/06 1800 See U Ye Flag Values U -Compound/Analytl not deleeted or less than 3 sigmar+ -Activity concenlration exceeds MDC and 3 sigmna peak identified(gamma only)U* -Compoand/Analyte not detected.

Peak not identified, but forced activity concentration exceeds MDC and 3 sigma High = Activity oaneentralion exceeds customer reporting value Spce -hMC exceeds customer technical specification L -Low recovery Page 2 of 22 H High recovery Bolded text indicates reportable value.No Peak notidentified in gamma speerm Yes = Peak identified in gammaspanrm R*C* Pesullt are reported on an as received basis unless otherwise noted MDC -Minimum DctectableConcentratian University of Washington More Hall Annex D&D, Project 10492 Attachment 40 -Bioshield Concrete Characterization Analytical Results UW-MCP-OP-13, Rev. 2

,AL TELEDYNE 01 BROWN ENGINEERING, INC.A Teledyne Technologies Company 2508 Quality Lane Knokville, TN 37931-3133.

MAY 3 0 2006 Cory DeWitt Enercon 4499 Old William Penn Highway Murrysville 1566*Report of Analysis/Certificate of Conformance, 05130/2006l LIMS #: L28599 Project ID#. EN005-3P61-06 Received:

05/10/2006 Delivery Date: 05/24/2006 PO. #:: MCIL VI00 i Release #: SDG #This is to certify that Teledyne Brown Engineering

-Efivironmental Services located at 2508 Quality Lane, Knoxville, Tennessee, 37931, has analyzed, tested and documented samples as specified in the applicable purchase order, This also certifies that requirements of applicable codes, standards and specifications have been fully met and that any quality assurance documentation which verified conformance to the purchase order is on file and may be examined upon request.I hereby certifý that the above statements are true and correct.Ke'th Jeter N Operations Manager-/Cross Reference Table.Client ID Laboratory ID Station ID(if applicable)ý W4__ ___ ______W5 1,28599-2

_W7" ______ L28599-4 _ _ _ _..W8 L2859975 .___.....W9 L28599-6 _...... .w ________ _ I L28599-7 ...._....._ _r1 L28599-8 Report o. W alysis TELEDYNE 0 BROWN ENGINLERING, INC, 05/3.0/06:16:32 .A~eledyfola Tchnologids Comupany L28599 Enercon Cory DeWitt EN005-31P61-06 Sample ID, W4 Collect Start: 05/02/2o06 09G30 Matrix: Solids (SD)Station: Collect Stop: Volume:

Description:

Receive Date: 05/10/2006

% Moisture: LIMS Number: L28599-1 IAtvt-Uncertainty.

I Run Aliquot Aliqu t -Reference ICount -Count Count Radionuclide So so# Itt 2 sigma MDC Units nits Date D.. Time T Units I Flag Values c-14 ___012-W0_1

<_1 8.95E-07:

uci/g _____2.007 I gwet _ I 05/26/06 50 ! M I u _ _141-3 1 2003 1 .4.87E-04 i 4,61,E-06 1 .uci/g 12.0076 g wet I _ 05/271061 50 1: M I + I I T BE-7 1! 2007 1 < ! I 1.10E-0S 1 uci/g '238.51 1 gwet 105/02/06 09:30 F 05/19/06[

900 1 Sec '1 _____ No-40. 2007 1 < _ _ I 4.52E-06 I uci/g 1 238.51, gwet I05/02/0609:30 05/19/061 900 " Sec I o I CRK-0 1 2007 1 < I .... .4 1.19E-06 1 uci/g [ :238,51 I gwet 105/02/0609:30I 05/19/06 900 1 sec l _____ o--T.MN-54 15 2007 1 < I I 1.51E-06 1 uci/g 238.51 1 gwet 105/02/0609:30 F 05/19/06J 900 :1 Sec Jl0 1 ViS--CO-57 1 2007 1 < _ ! 21.2E1-0 I uci/g :1 238.51 g wet 105/02/06 09:30 05/19/061 900 1 Scc I IU'&o IF CO-58 4 2007 1 < _ _ _ 1.512E-06 1 uci/g .238.51 .gwet 105/02/0609:30 1 05/19/061 900 1: See J U _ I No I FEC-59' < 2007 .1 360E-06 1 uci/g 238.51 ..gwet,, ,0/26 09:30 F 0519/06 900 " See (Ut .CO-60 1 2007..4.31E-05 1.36E-06 I ... uig .. .. 238.51 gwet 10 5/02/060930 105/19/061 900 Sec I I -es-N-65, 2007 1 <I 6.29E-06 1 uci/g 1 __ .238.51.1 gwet 105/02/0609:30 1 05/19/061 900 1. Sec iu* I INn.1o NB3-94 2007 1 < I I 1.27E-06 uci/g i I 238.51 gwet, 05/0210609:30 1 05/19/061 900 1 Sec IUI N -fi-N -ZB-95 T"06 < I I i.66E-06 I uci/g .1 238.51 I g wet 105/02/06 09:30 1 05/19/06!

900. 1 "Sec I U# I In N ZR-95 2007T < 1 _ 3.04E-06 1 uci/g i1 , 238.51 1 gzwet 105/02/06 09:30 1 05/19/061 900 I Sec fIUI Ii MO-99 7 200 T T < 1 ,[ 7.54E-04 1 .uci/g 1 1 238.51 1 g wet 105/02/06 09:30 1 05/19/061 900 1 Sec I-U1 t INo RU-103 1 2007 1 < 1 1 1.439-06 F uei/g 1 1 238.51 1 gwet 105/02/0609:301 05/19/061 90 Sec lul .--N AG-106 1:2007 1 < 7.54 3E-0. 4 uci/g 1 I 238.51 1 g wet 105/02/06 09:30 1 05/19/061 900 1 See IUF [i No 11 SB-124 E2::@07 < 1.43E06 ui/g : 238.51 1 g wet 105/02/06 09:30 1 05/19/061 90 1 Se 1 U____________

106__ ___.2007_1 1.917E-065 uci/g 1 23 8.5 1 1 gwet/0 09-30 1 05/19/06 1 900 1Sec FI U I I No S'.B-125 j 2007 _.... , ..82E'06. uci/g 1 < 238.51 i g wet 105/02/06 09:30 1 05/19/061 900 1 Sec I U I I No F 11-131. 1 2007 __< __ _ 4.569E-06 I uci/g 1 238.51 1 gwet, 105/02/06 09:30 1 05/19/06i 900 I Sec IU*d i NoF CS-134 1z 2007 __< : 1.15E-,06 f uci/g I i 238.51 g wet 105/02/06 09:30 1 05/19/061 900 Set I I iNo-CS-137 1 2007 < < _ 1.415E-061 uci/g II 238.51 w gwet 105/02/06 09:30 I 05/19/061 900 [1Seec I TU I No.. ," CA-140 F 2007 F < 1. 1 .02E-05 F u.ci/g 1 238.51. I gwet 105/02/0609:30 1 05/19/061 900 F Sec TWU 1 NoF LA-140 F 2007 F < I _ .1.44E-06 I uci/g 1. 1 238.51 1 gwet 105/02/06 09:30 1 05/19/061 900 1 See I U I NoFI CE-]I F1 2007" 1 < _ ____ 1.82E-06 1 uci/g 1 f 238.51. F g wet [05/02/06 09:30 :1'05/19/061 900 F Sec I U I I No CE-144 I 2007 F < 1 :1 5.76E-06 I uci/g Il [ 238.51 1 gwet105/02/0609:30 1 05/19/06!

900 1 Sec I U1 I 'fNo EU-152 I. 2007 1 1.37E-04.1 4,01E-06 : .1 uci/" I I 238,51. I g-wet 105/02/06 09:30 1 05/19/061 900 Sec 11+ I T-ýf.... ... ... ..?.... ....... ....,I ..., , ......i............

.:1 1 i .[ " 1".Flag Values U = Compound/Analyte got detected or. less than 3. sigma No = Peak not identified in gamma spectrum+ = Activity:concentration exceeds MDC and.3.sigma; peak identified(gamma only) Yes = Peak~identified in gamma spectrum U* = Compound/Anialyte not detected.

Peak not identified, but forced activity concentration exceeds.MDC and 3.sigma

• Results~are reported on an as received.

basis High = Activity concentration.

exceeds customer reporting value. unless otherwise noted.MPDCexqecds.customer technical specification L = Lw recovery MDC -Minimum Detectable Concentration H-1. 1Hi-gh recovery Page I of 16 B3olded.text:indicates reportable value.

Repoit oq aiysis 05/30106 16:32 L28599 Enercon EN005-3 P61-06.TELEDYNE 1.BROWN ENGINEERING, INC.A Teledyte Technologies Company Cory DeWitt Sample ID:. W4 Collect Start: 05/0212006 09:30 Matrix' 'Solids :(SD)Station: Collect Stop. Volume: Description; Receive Date, 05/10/2006

%Moisture:

LIMS Number; L28599-1 IActivity IUncertainty IRun IAliquo Aliquot Reference I Count count count Radionuclide SOPff Cone 2 Sigma MDC Units Volume Units Date. Date Time Units FlagValues EU-154 ..2007 7.31E-06 L,71E-06 uci/g 238.51 gwet: 05/02/06 09:30 05/19/06 900 See + Yes RA-226 1i. 2007... I 2.03&K05 I uci/g 1 1 *238.51 1 g.wet. 105/02/06 09:30 1 05/19/061 900 I..See U I I io. 7 TH-228 I 2007 I < 1.63E-06 .uci/g 1 I 238.51 1 gwet 105/02/06,09:30 I 05/19/061 900 I See I U I I No{TIH-232 '12007 I I " 5.591-06 .uci/g I 1 .238.51I g wet. 1 05/02/06 09:30 ] 05/19/061 900 1 Sec I U I I No I Flag Values U = Compound/Analyte not detected or less than 3 sigma+ = Activity concentration.exceeds.MDC and3 sigma; peak identified(gamma only)U* -Compound/Analyte not detected.

Peak not identified, but rorced activity concentration exceeds. MDC and 3 sigma Highb = Activity:concentration exceeds customer reportingvalue Spec = MDC exceeds~customer technical Specification L Low recovery L Lo recveiyPage 2 of 16 1- = High recovery Bolded text indicates reportable value.No. = Peak not identified in gamma spectrum Yes. =Peak identified in gamma spectrum**** Results are reported on.an as received basis unless otherwise noted MDC -Minimum Detectable Concentration Report c~rialyslis TELEDYNE 1.0"/0 16 BROWN ENGINLERING, INC., ,05/30/06 16:32 A TeledyqeaTechnologies Company.L28599 Enercon Cory DeWitt EN005-3P,61-06 Sample ID:: W5 Collect Start: 05/02/2006 10:00 Matrix: Solids (SD)Station::

Collect Stop:. Volume:

Description:

-eceive Date: 05/I 012006 % Moisture: LIMS Number, L28599-2: FActiVity Uncertainty IRun -Aliquot jiAliquot 1z Reference Count 1Count fCoun~t Radionuclide So onc Sigma MDC Units atets Flag Values 2OP C DC nit Volume unit Dae Date. Time 'nt C-14 032-80 1 i.12E-05 SSE.507] ." uei/g 1 218705 1; gwet 1: I 05/27/061 50 i M I + I H-3 .2003 T 5 05E-04 1 3691E-06 I uci/g .... 1 2.8705 1 gwet 1. ........ 1ý 05/27/061

50. M l +MV BE-7 _ _ 2007 I .. -] ..........

1 8.35E-06' uci/g 1..' _ 1 269.48 F gwet F05/02/06 10:00 1ý 05/19/061 900 1 See I U I I No I K-40 120071 < 1.'.5,77E&06 1 uci/g 1 _ 1 269.48 1 gwet. 105/02/06 10:00 1.05/19/061 900 I Sec IU* I INo l CR-51 '"2007 1 < 1 1 9,42E-06 1 uci/g 1 1 269.48 T gwet, r1o05/02/06 10.00 1 05/19/061 900 1 See TTUI U _I _ No I MN-54 1. 2007 .< ] ] 1.14E-06 I uci/g 11t 2.69.48.T gwet 1.05/02/06 10:00 1: 05/t19061 900 1 See TI U 1 1 o0.CO-57 F 2007 T < T [ 1.50E-06 I uci/g , 269.48 T gwet 105/02/06 10:00 1: 05/19/061 900 1 Sec ,I*. 1 1. No"I CO-58 ., 2007 1 ..... < " __.... 1.27E&06 uci/g 1 269.48 T gwet 1.05/02/06 10:00 1 05/19/061 900 1 Sec. 1 U I I No 1 FE-59 2007 .< 1I "_[_ 2.87E-06 uci/g 1 269.48 1 gwet.

10:00 !i 05/19/061 900 1 See Ul I.... No I CO-60 2007' 1 4.49E-05 1 1,23E-06 'I_.......

_ uci/g .1 269,48 1 gwet !05/02/06 10:00 1 05/191061 900 See + I .Yes I ZN-65 F 2007 "1_ <_ i .... .. 1: 4476E-06 1 uci/g .1 269.48 1 g wet [05/02/0610:00 05/19/061 900 1Sec 1] W _ No____ .....NB-94 F 2007 < 1 _ _ -9.71E-07 I uci/g i 1 269.48 F gwet 105/02/0610:00 I 05/191061 900 1 See I U I No NB-95 1 2007 F < T _ ;1.24E-06 I .uci/g. 1. 269.48 F gwet .05/02/0610:00 1 05/19/061 900 1 See .I U 1 1 No F ZR-95 1F 2007 " <. I _ 2.31E-06 I uci/g 1: 1 269.48 F gwet 105/02/06 10:00 .1 05/19/061 900 1 See I U I I No I MO-99: 2007 f < F _' 5.79E-04 I uci/g Ii_ 1 269.48 1 gwet 1:05/02/06 10:00 1 05/19/061 900 1 Sec I u I INo .F..RU-103 .2007 1 < I 1. f 1,08E-06 I uci/g 1- 1 269.48 1. g wet I05/02/06 10:00 1 05/19/061 9001 SI c s UA I ' F No I RU- 106 2007 1 < I _ 9.07E-06 1 uci/g 1o 269.48 1 g wet. 1:05/01/06 10:00 Il 05/19/06!

900 I Sec i U0 ..... 1 No 1 AG-I1OM 1 2007 1 < ____' 1.03E&06 uci/g I i 269.48 .1 gwet 105/02/06 10:00 j 05/19/06!

900 1 S.c-C U] __" INo. I SB-124 F 2007 1 < [ 1.07E-06 I uci/g :- 1 269.48 1. gwet 105/006 10:.00 .05/19/061 900 1: See U I I No I SB-125 .2007 F < 1 _: 2.27E-06 t uci/g T 1 269.48 i. g wet 1 05/02/06 10:00 1: 05/19/06; 900. 1 See [ i I No:.-131 .... ... 1 2007 1: ..........

I 3.57E-06 I uci/g :. 269.48 1 gwet 105/02/06.10:00

-05/191061 900 1 See i.U .I, I No i CS-134 f 2007 1 < .1 8.98E-07 I uci/g :F 269.48 1 gwet 1-05/02/06 10:00 1 05/19/061 900 1 See rU I No I C8-1 37 1! 20071 < [ I 1.08i-06 I uci/g F .269.48 F- gwet 105/02/06 10:00. F 05/19/061 900 1 See I U I I No F-BA-I40 1 2007 1 < 1 I 8.018E-06 1 uci/g 1 1 269.48 1: gwet 105/02/06 10:00 F 05/191061 900 1 Sec I U I I NI LA-140 1; 2007 1 < I _ _ 9.93E-07 1 uci/g I '269.48 F g~wet 105/02/06 10:00 1 05/19/061 900 51 See I U I .. I No I CE-141 1 2007 1 < 1" 1.42E-,06 I uci/g I , 269,48 1 g wet 105/02/06 10:00 F 05/19/06!

900 1 Sec ] U I [ No:!F CE-144 1! 20071 < tc 4.48E-06 1 uci/g _ _ F 269.48 1 105/02/06-:60.1 05/191061 900 1 See I U _ " No V EU-152 I 2007 1.05E-04 1 3.10E-06 __[ __ uci/g 1 1 269.48 g gwet. 105/02/06 10:00 05/19/46.

900 Seec i + 1 Yes I Flag Values U -Compound/Analyte:

not detected.or less than 3, sigma No = Peak not identified in gammaspectrum

+ = Activity concentration exceeds MDC and3, sigma; peak identified(gamma only) Yes = Peak identified in gamma spectrum U* Compound/Analyte.not detectedý Peak not idcntified, but forced activityconcentration exceeds:MDC and 3 sigma *** Results arereported on an as received.

basis High. = Activityconcenttation,exceeds dustonmet reporting vialue unless otherwise noted Spec. = MDC exceeds customer technical specification L = Low recovery MDC -Minimum Detectable Concentration H = High recovery Page 3 of 16 Bolded text Indicates reportable

value, Report *Jialysis o0530/0.616:32 L28599 Enercon EN005-3P61-06 TELEDYNE 0BROWN ENGINi+/-RING, INC.A Teledyne Tochn ologies Company Cory DeWitt Sample ID: W5 Collect Start: 05/02/2006 10:00 Matrix: Solids (SD)Station: Collect Stop; Volume:

Description:

Receive Date: 05/10/2006

% Moisture: LIMS Number: L28599-2 Radionuctide I Activity.

Uncertaint y I[Run Aliquot Aliquot I Reference I Count .Count Count SOP# Cone 2 Sigma MDC I Units : # Volume Units Date Date Time Units FlagValues

[ 5E- 4 ...i

• l.. I I -EJ-154 20.07 3.02E-06 uci/g 269,48 g wet 05/02/06:10:00 05/19/06'6 900 See U# No RA-226 2007 <. I 1.59E-05;1 uci/g I T 269.48 I wget 1 05/02/06 10:00 1 05/19/06T 900 I Sec U I .No " T1_1-228 I 2007 1 I. I 1.34E-06 I uci/g I 269.48C 1 gWet 1:05/02/06 10:00 I 05/19/061:

900 sec ' U " I No " TH-232 " 2007 [. I. I 4.56E-06 :1 uci/g I I 269.48 I gwet 705/02/06 10:00 1 05/19/061 900 1 See I U I. I -Ný'o Flag Values: U = Compound/Analyte notdetectetd or less than 3 sigma+ = Activity.concentration.

exceeds MDC and 3.sigma; peak identified(gamma only)U* Compound/Analyte not detected,.

Peak notaidentified,cbutor~ed actiyity concentration exceeds MDCG and 3 sigma High = Activityconcentration exceeds customer reporting value Spec = MDC -exceeds custormer technicat specification L = LowretoyPry.

H = High.recovery Page 4 of 16 Bolded ,ext indicates reportable value.No = Peak not identified in~gamma spectrum!Yes = Peak identified in gamma:spectrum

• • • Results are reported on an as received basis unless otherwise noted'MDC -Minimum Detectable Concentration

• Re .port o 9 inalysis.

T41EDYNE 05130/06 16:32 BROWN ENGINEERING, INC.A 0Tg!odyn'Teehnologies Comporty, L28599, Enercon Cory DeWitt EN005-3P61-06 Sample ID: W6 Collect Start: O5/02/2006 10:30 Matrix:. Solids (SD)Station: Collect Stop: Volume:

Description:

ReceiveDate:

05/10/2006

% Moisture: LIMS Number: L28599-3 A ivt t Alqu t eferenceý t " ' [i ae aActiity Uncertainty Run Aiqut Aiquot I eI Count. ICount Count.Radionuclide SOP# Conc 2 Sigma MDC Units # volume. UnitsL Date Date Time Units Flag Values C14 .............

..... 032-80 9.21E(-06F 6.58E-07F I_ _ uci/g I 2.165 lg'wet 1 05/27/061 5o0 M 1+ ____ t H-3 I

• 2003 I 2.79E_-04 1 3.39E-06 F " F uci/g ]: 2:165 F gwet F 1 05/27/06!

50 F M 1'" ___"_BE--7 1 2007 ...__..... 1 4.59E-06, I uci/g 1. ' 244.93 1 gwet [05/02/06 10:30 1: 05/1.9/061 900 1 "Secc T"i'_ " F _I&F K40 .z"207 '1 < F 1____ 2.65E-06 ' uci/g. 1 __T 244.93 1 gwet [05102/06 10:30 1: 05/19/061 900 F &Sec I U 1: [ Yes I CR-51 :2007 1 < I _ _ 4.84E-06 uci/g 1 244.93 1F gwet f _05/02/06 10:30 1 05/19/061 900 1 See, I U:I _ No.MN-54 1 2007 i. < I_ _ 5.85E-07 1 uci/g. .I .. 244.93 F gwet V[0502/06 10:30 1 05/19/061 900 1 Sec I UI U _ No, I CO-57 " ! 2007 ,I <________

______ _ 7.87E-07 1 uci/g ____ 244.93 gwet 105/02/06 10:30 [ 0519/06! .900 I Sece I-U* [ F No F CO-58. 1 2007 '1.... < I I " 6.98E:07 uci/g 1 244.93 Fg wet ý 05/02/06.10:30 1 05/19/061 900 See 'l UI U1 : No I FE&59 1. 2007 1 <: ..... 1.301E-06 i uci/g 1: 1 244.93 1 gwet 105/02/06 10:30 1: 05/19/061 900 F Sec T' U I .N61I CO-60 1 2007 1 8.01E-061 I5.54E-07 I ...... I uci/g 1. 1 244.93 F g.wet F.05/02/06 05/19/061 900 I Sec IV 1 + I .I Yes 1 ZN-65 1 2007 F < ' _1_" _I 2.40]E-06 F uci/g I 244.93 F1 gwet [05/02/0610:301 05/19/061 900 1 Sec IUll * [No I NB-94 1 2007. 1 < t F 4.80E-07 I uci/g I F 244,93 F g'wet 105102/06 10:30 1 05/19/06.

900 .1 Sec F I .U _ .___-' --NB-95: 1 2007 F <. F " " 6.84&-07 1 uci/g 1 1_ F 244.93 F: g wet 1F05/02/06 10:30 1 05/19/061 9001 Sec': I] " F No I ZR-95 1 2007 F < _ _ _I 1.22E-06 I uci/g .__ F 244.93 F g wet 105/02/06 10:30 1: 05119/061 900 1 See I ]U: I I No I MO-99 " 2007 1 < '_ .... l, 3.25E-04 1 uci/g F F 244.93 F g'wet 1 05/02/06 10:30 I. 0511.9/061 900 1 Sec. I UW 1 ______No RU-103 .2007 1 < F _ I 5.91E-07 I uci/g T, I 244.93 1 .gwet 105/02/06 10-30 F 05/19/061 900 Sec I U 1 F1 No I RU-t06 1 2007 .! .< _ I 4.731106 1 Uci/g F 244.93 1 gwet.1 05/02/06<1030 F 05/19/06 ;900 See T-.V NOI AG-l.0M 1 1 <_______ _________1 5.14E-07 1 uci/g i 244.93 F gwet 105/02/06 10:30 -0519/061 900 1Sec u: U ..l i SB&.124 , 1 '2007 I < 1 I 5;47E-07 I uci/g F1, F 244.93 F! gwet 105/02/06 10:30 1 05/19/061 900 I Sec F' U 1 .1 No I S131245 1 2007 < < I _ 1.097-06 1 uci/g F 1 244.93 1 gwet 1 05/02/06 10:30 t 05/19/061 900 1 Sec FUT U I I.No I 1-131 2007 I < I ___"_....

11.89E-06 I uci/g 1: I 244.93 I gwet. 105/02/06 10:30 5I7 05/19/061 900 1 Sec I U _ 1 1No1 CS-134 12007 1 < I "_ _ 4.889E-07 1 uci/g 1 F 244.93 1 gwet 105/02/0610:30 I 05/19/061 900 1 See I U I I No-I CS-134 2007 1 < I ....... I 5.4521-07

'1 uci/g F1 F 244.93 1 gwet 1.05/02/06 10:30 .1 05/19/061 900 1 Sec I L a. I -2007141 .2007 < -_- 4.234E-06 1 ucilg.: F 244.93 1 gwet :105/02/06 10:30 T 05/19/061 900 1 SecI *U I No I LA-140 I 2007 1 < 1 _1 7.09E-07 1 ueig I i 244.93: gwet 105/02/06 10:30 1 05/19/061 900 1 Sec I U i IN%CE-141 -',2007 1 < _ __ 7,32E-07 I uci/g : -. 244.93 1 gwetl 05/02/06 10:30 I. 05/19/061 900 ' Sec. 0U I No 1.CE-144 ]' 2007 .< 2,42E-06 i uci/g .. ____ 244.93 1 gwet 05/02/06 10:30 F 05/19/061 900 1 Sec U I __ No 1" EU-152 i 2007 1.80E-05, 9.30E-07 I. _ uci/g : 244.93 ' g.wet: 05/02/06 10:30F 05/19106i 900 I Sec +i + _ -_-_---Flag Values U = Compound/Analyte not detected or less than.3 sigma No = Peak not identified in gamma spectrum+ = Activity concentration exceeds MDC and 3 sigma, peak idcntified(gamma only) Yes = Peak:identified in gamma spectrum U = Compound/Analyte not.detected

Peak.not.identified, but forced activity concentration.exceeds MDC and 3 sigma

• Resultsarereportedon an asreeeivedbasis High = Activity concentration:exceeds.eustome-reporting value: unlessotherwise noted Spec = MDC exceeds.customer technical specification L = Low recovery MDC -Minimum Detectable Concentration H = High recovery -Page 5 of 1.6 Bolded.text indicates reportable value. -

Report 01 -nal 05/30/06 16:32 L28599 ,gOq, TELEDYNE 0 BROWN ENGINEERING, INC.ATeledyne acthologias Company Enercon Cory DeWitt EN0053P6.1-06 Sample ID: W6 Collect.Start:

05/0212006 10:30 Matrix: Solids (SD)Station::.

Collect Stop: Volume:

Description:

ReceiveDate:

05/10/2006

% Moisture: LIMS Number', L28599-3 Acvity Uncertainty I Run Aliquot Aliquot I Reference C te Count, Count RadionuAlide SOP# Cotn 2 Sigma MDC I Units R Volume Units Date Date: Time Units FaVlu ERa-'154 d 2007 Cn< .l58E-06 uci/g 244.93 g Wet 05/02/06 i0:30 05/19/06 900 Sec U* No RA-226 2007 1 < : " 8.59E-06 I uci/g 1I 244.93 I gwet 105/02/06 10:30 I 05/19/061 900 I See UI ..I I1o I TH-228 I 2007 .1 < I 661E-07 l ucilg I 244,93 1 gwet 105/02/06 10:30 I 05/19/061 900 sec ' U I YesK TH-232 I 2007 <r 2.43E-06 I ucilg I 244.93 I g wet 105/02/06:10:30 I 05/19/061 900 1: See I U :1 No I Flag.Values U Compound/Analyte not detected or less than 3 sigma+ Activity concentration exceeds: MDC and 3 sigma; peak identified(gamma only)U* = Compound/Analyte not detected, Peak not identified, but forced activity concentration exceeds MDC and 3 sigma High = Activity concentration exceeds customerreporting value Spec MDC exceeds customer.technical specification L = Low. recovery Page 6 of 16 H = High recovery Bolded text indicatesrreportable value.No = Peak notidentified in gamma spectrum Yes: -Peak identified in gamma spectrum**** Results are reported on an as received basis unless otherwise noted MDC -Minimum Detectable Concentration 0Report Apinalysies TELEDYNE 05/30/0616 32BROWN ENGiNEERING,+

INC.01632 A Teledyne Tachnologies Company L28599 Enercon Cory PdWit EN.005-3P61-06.

Sample ID: W7 Collect Start:. 05/02/2006'11,:00 Matrix: Solids: (SD)Station: Collect Stop: Volume:.Description:

Receive Date: 05/10/2006

%0Moisture:

LIMS Number: :L28599-4.Activity, Uncertainlty i Run -Aliquot.I Aliquot I Reference Count, Count [Count.Radionuclide Con 2Sigma MDC Units A Volume o ItUnits l Date Date Time Units Flag Values L~~~~~~~~~~0/701 50 T M _ _ _ _ _ _ _ __ _ _ ._ _ __ I +__ .__C7I14 1 032-80: 1 2.24E-06 1 5.97M-07 1 __1 uci/g 1 1_ 1.9631 1 g wet I_ 05127/061.

50 M I + 1 1 113 1 20031 1 1.89E--04 1 2w97E-06 1 1 uci/g: I 1_ 1.9631 1 gwet 1 " " 1 05/27/061:

50: 1 M: I + I. 1 1313-7 12007 1 < ... _...... 1 2.43E-06 I Uci/g I 1 257,61 1 gwet 1'05/02/06:

1:00 1 05/19/061.

1800 I See I U I I No l K-40 _ _ 1 2007" 2.44E-06 1: 12613-06 1 .uci/g I. 1 257.61 1 gwet 1;05/02/06 1.1:00 105/19/06 1800 1 See I + 1: YeT CR-51 1 2007 1 < 1 1 2.74E-06:6

uci/g 1 1257.61 1 gwet 105102/06 11:00 .05/19/061t 1800 11 See I U 1: 1 No]MN-54 1 2007 1 < _ _

1 uti/g r1 257'61 g wet 1,05/02/06 11:00 1 05/19/061 1800 1 Sec Iu __.... No1 CO-57 .2007 1 < 1 1 4.22E-07 .1 uci/g 1 257.61 1 wet 105/02/06 11:00. 1 05/191061.

1 6 1 Sec I No 1 *o58 2007 _ _ 1 3.62E-07 I uci/g _. 1. 257.61 1 gwet 105/02/06 1.:00 1 05/19/061:

1800 1 See I U* I No I FE-59 .2007 1 < 1 + I 7.60F-07 .. uci/g, .i. 257461 I ýgwet 1 05/02/0611:00 1 05/19/06i:

1800 T See IU ' 1 No I1 CO-60 2007 1 5.12Ei-06 1ý 2.83E-07 I "____ "_ uci/gk I _ _ 257.61 I gwet 1:05/02/06 1:00 1 05/19/061.

1800 :1 Set c + 1:l Y- -" ZN-65 T 2007 11 1.33E-06.

I uci/g 1 ,1 257.61 1 gwet 105/02/06 11:00 05/19/061:

1800 i See I U* I._ .No'NB-94 T oo7 1 < T I 2.54E-07 1 uci/g 1 1 257.61 1 gwet* 105/02/0611:00 1 05/19/061:

1:800 1 See I U I: I No I NB-95 120071 < T [ _ __ 3.68E-07 1.I uci/g " 1 1, 257.61 1 gwet 105/02/06 11:00 1 05/19/061:

1800 1 Sec " U 1, 1 NoT I ZR-95 1 2007 i < Z .I. 6.45E-07 I uci/g, 1 .J1 257.61 F gwet 1.05/02/06 11:00 1 05/1--9-/-061--7-800 1 Sec I. U 1: I No I MO-99 1 2007 0 < I' I 1.64E.04 I uci/g1 " __ 1 257.61 F gwet 1:05/02/0611:00 105/19/0*61 800 !F Sec FUL-_: _ No 1.RU4-03 F 2007 1 < I I 3.33E-07 .1 ucig 1I F 1257.61 1 .gwet 105/02/06 11:00 1 05/19/061:

1800 F See IU 1. I No .: RU-106 F 2007 1 < I I 2.61E-06 I uci/g 1 :1 1 257.61 g gwet 105/0210611:00 1

1800 1 Sec" i.Ul _ I No I AG-1tlM F 2007 I <1 .2.71 E-071 uci/g 1 1 257.61 g wet 1ý 05/02/0611:00

! 05/19/061:

1.800 i Sec: iU i _ F;NoI SB-124 r 2007 I < I _ 2.85E-07 F1 uci/g, 1 i 257.61 gwet 105/02/06 11::00 i 05/19/061 1.800 1 See IFU I., F No I S13-1,25 1 2007 1 < F I 6.32E-07 F uci/g I1 257.61 gwet 105/02/06 11:00 1 05/19/061.

1800 1 See Uif I 1-13 1 .. 2007 F' _ ___ < I 9.48E&07 1 uci/gL I _ .257.61 Igwet 105/02/06 11:00 1 05/19/061 1800 .Sec KUI [No-CS-134 1 20076F1 1 < .1 2.50E-07 I uci/g 1 I 257.61 1 gwet 105/02/06 11:00 r: 05/19/061:

1800 .1 See IrU I No I CS-13.7 _ 2007 F < F .... .F 2.78E,-07 F uci/g 1 T 257.61 F gwet 105/02/06 11:00 1 05/19/061 1800 1 Sec F lU. _____BA-i.40 1 2007 F < 2.I _.31E-06 1 UCi/g Fd 1 257.61 1 gwet 1FD5/02/06 11:00 'r /19/06171800 1 Sec i U __' I No-LA-140 1 2007 1 < 1 1 3.19E-07 I uci/g F 1 257.61 1 g wet 105/02/06 11:00 1 .05/19/061 1800 1 .Sec I u] : 1 No CE-141 1 2007 1 < F _ 4.04E-07 I uci/g: I _ 1 257.61 I gwet 105/02/0611:00 1 05/19/061.

1800 1 See I U V" I 'No 1 CE-_44__ 2007 IIE F _ 1.31E-06 uci/g.. 1 1 257.61 I gwet 105/02/0611:00 IF 05/19/061 1800 1 Sec 1T U I I No I_____ 1 2007 1 1.45E-05 I 4.86E3-07 Fr _ _ 1 Udi/g 1 257.61 I gwet 105/02/06 11:00 F 05/19/06 1800 1 Sec .1, IYes I Flag Values U "=' Compound/Analyte not detected or lessythan 3 sigma No =Peak~not identifiedin gamma spectrum+- Activity, concentration exceeds MDC and 3 sigma'; peakidentified(gamma only) Yes = Peak identified in gamma spectrum U* = Compound/Analyte not detected.

Peak notidentifled, but forced activity concentration exceeds MDC and 3 sigma Results. are reported on an as.received basis High = Activity concentration exceeds customer reporting value unless otherwise noted Sper = MDC exceeds customer technical specification:

L = Low recovery MDCG- Minimum Detectable Concentration H High recovery Page 7 of 16 Bolded teXt.indicates ,reportable.

value..

Report alysis 05/30/06 16:32 L28599 BROWN ENGUINEERING, INC.A Teledyne Technologies Company.Enercon Cory DeWitt EN005-3P6,1-06; Sample ID: W7 Collect Start: 05/02/200611"00 Matrix: Solids (SD)Station:'.

Collect Stop: Volume:

Description:

Receive Date: 05/10/2006

% Moisture:.LIMS Number:: L28599-4 I ciiy Uncertait Run! Aliquot Aliquot Reference

1Count -Count count E 1Radnuclide .SOP#. Cone 'ina MDC I units :# Volume Units IDate Date Time Units Flag Values EU-154 2007 -8.52E-07 ui0g/ 257.61 g wet 05/02/06 11:00 05/19/06 1800 See U* No RA-226 I 2007 <".1 1 [ 1: 4.48E-06 [ uei/g 1 .257.61 gwet 05/02/06 1 ;:00 1; 05/19/061 1800 1; See I U I I iNO I TIH--228 2007F F 4,57E-07 r 2.50E-07 I I uci/g i 257.6:1 9 g wet. 05/02/06 11:00 1 05/19/061 1800 [ See I + I 1 Yes I TH-232 .2007 1 < F I 1.19E-06 I uci/g 1 1 257.61 1 g wet :105/02/06 11:00 I1 05/19/061 1800 I See .U I No I i.8.6. Se I I. I *N o...Flag Values U Compound/Analytemnot detected or less than 3 sigma+ = Activity concentration exceeds MDC and 3 sigma;Tpeak identified(gamma only): U* = CompoundlAnalyte hot detected, Peaknot identifiedi but.forced activity concentration exceeds MDC and 3 sigma High = Activity concentration exceeds customer-reporting value Spec = MDC. exceeds customer technical, specification L = Low recovery Page 8 of 16 1-1 High recovery.Bolded text i.ndicates reportable~value..

No =.Peak not,identifiedin gamma spectrum Yes = Peak identified in gamma spectrum: Results are reported on an.as received basis unless otherwise noted MDC -Minimum Detectable Concentration Report. O aly 'is. j TELEDYNE @0530 1....... BROWN ENGINEERING, INC.A Tuiadyne Technologies.Company L28599 Enercon Cory DeWitt ENO05-3P61-06 Sample ID: W8 Collect Start: 05/021200611:30 Matrix: Solids (SD)Collect Stop: Volume:

Description:

Receive hate: 05110/2006

% Moisture: LIMS Number: L28599-5.....u ...e .Activity lUnertainty i Run Aliquot .AliquotI Reference I Count. Count Count.RadionuclideSOP#

Cone j 2 Sigma MDC j Units it Volume Units Date Date T Time Units Flag Values C-14 " 032-80 .1.65E-06 5.55E'07-F

.. ... I uci/g " I 2.0802 0 gwet _ _ __ 5/27/061 50 f M F F F 1I-I-3 2003 :1 1.47E,-04 2.56E-068 1 " ......_ uci/g:. " 1" .2.0802 g wet '1.... 1 05/27/061 50 1 M i + F -F -BE-7 2007:1 1 1__2.23E-06 I uci/g 1 229.23 1gwt 105/02/0611:301 05/1I9/06 1501 Sec F U No .1 K-40 1 2007 1i 6.31E-06 1 1,87E-06.

F _ I uci/g !229.23. ' gwet 05/02/06 11:30 P05/19/06!

1501 1 -Sec +CR-51 2007 1 6 "06 1 .870 2.76E06 i uci/g I I 229.23 gwet 105/02/06 11:30 1 05/19/061 1501 1 See -U _ .No I fMN=54__ .... ....... 1' 2007 " 2 <. .1 .....____ 3.42E-07 I uci/g F ___ 229.23' 1 105/02/06 11230 1 05/19/06!

1501 1 Sec r.1 __ [ 1Nol1 CO-57 ..... 1 2007 T < .I 2 { 4.39E-07 I uci/g 1 1 229.23 gwet 105/02/06 11:30 1 05/19/061 1501 1 See t U* I [No I 0N-58 1 2007 .<. < ....... 13,88E-07 I uci/g 1 229.23 F gwet. 105/02/06 11:30 1 05/19/06 1501 1 See VLlI I No I FE-59 7 2007 4"< F l_ I6.66E-07 1 uci/g I1 1 229.23 1 g wet 105/02/06 11:30 1 05119/06.1.

1501 1 See I...I No I:CO-60 1 2007 12.33E-06 2.59E-07 < 388E07 I uci/g l. F 229.23 1 gwet 105/02/06 11:30 1 05/19/061 1501 1 See. I No ' _ ,Ys1-CN--60' ___ _ 2007'ý < 2 .33E-0 6 1F23E-06 1 2uci/g _I 229.23 I g wet 105/02/06 11:30 F 05/19/06!

1501 1 Sec I +*I_.,, VNOT NB-94 2007 1 < F .........

2.88E-07 1 uci/g 1 _ F 229.23. 1 gwet 105/02/06 11:30 F 05/19/061 1501 Se [U .1 No .*_NB-95 i_ 2007 _ < 1_ 1: 3.68E-07 1 uci/g F T__2_2F 229.23 g wet ,05/02/06 11:30 .1.05/19/061 1501 Sec I U NoV 1 ZIN-95 1 2007 1 < 1 _ _ 5;93E-07 2 uci/g __ 1 229.23, = g wet 105/02/06 11:30 1 05/19/06!

1501 See I U TN' -MO-99 2007 i < 1 .__ .1.49E-04 i uci/g r F 229.23 I g wet 1 05/02/06 11:30 J 05/19/061 1501 1 Sec [.U '_ ..No l U-103._ 1 2007 1 .... < I "_ .l: 2.94E-07 1 uci/g F F 229.23 :1. g wet 105/02/06.11:30 1 05/191061 i50i 1 See I U _ .1 No I RU-I06 1" 2007 ' < l 1 2.44E-06 [ uci/g 1 1 229.23 I gwet 105/02/06 11:30 F 05/19/061 1.501 1 Sec I U _ ._No I_RUG-II0M3_

2007 1i 2.94&07" 1 -1 229.23 1 gwet 105/02/06 11:30 T1 05/19/061_!50i_

See tFUF___ _ _No_RU _________

2007 .< 1: .2.4406-0 1 uci/g F .229.23 &~wet 1 05/02/ 06 1 1:30 1 05/19/061 1501 1 Sec UT 1_ .1 No 1 SB-124 21.007 1 < I 28 307E-07 1 uci/g F F 229.23 1 g wet 105/02/06 11:30 1 05/19/061 1501 1 Sec IU U" __ I No 1 SB-125 1 20071 < Z .1 5.62E007 1 uci/g F 1 _ 229.23 1 gwet 105/02/06:11:30 1 05/19/061 1501 1 Sec U I I1 No I 1-131 1 2007 1 < 12h I9.8E-07 1 uci/g I _ 229.23 I g.wet 105/02/06 11:30 ' 05119)/061 1501 1 Sec .i-U iI No 1 1CS-134 2007 < 9 _ 2.70E-07 i uci/gI _.6/ r 229.23 1 gwet 105/02/06,11:30 1 05/19/061 1501 1 See U I I No .1 CS-137 .2007 1 < I I 3.OE-07 i uci/g I F 229.23 1 'gwet 1:05/02/06 11:30 1 05/19/0.61 1501 I See I U I I No-BA-140. ". 2007 i < 1 2.26E-06, I uci/g ! 229.23 i gwet 1%05/02/06.1:30 1 05/19/06i 1501 1 See 1 FU I .... 1No. I ,LA_140. " 1_ _ 2007 1 < IF _ 2.78E&07 jl' uci/g 1 " 229.23 1 gwet 1:05/02/06;11:30 j 05/19/061 1501 "1 se U I I No 1 C1-141 12007 I < 1. i 3.93E-07 1 uci/g I 1 :229.23" 1 gwet 105/02/06.1:1:30 1 05/19/06 1501 1 S1ec r __o _ 1 No 1 CE-14 *! 2007 1 < 1 _ 1.34E-06 I: uci/g. J 1 229.23. 1 gwet 105/02/06:11:301 05/19/061 1501 1. Sec Iu U I No[EU"152 "__1 2007 1 8.51E-06 I 5.11E-07 1 uci/g 2 F229.23 1 .gwet 105/02/06 11:30 1 05/19/066 1501 F. See ____ i+ ;i-s__I ____ .....__ 1 .....__ I ... .I: IIIi.... ...iI"II ...... .III ....i....Iii I ..] [ _ _ __]..i......

.I, .1 .Flag Values U = Compound/Analyte not detected or less than 3 sigma No Peak not~identified in gamma spectrum+ = Activity concentration exceeds.MDC and,3 ýsigma; peak identified(gamma only) Yes =Peak.identified in gamma spectrum U* = Compound/Analyte not detected.

Peaknot identified, but forced activity concentration exceeds MDC and 3 sigma

• Results are reported on anas received basis High = Activity concentration exceedsecustomer teporting value, unless otherwisenoted Spec =F MDC exceeds customer technical specification, L = Low recovery MDC -Minimum Detectable Concentration U-I High recovery Page 9 of 16 Bolded text indicates.

repoltable value.

Report #9 nalysis 05/30/06 16:32 L28599 Enercon ENOQ,5-3.P6 1-06 0 BROWN ENGINEERING, INC.A Teledyne Teohnalogies Company Cory DeWitt.Sample ID: W8 Collect Start: 05/02/2006 11:30 Matrix:. Solids. (SD)Station: Coliect.Stop:

Volume:

Description:

Receive Date: 05/10/2006

% Moisture:;

LIMS Number: L28599-5:.1Activity Y Uncertainty Run Aliquot Aliquot. Reference Count Count, Count.Radionuclide SOP# " Cone 2 Sigma MDC Units i .Volume Units Date Date Time Units Flag Values EU-!54 2007 < 8.83E-07 uci/g 229.23 gwet 05/02/06 11:30 05/19/06 1501 ýSec U*P: No RA-226 2007 .! < '" i47 1;0 c/ : ..1...229.23

] gw t: *1: 05/02/06 i1t:30 [ ý05/19/06i

.. 1501 i See" I U ] No I..... .....8 2007 '150 1 Se I U ..I .... .I..TI-i-228 20073I .51.E-07 I uci/g I 229.23 1 g wet 105/02/06 11:30 0 05/19/06.

1501 I Sec U 1 1 YO Vm222007 j < 1.32E-06 uig29.3 1g~wet 1,05/02/06 11:30 1 L05/19/06i 1501 1 See 1 1. U, No Flag Values U -Compound/Analyte not detected oruless than.3 sigma+ = Activity concentration exceeds MDC and'3 sigma; peak identified(gamma only)U* = Compound/Analyte.not detected.

Peak not identified, but forced! activity concentration exceeds MDC and 3 sigma High Activity concentration.exceeds .customer reporting value Spec. = MDC exceeds customer technical specification L = Low recovery Page 10. of 16 1- :High recovery Bol.ded text indicates reportable value.No. = Peak not identified in gamma spectrum Yes. = Peak identified in gamma spectrum* Results are reported on an-as received basis unless otherwise noted M.DC " Minimrurm.Detectable Concentration Repeot 1 naysis TELEDYNE 0"05130/06 16:32 BROWN ENGINEERING, INC.A Teledyne Technulogies Company L28599 Enercon Cory DeWitt EN005-3P61-06 Sample ID: .W9 CollectStart:

05/02/2006:12:30.

Matrix:. Solids (SD)Station: .Collect3Stop:

Volume:

Description:

Receive Date': 05/10/2006.

% Moisture: LIMS Number: L28599-6.Activity Uncertainty U ' Run Aliquot Aliquot: Reference Count Count. Count Radionuclide SOPff Conc 2 Sigma MDC Units j oUnits Date Date Units Flag Values.. .. ~~on 1 Sig .. .V .. ....olume ,, ,, ae i e U iS C-14 F .032-80 81 1.25E-06 1 6.32E-07 : r uci/g 1.7925 1 g.wet f :1 05/27/061 50 M m + I.H-I-3 2003 1T.23E-04 1 2.57E&06 1 .........

uci/g I 1.7925 g wet F 1: 05/27/061 50 1 M I+ 1 11 BE-7 2007 1 .< _! _. 1.72E-06.

'uci/g 1 1203.66 1 g wet ! 05/02/06 12:30 1: 05/19/061 1800. 1" Sec I U I " I No .K-40 1 2007 T 7.08E-06 i 1.89E-06 _____ uci/g ." 203.66 I g wet 105/02/06 12:30 :1 05/19/061 1800 F Sec I + I 1 Yes I CR-51 1: 2007 ,1 < 1 _ _ 1;90E&06 uci/g 203.66 1 gwet: 1'05/02/06 12:30 [ 05119/061 1800 [ Sec I U .N MN454 .2007 < < 1 _. 2.15E-07 uci/g I1 .1 203.66 1 gwet 105/02/06 12:30 1 05/19/061 1800 1 See I U I No CO-57 .2007 T 1. I l_ 3,02E-07 1 uci/g 1 1 203.66 1 gwet [05/02/06 12:30 :1 05/19/061 1800 1 Sec 'I U* ___"1 No F CO-58 I 2007 T < 2.23E-07 1F ucig .1 1 203.66 1 g wet 105/02/06 1.2:30 1 05/19/061 1800 1 Sec I U I I No ]-FE-59 1 2007 1 < 1 F 4.51E-07 I uci/g I_ 1 .203.66 1 g9wet 105/02/06.12:30 1 05/19/061

'1800 1 sec lu _ 1 No I-CO-60 F 2007 1 9.15E-071 1.50E-07 F ...... F uci/g I 1 203.66 1 g.wet 105/02/06 12:30 1 05/19/06 1800"1 Sec I + I I Yes ZN-65 2007 1 1 1 F 9.04E-07 1. uci/g 1 1 203.66. g wet r05/02/06 12:30. 1 05/19/06[

1800 1 See "1 u* I .No T 1NB 1 94 ;2007, T __ _ I F 1.86E-07 1 .uci/g 1 _ 203.66 1 g:wet 105/02/0612:30, 1 05/19/061 1800 1 Sec t U[ .... UN.I NB-95 2007 _ _ < 1 F 2.60E-07 1 uci/g I. 1 203.66 j gwet 105/02/06.12:30 i 05/19/061 1800 1. See I U 1 .. :1 No[ZR-95 ' " I2007 i _ _ 4.85E-07 i uci/g... t. il 4203.66 I gwet 105/02/06 12:30 1 05/1.9/061 1800 i: Sec I"U __" F Ni MO799 -. 2007 1 < t I1.15E-04

ý. uci/g 1 .203.66 1 gwet !05/02/06 12:30 1 05/19/061 1800 1 See " I _U ___ N .I RU-103 [2007 F < 1 2.26E&07 1 uci/g 1 1 .203.66 1 gwet 105/02/06.12:30 1 05/19/061 1800 1T See I U I tNo_ i ..RU-106 F 2007 F1 < "_ 1 1.69E&66 1 uci/g 1 1 203.66 1 gwet :05/02/06 12:30: 1 05119/061 1800 NoSecl __U INo " AG-I IOM [ 2007 F < 1 F 1.96E-07 I1 uci/g 1 1 203.66[ gwct 105/02106 12:30 1 05/19/061 1800.1 Sec IT U __ No -SB-124 12007 [..... ] .F 2.38E-07 I uci/g 1 1 203,661 g Wet 105/02/06.12;:30.

] 05/19/061 1800 1 See 1u NI S1-125 1 2007 F < 1 5.09-07 ), uci/g I 1 203.66 1 zg wet 105/02/0612:30:

1 051199/06 1800 1 Sec I 1- .No 1-131 2007 1 <_____,1[

7.74E

1 uci/g 1 1 203.66 F gwet 105/02/06 12:30. 1 05/19/061 1800 1 Sec [o NO CS-134 2007 F 1 [ 2,25E-07 uci/g _ 1 203.66 !; gwet F%05/02/06:

12301 05/19/061 1800 1 See iU 1! 1 No -CS-137

• 2007"F < Z F I 1.97E-07 I uci/g. g __ 203.66 1 gwet [:05/02/06.12:30:1 05/19/061 1800 1 Sec, U i I[No I BA-140 12007 < i 6 11E-06 1 uci/g , 203.66. gwet 1:05/02/06:12:30 1 05/19/061 1800 1 Sec ["I _ ":N-0 [-LA-140 1 2007 1 < 1 I 4.03E-07 I uci/g 1. 203.66 :g wet 105/02/06 12:30 1 05/1910611 1800:1 See I U I I__ o I:"._CE-141 1 2007 1 < I 3.17E-07 I uci/g 1 _ : 203.66 1 gwet [:05/02/06 12:30 1 05/19/061 1:800 1 Se1 [WI _ No I CE- 144 1 1 2007 [ < [ 1. F 9.22E-07 uci/g 1 ... 1 203.66 1 gwet [05/02/06 12:301 05/19/061:

1800 1 See I.U I ' I'_ No I EU-152 1 2007 1 5.72E-06 1 3,46E-07 1 1 uci/g 1 :. 1 203.66 F gwet [05/02/06 12:30 1 05/19/061:

1800 1 See I.+ I I Yes__ _ _ _ __ _ _ _ __ _ _ _ FI I ... .._____I_..

......I ... ..........

I .... ..,F I __ __ _ __ '_'_Flag Values U = Compound/Analyte~not detected or less than 3 sigma No = Peak not identified in gamma spectrum+ =. Activity concentration exceeds MDC and 3 sigma; peak identified(gamma only) Yes = Peak identified in gamma spectrum= Compoind/Analyte not detected., Peak not identified, but forcedtactivity concentration exceeds MDC and 3 sigma *** Results are reported on an as received basis High -Activity concentration exceeds customer reporting value unless otherwise noted Spec = MDC exceeds customer techni.al.specification L Low. recovery, Page 1.1 of 16 MDC -Minimum Detectable Concentration H = High.recovery Bolded text indicates reportable value.

Report Analysis 05/30/06 16:32 L28599 Enercon ENO05-3P6,1-06 A , TELEDYNE 0*" 9 BROWN ENGINEERING, INC.A Teledyne Technalogies Company Cory DeWitt Sample ID: W9 Collect Start: 05/02/2006 12:30 Matrix: Solids (SD)Station, Collect Stop: Volume: Description" Receive Date: .05/10/2006

%Moisture:

LIMS Number: L28599-6 Activity Uncertainty.

Run. Aliquot Aliquot Reference Count Count Count Radionuclide SOP# Cone 2 sigma MDC Units # Volume Units Date Date Time Units Flag Values EU-154 2007 < 6.11E-07 uci/g "203.66. ýgwet 05/02/06 12:30 05/19/06 1800: Sec U* No RA-226 1 2007 < 1 '3.55E-06 i uci/g .203.66 I gwet 105/02/06:12:30 I 05/19/061 1800 1 I U I I No I!TH-228 .2007 I 3.88E-07 i 1.93E-07 uci/g I 203,66 gwet 105/02/0612:301 05/19/061 1800 1: Sec I" + '¥' Yes I ITH-232. 2007 < 8I18E-07 i ucilg .203.66 .gwet 105/02/0612:30 1 05/19/061 1800 1 Sec I U I No I Flag Values U .Compotnd/Analyte'not detected or less.than 3 sigma* ÷Activity concentration exceeds MDC and 3 sigma; peak identified(gamma only)*= Compound/Analytenotcdetected, Peak.not identified, butforced aciv ty concentration exceeds MDC and 3 sigma High = Activity concentration exceeds customerreporting value Spec MDC exceeds customer techneial.spedificationh L = Lowrecovery Page 12 of 16:H = High recovery Bulded text indicates reportable value.No = Peak not identified:in gamma spectrum Yes -Peak identified in gamma spectrum****Results are reported on an as received basis:unless otherwise-noted MDC -Minimum Detectable Concentration Report #nnalysis TELEDYNE 0 05/3/06.6:32BROWN ENGINEERING, INC.05/30/06-16-32 A Teledyne Techhologies Company L28599 Enercon Cory DeWitt EN005-3P61-06 Sample ID: W11.0 CollectStart:

05/02/200601:00 Matrix: Solids. (SD)?.Station,:

Collect Stop: Volume: Descriptiont Receive. Date: 05/10/2006

% Moisture: LIMS Number: L28599-7 Activity Uncertainty

.Run Aliquot, Aliqupt Reference count. Count Count: Radionuclide UP Cone 2Sigma MDC [ aUnits VtsR Flog Values...... Volume Units, .Date Date Time: Units lgVle C-.i4 1 032-80 1 1.46E-06F11 4.36E1-07..] " _ _ uci/g __"_ F 2.6671 1 g wet I _05/27/061 50 .M I -I _ _ .H-3 .2003 F 2.52E-040T 2190E.06'

.I f uci/g F F 2.6671 1 gwet I 1 05/27/061.

50 1 M ! +.___ I: BE-7 1"2007 I *< .3.21E06 I.. uci/g FF 251.55 1 g wet 105/02/0601:00 1 05/19/061 1440 1 Sec: 1 1 .N; I...K-40 12007 " < .1.53E&06 I uci!g F F.251.55.

g.wet 105/02/0601:00 1 05/19/06 1440 1 Sec; I U _I I Ysl CR-5i 1 2007 F 1 :3.58E-06 I uci/g i F 251.55 1 gwet 105/02/06 01:005F005119/061 14401 Sec 1 Ul u NoY MN54 12007 < F4.46V-07 1 uci/g 1 251.55 g-wet 1:95/02/06 01:00 F 05/19/061 1440 1 Sec: 1I U. ! No CO-57 I 2007 F < :1 _ 6.05E-07 1 uci/g i 25.1.55 ; g wet 105/02/0601;00 1 051191061 14401 Sec [ U*] _ I No L.CO-58 .2007 F < F_ _ 15,07E-07 1 uci/g. IF 251.55 1 gwet 105/02/0601:00 1 05/19/061:

1440 1 Sec; 11 U L j ] No :1 FE-59 .1 2007 [ < 1 1.. ' 1.01E-06 I uci/g F -1 25.1.55 1 gwet 105/02/0601:00 F 05/19/06 1440 1 Sec .]._U _ I No I.CO-60 1 '.2007 '] .39F.06 3.99E-071

_ _"__" I uci/g F _ F 251.55 1 g~wet 105/02/0601:00 1 05/19/061 1440 1 See IV ..... -Y--ZN-65 1 2007 1 < F& 13 ....... I7 1.77E-06 I uci/g F 1 251.55 1 gwet 105/02/0601:00 1 05/19/061 1440 1 Secý F*. "1__ f--I NB-94 "2007 F < F1 I 3.82E-07 I uci/g 1 .1 251.55 1 g wet 105/02/06 01:00 1 05/19/061 14401 Sec Iul _ I_--NB-95 1 2007 1 < A L _ _ IS.00E-07 I 'uci/g F _ 251.5 I gwet .05/02/06.01:00 F 05/19/06 1440 1'Sec U] 1. No 1 ZR-95 ..I 2007 F < I _ _ I.8.46E-07 I uci/g 1 I 251.55 1 g wet 105/02/06 01:00 F 05/19/061 1440 1 Sec -U _" INo " M3-99 5 2007 F.. < 1 _ _ 12.44E04 i uci/g: __ 1 25)1.55 1 gwet 105/020601.:00 F 05/19/061 1440 1 .Sec [ ]U 1 _ No I RU-103 '2007 I* I 4.42E-07 uci/g 1 251.55 1 gwet 05/02/0601:00.05/19/061 1440 .Sec I U I ._INo-I U-106 1 2007 1_- I I 3.48E-06 i uci/g 1 251.55 1 gwet 105/02/06 01:00 '.05/19/061 440 1 See U I No.AG-10M 2007 < ._ Ii 3.94E-07 I uci/g F F 251.55 1 gwet 105/02/0601:00 05/19/061 1440 1 See I I 1 NoW RSB-124 1 2007 1:< ' _ 4,23E-07 I uci/g F. I 251.551 gwet 105/02/0601:00 F 05/19/061 1440 1 Sec IUI .Nol B-125 ,1 2007 1 <. .1 -I 8.75E-07 I uci/g F F 251.55 I: g wet 105/02/06 01-00 1 05/19/061 1440T1 See I U IT1 No I 1-13:1 2007 1 < .1 1.35E-06 I uci/g _ _ F 251.55 1 gwet 105/02/0601:00 1 05/19/061 1440 1 Sec I U 1 1. NoT CS-134 1" 2007 1 < I 1: 3.64F-07 I uci/g F 1 251.55 1 g wet 1 05/02/06 01:00 [ 05/19/061 1440 1 Se1 No I CS-13M [_ 2007 1 < F !_ 4.23E-07 I uci/g F _ 251.55 1. g.wet 105/02/06 01:00 1 05/19/061 1440 1 See 1 1 No 1.BA-_140 1_2007_ 1 < 1:_ 3.10E-06 1 uci/g _ 1 251.55 " gwet. 105/02/0601:00 1: 05/19/061 1440 I See .UT No I LA-140 I. 2007 ;1 < I _ _ _ 5,16E-071 uci/g F i 25:1.55 1 g wet 105/02106 01:00 1. 05/19/061' 1440 1 Sec I U 1 1lNo I CE-141 1 2007 1 < 1 7 .5.45E-07 I uci/g F 1 251.55 1 gwet 05/02/06 01:00 F105/19/061 14401 Sec l ' I[.LNo C-144 ".... 1...... 2007] <_______ 1 __ 1 1.76E-06 I. uci/g F 251.551 ..gwet..05/02/06 01:00 1 05/19/06 1440 1: Sec I U-I I No EU-152 1. '2007 1 1.75E-05 1 7.31E-07 1 uci/g 1 1 251.55 1 g.wet I 05/02/06 01:00. I 05/19/061 1440 1 Sec 1+ I Yes]T ,. _________________

... I ............ , __, ________ I .... ._______________,___I

..[ ____ I _______ I 7 1 m IIIIIIZ......

.....____ I ..... ,,.".,I,,,ii'i'1,IIIIIi Flag. Values U = Compound/Analyte not-detected or less than 3sigma No, = Peaknot identified in gainmia spectrum+ = Activity concentration

%exceeds MDC and'3:sigma; peak identified(gamma only) Yes. = Peakidentified in gunma spectrum U* = Compound/Analyte not detected.

Peak not identified, but forced activity concentration exceeds MDC and 3 sigma

• Results arereported on an asreceivedbasis High = Activity concentration exceeds.customer reporting value unless otherwise noted Spec = MDC exceeds. customer technical specification L Low recovery MDC -MinimuumDetectable Concentration H = Highrecovery.

Page 13 of 16 Bold-ed text indicates reportable value.

ýReport, O 9 alysis 05/30/06.16:32 L28599 Enercon EN005-3 P61-06TELEDY¥NE 9 BBOWN.ENGINEERING, INC.A Teledyne Technologies Compeny Cory De.itt Sample ID : W Collect'Start:

05102/2006 01:00. Matr -Solids ..(SD)Station: Collect Stop: Volume:

Description:

Receive Date: 05/10/2006

% Moisture: LIMS Number: L2.8599-7.... ........eActivity Uncertainty Run Aliquot'Aliquot Reference "ount Count Count uclideCone 2 Sigma MDC Units 7 Volume Units Date :Date Time Units. Flag Values EU-154 2007 < 1.22E-06 uci/g 251.55 gwet 05/02/06 01:00 05/19/06 1440 Sec, U* No RA-226 ;.2007 < .6.32E-06 I uci/g 1: 251.55 ' gwet I05/0210601:00 I 05/19/061 1440 f Sec : U I [No TH-228 I 2007 6.33E-07 ! 2.65E-07:

I : ucilg 251.55 i gwet [05/02/0601:00 i 05/19/061 14401 Sec " + I Yes1 TH-232 .2007 ' 1.66E-06 ucilg 1 2511.55 I gwet. 105/02/06 01:00 1 05119/061 1440- I Sec I Ui ] No T Flag Values U Compound/Analyte-not detected orless than 3 sigma+ = Activity concentration exceeds MDC and 3 sigma;:peak identified(gamma only)U* = Compound/Analyte not detected.

Peak not identified, but forced activity concentration exceeds MDC and 3 sigma*High = Activity concentration exceeds customer reporting value Spec = MDC exceeds customer technical specification L Low recovery Page 14 of 16 1-1 = High recovery Bolded: text.indicates reportable value..No =Peak not-identified in gammna.spectrumn Yes -Peak identified in gamma spectrum****Results are reported on an as received basis unless otherwise noted MDC -Minimum Detectable Concentration

'Repor 0- -wlysisTE .LEDYNE@0 3Repor6t 0 na2ysis BROWN ENGINLERING, INC..05/30/06 16:32 A Teledyne Technologies Company L28599 Enercon Cory. DeWitt EN005-31P61-06.

Sample ID:ý Wlt CollectStart:

05/02/2006.0130 Matrix: Solids (SD)Stati.on::

Collect Stop4 Volume:

Description:

Receive Date: 05/10/2006

% Moisture: LIMS Number: L28599-8 I Activity lUncertainty I I Run Aliquqt Aliquota[

Reference Count Cout unt Radionuclide SOP# [ :Con f 2 Sigma MDCUnits Time. its Flag Values.C-14 f. 032-80 ;, 9.29BE-06 It 6127B-07 ..... i uci/g I I 2.3037= I g wet _ 05/27/061 50 I M I. + I H-3 12003 "682E-04 T 5,07E-06 1 ...... 1 uci/g Ii ý 2.3037 gwet 1 m05/27/061

.50 1 M V -I ___BE-7 1 2007 ... < ___..... I 8,<0E-06 I ucilg _ 1 271.4 gwet 105/02/06 01:30 1 05/19/061 1200 1 See l l o-_-F--K-40 I---2-007

< t .........

"5.43E-061 1 ucl/g 1 1 271.4 1 gwet 105/02/0601"30 1 05/19/061 1200 1 Sec. IU* I I No , CR-51 1_ 2001 d _ .< :_ _ 8.86E&06 1 -ui/g I -1 271A4 1 gwet 105/02/06 01:30 1 05/19/061 1200 1 Sec, l U " I No I MN-54 1 2007 1 < T I 1.09E-06 1 ucilg. 1 .1 271.A4 gwet 105/02/0601:301 05/19/061 1200 1 See: I U I [N CO-57 _ _ _ 2007 :1. < i _ _ 1.44<-06 1 uci/g 1 1 271.4 1 gwet 105/02/0601:301 05/19/061 1200 1 See I U*1 I No--CO-58_'___

..........

_I 2007 1 < _ 1.22F,-06 1 uci/g 1: [T 271.4 I gwet 105/02/0601:30 1 05/19/061 1200 I Sec I. U I I NoIt FE-59 2007 1.. <. 1 1:_. ..._ 2.61E-06 I uci/g I. I 271.4 1 gwet. I 05/02/06 01:30 1 05/19/061 1200 See I U I NOTI ICO-60 1 2007 A 4.42E,-O5 I L08E-06 I I uci/g -1 1 271.4 1 g wet 105/02/06 01:30 1 05/19/061 1200 Sec I + I Yes I ZN-65 1 2007 .1 < I I 4.,47E-06 1uci/g 7 271.4 1 gwet 105/02/06 01.:30 [ 05/19/061 1200 Sec [ U* I 1No I NB-94 1 2007 __ <_ _ _ I U88619-07 I uci/g _ -- 271.4 gwet 105/02/0601:30 1 .05/19/061 1200 1 Sec V U I No I 1NB-95 1 2007 1__<. ._,__11.17.E-06 1 uci/g F F 271.4 1 gwet 105/02/06 01:30 F 05/19/06 1200 *I See. I U i."No ...ZR-95 1 2007 1 < F _ _ 2.19E-06 1 uci/g " F 271.4 1 g wet 105/02/06 01:30 F 05/19/061 1200 1 Sec IUI 1 No I MO-99 1 2007 1 < 1I 1 5.80E-04 l uci/g [1 271.4 1 gwet 105/02/06 01:30 1 05/19/061 1200 1 Sec I U i I.No I"RU-103 1 2007 1 .< J _ _ 1.03E:06 1 uci/g F F 271.4 g wet 105/02/06 01:30 [ 05/19/061 1200 1 Sec I U I No I RIU-.106 .2007 1 < ' _- 8.331 -06 1 uci/g [1 271.4 1, ' gwet I05/02/06 01:30 1 05/1.9/06 1200 T Sec U _ 1TN1 AG-I IOM 1 2007 1 < 1 1. 9,41E-07 1 uci/g I I 271.4 1 gw vet 05/02!0601:30 F 05/19/061

.1200 1 Sec I-U I NoI SB-124 .2007 1 < l t 9.729-07 1 uci/g *F 271.4 1 gwet 105/02/0601300 05/19/06 12QO 1 sec U "l Noo1 SB-125 2007 '1 .< _ _ __ 2,06E-06 T uci/g F 271.4 I giWet 105/02/0601:30

.05/19/061 1200 Sec VW U ____ No i 1-131 1 2007 i1 < I ...... 1 3.42E-06 I uci/g f 271.41 gwet 105/02/06 01:30 05/19/061 1200 1 .Set 1U. ',,1 1 No]I CS-134 1! 2007 1 < F .8.16E-07 I uci/g I 271.4 11 gwet 105/02/0601:30 1 05/19/061 1200 1 Sec 'U F7 I.1CS-137 1"2007 91 < 6 _ _ 9,75E-07 1 uci/g " 271.4 I gwet 105/02/06:01:30 F 05/19/06i 1200 1 Sec I U I lNo I 1BA-140 1 2007 1 < I 7.581&06 1 uci/g I 271.4 1 .gwet 105/02/06 01:30 1 05/19/061 1200. 1 See 1 U l1 No1 CE-140 1 2007 I < _ _ 1 ý1.02E-06 T uci/g 1 .271.4 1 , gwet 105/02/0601:3.0 1 05/19/061 1200 1 Sec IU-l ' NoI C-141 1 20071 < I

• I 1.341E-06 I uci/g 1 1 271.4 I gwet. 105/02/06 01:30 1 05/19/06 1200 1 Sec F U _... I No, I1 2007 ' < 11 1 4.18E-06 I uci/g I11 271.4 1 g'wet 1,05/02/06:01:30.

1 05/19/061 1200 1 See I U 1 No I EIJ-152 1 2007 1 1.291E-04 1 2.85E-06 1 _ _ uci/g 1 271.4 1 gwet 105/02/06 01:30 1 05/.19/061 1200 F See ]+ I !I-Yes--Flag Values U -Compound/Analyte not detected or less than 3 sigma No = Peak not identified in gamma spectrum+ = Activity concentration exceeds MOC and 3 sigma' peak identified(gamma only) Yes -=Peak identified in gamma spectrum U* = Compound/Analyte not detected, Peaknot identified, but forced:activity concentration exceeds MDC and 3 sigma

• Results arereportedonman as receiyedbasis High -Activityconcentration exceeds.custorner reporting value unless otherwise noted Spec -.MDC exceeds custonier technical specification L = Low recoveryr MDC -Minimum.DetectableConcentration 1 = High rccovery Page, 15 of 16 Bolded text indicates reportable value.

0 Report *knalysis 05/-30/0616:32 L28.599 Enercon.EN005-3P617-06,TELEDYNE

@BROWN ENGINEERING, INC.A Teledyne Technologies Company Cory DeWitt, Sample ID: WI .Collect Start: 05/02/2006 01:30 Matrix: Solids (SD);: D Station: Collect Stop: Volume: Description.-

Receive Date: 05/10/2006

% Moisture;LIMS.Number:

L28599-8 1Activity

!Uncertainty IR4un Aliquo Aliquot I Reference Count Count Count Radionuclide SOP Conc 2Sigma I MDC Units j N Volume o Date Time Units Flag Values.... ....... 1 .._ _ 1 EU-154 2007 < 2.89EA06 uci/g 271.4 -g wet 05/0210601.:30 05/19/06 1200 Sec U* No RA-226 2007 I I .5oE-05 uci/g .. I 271.A4 g.wet 105/0210601:30

] 05119/061 1200 1 Sec: I U I I No I.TH-228 2007 I < I 1.27E-06 uci/g 1 1 271.4. 1 .g.wet "f05/02/06:01:.30 1 05/19/061, 1200 1 See : U I No I ITHT1232 2007 < 1 3.97E-06 I uci/g -1 271.4 1 gwet 105/02/06 01:30 1 05/19/061 1200 1 See I U I I No I Flag Values U = Compound/Analyte not detected.or less than 3 sigma+ = Activity concentration exceeds MDC and 3 sigma; peak identified(gamnma only)U* = Compound/Analyte not detected.

Peak.not identified,.but forced: activity.concentration exceeds MDC and'3 sigma High = Activity concentration exceeds customer reporting value Spec MDC exceeds customer technical specification L -Low recovery: H = H-ligh recovery Page 16 of 16 Bolded .text indicates repo!rtable value.No, = Peak not identified in gamma spectrum Yes =Peak: identified in gammawspectrurn

• Results arereported on an as rcceivedwbasls unless otherwise noted MDC -Minimum Detectable.Concentration Services, Inc.)~g~ C~ j9~Chain of Custody Record Laboratory COntact P Corey Dewitt. Date: 59/2006 COC No: 0004 Laborator Contact...

T Dwit Site Dan Jordan Dae Name:, Teledyne'Brown Engineering Tel/Fax: 724-733.8711:

Lab Contact: Rebecca Charles Carrier FedEx Page I of I Address: SapeRciigAnalysis Turnaround Time JbN 09 2508 Quality Lane 0 Other. (Specify)i days Xnoxville:TN3.7931 "300Daye S _ __o.Phone:

021 Days: SDQNo., FAX. 14 Days: a , Project: VUnversityyofWaahiington 7 Days P0#:" MCILVI0I1

-z;Sample Sample Sample: "of 1~~Sample Identification Date Time *Type Matrix coot , L Sample SpeificNotes:

W4 511/2006 9:30 AM Concrete Solid 1. X x .x x x .x x :NI W5 5/2/2006 10:00 AM Concrete Solid 1 x x x x N W6 5/2=2006 10:30,AM Concrete Solid I x x x N W7 5/2/2006 111:00 AM Concrete Solid 1 X x x I x N _X IN V8 5/V/2006 11:30AM Concrete Solid 1 ,x x xxx *. N W9 5/2/2006 12:M0.PM Concrete Solid .1 X X X xx X N W10 51212006 1:00AM Concrete Solid 1 x x x X X N I Wit 5/2/2006 1:30 AM Concrete Solid 1 N I Preservation Used. I. = Ice, 2= HCl, 3=1004, 4=100340, 5NaO1, 6= Other =, N-None , Possible HazardIdentaficaton. .le .posalf fee y be assess iwn are rtetaindi h an I nmonth)[O.Non-Hazard

.3 Flammable 0 skin inlrritant 03 Poison 8 0 Unknown 13 Return to CIent EM Dlsposal by Lab 21 Archlve fbr 30 Months / Weeks / XDays (circle one).Special.Iaistructions/QCRequlrements

& Comments:

Email results toDan Jordanatdjordsn@enacon.coim.

Phone 804-384-8081.

BillProject.using thistCOC.as arefereioe.

Enerconbilling.contact is CoreyDowitt at edewitt@eneicon.com Phone 724-733-8711.

Relinqoished by: Dan Jordan Company:.

non Date/Time:

19-06 Rceiyed y:, Company: Il Date/Time:

_ 4,0OPM "v" b Y,,j .4 /o 6C(_ /__I.. 0 Relinqaished by: Company-.

DatelTime:

Received by: Company: Date/Time:.

Relinquished

by: Company: jDate/Time:.

Recived by: Company: Date/lTimc:

University of Washington More Hall Annex D&D, Project 10492 Attachment 41 -Final Bioshield Analysis for Hard to Detect Radionuclides UW-MCP-OP-13, Rev. 2 Co/Eu to Hard-to-Detect Nuclide Ratio Analysis Regulatory Guide 1.86 Criteria Removable 0-y ' Co/Eu Total H-3 Total dpm/100cm 2 dpm/1OOcm2 dpmrrlOOcm2 1000 5000 5000 Reduced Total Criteria Reduced -y f Derived H-3 dpm/1O0cmM2 dpm/1OOcm2 Unity Value__ '....7 ____ 3160 0.97 Reduced Removable Criteria Removable P-y Derived H-3 dpm/100cm2 dprn/m00cm2 Unity Value 34PO~>~ 632 0.97 HTD Sample Analysis Ratio T HTD to Co/Eu (pCi/g) HTD (pCi/g) Co/Euo Co-60 Eu-152 Eu-154 H-3 C-14 Ratio 1.06E+00 3.62E+00 nd 8.70E+00 nd 1.86>

Report, of.Analysis AV'rTELEDYNE Re o A a BROWN ENGINEERING,INC.

12/0.1/06 16:13 ATodyoThatnologios Company L30509 Enercon Cory DeWitt ENOO5-3EREG,-06A Sample: D: 'W13. Collect Start: 1.1/08/2006 M7M.30 Matrix: ,Solids (SD)Station: Collect Stop: Volume:, Desctiptionw; ReceivoDate;I 1.1/16/2006.

% Moisture: LIMS Number. L30509-14 Activity Uncertainty IRun 1 Aliquot fAllqtsot Reference jCount Count Count Radionuclide Sop# Coup 2Signa MDC Units , Vole, units Date Date ime Units Flag Values C-14 20031 < I 7..... '9.38E-01 1 pCl/g 1 517033 F gwet 1 ___ .... 112/01/061 101 M' VUi.Speo.H-3 F 2003 1 8.7066+001 i.01E+00 I I pCl/g [. 5.7033 F gweti. 1 1 12101/061 10 1 M 1 + I BE-7 I 2007 I < I _ 3,21E-01 1 pCi/g I [ 414.37 1 g dry 111/08/06.17:301 1fI/28/061 23400 1 See U I I NoF K-40 1 2007 1 4.54B.+00 f 4.36E-013

-.... I pCVg. I 1 44137 F gdry 111/08/0617:30 Se11/28/06 234001 Sec I + .I Yes F'TCR-51 2007 F < I I 4.10E.01 I pCilg I 1 414.37 F gdry 11/08/06 17:30]1 11/28/061 23400 1 Se I U" INo I MN-54 4 2007 F < I _ F3.56Eý02 I pCi/g 1 : .41437 1 g dry 111/08106 17.30 1 11/28/061 23400: Seo U1V [NF CO-57 1 2007 F < _ _ I 7,19E-02 i pCilg ." 414.37 1 -gd.. 1108106 17:30 1 1/28/061 23400 1 Se I'U* I I No CO-58 F 2007 F < I__ 1.3.94&02 F pCl/g 1 i1 414.37- 1 g dry 111/08/06 17:30 1 11/28/061 23400 1 se§ I U I 1i T: FE-59 F 2007 F < I "I fl18.44 -02 F pCi/g .1 1 414.37 1 gdry 111/08/0617:30 1 11/28/061 23400 :1 See I U I l INo CO-60 1 2007 1 1.06E+00 1 4,011E-02 I 1F pCi/g I 1I 414,37 1 gdry 111108/06 1730 1 11/28/061 23400. 1 See. I+! Yesl ZN-65 I 2007 1 < F .I 8.351-02:

F pCi/g 1 1: 414.37 1 g dry 111/08/06 17:30 1 11/28/061 23400 1 Sec I U I j NoI NB-94 1 2007 1 < F 1__ .19%-02 I pC/g 1 1. 414.37 1 gdry 1I1/08/06 17:301 I 11/28/061 23400 1. Sec lU- 1 No I NB-95 1 2007 1 < F I 4.19E-02 F pCvg 1i1 414.37 I dry 111/08/06 17:30 1 11/28/061 23400: 1 Sec I I NO I ZR-95; 1 2007 1 <1 I 7.251E-02 1 pCi/g .1 1F 414.37 dryf 11/08/06 17:301 11/28/061 23400. 1 Sec 1 'No Iol.MO-99 1 .2007 <: F _ I 3.691+01 1 pClg 1 F 414.37 1 gdry 11/08/06 1730 1 11/28/061, 23400' I See i1U :1 io RU-103 1 2007 1 < I I 4.13r1-02 I pCvg. 1i 414.37 1 gdry 1111/0806 17:30 1 1.1/281061 23400 1 See. IU-I .rNoI RU106 :2007 .. 6< 1 1 3,06E-01 .pCi/g 1 F 414.37 1 gdry 111/08/06 17:30 1 11/28/061.

23400 1 Sec I"U I I No I AG-I104M 1 2007 1 < 1 1"3.41E -02 1 pCi/g 1 1 414.37 1 g dry 111/08/0617:30.

1 11/281061 23400 1 See I 'I i7 No I SB-124 1 2007 1 < I I1 3.58E-02 pCi/g :1 1 414.37 1 gddry 111/08/06 1730 F 11/28/061 23400'1 U I i No l SB-125 12007 1 4 1 8.65E-02 1.pCi/g 1 414.37 1 gdry 111/08/06 1.7:30 1 11/28/061 23400 1 Seod ITUI 1 I NoI 1-131 1 2007 1 < '1 "_ 1 1.59E-.01 1 pCig. 11 414.37 1 gdr T11/08/0617:30 F 11/28/061 23400 F See I U I I No CS-134 1 2007 1 < 1 1 2.89E,-02 1 pCvg 1 1 414.37 1 gdry 111/08/06 17:30 1 .1/28/061 23400 1' Sec I U"'I I No CS-137 1 2007 1 < 1.7 1 73.54F-,02 I pCi/g 1 I 414.37 1 g dry I 11/08!06 17:301 IF1/28/061 234001 See. IU I Spec'I No I BA-140 [ 2007 1 <. ..... 1 315E_-01 I pCiig 1. 1 1 414.37 1 g.dry 111/08/06 17130 F 11/28/061.

23400 F Sec .. U I INo LA-140 1 2007 1 < 1 1 96.835-02.

I pCi/g 1 1: 414.37 1 :g dry. 111/08/06 17:30 1 11/28/061, 23400 F Sa I uI I No I CE-141 1 2007 1 < I _ 1 7.731-02.

I pCi/g 1 1. 414.37 1 gdry 111/08/06 17:30 111/28/06:

23400 1 Sec I U I I.No CE-i44 1 2007 1 < 1 I 236E-01. 1 pCi/g 1I. 414.37 1 g dry 111/08/06 17:30 1 H/28/061 23400 f Sec I U I I NoFI EU-152 I .2007 1 3.621E+001 1.41E-01:

I I pCivg 1 1 414.37 1 gdry 111/08/06 17:30 1 11/28/061 23400 1 Sec F FF IYs FlagValuesI

.......I...... ...U 1 Compound/Analyte not detected or less Ihan 3.sigma. No Peak not identified in gamma spectrum+: -Activity concentration exceeds MDC and 3 sigma; peak identified(gainma only) Yes =Peak ideotilied in gamma spectrum U* -Compound/Analyte not detected. .Peak not identified,.but forced activity concentration exceeds MDC and 3 sigma

• Results are reported on ti as received.basis High -Activity~concentration exceedscustomer reporting value unless otherwise noted Spec = MDCexceeds customer technical specificaltin L -Lowrecovery MDC -Minimum Detectable Concentration H gb eish:Pcovefy Page I of 2 Bolded: text indicates reportable value.

0 Report of Analysis 12101106 16:13 L30509 Enercon ENOO5-3ERIEG-06A.

.!b TELEDYNE BROWN ENGINEERING, INC.ATI odyno Taotntologies Company Cory DeWitt Sample oU; W13 CollectStart

11/08/2006 17

30 Matrix:. Solids (SD)Station:.

Collect Stop: Volume: Descrption, .Receive Date: 11/16/2006

% Moisture:.

LIMS Number: L30509-.1 Activity Sne: i iga Mt Run Aliquot Aliquot Reference

'Count: T Count.Radionuci.deSti U ttCtlns Date Time Units UFlag Values EU-t54 2007 LZ"E-01 pCi/g 414.37 gdry 11/08/06 17:30 11/28/06 23400 Sec U* No R226 < 07 7.69E-01 I pCi/g 1 1 414.37 11 dr 111/616/9:

0:30 I11/8/6 .240 1 Sec I U I I Yes 2TH-228 I 207 I 6.48ro1.,1 5.i0E-02 I [ pCi/g I I 414.37 1 gdry 111/08/0617:30 1 .11/28/061 23409 I See I + I I YesI TH-232 .1.2007 [ 5,471-01 .. 8.63E-02 1 I pClg 1 1 414.37 I gdry I 11108/061.7:30 I. il/28/061 23400 1 Sec " I + I Yes I Flag Values U Compound/Analyte not detected or less than 3 sigma+ Activitylconcentration exceeds MDC and 3 sigma; peak identilied(gamma only)U* Compound/Analyte not detected.

Peak not identified, but forced activity concentration exceeds MDC and 3sigma High = Activity oncenttatlon exceeds-custormer reportinglyalue Spec MDC exceeds customer technicat specification.

L. Low recovery,Page 2 of 2 H = High recoVery B.eolded text indicates reportable value.No -Peak not identified in ganuna spectrum Yes -.Peak identified in gamma spectrum* Results am teported on an as received basis unless otherwise noted MDC -Minimum Detectable Concentratlon University of Washington More Hall Annex D&D, Project 10492 Attachment 42 -Summary of Air Sample Results UW-MCP-OP-13, Rev. 2 Summary of Air Sample Results University of Washington Nuclear Reactor D&D Breathing Zone Air Samples DAC Alpha 7.OOE-12 Beta 8.00E-09 Alpha Average 1.09E-13%DAC= 2%Beta Average 7.89E-1 1 Max 6.39E-13 9%Max 4.80E-10 6%%DAC=1%General Area Air Samples DAC Alpha 7.00E-12 Beta 8.00E-09 Alpha Average 2.97E-14% DAC= 0%Beta Average 3.75E-1 1 Mx 1.51E-12 22%MaxI 4.72E-09 59%%DAC= I 0%Notes: " All values listed in pCi/ml" DAC values derived from 10CFR20 Appendix B Table 1, Column 3.DAC Relation to ALl The derived air concentration (DAC) values are derived limits intended to control chronic occupational exposures.

The relationship between the DAC and the ALl is given by: DAC=ALI(in pCi)/(2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> per working year x 60 minutes/hour x 2 x 104 ml per minute)=[ALI/2.4x1 09] pCi/ml, where 2x1 04 ml is the volume of air breathed per minute at work by "Reference Man" under working conditions of "light work." (10 CFR 20 Appendix B, pg 357, January 2006)In other words, a worker must breathe an air concentration at a level of 10% of the DAC for 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> to receive 10% of the ALl for a given nuclide.