ML102300557

E-mail Dated August 11, 2010, from David Sokolsky, Pg&E, to John Hickman, NRC, Regarding NRC Questions on Humboldt Bay 20.2002 Request Including Radiological Characterization Report

ML102300557
Person / Time
Site:	Humboldt Bay
Issue date:	08/11/2010
From:	Sokolsky D Pacific Gas & Electric Co
To:	John Hickman NRC/FSME
References
Download: ML102300557 (64)

Text

Hickman, John From: Sokolsky, David [DDS2@PGE.COM]

Sent: Wednesday, August 11, 2010 5:36 PM To: Hickman, John Cc: Roller, Paul James; Newey, John; Albers, John P; Baldwin, Thomas (DCPP); Rod, Kerry; Snyder, Robert A; Chad Hyslop; Griffin, John J

Subject:

HBPP RESPONSE TO QUESTION 1 Attachments: 20100811140207.pdf Follow Up Flag: Follow Up Flag Status: Flagged

John, The attached file is the Radiological Characterization Report developed for HBPP by Enercon, dated November 21, 2008, and responds to NRC Question 1 (concentrations expected in the waste) from your July 16, 2010 email to me, as discussed during our July 29, 2010 public meeting for the HBPP Alternate Disposal Exemption Request dated April 1, 2010.

In particular, reference to GEL laboratory reports are contained in Table 4-7 (page 40) and Table 4-9 (page 46).

It should be noted that surveys of highly impacted areas (much of Unit

3) do not apply to waste to be shipped under the exemption request.

Also, positive gross alpha results for Units I and 2 are naturally occurring nuclides in materials or lead paint.

GEL results for fuel oil tank waste (previously shipped as non-radioactive) show this is the case. The contamination of the above ground structures of Unitsl/2 occurred from gaseous decay of Xe-1 37 to Cs-1 37 released from Unit 3 during operations from 1963 to 1976.

This is the final email that responds to NRC questions. Previous emails responded to NRC Questions 3, 5 and

6. PG&E will respond to NRC Question 9 in a letter submittal shortly. NRC Questions 2, 4, 7 and 8 were resolved during the July 29 public meeting.

David Sokolsky Supervisor of Licensing Humboldt Bay Power Plant (707)444-0801 office (707)601-6703 cell

RADIOLOGICAL CHARACTERIZATION REPORT HUMBOLDT BAY POWER PLANT EUREKA, CALIFORNIA Prepared for Pacific Gas & Ilectrlc Company Humboldt Bay Power Plant 1000 Ki-g Sahnon Avornue Eureka, California 95503 Prepared by BNERCON 4490 Old William Penn Hwy Murrysville, Pennsylvania 15668 IEBPP-RPT-001 Rievlsion 1 November 21, 2008

RADIOLOGICAL CHARACTERIZATION REPORT HUIMBOLDT BAY POWER PLANT E-UREI(A, CALIFORNIA HIBPP-RPT-OO1 Revision 1 ENERCON Services, Inc.

Prepared by:

/A 01 Dustin G. Mille r,.Meadl i Physicist A

Date:

/"t Approved by:

Gerald F. Williams, Project Manager

Humboldt Bay Power Plant Characterization Report Table of Contents List of Tables ................................................................................................................................................ ii List of Figures .............................................................................................................................................. iii List of A ppendiCes ....................................................................................................................................... iv List of Acronym s and A bbreviations ............................................................................................................ v 1.0 Introduclion ............................................................................................................................................. I 1.1 Project Background ............................................................................................................................. I 1.2 Purposo and Scope ............................................................................................................................... 1 1.3 Sum m ary of Technical A pproach ................................................................................................... 3 1.3.1 Survey Design ............................................................... 4 1.3.2 Training and Q ualilicalions ....................................................................................................... 5 1.3.3 Field Activities ..........-.... ....... .................. ............. .................... ..................... 5 1.3.4 Sam ple Analysis ........................................................................................................................... 6 1.35 Analytical Q uality A ssurance and Q uality Control .............................................................. 10 1.3.6 Data M anagem ent ............................................................................................................... I.I 2.0 Investigation Tasks .......................................................................................................................... 12 2.1 utilding and Structure Surveys ................................................................................................. 12 2.2 Gumma Radiation Walkover Survey ...... I........... ....... ... ........ ...... ......12 2.3 Railroad Spur Drain Geophysical Surveys ............................................. 13 2.4 Surface Soil Sam pling ...................................................................................................................... 13 2.5 Sedimcnt Sam pling ........................................................................................................................... 13 2.6 H and A uger Sam pling ......... ..................................................................................... 13 21 7 Radiological D eep V ertical Bores ............................................................................................... 14 3.0 Data Evaluation ..................................................................................................................................... 15 3.1 Background Radionuclide M easurem ents ............................................................................... .... 15 3.2 Radiological M easurem ents In the 11B3PP SIudy Area ................................................................. 16 4.0 Sum m ary of Results ............................................................................................................................. 20 4.1 Impacted A reas ................................................................................................................................. 20 4.1.1 (Class I A reas .............................................................................................................................. 22 4.1.2 Class 2 Areas ............................................................................................................................. 32 4.1.3 Class 3 Areas ............................................................................................................................... 43 5.0 Conclusions ..... ....... ........ .......... .................... .......................................................... 47 6.0 References .................................................................... ......... ............................................... 48 HBPP-RPT-O01 i

Report HBPP-RPT-001 Number:

RADIOLOGICAL CHARACTERIZATION REPORT FOR HUMBOLDT BAY POWER PLANT Status Rev. Dale Prepared By Pages Description of Changes No.

Final 1 11/22108 Dustin G.Millcr 48 Original Issue

Humboldt Bay Power Plant Characterization Report List of Tables Table Title

- I Survey Instrumentation 3-I Natural Siirface Radioactivity L.evels 4-I 1IBPP Characterization Survey Unit List 4-2 Results Summary - Subsurliice Soil Samples 41-3 Radionuclide Data for HBPP Concrete Dust Samples 4-4 Results Summary - Class I Drain and Trench Samples 4-5 Results Sunmmary - Class 2 Surface Soils 4-6 Survey Areas_ withlMeasurements Greater than MDA 41-7 Results Summary - Class 2 Drain and Trench Samples

',-8 Results Summnary - HBRlI Surface Soil Samples 4-9 Results Summary -- Class 3 Drain and 'Trench Samples I-IBPP-RPT-O01 ii

Humboldt Bay Power Plant Characterization Report List of Figu res Figure Title.

A-i Site Map A-2 Liquid Radwasie Tankage Drain Line A-3 Radwaste Discharge Line A-4 North Yard Drain Systcm A-5 Radiological Characterization Localions A-6 Radiological Deep Vertical Boring Locations A-7 001 SS2- Surface Soil Sample Locations A-8 002SS2 - Surface Soil Sample Locations A-9 004SS2-- Surface Soil Sample Locations A-1) Gamnma Walkover Survey A-I I 005SS3 - I-BRP Area Sample Locations A- 12 006SS3 - HJ3RP Access Road Sample Localions A-1 3 Discharge Canal Sample Locations HBPP-RPT-001 iii

Humboldt Bay Power Plant Characterization Report List of Appendices Appendix Title A Figures - Site Map and Sample L.ocations 13 Work Packages and Survey Packages C Instrumentation and Training Records D GEL Sample Analysis Results r_ Unit 3 Characterization by I113l1P Radiation Protection Dept IHIBPP-RPT-001 iv

H-lumboldt Bay Power Plant Characterization Report List of Acronyms and Abbreviations Acronymn Description COC Chain Of Custody DCG(L Derived Concentration (uideline Level DPM Disintegratlons Per Minute DQO Data Quality Objectives FSS Final Status Survey FST Field Sample Technician OPS Global Positioning System HB13 Humboldt Bay Power Plant I ISA Ilistorical Site Assessment ISFSI Independent Spent Fuel Storage Installation MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDA Minimum Detectable Activity MDC Minimurn Detectable Concentration MDC,,, Minimum Detectable Concentration via Scan Na! Sodium Iodide NIST National Institute for Standards and T'esting PG&E" Pacific Gas and wlectric QA/QC Quality Assurance/Quality Control SA FSTI'OR Safe Storage USNRC United Stales Nuclear Regulate1y Commission VSP Visual Sample Plano HBPP-RPT-O01 V

Humboldt Bay Power Plant Characterization Report 1.0 Introduction 1.1 Project Background Pacific (as and Electric Company (PG&E) contracted ENFRCON to perform site radiological characterization survoys at the Humboldt Bay Power Plant (HBPP) locatcd al 1000 King Salmon Avenue, Eureka, California, A site map is shown in Appcndix A, Figure A-I . This Characterization Report, along with ttle supporting data, will support the development of the I IBPP Iicense Termination Plan (I,TP). Radiological characterization activities consisted of a survey of Unit I and 2 structures; sampling of surface and subsurface soils and sclimenis within H-IBPP properties; and radiological measurements of construction materials at HBI'P to assess background levels of radioactivity. This report summarizes the results of the characterization activities at Il1l]PI. The data was collected per guidance in NUREG 1575, Revision 1, August 20{)0, ,lhltl-Algei' Radiation Sur'ey, and Site Jesiigationi M/amna (MARSSIM). ENERCON developed several planning documents, for the characterization activitics. These documents were approv'ed as Vendor Procedures by the HBPP'PIlant Safety Review Committee and included in the IIBPP Plant Manual. The documenits included HBPP-PP-003, Site ChiaracterizationPlan, operating procedures, and survey packages, Field survcy aclhvitics were conducted using PG&E

\York Puckages to support work control. Each Work Package implemented the HBPP Work Control process for one or more characterization survey packages. The Work Packages and Survey Packages are presented in Appendix 13.

1.2 Purpose and Scope

'fhe purpose of thie HIBPP Characterization activities was to assess the radiological status of the H-IBIP site in accordance with MARSSIM guidance. The characterization activities were guided by HBIPP-PP-003, Site Ch'aracterizationi Plan, which used the MARSSIM DQO process to establish the necessary requirements and methods for obtaining high quality characterivation data.

The data collected using tie Characterization Plan, as well as previous characterization data, is vital to developing the LTP. The informatlon from the characterization surveys also provides guidance for decontamination and remediation planning.

HBPP-RPT-001 I

i-Humboldt Bay Power Plant Characterization Report Thc Characterization Plan outlined the following areas:

I. Site organizational structure, responsibilities, and training required for characterization activities;

2. Design of and instructions for the characterization survey packages;

3. Survey methods to be employed tbr different media; 4, The quality control measures to be implemented;

5. Personnel, public and environment safety requirements related to field activities; and 6, Characterization report requirements.

The scope of thc characterization survey of the HBIP site was the following:

• Identify' and quaitify the nature and ex'lett of radiological naitcrials;

• Determine the distribution of radioactive matcrlal conlamination in each area that contained radioactive materials contamination;

" Obtain data to provide guidance for decontainnation/'eniedtion activities planning;

" Obtain data to provide guidance for waste management planning;

• Provide information to support the development of the site-specific DCGLs; and

• Provided the information needed to develop the FSS [or each survey area, FiBPP-RPT-001 2

Humboldt Bay Power Plant Characterization Report 1.3 Summary of Technical Approach A central concept of the technical approach was the initial classification of survey areas described in the l-iBPP Historical Site Assessment (HSA) developed by ENERCON in January 2007. Tle HSA collected historical documentation, i.e., radiological scoping surveys, Unit 3 operating reports, environmental reports, incident reports, etc. and then compared potential residual radiological contamination with potential release criteria. Tlhe release criteria used in thelHSA was a very restrictive Resident Farmer scenario. The general criteria used to classify the survey areas were drawn from the regulatory guidance of NUREG-1575 (MA RSSIM) as l'ollows:

Non-hnpaclcd Area: Areas where there Is no reasonable possibility (extremely low probability) of residual contamination. Non-impacted areas are typically ofilsite and may be used as background reference areas.

Ihpacted Area: Areas that could possibly contain residual radioactivity in excess of natural background or litllout levels. All impacted areas must be classified as Class I, 2 or 3 as described in NUREG-1575.

Class I Area: Impacted areas that have, or had prior to reemediatlon, a potential for radioactive contamination (based on site operating histoiy) or known contamination (based on previous radiological surveys) above the anticipated Derived Concentration (inidoli*ne I~ev'l (DCG IM).

Class 2 Area: Impacted areas that have a potential for residual radioactive contamination or known contamination, but are not expected to exceed the anticipated DCGL.

Class 3 Area: Impacted areas that are not expected to contain any residual radioactivity, or are expected to contain levels of residual radloactivity at a small fracltion of the anticipated DCGL, based on site operating history and previous radiological surveys.

This chanrcterization report contains the data necessary to update the HSA and to update the initial MARSS1M classifications listed In the HSA. Areas listed as Class 2 or Class 3, should be upgraded to a Class I area if contamination is found that Is in excess of the DCGLs.

IIBPP-RPT-001 3

Humboldt Bay Power Plant Characterization Report 1.3.1 Survey Design ENERCON developed survey packages for all survey units. Tho survey package development involved performing walk-downs of each area. During (he walk-down details regarding the physical survey area were compiled in the survey package such as type of area (structure, system or cnviron), surfaces in the area (wall, floor, ceiling, surface soil, or other feature,) and dimensions. Data from previous HBPP characteriztlion mid scoping surveys were reviewed and utilized as appropriate. Each survey package contained the following eight sections of information:

1) Detailed description of the survey area and/or survey units

2) Photographs, drawing or drawings of the survey area and/or survey units

3) Survey area operational history including summary data from previotL surveys.

4) Characterization surv'ey instructions -Types and number of survey measurements and/or samples prescribed for the survey.

5) Survey support requirements such as shovels, scoops, ladders, GPS, and coring tools.

6) 1Icalth and safety requirements.

7) IMVP requirements.

8) Characterization Data - Survey histrument data downloads, survey reports, and sample analysis reports.

For each survey area in a designated survey unit, ENERCON used 30 samples/measurements as a standard number of characterization survey locations for all areas that were designated as MARSSIM Class 2 or Class 3 at H-BPP. The basis for using this number is that the quantity is an important standard number in Large Population Statistics and was used historically in NRC HBPP-RPT-O01 4

Humboldt Bay Power Plant Characterization Report guidance, NUREG/drafi 5849, Manual fnr Conducting Swrveys in Suppori of License Termination. NUREG 5849 states that for survey areas wilh a low potential for residual contamination, 30 random measurements should be collected to ldentify the condition of ar area within a 95% confidence level. in regards to lhe statistical number of locations using MARSSIM, the number 30 corresponds to designing a survey using the more conservative relative shift of 1, which typically provides a sample number requirement of 29. These statistical methods are only able to work if all of the surfaces in the survey area have tlie same potential for having residual contamination, i.e. walls, floors, horizonlal pipes/bcams, ceilings, etc. For Class I areas such as the soils around Unit 3, a more direct bounding survey was used since the data would not be use(d for final status surveys since the area would most likely require remnediation, 1.3.2 Training and Qualifications ENIRCON utilized qualified Health Physics Tlchnicians as the Field Sample Technicians (FST) to complete the characterization effort. The training of every rST was documiented using -IlBPP-OP-012, Technician Training, Qualificatlon and Authorization. This procedure established the requirements for training, qualificution and authorization of rndiological technicians to perforn scoping, characterization, reinediation and final status surveys at I hunboldt Bay Power Plant (I 1PP), 1s1's received training on all characterization operating procedure and histrumentation.

The prospective FSTs were then observed In the field implementing the procedures and survey package Instructions. Once the Survey Supervisor was satistied with the training, a qualilioatlon and authorization forn was completed and lbrwarded to H131BI' flor their concurrence.

1.3.3 Field Activities Site Access Field Sample Technicians participated in tie HBPI' training program in order to obtain umescorted access to the restricted area and to document their successflil completion of raining to conduct charucterization survey operations. Access to areas for characterlzation surveys was coordinated with the area/trnit supervisors. In addition, ENERCON attended the daily work planning meetings to ensure access was available.

HBPP-RPT-001 5

lHumboldt Bay Power Plant Characterization Report Building annd Structure Surfaces The primary instrument for detecting surface contamination on building and structure surfaces was the l.udlum Model 2360 Alpha/Beta scaler/ratemeler with n Ludlum Model 43-68 gas proportional detector. This instrument/detector combination simullaneously detected alpha radiation and beta/gamma radiation. The meter is equipped with a discriminator switch enabling the user to read alpha only counts, beta plus alpha counts, and beta only counts. The beta plus alpha combination was used to obtain static measurements at prescribed locations to quantify the amount of radioactive material if present. This instnrment was also utilized to scan large areas such as walls, ceilings, and structure surfaces.

General Area Dose Rates The Ludlum Model 9 was used to obtain general area dose rates throughout survey areas. The gencral area dose rates gave a qualitative view of the background radiation and the possible contamination level of a room.

Loose Conlamination Smears Loose contamination smears were collected at the same location as static radiation measurements.

The smears identified the amount of loose contamination at a location.

S'fppori EqI1pment Chlm'icterlzatlon surveys required the use of a largc boom lift to sttrvcy the tops and sides of some buildings and struIctures. Equipment was handled sarely in accordance with the ENERCON I IASP and In accordance with Job Hazards Analyses.

Utility Clearance Ground penetrations greater than 6" had an excavalion penrmit completed per HBPP procedures.

Utility clearance included the review of I-tBPP plant drawings and the use of a physical detection instrument, i.e. ground penetrating radar or magnelometer.

1.3.4 Sample Analysis 13A4.1 Identification of Contaminants of Concern The radionuclides of concern were identified in the HBPP HSA and were derived from the operation of Unit 3 with the primary isotopes being Cesium-137 (Cs-137), Cobalt-60 (Co-60),

IIBPP-RPT-001 6

THumboldt Bay Power Plant Characterization Report Tritium, Amiericium-241 (Am-241), Pilutonium-239 (Pu-239), lron-55 (Fe-55), and Nickel-63 (Ni-63), Additional radionuclides were also expected to be present but the relative fractions were expected to be minimal as compared to the primary radionuclides. All soil samples were analyzed for gamma emitting isotopes using Gamma Spectroscopy analysis. All analyses were not conducted for every sample due to the gamma to alpha ratios. Alpha contamination -vllnot be present without ,s-137and Co-60 present, Typically, samples with detectable Cobalt-60 or elevaled Cs- 137 were also analyzed for Am-24 I and Pu-239.

1.3.4.2 Minimum Detcctable Concentration The minimum detectable concentration (MDC) Is the concentration of radioactivity that an instrument can be expected to detect aclivity al a 95 percent confidence level. For instruments perornning direct measuremenits and for laboratory analyses, the MDC goal was 10-50% of any applicable limit or DCOL.

For stalic (direct) surface measurements, with conventional detectors, the MDC was calculated using the formula:

MDC (dpm!I00 ,i ) = -3+3.29.(RX &i,;*I + / ' -

Va riables:

Rb - Background count rate (eprn)

Tb = Background count time (min)

'/'.I -Sample Run Time (miO)

Tt = Sample Count Time (rain)

F,=Total Instrument Efficiency (MARSSIM section 6.6.1)

Thlle MDC.I for beta-gamma measurements was calculated by determining the Mihlmum Detectable Count Rate (MDCR). The MDCR is determined by first determining the mlinimum detectable net source counts using Formula 6-8 in the MARSSIM as below.

liBIT-RPT-001 7

I --- I Humboldt Bay Power Plant Characterization Report Minhiurn numbe'r of detectable source counts: s,=d'.b_"

Where:

d'= value taken from Table 6.5 in the MARSSIM for applicable true and false positive rates b, = Number of background counts in a given time interval The MDCR was calculated from Formula 6-9 in the MARSSIM:

Minimum detectable count rate: MDCR = S,*

i Where:

I = Observed time interval Finally, applying the detection efficiency correction resulted in an MDCU* in standardized units (DEPM/ 00-cmn) from this onrmula:

MDCR Scan MDC: A'fDC**

, probetarea I100cmII Where:

p - Surveyor efficiency (value friom a range between 0.5 and 0.75) si - Instrument efficiency

ý,, Surface efficiency 2

probearea = total area of the detector race in cm The value for p was developed in Dralf NUREG/CR-6364 and N UREG- 1507. lt is a percentage estimatc of the likelihuod a surveyor will reliably detect an clevated count rate.

1.3.4.3 Survey Instrumentation Radiological survey instrumentation was selected to ensure that sensitivities were suflicient to detect the expected radionuclides at the minimum detection requirements. A list of the survey instrumentation, radiations detected and calibration sources is provided in Table 1-1.

HBPP-RPT-001 8

Humboldt Bay Power Plant Characterization Report Table 1-1 Survey Instrumentation Instrument/ Radiation Calibration Detector Detector Type Detected Source Use Ludlum 222i (2"X 2") Nal Detector Gamnna Am--241 Qualitative Soil (gamma scintillator) Contamination Measurement Ludlum Model 2360 Gas flow proportional Alpha/Bela/ Th-230iTc-99 Surface static/scan (126 cin 2 area) Gainma incasurements l.udlumn Model 19 Nal Gamma Cs-137 Area exposure measurements L.udlum Model 2929 ZnS Alpha/beta/ Pu-239/Tc-99/I- Swipe/smear

_Gamma 1131/C-14 counting Instrument Calibrations Accurate and precise instrument calibrations are vital lo the quality of a characterization survey.

Portable electronic field instruments were calibrated in accordance with approved procedures to NIST traceable standards at frequencies not to exceed 12 months. Field instruments were calibrated by offsite commercial calibration facilities utilizing NIST traceable calibration sources.

The commercial calibration facilities included Ludlun Measurements, Sweetwater, Texas; SEC, Oak Ridge, Tennessee; ERG, Albuquerque, New Mexico; and ENERCON, Murrysville, Pemisylvania.

The instruments were calibrated by Nuclear" Regulatory Commission (NRC) licensed facilities using NIST traceable standard calibration sources. Calibration facilities operated under approved Quality Assurance Programs, Portable Instruments were source checked daily using Cs-137 for gamma only measurements and Th-230/Tc-99 lbr AlphafBetalGaminmia measurements.

During characterization activities, portable field instruments had a background and efficiency control chart established, per HBII-OP-006, Instrumeat ,ource and Response Check, to monitor the performanlce of field instruments on a daily basis. Control parameters were established for instrument background and efficiency. At the beginning and end of the day, portable instruments were source checked daily using Cs-137 for gamma only measurements and Tni-230 for alpha measurements and Tc-99 for beta measurements, These measurements were recorded on the established control chart. hIstruments with elevated backgrounds required decontamination or HBPP-RPT-001 9

Humboldt Bay Power Plant Characterization Report repair, lnstruments with efficiencies out of tolerance were taken out of service until the issue was resolved and documented per approved instrument procedures. When an instrument was found to be out of tolerance at the end of the day, the data acquired by that particular instrument was suspect until verified to be accurate by Independent measurement or else the data was discarded and new data collected. Instrument Calibration Certificates and source check records are attached in Appendix C.

FSTs were responsible for ensuring that pre-operational and post-operational checks were perfonned in accordance with approved instrument procedures. FSTs signed out and signed in instruments daily when used. FSTs annotated on radiation survey foms the type, model, serial number, efficiency, background, MDC, and other dam as required by approved procedures and the survey package.

1.3.4.4 Sotrces Sources used for daily source checks and efficiency determinations were selected to be representative of the Instrument's response to the Identified radionuclides and were traceable to the National Institute of Standards and Technology (NIST), Radioactive sources used for instrtnicnI response checks and efFiciency determination were stored securely when not in use.

Radioactive sources used to perfunf instrument operalional checks are listed below:

, Ludluni model 2360 Tecchnetium 99- 5, 000 dpin lid Thorimn 230- 4,000 dpm.

" Ludlum model 2929 Thorium 230- 16,500 dpai and Technetium 99- 11,700 dpm.

" L.udlum model 2221 Cesium 137 - 4.82 uCI.

" Ludlum model 19 Cesium 137- 4.82 uCi.

1.3.5 Aunlytlcal Quality Assurance and Quality Control Samples were sent to General Engineering Laboratories (GEL) In South Carolina for gamma spectroscopy analysis. GEL maintains there own In house QA Program for sample analysis traceability and are an approved PG&E vendor; therefore, it was unnecessary provide split or duplicate samples for Quality Assurance and Quality Control. GEL utilizes method blanks, blind HBPP-RPT-0O01 10

Humboldt Bay Power Plant Characterization Report spikes and duplicate samples as part of their QA program. The results of these QA/QC sample analyses are included ln the laboratory reports in Attachnient D.

1.3.6 Data Management Laboratory rcsults received from GET, L.aboratory were reviewed for anomalies and tabulated.

Field nicasurenients were docunicnted on radiological survey report forms and reviewed by a Certified Health Physicist HBPP-RPT-001 II

Humboldt Bay Power Plant Characterization Report 2.0 Investigation Tasks Tlic following sections present the field tasks perfonned during the radiological characterization of soils, sediments, buildings and structures at HIBPP. *rhe field investigation was implemented using the initial MARSSTM Classifications described in the HIfPP lISA. .The initial Classificaltons were used to guide the level of effort necessary to characterize the area. Another key component was the identification of elevated measurements identified in the characterization eflort by lT/Duratek in 1997.

2.1 Building and Structure Surveys During the dccommissioning process, Units I and 2 will be dismantled to provide laydown area lbr t[ie decommissioning of Unit 3 as well as to eliminate the polenlial for cross contamination of Units I and 2 during Unit 3 decommissioning. Characlerihation of Units I and 2 focused on gathering daia for waste disposition of the building and structures. The steel 1-beams are a good candidates for recycling, however, they may need to be decontaminated before they are sent to a recycler or to a landfill.

The support buildings and structures outside of Unit 3 RCA have been impacted by the operation of Unit 3. However, these items should aol requir remiediaition and items may he able to bh released lbr unrestricted use following I IB3PP procedures. The characterization data for buildings and structure to remain after license termination was collecled primarily to asslst in the design of the I-SS. For items that will be demolished, dismantled or released from the site before license termination, the characterization data should aid In the disposition planning.

2.2 Gamma Radiation Walkover Survey A walkover survey for gamma radiation was conducted over MARSSIM Class 2 areas adjacent to Units I, 2, and 3 to characterize the gross gamma radiation within the surface soil column (0 to 6 inches) in conjunction with the collection of surface soil samples. The survey was conducted using a Ludlum Model 44-10 2x2 Nal detector coupled to a L.udlum Model 2221 Meter. The 2" x 2" Nal was used by walking over the land areas and collecting the measurements. The meter was connected to a Trimble" Pathfinder ProXR (or similar) Global Positioning System (GPS) unit to record the current ralemeter data along with the GPS coordinates.

HBPP-RPT-001 12

Humboldt Bay Power Plant Characterization Report 2.3 Railroad Spur Drain Geophysical Surveys A geophysical survey was performed near the end of the railroad track drain line in an effort to locate the end of the drain line and to collect samples to bound the contamination detected by the 1997 IT/Duratek Environmental Characterization.

2.4 Surrace Soil Sampling Surface soil sampling was conducted as parl of the systematic and random sampling programs in Survey Units 001, 002, 004, 005, and 006 which are displayed in Figures A-7 through A-12 in Appendix A. Surface soils were defined as the top 6-inch layer of soil available for direct exposure. Engineered surfaces, including asphalt and gravel, although potential surface sources of radiation, were not included in the definition of strface soils.

2.5 Sedinent Sampling Sediment sampling was conducted in the discharge canal (Figure A-13 in Appendix A).

Syslemalic sampling was conducted to provide a greater lateral and vertical profile of potential contamination since the primary sample locations used in the 1997 IT/Duratck study was straight down thie middle of the discharge canal. Core samples of the sediment were collected fromn a Iloating barge using a hand sediment sampler to penetrate the sediment layer. Sediment samples were collected at a total of 19 locations. 18 locatlons were sampled at intervals of 0-1 feel and 1-2 feet in depth. 12 locations.were able to be samipled at an additional depth Interval of 2-3 feet.

2.6 Hand Auger Sampling Hland Auger sampling was conducted as part of a judgmental sampling of subsurface soils for the Unit 3 RCA, the Hlumboldt Bay Repowering Project Area (HlBRPI), and to obtain subsurface soil data ncar radiologically conlaminated drain and discharge lines. The targeted subsurface pipes and locations, shown in Figures A-3 through A-5, were the following:

• Radwaste Tankage Drain Line o Radwaste Discharge Line

= North Yard Drain System

• Radiological Characterization Locations in the HBRP Area HBPP-RPT-00 I 13

Humboldt Bay Power Plant Characterization Report "lM1e intent of [ihe hand auger sample was to determine if thie associated lines had leaked radioactive material and if so, how much had affected the subsurface soils. A utility locating company was used to specifically locate vertical and horizontal location of each of the lines in order to sample as close as possible to the lines. Once the line was located, the hand auger was advanced to the depth of the line and a sample was collected, A second sample was collected 3 feet below the line. A total of 46 hand auger sample locations were sampled.

2.7 Radiological Deep Vertical Bores Radiological Deep Vertical Borings (RDVB), showNi in Figure A-6, were advanced north or Unit 3 to a depth of approximately -85 feet below grade surface (bgs). Two RDVBs were advanced using a mud rotary truck mounted drill witlh a five-foot long wireline simpling system. One RDVI3, however, was advance by hand after the rotary bit struck an unidenlified water pipe due to incorrect drawings. 'he borings were sampled at 5 foot intervals. Prior to collecting a sample from the 5 foot long core, a Ludlum 44-9 detector was used to determine if an elevated contamination spot existed in the core. If no elevated areai was defected, a sample was collected In the middle of the core sample.

HBPP-RPT-001 14

Humboldt Bay Power Plant Characterization Report 3.0 Data Evaluation The following sections provides a summary of analytical radionuclide data rrom samples collected in areas determined to be representative of background and in 1he I IITPP survey units.

Section 3,1 Is a summary of natural background measurements for different types of material at HBPP, and Section 3.2 is a summary of the radionuclide measurements in the HBPP study area.

3.1 Background Radlonufelide Measurements Samples were collected and surface measurements were performcd to provide data on natural background content. Natural Background Radioactivity for Building Material Surfaces were mecasured and evaluated as part of the III111P1 characterization effort, Surface activity measurements were perfonned in areas where radioactive contaminallon was not suspected to be present based on operational and historical knowledge and based upon characterization results that indicated areas were not contaminated. The backgound determinations were completed at the end of the project to better select non-impacted areas. The results of the natural background study for IIBPP building materials are presented In the 'rable 3-1 below.

Table 3-I Natural Surhfce Radloacth'ity Levels for IIBPP Building Materials 95 % Confidenceo nterval 95% Confidence Interval Surface Alpha Activity Level* Surface Beta Avtivitý' Level*

(dpm/100 cmi2) (dp1ml/i 00 c )

.................. -Menn 2 Sigma Mean*t 2 Si,.Ma Unit 1 12' Elevation Concrete Floor 6.6 16.8 91.7 134.

Unit 1 12' Elevation Cindcr Block Walls 2.5 9 115,6 89.4 Unit I 12' Elevalion Structurnl Steel 8.4 17.7 -12.2 131 Relay Building Concretc Floor 9.1 21 219.6 1 64.3 Relay Buildina Cinder Block \Wal.ls 9.2 18.7 257.1 237.9 Steel Walls and Support Beams 8.2 21.7 -14.9 142

• Levels n-,eaw d ty a Ludu.n Moldet 2221 Meter and l.udh.m hodd 2360 G-as Pwpo:tloiil Probe. 1lhe tne-n and 95%t cmslid-cnc Icvcl ( 2 sigma) values t-wre delermincd frorn 30 static on. minL'1C nweas.jremenis Pi uncontamirztod surfacts wvith open air hackground levels subtracted.

• • A reaolve mean value for d:e beta surface activity level indiicaes ithat tha beta acth'ity of the s el'ctf Is less tian the oven at, background reading of the detectoy rot tm r*týa. Uncontaminated steel acts nas a shilcd and e-ss.ntially towurs the open air background beta r.ntlvity levels HBPP-RPT-00 I 15

Humboldt Bay Power Plant Characterization Report The concrete floor, the cinder block walls and the structiural support steel of Unit 1 12' elevation were selected for background surface determinations since these materials are representative of the bulk of the building materials comprising Units I and2, and were found essentially non-impacted radiologic-ally based on characterization results.

The concrete floors and cinder block walls of the relay/swilchgear building were selected for background surface determinations as being representative of auxiliary type buildings found onsite at H11P31. The hazardous waste storage building was selected for background analyses because of its structural steel walls and support beams and non-Impacted status.

Thirty random locations were picked from each surface and one minute static alpha and beta measurements were obtained simultaneously using a Ludlum Model 2221 meier and Model 2360 gas proporlional probe. "llie same instrumentation was utilized during the characterization project.

The instruments were calibrated and source checked prior to and post use. Open air background levels were delermined by performing a 10 minute open air background count in each monitoring area. Open air alpha and beta background levels were then subtracted accordingly from the untaerial readings The characterization survey results for building surfaces presented iWthis report are biased high becatuso the natural background of the building materials was Intentionally not subtracted.

Including ntu(ral background with the surface chnracTcrlItion results provides the most conservative results. Characterization results will be evaluated by the licensee to detennine waste volunues for Low Level Radkiactive Waste (LLR\V), materials for recovery/recycle, waste materials for clean disposal, and materials to be interned on site.

3.2 Radlological Measurements in the HI3PP Study Area This section of the characterization report presents the results of the data collectcd. This section includes radiological survey results for facility grounds, buildings, Fossil Frueled Units 1 &2, and for some auxiliary buildings of the Unit 3 Nuclear Power Plant. The data presented in this report is comprised of results for surface radiological measurements for Flied and loose contamination listed in disintegrations per minute per 100 square centimeters (dpm/]00 cm 2), area radiation measurements in micro-R per hour (uR/hr), and also surface/subsurface soil sample results in RBPP-RPT--001 16

Humboldt Bay Power Plant Characterization Report picocuries per gram (pCi/g), The radiological characterization was conducted in accordance with applicable guidance found in MARSSIM to ensure data quality and appropriate radiological survey techniques. To ensure a high quality of radiological survey results, guidance from the MARSSIMt was incorporated. MARSSIM was aulhored by several government and regulatory agncices to establish radiological survey methods and strategies for the final release of contaminated facilities. Although the charactcrization results presented in this report are not final relese surveys the licensee could use the data to support final status surveys, The survey approach, documentation, personnel qualifications, and instrument calibraltions presented in this report are guided by MARSSIM and have been successfully incorporated at other facilities to perform characterization and final status surveys.

Radiolodcli Survey Criteria Instrument sensitivities, scan rates, and measurements Are based on Nuclear Regulatory Guide (NuReg) 1.86. Nu Reg 1.86 is referenced in Malcrials License DPR-7 as the guideline for the free release of materials that leave the Ilumboldt Bay facility. Radiological survey criteria was established to salisfy the Nu Reg 1.86 criteria. Radiological survey criteria for alpha activity was assumed for transuranic nuelides at 20 dpn/l00 cm2 for removable activity and 100 dpm/n100 cm-2 ror fixed activity. Release criteria for beta activity wvas assumed to be for Sr-90 at 200 dpm/100 cm1 for removable activity and 1000 dpm/100 cm2 for fixed activity. Radiological surveys were performed with a 95% Confidence Limit to ensure that the radiological survey criteria would be satisfied.

Instrumentation To ensure that the radiological survey minlimum detection criteria would be etne hand held gas flow proportional instruments with 126 cm2 detectors were utilized and the survey results were normalized 100 cm2. Gas flow proportional detectors are more sensitive to low levels of radiation than Geiger Mueller or sodium iodide type detectors. Minhnum detectable activities are documented for the referenced instrument for each survey. The highly sensitive detectors and slow scan rates were capable of detecting less than the stated Regulatory Guide 1.86 criteria. Area radiation measurements were made with hand held exposure rate meters that incorporated sodium iodide (Nal) detectors with sensitivities below I micro remn. Smears (swipes) were counted using a calibrated ZnS (Ag) detector with 2 minute counting times to acquire established MDAs.

HBPP-RPT-0O01 17

Humboldt Bay Power Plant Characterization Report Field instruments were calibrated by licensed calibration facilities meeting the requirements established by American National Standards Institute (ANSI N93, IXZ). Source checks were performed twice dally and documented as rcquired by approved procedures. Commercial analytical laboratories performing soil and water analyses maintained approved Quality Assurance Programs. Tlhe established Quality Assurance Programs required documentation of instrument calibration and performance checks.

Radlological Survey Technique To meet the industry standard Nu Reg 1.86 release criteria with the stated instrumentation field survey techniques were adopted to establish adequate sensitivities. The field survcy techniques were derived based on fihe MARSSIM guidance that set scan rates (rate to move the detector) at 5 cmn/sec (2 inches/see). Static (stationary) measurements were set at I minute each to establish instrument Minimum Detectable Activity (AMDA),

Ceiling static measurenments were sometimes increased firom one minutle to two minutes to adjust lor decreased detection efficiency of the instrument because of longer detector to meter cables required to reach the elevated area being monitored. Smears (swipes) were collected on building surfaces to monitor loose radloactivity. Smears were collected by qualified and experienced FSTs implementing approved procedures and industiy accepled practices. The MDA rur removable (loose) contnamination was calculated based on MARSSIM guidance and slated on t10 radiological survey report.

Cltorjiyterlzatfon Personnel Quatlficatlons Field characterization personnel perfonning measurements and collecting data were trained regarding approved plans and proceduires to ensure accurate implementation of survey package instructions, instrument use, and sample collection, Characterivation personnel performing field measurements and collecting samples met general industry requirements for Radiological Control Technicians (RCTs).

Senior RCTs oversaw monitoring performance of Junior RICTs. Senior RCTs met the requirements ANSI 3.1 and several were qualified by the National Registry of Radiological H-lBPP-RPT-O01 Is

Humboldt Bay Power Plant Characterization Report Protection Technologists (NRRPT). Field monitoring activities, sample collection, Quality Control, and data review was overseen by a Sr. Health Physicist Certified by the American Board of Health Physics (CHP). Survey data was reviewed for completeness and quality by a senior technician responsible for oversight of the survey and also by a certified health physicist for final roview. Such parameters as survey completeness (i.e. survey date, number, maps, and signatures) were checked. Acceptable meter and counter backgrounds, efficicneies, and adequaieness of MDAs were reviewed for both alpha and beta measurements. Survey monitoring points and locations were reviewed to be consistent with the requirements of applicable survey packages, Maps, photographs, and GPS coordinates tire included hi the survey packages in Appendix B to support the data for reproducibility and detailed orientation.

Because of ongoing Unit I operations the interiors of the Unit I boiler, ventilation, and firebox wore not surveyed for surface radiological contamination due to the areas being inaccessible. In addition, this radiological characterization report does not include hazardous material characterization results. At the time of this report, PG&E's Corporate Environmental Department is conducting a hazardous materials investigation at the site in support of' eventual decommissioning of the lbssil power plant and to support construction of the New Generation Plant.

HBPP-RPT-001 19

Humboldt Bay Power Plant Characterization Report.

4.0 Summary of Results The following sections summarize the results of the radiological characterization effort. For area specific Infomation and to locate the exact locations, please refer to the supporting Appendices.

All laboratory analysis reports are contained in Appendix D. All radiological measurement results, survey packages, work packages, areas pictures, sample locations, sample numbers, and safety analyses are contained in Appendix B.

4.1 Impacted Areas Radiological surveys, past and present, show that Unit 3 has impacted all areas ot IIIBPP.

Impacted areas, as defined in Section 1.3 und in the MARSSIM, are areas having some potential for residual contamination. These impacted areas are further divided into Class I, Class 2, and Class 3 areas, based primarily on the relative potential for elevated activity, as discussed ill Section 1.3. For selected survey packages, a detailed description of the area, the history of the area, previous survey results, and an analysis of the results for that area are sumnarized in the subsequent sections. The areas are lisled by classification in order by survey unit in table 4-1

below, TABLE 4-1 H--BPP Charaicterization Survey UnIt list 00 ISS2 Land area on hill north of Unit 3. Contalns spoils pile.

002SS2 Land Area east of Unit 3 RCA and around Discharge 003SS2 Asphalt and concrete areas north, west and south of Units 004SS2 Land area north of Units I and 2. Contains SWN4U 41 OOSSS3 New Gen Area Surface Soils 006SS3 Land Are-a where New Gen Road is to be constructed.

007BS3 Sand Blast Building Floors 010BS2 Unit 2 Ventilation Intake 011 BS2 Unit I Ground Floor (+12 ft elevation) 012BS2 Unit I Second Floor (+27 fl elevation) 013BS2 Unit 2 Ground Floor (+12 fl elevation) 014BS2 Unit 2 Second Floor (+27 ft elevation) 015BS2 Unit 2 Seal Oil Room 016BS2 Unit 2 Condenser 017BS2 Unit 2 Boiler 018BS2 2.4 KV Room 019BS2 Unit 2 Building Structures HBPP-RPT-001 20

IlHumboldt Bay Power Plant Characterization Report 020BS2 Unit I Seal Oil Room 021BS2 Unit I Condenser 022BS2 Unit I Boiler 023BS2 Unit 1 Building, Structures 02,1BS2 Unit ! and 2 Fireboxes.

025BS2 Cold Machine Shop 026BS2 Welding Shop 027BS2 Warehouse 028BS2 Office and Shop Stntctures 029BS2 Unit OilyI Water Surnp ....

03 IBSI Unit 3 Condensate Demlneralizer Room 032BS1 Unit 3 Seal Oil Room 044BSI Unit 3 Propme Engine Generafor 046BS I lUnit 3 Generator/Exciter 055BS3I Unit 3 Hot Shop and Calibration Facility 060BS3 Relay Building 06 IBS3 Steam Cleaning Station 062BS3 Oil/Water Separators 063BS3 Assembly Building 064BS3 Training Building 065BS3 Out of Stock Warehouse 066BS3 Intake Structure 067BS3 Switchyard Structures 068BS3 Riggers Shed 069BS3 Fucl Oi1Service Tanks 070BS3 IHydrogen Bottle Storage 071BJ3S3 IPropane Tank 07213S3 Fresh Water Tank 073BS3 Fire Water Pump Hlouse 074BS3 Office Annex 075BS3 MEPPs 2.and 3 Buildings 076BS3 MEPPs Control Bldg 077BS3 Securlty Building 07813S3 FFDPTrailer 079BS3 Effluent Ponds OSOBS3 Caustic Storage Area 081 BS3 Hlavardous waste Storage 082BS3 Fuel Oil Storage Tanks 083BS3 Diesel Fuel Tanks 084BS2 Distilled Water Tanks 085BS3 Lube Oil Fuel Tanks 086SD I Discharge Canal 088SB I Radwaste Piping Below Grade 089SB I North Yard Drain System 090SB1 South Yard Drain System 095BS I Unit 3 Roof HiBPP-RPT-001 21

Humboldt Bay Power Plant Characterization Report 098BS2 Unit I Roofs 098SBW XZell Installation Samples 099BS2 Unit 2 Roof 101 BS2 Unit I & 2 1st and 2nd Floor Exterior 102BS2 Unit 1& 2 Pre-heaters Area and Outside 104BS3 Metal Storage Building 105BS3 Miscellaneous Class 3 Buildings 4.1.1 Class I Areas 4.1.1.1 Soils and Sediments The Class 1 surface and shallow subsurrace soils around Unit 3 were adequately characterized by IT/Duratek in 1997, however, some additional data was nccessry at depths greater than 4 feet In subsurface soils that had a high potential for being Impacted by leakage from the Spent Fuel l0ool, spills, and/or operations. Several boring were advance around radiologicaly impacted pipes as described in section 2.6. The pipes, sample results, and sample depths are shown in Appendix A, Figures A-2, A-3, and A-4. Subsurfaco soil data was vital to the development of DECON-POS-11010, Excavatilon and removal of Subsurface Soil for Ilumboldi Bay Power Plant Decommissioning, which estimated the potential remedlation costs of class A low level radiological waste during decommissioning of the Unit 3 NRC License. The laboratory results are attached in Appendix D and are summarized in Table 4-2 below.

In addition, the sediments in the Discharge Canal were sampled as described in section 2.5. This data was also used in the developmcnt of DECON-POS-1,010. The results of tilo samnples indicate an Increase in sediment contamination in the first half of the canal over the last decade.

Samples were also collected at greater depths than the IT/Duratek samples and indicate that contaminalion most likely has not leached Into the deep subsurface soils, but remains in the top 2 feet of sediment and soils.

The laboratory results are attached in Appendix D and are summarized In Table 4-2 below.

HBPP-RPT-001 22

Humboldt Bay Power Plant Characterization Report TABLE 4-2 Results Summary - Subsurface Soil Samples Cesium -.137 Ci/g) Cobalt-60 Std Area (Sample Pre-Fix) Max Mean Sid Dev. Max Mean Dev.

Radwaste Discharge Line (RWL) 0.03 0.00 0.01 0.04 -0.01 0.03 Discharge Canal (IDC) 40.50 3.70 .7.94 0.80 0.11 0.16 N. Yard Drain System(RNY) 21.70 1428 4.36 0.18 0,01 0.04 Mise Hand Auger (RCS) 0.55 0.07 0.14 0.04 0,00 0.02 Liquid Radwaste Tankage Drain (RW'i) 0.08 0.00 0.02 0.05 -0,01 0.02 Deep Vertical Borinlgs (RDVB) 21.00 1.98 5.69 0.04 0.00 0.02 Tritium Wells (RCW-SFP and RCW-CS) 0.26 0.00 0,04 0.06 0.00 0,02 4.1.1.2 Buildings and Structures Due to spent fuel movement operutions and due to the availability of data collected by the H-Bl3PI' Radiation Protection (RP) Department, Class I areas were generally not surveyed. The HBPP RP data was collected in several areas of Unit 3. The data consisted of smears inside contaminated systems and concrete dust samples. The concrete dust sampleos were collected using a drill bit and a HEPA vacuum. The process used to collect these samples, as well as the data, was collected from various data archive locations at I IBPP and placed together in Appendix E.

The data collected by the HIBPP RP Department shows that concrete exposed to water contaminated with reactor generated radioactive materials has been volumetrically contaminated.

In general, volumetric contamination Is within the top .V inch of the exposed concrete surface.

Cracks and crevices were not investigated and may show increased depth of contamination when investigated and/or remediated.

Table 4-3 on the next page summarizes the available data for the concrete dust samples collected.

-IIBPP-RPT-001 23

Humboldt Bay Power Plant Characterization Report Table 4-3 Radionuclide data for HBPP Concrete Dust Samples Hot Machine Shop 118" Sampl 1/4" Sample 318" Sample Sample Sample Sample Sample

1. Location # Cs-137 uCi/gqn # CGs-137 uCi/gm ft Cs-137 uCUgm I Floor'in front of Lathe 153 6,69E-06 N/A NIA 215 <.22E-7 2 Floor by rollup door drain 154 1.94E-05 181 1.79E-06 214 3.331E-07 3 Floor in front ofsink 155 2.89E-04 182 4.20E_-05 216 9.7813-06 4 Wall behind the sink 156 8.45r-06 183 1.46E-06 217 4-931-07 5 Floor by souih-we.t drain 157 S.29E-06 184 2.02E-06 219 7.60E--07 Air Eector Room 118" Sample 1/4" Sample 3/8" Sample Sample Sample. Sample Sample

1. Location # Cs-137 uCi/gm # C-s-137 uCi/gm A, Cs-137uCi/gm I Floor at plant east end 261 1.06E-04 477 3.19E-05 504 7.82E-06 2 Adjacent to A/E Condenser 264 ).55E-02 N/A N/A N/A N/A Outer outer ring 309 4.5 IE-03 N/A N/A N/A N/A Outer Ring 233 6.01 E-03 N/A N/A 308 8.77E-04 Middle Ring N/A N/A N/A N/A N/.A N/A Inner Rin.. N/A N/A NIA N/A NIA N/A 3 Crack in floor at plant NWt End 265 1.35E-04 475 4.72E-05 505 1.65E-05 4 Plant West Wal 266 5.1OE-05 N/A N/A 310 2.761.-06 5 Plant SW floor by Grate 267 1.73E,-04 476 5.08E,-05 506 1.05E-05 6 Plant East Wall 311 6.03E-06 NI/A N/A N/A N/A 7 Plant North Wall 312 6.71B-06 N/A N/A NIA N/A HBPP-RPT-001 24

Humboldt Bay Power Plant Charactcrization Report

!nw I.~vi~1 Rid w~iq(p I/8" Sample 1/4" Sample 3/8" Sample Sample Sample Sample Sample

1. Location _ Cs-137 uCi/grm # Cs-137 uCi/gm # Cs-137 uCi/ltn Floor near # I Waste Holdup Tank 510 4.91E-04 521 1.69E-04 552 4.25E-05 2 FRoorb drip pan 512 1.30E-03 523 8.88E-04 554 2.44E--04 3 Floor next to #3 WRT 511 6.81E-04 522 3.4SE-04 553 3.58E-04 4 Floor next to LRW Sump 513 1.22E-03 524 6.83F,-05 555 3.9313-05 5 Floor between LRW pumps 514 3.79E-03 525 7.8 1E-04 556 3.42E-04 6 Wall on plant north of trough 515 2.73E-03 526 9.32&-04 557 3.48E-04 7 Roof lower plant so. Floor 534 1.08F.-05 781 6.481--06 784 1.06E-05 8 Roof floor plant NE corner 535 4.33E-05 780. 9.511r-06 783 4.72E-06 9 Roof near compactor 536 2.35E-03 779 3.16E-04 782 2.20E-04 Cal Focility Sample Sampl 1eS." Sample 1Sample 14" Sample Sample 3/8" Sample U Location #_ e Cs-137 uCi/fni # Cs-137 uCi/gm # Cs-137 uCi/gm I Floor 979 3.75E-06 981 1203E-06 984 1.03E-06 2 'Wall 980 5.76E-07 M983 2.1013-07 985 <3.213-7 Turbine Enclosure 1/8" Samplc 1/4" Sample 3/8" Sample Sample Sample Sample Sample Location #._______- ______ Cs-137 uCi/gm # Cs-137 uCi/gm

_ Floor 1186 1 1.13 E-05 1187 2.51E-06 1188 8.93F_,-07 2 Wall j 190" 1.85E-06 1 1191 4.12E-07 1192 1.7413-07 HBPP-RPT-001 25

M H-uwnboldi Bay Power Plant Characterization Report Reactor Feed Pump Room .....

1/8" Sample 114" Sample 3/8" Sample Sample Sample Sample Sample

1. Location # Cs-137 uCigm # Cs-137 uCi/ugm Cs-137 uCi/gm I Floor (Plant North) 1196 1.12E-06 1197 3.92E-07 1198 -<3.55E-7 2 Floor(Plant South) 1200 3.21E-07 1201 237E-07 1202 <4.75E-7 Pipe Tunnel, Condenaser. & Valve Gallery ....

1/8" Sample 1/4" Sample 3/8" Sample Sample Sample Sample Sample ft Location # CQ;-137 uCilg',m 0 Cs-137 uCi/gmn # -Cs-137 uC'/gm I Floor East Side of Rcheater 1206 4.92E-04 1207 4.73E-05 1208 1.82E-05 2 Floor N End of Condenser Box 1210 5.54E-04 1211 721E-06 1212 9.16E-06 3 North Pipe Tunnel Floor 1216 1.12E-04 1217 3.03E-05 121S 2.15E--05 4 NorthPipeTunnel Wall 1.220 6.40E-06 1221 1.10E-06 1222 5.51_-07 5 Valve Gallery (wall to Rx) N/A " NJA N/A N/A "N/A N/A 6 Valve Gallerycfloor by SFP Pipe) N/A N/A N/A NIA N/A N/A 7 Valve Gallery (Wall to SIrP) NIA I N/A N/A N/A [ NIA N/A Refuel Building 18" Sample I14" Sample 3(8" Sample Sample Sample Sample Sample

1. Location # Cs-137 uCi/gm # Cs-137 uC!/gm # Cs-137 uCi/lgr I Clean Up Lx Room Floor 1358 5,575-04 1359 4.08E-05 1360 1.14E-05 2 Floor by SFP Pumps (+12') 1366 133E,05 1367 5.13E-07 N/A N/A 3 Cask Wash Doon A.rea Floor 1362 7.34E-05 1363 1 3.10E-06 1364 5.67E-06 4 Shutdown R-Lx Room Floor 1347 9.57E-05 1348 3.77E-06 1349 2.301-06 5 Access Shaft -14' Wall 1343 2.78E-06 1344 7.40E-07 1345 7.15E-07 6 Acce Shaft -14' Floor 1339 1.45"E-05 1340 9.96E-07 .1341 4.51E-07 7 Access Shaft -24' Floor , N/A N/A N/A NIA N/A N/A I-IBPP-RPT-00 1 26

Humboldt Bay Power Plant Characteriztion Report I

8 Access Shaft -34' Floor I N/A N/A N/A 1 N/A N/A N/A 9 Wall -66Nea Man-Lift I 1302 3.95E-05 1303 8.32E-06 1304 3.4313-06 10 Floor -66' under Reactor 1294 4.81E-04 N/A N/A 1296 5.97E-06 11 Wall -66' under Reactor 1298 2.71E-05 N/A NiA N/A N/A 12 Floor-66 near REDT N/A - N/A N/A N/A N/A N/A Hot Machine Shop lS2" Saple 518" Sanple 3/4" Sample7/8" Samlle Sample Cs-137 Cs-137 Cs-137 Cs-137 9 Location Sample # u Ci/g-m Sample # uCi/gm Sample # uCi/gm Sample # uT igm Floor in front I I of Lathe NIA N/A N/A N/A N/A N/A N/A N/A Floor byI rollup door I 2 drain N/A \-N.I/.Ak NI/A N/A N/A NIA N/A N/A Floor in front I 3 of sink 259 1.02E-06 N/A N/A N/A N/A NIA N/A Wall behind 4 the sink N/A N/A NIA N/A I N/A N/A N/A N/A.

Floor by 1 south-west 127E-5 drain N/A N/A 307 1 03 N/A N/A "N/A N/A Air Ejector Room

/'2" Sample 5/8" Sam le 3/4" Sample 7/8" Sampie Sample Cs-137 Cs-137 Cs-137 Cs-137

1. Location Sample # uCi/gm .Sample # uCi/gm Sample # uCi/am Sample # uCi/zm Floor at plant 1 east end N/A NIA N/A N/A N/A N/A N/A N/A.

2 1 Adjacent to N/A NIA N/A N/A N/A N/A N/A N/A HBPP-RPT-001 27

Humboldt Bay Power Plant Charactcrization Report A/E Condenser _

Outer outer ring N/A N/A N/A N/A N/A NUA N/A N/A Outer Ring NIA N/A N/A -NIA N/A N/A NIA N/A Middle S Ring 282 I.15E-02 N/A N/A 307 I,27rE-0.^ N/A N/A 1.15E-Inner Rin* N/A N/A 281 03 NA N/A 306 2.49E-04 Crack in floor at plant N-Wt 3 End N/A NIA NIA N/A N/A N/A N/A N/A Plant West 4 Wall NIA N/A N/A N/A N/A N/A NTA N/A Plant SW 5 floor by Grate N/A N/A N/A NI/A N/A N/A N/A N/A Plant East 6 N/A N/A N/A N/A N/A N/A N/A Plant North 7 Wall N/A NIA N/A NIA N/A N/A N/'A N/A Low Level Rid w estc 1/2" Sample 5/8", Sam pl 314" Sample 718" Sample Sample Cs-137 Cs-i37 Cs-137 Cs-137

1. LoCation Sample# uCi/gn Sample uCi/gm Snmple # uCi/lgm Sample # uCi/gm Floor near #1 Waste I Holdup Tank 617 8.65E-06 N/A NIA N/A N/A N/A N/A Floor by drip 2 pan 619 2.04E-04 N/A N/A N/A N/A N/A N/A Floor ncxt to 3 #3 WRT 61S 3.65DE-04 N/A N/A N/A N/A N/A N/A 4 Floor next to 620 2.13E-05 N/A N/A N/A "N/A N/A N/A HIBPP-RPT-001 28

Humboldt Bay Power Plant WE Characteritjion Report LRWS p [ump Floor I t between I 5 LRW pumps 621 1 4.80E-04 N/A jN/A N/A N/A N/A N/A Wall on plant north of 6 trough 622 1.27E-04 N/A N/A N/A N/A N/A N/A Roof lower plant so.

7 Floor N/A N/A N/A NIA N/A N/A N/A N/A Roof floor plant NE corner N/A N/A N/A NIA N/A NIA N/A N/A Roof near  ! I 9 compactor N/A N/A N/A I N/Al N/A N/'A N/A N/A CaI Facili" 1/2"SSame SampeIC , 3/4" Sample 7/8" Sample Sample Cs-137 Cs-137 Cs-137 Cs-137

1. Location Sample # uCi/gn Sml# i Smpl# uCi/M Spl# uCigm I Floor NIA [ N/A NIA N/A N/A N/A N/A N/A 2 Wall N/A N/A I N/A N/A N/A N/A N/A N/A Turbine Endosure I/2" Sample 5/8" Sample , 3/4" Sample ,7/8" Sample Sample Cs-137 Cs-137 Cs-137 . Cs-137

1. Location uCi/-mm Sample # Sample # uCi/-gm Sample # UCilgm Sample # uCi/gm I Floor 11189 4.35E-07 NIA N/A N/A N/A N/A N/A 2 Wall 1193 1.75E-07 N/A N/A I NIA N/A N/A N/A Reactor Feed Pump Room Sample I Location 1 1/2" Sample Sf8" Samp I 314" Sample 7/8" Sample HBPP-RPT-001 29

Humboldt Bay Powcr Plant Characterization Report Cs-137 Cs-137 Cs-137 Cs-137

__uCi/gm Sample # Sample # uCi/gm Samnplc # uCi/grn Sample # qCi/gM Floor (Plant I North) 1199 3-33E-07 N/A N/A N/A N/A N/A N/A Floor (Plant 2 South) 1203 <4SS-E-7 N/A 1 NIA NIA I N/A N/A N/A Pipe Tuincel, Condcnser, & Valve Gallery 721 Samp 5/8" Sample 314" Sample 718" Sample Snample Cs-137 Cs-137 Cs-137 Cs-137 A Location uCi/gm , Sample# Sampile# uCi/.gm Sample # uCi/* Sample # uCl/gm Floor -aqt Side of I Rchcater 1209 5.25E-06 N/A N/IA N/A N/A N/A N/A Floor North End of Condenser 2 Box 1213 3.29E-06 N/A N/A NIA N/A .N/A N/A North Pipe 3 Tunnel Floor 1219 1.50E-05 N/A NIA N/A NI/A N/A N/A North Pipe 4 Tunnel Wall 1223 8.13 E-07 NIA N/A N/A N/A N/A N/A Valve Gallery 5 (wall to R-x) NIA N/A N/A N/A N/A N/A N/A N/A Valve Gallcry(floor near SFP

.6 Pipe) N/A N/ANA I N/A N N/A N/A N/A N/A Valve GallcryI 7 (Wall to SIP) N/A N/A N/A N/A N/A NI/A N/A N/A Refueling Building Sam ple Location la" Sample- 5/8" Sample 3/4" Sample 7/8" Sample HBPP-RPT-00 I 30

a Humboldt Bay Power Plant Characterization Report Cs-E37i Cs-137 Cs-137 Cs-137 uCi__mS Samplee l Sample# i/i/g Sample P

1. Sample# uCi/gm I

Clean Up Ix Room Floor 1361 1L16E-05 N/A N/A N/A N/A N/A N/A Floor "ySFP 2 Pumps (+121) 1369 6.44E-07 N/A Nt/A N/A NIA N/A N/A Cask Wash 5.89E-07 Down Area (Co-60 &

3 Floor 1365 Am241) N/A N/A N/A N/A NIA N/A Shutdovm [-Lx 4 Room Floor 1350 239E-06 N,/A N/A N/A N/A N/A N/A Access Shaft 5 -14' Wall 1346 <3.91E-7 N/A N/A N/A N/A N/A N/A Access Shaft 6 -14' Floor 1342 <4.SIE-7 N/A N/A N/A N/A N/A N/A Access Shaft 7 -24' Floor N/A 'N/A NiA N/A N/A N/A N/A N/A Access Shaft AN/A NIA 8 -34' Floor _ /A N/A V____NA N/A N/A N//A Wall-.6 Near Man-9 Lift 1305 9S7E-07 NIA N/A N/A N/A N/A N/A Floor-66' 10 under Reactor 1297 1.55E-05 N/A N/A N/A N/A N/A N/A Wall -66' 11 under Reactor N/A N/A NIA N/A N/A N/A N/A N/A Floor -66 /

12 near REDT N/A N/A N/A N/A N/A N/A N/AN/A HBPP-R.PT-001 31

Humboldt Bay Power Plant Characterization Report Several Draht and trench samples were collected in Unit 3 Class 1 areas. Specifically, two drains on Unit 3 roof had positive detections for Plutonium 239/240, Co-60, and Cs-137. One drain sample from the Unit 3 Generator Exciter area had detectable Cs-137 and Co-60, Table 4-4, below, summarizes the results for samples with delectable radioactive materials present.

Table 4-4 Results Summary- Class 1 Drain and 'Trench Sam ples

. Result (C1/g) (GEL Report 11217584)

Sample Number/l.oeatlon Cesium- 137 Cobalt-60 Plutonium-239/240 Americium-2,t I U3 Gen/Exciter 04613S 1 25.20 2.05 ND ND 4.27 0.32 N'D ND Unit 3 Roof 5.40 0.45 0.12 NID (Survey Unit 095BS1) 2.11 ND ND NDD 17.1o ,.30 _ 0.17 ND I. Rqdsut in bokd .nul indkAtk conCenuatilonf s gre*atr than ba.knum,,] kvds.

2. \D ?Xo.L-DdiaVct'b.e. NesulI tlitn0, Uv -at'Iiuhy MDC._,

3. N/A - Analsis r-o rc.iLwsted fbcsmple.

4.1.2 Class 2 Areas 4.1.2.1 Soits

"'he primary Class 2 Soils, per Ohe HBrPP lISA Initial MARISSIM Classilications, are the soils surrounding tho Unit 3 RCA. In August and Sepiember 2007, the surface soils in this area were investigated in an effort to provide enough data norevise the MARSSIM classifications to a Class 3 area.

With the data collected (i.e., soil samples and 100% gammna walkover survey), prior characterization data, and the use of an industrial release scenario, the areas may be changed to a MARSSIM Class 3 in the next revision of the HSA and also be listed as a Class 3 area in the LTP.

The characterization survey consisted or 29 soil samples and a gamma radiation walkover survey. The design of the survey was based on criteria from NUREG-1757, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). Soil samples were collected at locations that were determined by using a random start point systematic grid. The sample locations were selected using the current version of Visual Sample Plan. Physical collection of the soil samples was delineated in the Survey Instructions which included the sampling process, field decontamination of tools, sample labeling requirements, and sample location. The procedure HPP-OP-002, Chain of Cuslody, was used to delineate the required chain NBPP-RPT-001 32

Humboldt Bay Power Plant Characterization Report of custody process and requirements to ensure the integrity of the samples collected. Soil samples were submitted to General Engineering Laboratories (GEL) for gamma spectroscopy for Cs-137 and Co-60 and for analysis ofAm-241, Pu-239/240, Cm-242/244, and Sr-90.

The Sm*rvey Instructions also described the procedures to be followed for the gamma radiation walkover survey which covered 100% of accessible surface soil areas using a 2W2 Sodium Iodide (NaeD detector with it scanning speed of less than 0.5 m/s. The Gamma Walkover survey was performed using a Ludluin Model 44-10 (2T"x 2") Nal detector coupled to a Ludlum Model 2221 meter. A Trlhble Pathfinder ProXR Global Positioning System (GPS) was used to log thie position and radiation measurements collected during the gamma walkover survey. The 011S was also used to located and log the surface soil samples collected in the area.

As shown in Table 4-5 below, the tihrec survey units where soil samples were collected have little (o no contamination present. Detectable levels of Cs-137, however all of these levels are below 0.5 pCi/g which is the site establishod-baekground for Cs-137 from atmospheric testing of nuclear weapons, Survey Unit 002SS2 had the only Co.

Tahblc 4-5 Results Summary - Class 2 Surface Soils Cesium -137 (pCi/g- Cobalt-60 No of N\o of samples Std samples Area >MDA Maximnum Mean Deviation >MDA Maximum Mean Std Deviation 001SS2 19 0.92 0.17 0,21 0 0.05 0.01 0.01 002SS2 22 1.00 0.21 0,25 i 0.07 0.01 0.02 003SS2 Samples not collected through asphalt.

004SS2 14 2.69 0.581 0.70 0 0.06 0,01 0.02 NOTE: All 0-:437 analysL,8 were below site established backgrowid.

4.1.2.2 Buildings and Structures The Class 2 buildings and structures were surveyed as described in Section 1.3,1. All surveys are attached to the survey package and controlling work package in Appendix B, All laboratory analytical data of drain and trench samples is contained in Appendix D.

H1BPP-RPT-001 33

Humboldt Bay Power Plant Characterization Report Table 4-6 below shows the various HBPP buildings and areas with a monitoring result greater than MDA.

Characterization results will be evaluated by the licensee to determine waste volumes for Low Level Radioactive Waste (LLRW), materials for recovery/recycle, waste materials for clean disposal, and materials to be interned on site.

A review of the data In Table 4-6 shows most areas surveyed to be below the applicable survey criteria especially when construction material backgrounds are considered and subtracted for fixed alpha and beta levels. However low level fixed alpha and/or beta activity was detected particularly on the HBPP site roofs, the unit 1 and unit 2 exterior building structure including ventilation systems at all levels, and the olisite storage tanks.

'Table 4-6 also shows a number of locations where fixed alpha activity levels were obtained that exceeded the fixed alpha survey criteria of 100 dpm/l00 c11 2. Unit 2 exterior building structures including ve.aptation systems showed some fixed alpha activity results that exceeded the MDA ranging from 58-508 dpm/l00 cm2. Unit 2 roofs showed some fixed alpha activity results that exceeded the MDA ranging from 42-302 dpm/l100 tm 2. Unit I exterior building struclures including ventilation systems showed fixed alpha activity that exceeded the MDA ranging from 45-3884 dpm/100 cm2. Unit I roofs showed some fixed alpha activity results that exceeded the MDA ranging from 47-3,'8 dpm /100 cm2.

Several tanks showed some fixed alpha activity results that exceeded the MDA above the fixed alpha survey criteria. These tanks included the Fuel Oil Storage Tank #1 (40-188 dpm/100 cmr), Fuel Oil Storage Tank #2 (45-180 dpm/l 00 cm 2), the Diesel Fuel Tanks (58-130 dprn/100 cm 2), the Distilled Water Tank (58-570 dpmi/100 cm2) and the Lube Oil Storage Tank (65-317 dpi/100 cm 2) Unit I and Unit 2 preheater areas showed some lIxed alpha activity results that exceeded the MDA above the fixed alpha survey criteria ranging from 42-5 13 dpm/1 00 cm2 .

Further general review of the data In Table 4-6 shows several locations where some removable alpha activity results exceeded the removable survey criteria of 20 dpmln100 cra 2

. The Unit 3 Generator Excitor Enclosure had some removable alpha activity results ranging from 7-43 dpln/100 em2. Four tanks had some rmmovable alpha activity results ranging from 20-40 dpm/l00 om2 . These tanks included the Distilled Water tank, the Diesel Fuel tank, the Lube Oil Storage tank and the Freshwater tank. Four areas had some elevated removable. alpha activity results (21 dpm/100 cm2 ) just at the survey criteria. These HBPP-RPT-001 34

Humboldt Bay Power Plant Characterization Report M

results may have just exceeded the survey criteria due to statistical variation (Haz Mat Building, Riggers shed, Main Office and Cold Shop Roof and the Unit 3 roof).

General review of Table 4-6 also shows locations where some beta activity results exceeded the survey criteria of 1000 dpm/100 cin 2 ror fixed contamination. 'Ihese locations included spot contamination on the Unit 2 exhlaust support structure (5855 dpm/100 cm 2 ), the Unit I Ground Floor (1011 dpm/l00 cm2), the Unit 2 Seal Oil Room Roof (2556 dpm/100 cm 2 ), the Office and Cold shop roof(1 126 dpm/100 cm 2),

three tanks including the Fuel Oil Storage Tank 111(1043 dpmi/lOO 61 2 ), hile Freshwater tank (1436 dpm/l00 cm2) and the Distilled tank walls and roof (2256 and 1005 dpm/ 00 cull respectively), the Unit I and Unit 2 preheater pads (maxinum value of 4769 dpm fixed beta/100 cm2). The elevated beta result from the riggers shed was remediated by PG&E RP.

Three locations showed some removable beta activity results that exceeded the survey criteria of 200 dpm/100 cm2. These areas included the Unit I Building Structure 80' Level (95-275 dpnmlOO em 2 ), tie Unit 3 Generator Excitor (200 dpm/100 cm 2) and tile Unit 2 Penthouse Roof (220 dpmt/O0 cmr).

Table 4-6 Survey Areas with Measurements Grcater than M DO)

Alpha (DPMV100 cm 2 ) Beta (DPMJ100 cm2 )

Location Fixed Removable Fixed Removable 009BS2 Unit I Exhaust Stack and Structure 25-130 7 166-678 39-60 009BS2 Unit I Intake Ducting, Fan and Motor Exterior 45-144 7-11 397 < MDA 01OBS2 Unit 2 Exhmust Stack Exterior 50-89 6-21 278-815 <MDA 217-545, 1 010BS2 Unit 2 Exhaust Support Structure < MDA 7-11 Pt A 5855 < MDA 2 pis @

0 1OBS2 Ventilation, Steam Drum 2i < MDA < MDA < MDA 010BS2 Ventilation, U2 Air Inlet Exterior < MDA 7 234-310 40-56 OOBS2 Ventilation, U2 Air Intake Fan I.lousing 55-214 < MDA 221-714 < MDA 0 1OBS2 Ventilation, U2 Air Intake Interior <,MDA < MDA 206-291 117 01 1BS2 Unit 1 Ground Floor .Floors <MDA 1-2 210-1011 < MDA 01 IBS2 Unit 1 Ground Floor Walls < MDA < MDA 130-240 <MDA 011BS2 Unit I Ground Floor Ceiling < MDA < MDA 170-315 < MDA HBPP-RPT-001 35

0 Humboldt Bay Power Plant Characterization Report 012BS2 Unit I 2nd Floor Ceiling 30-90 < MBA < MDA < MDA 012BS2 Unit I 2nd Floor Walls < MDA <MDA 140-240 18 012BS2 Unit I 2nd Floor Floors < MDA < MDA 180-350 28 01 3BS2 Unit 2 Ground Floor Floors < MDA < MDA 200-400 < MDA 013BS2 Unit 2 Ground Floor Ceiling < MDA 1 300-420 < MDA 013BS2 Unit 2 Ground Floor Walls < MDA 1 I pt 200 < MDA 014 BS2 Unit 2 2nd Floor Floors 8-12 1 200-400 <MDA 01 4BS2 Unit 2 2nd Floor Ceiling < MDA < MDA < MDA < MDA 014BS2 Unit 2 2nd Floor Walls <MDA < MDA 260-330 <MDA 015BS2 Unit 2 Seal Oil IRoom Exterior < MI)A < MDA 275-341 < MDA 015BS2 Unit 2 Seal Oil Room Roof 42-656 < MDA 180-2556 <MDA 015BS2 Unit 2 Seal Oil Room Inlerior < MDA <MDA 200-400 <MDA 0163BS2 Unit 2 Condenser < MDA < MDA 204-317 <MDA 017BS2 Unit 2 Firebuxt Interior 42-79 7-14 385-556 <MDA 017BS2 Unit 2 Firebox, Exterior < MDA <MDA 276-408 < MDA 2 pts O 017BS2 Unit 2 Lower Exhaust to Stack 23 < MDA <MDA < MDA 018BS2 Unit 2 2.4 k%, room 42-106 < MDA 246-514 < MDA 0o19BS2 Unit 2 56'structures I p153 7 159-430 <MDA 019BS2 Unit 2 73' structures 65-72 7 1 pt (a 542 < MDA 019BS2 Unit 2 80' Structures60-508 < MDA 198-282 < MDA 01 9BS2 Unit 2 46' Struclures <MDA <MDA 170-520 <MDA 0139S2 Unit 2 47.5' Structures58-108 7-10 1 pt@234 <MDA 019BS2 Unit 2 27' Structures < M)A < MDA 189-317 < MDA 019BS2 UntIt 2 97.5' Structures 55-60 7 < MDA <MDA 019BS2 Unit 2 64'Sirttctures 16-90 < MDA < MDA < MDA 020BS2 Unit 1 Seal Oil Room, Interior < MDA 1 163-681 < IUDA 020BS2 Unit I Seal Oil Room, Exterior I1 7 195-722 <MDA 020BS2 Unit 1 Seul Oil Room, Roof 37-107 1 < MDA < MDA 021BS2 Unit I Condenser 29-13 7 1pt n 190 < MDA 023BS2 Unit I Building Structures, Ul 27' Structures 69 I pi @ <MDA 201-317 <MDA 023BS2 Unit I Building Structures, U1 47.5' Structures45-142 < MDA 188-304 <MBDA 023BS2 Unit I Building Structures, UI 56' Structures64-176 < MDA 248-944 <MDA 023BS2 Unit I Building Structures, UI 64' Structures71-221 <MDA 253-464 <.MDA 023BS2 Unit I Building Structures, UI 73' Structures45-172 <MDA 194-642 < MDA HBPP-RPT-003 36

a Hlumboldt Bay Power Plant Characterization Report 02313S2 Unit I Building Structures, UI 80' Structures73-384 < MDA 287-559 95-275 02313S2 Unit I Building Stnlctures, Ul 97.5' Structures60-271 7 208-231 < MDA 025BS2 Cold Machine Shop Walls < MDA <,MDA 195-202 < MDA 02513S2 Cold Machine Shop Floors < MDA < MDA 180-340 < MDA 02513S2 Cold* Machine Shop tUpper Walls &

Cetling < MDA < MDA 168-260 < MDA 02613S2 Weld Shop Walls & ceiling < MDA 7 < MDA < MDA 0268S2 \Veld Shop Floor <MDA < MDA 184-311 < MDA 027BS2 Warehouse Floor 16-37 < MDA 208-280 < MDA 027BS2 Warehouse Interlor < MDA < MDA 124-692 < MDA 02813S2 Office & Shop Inlerior Floors 18-24 < MDA 221-347 <MDA 028BS2 Office & Shop Interior Walls &

Ceiling < MDA < MDA 225-331 < MDA 02813S2 Office and Shop Spaces Roof 25-536 7-21 224-1126 <)DA 028BS2 Office and Shop Spaces Exterior 18-110 7 197-382 < MDA 029BS2 Oily Water Sump < MDA < MDA < MDA < MDA 03213SI Unit 3 Seal Oil Room Walls < MDA < MDA 216-511 < MDA 032B1SI Unit3 Seal Oil Room Floor < MI)A 7 1 pt na. 328 < MDA 032IS I Unit 3 Seal Oil Room Ceiling < IMDA 7 < MDA < MDA 04413S1 Propane Engine Generator Interior Floor < MDA < MDA 234-487 < MDA 04413SI Propane Engine Generator Interior Walls < MDA 7 227-476 < MDA 044flS I Propane Engine Generator Ceiling _ < MvDA 7 231-126 < MDA 044BSI Propane Engine Generator Exterior Walls I 1p*,1,58 < MDA 247-626 <MDA 01613S1 Unit 3 Generator Excilor Walls63-151 7-11 167-339 <MDA 04613S I Unit 3 Generator Excitor Floor 63-302 7 177-505 < MDA 046BS1 Unit 3 Generator Ixeltor Drains < MDA 7-14 242-663 < MDA 046BSI Unit 3 Generator Excitor Enclosure Exterior Walls and Ceiling 79-143 7-43 1 pt Q 170 200 046BSI Unit 3 Generator Excitor Interior Surfaces < IDA 7 < MDA < MDA 060BS3 Relay building exterior and interior < MDA <IMIDA < MDA <MNUDA 061 BS3 Steam Cleaning Station <,MDA < MDA 223-385 < MDA 062BS3 Oily Water Sepators Pits < MDA <MDA 227-354 104-157 062BS3 Oily Water Sepators Pad and Walkways 79 <MDA 220-278 104-126 0638S3 Assembly Building Roof < MDA < MDA 260-300 <MDA 063BS3 Assembly Building Interior < MDA < MDA 219 <MDA HBPP-RPT-00 I 37

Humboldt Bay Power Plant Characterization Report 063BS3 Assembly Building Exterior Wall 58 < MDA < MDA < MDA 064BS3 Training Building Exterior <MDA < MDA 234-340 <MDA 064BS33 'lfining Building Roof 50-75 7 250-400 < MDA 064BS3 Training Building Interior < MDA < MDA 249-733 <MDA 065BS3 Out of Stock Warehouse Fxterlor Walls < MDA < MDA 191-354 < MDA 065BS3 Out of Stock Warehouse Interior Floor 18-49 7 191-285 <MDA 065BS3 Out of Stock Warehouse hiterior Walls and Ceiling < MDA < MDA 191-285 <MDA 066BS3 Fecdwater Intake Structure Ground 55-89 < MDA 370-789 < MDA 066BS3 Feedwater Intake Structure Pits 15-60 7 566 <MDA 067BS3 Unit 3 Transfer Yard Structures 40 7 280 < MDA 068BS3'Rlggýrs Shed Exterior <MDA 7-21 90-160 <iDA ..

068BS3 Ri gers Shed Interior <,MDA < MDA 8178 120 069BS3 Fuel Oil Service Tanks, Tank ll Walls 72-94 7-10 176-473 < MDA 069BS3 Fuel Oil Service Tanks, Tank #1 Roof 65-87 7-10 166-393 < MDA 069BS3 Fuel Oil Service Tanks, T'ank #2 Walls < MDA 7-10 212-370 < MDA 069BS3 Fuel Oil Service Tanks, Tank #2 Roof I Pt @ 45 7-10 197-249 < MDA 070BS3 Hydrogen Storage Building Interior of Enclosed Room < MDA < MDA 309-353 < MDA 070BS3 I lydrogen Storage Building Interior ofOpen Air Section < MDA <MDA 322-573 <MNlDA 070BS3 Ilydrogen Storage Building Exterior 72-108 7 1 pt (.al256 <Ml DA 071BS3 Propane Tank < MDA < MIA 249-257 < MBA 072BS3 Frcshwater Tank, Roof 58-462 7-20 185-828 < MDA 072BS3 Freshwater Tank, Walls57-260 17-33 212-1436 < MDA 073BS3 Fire Water Pump House Exterior < MDA < MDA 90-450 < MDA 073BS3 Fire Water Pumnp House Ceiling < MDA < MDA 367 <MDA 073BS3 Fire Water Pump House Jnteior. < MBDA < MDA 170-195 < MDA 073BS3 Fire Water Pump House Roof 50-98 < MDA 193-465 < MDA 073BS3 Fire WaterPump Ilouse Floor <MDA < MDA 150-359 <_MDA 074BS3 Office Annex Floors . I pt @ 16 < MDA 220-630 < MDA 074BS3 Office Annex Interior Walls I pt R. 16 < MDA <MDA <M.DA 074BS3 Aux Admin Roof 55-105 < MDA 310-560 < MDA 074BS33 Oflice Annex Exterior Walls <MDA 7 < MDA < MDA 075BS3 MEPPS 2 & 3 Control Trailer Roof 25-100 7 170-530 < MDA 075BS3 MEPPS 3 Enclosure & Horizontal 55-130 <MDA 200-250 <MDA HBPP-RPT-00 338

Humboldt Bay Power Plant Characteri7ation Report

[Surfaces 075BS3 MEPPS 2 Enclosure & Horizontal Surfaces 55-110 < MDA 184-303 <MDA 075BS3 MlIPPS 2 Interior < MDA < MDA I pt 0 200 < MDA 075BS3 MEPPS 2 & 3 Control Trailer Ext.

Walls 58-87 < MDA <MDA <MDA 07513S3 MEPPS 2 Enclosure Building Ext.

Walls Ipt (@ý 58 <MDA I pl @, 2 3 4 <MDA 075BS3 MEPPS 3 Enclosure Building Ext.

Walls < NIDA < MDA <,MDA < MDA 075BS3 MEPAS Interior < MDA < MDA < MDA < MDA 076BS3 tvlEl'l Control Building Ext. Wall < MDA < MDA < MDA < MDA 076BS3 MEPPS Control Building Roof < MDA 7 1 pt (a219 < MDA 077BS3 Security Building Interior < MDA < MI)A 250-500 < MDA 077BS3 Security Buildlng Roof 80 7 200-500 < MDA 07713S3 Security Building Exterlor < MDA < MDA < MDA <-MDA 078BS3 FFD Trailer Exterior 70-100 7 250-400 < MDA 078BS3 FFFD Trailer Interior < MDA < MDA < MDA < MIDA 081 BS3 Haz-Mat StorageBuilding Exterior < MDA 7-21 190-300 < MDA 081 BS3 laz-Mat Storage fluilding Interior < MDA <MDA 100-200 < MDA 08IBS3 1laz-Mat Storage Building Roof 55-200 7-10 260-400 < MDA 0821BS3 Fuel Oil Storage Tanks, Tank P1r Walls58-188 < MDA 204-469 < MDA 082BS3 Fuel Oil Storage Tanks, Tank #1 Roof 40-129 < MDA 238-1043 < MDA 082BS3 Fuel Oil Storage Tanks, Tank V2 Walls60-180 < MIDA 224-304 < MI)A 082BS3 Fuel Oil Storage Tanks, Tank 112 Roof 15-153 < MDA 179-605 < MIDA 083BS3 Diesel Fuel Tanks, Walls58-130 7-10 169-355 108-164 083BS3 Diesel Fuel Tanks, Roofs58-108 7-13 < MDA < MDA 084BS2 Distilled Water Tanks. Walls < MDA 7-20 317-2256 <MDA 084BS2 Distilled Water Tanks, Roof 58-570 7-40 212-1005 117-146 085BS3 Lube Oil Storage Tanks. Roofs65-317 20 214-504 <MIDA 085BS3 Lube Oil Storage Tanks, Walls < IvIDA < MDA I pt (21 186 < MDA 2 pts @

085BS3 Lube Oil Storage Tanks, Basin 58 < MDA 190-473 < MDA 095BS1 Unit 3 Roof 79-317 7-21 190-952 <MDA 098BS2 Unit I Roofs, U11 42' SouthRoof 65-348 7-10 317-586 <MDA 098BS2 Unit I Roofs, U1 42' Northwest Roof < MDA 7-10 234-268 < MDA 098BS2 Unit 1 Roofs, UI 42' Northeast Roof 60-99 <MDA I pt @212 <MDA 098BS2 Unit I Roofs, Ul 50'Roofr 47-177 <MMDA 261-548 98-107 H-IBPP-RPT-001 39

M Humboldt Bay Power Plant Characterization Report 098BS2 Unit I Roofs, Penthouse Roof 49-293 7-10 189-363 <MDA 099BS2 Unit 2 50' Roof 37-180 7 263-685 < MDA 099BS2 Unit 2 42' NE & NW Roof 45-68 7 214-603 <MDA 099BS2 Unit 2 Penthouse Roof 42-143 7 363-981 220 099BS2 Unit 2 42' Souih Roof 48-302 10 462-760 <MDA OIBS2 Unit I Penfltouse Exterior Walls 15,134 7-11 198-556 < MDA IOIBS2 Unit 2 Penthouso Exterior Walls 55-99 7-11 231-624 <MDA 102BS2 Unit 2 Prehea(er Pad 2nd Level 42-513 <MDA 242-4769 <MDA 102BS2 Unit 2 Preheater Pad Ist Level 45-164 7 223-590 <MDA 146-839, 1 10213S2 Unit I Preheater 42-513 .<MDA pt @24 23 < I)DA 102BS2 Unit 2 Preheater 22-208 < IDA 219-722 <MDA 1041353 Metal Storage Building Floor < MDA 7 < MDA < MDA 104BS3 Metal Storage Building Roof I pt @ 61 7 <MDA < MDA 104BS3 Metal Storage Building Extedor Walls < MDA 10 < MDA 104 104BS3 Metal Storage Building Interior Walls < MDA < MDA < MDA < MDA 105BS3 Paint Shop F-'derior Walls49-104 < MDA 412-480 < MDA 15BS3 Paint Shop Exlerior Roof 79-238 17 231-729 < MDA NO'71i, (I) MaWtcr'speife ri-zlI backm d mcL diiaokn h.s rat tn svborct4d from r$ults shown In general, Units I and 2 are primarily free of radioactive materials, however, some detectable contamination was detected on the rools, in drains, and in Irenches. Primarily, the measured radioactivity was Cs-137, with a couple detections of Co-60 and P1lutonlitm 239/240 (Unit 3 Roof Drains), Table 4-7, shown bclow, provides a suminary of sample results from laboratory data for drains and trenches for Class 2 Areas is attached, Table 4-7 Results Summary - Drain and Trench Samples Result 'pCi/g) (GEL Report #217584)

Sample Number/Location Cesium-137 Cobalt-60 Plutonium-239/240 Amerdcium-241 Unit 2 Ventilation Intake. 0.66 ND N/A ND (Survey Unit 010BS2) 0.11 ND N/A N)D Unit I Second Floor 0.86 ND N/A ND (Survey Unit 012BS2) 0.82 0.08 N/A ND 2.58 ND NIA NID 0.59 NIO N/A ND 1.18 ND N/A ND HBPP-RI>T-001 40

Humboldt Bay Power Planit Characterization Report 4.44 ND I N/A ND 7.79 0.42 N/A IND 4.66 ND N/A IND Unit I Second Floor 1.72 ND N/A ND (Survey Unit 012BS2) 2.82 ND NIA ND (cont.) 1.02 ND NIA ND 0.72 ND N/A ND 2.29 ND NIA ND 1.12 ND N/A ND 1.37 ND N/A ND 1.07 ND NI/A ND 0.70 ND I N/A ND 1.55 N) N/A IND 0.97 ND) I N/A 'ND 4.77 ND N/A ND Unit 2 Ground Floor 7.53 .0.30 N/A ND (Survey Unit 13BS2) 1.03 ND N/A ND 0.68 ND N/A ND 1.40 ND N/A ND 15.20 0.52 N/A ND 2.12 0.14 NIA ND Unit 2 Second Floor 9 .09. . N/A . ND 3.79 0.27 N/A ND (Survey Unit 01 4BS2) 2.57 IND N/A ND 3.06 ND N/A ND 0.16 ND N/A ND 0,19 ND N/A ND Unit 2 Condenser .. 0.16 N......ND ND) N/A ND (Survey Unit 0161BS2) 0.12 N) N/A ND 0.72 ND N/A ND 0.16 ND N/A _ ._ND Unit I Seal O1l1Rm 020BS2 1.27 NI) N/A ND 0,28 ND N/A ND 0.14 ND N/A ND Unit I Condenser (Survey Unit 0211BS2) 0.50 ND NIA ND 0.29 ND NIA ND 0.22 ND NI/A ND U2 Oil/Water Sump 029BS2 0.23 ND N/A ND U3 Gen/Exciter 04613S1 25.20 2.05 ND ND 1.07 ND N/A ND 0,35 ND N/A ND Switcbyard Structures 0.40 ND N/A ND (Survey Unit 067BS3) 0.17 ND N/A ND

_ 0.20 ND N/A ND Fire Water P-House 073BS3 0.60 ND NI/A ND MEPPS C0 Bldg 075/076BS3 0.53 ND ND ND HBPP-RPT-00 I 41

Humboldt Bay Power Plant Characterization Report Security Bldg 077BS3 0.42 ND N/A ND 4.27 0.32 ND ND Unit3 Roof 5.40 0.45 0.12 ND (Survey Unit 095BS1) 2.11 ND ND ND 17.10 1.30 0.17 ND 0.81 ND N/A ND Unit 09R1of 2)3.86 ND N/A ND (Survey Unit 09813S2) 0..1.../AN.

0.81 ND N/A ND 8.72 ND N/A ND 7.94 NIP N/A ND 4.81 ND N/A ND 4.43 ND NIA ND 1.97 NTD N/A ND Unit 2 Roofs 0.56 ND N/A ND (Survey Unit 099B52) 738 ND N/A NID 1.76 0.52 N/A ND 3.37 ND N/A ND 2.94 ND N/A ND 7.24 ND N/A ND 2.55 ND N/A ND 0.29 ND N/A ND 1.03 ND N/A m 2.28 ND N/A NTD 6.01 ND N/A ND 1.62 ND N/A ND Unit I and Unit 2 Feed Wntcr 12.32 ND N/A ND Heater Ground Area and 0.7 N .. N/A ND Floor Platform (Pre-leoators) 0.75 . 5ND N/A ND_.......

(Survey Unitl02BS2) 22.50 0.58 N/A ND 5.47 01.301 N/A ND 1.65 ND N/A ND 0.64 ND N/A NID 0.59 ND N/A ND 0.52 ND N/A ND Noler:

1. RsUIL in botd print indiwalcs coaxcti atim is grcaiei thaan tv.d!.rjond levvds.

2. NI) = NmorDclcctbk. RtJII less than I-bolaor,' *mahblis 'evdMWC

3. N/A - AwaisZs ". rcqucsf(d for sample.

HBPP-RPT-00 I 42

Humboldt Bay Power Plant Characterization Report 4.1.3 Class 3 Areas 4.1.3.1 Soils Two Class 3 survey areas were surveyed in 2007. 'rho purpose of the sampling effort was to characterize the soils in the area designated for the Humboldt Bay Repowering Project (HBRP); also kno\w as the New Gen area. The lillowing is a summary ofhe sar)pling effort in the ItBRP Area. The informnalion was extracted from a lotter dated September 2, 2008, DIU08-004, that was sent to Mr. David Sokolsky, H13PP itcensing Manager, in regards to the "Radiological Status of the H-umboldl Bay Ropowerlng Project Soils." Trhe letter also sunmmarized previous sampling efforts in the HBRP/New Gcn area.

Su!'rvey Package 005SS3, H umb)oldt Bay Renowering Project Area Operational Hlistory of Survey Unit hlie 14BRP area was not involved in typical plant work activities during operation of the IIBPP Unit 3 Nuclear Reactor. 'The Northern portion of this area is downwind of the Unit 3 stack, for the typical Winter South to Southeast winds. A large portion or this area has been covered by fill material with about one third of the rill material placed prior to Unit.3 operation anid about half of the fill material placed since the beginning of Unit 3 operation. The historical activities in filled portions of this survey area are related to landscaping, operation of the Mobile Electric Power Plants (ME1PIs), diesel oil storage, material/equipment storage, painting (and sandblastlog to prepare for painting), oflice space and employee parking. The area has underground piping and electrical conduits, Items of interest in the survey area include the original sunitary sewer leach field lbr UnIt 3 (South of'the Oily Water Separa(or),

and the filled drainage ditch/drainpipe that was constructed parallel to the rail spur roadbed.

Detailed Physical Description of the HBRP This survey unit contains the land area where the HBRP will occur. Some of Ihe survey unit, approximately 50%, is covered by asphalt and/or rock. The remaining surface soil is covered with grass and other natural vegetation. This area has been Initially classified as a MARSSIM Class 3 area due to the very low potential for radiological contamination to be present based off of soil sample data from the IT/Duratek 1997 Characterization effort.

Characterization Survey Instructions Summanr The characterization survey consisted of 14 soil samples and a gamma radiation walkover survey. The design of the Characterization Survey was based on criteria from NUREG-1757, Multi-Agency Radiation HBPP-RPT-0O01 4:3

I Humboldt Bay Power Plant Characterization Report Survey and Site Investigation Manual (MARSSIM). Soil samples were collected at locations (hat were determined by random selection using the current version of Visual Sample Plan. Physical collection of the soil samples was delineated ih the Survey Instructions which Included the sampling process, field decontamination of tools, sample labeling requirements, and sample location. The procedure HPP-OP-002, Chain of Cuwlodi?, was used to delineate the required chain of custody process and requirements to ensure the integrity of the samples collected. Soil samples wero submitted to General Engineering Laboratories (GFL,) for gamma spectroscopy for Cs-137 and Co-60 and for analysis of Ani-241, Pu-239/240, Cm-242/244, Sr-90, and Tritium.

The Survey Instructions also described the procedures to be followed for the gamma radiation walkover survey which covered .100% of accessible surface soil areas using a 2x2 Sodium Iodide (Na)) detector with a scanning speed of less than 0.5 ni/s. The Gamma Walkover survey was performed using a Ludlum Model 44-10 (2" x 2") Nal detector coupled to a Ludlum Model 2221 meter. A TrrilblOD Pathdfider ProXR Global Positioning System (GPS) was used to lag the position and radiation measurements collected during the gamma walkover survey. The GI'S was also used to located and log the surface soil samples collected in the area.

Characterization Data Resutd*

The survey of the area indicaled no significant detectable contamination from HBPP Unit 3 nuclear reactor operations. One surface soil sample result Indicated a Cs- 137 concentration of"0.653 pCi/g with a two-sigma uncerlainty of +-0.084pCi/g. All other Cs- 137 sample results were less than tde HBPP site established background of 0.5 )Ci/g Cs-137. The Cs-137 and Co-60 results are summarized in Table 4-5 below. All results for Co-60, Am-24 1, Pu-239/240, c01-242/244, Sr-90, and Tritium were not detected.

The result of the soil sample Gamma radiation surveys indicated no levels of gamma radiation greater than twice background.- Laboratory analysis reports from General Engineering Laboratories are attached as well as drawings of the surface soil sample locations and the gamma walkover measurement locations.

l-HBPP-RPT-001 44

Humboldt Bay Power Plant Characterization Report m

Table 4-8, below, summarizes the sample results for (he HBRP nrea, Table 4-8 Results Summary - Ii BRP Surface Soil Samples Cesium - 137 (pCi/_) Cobalt-60 No of No of samples samples Area >MDA Max Mean Std Dev. >MDA Max Mean Std Dev.

OOSSS3 IJIP, Area 8 0.65 0.13 0.17 0 0.02 0.00 0.02 006SS3 IHBRII Access Rd 13 0.4I 0.17 0.11 0 0.02 10oo1 0.01 HBPP-RPT-00 I 45

Humboldt Bay Power Plant Characterization Report 4.1.2.2 Buildings and Structures For Class three areas, trenches and drains were sampled for radioactive material. The samplcs were collected and sent to GEL for analysis. Only a few drains In Class three areas had detectable levels of radioactive materials; of wich, only Cs-137 was detected. No alpha emitting radionuclides were detected and Co-60 was not detected. Table 4-8 below provides a summary of the analysis data for samples with delectable levels of radioactive materials, The GEL laboratory reports are contained *i Appendix D.

Table 4-9 Results Summary - Class 3 Drain and Trench Samples

,, Result (p/g)(GEL Reportl 217584)

Sample Numnher/iLocation Cesium-137 Cobahl-60 Plutonium-239/240 Americium-241 0.26 ND ND ND 0.34 ND ND ND 0.36 ND ND ND Office and Shop Structures (Survey Unit 028BS3) 0.44

....... NTD ND NDD 0.40 NrD ND ND 0.40 ND) NI) ND 0.51 ND ND ND 0.41 ND ND ND 1.07 ND NIA ND 0.35 ND NIA ___ND ND Switohyard Structures 0.40 ND N/A (Survey Unit 067BS3) 0.17 ND NI/A ND 0.20 NI) N/A ND Fire Water P-1 louse 073BS3 0.60 ND N/A ND MEPPS Ctl Bldg 075/076BS3 0.53 NI) ND ND Security Bldg 0771S3 0.42 ND N/A NTD Notes:

I. RcuII in bold th-int indintes cor.cenlrction is Vrcr .ann bqdkgsound Ives, ,

I ND - Non-Dttiable. RevI! iW.% than labx*,oycs'ablisheJ MDC.

3, NIA - Analysis not jiucv.d for samplc.

IIBPP-RPT-001 46

Humboldt Day Power Plant Characterization Report 5.0 Conclusions Characterization surveys were conducted at HBPP following a MARSSIM process described In 14BPP-PP-003, Site ClharacterizatlOnI Plan. After performing an area walkdown and an analysis of prior characterization data, each survey was planned using an HBPP Work Control Package and a Characterization Survey Package. The Characterization Survey Package was used to document the survey instructions, the history of each area, a detailed description ofeeach area, pictures, and data results.

The work control package was used to notify area supervisors of pending work and to establish the required safety protocols.

The radlologleal characterization surveys showed that surveyed areas of HBPP that were impacted by the operation of the Unit 3 nuclear reactor. However, not all measurements and samples exhibited detectable contamination. Where detected, the levels of contamination are low and are typically limited to building roofs, drains and/or trenches. For soils, tile levels of contamination, when detected in a sample, were significantly less than the potential site specific Derived Concentration Guideline Levels (DCGL) that are being developed Ior the 1IBPP iTP industrial release scenario. All sample results tbr Class 2 and Class 3 soils were less than the NRC Radionuclide Screening values, which are less that the industrial release scenario DCOLs by a factor of approximately 5. Nearly all radiologieal measurements for Class 2 and Class 3 buildings and surfaces were less than the HBPP release values that are based oil Rog Guide 1.86.

The HIBPP Characterization data will be used, in conjunction with previous data, to support the Humboldt Bay Power Plant License Termination Plan. In addition, revision of lhe 111311P HiiSA to include the new characterization data should be completed, I-IBPP-RPT-001 47

or Humboldt Bay Power Plant Characterization Report 6.0 Rererences NURIG- 1757, Revision 1,August 2000, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM).

HIBPP-PP-003 Rev. 0 Site Characterization Plan IIIBPP-OP-002 Rev. 0 Chain of Custody I I3PP-OP-005 Rev. 0 Radiological Surveys 7-HBIPP-OP-006 Rev. I Instimment Source and Response Check I 131PP-OI-00S Rev. 0 Field Decontamination of Sampling Equipment H.'PP-OP 009 Rev. 0 Sampling Malerials for Radiological Characterizalion "

HBI1P-O1-010 Rev. 0 Sample HandLing IJBPP-OP-0I I Rev. 0 Radiological Characterization Scans and MeasurcnewnLt HBPP-OP-012 Rev. 0 'Iechnlclan Training, Qualifications and Authorization Battelle, 1983, Residual Radionuclide and Inventory at the Humboldt Bay Nuclear Power Planil.

GTS Durnlek, 1998a, Backgr-ound Study for the HuImboldt flay Power Plant.

GTS Duratek, 1998b, Struhtural Characterization Report for the Ilumboldt Bay Power Plant.

(I'PS Dutatek, 1997a, HIBPP Site Radiological Characterlzalion Quality AstIrnMce Project Plan.

OTS Duratek, 1997b, Sample Antalysis and Data Munagenen*t Plan.

OTS Duratek, 1997e, lllness and Injury Prevention Plan.

IT Corporation, 1997a, Environtmental Radiological Survey Plan.

IT Corporation, 1997b, Calculation of Soil Cleanup Guidelines for Residual Radionuclides at the PG&E Humboldt Bay Power Plant.

I-IBPP-RPT-001 48

HBPP Work Package SAPN Listings and Survey Packages

• Work Package SAP# 1246478 - First Work Order o Survey Package 073BS3 - Fire Water Pump House

• 08-001, 29/05/2008, Ceiling Fire Water Pump House

• 08-002, 29/05/2008, Fire Water Pump.House Interior

• 08-003, 29/05/2008, Fire Water Pump Hlouse Exterior

• 08-004, 29/05/2008, Fire Water Pump House Roof

,08-005, 29/05/22008, Fire Water Pump I louse Floor

• 08-179, 20/09/2008, QC2 of Fire Water Pump House

• 08-180, 21/09/2008, QA of Fire Water Pump Ilouse a Work Patckajc SAP# 1246478 - Second Work Order

• 08-008, 30/05/2008, Unit I & Unit 2 Asbestos Containing Mate"ial.

"08-016, 09106/2008, Unit I & Unit 2 Trenches ,& Drains Package O11BS2 - Unit 1 Ground Floor (+12 Elmv,)

o Survey ,08-009, 30/05/2008, Unit 1 Ground Floor

"08-010, 03/06/2008, Unit 1 Ground Floor Walls08-020, 20/06/2008, Unit 1 1.12 Ceiling

) Survey Package 1)12BS2 - Unit I Second Fhoor (+27 Elcv.)

0(8-013, 09/06/2008, Unit 1 2nd Floor, Floor

• 08-023, 23/06/2008, Unit 1 -27 Walls

"08-027, 23/06/2008, Unit 1 +27 Ceiling (1 of 2)

• 08-028, 23/06/2008, Unit 1 127 Ceiling (2 o1"2) o Survey Package 0130S2 - Unit 2 G round Floor (+12 E11v)08-011, 03/06/2008, Unit 2 Ground Floor

• 08-021,20/06/2008, Unit 2 +12 Ceiling 024, 23/06/2008, Unit 2 112 Walls

, 08&053, 16/07/2008, Unit 2 12' Walls 2

• 08-111, 27/08/2008, Unit 2 +12 Walls 3 o Survey Package Ol4BS2- Unit 2 Ground Floor (+27 Elcv,)08-012, 09/06/2008, Unit 2 27' Floor

• 08-015, 09/06/2008, Unit 2 27' Walls

"08-025, 23/06/2008, Unit 2 +27 Ceiling (I of 2)

N 08-026, 23/06/2008, Unit 2 +27 Ceiling (2 of 2) o Survey P'ackage 060BS3 - Relay Building 08-006, 30/05/2008, RelayBuilding Interior 08-007, 30/05/2008, Relay Building Exterior o Work Package SAP#-Work Order U1-4 o Survey Package 009BS2- Unit 1 Ventilation Intake 08-206, 29/09/2008, Unit I Stack and Exhaust Structures08-268, 15/10/2008, Unit I Intake Ducting, Fan, & Fan Motor Exterior o Survey Package 021BS2- Unit 1 Condenser

• 08-104, 23/08/2008, Unit I Condenser o Sunvcy Package 022BS2 -Unit I Boiler/Firebox N Surveyed within 023BS2-Unit 1 Building Structures

Work Package SAP# 1246478 - Work Order UL-2 o Survey Package 020BS2 -Unit I Seal Oil Room

• 08-017, 16/06/2008, Unit I Seal Oil Room Roof 08-018, 1710612008, Unit 1 Seal Oil Room Exterior

• 08-019, 17/0612008, Unit 1 Seal Oil R0om hiterior o Survey Package 023BS2- Unit I Building Structures

• 08-047, 11/07/2008, Unit 1 97.5' Structures08-048, 11/07/2008, Unit 1 73' Structures Additional Points

• 08-049, 11/07/2008, Unit 1 64' Structures Additional Points

• 08-055, 17107/2008, Unit 1 56' Structures Additional Points

• 08-056, 17/07/2008, Unit 1 47.5' Structures Additional Points

• 08-057, 17/07/2008, Unit t 80' Structures Additional Points

• 08-059, 18/07/2008, Unit 1 27' Structures Additional Points08-060, 23/07/2008, Unit 1 27' Structures

• 08-061, 23/07/2008, Unit 147.5' Structures

• 08-062, 23/07/2008, Unit 1 56' Structures

• 08-063, 23/07/2008, Unit 164' Structures

• 08-064, 23/07/2008, Unit 1 73' Structures

• 08-065, 23/07/2008, Unit 1 80' Structures o Survey Package 098BS2 -Unit I Roofs08-022, 20/06/2008, Unit 150' Roof

• 08-029, 23/06/2008, Unit 1 42' Roof South

• 08-030, 24/06/2008, Unit 1 42' Roof Northwest

"08-031, 24/06/2008, Unit 1 42' Roof(resurvey)08-032, 25/06/2008, Unit I Penthouse Roof

• 08-033, 25/06/2008, Unfit I Penthouse Roof (resurvey)

• 08-038, 26/06/2008, Unit 1 42' Roof Northeast Work Package SAPI 1246729 Work Order U2-1 o Survey Package 015BS2 - Unit 2 Seal Oil Room

• 08-041, 01/07/2008, Unit 2 Seal Oil Room Interior 08-044, 02/07/2008, Unit 2 Seal Oil Room Roof 08-045, 07/07/2008, Unit 2 Seal Oil Exterior Walls o Survey Package 0181BS2 - 2.4 kV Room

• 08-046, 09/07/2008, Unit 2 2.4 kV Room o Su rvey Package 019BS2 - Unit 2 Building Structures

• 08-066, 25/07/2008, Unit 2 46 Foot Structures

• 08-067, 25/07/2008, Unit 2 80' Structures

• 08-068, 25/07/2008, Unit 2 73' Structures08-071, 05108/2008, Unit 2 56' Structures (1 of 3)

"08-072, 05/08/2008, Unit 2 56' Structures (2 of 3)08-073, M 05/08/2008, Unit 2 56' Structures (3 of 3)

,08-074, 05/08/2008, Unit 2 64' Structures (1 of 4)

• 08-075, 05/08/2008, Unit 2 64' Structures (2 of 4)

"08-076, 05/08/2008, Unit 2 64' Structures (3 of 4)

• 08-077, 05/08/2008, Unit 2 64' Structures (4 of 4)

• 08-079, 05/08/2008, Unit 2 97.5' Structures

• 08-080, 05/08/2008, Unit 2 27' Structures

• 08-101, 20/08/2008, Unit 2 47.5' Structures o Survey Package 029BS2- Unit 2 Oily Water Sump

• 08-203, 25/09/2008, Unit 2 Oily Water Sump o Survey Package 099BS2- Unit 2 Roofs

• 08-039, 27/06/2008, Unit 2 Penthouse Roof

• 08-040, 30/06/2008, Unit 2 42' N13 and NW Roof

• 08-042, 01/07/2008, Unit 2 50' Roof

• 08-043, 01/07/2008, Unit 242' Roof South Work Package SAP# 1246832 - Work Order U2-2 o Survey Package 025BS2 - Cold Machine Shop

• 08-146, 13/09/2008, Cold Machine Shop Floor 08-164, 16/09/2008, Cold Machine Shop Walls08-202, 25/09/2008, Cold Machine Shop Ceiling and Upper Wails o Survey Package 026BS2- Welding Shop

• 08-177, 20/09/2008, Weld Shop Floor and Brick

• 08-185, 23/09/2008, Weld Shop Walls & Ceiling o Survey Package 027BS2 - Warehouse 08-147, 13/09/2008, Warehouse Floor

• 08-176, 20/09/2008, Warehouse Interior 008-194, 24/09/2008, Warehouse Interior Pt. 1 o Survey Package 028BS2,- Office and Shop Structures08-181, 21/09/2008, Office & Shop Interior Wails and Ceiling 08-182, 21/09/2008, Office & Shop Interior Floors

• 08-212, 01/10/2008, Office & Shop Roofs08-215, 01/10/2008, Office & Shop ilxterior o Survey Package 101BS2 - Unit 1 & 2 0 and 2 'od Floor Exteriors08-226, 03/10/2008, Penthouse #2 Exterior Walls

• 08-227, 03/10/2008, Penthouse 1IIExterior Walls Survey Package Completed within other Survey Packages o Survey Package 102BS2 - Unit I & 2 Pre- llcater Areas and Outside

• 08-183, 23/09/2008, Pre-heater Pad Second Level (Part 1 of 2)

• 08,184, 23/09/2008, Pre-hcater Pad Second Levcl (Part 2 of 2)

• 08-190, 23/90/2008, Pre-heater Pad

,08-197, 24/09/2008, Unit 2 Pre-heaters

• 08-210, 30/09/2008, Unit I Pro-heaters Work Package SAPN 1247496 o Survey Package O1OBS2 - Unit 2 Ventilation Intake

• 08-144, 12/09/2008, Unit 2 Steam Drum 145, 12/09/2008, Unit 2 Air Inlet Exterior

• 08-165, 16/09/2008, Unit 2 Intake Fan Housing (I of 3)

,08-175, 19/09/2008, Unit 2 Intake Fan Housing (2 of 3)

• 08-178, 20/09/2008, Unit 2 Intake Fan Housing (3 of 3)

• 08-187, 23/09/2008, Unit 2 Characterization of Air Intake Pt. 1

• 08-188, 23/09/2008, Unit 2 Characterization of Air Intake Pt. 2 08-189, 23/09/2008, Unit 2 Characterization of Air Intake Pt. 3

K 08-207, 29/09/2008, Unit 2 Exhaust Support Structure I 08-208, 29/09/2008, Unit 2 Exhaust Stack o Survey Package 016BS2- Unit 2 Condenser a 08-186, 23/09/2008, Unit 2 Condenser o Survey Package 0.17BS2 - Unit 2 Boiler/Firebox

• 08-132, 09109/2008, Unit 2 Firebox Interior X 08-133, 09/09/2008, Unit 2 Firebox Exterior X 08-195, 24/09/2008, Unit 2 Lower Exhaust to Stack Building

• Work Package SAP# 1247474 - Work Order U3-2 o Survey 032BS1 - Unit 3 Seal Oil Room

• 08-246, 11/10/2008, Unit 3 Seal Oil Room Floor 08-247, 11/10/2008, Unit 3 Seal Oil Room Ceiling

• 08-248, 11/10/2008, Unit 3 Seal Oil Room Walls

• Work Packa -e SAPH 1247474- W.ork Order U3-3 o Survey Package 04413S1 - Unit 3 Propane Engine Geucrator 08-220, 02/10/2008, Propane Generator Interior Floor

,"08-221, 02110/2008, Propane Generator Interior Walls 08-23 I, 03/10/2008, Propane Generator Room hIterior Ceiling 08-232, 07/10/2008, Propane Generator Room Exterior Walls o Survey Package 046BSI -Unit 3 Generator/Exciler n 08-243, 10/1012008,Generator/Exciter EMerior Surfaces08-257, 13/10/2008, Unit 3 Exciter Interior & Exterior Floor

• 08-258, 13/10/2008, Unit 3 Generator/Exciter Drains08-259, 13/10/2008, Unit 3 GCencrator/1'xcitcr Interior Walls & Ceding

• 08-270, 17110/2008, Unit 3 Generator/lxciter Building Walls Work Package SAVP# 1247474 - Work Order U3-6 M

o Survey Package 095BS1 - Unit 3 Roof

• 08-261, 14/10/2008, Unit 3 Roof Work Package SAPN 1246914 - Work Order BS-1 o Survey Package 082BS3 -Fuel Oil Slorage Tanks

• 08-069, 30/07/2008, Fuel Tank 2 Roof

• 08-070, 04/08/2008, Fuel Tank 2 Outer Walls

• 08-081, 06/08/2008, Fuel Oil Storage T'ank #1 Walls08-083, 08/08/2008, Fuel Oil Storage Tank I/l Roof o Survey Package 083BS3 - Diesel Fuel Tanks

• 08-094, 15/08/2008, Light (Diesel) Tank Walls

• 08-095, 15/08/2008, Light (Diesel) Tank Roof o Survey Package 084BS2- Distilled Water Tanks08-105, 26/08/2008, Distilled Water Tank Walls- 08-106, 26/08/2008, Distilled Water'Tank Roof o Survey Package 069BS3 -Fuel Oil Service Tanks

• 08-091, 14/08/2008, Service Tank 2 Walls

• 08-092, 14/08/2008, Service Tank 1 Walls

• 08-096, 18/08/2008, Service'rank I Roof

• 08-100, 20/08/2008, Fuel Oil Service Tank 2 Roof o Survey Package 072BS3- Freshwater Tank

5-

• 08-098, 19/08/2008, Fresh Water Tank Roof 08-103, 22/08/2008, Fresh Water Tank Walls o Survey Package 085BS3 - Lube Oil ranks

• 08-107, 26/08/2008, Lube Oil Storage Tank Roofs

• 08-108, 26/08/2008, Lube Oil Storage Tank Walls

• 08-109, 26/08/2008, Lube Oil Storage Tank Basin Work Package SAP# 1247167 - Work Order BS-2 Al o Survey Package 063BS3-Assembly Building 08-116, 29/08/2008, Assembly Building Interior

• 08-148, 15/09/2008, Assembly Building Roof

• 08-149, 15/09/2008, Assembly Building Exterior Walls o Survey Package 064BS3 -,Training Building 08-129, 05/09/2008, Triining Building Roof

• 08-150, 15/09/2008, Training Building Interior 08-166, 17/09/20t8, Training Building Fxtcrior and Overhang o Survey Package 065BS3 - Out-of-Stock Warehouse m 0(8-138, 11/09/2008, Out-of-Stock Interior Walls

• 08-154, 15/09/2008, Out of Stock Warehouse Floor

• 08-159, 15/09/2008, Out of Stock Exterior Walls

• 08-161, 16/09/2008, Out of Stock Warehouse Floor Pt, 2 o Survey Package 0681BS3- Rigger's Shed

• 08-158, 15109/2008, Rigger's Shed Interior

• 08-171, 17/09/2008, Rigger's Shed Exterior Surlhces o Survey Package 074 BS3 -Office Aunex 0(8-124, 03/09/2008, Aux. Admin Building Roof 08-151, 15/09/2008, Office Amex Interior Walls

• 08-152, 15/09/2008, Office Annex Floors

• 08-201, 25/09/2008, Office Annex Exterior Walls o SUlr'ey Package t75BS3 - MEPPS 2 & 3 Coitirol Building

• 08-173, 17/09/2008, MIEPPS 2 Interior

• 08-174, 17/09/2008, MMlPS 3 Interior

• 08-191, 24/09/2008, MEI)PS 2 Enclosure & Horizontal Structures

"08-192, 24/09/2008, MEPPS 3 Enclosure & Horizontal Structures08-196, 24/09/2008, MEPPS 2 & 3 Control Trailer Roofs

• 08-222, 01/10/2008, MEPPS 2 & 3 Control Trailer Walls08-223, 03/10/2008, MEPPS 2 Enclosure Building fixterior

• 08-224, 03/10/2008, ME PPS 3 Enclosure Building Exterior o Survey Package 077BS3 - Security Building 08-123, 03/09/2008, Security Building Roof

• 08-213, 01/10/2008, Security Building Interior

• 08-214, 01/10/2008, Security Building Exterior o Survey Package 078BS3 - FFD Trailer

• 08-153, 15/09/2008, FFD Trailer Interior

"08-172, 17/09/2008, FFD Exterior Surfaces o Survey Package 081BS3 -Hazardous Waste Storage a 08-130, 05/09/2008, HazMat Building Roof

9 08-160, 15/09/2008, HazMat Storage Interior a 08-170, 17/09/2008, Haz2vfat Building Exterior Surfaces o Survey Package 104BS3 - Metal Storage Building

• 08-139, 11/09/2008, Metal Storage Building Floor

• 08-155, 15109/2008, Metal Storage Roof

• 08-156, 15/09/2008, Metal Storage Exterior Walls

• 08-157, 15/09/2008, Metal Storage Building Interior o Survey Package 105BS3-Paintshop

• 08-118, 02/09/2008, Paintshop North Exterior Wall

• 08-119, 02109/2008, Paintshop Exterior Roof

• 08-131, 05/09/2008, Paintshop Office Building Roof

• 08-140, 11/09/2008, Paintshop Building Exterior South Wall

• 08-142, 11/09/2008, Paintshop Exterior West Wall Work Packagc SAP# 1247761 - Worl( Order BS-2 A2 o Survcy Package 061BS3 - Steam Cleaning Station X 08-230, 07/10/2008, Steam Cleaning Station o Survey Package 062BS3 - Oil/Watcr Separators

• 08-266, 14/10/2008, Oily Wiater Separators, Concrete & Pits

• 08-267, 14/10/2008, Oily Water Separators, Separators & Walkways

• Survey Package 066BS3 - In(akc Structures i 08-233, 08/10/2008, Feed Water Intake (Ground) a 08-269, 15/10/2008, Intake Structure Pits & Pump Wells o Survey Package 067BS3- Unit 3 Transfer Yard Structures 1 08-265, 14/10/2008, Unit 3 Transfer Yard Structures o Survey Package 070BS3 - 13ydrogen Bottle Storage

• 08-262, 14/10/2008, Hydrogen Storage Building Open Air-Interior 08-263, 14/10/2008, lydrogen Storage Building Enclosed Room Interior

• 08-264, 14/10/2008, Hydrogen Storage Building Exterior o Survey Package 071BS3 - Propane Tanl(

a 08-228, 06/10/2008, Propane Tank o Survey Package 0763S3-MrEPP Contirol Building a 08-167, 17/09/2008, MEPP Control Bldg. Interior Office Space Wall and Ceiling

"08-168, 17/09/2008, MEPP Control Bldg. Interior Office and Equipment Space Floors N 08-169, 17/09/2008, M17PP Control Bldg. Interior Equipment Space Wall and Ceiling a 08-193, 24/09/2008, MEPP Control Building Roof 0 08-225, 03/10/2008, MEPP Control Building Enclosure e Work Package SAP# - Work Order BS-3 o Survey Package 086SD1- Discharge Canal a 08-229 Discharge Canal Samples o Survey Package 088S11 - Radwaste Piping Below Grade

"08-050, 14/07/2008, Soil Bores a 08-051, 15/07/2008, Soil Bores M 08-054, 16/07/2008, Soil Bores

IIIIIIII- 1 r r 1.

1 R O'

"08-058, 14/07/2008, Soil Bores

• 08-112, 27/08/2008, Hland Bore RNY-35 and RNY-41 08-113, 28/08/2008, Hand Bore RNY-31+33

• 08-114, 28/08/2008, Hand Bore RNY-38, 39, & 40

• 08-115, 29/08/2008, Deer Bore RI)VB13-74 08-117, 29/08/2008, Hand Bore 34, 35 08-120, 02/09/2008, lland Bore 4, 5, 6, 7, 8, & 9 f 08-121, 03/09/2008, Hand Bores (6) and 10 Samples a 08-122, 03/09/2008, land Bores RCS 46-49 a 08-125, 04/09/2008, Hand Bores RWT 16 & 18 0 08-126, 04/09/2008, land Bores (3 1loles & 6 Samples)

"08-127, 04/09/2008, Boring RDVB-76 I i Samples N 08-128, 05/09/2008, 5 1land Bores 12 Samples i 08-134, 09/09/2008, 1-land Bore RCS 42-45 & 50 08-136, 10/09/2008, 1land Bore RCS 51, 52, 53, & 77 008-137, 10/09/2008, Hand Bore RIDV\B-75

"08-141, 11/09/2008, RDVB-75

• 08-143, I I/)9/2008, I land Bore RNY-37 o Surcey Package 098SB2- Well Insiallation Samples

• 08-078, 05/08/2008, Tritiumn Well Installation

• 08-082, 07/08/2008, Tritium Well Installation

"08-084, 11/08/2008, Triitiwn Well Installation

"08-090, 13/08/2008, Tritium Well Installation C-I

• 08-099, 19/08/2008, Tritium Well 098BSW-RCW-CS-02

• 08-102, 21/08/2008, Tritium Well 098BSW-SFH-I

• 08-110, 26/08/2008, Tritium Well 098BSW-RCW-CS-3