ML16250A432

Final Report - Confirmatory Survey of the Fuel Oil Tank Area

ML16250A432
Person / Time
Site:	Humboldt Bay
Issue date:	04/09/2012
From:	Adams W Oak Ridge Institute for Science & Education
To:	John Hickman NRC/NMSS/DWM
References
5167-SR-01-0
Download: ML16250A432 (62)

Text

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• OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION E

Managed by ORAU for the U .S. Depertment of Energy April 9, 2012 Mr. John Hickman Mail Stop: T-E18 Division of Waste Management

.S. uclear Regulatory Commission 11545 Rockville Pike Rockville, NID 20852

SUBJECT:

FINAL REPORT-CONFIRMATORY SURVEY OF THE FUEL OIL TANK AREA, HUMBOLDT BAY POWER PLANT, EUREKA, CALIFORNIA DCN: 5167-SR-01-0

Dear Mr. Hickman:

The Oak Ridge Institute for Science and Education (ORISE) performed confirmatory radiological survey activities on the former Fuel Oil Tank Area and other portions of the Humboldt Bay Power Plant as requested by the .S. Nuclear Regulatory Commission (NRC) site representative. These survey activities were conducted during the period of Febmary 14 and 15, 2012. Enclosed is the final report that summarizes ORISE's survey procedures and provides the results of the ORISE radiological survey activities. The surveys included gamma walkover scans, gamma direct measurements, and soil sampling.

My contact information is listed below, or you may contact E rika Bailey at 865.576.6659 or Tim Vitkus at 865.576.5073, should you require any additional information.

Wade C. Adams Project Manager/Health Physicist Independent Environmental Assessment and Verification WCA:fr Enclosure c: G. Schlapper, NRC Region IV R. Evans, NRC Region IV T. Carter, NRC HQ File 5167 electronic: S. Roberts, ORISE/IEA V T. Vitkus, ORISE/IEA V E. Bailey, ORISE/IEAV A. Hood, ORISE/IEAV Telephone: 865.576.0065 Fax: 865.241.3497 E-mail: Wade.Adams@orau.org P.O . Box 117 I Oak Ridge. TN 37831 I www .ons e.orau.gov

CONFIRMATORY SURVEY OF THE FUEL OIL TANK AREA HUMBOLDTBAYPOWERPLANT EUREKA, CALIFORNIA W. C. Adams Prepared for the U.S. Nuclear Regulatory Commission Approved for public release; further dissemination unlimited.

The Oak Ridge Institute for Science and Education (ORISE) is a U.S. Department of Energy facility focusing on scientific initiatives to research health risks from occupational hazards, assess environmental cleanup, respond to radiation medical emergencies, support national security and emergency preparedness, and educate the next generation of scientists. ORISE is managed by Oak Ridge Associated Universities.

NOTICES The opinions expressed herein do not necessarily reflect the opinions of the sponsoring institutions of Oak Ridge Associated Universities.

This report was prepared as an account of work sponsored by the United States Government.

Neither the United States Government nor the U.S. Department of Energy, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe on privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, mark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement or recommendation, or favor by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof.

CONFIRMATORY SURVEY OF THE FUEL OIL TANKAREA H UMBOLDT BAY POWER PLANT EUREKA, CALIFORNIA Prepared by W. C. A dams

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OR IS E Independent E nvironmental Assessment and Verification Program Oak Ridge Institute for Science and Education Oak Ridge, Tennessee 37831-0017 Prepared for the U.S. Nuclear Regulatory Commission FINAL REPORT APRIL 2012 This report is based on work performed by the Oak Ridge Institute for Science and E ducation under contract number DE-AC05-060R23100 with the Department of Energy.

Prepared by the Oak Ridge Institute for Science and E ducation, under interagency agreement (NRC FIN o. F1008) between the U.S. uclear Regulatory Commission and the U.S. Department of Energy.

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• OAK RIDGE INSTITUTE FOA 8CtENCE AND EDUCATION

- - - - - - - - - - - - - ManegedbyORAUfCM'theU.S.oepwtmentofEnergv CONFIRMATORY SURVEY OF THE FUEL OIL TANKAREA HUMBOLDT BAY POWER PLANT EUREKA, CALIFORNIA Prepared by: Date 'f/q (n_

W. C. Adams, Health Physicist/Project Manager Independent Environmental Assessment and Verification Pr gram Reviewed by:

ey Operations Director Date 1/{bB-Independent E nmental Assessment and Verification Program Reviewed by ft,;'rUY f. ~ Date: .l/J 9/J Z.

W. P. Ivey, LaborntoGroup Manager Independent Environmental Assessment and Verification Program Reviewed by i1 ~ ~ ~A ~

lf.H~Bto\T;iualitYAs;urnncespecialist Independent Environmental Assessment and Verification Program Approved for release by: { ),

E. N. Bailey, Survey Projects Independent Environmental and Verification Program HBPP Fuel Oil Tank Area, Eureka, CA 5167-SR-01 -0

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~~~~~~~~~~~~~~~~~~~~~~~ Monepd ~ORAU ~~ U ~ o.p.1ment~ £nervy CONTENTS FIGURES . . . ..................... ............................................................................................................ ...................... v TABLES ......................................................................................... ..................................................................vi ACRONYMS ..................................................... .............................................................................................. vii

1. INTRODUCTIO A D SITE HISTORY .................................. ..........................................................1

2. SITE D E SCRIPTION ................................................................................................ ................................. 2

2. 1 FUEL OIL TA KAREA (FOTA) ...................................................................................................2 2.2 U IT 1 AND U IT 2 CONCRETE P ADS ... ..... ....... .. ....... ... .... ... .. ... ..... ....... .... .......... ....... .... ... ......... 2 2.3 ORTHEAST L AYDO AREA .................................................................. ...................................3 2.4 NE\V ASPf-L\LT R OADWAY .. ...... ........ ......... ............................................. ...... ... ....... ..... ..... ... ......... 3

3. OBJECTIVES ................................................................................................................................................ 3

4. DOCUMENT REVIEW .............................................................................................................................3

5. DATA QUALITY OBJECTIVES .............................................................................................................4

6. CO FIRMATORY RADIOLOGICAL SURVEY PROCEDURES ................................................. 5 6.1 SURVEY u IT CLASSIFICATIO ..... .. .......... ...... ... .... .... ... .... ......... ... ..... .... ... ......... .... .... ... ..... ..... ... . 5 6.2 REFERENCE SYSTEl\f .... ........ ..... .... ..... ..... ... .... ... ....... .... .. ... .............. .... ................ .. .. ..... ..... .. ... ....... 6 6.3 SURFACE SCANS .. .. ... ......... ...... .... ..... ....... ... ....... ... ... ... ......... .... ........... ... ...... ... ......... ..... ... ....... .... .. .. 6 6.4 GAMl\f.A D IRECT MEASUREl\fENTS ... ..... ...... .. ............ ......... ..... ......... ..... ................. ..... .. ... .. ......... 6 6.5 SOIL SAl\IPLING ..............................................................................................................................6 6.5. 1 System atic Sample Locations .................................................................................................. 6 6.5.2 Judgmentally-Selected Sample Locations ....................... .. ..................................................... 7 6.6 INTERLABORATORY COMPARISON ANALYSES .................. ..................... ............... ...... ......... ..... 7

7. ADDITIONAL RADIOLO GICAL SURVEY PROCEDURES ........................................................8

8. RADION UCLIDE S OF CONCERN ...................................................................................................... 8 9.SAMPLEA ALYSIS A DDATA I TERPRETATIO ...............................................................10

10. FINDI GS AND RESULTS ........................................................................................... ......................10 10.1 D OCUl\ffi TREVIEW .... .. ........ .. .... ,..... ..... ........ .. .......... ... .... ................. ............... ... ......... ... ... ....... 10 10.2 SURFACE SCANS ..... ... ........ ... .... ...... ................ ..... ......... ..... .. ....... ..... .. ........ ... ....... .. ...... ........... ..... . 10 10.3 GAMl\f.A D IRECT MEASUREl\ffiNTS ... ... ............ ..... .................................. .. .... ... ..... .. ...... ......... .. .. 11 10.4 RADIO UCLIDE Co CE TRATIONS IN Co FIRMATORY SOIL SAMPLES ... ... ... .... .. ........... .. 11 HBPP Fuel Oil Tank Area, Eureka, CA 111 51 67-SR-01-0

10. 5 .RADIONUCLIDE CONCENTRATIONS IN INTERLABORATORY COMPARISON ANALYSES SOIL SAMPLES....................................................................... ..................................................... ...12

11. COMPARISON OF RESULTS WITH RELEASE CRITERIA. ............................. ........................ 12

12. ADDITIONAL RADIOLOGICAL SURVEY ACTIVITIES ......................... .. .. .. ..........................13 12.1 UNIT 1 AND UNIT 2 - GAMMA WALKOVER SCANS.............................................................. ...13 12.2 NORTHEAST LAYDOWN AREA - GAMMA WALKOVER SCANS........ ....................................... 13 12.3 NEWASPHALT ROADWAY - GAMMA WALKOVER SC\NS ...................... ........................... .....13

13.

SUMMARY

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10. REFERENCES ......................................................................................................................................... 15 APPENDIX A: FIGURES APPEND IX B: TABLES APPE NDIX C: MAJO R INSTRUMENTATIO N APPENDIX D : SURVEY AND ANALYTICAL PROCED URES HBPP Fuel Oil Tank Area, Eureka, CA lV 5167-SR-01-0

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FIGURES Fig. A-1. Site Location Map - Humboldt Bay Power Plant, Eureka, California ................................. A-1 Fig. A-2. Humboldt Bay Power Plant - Site Overview of Surveyed Areas ......................................... A-2 Fig. A-3. HBPP Fuel Oil Tank Area - Gamma Walkover Scans .......................................................... A-3 Fig. A-4. HBPP FOTA - PG&E Systematic Soil Sample Locations .................................................... A-4 Fig. A-5. HBPP FOTA - Confirmatory Soil Sample Locations ............................................................. A-5 Fig. A-6. HBPP Unit 1 and Unit 2 Concrete Pads - Gamma Walkover Scans ................................... A-6 Fig. A-7. HBPP Northeast Lay down Area - Gamma Walkover Scans ................................................ A-7 Fig. A-8. HBPP New Asphalt Roadway - Gamma Walkover Scans .................................................... A-8 Fig. A-9 . HBPP Fuel Oil Tank Area - Gamma Scan Count Rate Distribution .................................. A-9 Fig. A-10. Fuel Oil Tank Area - Pictures of the Natural Strata Layer that Exhibited Elevated Gamma Radiation Levels ........... ............................................... .............................................. ... A-10 Fig. A-11. HBPP Units 1 & 2 Concrete Pads - Gamma Scan Count Rate Distribution ................. A-11 Fig. A-12. HBPP Northeast Laydown Area Asphalt Pad- Gamma Scan Count Rate Distribution ............................................................................................................. A-12 Fig. A-13. HBPP New Asphalt Roadway- Gamma Scan Count Rate Distribution ........................ A-13 HBPP Fuel Oil Tank .Area, Eureka, CA v 5167-SR-01-0

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• OAK flllOOm .-nTUlW fOft 9CCNC9: AHO U>UCAllOH TABLES Table 1. Derived Concentration Guideline Levels for Surface Soil Radionuclides-of-Concern Humboldt Bay Power Plant E ureka, California ............................................................................. 9 Table 2. Radionuclide Concentrations in FOTA Soil Samples Summary Results ................................. 11 Table B-1. Radionuclide Concentrations in ORISE Soil Samples .......................................................... B-1

• Table B-2. Fuel Oil Tank Area Comparison Data .................................................................................... B-2 Table B-3 . Radionuclide Concentrations in Interlaboratory Comparison Soil Samples ..................... B-4 HBPP Fuel Oil Tank Area, Eureka, CA vi 5167-SR-01-0

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- - - - - - - - - - - - - - - - - - - - - - - - - - - MenepdbyORAUforhtU.S. Depw1montofl!ntM"VY ACRONYMS CPR Code of Federal Regulations cpm counts per minute CSPW Characterization Survey Planning Worksheet DCGL derived concentration guideline level DQO data quality objectives ESI Enercon Services, Incorporated FOTA Fuel Oil Tank Area PSS final status survey GPS global positioning system GWS gamma walkover scans HBPP Humboldt Bay Power Plant HBRP Humboldt Bay Repowering Project IEAV Independent Environmental Assessment and Verification MARSSIM Multi-Agency Radiation Survey and Site Inves tigation Manual MDC minimum detectable concentration MeV million electron volts MWe megawatt electric NORM naturally occurring radioactive material NRC U.S. Nuclear Regulatory Commission OOL Open Outside (of RCA) Land Area ORAU Oak Ridge Associated Universities ORI SE Oak Ridge Institute for Science and Education pCi/g picocunes per gram PG&E Pacific Gas & Electric Company RCA radiological control area RER Replicate Error Ratio ROC radionuclide of concern SAFSTOR cold shutdown and safe storage SOR Sum-of-Ratios SPCS State Plane Coordinate System SU survey unit HBPP Fuel Oil Tank Area, E ureka, CA vu 5167-SR-01-0 L

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CONFIRMATORY SURVEY OF THE FUEL OIL TANK AREA H U MBOLDT BAY POWER PLANT EUREKA, CALIFORNIA

1. INTRODUCTION AND SITE HISTORY The Pacific Gas & Electric Company (PG&E) operated the Humboldt Bay Power Plant (HBPP)

Unit 3 nuclear reactor near Eureka, California under U.S. Atomic Energy Commission provisional license number Demonstration Power Reactor license DPR-7. HBPP Unit 3 achieved initial criticality in February 1963 and began commercial operations in August 1963. Unit 3 was a natural circulation boiling water reactor with a direct-cycle design. This design eliminated the need for heat transfer loops and large containment structures. Also, the pressure suppression containment design permitted below-ground construction. Stainless steel fuel claddings were used from startup until cladding failures resulted in plant system contamination-zircaloy-clad fuel was used exclusively starting in 1965 eliminating cladding-related contamination. A number of spills and gaseous releases were reported during operations resulting in a range of mitigative activities (see ESI 2008 for details).

In July 1973, Unit 3 was shut down for annual refueling and seismic modifications. However, by December 1980 it was concluded that completing the required upgrades and restarting Unit 3 would be cost prohibitive. PG&E decided in June 1983 to decommission Unit 3, received a possession-only license amendment, and placed the unit into cold shutdown and safety storage (SAFSTOR). Unit 3 is currently undergoing decommissioning. Decommissioning activities have also been completed on the adjacent fossil fuel Units 1 and 2, with all materials being removed to ground level. As part of the Humboldt Bay Repowering Project (HBRP), PG&E has built ten new fossil fuel units (16.3 MWe [megawatt electric] each) on the site in the vicinity of Unit 3.

Currently, PG&E has demolished the Fuel Oil Tank and has performed final status surveys (FSS) on the former Fuel Oil Tank Area (FOTA) soils. Hence, the U.S. Nuclear Regulatory Commission's (NRC's) Headquarters and Region IV Offices have requested that the Independent Environmental Assessment and Verification (IEA V) Program of the Oak Ridge Institute for Science and Education (ORISE) perform confirmatory surveys of the former FOTA excavation. Due to the small footprint of the site, the licensee has found it necessary to conduct surveys of the decontaminated survey areas and then backfill and / or pave those areas to allow for further decommissioning work.

Therefore, the RC requested that ORISE perform confirmatory surveys coincident with the HBPP Fuel Oil Tank Area, Eureka, CA 5167-SR-01 -0

C>RISE

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- - - - - - - - - - - - - - - - - - - - - - - - - - - MenegedbyORMlfortheU.&~otE.....-gy licensee's surveys and soil sampling prior to backfilling. During the ORISE survey activities, the NRC also requested additional radiological survey activities consisting of gamma walkover scans (GWS) of the newly paved road along the north and east side of the site, the Unit 1 and Unit 2 concrete pads and the Northeast Laydown Area.

2. SITE DESCRIPTION The HBPP site, owned by PG&E, consists of 143 acres on the southern edge of Humboldt Bay four miles southwest of the town of Eureka, in Humboldt County, in the State of California (Fig. A-1).

PG&E maintains ten new operating electric generating units at the HBPP site (in the New Generation Footprint Area) that run on fossil fuels, two non-operating fossil fuel units (Units 1 and 2) and one non-operational nuclear unit (Unit 3). Units 1 and 2, which were recently decommissioned to ground level, were interconnected with and west of Unit 3 (ESI 2008). The remaining property includes mostly open areas and protected wetlands.

2.1 FUEL OIL TANK AREA (FOTA)

The FOTA, pictured in Figs. A-2 and A-3, covers approximately 6,500 square meters (m2) and is located in the northwest section of the HBPP to the west of Units 1 and 2, north of the Intake Canal and south of the Independent Spent Fuel Storage Installation. Within the FOTA is a bermed soil area that contains some asphalt roadway on portions of the berm and concrete pads, which are positioned between an access ramp and metal stairs. With the exception of the areas that were remediated from under the tank and immediately adjacent to the tank due to hydrocarbon contamination, the soil remains at the level that existed when the fuel oil tank was present. FSS activities were performed on a section of the FOTA so that a portion of the FOTA could be used for a soil pile. ORISE did not perform any confirmatory activities of that portion of the FOTA. The FOTA is identified as an Open Outside (of the Radiological Control Area) Land Area (OOL) by PG&E. The survey unit (SU) designation is OOL10.

2.2 UNIT 1 AND U NIT 2 CONCRETE PADS The Unit 1 and Unit 2 concrete pads are located east of the FOTA and west of the nit 3 (the Reactor Building). These were where the fossil fuel units once stood (Fig. A-2). Portions of these pad areas were in use for radiological waste container storage and as material laydown areas and these portions were therefore inaccessible.

HBPP Fuel Oil Tank .Area, Eureka, CA 2 5167-SR-01-0

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2.4 N EW A SPHALT ROADWAY The New Asphalt Roadway stretches from an east/ west direction at the northern portion of the site and curves to a north/ south direction along the eastern portion of the site just east of Unit 3 and west of the Discharge Canal (Fig. A-2).

3. OBJECTIVES The objective of the confirmatory side-by-side survey was to generate independent radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's radiological soil sampling results from the FOTA. Data collected by ORISE and the licensee were reviewed to assess whether classifications based on the Multi-Agenry Radiation Surory and Site Investigation Manual (MARSSIM) (NRC 2000) were appropriate; whether radionuclides of concern (ROCs) were detected above historically low levels in the HBRP footprint (i.e., averaged 0.38 picocuries per gram [pCi/ g]

for cesium-137 [Cs-137] and non-detected for all other ROCs); and, whether data quality were sufficient for comparison to generic NRC screening values and FOTA-specific derived concentration guideline levels (DCGLs) .

During the ORISE confirmatory survey activities for the FOTA, the NRC site representative also tasked ORISE with performing GWS of three additional areas as stated in Section 1.

4. DOCUMENT REVIEW ORISE has reviewed PG&E's Characterization Surory Planning Worksheet (CSPW) (PG&E 2012). Since the FOTA was classified as Class 3 SU as described in Section 5, it was PG&E's intention to use the data as FSS data in the event that the characterization survey findings met the classification criteria for a Class 3 SU. The characterization plan worksheet was specifically reviewed for historical information and to identify the ROCs and the applicable DCGLs for the FOTA. ORISE also reviewed preliminary FSS data for the soil pile area within the FOTA. The purpose of these reviews was to ensure that regulatory requirements were being met by PG&E and to develop the HBPP Fuel Oil Tank Area, Eureka, CA 3 5167-SR-01 -0

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5. DATA QUALITY OBJECTIVES The ORISE independent confirmatory survey planning relies on the Data Quality Objectives (DQO) process to design and implement the confirmatory activities planned for the HBPP site. The DQO process includes the following seven steps:

• Step 1: State the problem

• Step 2: Identify the decisions

• Step 3: Identify inputs to the decisions

• Step 4: Define the study boundaries

• Step 5: Develop a decision rule

• Step 6: Specify the decision errors

• Step 7: Optimize the survey design The confirmatory DQO steps for the HBPP site were as follows:

• Step 1, problem: The confirmatory survey must assess the reliability and adequacy of the HBPP FSS results .

• Step 2, decisions: Are HBPP procedures sufficiently robust to identify residual material with concentrations that exceed the DCGLs for the ROCs, and are the residual concentrations of the primary ROC, Cs-137, sufficiently low (at background levels)?

• Step 3, decisions inputs: The decision inputs included: 1) gamma walkover scan results, and

2) soil sample results and comparison of ORISE and PG&E soil sample concentrations.

• Step 4, study boundaries: The former FOTA is the study boundary.

• Step 5, decision rules: There were two decision rules. The first was based on the comparison of the confirmatory soil sample results to the HBPP FSS results and to the site cleanup goals. The second rule was based on surface scan and judgmental sample results to HBPP Fuel Oil Tank Area, Eureka, CA 4 5167-SR-01-0

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• Step 6, decision errors: The gamma walkover scans and side-by-side split soil sample results should be in good agreement and soil sample results for the MARSSIM Class 3 Survey nit should be at or near background levels and all ROCs below the CSPW survey design release criteria.

• Step 7, survey design optimization: The survey design was optimized to collect the appropriate data based on the procedures detailed below.

6. CONFIRMATORY RADIOLOGICAL SURVEY PROCEDURES To expedite the survey process, ORISE coordinated and worked with the NRC site representative as the licensee planned their survey activities. This assured that O RISE would complete side-by-side confirmatory surveys at such a time as the licensee determined the probability of satisfying the FSS DQOs was high.

ORISE personnel visited the HBPP site from February 14 to 15, 2012 to perform visual inspections and independent measurements and sampling. The radiological survey activities were conducted in accordance with a project-specific plan submitted to and approved by the RC, the ORISE Surory Procedures Manual and the Oak Ridge Associated Universities (ORAU) Q11aliry Program Manual (ORISE 2012, 2008 and ORAU 2011).

6.1 SURVEY UNIT C LASSIFICATION PG&E classifies SUs in accordance with MARSSIM guidance RC 2000) with three classifications for impacted areas, based on contamination potential-as either Class 1, 2, or 3. The FOTA has been classified by PG&E as a Class 3 SU and the historical documentation supports this classification. Class 3 area are designated as any impacted areas that are not expected to contain residual contamination, or are expected to contain levels of residual contamination at a small fraction of the DCGL.

Although the FOTA is a Class 3 SU, ORISE confirmatory survey activities coverage within the FOTA SU were conservative and on the same order of rigor as the PG&E CSPW (PG&E 2012).

The PG&E CSPW called for 100% gamma scan coverage of the FOTA. Also, a portion of the HBPP Fuel Oil Tank Area, E ureka, CA 5 5167-SR-01 -0

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FOTA had already been surveyed and soil samples had been collected by the licensee. This was done so that a dirt pile could be placed in this portion of the FOTA SU.

6.2 REFERENCE SYSTEM Global positioning system (GPS) coordinates were used for referencing measurement and sampling locations. The specific reference system used by the licensee was the California State Plane Coordinate System (SPCS FIPS 0401 US Survey feet; orth American Datum 83).

6.3 SURFACE S CANS High-density gamma radiation surface scans were conducted over the soil, concrete, and asphalt surfaces within the FOTA, the area of interest for this survey report (Fig. A-3) . Surface scans were performed using sodium iodide thallium-activated (Nal[Tl]) scintillation detectors coupled to ratemeter-scalers with audible indicators. Detectors were also coupled to global positioning systems (GPSs) that enabled real-time gamma count rate and position data capture. Field personnel relied on the audio output to identify and mark any locations of elevated direct gamma radiation for further investigations that might suggest the presence of residual contamination.

6.4 G AMMA DIRECT M EASUREMENTS A one-minute static gamma count rate measurement was performed at each of the twelve remaining characterization soil sample locations determined per PG&E for the FOTA (Fig. A-4) . A fter each soil sample was collected, a post-sample one-minute static gamma count rate was performed.

Pre- and post-sample gamma direct measurements were also performed at judgmentally-selected locations exhibiting elevated gamma radiation level as determined by surface scans (Fig. A-5).

6.5 SOIL SAMP LING 6.5.1 System atic Sample Locations Twelve duplicate systematic surface samples, 0 to 15 cm each, were collected from the FOTA at locations predetermined in the PG&E CSPW (Fig. A-4). Although ORISE collected one of the duplicate samples in conjunction with PG&E personnel, the final number of soil samples retained for confirmatory analysis depended upon the ORISE gamma direct measurement results and/ or the PG&E preliminary gamma spectroscopy analyses of the ORISE samples. Based on the ORISE review of the aforementioned data, four of the twelve systematic soil sample duplicates were HBPP Fuel Oil Tank Area, Eureka, CA. 6 5167-SR-01-0

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6.5.2 Judgmentally-Selected Sample Locations Judgmental surface soil samples were collected at six locations of suspected elevated gamma radiation detected during the ORISE GWS of the FOTA surfaces (Fig. A-5). Since these were judgmental samples, ORISE requested each of these samples for independent analyses. These were ORISE samples S016 to S021 (Refer to Fig. A-5 and Table B-1).

6.6 INTERLABORATORY COMPARISON ANALYSES Since some areas within the FOTA were covered with clean fill prior to ORISE gaining access, thus precluding direct confirmatory surveys for the soil pile area, ORISE requested that the three samples previously collected by PG&E (PG&E samples OOL10-4, 9, and 15, which were ORISE samples S004, 9, and 15, respectively) be provided to ORISE for interlaboratory comparison analysis.

HBPP Fuel Oil Tank Area, Eureka, CA 7 5167-SR-01-0

7. ADDITIONAL RADIOLOGICAL SURVEY PROCEDURES At the request of the NRC site representative, ORISE also performed limited, low-density radiological GWS of three other areas: the Unit 1 and Unit 2 remaining concrete pads (Fig. A-6), the Northeast Laydown Area (Fig. A-7), and the newly paved asphalt haul road (Fig. A-8). The additional surveys were to provide radiological scan data to ensure that radiological contamination was not being spread by continuing decommissioning activities of the Unit 3 reactor on previously released site surfaces as per the Cross Contamination Prevention and Monitoring Plan (CCPMP)

(PG&E 2008).

8. RADIONUCLIDES OF CONCERN The major ROC identified in the FOTA was Cs-137. A complete listing of ROCs and associated generic NRC Screening Values and FOTA-specific DCGLs are provided in Table 1. The soil DCGLs are reported in units of picocuries per gram (pCi/ g).

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Table 1. Derived Concentration Guideline Levels for Surface Soil Radionuclides of Concern Humboldt Bay Power Plant Eureka, California Nuclide NRC Screening Value DCGLs (pCi/ g)* FOTA-Specific DCGLs (pCi/ g)b Easy to Detect - Gamma Spectroscopyc Co-60 3.8 1.9 Nb-94 5.8 2.9 I-129 0.5 0.25 C s-137 11 5.5 Eu-152 8.7 4.35 Eu-154 8 4 d 11 5 Np-237 -

Hard to Detect - Wet Chemistryc H-3 110 55 C-14 12 6 Ni-59 5,500 2,750 Ni-63 2,100 1,050 Sr-90 1.7 0.85 Tc-99 19 9.5 Pu-238 2.5 1.25 Pu-239 2.3 1.15 Pu-240 1,240 Pu-241 72 36 A m-241 2.1 1.05 Cm-243 3.2 1.6 Cm-244 2,200 Cm-245 276 Cm-246 1,190

• Derived concentration guideline levels from UREG-1757, Volume 1, Revision 1 Table B-2 (NRC 2003) bDCGLs applied under the Characterization Survry Pia1111ing Worksheet for the HBPP FOTA correspond to the lesser of either an annual dose of 15 mrem/ y (the 25 mrem/ y DCGL adjusted to an assumed California Department of Toxic Substance Control risk-based release of 15 mrem/ y) or 50% of the NRC Screening Values (PG&E 2012) cEasy-to-detect radionuclide concentrations determined via gamma spectroscopy dNRC Screening Value not provided

<Hard-to-detect radionuclide concentrations may be determined with wet chemistry analytical procedures based on the gamma spectroscopy results and with guidance from the NRC site representative HBPP Fuel Oil Tank Area, Eureka, CA 9 5167-SR-01-0

C>R , SE OAK A100a ..-nTUTE FOfll llCll£NC& NID IEDUCATtON

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9. SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data were returned to the ORISE laboratory in Oak Ridge, Tennessee for analysis and interpretation. Sample analyses were performed in accordance with the ORISE Laboratory Procedures Manual (ORISE 2011 ). Soil samples were analyzed by gamma spectroscopy with the primary ROC being Cs-137; however, spectra were also reviewed for other gamma-emitting radionuclides (i.e., fission and activation products) associated with the HBPP. After reviewing the gamma spectroscopy results, wet chemistry analyses for additional radionuclides such as Ni-63, Sr-90, and transuranics were deemed not necessary.

Soil sample results were reported in units of pCi/ g. Gamma count rate measurement results were reported in units of counts per minute (cpm). The data generated were compared with the PG&E analytical results (specifically for Cs-137) and then with the CSPW survey design release criteria established for the primary site-specific ROC for the FOTA. All sample results were compared \.vith the FOTA-specific applicable DCGL and MARSSIM guidance to determine if the FOTA Class 3 designation was appropriate. Additional information regarding instrumentation and procedures may be found in Appendices C and D.

10. FINDINGS AND RESULTS The results for each radiological survey procedure component are discussed in the following sections.

10.1 DOCUMENT REVIEW The O RISE reviews of PG&E's CSPW and preliminary radiological data indicated that the procedures and methods implemented were appropriate for the FOTA (PG&E 2012).

10.2 SURFACE SCANS Gamma radiation surface scans identified six areas of elevated gamma radiation, primarily along the excavation trenches used to drain standing water from the site, along other surface water runoff areas, and at the asphalt entrance at the northeast corner of the berm. The gamma scan paths and the normalized count rate in cpm are provided in Fig. A-3. The gamma scans ranged from less than 3,800 to 11,390 cpm. Figure A-9 is the frequency histogram of the normalized walkover gamma count rate data population for the FOTA; the histogram indicates a normal distribution typical of the background concentrations associated with those areas. O RISE did observe slightly elevated HBPP Fuel Oil Tank Area, Eureka, CA 10 5167-SR-01-0

C>R. , SE OAK NDOm ~ ll'OA 8QIENCa: AHO EDUCATION

- - - - - - - - - - - - - - - - - -- - - - - - - - - ~byOA.t.UfortheU.&Oeipwtment.of£norvr gamma radiation levels over the ground surface where the standing water excavation trench dirt was piled. Further investigation indicated a natural soil strata layer deposit. The dark lines in the trench pictures (Fig. A-10) indicate the locations where the elevated gamma radiations were in the southern portion of the FOTA near where the former fuel tank used to be located.

The ORISE GWS data indicates that the low gamma radiation levels associated with the Class 3 SU is typical of background levels that ranged from 3,200 to 5,400 cpm over the various surfaces (soil, asphalt and concrete) within the FOTA.

10.3 GAMMA DIRECT MEASUREMENTS Gamma direct measurements were performed at each soil sample location. The results indicated that gamma radiation levels were at or near background levels (3,500 cpm). ORISE selected soil samples from locations that exhibited the highest gamma radiation levels even though those locations were slightly above background levels.

10.4 RADIONUCLIDE CONCENT RAT IONS IN CONF IRMATORY SOIL SAMPLES The summary data for the FOTA systematic and judgmental soil samples are presented in Table 2.

The data for the radionuclide concentrations in individual samples are provided in Table B-1. All soil results for Cs-137 were less than the respective FOTA CSPW designed release criteria for each individual soil sample. Total uranium concentrations, as a naturally occurring radioactive material (NORM), are provided to account for the elevated gamma radiation levels determined by the GWS in the FOTA.

Table 2. Radionuclide Concentrations in FOT A Soil Samples Summary Results Soil Sample Radionuclide Concentrations (pCi/ g)

Summary Cs-137 Co-60 U-235 U-238 Total U*

Systematic 0.03 to 0.37 -0.02 to 0.01 0.04 to 0.16 0.15 to 0.69 0.34 to 1.48 Mean Concentration 0.26 0.001 0.07 0.45 0.97

-0.01 to Judgmental -0.01 to 0.01 -0.02 to 0.08 0.28 to 1.84 0.60 to 3.75 0.51 Mean Concentration 0.14 0.00 0.04 0.82 1.69

• Total U = U-238

• 2 + U-235 bZero values due to rounding HBPP Fuel Oil Tank Area, Eureka, CA 11 5167-SR-01-0

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- - - - - - - - - - - - - - - - - - - - - - - - - - - MenogedbyORAUforhtU.&OepenmentofEnorgy ORISE also performed a comparison of the ORISE and PG&E soil samples results (Table B-2).

PG&E's Cs-137 results, for those sample locations where both ORISE and PG&E provide analytical data, are in good agreement and indicate that the FOTA Cs-137 concentrations are at background levels.

10.5 RADIONUCLIDE CON CENTRATIONS IN INTERLABORATORY COMPARISON ANALYSES SOIL SAMPLES The results of the interlaboratory comparison soil samples indicate that the ORISE and PG&E radiological soil sample results are in good agreement. The comparison soil sample results are presented in Table B-3.

11. COMPARISON OF RESULTS WITH RELEASE CRITERIA The applicable site-specific soil DCGLs for the ROCs are provided in Table 1 and have been approved by the NRC (ESI 2007). The primary ROC for the FOTA, as designated by the CSPW, was Cs-137. To demonstrate compliance with the Table 1 FOTA-specific criteria, each radionuclide concentration should be less than its respective DCGL-with consideration for small areas of elevated activity----as well as application of the unity rule (Sum-of-Ratios [SOR]). The unity rule requires that the sum of the concentration of each contaminant divided by the respective guideline be less than one.

Conc1 Conc 2 Concn SOR = DCGL 1 + DCGL 2 + ... + DCGln ::::; 1 Cs-137 and Co-60 were the only identified ROCs in the ORISE-analyzed soil samples. ORISE also reported the uranium concentrations to determine the natural concentrations associated with the ORM soil strata determined in the FOTA. Radionuclide concentrations in soil samples were directly compared with the Cs-137 DCGLs provided in Table 1. ORISE did not apply the unity rule/SOR in the activity calculations for each of the soil samples since the primary ROC, Cs-137, was well below the release criteria and a review of the gamma spectroscopy data did not indicate any other easy-to-detect ROC other than Co-60. Each of the 13 soil samples analyzed by ORISE was below the individual Cs-137 FOTA-specific release criteria.

HBPP Fuel Oil Tank Area, Eureka, CA 12 5167-SR-01-0

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~~~~~~~~~~~~~~~~~~~~~~~~~~~ ~~ORAU*theU&~~EnofVY

12. ADDITIONAL RADIOLOGICAL SURVEY ACTIVITIES 12.1 UNIT 1 AND UNIT 2 - GAMMA WALKOVER SCANS GWS over the Unit 1 and Unit 2 concrete pads indicated a gamma count rate range from less than 3,300 to approximately 13,000 cpm. The elevated gamma radiation levels were determined to be from shine when the surveyor was in the proximity of radiological waste containers and the radwater waste treatment facility. Elevated gamma radiation levels were not found on the portion of the concrete pads that were scanned. The GWS results are presented in Fig. A-6 and the GWS frequency histogram is provided in Fig. A -11.

12.2 NORTHEAST LAYDOWN AREA - GAMMA WALKOVER SCANS G\VS over the Northeast Laydown Area asphalt pad indicated a gamma count rate range from less than 3,000 to approximately 21,000 cpm. The elevated gamma radiation levels were determined to be from shine when the surveyor was in the proximity of radiological waste containers and other wrapped radiological waste. The highest count rate was on a pie<:::e of equipment that had been determined to an X-bar equipment lift; this piece of equipment was determined to not be tagged with a radiological identification tag). Elevated gamma radiation levels were not found on the portion of the Northeast Laydown Area asphalt pad that was scanned. The GWS results and a picture of the X-bar are presented in Fig. A-7 and the GWS frequency histogram is provided in Fig. A-12.

12.3 NEW ASPHALT ROADWAY- GAMMA WALKOVER SCANS GWS over the new asphalt roadway indicated a gamma count rate range from less than 3,400 to approximately 11,000 cpm. The elevated gamma radiation levels were determined to be from shine when the surveyor was in the proximity of radiological waste containers and the radiological cleanup work associated with the reactor decommissioning. E levated gamma radiation levels were not found on the portion of the asphalt roadway that was scanned. The GWS results are presented in Fig. A-8 and the GWS frequency histogram is provided in Fig. A-13.

13.

SUMMARY

During the period of February 14 to 15, 2012, ORISE performed radiological confirmatory survey activities for the former FOTA and additional radiological surveys of portions of the HBPP site in Eureka, California. The radiological survey results demonstrate that residual surface soil HBPP Fuel Oil Tank Area, Eureka, CA 13 5167-SR-01 -0

C>R , SE OAK ..:>QA ...-nTVTa FOR 8C1ENCa: AHO IEDUCAnoN

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contamination was not present significantly above background levels within the FOTA. Therefore, it is ORISE's opinion that the radiological conditions for the FOTA surveyed by ORISE (refer to Tables 2 and B-1) are commensurate with the site release criteria for final status surveys as specified in PG&E's CharacteriZfllion Sttrory Planning Worksheet (PG&E 2012). In addition, the confirmatory results indicated that the ORISE FOTA SU Cs-137 mean concentrations results compared favorably with the PG&E FOTA Cs-137 mean concentration results, as determined by ORISE from the PG&E characterization data (refer to Table B-2). The interlaboratory comparison analyses of the three soil samples analyzed by PG&E's onsite laboratory and the ORISE laboratory indicated good agreement for the sample results and provided confidence in the PG&E analytical procedures and PSS soil sample data reporting (Table B-3).

HBPP Fuel Oil Tank Area, Eureka, CA 14 5167-SR-01-0

C>RISE

• OAK N008 INS1'fTU'TE FOfll 8CENC9i AHO EDUCATION

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10. REFERENCES Enercon Services, Inc. (ESI) 2007. Site CharacteriZfltion Plan - Humboldt Bery Power Plant. HBPP-PP-003, Rev. 0. July 16.

ESI 2008. Historical Site Assessment, prepared for the Humboldt Bay Power Plant Pacific Gas &

E lectric Company, Eureka, California. D raft. September.

Pacific Gas & Electric Company (PG&E) 2008. Cross Contamination Prevention and Monitoring Plan.

Prepared for the Humboldt Bay Power Plant, Pacific Gas & Electric Company, Eureka, California.

HBAP C-220. October 14.

PG&E 2012. Characterization Surory Planning Worksheet. Prepared for the Humboldt Bay Power Plant, Pacific Gas & Electric Company, E ureka, California. Draft; Revision 3. February 9.

Oak Ridge Associated Universities (ORA U) 2011 . Quality Program Manual for the Independent Environmental Assessment and Verification Program. Oak Ridge, Tennessee. D ecember 1.

Oak Ridge Institute for Science and E ducation (ORISE) 2008. Surory Procedures Manual for the Independent Environmental Assessment and Verification Program. Oak Ridge, Tennessee. May 1.

ORISE 2010. Radiation Protection Manual. Oak Ridge, Tennessee. June 3.

ORISE 2011. Laboratory Procedures Manualfor the Independent Environmental Assessment and Verification Program. Oak Ridge, Tennessee. December 1.

ORISE 2012. Final Prqject-Specific Plan far the Independent Confirmatory Survry of the Former Fuel Oil Tank Area at the Humboldt Bery Power Plant, Eureka, California. DCN: 5167-PL-01-0. Oak Ridge, Tennessee.

February 9.

U.S. uclear Regulatory Commission (NRC) 2000. Multi-Agenry Radiation Surory and Site Investigation Manual (MARSSIM), NUREG-1575; Revision 1. Washington, DC. August.

NRC 2003. Consolidated NMSS Decommissioning Guidance: D ecommissioning Process for Materials Licensees.

NUREG- 1757; Volume 1, Revision 1. Washington, D C. September.

HBPP Fuel O il Tank .Area, Eureka, CA 15 5167-SR-01-0

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APPENDIX A FIGURES HBPP Fuel Oil Tank Area, Eureka, CA 5167-SR-01-0

THIS PAGE LEFT BLANK INTENTIONALLY HBPP Fuel Oil Tank Area, Eureka, CA 5167-SR-01-0

Nevada Arizona D Site Location ll11r1 Humboldt Bay ~owe~ Plant

~~ E ureka, Cahforrua

~~

ORISE 0 50 100 Created b )': A. Hoo d Date: J~ua.ry 26, 201 1 Miles Fig. A-1. Site Location M ap - Humboldt Bay Power Plant, Eureka, California HBPP Fuel Oil Tank Area, Eureka, CA A-1 5167-SR-01-0

II Surveyed Areas Fuel Oil Tanlc Area "" H umboldt Bay Power Plant 5167 t

- - Unit 1 and 2 Concrete Pad s

- - Northeast Laydown Area Eureka, California

- - N ew Asphalt Road ORISE 0 50 100 Crc a rcd by: A. Hood Da re: ~ bru ary 27 , 2012 Miles "f\IEA Pto,ecn \S IG'Hurnboldt8.,-~1rt.ar.\GIS Fig. A-2. Humboldt Bay Power Plant - Site Overview of Surveyed Areas HBPP F uel Oil Tank .Area, E ureka, CA A-2 5167-SR-01-0

Normalized Gamma Count Rate (CPM)

. . 10001 - 11390 . . 4601 - 5000 II Humbo ldt Ba:;;:er Plant 5167 6201 - 10000 . . 4201 - 4600 ~'I Gamma Walkover Scans 5801 - 6200 . . 3601 - 4200 ORISE

. . 5401 - 5800 . . < 3800 0 20 40 Cn!it.ted by: A. 1lood Date: February 2.1, 2012

. . 5001 - 5400 Survey Boundary Feet Fig. A-3. H BPP F uel Oil Tank Area - Gamma Walkover Scans HBPP Fuel Oil Tank Area, Eureka, CA -3 5167-SR-01 -0

Survey Boundary

"' Humboldt Bay Power Plant 5167 Site Sample Locations Concrete Remnant 0

t 25 50 Created by: A. H ood Da te: February 8, 2012 Feet l'\IEA ~u\ 5095Y l ?81-101\<<'1\CIS\

Fig. A-4. HBPP FOTA - PG&E Systematic Soil Sample Locations HBPP Fuel Oil T ank Area, Eureka, CA A-4 5167-SR-01 -0

- Survey Boundary

~ Inaccessible O RISE Judgmental Sample Location H BPP Systematic Sample Location 0 25 Feet 50 II ORISE Humboldt Bay Power Plant 5167 FOTA Soil Sample Locations A ORISE Soil Samples at H BPP Systematic Location Created by: A. H ood D ate: Fitbrua.ry 23, 2012

'r:\JEAV\PUIJ8Cn\ S167Humboktt\ GIS\

Fig. A-5. HBPP FOTA - Confirmatory Soil Sample Locatio ns H BPP Fuel Oil Tank Area, Eureka, CA A-5 5167-SR-01 -0

r Normalized Gamma Count Rate (CPM) 9301 - 13332 8301 - 9300

. . 5301 - 6300

- 4301 - 5300 I~'I I Humboldt ~~t~o;'; Plant 5167 Gamma Walkover Scans

. . 7301 - 8300 - 3301 - 4300 0 10 20 ORISE

-=:::J

. . 6301 - 7300 - < 3300 Feet Created by. A. Hood Date: February 23, 2012 Y: \ILW\~\ !'i l C'l lombokh\ CIS\

Fig. A-6. HBPP Unit 1 and Unit 2 Concrete Pads - Gamma Walkover Scans HBPP Fuel Oil Tank Area, Eureka, CA A -6 5167-SR-01-0

10001 - 15000 3601 - 3700

. . 4501 - 10000 . . 3301 - 3600 0 10 20

. . 4201 - 4500 . . 3001 - 3300 Cttated by: A. Hood D ale: February 23, 2012 Feet

. . 3901 - 4200 . . < 3000 Fig. A-7. HBPP Northeast Laydown Area - Gamma Walkover Scans HBPP Fuel Oil Tank Area, Eureka, CA -7 5167-SR-01-0

Gamma Count Rate (CPM)

~-

10001 - 10633 - 5601-6700 Humboldt Bay Power Plant 5167 New Road 8901 -10000

. . 7801-8900 4501-5600 3401-4500 0 1

25 50 ORISE Gamma Walkover Scans

. . 6701-7800 - <3400 Created by: A. Hood Da1c: February 23, 2012 Feet

'l" ' IL.A\"*_Pft'lllflC'9\Slrll..-boldt(J.I" Fig. A-8. HBPP New Asphalt Roadway - Gamma Walkover Scans HBPP Fuel Oil Tank Area, Eureka, CA A-8 5167-SR-01-0

Humboldt Bay Power Plant - Fuel Oil Tank Area Normalized Count Rate Histogram 900 Median BKG = 5051 CPM 800 700 600

~

Q.

~0 500

~

c

~ 400 r:T

~

Maximum Count Rate= 11,390 CPM 300

\

200 100 o +---~--~

3000 3500 4000 4500 5000 5500 6000 6500 7000 7500 8000 8500 More Normalized Counts Per M inute (CPM)

BKG =background Fig. A-9. HBPP Fuel Oil Tank Area - Gamma Scan Count Rate Distribution

Fig. A-10. Fuel Oil Tank Area - Pictures of the Natural Strata Layer that Exhibited Elevated Gamma Radiation Levels HBPP Fuel Oil Tank Area, Eureka, C A-10 5167-SR-01-0

Humboldt Bay Power Plant - Units 1 & 2 Concrete Pads Normalized Count Rate Histogram 1200 Median BKG =6,436 CPM 1000 800

~

0.

u 0

~

c 600

I Cl"

~ Maximum Count Rate =13,332 CPM 400 200 0 +-----..--1-~-

3000 3800 4600 5400 6200 7000 7800 8600 9400 10200 11000 11800 12600 More Normalized Counts Per Minute (CPM)

BJ.;:G = background Fig. A-11. HBPP U nits 1 & 2 Concrete P ads - Gamma Scan Count R ate D is tribution

Humboldt Bay Power Plant - Northeast Laydown Area Count Rate Histogram 200 Median BKG = 3,674 CPM 180 160 140

~

~

120 0

~ 100 These outliers represent the elevated cQj

I gamma activity around the rad waste

...~ 80 containers .

60 40 20 2600 2800 3000 3200 3400 3600 3800 4000 4200 4400 4600 4800 5000 5200 5400 5600 More Counts Per Minute (CPM)

"'~ BJ.;:G = backgrow1d

/.r,

~ Fig. A-12. HBPP Northeast Laydown Area Asph alt P ad - Gamma Scan Count R ate Distribution 6

Humboldt Bay Power Plant - New Asphalt Roadway Count Rate Histogram 250 Median BKG =6,672 CPM c

8 If 200 n

e; 150 0

~

c Cll 5- 100

~

so 0

5000 5500 6000 6500 7000 7500 8000 8500 9000 9500 10000 More Counts Per M inute (CPM)

BKG = background Fig. A-13. H BPP New Asphalt Roadway - Gamma Scan Count Rate D istribution

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APPENDIX B TABLES HBPP Fuel Oil Tank Area, Eureka, CA 5167-SR-01-0

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I Table B-1. Radionuclide Concentrations in ORISE Soil Samples c;;;

-0

-0 Confirmatory Survey Activities for the Fuel Oil Tank Arca

""I1 Humboldt Bay Power Plant

§.

Eureka, California 2...,

,,. Cs-137 *** U-235 U-238 Total Ub

~

? Humboldt Bay Systematically-Selected Soil Sample Locations

i

!:; SOO l 5949071 2160777 003 +/- 0.02< -0.01 +/- 0.04 O.Q7 +/- 0.06 0.26 +/- 0.28 0.59 +/- 0.56 F S002 5948982 2160894 0.30 +/- 0.04 0.01 +/- 0.04 0.05 +/- 0. 14 0.52 +/- 0.32 1.09 +/- 0.66 n

> S004 5948902 2160738 0.25 +/- 0.04 OO()d +/- 0.04 0.04 +/- 0.08 0.24 +/- 0.33 0.52 +/- 0.66 S007 5949124 2160907 0.37 +/- 0.04 0.00 +/- O.Q3 0.06 +/- 0. 11 0.67 +/- 0.33 1.40 +/- 0.67 S009 5948880 2160868 0.20 +/- 0.02 O.Ql +/- O.Q3 0. 16 +/- 0.1 1 0.59 +/- 0.21 1.34 +/- 0.43 SO ll 5949146 2160803 0.34 +/- 0.04 0.00 +/- 0.04 0.10 +/- 0.08 0.69 +/- 0.32 1.48 +/- 0.64 S015 5948869 2160764 0.35 +/- 0.04 -0.02 +/- 0.04 0.04 +/- 0. 11 0.15 +/- 0.36 0.34 +/- 0.73 FOTAAvr:rage 0.26 0.00 0.07 0.45 0.97

'? FOTA Standard Deviation 0.12 0.01 0.04 0.22 0.47 ORISE Judgmental Soil Sample Locations S016 5948965 2160774 0.02 +/- 0.01 0.00 +/- 0.03 0.08 +/- 0.06 0.72 +/- 0.30 1.52 +/- 0.60 S017 5948969 2160768 0.00 +/- 0.03 0.00 +/- O.Q4 0.08 +/- 0.06 1.11 +/- 0.34 2.30 +/- 0.68 5018 5948967 2160766 -0.01 +/- 0.03 O.Ql +/- 0.05 0.07 +/- 0.09 1.84 +/- 0.42 3.75 +/- 0.84 5019 5949108 2160832 0.29 +/- O.Q3 -0.01 +/- 0.03 -0.02 +/- 0. 13 0.58 +/- 0.24 1.14 +/- 0.50 S020 5949061 2160958 0.01 +/- 0.02 0.00 +/- 0.03 0.04 +/- 0.09 0.28 +/- 0.23 0.60 +/- 0.47 S021 5949062 2160970 0.51 +/- 0.05 0.00 +/- 0.04 -0.01 +/- 0.12 0.41 +/- 0.27 0.81 +/- 0.55 Judgmental Average 0.27 0.00 0.04 0.82 1.69

• Refer to Figs. A-4 and A-5

~ bTotal Uranium calculations for natural uranium were 2*U-238 + U-235

°'_. <Uncertainties represent d1e 95°'o confidence Je,-el, based on total propagated uncertainties s"'6"' dZero ,-alues a.re due to row1ding

~~~~~~~-

Table B-2. Fuel Oil Tank Arca Comparison Data Confirmato~ Survey Activities for the Fuel Oil Tank Arca Humboldt Bay Power Plant Eureka, California ORISE Sample PG&E Sample Cs-137 Concentrations (pCi/g) Relative Error Ratio

> I Db East (ft) Nonh (ft) (RER)d

ID*

ORISE PG&Ec

?

~- Humboldt Bay Systematically-Selected Soil Sample Locations

?" SOOl OOLl0-1 5949071 2160777 0.03 +/- 0.02< <0.120 _J

()

> S002 OOLl0-2 5948982 2160894 0.30 +/- 0.04 0.322 +/- 0.080 0.25 S003 OOLl0-3 5948991 2160933 - +/- - 0.353 +/- 0.096 -

S004 OOLl0-4 5948902 2160738 0.25 +/- 0.04 0. 193 +/- 0.053 0.86 SOOS OOLl0-5 5949079 2160855 - +/- - <0.099 -

S006 OOLl0-6 5948946 2160790 - +/- - <0.094 -

S007 OOLl 0-7 5949124 2160907 0.37 +/- 0.04 0.313 +/- 0.082 0.62 SOOS OOLl0-8 5949013 2160829 - +/- - <0.106 -

S009 OOLl0-9 5948880 2160868 0.20 +/- 0.02 0.195 +/- 0.057 0.08 S010 OOLl0-10 5948969 2160686 - +/- - <0.179 -

SOll OOLl0-11 5949 146 2160803 0.34 +/- 0.04 0.317 +/- 0.088 0.24 S012 OOLl0-12 5949002 2160725 - +/- - 0.350 +/- 0.076 -

S013 OOLl 0-13 59489 13 2160842 - +/- - <0.088 -

S014 OOLl0-14 5949087 2160957 - +/- - <0.129 -

S015 OOLl 0-15 5948869 2160764 0.35 +/- 0.04 0.345 +/- 0.083 0.05 FOTAAverage 0.26 0.30 0.30 FOTA Standard Deviation 0.12 0.07 0.32

~~~~~~~~~~~~~~~~~~~-

Table B-2. Fuel Oil Tank Arca Comparison Data Confirmatory Stlr\'C} ActiYitics for the Fuel Oil Tank Arca Humboldt Ba} Power Plant Eureka, California PG&E Cs-137 Concentrations (pCi/g)

ORISE Relative Error Ratio Sample East (ft) Nonh (ft)

Sample ID* ORISE PG&Ec (RER)*

I Db ORISE Judgmental Soil Sample Locations S016 OOLl0-20 5948965 2160774 0.02 +/- 0.01 <0.084 -

n S017 OOLl0-21 5948969 2160768 0.00g +/- 0.03 <0.082 -

S018 OOLl0-22 5948967 2160766 -0.01 +/- 0.03 <0. 108 -

S019 OOLl0-23 5949108 2160832 0.29 +/- 0.03 0.318 +/- 0.074 0.35 S020 OOLl0-24 5949061 2160958 O.Dl +/- 0.02 <0.077 -

S021 OOLl0-25 5949062 2160970 0. 51 +/- 0.05 0.621 +/- 0.096 1.03 Judgmental Averagd' 0.40 0.47 0.69

• Refer to Figs. A-4 and A-5 bPG&E Sample ID prm;ded by PG&E

<PG&E Cs-137 concentrations from PG&E-prm;ded gamma spectroscopy reports

• Re!atiYe Error Ratio (RER) was calculated based on the formula in the DO E's Quality Systems for Analytical Services and provides a way to detenni.ne if analytical results of duplicates (in this case, split samples) a.re in agreement. A RER < 3 means the samples a.re in agreement at the 99%

confidence le,*el.

• Uncertainties represent the 95° o confidence 1e,-e1, based on total propagated uncertainties

£Measurement or analysis not performed

• Zero ,*alues are due to rounding "Calculated using concentrations that were greater than the minimum detectable concentration (MDC); ORISE samples used were 5019 and S021

Table B-3. Radionuclide Concentrations in lnterlaboratory Comparison Soil Samples Confirmatory Sur.'e) Activities for the Fuel Oil Tank Arca Humboldt Ba) P<mer Plant Eureka, California

Cs-137 Concentrations (pCi/g)

~

ORISE Sample ID* PG&E Sample IDb Relative Error Ratio (RER)<

-- ORISE PG&E<

J' S004 OOLl0-4 0.25 +/- 0.04' 0. 19 +/- 0.05 0.9

i

=; S009 OOLl0-9 0.20 +/- 0.02 0.20 +/- 0.06 0.1

?" S015 OOLl0-15 0.35 +/- 0.04 0.35 +/- 0.08 0.1

~ *Refer to Figs. 1\-4 and A-5 bPG&E sample identification and sample Cs-137 concentrations provided by PG&E

' Relati,-e Error Ratio (RER) was calculated based on the formula in the DOE's Quality Systems for Analytical Sen-ices and prmides a way to determine if analytical results of duplicates (in this case, split samples) are in agreement. A RER < 3 means the samples are in agreement at the 99°'o confidence level.

dQRJSE uncertainties represent the 95° o confidence le,*el, based on total propagated uncertainties

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APPENDIX C MAJOR INSTRUMENTATION HBPP Fuel Oil Tank Area, Eureka, CA 5167-SR-01-0

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The display of a specific product is not to be construed as an endorsement of the product or its manufacturer*by the author or his employer.

C.1 SCANNING AND M EASUREMENT I NSTRUMENT / D ETECTOR C OMBINATIONS C.1.1 Gamma Ludlum NaI Scintillation Detector Model 44-10, Crystal:2 in x 2 in coupled to:

Ludlum Ratemeter-scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, TX) coupled to:

Trimble GeoXH Receiver and Data Logger (Trimble Navigation Limited, Sunnyvale, CA)

C .1.2 Laboratory Analytical Instrumentation High Purity E xtended Range Intrinsic Detector CA BERRA/ Tennelec Model No: ERVDS30-25195 (Canberra, Meriden, CT)

Used in conjunction with:

Lead Shield Model G -11 (Nuclear Lead, Oak Ridge, TN) and Multichannel Analyzer Canberra's Apex Gamma Software Dell Workstation (Canberra, Meriden, CT)

High Purity Extended Range Intrinsic Detector Model o. GMX-45200-5 (AMETEK/ ORTEC, Oak Ridge, TN) used in conjunction with:

Lead Shield Model SPG-16-K8 (Nuclear Data)

Multichannel Analyzer Canberra's Apex Gamma Software Dell Workstation (Canberra, Meriden, CT)

High-Purity Germanium Detector Model GMX-30-P4, 30% Eff.

(AMETEK/ ORTEC, Oak Ridge, TN)

Used in conjunction with:

Lead Shield Model G-16 (Gamma Products, Palos Hills, IL) and Multichannel Analyzer Canberra's Apex Gamma Software Dell Workstation (Canberra, Meriden, CT)

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APPENDIXD SURVEY AND ANALYTICAL PROCEDURES HBPP Fuel Oil Tank Area, Eureka, CA 5167-SR-01-0

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D .1 PROJECT HEALT H AND SAFETY The proposed survey and sampling procedures were evaluated to ensure that any hazards inherent to the procedures themselves were addressed in current Job Hazard Analyses GHA). All survey and laboratory activities were conducted in accordance with ORISE health and safety and radiation protection procedures (ORISE 2008 and 2010).

Pre-survey activities included the evaluation and identification of potential health and safety issues.

Survey work was performed per the ORISE generic health and safety plans and a site-specific Integrated Safety Management (ISM) pre-job hazard checklist. PG&E personnel also provided site-specific safety awareness training. An ORISE safety walkdown of the site indicated that the land clearing activities and restoration activities by PG&E personnel left uneven terrain in some areas typical for outdoor survey activities, steep inclines on the berms, and standing water and thick mud in a portion of the FOTA.

D .2 CALIBRATION AND QUALITY ASSURANCE Calibration of all field and laboratory instrumentation was based on sources/ standards, traceable to the ational Institute of Standards and Technology (NIST).

Analytical and field survey activities were conducted in accordance with procedures from the following ORAU and ORISE documents:

• Survey Procedures Manual (May 2008)

• Laboratory Procedures Manual (December 2011)

• Quality Program Manual (December 2011)

The procedures contained in these manuals were developed to meet the requirements of 10 Code of Federal Regulations (CFR) 830 Subpart A,QualityAss11rance Requirements, Department of Energy Order 414.1 C Quality Assurance, and the U.S. uclear Regulatory Commission Quality Assurance Manual for the Office ofNuclear Material Sefety and Sefeguards and contain measures to assess processes during their performance.

HBPP Fuel Oil Tank Area, Eureka, CA D -1 5167-SR-01 -0

Quality control procedures include:

• Daily instrument background and check-source measurements to confirm that equipment Operation is within acceptable statistical fluctuations.

• Participation in Mi.."Xed-Analyte Performance Evaluation Program (MAPEP),  !ST Radiochemistry Intercomparison Testing Program (NRIP), and Intercomparison Testing Program (ITP) Laboratory Quality Assurance Programs.

• Training and certification of all individuals performing procedures.

• Periodic internal and external audits.

D.3 SURVEY PROCEDURES D .3.1 SURFACE S CANS A Nal(Tl) scintillation detector was used to scan for elevated gamma radiation. Identification of elevated radiation levels was based on increases in the audible signal from the recording and/ or indicating instrument. Additionally, the detectors were coupled to GPS units with data loggers enabling real-time recording in one-second intervals of both geographic position and the gamma count rate. Positioning data files were downloaded from field data loggers for plotting using commercially available software (http: // trl.trimble.com/ docushare/ dsweb/ Get/ Document-261826 / GeoExpl2005_100A_GSG_E G.pdD. Position and gamma count rate data files were transferred to a computer system, positions were differentially corrected, and the results were plotted on geo-referenced aerial photographs. Positional accuracy was within 0.5 meters at the 95m percentile.

ORISE Survey Procedures (ORISE 2008) require a minimum scan speed of 0.5 to 1 meter per second (m / s) based on the site contaminant and the DCGL for the primary contaminant of concern. A review of the gamma walkover scan data points relative to the scan area coverage indicate that the scan speed was less than 0.5 m/s. The scan minimum detectable concentrations for the Nal scintillation detectors was 6.6 pCi/g for Cs-137, the primary radionuclide of concern as provided in NUREG-1507 (Table 6.4). Any audible increase in radiation levels were investigated by HBPP Fuel Oil Tank Area, Eureka, CA D -2 5167-SR-01 -0

ORISE. It is standard procedure for the ORISE staff to pause and investigate any locations where gamma radiation is distinguishable from background levels.

D .3.2 SOIL SAMPLING Approximately 0.5 to 1 kg of soil was collected at each sample location. Collected samples were placed in a Marinelli jar, sealed, and labeled in accordance with ORISE survey procedures. The systematic soil samples were collected as split soil samples with PG&E personnel from the systematically-selected soil sample locations as determined by PG&E. The judgmental samples were collected as split samples with PG&E personnel from locations of elevated gamma radiation levels as determined by the ORISE gamma walkover scans.

D .4 RADIOLOGICAL ANALYSIS D .4.1 G AMMA SPECTROSCOPY Samples of soil were dried, mixed, crushed, and/or homogenized as necessary, and a portion sealed in a 0.5-liter Marinelli beaker or other appropriate container. The quantity placed in the beaker was chosen to reproduce the calibrated counting geometry. Net material weights and volumes were determined and the samples counted using intrinsic germanium detectors coupled to a pulse height analyzer system . Background and Compton stripping, peak search, peak identification, and concentration calculations were performed using the computer capabilities inherent in the analyzer system. All total absorption peaks (TAP) associated with the radionuclides of concern (ROCs) were reviewed for consistency of activity. TAPs used for determining the activities of ROCs and the typical associated minimum detectable concentration (MDCs) for a one-hour count time were:

Radionuclide TAP*' (MeV) MDC (pCi/g)

Co-60 1.173 0.06 Cs-137 0.661 0.05 U-235 0.143 0.24 U-238 by Th-234 0.063 0.75

• Spectra were also reviewed for other identifiable easy-to-detect TAPs that would not be expected at this site.

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D.4.2 UNCERTAINTIES The uncertainties associated with the analytical data presented in the tables of this report represent the total propagated uncertainties for that data. These uncertainties were calculated based on both the gross sample count levels and the associated background count levels.

D.4.3 DETECTION LIMITS Detection limits, referred to as minimum detectable concentrations, were based on 3 plus 4.65 times the standard deviation of the background count [3 + (4.65 (BKG) 112)]. Because of variations in background levels, measurement efficiencies, and contributions from other radionuclides in samples, the detection limits differ from sample to sample and instrument to instrument.

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