Text

Annual Radiological Environmental Monitoring Report for 2013
	ML14127A083
Person / Time
Site:	Humboldt Bay
Issue date:	04/24/2014
From:	Sharp L; Pacific Gas & Electric Co
To:	; Document Control Desk, NRC/FSME
References
	PG&E Letter HBL-14-011
	Download: ML14127A083 (60)
	v • d • e

WI Pacific Electric Gas and Companyf Loren D. Sharp Humboldt Bay Power Director and Plant Plant Manager 1000 King Salmon Avenue Humboldt Bay Eureka, CA 95503 Nuclear 707.444.0819 Internal: 375.0819 Fax: 707.444.0871 April 24, 2014 PG&E Letter HBL-14-011 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-133 License No. DPR-7 Humboldt Bay Power Plant Unit 3 Annual Radiological Environmental Monitoring Report for 2013

Dear Commissioners and Staff:

Enclosed is the Humboldt Bay Power Plant Unit 3, "Annual Radiological Environmental Monitoring Report" for 2013. This report provides the information required by Section 4.1 of the SAFSTOR/Decommissioning Offsite Dose Calculation Manual (ODCM).

The report has three sections. Section A provides a summary description of the SAFSTOR Radiological Environmental Monitoring Program (REMP), including maps of sampling locations. Section A also provides the results of licensee laboratory participation in the Interlaboratory Comparison Program.

Section B provides summaries, interpretations, and analyses of trends of the results of the REMP for the reporting period. The material provided is consistent with the objectives outlined in the ODCM, and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

Section B also includes a comparison with the baseline environmental conditions at the beginning of SAFSTOR.

Section C provides monitoring results for the reporting period, with summaries and tabulations. Radiological environmental samples and environmental radiation measurements were taken at the locations identified in ODCM Table 2-7 as quality-related locations. The summarized results are formatted for applicable reporting requirements of the NRC Radiological Assessment Branch's Branch Technical Position.

There are no regulatory commitments made in this letter.

Document Control Desk PG&E Letter HBL-14-011 April 24, 2014 Page 2 If you wish to discuss the information in the enclosed report, please contact David Sokolsky at (415) 973-5024.

Sincerely, Directorand Plant ManagerHumboldt Bay Nuclear cc/enc: Marc L. Dapas, NRC Region IV Administrator John B. Hickman, NRC Project Manager HBPP Humboldt Distribution Enclosure

Enclosure PG&E Letter HBL-14-011 HUMBOLDT BAY POWER PLANT UNIT 3 ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT JANUARY 1 THROUGH DECEMBER 31, 2013

TABLE OF CONTENTS A. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ............................. 1

1. P ro g ra m De scriptio n ........................................................ . ................................ ....... 1

2. Monitoring Requirements ............................................................................... 2

a. Offsite Environmental Monitoring .................................. 2

b. Onsite Environmental Monitoring ............................... 3

c. Othe r Monito ring ..................................................................................... .. 4

3. Interlaboratory Comparison Program ............................................................ 5

4. NEI Groundwater Protection Initiative .................................................... 5 B. TRENDS, BASELINE COMPARISONS AND INTERPRETATIONS ..................... 5

1. General Comments ......................................................................................... 6

2. Direct Radiation Pathway .............................................................................. 6

3. Airbo rne P athw ay .......................................................................................... .. 7

4. W aterborne Pathway ....................................................................................... 7 a . S urface W ate r .......................................................................................... .. 7 b . G ro u ndw ate r ............................................................................................ .. 8

5. Ingestion Pathway ......................................................................................... 8 6 . Te rrestrial P athw ay ........................................................................................ .. 8 C. MONITORING RESULTS ..................................................................................... 9

1. A nnual S um m ary .......................................................................................... .. 9

2. Direct Radiation Pathway ................................................................................ 9 3 . A irborne P athw ay .......................................................................................... .. 9

4. W aterborne Pathway ..................................................................................... 10

a. Surface W ater ......................................................................................... 10

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TABLE OF CONTENTS (Continued) b . G ro u ndw ate r ......................... .............. ...................................................... 10

5. Ingestion Pathway............................................ 12 6 . Te rre stria l Pathw ay ........................................................ .............. ...................... 12

7. NEI Groundwater Protection Initiative Voluntary Reportibg'Results ......... 12

8. Errata For Previous Years' Reports .............. .................... 13

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LIST OF TABLES Table Page A-1 HBPP RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ...... 14 A-2 DISTANCES AND DIRECTIONSTO HBPP OFFSITE SAMPLE LOCATIONS ... 15 A-3 GEL PARTICIPATION - INTERLABORATORY CROSS-CHECK PROGRAM

.....: ....... ........... .... .......... .. ............................................... 16 DA TA ................... ....

A-4 HBPP PARTICIPATION - ECKERT.& ZIEGLER INTERLABORATORY CROSS-CHECK PRO G RA M DATA .............................................................................. 20 C-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL REPORT S UMMA RY ..................................................................................................... . . 24 C-2 ONSITE ENVIRONMENTAL TLD STATIONS ................................................. 26 C-3 OFFSITE (Control) ENVIRONMENTAL TLD STATIONS ................................. 27 C-4 DISCHARGE CANAL SAMPLE RESULTS .................................................... 28 C-5 GROUNDWATER MONITORING WELL RESULTS ....................................... 30 C-6 CAISSON SUMP MONITORING RESULTS .................................................... 34 C-7 FRENCH DRAIN MONITORING RESULTS .................................................... 35 C-8 ODCM REQUIRED AIR SAMPLES ................................................................. 36 LIST OF FIGURES Figure Page A-1 HBPP ONSITE AIR SAMPLE LOCATIONS .................................................... 43 A-2 HBPP OFFSITE AIR SAMPLE LOCATION .................................................... 44 A-3 HBPP ONSITE TLD LOCATIONS .................................................................... 45 A-4 HBPP OFFSITE TLD LOCATIONS .................................................................. 46 A-5 HBPP EFFLUENT SAMPLING STATION ...................................................... 49 A-6 HBPP GROUNDWATER SAMPLE POINTS ........................................................ 50

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LIST OF FIGURES (Continued)

Figure Page A-7 HBPP OFFSITE DAIRY SAMPLE POINTS ................................ 51 B-1 OFFSITE ENVIRONMENTAL RADIATION LEVEL TRENDS............................ 52 B-2 ONSITE ENVIRONMENTAL RADIATION-LEVEL TRENDS ............... 53

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PACIFIC GAS AND ELECTRIC COMPANY ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT FOR HUMBOLDT BAY POWER PLANT UNIT 3, COVERING THE PERIOD JANUARY 1 THROUGH DECEMBER 31, 2013 This annual report is required by.Section 4.1 of the SAFSTOR Offsite Dose Calculation Manual (ODCM).. This report provides information about the Radiological Environmental Monitoring Program (REMP) for the period of January 1 through December 31, 2013, in a manner consistent with the objectives outlined in the ODCM, and in 10CFR 50, Appendix .I, Sections IV.B.2, IV.B.3, and IV.C.

The report has three sections. Section-A provides a summary description of the REMP, including maps of sampling locations.S.. Section A also provides the results of licensee laboratory participation in the Interlaboratory Comparison Program.

Section B.provides summaries, interpretations, and analyses of trends of the results of the REMP for the reporting period., The material provided is consistent with the "objectives outlined in the ODCM, and in 10CFR 50, Appendix I, Sections IV.B.2, IV.B..3, and IV.C. Section B also includes a comparison with the baseline environmental conditions at the beginning of SAFSTOR.

Section C provides the results of analyses of radiological environmental samples and of environmental radiation measurements taken during the period pursuant to the quality related locations specified in the table and figures in the ODCM, presented as both summarized and tabulated results of these analyses and measurements. The summarized results are formatted for applicable reporting requirements of the NRC Radiological Assessment Branch's Branch Technical Position.

A.- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

1. Program Description The NRC Radiological Assessment Branch issued a Branch Technical Position (BTP) on environmental monitoring in March 1978. Revision 1 of the BTP was issued as Generic Letter 79-65, "Radiological Environmental Monitoring Program Requirements - Enclosing Branch Technical Position," Revision 1, dated November 27, 1979, and sets forth an example of an acceptable minimum radiological monitoring program. The specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of individuals resulting from plant effluents.

As discussed below, many of the exposure pathway sample requirements specified in the BTP are not required for the HBPP REMP because of the baseline conditions established in the SAFSTOR Decommissioning Plan (now identified as the Post Shutdown Decommissioning Activities Report (PSDAR) and Defueled Safety Analysis Report (DSAR)) and the Environmental Report.

In addition, the nuclides' specified for analysis by the BTP have been revised to reflect the available source term.ata nhclear power plant that has been shut down since July 2, 1976.

The REMP consists of the collection and analysis of both onsite and offsite environmental samples. HBPP personnel performrsample collection and sample analysis of airborne radioactivity and surface water radioactivity.

General Engineering Laboratories (GEL)-personnel perform sample analysis of surface water strontium radioactivity, ground water radioactivity and milk radioactivity.. The Diablo Canyon.Power, Plant (DCPP) dosimetry group performs analysis of thermoluminescent dosimeters (TLDs) used for monitoring direct radiation. A summary of the REMP is provided as Table AXI, "HBPP RADIOLOGICAL ENVIRONMENTALMONITORING PROGRAM."

Sample collection for the REMP is performed at the sampling stations defined by Table A-2, "DISTANCES AND DIRECTIONS TO HBPP OFESITE SAMPLE LOCATIONS", Figure A-1, "HBPP ONSITE AIR SAMPLE LOCATIONS;" Figure A-2, "HBPP OFFSITE AIR SAMPLE LOCATION;" Figure A-3, "HBPP ONSITE TLD LOCATIONS", Figure A-4 "HBPP OFFSITE TLD LOCATIONS", FigureA-5 "HBPP EFFLUENT SAMPLING STATION", Figure A-6 "HBPP GROUNDWATER SAMPLE POINTS", and Figure A-7 "HBPP OFFSITE DAIRY SAMPLE POINTS."

2. Monitoring Requirements,

a. Offsite Environmental Monitoring

1. Airborne The SAFSTOR ODCM requires one (1) offsite environmental air sampling station. The air sampler is run continuously and samples are analyzed weekly for Gross Beta and Gross Alpha activity. Station 3 satisfies this requirement as shown on Figure A-2. Quarterly the composited samples are analyzed for Gamma Isotopic.

2. Direct Radiation The SAFSTOR ODCM requires four (4) offsite environmental monitoring stations and one (1) offsite control station equipped with TLDs to monitor gamma exposure. The TLDs are required to be exchanged quarterly.

The stations selected to satisfy this requirement are Stations 1, 2, 14, 25,

.and T17 as shown on Figure A-4. These stations are considered to be the five control locations for the direct radiation dose pathway.

3. Ingestion The SAFSTOR ODCM requires-two (2) offsite milk samples be collected, annually. The samples are collected .from the Pedrotti and Holgerson Dairies, local to the plant.. Locations of the two dairies are shown on Figure A-7. The samples are analyzed for Strontium -90 and Gamma Isotopic.,

b. Onsite Environmental Monitoring

1. Airborne The SAFSTOR ODCM require.s five (5) air sampling stations. The stations selected to satisfy this requirement are Stations AM1 through AM5 as shown on Figure A-1. The air samplers are run continuously and samples are. analyzed weekly for Gross Beta and Gross Alpha activity.

Quarterly the composited samples are analyzed for Gamma Isotopic, by station.

2. Direct Radiation The SAFSTOR ODCM requires 16 onsite environmental monitoring stations, equipped with TLDs to monitor gamma exposure. The TLDs are required to be exchanged quarterly. The stations selected to satisfy this requirement are Stations T1 through T16, shown on Figure A-3. Four (4) additional TLDs were added around the ISFSI in 2010. These are Stations T18 through T21..

Each quarter the exposures from 20 stations are determined, which results in 80 analyses for a full year. Each TLD station has three TLDs, each containing a number of phosphors (normally three). The phosphor exposures for each TLD are averaged and then the three TLDs per station are averaged to provide the quarterly exposure-for the station.

3. Waterborne Surface Water The SAFSTOR ODCM requires the discharge canal effluent be sampled.

Composite samples are normally collected weekly from a continuous sampler, with dip (grab) samples collected if the sampler is inoperable.

Location of the effluent sample station is shown on Figure A-5. These samples are analyzed for gamma isotopic analysis, Strontium-90, and tritium analysis.

Groundwater The SAFSTOR ODCM Revision 22 required twelve groundwater wells be monitored by gamma isotopic analysis, Strontium-90 and by tritium analysis. Samples are to be collected quarterly. The monitoring wells selected to satisfy this .'requirement are identified as: MW-1, MW-2, MW-4, MW-6, MW-1 1, RCW-SFP-1, RCW-SFP-2, RCW-CS-I,, RCW-CS-2, RCW-CS-3, RCW-CS-4, and RCW-CS-5.

Revision 23 of the ODCM transferred ground water monitoring program requirements from the ODCM to HBPP's ground water monitoring program procedures. The number and type of required monitoring wells are specified by procedure ratherthan the ODCM. This was done to allow operational flexibility needed to-adjust-to changes to site access and hydrogeology as soils and building substructures are removed. SAPN 1290022 documents the changes made to Revision 23 of the ODCM.

Shallow ground water monitoring wells RCW-SW-1, RCW-SW-2, RCW-SW-3 and RCW-SW-4 were developed in January 2012. Intermediate ground water monitoring well RCW-SFP-3 and deep ground water monitoring wells RCW-CS-6 and RCW-CS-7 were developed in June 2012." Intermediate ground water monitoring wells RCW-SFP-4 and RCW-SFP-5 and deep ground water monitoring wells RCW-CS-8 and RCW-CS-9 were developed in August 2013.

A total of nineteen (19) monitoring wells were sampled during the first and second quarterly sampling events, including the 12 wells previously required by the ODCM. During the third quarter event, twenty-one (21) monitoring wells were sampled, and twenty-two (22) wells were sampled during the fourth quarter sampling event. Well locations are shown on Figure A-6, "HBPP GROUNDWATER SAMPLE POINTS."

c. Other Monitoring Airborne, ingestion and terrestrial pathway monitoring is not required by the ODCM. The Environmental Report, submitted to the NRC as Attachment 6 to SAFSTOR License Amendment Request 84-01, dated July 31, 1984, established baseline conditions for these pathways. In accordance with the NRC-approved SAFSTOR Decommissioning Plan, (now identified as the PSDAR and DSAR), these baseline conditions will only need to be reestablished prior to final decommissioning if a significant release occurs during SAFSTOR. The Environmental Report also contains a description of the demography and human activities within the environs surrounding the site.

As a matter of plant policy, groundwater leakage into the reactor caisson is routinely sampled, approximately monthly, and analyzed for tritium and gamma emitters, in order to develop a historical record of these parameters.

The results are reported in Table C-6, but are not considered part of the SAFSTOR REMP.

3. Interlaboratory Comparison Program PG&E's contract laboratory, GEL, ,has analyzed evaluation samples provided by

..a commercial supplier.to satisfy the-requirement to participate in an-Interlaboratory Cross-Check Program., HBPP countroom personnel also participated in the-Eckert & Ziegler Interlaboratory Cross-Check Program. This participation includes sufficient determinations (sample medium and.

radionuclide combination) to ensure independent checks on the precision and accuracy of the measurements of radioactive materials in the REMP'samples.

Table A-3, "GEL PARTICIPATION - INTERLABORATORY CROSS-CHECK PROGRAM DATA", and Table A-4, '.HBPP PARTICIPATION - ECKERT &

ZIEGLER INTERLABORATORY QROSS-CHECK PROGRAM DATA",

represent analyses performed for HBPP. (Table A-3) and by HBPP personnel (Table A-4). The agreement criteria: are consistent with the guidance for "Confirmatory Measurements" as described in NRC Inspection Procedure 83502.03, ."Radiological -Environment Monitoring Program and Radioactive Material Control Program."

GEL analyzed four sets of Eckert & Ziegler Analytics samples for 23 parameters that are representative of analyses performed for HBPP during 2013. All results met the acceptance criteria.

HBPP analyzed four sets of Eckert & Ziegler Analytics samples for: gamma in soil, gamma in water ( 1 st & 3 rd quarters), -tritium in water (3r quarter), and alpha beta - air filter, gamma - air-filter (2 nd, & 4 th quarters). These analyses are representative ofthose performed-by HBPP.count room personnel during 2013.

All results met the acceptance criteria.

4. NEI Groundwater Protection Initiative Groundwater monitoring data. is collected in accordance with the Nuclear Energy Institute (NEI) Groundwater Protection Initiative. The results show that there are detectable concentrations of radionuclides in the groundwater within the HBPP restricted area. These are believed to be the results of historical spills at the site.

The impact of these detectable concentrations is negligible, because the groundwater is saline and is not used now nor likely to be used in the future for either direct consumption or for agricultural purposes.

B. TRENDS, BASELINE COMPARISONS AND INTERPRETATIONS Section B provides interpretations of results, and analyses of trends of the results. The material provided is consistent with the objectives outlined in the ODCM, and in 10CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

Section B also includes a comparison with the baseline environmental conditions at the beginning of SAFSTOR.

1. General Comments The Environmental Report, submitted to -the NRC as Attachment 6 to SAFSTOR License Amendment ReqUest 84-01, established baseline conditions

,for soil, biota and sediments: The results to date indicate no significant change from the baseline environmental conditions establishediin the Environmental Report.

The results, interpretations, and analysis 6f trends of the results, indicate that

SAFSTOR activities have had no measurable radiological effect on the environment. Facility surveys for radiation!and radioactive surface contamination are performed on. both a scheduled basis and on an as-required basis. These surveys indicate that the radioactivity control barriers established for SAFSTOR and decommissioning continue to be effective.

As discussed below, the ODCM calculation model conservatively assumes that exposure pathways begin at the unrestricted area boundary, also'known as the owner controlled area (OCA) boundary. Since there have been no significant changes in the location of the boundary, no survey for changes to the use of unrestricted areas was necessary.

2. Direct Radiation Pathway A plot of the radiation level trends for the five (offsite) locations is shown in Figure B-I, "OFFSITE ENVIRONMENTAL RADIATION LEVEL TRENDS." A plot of the radiation level trends for onsite stations is shown in Figure B-2, "ONSITE ENVIRONMENTAL RADIATION LEVEL TRENDS." The plots show that the offsite annual doses continue to be within the ranges that have been observed over the last ten years.

Figure B-2 includes the average dose for two-groups of onsite stations, selected by their potential to be affected by radioactive waste handling activities. Figure B-2 also shows that dose measurement variations can be attributed to in-plant sources and low-level waste packaging and shipping activities. However, allowing for the background change in the general environs, all measurements were comparable to the ranges observed at these locations since entering SAFSTOR, with the onsite station dose levels approximately within the range of dose levels shown by the offsite stations.

The ODCM calculation model for the direct radiation exposure pathway assumes an occupancy factor for the portion of the unrestricted area boundary that is closest to the radioactive waste handling area of the plant, (TLDs T5-T8),

which is the location of the highest potential exposure. The occupancy factor is 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months per year, based on regulatory guidance for shoreline recreation, even though the actual shoreline is farther from the boundary. Since there have been no significant changes of the locations of the radioactive waste handling activities, boundary, or shoreline, no further survey for changes to the use of unrestricted areas is necessary. Using the maximum yearly dose, as seen on TLDs T5-T8 and corrected to the 67 hour7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months occupancy, and subtracting the average of the five (5) offsite TLDs, the dose to the maximum exposed individual from this source was indistinguishable from background.

The Independent SpentFuel Storage Installation (ISFSI) was constructed in 2008, and spent fuel transfer from thespent fuel pool.(SFP) was completed in December 2008. As..a result of this, the dose rates. at the OCA fence line increased slightly. The. ISFSI Final Safety Analysis Report (FSAR) assumes an occupancy factor of 2,080 hours9.259259e-4 days 0.0222 hours 1.322751e-4 weeks 3.044e-5 months per year at the OCA fence line. Using the maximum yearly dose, as seen on TLDs T18-T21 and corrected to the 2080 hour0.0241 days 0.578 hours 0.00344 weeks 7.9144e-4 months occupancy, and subtracting the average of the.five (5) offsite control TLDs, the dose to the maximum -exposed individual from. this source would be 1.8 mRem per year.

3. Airborne Pathway.

Airborne pathway monitoring is not required by the ODCM. The Environmental Report, submitted to the NRC as Attachment 6 to SAFSTOR License Amendment Request 84-01, established baseline conditions for the airborne pathway: In accordance with the NRC-approved SAFSTOR Decommissioning Plan, (now identified as the PSDAR and DSAR), these baseline conditions will only need to be reestablished prior to final decommissioning if a significant release occurs during SAFSTOR. The ODCM calculation model for the airborne pathway assumes that the airborne exposure pathway (inhalation exposure) is at the unrestricted area boundary, which is the location of the highest potential exposure.

4. Waterborne Pathway

a. Surface Water None of the REMP samples indicated detectable levels of tritium or gamma radioactivity. .These sample results were typical of those observed since entering SAFSTOR.

The ODCM calculation model for the surface water waterborne pathway assumes that the waterborne exposure pathway (vertebrate and invertebrate food consumption) begins at the unrestricted area boundary, which is the location of the highest potential exposure.

The ODCM calculation model is based on the average concentration of the radioactivity released and diluted by the tidal flow of water in the discharge canal. For the purposes of comparing the sampling results with effluents, consider a conservatively estimated liquid waste batch of 7,000 gallons containing tritium at 30,000 pico-Curies/liter, Cs-137 at 1,000 pico-Curies/liter, and Co-60 at 100 pico-Curies/liter. For a single batch release during a week-long canal composite sample, the tidal flow volume is approximately 7E+06 gallons, so the diluted activity for tritium, Cs-1 37 and Co-60 would be 30, 1.0, and 0.1 pico-Curies/liter, respectively. These concentrations are unlikely to be detected.

b. Groundwater None of the samples of the twelve (12) SAFSTOR REMP monitoring wells indicated detectable levels of tritium.. Additional well sampling also did not indicate detectable levels of tritium. -For gamma radioactivity, sample results were typical of those observed since entering SAFSTOR. Results for other parameters and samples were comparable to the ranges observed since

.entering SAFSTOR.

This report also contains information ongamma emitting radionuclides and tritium concentrations in the Caisson Surnmpand gammaemitting radionuclide concentrations for the SFP French Drain. There is detectable radioactivity, due to plant operations, at these sample points. Both of these locations are believed to be contaminated as a result of groundwater intrusion into historically contaminated areas of concrete and fill material.

The ODCM does not provide a model for the groundwater waterborne pathway, because the groundwater is saline and is not used now nor likely to be used in the future.for either directconsumption or for agricultural purposes.

5. Ingestion. Pathway Ingestion pathway monitoring is not required by the ODCM. The Environmental Report, submitted to the NRC as Attachment 6 to SAFSTOR License Amendment Request 84-01, established baseline conditions for the ingestion pathway. In accordance with the NRC-approved SAFSTOR Decommissioning Plan, (now identified as the PSDAR and DSAR), these baseline conditions will only need to be reestablished prior to final decommissioning if a significant release occurs during SAFSTOR.

The ODCM calculation model for the airborne pathway assumes that the ingestion pathways (milk, meat and vegetable consumption) begin at the unrestricted area boundary, which is the location of the highest potential exposure, whether any dairy, farm,; etc. is actually present.

6. Terrestrial Pathway Terrestrial pathway monitoring is not required by the ODCM. The Environmental Report, submitted to the NRC as Attachment 6 to SAFSTOR License Amendment Request 84-01, established baseline conditions for the terrestrial pathway. In accordance with the NRC-approved SAFSTOR Decommissioning Plan, (now identified as the PSDAR and DSAR), these baseline conditions will only need to be reestablished prior to final decommissioning if a significant release occurs during SAFSTOR.

The ODCM calculation model for the terrestrial pathway conservatively assumes that the terrestrial exposure (direct radiation from airborne radioactivity deposition) is at the unrestricted area boundary, which is the location of the highest potential exposure.

C. MONITORING RESULTS

1. Annual Summary Results of the REMP sampling and analysisare summarizedin Table C-1 in the format of the BTP Table 3. 1None-of the REMP samples results exceeded the reporting levels for radioactivity concentration in-environmental samples specified in HBPP ODCM Table 2-8.

All of the minimum detectable activities (MDAs) for analyses required by the SAFSTOR REMP were less than or equal to the lower limit of detection (LLD) criteria for radioactivity in environmental samples specified in Table C-1 of this report, with one exception. The air sample pump located at the Oil Water Separator (OWS) malfunctioned after running approximately 17 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months on 6/12/2013. The beta LLD 3.

was determined to be 6.05E-02 pCi/M 3 instead of the required 1.,OE-02 pCi/mi Because alpha and beta radioactivity analyses of the saline ground water are less effective than tritium and gamma radioactivity analyses for monitoring potential SFP leakage, the ODCM does not currently require alpha and beta radioactivity analyses in water to be part of the SAFSTOR REMP.

2. Direct Radiation Pathway...

Monitoring of the.*direct radiation pathway is performed at 20 onsite locations near the OCA fence line, and at four offsite environmental monitoring stations and one offsite (control) location (Location number T17) in the vicinity of the facility. Monitoring is performed with TLDs, with multiple crystal elements.

Three TLDs are installed at each station, and the set is exchanged quarterly.

The reported result and its standard error are calculated from the measurements of multiple elements in the TLD triplet. Results of the onsite and offsite monitoring are provided in Tables C-2 and C-3, respectively.

3. Airborne Pathway Five onsite samples and one offsite sample were collected and analyzed weekly for Gross Beta and Gross*Alpha activity, with the following exceptions:

Relay Building, collected 6/06/2013, Oil Water Separator (OWS), collected 6/12/2013, and Humboldt Hill, collected 7/25/2013. In the first case, the Relay Building air sampler was found running but the timer used for verification purposes was found to have malfunctioned. In the second case, the air sample pump at the OWS malfunctioned after running approximately 17 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months . In the third case, the air sampler at Humboldt Hill was found with a blown fuse. Air sample analysis was based on instrument totalizer measurement. These problems were described in corrective action SAPNs 1299910, 1300292, and 1301384.

The required quarterly composited samples were analyzed for Gamma Isotopic by station.

All LLD's were met for Gross Beta (required LLD 1.OE-02 pCi/m 3 ) and Cs-1 37 (required LLD of 6.0E-02 pCi/m 3 ): 'The only exception was the air sample taken from the Oil Water Separator (OWS), on 6/12/2013, which had a sample pump malfunction after running approximately'17 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months . The beta LLD was determined to be 6.05E-02 pCi/m 3 instead of the required 1.0E-02 pCi/m 3 . This problem was documented in SAPN 1300292::-

4. Waterborne Pathway

a. Surface Water Surface water sampling of the waterborne pathway is performed by sampling the discharge canal effluent. Sampling is normally performed by collecting a weekly sample from a discharge canal continuous composite sampler. If the composite sampler is found to be inoperable, dip samples from the discharge canal are taken.

All samples with the exception of one collected during the reporting period were obtained from the continuous composite sampler. The discharge canal sample collected on 7/3/2013 was a dip sample that was performed due to a malfunctioning sample pump. This problem was documented in SAPN 1300490.,

Detailed results of the discharge canal monitoring are provided in Table C-4.

None of the REMP samples indicateddetectable levels of tritium or gamma radioactivity at or above the MDA.

The ODCM states in a footnote to Table 2-7 that sampling of the Discharge or Intake Canal may be suspended when no effluent discharge has occurred in the previous 10 days. Final release of treated process water to the discharge canal was performed on 12/11/2013 and the final sample collected from the discharge canal compositor was obtained on 12/23/2013.

SAPN 1382252 was written to document the cessation of process water discharges to thecanal and subsequent actions that occurred as a result of the termination.

b. Groundwater Groundwater sampling of the waterborne pathway is performed by sampling twelve (12) monitoring wells located to monitor for leakage from the SFP.

Sampling of these monitoring wells is performed quarterly in accordance with Revision 22 of the ODCM.

Revision 23 of the ODCM transferred ground water monitoring program requirements from the ODCM to HBPP's ground water monitoring program procedures. The number and type of required monitoring wells are specified by procedure rather than the ODCM to allow operational flexibility needed to adjust to changes to the site during decommissioning and demolition activities. Ground water results will continue to be reported in the annual REMP report.. Detailed-, results of-groundwater monitoring are provided in Table C-5.

The tritium concentration fo.r all of the wells listed in Table C-5 during 2013

.was less than the.MDA of approximately 300 pCi/liter. All of the monitoring wells are inside. the.OCA boundary, and the groundwater is saline and is not used now nor likely to be used, in the future-for either direct consumption or for agricultural purposes.- Therefore, there is no groundwater waterborne pathway for a member of the public. None of the other ODCM required REMP samples indicated detectable levels of tritium or gamma radioactivity.

Because alpha and beta radioactivity analyses of the saline groundwater are less effective than tritium and gamma radioactivity analyses for monitoring potential SFP leakage, the ODCM does not currently require alpha and beta radioactivity analyses to be part-of the SAFSTOR REMP. Nevertheless, alpha and beta radioactivity analyses are performed as a matter of plant policy, in order to maintain a historical record of this parameter for the remainder of SAFSTOR. These results are included in Table C-5, but are not considered part of the SAFSTOR REMP.

All required sampling and analysis for the monitoring wells of the waterborne pathway required during this reporting period were performed successfully with the following exceptions:.. -

A sample for tritium from MW-11 in the second quarter was received by GEL with a broken cap. Although it appeared that inadequate sample remained for the tritium analysisiGEL was able to perform the analysis.

This was documented in corrective action SAPN 1299438.

, Monitoring wells MW-1 and RCW-CS-4 were not sampled during the third quarter of 2013 as they were covered by decommissioning debris.

Monitoring well MW-1 was not sampled during the fourth quarter of 2013, again because the well remained covered by decommissioning debris. These problems were documented in corrective action SAPNs 1303015 and 1305723.

Shallow monitoring wells RCW-SW-2 and RCW-SW-3 were observed to exhibit poor groundwater recharge during the fourth quarter sampling event. Samples from each of the shallow wells also displayed higher than normal turbidity levels. The change in well conditions may be associated with seasonal influence and the lack of precipitation over the past several months. The problem was documented in SAPN 1381086 and will be monitored during future events by the certified geologist who oversees the sampling effort.

Groundwater leakage into the reactor caisson is also routinely sampled, approximately monthly, and analyzed for gamma emitters and tritium as a matter of plant policy, in order to develop a historical record of these parameters for SAFSTOR and.decommissioning. These results are included in Table C-6, but are not considered part of the SAFSTOR REMP.

The french drain beneath the SFP is also routinely sampled, approximately monthly, and analyzed for gamma emitters as a matter of plant policy, in order to develop a historical record of this parameter for SAFSTOR and decommissioning. These results are included inTable C-7, but are not considered part of the SAFSTOR REMP.,_:--'1

5. Ingestion Pathway HBPP personnel collected two (2) milk samples and sent the samples off site to GEL laboratories for analysis. The samples were collected and counted for gamma isotopic with no gamma peaks identified other than naturally occurring, and the Total' Strontium was reported as undetected.

6. Terrestrial Pathway Terrestrial pathway monitoring is not required by the ODCM.

7. NEI Groundwater Protection Initiative Voluntary Reporting Results The NEI Groundwater Protection Initiative contains the following requirements:

OBJECTIVE 2.2 VOLUNTARY COMMUNICATION Make informal notification as soon as practicable to appropriateState/Local officials, with follow up notification to the NRC, as appropriate,regarding significant onsite leaks/spills into groundwaterand onsite or offsite water sample results exceeding the criteria in the REMP as described in the ODCM/ODAM.

HBPP Response to 2.2:

There were no reports or notifications required to be generated in 2013 for groundwater results exceeding reporting/notification levels or significant onsite leaks/spills.

OBJECTIVE 2.3 THIRTY-DAY REPORTS Submit a 30-day report to the NRC for any water sample result for onsite groundwaterthat is or may be used as a source of drinking water that exceeds the criteriain the licensee's existing REMP for 30-day reporting of offsite water sample results., Cbpies'ofO30-day reportsfor both onsite and offsite water samples will also be provided to the appropriateState agency, and.-

HBPP Response to 2.3:

There were no reports or notifications required to be generated in 2013 for groundwater results exceeding reporting/notification levels or significant onsite leaks/spills.

OBJECTIVE 2.4 ANNUAL REPORTING Document all on-site ground water sample results and a descriptionof any significant on-site leaks/spills into groundwaterfor each calendaryear in the AREOR for REMP or the ARERR for the RETS as containedin the appropriatereporting procedure, beginning with Calendaryear 2006.

HBPP Response to 2.4:

Onsite groundwater monitoring points are described and reported in this report as follows: MW-1, MW-2, MW-4, MW-6, MW-1 1, RCW-SFP-1, RCW-SFP-2, RCW-SFP-3, RCW-CS-I., RCW-CS-2, RCW-CS-3, RCW-CS-4, RCW-CS-5, RCW-CS-6, RCW-CS-7, RCW-SW-1, RCW-SW-2, RCW-SW-3, RCW-SW-4, the caisson sump and the french drain. A summary of the sample results are provided in Section C.

There were no significant onsite leaks/spills into groundwater in 2013.

Note: the term "significant" is defined by the NEI Initiative as greater than 100 gallons.

8. Errata for Previous Years' Reports None.

TABLE A-I:

HBPP RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and Type of Analysis And/Or Sample And' Locations - Collection Frequency . _ _

AIRBORNE 5 onsite locations,." Continuous. sampler Gross alpha and 1 offsite Iocation '.operationwith sample . Gross beta collection at least once per radioactivity following 7 days filter change. Gamma Isotopic(a) analysis on quarterly composite (by

... _________________...___'station).

DIRECT RADIATION 20 onsite stations with TLDs exchanged quarterly Gamma exposure TLDs .*

5 offsite stations with TLDs exchanged quarterly Gamma exposure TLDs WATERBORNE S--urface water ischargecanaleffIuent.....Con-tinu-ous sam-pler ........ .G-amma- lsotopic(a .

-D-----------

'operation with sample and tritium analysis collection weekly. of weekly sample.

Dip samples if sampler inoperable Groundwater 19 monitoring wells Quarterly Gross alpha and sampled in Q1 and Q2; Gross beta 21 monitoring wells radioactivity, Tritium sampled in Q3; 22 and Gamma monitoring wells sampled Isotopic(a) analysis.

in Q4 INGESTION Milk 2- (Holgerson & Pedrotti Annually Strontium 90, and Dairies) ...

Gamma Isotopic(a)

_ _.__. "__"analysis (a) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the facility.

TABLE A-2 DISTANCES AND DIRECTIONS TO HBPP OFFSITE SAMPLE LOCATIONS Radial Direction Offsite Station: Measurement By Radial Distance Number Pathway . Station Name Sector Degrees From Plant (Miles) 3 Airborne HumibQldt Hill. SSE *158 0.9 King Salmon 1 Direct Radiation Picnic Area... W.. 270 0.3 2 Direct Radiation City of Fortuna SSE 158 9.4 Water POllutiQn Control Plant,.:180 Dinsmore Drive, Fortuna 14 Direct Radiation South Bay School S 180 0.4 Parking Lot 25 Direct Radiation Irving Drive, SSE 175 1.3 Humboldt Hill T17 Direct Radiation Mitchell Heights NNE 45 6 Drive _

16 Ingestion - Milk Pedrotti Dairy ENE 72 1.4 48 Ingestion - Milk , Holgerson Dairy' S 180 5.1 TABLE A-3 GEL PARTICIPATION - INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2013 Date Value Value (pCi/L) (pCi/L)

Gamma Water 1-131 E10380 1st 2/01/2013 7.47E+01 7.25E+01 1.03 Acceptable Cr-51 E10380 1st 2/01/2013 3.81E+02 3.62E+02 1.05 Acceptable Cs-134 E10380 1st 2/01/2013 1.57E+02 1.73E+02 0.91 Acceptable Cs-137 E10380 1st 2/01/2013 1.25E+02 1.22E+02 1.03 Acceptable Co-58 E10380 1st 2/01/2013 1.02E+02 1.03E+02 0.99 Acceptable Mn-54 E10380 1st 2/01/2013 1.28E+02 1.21E+02 1.06 Acceptable Fe-59 E10380 1st 2/0112013 1.38E+02 1.21 E+02 1.14 Acceptable Zn-65 E10380 1st 2/01/2013 2.13E+02 1.94E+02 1.10. Acceptable Co-60 E10380 1 st 2/0112013 1.80E+02 1.77E+02 1.01 Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2013 Date Value Value (pCi/L) (pCi/L)

Milk Sr-89 E10324 1st 2/0112013 9.18E+00 9.66E+00 0.95 Acceptable Sr-90 E10324 1st 2/01/2013 9.89E+00 1.38E+01 0.72 Acceptable 1-131 E10325 1st 2/01/2013 9.57E+01 9.OOE+01 1.06. Acceptable Cr-51 E10325 1st 2/01/2013 3.67E+02 3.48E+02 1'.06 Acceptable Cs-134 E10325 1st 2/01/2013 1.54E+02 1..65E+02-! - 0.938 Acceptable Cs-137 E10325 1st 2/01/2013 1.18E+02 1.17E+02 . .1.01 Acceptable Co-58 E10325 1st 2/01/2013 9.85E+01 9.85E+01.. 1.00 Acceptable Mn-54 E10325 1st 2/01/2013 1.16E+02 1.16E+02 1.00 Acceptable Fe-59 E10325 1st 2/01/2013 1.33E+02 1.16E+02 1.15 Acceptable Zn-65 E10325 1st 2/01/2013 3.19E+02 2.91E+02 1.09 Acceptable Co-60 E10325 1st 2/01/2013 "1.73E+02 1.70E+02 1:002 Acceptable Cs-141 E10325 1st 2/01/2013 5.38E+01 5.10E+01 1.05 Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2013 Date Value Value I (pCi) (pCi) I .

Cartridge 1-131 E10323 1st 2/01/2013 7.31E+01 7.29E+01 1.00 Acceptable TABLE A-3 (Continued)

GEL PARTICIPATION - IN"FERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2013 Date Value Value (pCi/L) (pCi/L)

Gamma Water 1-131 E10472 2nd 4/25/2013 1..12E+02 9.28E+01 1.21 Acceptable Ce-141 E10472 2nd 4/25/2013 1.88E+02 1.79E+02 1.05 Acceptable Cr-51 E10472 2nd 4/25/2013 4.84E+02 4.52E+02 1.07 Acceptable Cs-134 E10472 2nd 4/25/2013 1.96E+02 2.05E+02 0.96 Acceptable Cs-137 E10472 2nd 4/25/2013 2.71E+02 2.54E+02 1.07 Acceptable Co-58 E10472 2nd 4/25/2013 2.03E+02 1.99E+02 1.02 Acceptable Mn-54 E10472 2nd 4/25/2013 2.15E+02 1.99E+02 1.08 Acceptable Fe-59 E10472 *2nd 4/25/2013 2.67E+02 2.41 E+02 1.11 Acceptable Zn-65 E10472 2nd 4/25/2013 3.14E+02" 2.88E+02 1.09 Acceptable Co-60 E10472 2nd 4/25/2013 3.92E+02 3.83E+02' 1.02 Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2013 Date Value- Value (pCilL) (pCi/L) .

Milk 'Sr-89 E10470 2nd 4/25/201.3 1.07E+02 9.97E+01 --1.07 Acceptable Sr-90 E10470 2nd 4/25/2013 1.18E+01 11110,E+01 -1.07 Acceptable 1-131 E10471 2nd 4/25/2013 1.12E+02 1.OOE+02 t1.12 Acceptable Ce-141 E10471 2nd 4/25/2013 2.OOE+01 1.87E+01 1.07 Acceptable Cr-51 E10471 2nd 4/25/2013 5.09E+01 4.72E+01 1.08 Acceptable Cs-134 E10471 2nd 4/25/2013 2.06E+02 2.14E+02 0.96 Acceptable Cs-137 E10471 2nd 4/25/2013 2.83E+02 2.66E-02 1.07 Acceptable Co-58 E10471 2nd 4/25/2013 2.19E+02 2.08E+02 1.05 Acceptable Mn-54 E10471 2nd 4/25/2013 2.21E+02 2.08E+02 1.06 Acceptable Fe-59 E10471 2nd 4/25/2013 2.78E+02 2.52E+02 1.10 ,Acceptable Zn-65 E10471 2nd 4/25/2013 3.39E+02 3.01E+02 1.13 Acceptable Co-60 E10471 2nd 4/25/2013 4.02E+02 4.OOE+02 1.01 Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2013 Date Value Value (pCi) (pCi) I Cartridge 1-131 E10469 2nd 4/25/2013 9.38E+01 9.27E+01 1.01 Acceptable TABLE A-3 (Continued)

GEL PARTICIPATION - INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2013 Date Value Value (pCi/L) (pCilL)

Gamma Water 1-131 E10178 3rd 8/02/2013 9.33E+01 9.54E+01 .0.98 Acceptable Ce-141 E10178 3rd 8/02/2013 1.15E+02 1.1OE+02 1.04 Acceptable Cr-51 E10178 3rd 8/02/2013 3.40E+02 3.06E+02 1.11 Acceptable Cs-134 E10178 3rd 8/02/2013 1.48E+02 1.53E+02 0.97 Acceptable Cs-137 E10178 3rd 8/02/201.3 1.83E+02 1.84E+02 0:99 Acceptable Co-58 E10178 3rd 8/02/2013 1.13E+02 1.15E+02 0.99 Acceptable Mn-54 E10178 3rd 8/02/2013 2.09E+02 2.1OE+02 " 1.00 Acceptable.

Fe-59 E10178 3rd 8/02/2013 1.51 E+02 1.46E+02 1.03 Acceptable Zn-65 E10178 3rd 8/02/2013 2.86E+02 2.65E+02 1.08 Acceptable Co-60 E10178 3rd 8/02/2013 2.25E+02 2.14E+02. 1.05 Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 20,13 Date Value Value

__ _ __ _ ___(pCi/L) (pCi/L) :_ -_ ._ ..

Milk Sr-89 E10578 3rd 8/02/2013 9.27E+01 9.50E+01 0.98 Acceptable Sr-90 E10578 3rd 8/02/2013 1.20E+01 1.7*0E+0,'1. 0.70 Acceptable 1-131 E1.0579. 3rd 8/02/2013 9.86E+01 9.55.+01, 1.03 Acceptable Ce-141 E10579 3rd 8/02/2013 9.44E+01 9.04E+01 - 1.04 Acceptable Cr-51 E10579 3rd 8/02/2013 2.58E+02 2.50E-40.2 1.03 Acceptable Cs-1 34 E10579 3rd 8/02/2013 1.21E+02 1..25E+02. 0.97 Acceptable Cs-137 E10579 3rd 8/02/2013 1.49E+02 1.51E+02 0.99 Acceptable Co-58 E10579 3rd 8/02/2013 9.44E+01 9.40E+01 1.00 Acceptable Mn-54 E10579 3rd 8/02/2013 1.80E+02 1.72E+02 1.05 Acceptable Fe-59 E10579 3rd 8/02/2013 1.36E+02 1.20E+02' 1.14 Acceptable Zn-65 E10579. 3rd 8/02/2013 2.39E+02 2.17E+02 1.10 Acceptable.

Co-60 E10579 3rd 8/02/2013 1.77E-+0.1- 1.75E+01 1.01 'Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2013 Date Value-- Value (pCi) . (pCi) -_. _ .-- _ "

Cartridge 1-131 E10577 3rd 8/02/2013 9..16E+01 8.96E+01 1.02 Acceptable TABLE A-3 (Continued)

GEL PARTICIPATION - IN"TERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis "Number 2013 Date Value Value (pCilL) (pCi/L)

Gamma Water 1-131 .E10628 4th 10/25/2013 1.01 Et02 9.79E+01 1.03 Acceptable.

Cr-51 E10628 4th 10/25/2013 2.80E+02 2.51E+02 1.12 Acceptable Cs-134 E10628 4th 10/25/2013 1.42E+02 1.56E+02 0.91 Acceptable Cs-137 E 10628 4th 10/25/2013 1.19E+02 1.18E+02 1.01 Acceptable Co-58 E10628 4th 10/25/2013 9.80E+01 9.73E+01 1.01 Acceptable Mn-54 E10628 4th 10/25/2013 1.29E+02 1.25E+02 1.05 Acceptable Fe-59 E10628 4th 10/25/2013 1.23E+02 1.18E+02 1.04 Acceptable Zn-65 E10628 4th 10/25/2013 .2.62E+02 2.41E+02 1.09 Acceptable Co-60 E10628 4th 10/25/2013 1.87E+02 1.77E+02 1.06 Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2013 Date Value Value (pCi/L) (pCi/L) .. ... .

Milk Sr-89 E10626 4th 10/25/2013 9.33E+01 9.60E+01 0.97, Acceptable Sr-90 E10626 4th 10/25/2013 1.09E+01 1.32E+'61 0.83 Acceptable 1-131 E10627 4th- 10/25/2013 1.OOE+02 9.83E+01 . 1.02 Acceptable Cr-51 E10627 4th 10/25/2013 3.09E+02 2.77E+02 1.11 Acceptable Cs-134 E10627 4th 10/25/2013 1.46E+02 1.72E402 0.85 Acceptable Cs-137 EE10627 4th 10/25/2013 1.33E+02 1.31 E+02 1.02 Acceptable Co-58 El 0627 4th 10/25/2013 1.04E+02 1.08E+02 0.:97 Acceptable Mn-54 El10627 4th - 10/25/2013 1.44E+02 1.39E+02 1.04 Acceptable Fe-59 E10627 4th 10/25/2013 1.43E+02 1.30E+02 1.10 Acceptable Zn-65 E10627 4th 10/25/2013 2.86E+02 2.66E+02 1.07 Acceptable Co-60 E10627 4th 10/25/2013 2.01 E+02 1.96E+02 1.03 Acceptable Sample/ Radionuclide Sample Quarter Report GEL- Reference Ratio Evaluation Analysis Number 2013 Date Value Value I (pCi) (pCi) I Cartridge 1-131 E10625 4th 10/25/2013 8.57E+01 7.96E+01I 1.08 Acceptable TABLE A-4 HBPP PARTICIPATION - ECKERT & ZIEGLER INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2013 Date Count Value Room (pCi/L)

(pCi/L)

Gamma Water Ce-141 E10482 1st 4/15/2013 1.89E+02 1.79E+02 1.05 Acceptable Cr-51 E10482 1st 4/15/2013 4.60E+02 4.52E+02 1.02 . Acceptable Cs-134 E10482 1st 4/15/2013 2.15E+02 2.05E+02 1.05 Acceptable Cs-137 E10482 1st 4/15/2013 2.63E+02 2.54E+02 1.03 Acceptable Co-58 E10482 1st 4/.15/2013 2.02E+02 1.99E+02 1.01 Acceptable Mn-54 E10482 1st 4/15/2013 2.08E+02 1.99E+02 1.04 Acceptable Fe-59 E 10482 1st 4/15/2013 2.82E+02 2.41E+02 1.17 Acceptable Zn-65 E 10482 .1st 4/15/2013 3.13E+02 2.88E+02 1.09 Acceptable Co-60 E10482 1st 4/1.5/2013 3.61E+02 3.83E+02 0.94 Acceptable Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2013 Date . Count Value ...

Room (pCi/g) .

_____________ (pCi/g) ._.__._, _ -_"." _" . ..

Gamma Soil Ce-141 E10483 1st 4/15/2013' 3.53E-01 3.1L3E-01 -1.13 Acceptable Cr-51 E10483 1st 4/15/2013 8.06E-01 7.89E-01' . 1.02 Acceptable Cs-134 E10483 1st 4/15/2013 3.60E-01 3.58E-0.1 ... . 1.01 Acceptable..

Cs-137 E10483 1st 4/15/2013 5.63E-01 5.29E-01 1.06 Acceptable Co-58 E10483 1st 4/15/2013 3.54E-01 3.48E-01 1.02 Acceptable Mn-54 E10483 1st 4/15/2013 3.92E-01 3.48E-01 1.13 Acceptable Fe-59 E10483 1st 4/15/2013 4.69E-01, 4.22E-01 1,. 1,1- Acceptable Zn-65 E10483 1st 4/15/2013 5.48E-01 5.03E-01 1.09 Acceptable Co-60 E10483 1st 4/15/2013 6.90E-01 6.68E-01 -1.03 Acceptable Sample/ Radionuclide -Sample Quarter Report HBPP. Reference- Ratio Evaluation Analysis Number 2013 Date Count'. Value...

Room. (pCi/L)

(pCi/L) __....

Tritium Water H-3 E10484 1st 4/15/2013 1.35E+04 .1.40E+04 0.96 Acceptable

- 20 -

TABLE A-4 (Continued)

HBPP PARTICIPATION - ECKERT & ZIEGLER INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2013 Date Count Value (pCi)

Room (pCi)

Gamma Filter Ce-141 E10537 2nd 8/19/2013 8.69E+01 7.49E+01 1.16 Acceptable Cr-51 E10537 2nd 8/19/2013 1.97E+02 2.07E+02 0.95 Acceptable Cs-134 E10537 2nd 8/19/2013 9.63E+01 1.04E+02 0.93 Acceptable Cs-137 E10537 2nd 8/19/2013 1.19E+02 1.25E+02 0.95 Acceptable Co-58 E10537 2nd 8/19/2013 8.47E+01 7.78E+01 1.09 Acceptable Mn-54 E10537 2nd 8/19/2013 1.59E+02 1.42E+02 1. 12 Acceptable Fe-59 E10537 2nd 8/19/2013 1.09E+02 9.91E+01 1.10 Acceptable Zn-65 E10537 2nd 8/19/2013 1.92E+02 1.80E+02 1.07. Acceptable Co-60 E.10537 .2nd 8/19/2013 1.47E+02 1.45E+02 1.01 Acceptable Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio. Evaluation Analysis Number 2013 Date Count Value (pCi)

Room (pC i) ... .

Alpha/Beta Alpha E10650 2nd 9/30/2013 4.54E+01 4.7.3E+01 0.96 Acceptable Filter Beta E10650 2nd 9/30/2013 1.57E+02 1.59E+02 0.99 Acceptable

-21 -

TABLE A-4 (Continued)

HBPP PARTICIPATION - ECKERT & ZIEGLER INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2013 Date Count Value Room (pCi/L)

(pCi/L)

Gamma Water Cr-51 E10653 3rd 10/7/2013 2.59E+02 2.51E+02 1.03 Acceptable Cs-134 E10653 3rd 10/7/2013 1.49E+02 1.56E+02 0.96 Acceptable Cs-137 E10653 3rd 10/7/2013 1.28E+02 1.18E+02 1.08 Acceptable Co-58 E10653 3rd 10/7/2013 9.46E+01 9.73E+01 0.97 Acceptable Mn-54 E10653 3rd 10/7/2013 1.37E+02 1.25E+02 1.09 Acceptable Fe-59 E10653 3rd 10/7/2013 1.09E+02 1.18E+02 0.93 Acceptable Zn-65 E10653 3rd 10/7/2013 2.58E+02 2.41 E+02 1.07 Acceptable Co-60 E10653 3rd 10/7/2013 1.84E+02 1.77E+02 1.04 Acceptable Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2013 Date Count Value Room (pCi/g)

_ _ _ _ _ __ (pC il/g) -.. _ _ .... .

Gamma Soil Cr-51 E10654 3rd 10/7/2013 4.91 E-01 4.83E-0i 1.02 Acceptable Cs-134 E10654 3rd 10/7/2013 2.66E-01 3.OOE-01 0.89 Acceptable Cs-137 E10654 3rd 10/7/2013 3.11 E-01 3.12E-01 1.00 Acceptable Co-58 E10654 3rd 10/7/2013 2.02E-01 1.88E-01 1.08 Acceptable Mn-54 E10654 3rd 10/7/2013 2.52E-01 2.42E-01'.. .1'.04 Acceptable Fe-59 E10654 3rd 10/7/2013 2.21 E-01 2.27E-01 0.97 Acceptable Zn-65 E10654 3rd 10/7/2013 5.06E-01 4.64E-01 1.09 Acceptable Co-60 E10654 3'rd 10/7/2013 3.47E-01 3.41 E-01 1.02 Acceptable Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio. Evaluation Analysis Number 2013 Date Count Value Room, (pCi/L)

_________(pCilL) _ _.,

Tritium Water H-3 E10652 3rd 10/7/2013 9.84E+03 9.96E+03 0.99 Acceptabe TABLE A-4 (Continued)

HBPP PARTICIPATION - ECKERT & ZIEGLER INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2013 Date Count Value (pCi)

Room (pCi) ....

Gamma Filter Ce-141 E10749 4th 1/7/2014 9.49E+01 . 8.76E+01 1.08 Acceptable Cr-51 E10749 4th 1/7/2014 2.40E+02 2.37E+02 1.01 Acceptable Cs-134 E10749 4th 1/7/2014 1.01 E+02 1.13E+02 0.89 Acceptable Cs-137 E10749 4th 1/7/2014 1.09E+02 1.01E+02 1.08 Acceptable Co-58 E10749 4th 1/7/2014 9.38E+01 8.95E+01 1.05 Acceptable Mn-54 E10749 4th 1/7/2014 1.45E+02 .1.34E+02 1.08 Acceptable Fe-59 E10749 4th 1/7/2014 1.01E+02 8.80E+01 .1.15 Acceptable Zn-65 E10749 4th 1/7/2014 6.66E+02 5.92E+02 1.12 Acceptable Co-60 E10749 4th 1/7/2014 1.23E+02 1.17E+02 1.05 Acceptable Sample/ Radionuclide Sample Quarter Report HBPP. Reference Ratio Evaluation Analysis Number 2013. Date Count. Valueý(pCi)

Room

._______ _________ (pCi) _________,

Alpha/Beta Alpha E10750 4th 1/7/2014 6.86E+01 6.62E+0.1 1.04 Acceptable Filter Beta E10750 4th 1/7/2014 1.29E+02 1.36E+02 , 0.95 Acceptable TABLE C-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL REPORT

SUMMARY

Name of Facility Humboldt Bay Power Plant Unit 3 Docket No. 50-133; License No. DPR-7 Location of Facility Humboldt County, California Reporting Period January 1 - December 31, 2013 uCo nty, State)

Medium or Type and Lower Limit All Indicator Locations Location with Control Number Pathway Total of Detection Highest Annual Mean Locations of Non-Sampled Number of (LLD) routine

[Unit of Analyses Reported Measurement] Performed Mean,(Fraction), & [Range]f Name Mean, Mean, Measure-(Fraction) (Fraction) ments

& [Range] b & [Range]b (53) samples per

Gross Beta East Fence (AMI) Annex Gross Alpha Humboldt Hill N/A AIRBORNE station 1.OOE-02 Gross Alpha (pCi/m3) mean 2.65E-03, (8/53), [2.32E-03 to 3.50E-03] (pCi/m3) mean (Station 3)

" Gross Beta, pCi/m3 Gross Beta (pCi/m3) mean 1.18E-02, (45/53), [3.39E-03 to 2.67E-02] 3.01E-03, (7/53), Gross Alpha Particulates & Gross Alpha Building 12 (AM2) [2.34E-03 to (pCi/m3) mean

" Gamma 9 Gamma Gross Alpha (pCi/m3) mean 2.68E-03, (9/53), [2.30E-03 to 3.57E-03] 3.94E-03] 2.90E-03,

[pCi/m3] Isotopic Isotopic Gross Beta (pCi/m3) mean 1.27E-02, (45/53), [4.03E-03 to 3.81 E-02] (7/53),

analysis on analysis on Annex (AM3) OWS Gross Beta [2.36E-03 to quarterly quarterly Gross Alpha (pCi/m3) mean 3.01 E-03, (7/53), [2.34E-03 to 3.94E-03] (pCi/m3) mean 3.66E-03]

composite (by composite Gross Beta (pCi/m3) mean 1.30E-02, (43/53), [3.44E-03 to 3.1OE-02] . 1.49E-02,..

station) (by station) Relay Building (AM4) * (50/53)" Gross Beta; Gross Alpha (pCi/m3) mean 2.87E-03, (7/53), [2.30E-03 to 3.55E-03] " (3.48E-03 to (pCi/m3) mean (5) Onsite cs-137 Gross Beta (pCi/m3) mean 1.08E-02, (49/53), [3.66E-03 to 2:90E-02] 4.15E-02] 1.OOE-02, Locations Oil Water Separator (OWS - AM5) (39/53),

(1) Offsite 6.00E-02 Gross Alpha (pCi/m3) mean 2.58E-03, (12/53), [2.32E-03 to 2.97E-03] . Cs-137!<MDA [3.54E-03 to Locations pCi/m3 Gross Beta (pCi/m3) mean 1.49E-02, (50/53), (3.48E-03 to 4.15E-02] ..2.25E-021 (80) Fence line 5 mRem Fence LineTLDs (T1 to T16 and T18 to T21) Stations T19 (mR/qtr) Stations 1, 2, 0 DIRECT TLD readings 12.8 + 0.1, (80/80), [10.8-to 15.4] T-19 & mean 14, 25 and T17 RADIATION ( T20, 14.2 +/- 0.4, (mR/qtr) mean

[mR/quarter] (20) off-site TLD Readings Figure B-1 (1/4), [13.4-14.5]

T20 (mR/qtr) .

12.1 +/- 0.2, (20/20),

mean, [10.4-14.1]

14.2 +/- 0.3, (1/4), [12.6-14.9]

Gamma isotopic Co-60:15 pCi/L Co-60 (pCi/L) mean < MDA, (0/52), (NA] N/A N/A Not Required 0 WATERBORNE (52) Cs-137:18 pCilL Cs-137 (pCi/L) mean < MDA, (0/52), [N/A]

[pCi/L] .

Surface Tritium (52) ODCM: 3.OE+03 H-3 (pCi/L) mean < MDA, (0/52), [N/A] N/A N/A Not Required Water pCi/L Discharge ,

canal effluent -_....

TABLE C-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL REPORT

SUMMARY

Type All Indicator Location with Highest Annual Mean Control,.

Medium or and Total Lower Locations Locations Number of Pathway Sampled Number of Limit of Mean, Name, Mean, Mean, Non-routine

[Unit of Analyses Detectiona (Fraction) Distance and (Fraction) (Fraction) Reported Measurement] Performed (LLD) & [Range] b Direction [Range & [Range] b Measurements Gamma isotopic Co-60:15 pCi/L Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 0 WATERBORNE (81) Cs-137:18 pCi/L (continued)

Groundwater <MDA <MDA N/A N/A ,<MDA <MDA N/A: N/A (Monitoring wells) (0/81) (0/81) (0/81) (0/81)

[pCi/L] [N/A] [N/A] .[N/A] [N/A]

Tritium(81) ODCM: 2.0E+03 <MDA, (0/81), [N/A] N/A <MDA, (0/81), [N/A] N/A - .. 0 ,

pCi/L Plant Policy: 400 Drinking Water Not Required N/A N/A . N/A N/A . . Not Required . N/A .

SdmnNoRequired N/ /A N/A N/A Not Required N/A' Algae Not Required N/A N/A N/A N/A Not Required N/A INGESTION Strontium 90, and Sr-90: Sr-90 Cs-137 N/A N/A Not Required N/A Milk Gamma lsotopic(a) 2.00E+00 pCi/L <MDA <MDA analysis Cs-137: 1.80E+01 [N/A] [N/A] '

[pCi/L] (2) Samples pCi/L Fish and Not Required N/A N/-/AA N/ A NotfRequired N/A invertebrates "_:___,___.

TERRESTRIAL Soil Not Required N/A N/A N/A N/A Not Required N/A aThe LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

LLD is defined as the a orio (before the fact) lower limit of detection (as pCi per unit mass or volume) representing the capability of a measurement system and not as the a posteriori (after the fact) limit for a particular measurement. (Current literature defines the LLD as the detection capability for the instrumentation only, and the MDA, minimum detectable concentration, as the.detection capability for a-given instrument, procedure and type of sample.) The actual MDA for these analyses was at or below the LLD.

bThe mean and the range are based on detectable measurements -only. The fraction of detectable measurements at specified- locations is indicated-in parentheses; e.g., (10/12) means that 10 out of 12 samples contained detectable activity. The range of detected results is indicated in brackets; e.g.,

[23-34].

Not Required: Not required by the HBPP Unit 3 Technical Specifications or the SAFSTOR Offsite Dose Calculation Manual. Baseline environmental conditions for this parameter were established in the Environmental Report as referenced by the SAFSTOR Decommissioning Planý(now identified as the Post Shutdown Decommissioning Activities Report and Defueled Safety Analysis Report).

N/A - Not applicable

- 25 -

TABLE C-2.

ONSITE ENVIRONMENTAL TLD, STATIONS iStation TLD Exposure Measurements (mR)

Number First Quarter Second Quarter Third Quarter Fourth Quarter TI 13.7 +/- 0.4 13.9 +/- 0.7 13.2 +/- 1.0 15.31+/- 0.8 T2 12.3 +/- 0.4 12.4 +/- 0.7 12.5 +/- 0.8 13.7 +/- 0.7 T3 12.8 +/- 0.5 12.0 +/- 0.5 12.1 +/- 0.6 12.2 +/- 0.6 T4 13.4 +/- 0.5 11.9 +/- 0.8 12.7 +/- 1.0 12.7 +/- 0.8 T5 12.6+/-0.9 11.7:+/-0.9 .12.00+/- 0.5 12.1 +/-0.7 T6 11.8 +/- 0.7 11.6:+/- 0.7 '-11.7 +/- 0.8 11.9 +/- 0.9 T7 112.7 +/- 0.6 11.6 +/- 0.9 j.: 11.9+/-0.4 11.6+/- 0.6 T8 124 +/- 0.4 10.8.+/--0.6. -11 .0 +/-+0.5 11.6 +/- 0.5 T9 13.0 +/- 0.6. 12.0 +/- 0.4 12.9 +/- 0.7 12.6 +/- 0.7 T10 11.7+/-0.7 11.0+/-0.6 11.1 +/-0.9 . 11.8+/- 0.7 T11 13.4 +/- 0.9 12.4 +/- 1.1 12.6 +/- 0.8 12.7 +/- 0.8 T12 1.3.8 +/- 0.8 12.7 +/- 0.4 1,2.6 +/- 0.6 12.9 +/- 0.8 T13 14.2 +/- 0.5 12.3 +/- 0.6 13.0 +/- 0.6 . 13.6 +/- 0.8 T14 13.7+/-0.9 11.6+/-0.8 12.1 +/-0,5 13.2+/-017 T15 14.1 +/- 0.9 13.3 +/- 0.8 12.3 +/- 0.7 13.0 +/- 0.6 T16 12.8 +/- 0.6- 11.7 +/- 0.7 11.4 +/- 0.4 11.8 +/- 0.7 T18 13.3 +/- 0.5 13.3 +/- 0.4 13.4 +/- 1.3 14.3 +/- 0.4 T19 15.1 +/- 0.6 13.4 +/- 0.8 14.5 +/- 0.7 13.8,+/- 0.8 T20 15.4 + 0.4 12.6 +/- 0.6 13.7 +/- 0.1 14.9 +/- 1.0 T21 14.6 +/-0.2 14.1 +/- 1.1 12.9 +/- 0.3 14.5 +/- 1.0 I Parameter Average i First Quarter 13.3 +/- 0.1 Calculated Parameters (mR)

Second Quarter 12.3 +/- 0.2 Third Quarter 12.5 +/- 0.2 Fourth Quarter 13.0 +/- 0.2 1 ý

-I Maximum j 15.4+/-0.4 14.1 +/- 1.1 14.5 +/- 0.7 15.3 +/- 0.8 Table C-2 Notes:

1. These exposures are reported for a standardized period of 90 days.

TABLE C-3 OFFSITE (Control) ENVIRONMENTAL TLD STATIONS

.'Station. ..TLD Exposure Measurements (mR)

Number First Quarter Second Quarter. Third Quarter Fourth Quarter 1 12.9 +/- 0.6, 11.4ý 0.9 12.9 +/- 1.0 12.2 + 0.7 2 14.1 +/-0.8 13:2+/- 0.7 13.8 +/- 0.7 14.1+/-1.1 14 113 +/- 0.7 10.4+/--0.8 11.6+/-0.7 .11.8+/-0.9 25: 11.9+/-0.7 111+/-

10.9 11.0+/-0.9 12.4+/-0.6 T17 .12.1 +/-0.7 10.9+/-0.4 11.3+/-0.6 11.2+/-0.6

___ Calculated Parameters (mR).

Parameter First Quarter Second Quarter Third Quarter Fourth Quarter Average 12.5 +/- 0.3 11.4 +/- 0.3 12.1 +/- 0.4 12.3+/- 0.4 Maximum 14.1 +/- 0.8 13.2 +/- 0.7 13.8 +/- 0.7 14.1 +/- 1.1 Table C-3 Notes:

1. These exposures are reported for a standardized period of 90 days.

TABLEý C-4 DISCHARGE CANAL SAMPLE RESULTS Gamma Activity (pCi/L) Tritium Activity Sample Date Cs-1 37. Co-60. (pCi/L),..

0.1/02/20.13 <MDA. " <MDA <MDA 01/09/2013 <MDA .<MDA <MDA..

01/16/2013 .<MDA. .. <MDA <M'DA 01/23/2013 <MDA .<MDA <MDA 01/30/2013 <MDA -. .<MDA <MDA 02/06/2013 <MDA <MDA <MDA 02/13/2013 <MDA <MDA <MDA 02/20/2013 <MDA <MDA <MDA 02/27/2013 <MDA <MDA <MDA 03/06/2013 <MDA <MDA <MDA 03113/2013 <MDA <MDA <MDA 03/20/2013 <MDA <MDA <MDA 03/27/2013 <MDA <MDA <MDA 04/03/2013 <MDA <MDA <MDA 04/10/2013 <MDA <MDA <MDA 04/17/2013 <MDA <MDA <MDA 04/24/2013 <MDA <MDA <MDA 05/01/2013 <MDA <MDA <MDA 05/08/2013 <MDA <MDA <MDA 05/15/2013 <MDA <MDA <MDA 05/22/2013 <MDA <MDA <MDA 05/29/2013 <MDA <MDA <MDA 06/05/2013 <MDA <MDA <MDA 06/12/2013 <MDA <MDA <MDA 06/19/2013 <MDA <MDA <MDA 06/26/2013 <MDA <MDA <MDA 07/03/2013 <MDA <MDA <MDA 07/10/2013 <MDA <MDA <MDA 07/17/2013 <MDA <MDA <MDA 07/24/2013 <MDA <MDA <MDA 07/31/2013 <MDA <MDA <MDA 08/07/2013 <MDA <MDA <MDA 08/14/2013 <MDA <MDA <MDA 08/21/2013 <MDA <MDA <MDA 08/28/2013 <MDA <MDA <MDA 09/04/2013 <MDA <MDA <MDA 09/11/2013 <MDA <MDA <MDA 09/18/2013 <MDA <MDA <MDA 09/25/2013 <MDA <MDA <MDA TABLE C-4 (Continued)

DISCHARGE CANAL SAMPLE RESULTS Gamma Activity (pCi/L) Tritium Activity Sample Date Cs-1 37 Co-60 (pCi/L) 10/02/2013 <MDA <MDA <MDA

,10/09f2013 <MDA <MDA <MDA 10116/2013 <MDA <MDA <MDA 10/23/2013 <MDA <MDA <MDA 10/30/2013. . <MDA <MDA <MDA 11/06/2013 <MDA - <MDA <MDA 11/13/2013 <MDA.. - <MDA <MDA

11/20/2013 <-MDA. <MDA <MDA 11/27/2013 .<MDA- <MDA <MDA 12/04/2013 . <MDA <MDA <MDA 12/11/2013 <MDA <MDA <MDA 12/18/2013 <MDA .. <MDA <MDA 12/23/2013 <MDA <MDA <MDA Calculated Gamma Activity (pCi/L) Tritium Activity Parameters Cs-1 37 Co-60 (pCi/L)

Average Note 4 Note 4 Note 4 Maximum Note. 4 Note 4 Note 4 Table C-4 Notes:

1. Gamma measurements:are performed on the original sample, with results corrected to the time of .sampling. Naturally occurring isotopes are not reported.

The maximum lower limits of detection (LLDs) for Co-60 and Cs-1 37 are 15 and 18 pCi/L, respectively. The MDA for'these analyses was. at or below the LLD and are reported as "<MDA".

2. For purposes of this report, LLD is defined as the a priori (before the fact) lower limit of detection, which represents the capability of the measurement system.

MDA is defined as the a posteriori (after the fact) limit of detection capability considering a given instrument, procedure and type of sample.

3. Tritium analysis is performed on a measured aliquot of distilled sample. The reported values are net measurements above instrument background. The normal MDA for the analyses for tritium was less than 600 pCi/L. Results that are at or below the normal MDA are reported as "<MDA".

4. Results identified as "<MDA" are not included in the calculation of average and maximum values.

TABLE C-5 ..

GROUNDWATER MONITORING WELL RESULTS Monitor Alpha Beta Gamma Tritium Well Sample Activity Activity Activity Activity Number Date (pCi/L), (pCi/L) (pCi/L) (pCi/L)

Cs-1 37 Co-60

MW-l* 2/14/2013 <0.72(MDA) <1.29(MDA) .<5.50(MDA) <5.08(MDA) <248(MDA)

MW-2* 2/14/2013 <1.46(MDA). <1.45(MDA) .. 3.87(MDA) <5.68(MDA) <241(MDA)

MW-4* 2/14/2013 <2.35(MDA) 11.0 2.78 <-535(MDA) <5.61(MDA). <241(MDA)

MW-6* .2/14/2013 <2.06(MDA) 2.69 1.20 --<5.16(MDA) <5.59(MDA) <242(MDA)

MW-11* 2/14/2013 <5.18(MDA) <8.90(MDA) -.,;-<5.12(MDA) <3.73(MDA) <247(MDA)

RCW-CS-I* 2/14/2013 <43.2(MDA) <56.6(MDA) -- ':.<4.89(MDA) <3.51(MDA) - <235(MDA)

RCW-CS-2* 2/14/2013 <13.8(MDA) <21.9(MDA) -' <3.77(MDA) <4.65(MDA) <252(MDA)

RCW-CS-3* 2/14/2013 <1.58(MDA) <1.82(MDA) - <4.51(MDA) <3.82(MDA) <245(MDA)

RCW-CS-4* .2/14/2013 <1.41(MDA) 3.00+/-1. 35. <3.25(MDA) <4.53(MDA). <238(MDA)

RCW-CS-5* 2/14/2013 <2.15(MDA) 2.14 +/- 0.96 4:5.52(MDA) <4.65(MDA) <245(MDA)

RCW-CS-6 2/14/2013 <29.6(MDA) <47.3(MDA) .<6.75(MDA) <6.47(MDA)' <241(MDA)

RCW-CS-7 2/14/2013 <30.9(MDA) <27.4(MDA) <5.58(MDA) <4.50(MDA) <240(MDA)

RCW-SFP-I* 2/14/2013- <1.49(MDA) <1.80(MDA) <4.66(MDA) <6.09(MDA) <243(MDA)

RCW-SFP-2* 2/14/2013 <4.73(MDA) < 6.69(MDA) <4.16(MDA) -<5.50(MDA)- <239(MDA)

RCW-SFP-3 2/14/2013 <2.18(MDA) <4.83(MDA) <4.32(MDA) <4.35(MDA) <240(MDA)

RCW-SW-1 . 2/14/2013 2.56 +/- 1.69 , <1.68(MDA) <4.94(MDA) <4.99(MDA) <244(MDA)

RCW-SW-2 2/14/2013 <3.41(MDA) 4.66 +/- 1.25 <5.01(MDA) <5.23(MDA) <244(MDA)

RCW-SW-3 2/14/2013 <2.16(MDA) 2.08 +/- 0.95 <5.49(MDA) <4.07(MDA) <242(MDA)

RCW-SW-4 .2/14/2013 <1.88(MDA) <1.34(MDA) <4.97(MDA) <4.53(MDA) <244(MDA)

MW-1* 5/10/2013 <1.81 (MDA) <2.79(MDA) <3.80(MDA) <4.33(MDA) <294(MDA)

MW-2* 5/10/2013 <1.76(MDA) 3.32 +/- 1.61 <3.45(MDA) <3.97(MDA) <295(MDA)

MW-4* 5/10/2013 <4.96(MDA) 13.7 +/- 3.06 <3.42(MDA) <4.19(MDA) <285(MDA)

MW-6* 5/10/2013 <1.73(MDA) .. 6.38 +/-1.40.. <3.88(MDA) <4.13(MDA) <302(MDA)

MWA1I* 5/10/2013 <11.7(MDA) <8.64(MDA) <3.87(MDA) <3.77(MDA) <286(MDA)

RCW-CS-I* 5/10/2013 <13.6(MDA) <19.8(MDA) <4.84(MDA) <3.41(MDA) <295(MDA)

RCW-CS-2* 5/10/2013 <30.2(MDA) <23.4(MDA) <4.29(MDA) <5.30(MDA) <297(MDA)

RCW-CS-3* 5/10/2013 <3.10(MDA) <3.06(MDA) <4.36(MDA) <6.12(MDA) <299(MDA)

RCW-CS-4* 5/10/2013 <2.31(MDA) <2.70(MDA) <4.28(MDA) <4.18(MDA) <289(MDA)

RCW-CS-5* 5/10/2013 <3.27(MDA) <2.13(MDA). <5.95(MDA) <6.45(MDA) <289(MDA)

RCW-CS-6 5/10/2013 <43.2(MDA) <42.9(MDA) <4.86(MDA) <3.46(MDA) <297(MDA)

RCW-CS-7 5/10/2013 <99.6(MDA) <90.6(MDA) <5.58(MDA) <4.58(MDA) <300(MDA)

RCW-SFP-I* 5/10/2013 <1.90(MDA) 2.57 +/- 1.49 <3.91(MDA) <4.67(MDA) <286(MDA)

RCW-SFP-2* 5/10/2013 <8.62(MDA) 16.2+/- 4.30 <4.62(MDA) <3.73(MDA) <296(MDA)

RCW-SFP-3 5/10/2013 <3.97(MDA) <9.70(MDA) <5.61(MDA) <5.59(MDA) <300(MDA)

RCW-SW-1 5/10/2013 5.06 +/- 2.35 <3.05(MDA) <5.54(MDA) <5.23(MDA) <299(MDA)

RCW-SW-2 5/10/2013 <4.97(MDA) 7.58 +/- 2.25 <4.29(MDA) <4.57(MDA) <295(MDA)

RCW-SW-3 5/10/2013 <2.20(MDA) <3.70(MDA) <3.51(MDA) <4.17(MDA) <298(MDA)

RCW-SW-4 5/10/2013 <3.44(MDA) <2.36(MDA) <3.38(MDA) <4.23(MDA) <295(MDA)

Indicates twelve (12) groundwater monitoring wells specified in ODCM Revision 22.

TABLE C-5 (Continued)

GROUNDWATER. MONITORING WELL RESULTS Monitor Alpha Beta Gamma Tritium Well Sample, Activity Activity Activity Activity Number Date (pCiIL). (pCi/L) (pCi/L) (pCi/L)

Cs-1 37 Co-60 MW-1* . 8/21/2013 Note 5 Note5 Note 5 Note 5 Note 5 MW-2*. 8/21/2013 <2.25(MDA) 3.34 +/- 1.25 <3.98(MDA) <4.92(MDA) <311(MDA)

MW-4*. 8/21/2013. <3.98(MDA) .4.10 +/- 1.52- <5.77(MDA) 4.92(MDA) <313(MDA)

.MW-6* 8/21/201.3 <3.32(MDA) *<2.35(MDA) <5.26(MDA) <4.95(MDA) <314(MDA)

MW-11* 8/21/2013 <8.45(MDA)' <5.99(MDA) <6.12(MDA) <3.58(MDA) <312(MDA)

RCW-CS-I* 8/21/2013 <60.9(MDA) <42.9(MDA) <4.42(MDA) <4.04(MDA) <256(MDA)

RCW-CS-2* 8/21/2013 <26.2(MDA) <20 1(MDA) <4.16(MDA) <5.03(MDA) <255(MDA)

RCW-CS-3* 8/21/2013 <1.85(MDA) <1.32(MDA) <4.09(MDA) <4.85(MDA) <252(MDA)

RCWCS-4* 8/21/2013 Note 5 .-Note 5 Note 5 Note 5 Note 5 RCW-CS-5* 8/21/2013 <2.22(MDA) <1.79(MDA) <4.48(MDA) <4.20(MDA) <260(MDA)

RCW-CS-6 8/21/2013 <55.7(MDA) <46.5(MDA) <6.25(MDA) <6.25(MDA) <255(MDA)

RCW-CS-7 8/21/2013 <107(MDA) <67.0(MDA) <3.57(MDA) <2.90(MDA) <243(MDA)

RCW-CS-8 8/21/2013 <124(MDA) <97.3(MDA) <4.80(MDA) <4.56(MDA) <279(MDA)

RCW-SFP-I* 8/21/2013 <3.38(MDA) <2.40(MDA) <4.58(MDA) <4.03(MDA) <316(MDA)

RCW-SFP-2* 8/21/2013 <3.28(MDA) 3.08 +/- 1.68 <5.39(MDA) <5.00(MDA) <313(MDA)

RCW-SFP-3 8/21/2013 <4.51(MDA) <3.47(MDA) <5:71(MDA) <5.46(MDA) <255(MDA)

RCW-SFP-4 8/21/2013 <5.21(MDA) <3.59(MDA) <4.75(MDA) <3.94(MDA). <257(MDA)

RCW-SFP-5 8/21/2013 <2.63(MDA) <3.09(MDA) <4.33(MDA) <4.69(MDA) <254(MDA)

RCW-SW-1 8/21/2013 <3.01(MDA) <3.04(MDA) <4.56(MDA) <5.28(MDA. <312(MDA)

RCW-SW-2 8/21/2013 <2.67(MDA) <1.51(MDA) <3.80(MDA) <3.44(MDA) <313(MDA)

RCW-SW-3 8/21/2013 <4.50(MDA) <2.83(MDA) <4.50(MDA) <5.28(MDA) <317(MDA)

RCW-SW-4 8/21/2013 <2.82(MDA) <1.82(MDA) <4..65(MDA) <4.60(MDA) <316(MDA)

MW-I* 11/8/2013 Note 5 Note 5 .Note 5 Note 5 Note 5 MW-2* 11/8/2013 <3.5.1(MDA) <1.61 (MDA) <4.46(MDA) <4.64(M DA) <257(MDA)

MW-4* 11/8/2013 <7.56(MDA) <5.56(MDA) <4.22(MDA) <3.16(MDA) <256(MDA)

MW-6* 11/8/2013 <3.40(MDA) 1.81 +/- 1.18 <5.32(MDA)- <5.34(MDA) <259(MDA)

MW-11* 11/8/2013 <6.15(MDA) <3.27(MDA) <3.72(MDA) <4.00(MDA) <256(MDA)

RCW-CS-I* 11/8/2013 <102(MDA) <67.5(MDA) <5..85(MDA) <4.13(MDA) <280(MDA)

RCW-CS-2* 11/8/2013 <23.3(MDA) <17.2(MDA) "<3.5.1(MDA) <5.84(MDA) <280(MDA)

RCW-CS-3* .11/8/2013 <3.00(MDA) <2.42(MDA) <4.49(MDA) <5.22(MDA) <280(MDA)

RCW-CS-4* 11/8/2013 <2.26(MDA) <1.76(M DA) <4.69(MDA) <4.27(MDA) <280(MDA)

RCW-CS-5* 11/8/2013 <3.17(MDA) <2.57(MDA) <4.86(MDA) <4.20(MDA) <280(MDA)

RCW-CS-6 11/8/2013 <57.0(MDA) <39.9(MDA) <6.05(MDA) <6.75(MDA) <280(MDA)

RCW-CS-7 11/8/2013 <140(MDA) <104(MDA) <4.97(MDA) <4.87(MDA) <280(MDA)

RCW-CS-8 .11/8/2013 <171(MDA) <92.8(MDA) <5:28(M DA) <4.49(MDA) <280(MDA)

RCW-CS-9 11/8/2013 <37.2(MDA) <20.5(MDA) <4.32(MDA) <3.54(MDA) <282(MDA)

RCW-SFP-l* 11/8/2013 <3.47(MDA) <1.64(MDA) <5.42(MDA) <4.22(MDA) <255(MDA)

RCW-SFP-2* 11/8/2013 <2.04(MDA) <2.07(MDA) <3.79(MDA) <5.15(MDA) <259(MDA)

RCW-SFP-3 11/8/2013 <6.51(MDA) <3.55(MDA) <5.93(MDA) <5.48(MDA) <260(MDA)

RCW-SFP-4 11/8/2013 <5.99(MDA) <4.05(MDA) <4.22(MDA) <3.95(MDA) <280(MDA)

RCW-SFP-5 11/8/2013 <8.01(MDA) <3.03(MDA) <3.50(MDA) <4.21 (MDA) <280(MDA)

RCW-SW-1 11/8/2013 <5.43(MDA) <3;36(MDA) <4.45(MDA) <3.68(MDA) .<257(MDA)

RCW-SW-2 11/8/2013 <3.77(MDA) 8.91 +/- 1.57 <4.40(MDA) <3.36(MDA) <256(MDA)

RCW-SW-3 11/8/2013 <6.68(MDA) <4.65(MDA) <5.10(MDA) <5.20(MDA) <258(MDA)

RCW-SW-4 11/8/2013 <3.39(MDA) <2.14(MDA) <5.19(MDA) <4.71(MDA) <258(MDA)

Indicates (12) groundwater monitoring wells specified in ODCM Revision 22.

TABLE C-5 (Continued)

GROUNDWATER MONITORING WELL RESULTS Calculated Alpha Beta Gamma Tritium Parameters Activity Activity. Activity. Activity (By Monitor Well (pCi/L) (pCi/L).). (pCi/L) (pCi/L)

Number) .. Cs-1 37 Co-60 Average: MW-I Note 4 Note 4. Note 4 Note 4 'Note 4 Average: MW-2 Note 4 3.33 +/-_1.02" Note.4 . Note 4 Note 4 Average: MW-4 Note 4 9.60 +/- 1.47, Note 4 Note 4 Note 4 Average: MW-6 ,. Note 4 3.63 +/- 0.73 Note 4 . Note.4- Note 4 Average: MW-11 Note 4 Note 4 - Note 4 Note 4 Note 4 Average: RCW-CS-1 Note 4 Note 4 Note 4 Note 4 Note 4 Average: RCW-CS-2 Note 4 ..Note 4 "Note 4 Note 4 Note 4 Average: RCW-CS-3. Note 4 Note 4: Note.4 Note 4 Note 4 Average: RCW-CS-4 Note 4 3.00-+/- 1.35 Note 4 *Note.4 Note 4 Average: RCW-CS-5 Note 4 2.14,, 0.96 ..Note 4 Note 4 Note 4 Average: RCW-CS-6 Note 4 Note:4 Note 4" Note 4 Note 4 Average: RCW-CS-7 Note 4 Note 4 Note.4 Note 4 Note 4 Average: RCW-CS-8 Note 4 Note 4 -

Note 4 Note 4 Note 4 Average: RCW-CS-9 Note 4-. Note 4 Note 4 Note 4 Note 4 Average: RCW-SFP-I Note 4 2.57 +/- 1.49 Note 4 Note 4 Note 4 Average: RCW-SFP-2 Note 4 9.64 +/-.2.31

Note 4 Note 4 Note'4 Average: RCW-SFP-3 Note 4 Note.4 Note 4 Note 4 Note 4 Average: RCW-SFP-4 Note 4 Note 4 Note 4 Note 4 Note 4 Average: RCW-SFP-5 Note 4 Note 4 Note 4 Note 4 Note 4 Average: RCW-SW-I 3.81 +/- 1.45 Note 4 Note 4 Note 4 Note 4 Average: RCW-SW-2 Note 4 - 7.05 +/- 1.00 Note 4 Note 4 Note 4 Average: RCW-SW-3 Note 4 2.08 +/- 0.95 Note 4. Note 4 Note 4 Average: RCW-SW-4 Note 4 - Note.4 Note 4. Note 4 Note 4 Maximum: MW-1 Note 4 Note-4 Note 4 Note'4 Note 4.

Maximum: MW Note 4 3.34 +"1.25 Note 4 Note 4 Note 4 Maximum: MW-4 Note 4 13.7 +/- 3.06 Note 4 Note 4 Note 4 Maximum: MW-6 Note 4 6.38 + 1.40 Note 4 Note 4 Note 4 Maximum: MW-11 Note 4 - Note 4 Note 4 Note 4 Note 4 Maximum: RCW-CS-1 Note 4 Note 4 Note 4 Note 4 Note .4 Maximum: RCW-CS-2 Note 4- Note 4 Note 4 Note 4 Note 4 Maximum: RCW-CS-3 Note 4 Note 4 Note 4 Note 4 Note 4 Maximum: RCW-CS-4 Note 4 3.00 +/- 1.35 Note 4 Note 4 Note 4 Maximum: RCW-CS-5 Note 4 2.14 +/- 0.96 Note 4 Note 4 Note 4 Maximum: RCW-CS-6 Note 4 Note 4 Note 4 Note 4 Note 4 Maximum: RCW-CS-7 Note 4 Note 4 Note 4 Note 4 Note 4 Maximum: RCW-CS-8 Note 4 Note 4 Note 4 Note 4 Note 4 Maximum: RCW-CS-9 Note 4 Note 4 Note 4 Note 4 Note 4 Maximum: RCW-SFP-1 Note 4 2.57 +/- 1.49 Note 4 Note 4 Note 4 Maximum: RCW-SFP-2 Note 4 16.2 +/- 4.30 . Note 4 Note. 4 Note 4 Maximum: RCW-SFP-3 Note 4 Note 4 Note 4 Note 4 Note 4 Maximum: RCW-SFP-4 Note 4 Note 4 Note 4 Note 4 Note 4 Maximum: RCW-SFP-5 Note 4 Note 4 Note 4 Note 4- Note 4 Maximum: RCW-SW-1 5.06 _+2.35 Note 4 Note 4 Note 4 Note 4 Maximum: RCW-SW-2 Note 4 8.91 +/- 1.57 Note 4 Note 4. Note 4 Maximum: RCW-SW-3 Note 4 2.08 +/- 0.95 Note 4 Note 4 Note 4 Maximum: RCW-SW-4 Note 4-- Note 4 Note 4 Note 4 Note 4

Indicates (12) groundwater monitoring wells specified in ODCM Revision 22.

32-

Table C-5 Notes:

1. Reported values are net -measurements (above instrument background). The normal minimum detectable activities (MDAs) for the analyses for gross. alpha, gro.s beta and tritium are approximately 4, 4 and 300 pCi/L, respectively.

Results that are at or below the normal MDA are reported as "<MDA".

2. Gamma activity measurements are performed on the original sample, with results corrected .to the time.of sampling. Naturally occurring isotopes are not reported.

The maximumlower limits of detection (LLDs) for Co-60 and Cs-1 37 are 15 and 18 pCi/L,-respectively. The actual MDAs for these analyses were at or below the LLD.

3. For purposes of this report, LLD is defined as the a Driori (before the fact) lower limit of. detection, which represents the capability of the measurement system.

MDA is defined as the a posteriori (after the fact) limit of detection capability considering -a given instrument, procedure and type of sample.

4. Results identified as "<" are not included in the calculation of average and maximum values.

5. Wells were inaccessible t6 sample due to decommissioning debris. These problems were documented in corrective action SAPNs 130301.5 and 1305723.

-.33 -

TABLE C-6 CAISSON SUMP MONITORING RESULTS Sample Cs-1 37 Activity Co-60.Activity Tritium Activity Date (pCi/L) (pyi/L) (pCiiL) 1/04/2013 <MDA <MDA . <620 (MDA):

2/07/2013 <MDA <MDA 1010 380 3/07/2013 <MDA . <MDA 800 + 370 4/04/2013 <MDA <MDA. 710.+/- 370 5/02/2013 <MDA .<MDA .800 +/- 360 6/06/2013 <MDA <MDA: .. <600 (MDA) 7/03/2013 <MDA <MDA 800 + 370 8/08/2013 <MDA <MDA 1060 370 9/19/2013 <MDA'. <MDA. 740+/-.370 10/10/2013 13.90 +/- 5.36.*-,i; <MDA 970 +/- 370 1110512013 <MDA <MDA: 920 +/- 380:

12/18/2013 <MDA <MDA 1110 390 Table C-6 Notes:

1. Gamma measurements are performed on the original sample, with results corrected to the time of sampling. Naturally occurring isotopes are.not reported.

The maximum lower limits of detection (LLDs) for Co-60 and Cs-1 37 are 15 and 18 pCi/L, respectively. The MDA for these analyses was at or below the LLD and are reported as "<MDA".

2. For purposes of this report, LLD is defined as the a priori (before the fact) lower limit of detection, which represents the capability of the measurement system.

MDA is defined as the a posteriori (after the fact) limit of detection capability considering a given instrument, procedure and type of sample.

3. Tritium analysis is performed on a measured aliquot of distilled sample. The reported values are net measurements above instrument background. The normal MDA for the analyses for tritium was less than 600 pCi/L. Results that are at or below the normal MDA are reported as "<MDA".

- 34 -

TABLE C-7 FRENCH DRAIN MONITORING RESULTS Sample Cs-1 37 Activity Co-60 Activity Tritium Activity Date (pCi/L) (pCi/L) (pCi/L) 1/04/2013 229 +/-23 <MDA <620 (MDA) 2/07/2013 237 +/- 24". - <MDA 1150 380 3/07/2013 255 +/- 26, <MDA 780 370 4/04/2013 252 +/- 26 , <MDA.. 1090 380 5/02/2013 .264 +/-25' <MDA" 1630 380 610612013 264+/-ý-26 <MDA 1160 380 7/05/2013 275 +/-26 <MDA 920 370 8/08/2013 270 +/-271 <MDA 1060 +/- 370 9/13/2013 310 +/-.29.,-'- <MDA 1190 380 10/10/2013 301 +/--28-*.- <MDA 690 +/-370 11/05/2013 232 +/- 24 <MDA 700 380 12/17/2013 204+/-21 <MDA 1160+/-390 Table C-7 Notes:

1. Gamma measurements are performed on the original sample, with results corrected to the time of sampling. Naturally occurring isotopes are not reported.

The maximum lower limits of detection (LLDs) for Co-60 and Cs-1 37 are 15 and 18 pCi/L, respectively. The MDA for these analyses was at or below the LLD and are reported as "<MDA".

2. For purposes of this.report, LLD is defined as the a priori (before the fact) lower limit of detection, which represents the capability of the measurement system.

MDA is defined as the a posteriori (after the fact) limit of detection capability considering a given instrument, procedure~and type of sample.

3. Tritium analysis is performed on a measured aliquot of distilled sample. The reported values are net measurements above instrument background. The normal MDA for the analyses for tritium was less than 600 pCi/L. Results that are at or below the normal MDA are reported as "<MDA".

Table C-8 01)CM RFOIIRFfl AIR kAMP1 FR, FAPAT FFNICF AMI Sample Alpha Activity Beta Activity Composite Gamma Date (pCi/m 3) (_pCi/m3 ) Activity (pCi/m 3 )

_Co-60 Cs-1 37 1/03/2013 < 4.48E-03 (<MDA) 1.05E-02 + 4.82E-03 1/10/2013 3.1OE-03 +/- 2.51E-03 1.52E-02-+/-+5.44E-03 1/17/2013 < 4.42E-03 (<MDA) 1.36E-02 +/- 5.19E-03 1/24/2013 < 4.51 E-03 (<MDA).. 2.53E-02 _ 6.52E-03-,

1/31/2013 < 4.44E-03 (<MDA) 7.54E-03 +/- 4.40E-03 2/07/2013 < 4.53E-03 (<MDA), 1.68E-02 +/- 5.64E-03 <1.65E-03 <1.85E-03 2/14/2013 < 4.35E-03 (<MDA), 6.47E-03 +/- 4.1,8E-03 < (.6E-0 *M-8 0 2/21/2013 < 4.62E-03 (<MDA) <8.52E-03 (<MDA) 2/28/2013 < 4.33E-03'(<MDA) 1.15E-02+/-:a4.85E-03 3/07/2013 < 4.55E-03 (<MDA) 1-.06E-02++/- 4.90E-03 3/14/2013 < 4.51 E-03 (<MDA) -. 1.10E-02i.ý 4.95E-03 3/21/2013 < 4.51 E-03 (<MDA) ..... 4;81 E-03:- 4.05E-03 3/28/2013 <.3.34E-03 (<MDA) 9.23E-03 -+/- 3.81 E-03 _._

4/04/2013 < 3.32E-03 (<MDA) < 6..13E-03.(<MDA) 4/11/2013 < 3.42E-03 (<MDA) 5.58E-03 +/- 3.33E-03 4/18/2013 < 3.36E-03 (<MDA) 6.54E-03 +/- 3.44E-03 4/25/2013 < 3.42E-03 (<MDA) 1.16E-02 +/- 4.16E-03 5/02/2013 < 3.36.E-03 (<MDA) 1.10E-02 +/- 4.04E-03 5/09/2013 2.86E-03 +/- 2.08E-03 1.26E-02 +/- 4.14E-03 5/16/2013 < 3.42E-03 (<MDA) 1.13E-02 +/- 4.12E-03 < 1.20E-03 < 1.41E-03 5/23/2013 < 3.38E-03 (<MDA) .1.29E-02 +/- 4.25E-03 (MDA) (MDA) 5/30/2013 < 3.39E-03 (<MDA) < 6.02E-03 (<MDA) 6/06/2013 < 3.35E-03 (<MDA) 3.39E-03 +/- 2.96E-03 6/13/2013 < 3.36E-03 (<MDA) < 6.19E-03 (<MDA) 6/20/2013 < 3.41 E-03 (<MDA) 4.OOE-03 +/- 3.12E-03 6/27/2013 2.32E-03 +/- 1.88E-03 5.69E-03 +/- 3.32E-03 7/05/2013 < 2.95E-03 (<MDA) < 543E-03 (<MDA) 7/11/2013 < 3.78E-03 (<MDA) 5.62E-03 +/- 3.63E-03 7/18/2013 < 3.41 E-03 (<MDA) < 6.28E-03 (<MDA) 7/25/2013 2.37E-03 +/- 1.92E-03 7.27E-03 +/- 3.60E-03 8/01/2013 < 3.37E-03 (<MDA) 6.21E-03 +/- 3.39E-03 8/08/2013 < 3.32E-03 (<MDA) 9:17E-03 +/- 3.79E-03 8/15/2013 < 3.45E-03 (<MDA) 5.28E-03 +/- 3.31 E-03 8/22/2013 < 3.37E-03 (<MDA) < 5.99E-03 (<MDA) (MDA) (MDA) 8/29/2013 < 3.29E-03 (<MDA) 4.36E-03 +/- 3.06E-03 9/05/2013 < 3.49E-03 (<MDA) 3.89E-03 +/- 3.13E-03 9/12/2013 < 3.32E-03 (<MDA) < 5.89E-03 (<MDA) 9/19/2013 < 3.48E-03 (<MDA) 7.50E-03 +/- 3.64E-03 9/26/2013 < 3.31 E-03 (<MDA) 7.82E-03 +/- 3.57E-03 10/03/2013 < 3.45E-03 (<MDA) 4.56E-03 +/- 3.20E-03 10/10/2013 3.49E-03 +/- 2.24E-03 1.75E-02 +/- 4.66E-03 10/17/2013 2.42E-03 +/- 1.96E-03 2.18E-02 +/- 5.25E-03 10/24/2013 2.34E-03 +/- 1.89E-03 2.60E-02 +/- 5.52E-03 10/31/2013 < 3.31 E-03 (<MDA) 2.24E-02 +/- 5.14E-03 11/07/2013 < 3.42E-03 (<MDA) 1.03E-02 +/- 3.96E-03 11/14/2013 < 3.37E-03 (<MDA) 1.68E-02 +/- 4.63E-03 <1.19E-03 <1.43E-03 11/21/2013 < 3.32E-03 (<MDA) 7.59E-03 +/- 3.53E-03 (MDA) (MDA) 11/27/2013 < 4.01 E-03 (<MDA) 1.96E-02 +/- 5.48E-03 12/05/2013 < 2.90E-03 (<MDA) 2.67E-02 +/- 5.09E-03 12/12/2013 < 3.38E-03 (<MDA) 2.43E-02 +/- 5.37E-03 12/19/2013 2.36E-03 +/- 1.89E-03 1.99E-02 +/- 4.96E-03 12/26/2013 < 3.44E-03 (<MDA) 5.37E-03 +/- 3.32E-03 1/02/2014 < 3.29E-03 (<MDA) 2.27E-02 +/- 5.14E-03

- 36 -

Table C-8 (Continued) nfrlM 1*R1I IRf AIn RAMPl

. F:.m RHI.I MKIIrI 1.9 IAM9*

Sample Alpha Activity . Beta Activity Composite Gamma Date (pCi/m 3) (pCi/m 3) Activity (pCi/m 3 )

Co-60 Cs-I 37 1/03/2013 < 4.49E-03 (<MDA) 5.27E-03 +/- 4.10E-03 1/10/2013 < 4.47E-03 (<MDA) 9.98E-03 +/- 4.77E-03 1/17/2013 3.06E-03 +/- 2:48E-03 .. 6.59E-03 +/- 4.25E-03 1/24/2013 < 4.50E-03 (<MDA) - :' :2.38E-02 +/- 6.37E-03 1/31/2013 <4.44E-03 (<MDA) <8.19E-03(<MDA) 2/07/2013 < 4.56E-03 (<MDA) 2.56E-02 +/- 6.61 E-03 <1.66E-03 <1.68E-03 21/14/2013 < 4.35E-03 (<MDA),-" < 8.01 E-03 (<MDA) (

2/21/2013 < 4.62E-03 (<MDA) -. 8.35E-03 +/- 4.66E-03 2/28/2013 < 4.31 E-03 (<MDA) -9.16E-03 +/- 4.54E-03 3/07/2013 < 4.57E-03 (<MDA) . 6.80E-03 +/- 4.39E-03 3/14/2013 < 4.50E-03 (<MDA) . 8.13E-03 +/- 4.54E-03 3/21/2013, < 4.51 E-03 (<MDA) ." 6.24E-03 +/- 4.27E-03 3/28/2013 < 3.34E-03 (<MDA) 1.28E-02 +/- 4.20E-03..

4/04/2013 < 3.32E-03 (<MDA) 4.94E-03 +/- 3.19E-03 4/11/2013 < 3.43E-03 (<MDA),. 4.54E-03 +/- 3.19E-03 4/18/2013 < 3.35E-03 (<MDA) 1.OOE-02 +/- 3.86E-03 4/25/2013 2.37E-03 +/- 1.92E-03 1.67E-02 +/- 4.71 E-03 5/02/2013 < 3.36E-03 (<MDA) 1.49E-02 +/- 4.47E-03 5/09/2013 < 3.30E-03 (<MDA) 1.12E-02 +/- 4.01 E-03

.5/16/2013 < 3.43E-03 (<MDA) 8.76E-03 +/- 3.81 E-03 < 1.13E-03 <9;62E-04 5/23/2013 < 3.38E-03 (<MDA) 4.82E-03 +/- 3.19E-03 (MDA) (MDA) 5/30/2013 < 3.38E-03 (<MDA) 7.99E-03 +/- 3.65E-03 6/06/2013 < 3.38E-03 (<MDA) 1.29E-02 +/-4.24E-03 6/13/2013 < 3.32E-03 (<MDA) < 6.12E-03 (<MDA) 6/20/2013 2.38E-03 +/- 1.93E&03 < 6.33E-03 (<MDA) 6/27/2013 < 3.34E-03 (<MDA) 5.69E-03 +/- 3.32E&03 7/05/2013 < 2.95E-03 (<MDA). < 5.44E-03 (<MDA) .

7/11/2013 <3.78E-03 (<MDA) 6.02E-03 +/- 3.69E-03 7/18/2013 < 3.40E-03 (<MDA) < 6.27E-03 (<MDA) 7/25/2013 < 3.42E-03'(<MDA) < 6.30E-03 (<MDA) 8/01/2013 2.39E-03 +/- 1.84E-03 9.03E-03 +/- 3.78E-03 8/08/2013 2.30E-03 +/- 1.87E-03 5.30E-03 +/- 3.25E-03 8/15/2013 < 3.45E-03 (<MDA) 5.28E-03 +/- 3.31 E-03 <1.40E-03 < 1.08E-03 8/22/2013 < 3.37E-03 (<MDA) < 5.98E-03 (<MDA) (MDA) (MDA) 8/29/2013 < 3.30E-03 (<MDA) - 4.03E-03 +/- 3.02E-03 9/05/2013 < 3.50E-03 (<MDA) 5.72E-03 +/- 3.41 E-03 9/12/2013 < 3.30E-03 (<MDA) 5.74E-03 +/- 3.27E-03 9/19/2013 < 3.47E-03 (<MDA) 1.33E-02 +/- 4.36E-03 9/26/2013 < 3.30E-03 (<MDA) 9.51 E-03 +/- 3.76E-03 10/03/2013 < 3.45E-03 (<MDA) 5.64E-03 +/- 3.37E-03 10/10/2013 2.36E-03 +/- 1.82E-03 1.27E-02 +/- 4.18E-03 10/17/2013 < 3.50E-03 (<MDA) 1.78E-02 +/- 4.85E-03 10/24/2013 < 3.38E-03 (<MDA) 1.90E-02 +/- 4.87E-03 10/31/2013 < 3.30E-03 (<MDA) 2.54E-02 +/- 5.40E-03 11/07/2013 < 3.42E-03 (<MDA) 7.84E-03 +/- 3.64E-03 11/14/2013 2.93E-03 +/- 2.13E-03 2.01 E-02 +/- 4.97E-03 11/21/2013 < 3.31 E-03 (<MDA) 5.83E-03 +/- 3.30E-03 (MDA) (MDA) 11/27/2013 2.78E-03 +/- 2.25E-03 2.67E-02 +/- 6.19E-03 12/05/2013 3.57E-03 +/- 2.11 E-03 3.82E-02 +/- 5.93E-03 12/12/2013 < 3.38E-03 (<MDA) 3.45E-02 +/- 6.20E-03 12/19/2013 < 3.36E-03 (<MDA) 2.63E-02 +/- 5.52E-03 12/26/2013 < 3.45E-03 (<MDA) 1.11 E-02 +/- 4.09E-03 1/02/2014 < 3.29E-03 (<MDA) 2.91 E-02 +/- 5.69E-03

- 37 -

Table C-8 (Continued)

ODCM REQUIRED AIR SAMPLES: ANNEX BUILDING (AM3)

Sample Alpha Activity Beta Activity Composite Gamma Date . (pCi/m 3 ) (pCi/m 3 ) Activity (pCi/m 3 )

Co-60. Cs-1 37 1/03/2013 < 4.49E-03.(<MDA) 1.38E-02 +/- 5.26E-03 1/10/2013 < 4.48E-03 (.<MDA) 1.76E-02 +/- 5.72E-03 1/17/2013 < 4.43E-03 (<MDA) 1.41 E-,02 +/- 5.25E-03 1/24/2013 < 4.48E-03 (<MDA) 2.94E-02 +/- 6.91 E-03.

1/31/2013 < 4.44E-03 (<MDA) < 8.19E-03 (<MDA) 2/07/2013 < 4.55E-03 (<MDA) 1'.54E-02 +/- 5.52E-03 .. ..1 E 2/14/2013 < 4.34E-03 (<MDA) < 7.99E-03 (<MDA) <(M(MDA) DA<

2/21/2013 < 4.63E-03 (<MDA) 1.08E-02 +/- 4.99E-03 2/28/2013 3.00E-03 +/- 2.43E-03 6.46E-03 +/- 4.17E-03'.

3/07/2013 3.94E-03 +/- 2.86E-03 6.27E-03 +/- 4.29E-03 3/14/2013 < 4.53E-03 (<MDA) < 8.35E-03:(<MDA) 3/21/2013 < 4.52E-03 (<MDA) "' - 8.33E-03 (<MDA) 3/28/2013 < 3.34E-03 (<MDA) '1.17E-02 +/- 4.10E-03 4/04/2013 < 3.31 E-03 (<MDA) <.6.09E-03 (<MDA) 4/11/2013 < 3.43E-03 (<MDA) < 6.08E-03 (<MDA) 4/18/2013 < 3.36E-03 (<MDA) ' 7.96E-03 +/- 3.63E-03 4/25/2013 < 3.42E-03 (<MDA) 1.23E-02 + 4.23E-03 5/02/2013 < 3.36E-03 (<MDA) 1.32E-02 + 4.29E-03 5/09/2013 < 3.28E-03 (<MDA) 1.18E-02 +/- 4.06E-03 5/16/2013 < 3.43E-03 (<MDA) 1.02E-02 + 3.99E-03 <1.19E-03 < 1.17E-03 5/23/2013 < 3.38E-03 (<MDA) 8.OOE-03 +/- 3.65E-03 (MDA) (MDA) 5/30/2013 < 3.40E-03 (<MDA) 6.26E-03 +/- 3.42E-03 6/06/2013 < 3.36E-03 (<MDA) 5.84E-03 +/- 3.33E-03 6/13/2013 < 3.32E-03 (<MDA)- 4.95E-03 +/- 3.19E-03 6/20/2013 < 3.42E-03 (<MDA) < 6.30E-03 (<MDA).

6/27/2013 < 3.35E-03 (<MDA) 8.91 E-03 +/- 3.76E-03 7/05/2013 < 2.95E-03 (<MDA)'- < 5.44E-03 (<MDA) 7/11/2013 < 3.78E-03 (<MDA) 5.62E-03 +/- 3.63E&03 7/18/2013 < 3.39E-03 (<MDA) 9.01 E-03 +/- 3.80E-03, 7/25/2013 < 3.45E-03 (<MDA) 4.77E-03 +/- 3.26E-03 8/01/2013 < 3.36E-03 (<MDA) 8.99E-03 +/- 3.76E-03 8/08/2013 3.47E-03 +/- 2.30E-03 6.OOE-03 +/- 3.35E-03 8/15/2013 2.44E-03 +/- 1.88E-03 9.92E-03 +/- 3.93E-03 8/22/2013 < 3.40E-03 (<MDA) ' 3.44E-03 +/- 3.OOE-03 < 1-12E-03 < 1.37E-03

< 3.28E-03 (<MDA) < 5.82E-03 (<MDA) .. ..

8/29/2013 9/05/2013 < 3.50E-03 (<MDA) 6.81 E-03 +/- 3.58E-03 9/12/2013 < 3.30E-03 (<MDA) 6.42E-03 +/- 3.37E-03 9/19/2013 < 3.50E-03 (<MDA) 1.05E-02 +/- 4.04E-03 9/26/2013 < 3.29E-03 (<MDA) < 5.84E-03 (<MDA) 10/03/2013 < 3.43E-03 (<MDA) 1.35E-02 +/- 4.35E-03 10/10/2013 2.37E-03 +/- 1.83E-03 2.14E-02 +/- 5.06E-03 10/17/2013 < 3.50E-03 (<MDA) 2.23E-02 +/- 5.30E-03 10/24/2013 < 3.36E-03 (<MDA) 1.40E-02 +/- 4.35E-03 10/31/2013 < 3.32E-03 (<MDA) 1.97E-02 +/- 4.88E-03 11/07/2013 < 3.42E-03 (<MDA) 1.07E-02 +/- 4.OOE-03 11/14/2013 < 3.36E-03 (<MDA) 1.47E-02 +/- 4.41 E-03 <6.86E-04 <1.27E-03 11/21/2013 < 3.33E-03 (<MDA) 7.62E-03 +/- 3.54E-03 (MDA) (MDA) 11/27/2013 3.48E-03 +/- 2.53E-03 2.63E-02 +/- 6.14E-03 12/05/2013 < 2.90E-03 (<MDA) 2.92E-02 +/- 5.29E-03 12/12/2013 2.34E-03 +/- 1.88E-03 3.10E-02 +/- 5.89E-03 12/19/2013 < 3.39E-03 (<MDA) 1.87E-02 +/- 4.86E-03 12/26/2013 < 3.43E-03 (<MDA) 1.36E-02 +/- 4.35E-03 1/02/2014 < 3.31 E-03 (<MDA) 2.93E-02 +/- 5.72E-03

- 38 -

Table C-8 (Continued)

ODCM REQUIRED AIR SAMPLES: RELAY BUILDING (AM4) .

Sample Alpha Activity Beta Activity Composite Gamma bate (pCi/m 3) (pCi/m 3 ) Activity (pCilm 3) 0o-60 C Cs-1 37 1/03/2013 < 4.49E-03 (<MDA) 1.43E-02 +/- 5.30E-03 1/10/2013 3.1OE-03 +/- 2.51 E-03 - :24E-02 +/- 5.11 E-03 1/17/2013 < 4.43E-03 (<MDA) 1.04E-02 +/- 4.78E-03 1/24/2013 < 4.49E-03 (<MDA) -.2.38E-02 +/- 6.35E-03 1/31/2013 < 4.44E-03 (<MDA) < 8.19E-03 (<MDA) 2/07/2013 < 4.55E-03 (<MDA) " 1:79E-02-< +/- 5.82E-03 . 2.49E-03 < 1.92E-03 2/14/2013 ,< 4.33E-03 (<MDA) 7.37E-03 +/- 4.30E-03 (MDA) (MDA) 2/21/2013 < 4.63E-03 (<MDA) 4'.94E-03 +/- 4.15E-03 2/28/2013 < 4.34E-03 (<MDA),2 6.: 01 E-03 +/- 4.1OE-03 3/07/2013 < 4.53E-03 (<MDA) 101

.- E-02 +/- 4.84E-03 3/14/2013 < 4.53E-03 (<MDA) <8.35E-03 (<MDA) 3/21/2013 < 4.51 E-03 (<MDA) :6.72E-03 +/- 4.34E-03 3/28/2013 < 3.35E-03 (<MDA) 9.96E-03 +/- 3.89E-03 4/04/2013 < 3.31 E-03 (<MDA) 4.23E-03 +/- 3.08E-03 4/11/2013 < 3.42E-03 (<MDA) < 6.07E-03 (<MDA) 4/18/2013 < 3.36E-03 (<MDA) 5.15E-03 +/- 3.23E-03 4/25/2013 < 3.42E-03 (<MDA) 1.05E-02 +/- 4.01 E-03 5/02/2013 < 3.36E-03 (<MDA) 9.98E-03 +/- 3.90E-03 5/09/2013 < 3.28E-03 (<MDA) 1.57E-02 +/- 4.48E-03 5/16/2013 2.98E-03 +/- 2.16E-03 1.27E-02 +/- 4.27E-03 < 9.04E-04 < 1.15E-03 5/23/2013 3.55E-03 +/- 2.28E-03 5.17E-03 +/- 3.24E-03 (MDA) (MDA) 5/30/2013 < 3.40E-03 (<MDA) < 6.03E-03 (<MDA) 6/06/2013 < 3.36E-03 (<MDA) 7.95E-03 +/- 3:63E-03 6/13/2013 < 3.39E-03 (<MDA) .5.04E-03 +/- 3.26E-03 6/20/2013 < 3.35E-03 (<MDA) 6.06E-03 +/- 3.38E-03 6/27/2013 < 3.38E-03 (<MDA) 3.96E-03 +/- 3.09E-03 7/05/2013 < 2.95E-03 (<MDA) ., 5.01 E-03 +/- 2.93E-03 7/11/2013 < 3.75E-03 (<MDA) 4.40E-03 +/- 3.43E-03 7/18/2013 < 3.41 E-03 (<MDA)ý 6.16E-03 +/- 3.44E-03 7/25/2013 < 3.45E-03 (<MDA) 5.14E-03 +/- 3.32E-03 8/01/2013 < 3.36E-03 (<MDA) 4.10E-03 +/- 3.07E-03 8/08/2013 < 3.32E-03 (<MDA) 4.24E-03 +/- 3.09E-03 8/15/2013 < 3.44E-03 (<MDA) 9.57E-03 +/- 3.89E-03 8/22/2013 <3.40E-03 (<MDA) 8.74E-03 +/- 3.74E-031.29E-03 8/29/2013 < 3.28E-03 (<MDA) 3.66E-03 +/- 2.94E-03 (MDA) (MDA) 9/05/2013 < 3.50E-03 (<MDA) 4.27E-03 +/- 3.20E-03 9/12/2013 2.91 E-03 +/- 2.03E-03 6.08E-03 +/- 3.32E-03 9/19/2013 < 3.50E-03 (<MDA) 9.01 E-03 +/- 3.85E-03 9/26/2013 < 3.29E-03 (<MDA) 8.13E-03 +/- 3.59E-03 10/03/2013 < 3.44E-03 (<MDA) 9.21 E-03 +/- 3.85E-03 10/10/2013 < 3.34E-03 (<MDA) 1.20E-02 +/- 4.09E-03 10/17/2013 < 3.50E-03 (<MDA) 1.28E-02 +/- 4.31 E-03 10/24/2013 < 3.36E-03 (<MDA) 1.68E-02 +/- 4.63E-03 10/31/2013 2.30E-03 +/- 1.86E-03 2.53E-02 +/- 5.40E-03 11/07/2013 < 3.42E-03 (<MDA) 7.83E-03 +/- 3.64E-03 11/14/2013 2.91 E-03 +/- 2.12E-03 1.75E-02 +/- 4.69E-03 11/21/2013 < 3.33E-03 (<MDA) 1.32E-02 +/- 4.24E-03 81(MDA) (MDA) 11/27/2013 < 4.01 E-03 (<MDA) 1.71 E-02 +/- 5.22E-03 12/05/2013 < 2.90E-03 (<MDA) 2.01 E-02 +/- 4.54E-03 12/12/2013 2.35E-03 +/- 1.66E-03 2.90E-02 +/- 5.07E-03 12/19/2013 < 3.39E-03 (<MDA) 2.44E-02 +/- 5.39E-03 12/26/2013 < 3.43E-03 (<MDA) 9.29E-03 +/- 3.85E-03 1/02/2014 < 3.31 E-03 (<MDA) 2.41 E-02 +/- 5.28E-03

- 39 -

Table C-8 (Continued)

ODCM REQUIRED AIR SAMPLES: OIL WATER SEPARATOR (AM5)

Sample Alpha Activity 3 Beta Activity 3 Composite Gamma 3 Date .: (pCi/m ) (pCi/m ) Activity (pCi/m )

0o-60 C Cs-1 37 1/03/2013 < 4.48E-03 (<MDA) " 1.19E-02 +/- 5.01 E-03 1/10/2013 < 4.48E-03 (<MDA) 1.33E-02 +/- 5.20E-03 1/17/2013 < 4.43E-03 (<MDA) ,1.51E-02 +/- 5.38E-03 1/24/2013 < 4.49E-03 (<MDA) 2.67E-02 +/- 6.65E-03 1/31/2013 < 4.46E-03 (<MDA) 4.76E-03 +/- 4.01E-03 2/07/2013 < 3.39E-03 (<MDA) 1.80E-02 +/- 4.80E-03 2/14/2013 < 3.25E-03 (<MDA) < 5.99E-03 (<MDA) ....(MDA) (MDA)-

2/21/2013 < 3.47E-03 (<MDA) 5.16E-03 +/- 3.33E-03 _ AM 2/28/2013 2.83E-03 +/- 2.06E-03 .3.48E-03 +/- 2.93E-03 3/07/2013 < 3.40E-03 (<MDA) .1.26E-02 +/- 4.24E-03 3/14/2013 < 3.40E-03 (<MDA) 1.19E-02 +/- 4.16E-03 1.

3/21/2013 < 3.38E-03 (<MDA) .,6%.46E-03 +/- 3.46E-03 3/28/2013 2.91 E-03 +/- 2.11E-03 :-,:.,1.46E-02 +/- 4.42E-03 4/04/2013 < 3.31 E-03 (<MDA) < 6.11E-03 (<MDA) 4/11/2013 < 3.42E-03 (<MDA) 4.52E-03 +/- 3.18E-03 4/18/2013 < 3.36E-03 (<MDA) .1.53E-02 +/- 4.46E-03 4/25/2013 < 3.42E-03 (<MDA) 1.74E-02 +/- 4.78E-03 5/02/2013 2.33E-03 +/- 1.88E-03 . 1.92E-02 +/- 4.89E-03 5/09/2013 2.86E-03 +/- 2.08E-03 1.92E-02 +/- 4.83E-03 5/16/2013 2.97E-03 +/- 2.16E-03 1.67E-02 +/- 4.70E-03 < 1.27E-03 < 1.12E-03 5/23/2013 < 3.38E-03 (<MDA) 4.12E-03 +/- 3.09E-03 (MDA) (MDA) 5/30/2013 < 3.40E-03 (<MDA) 5.91 E-03 +/- 3.37E-03 6/06/2013 < 2.96E-03 (<MDA) 7.94E-03 +/- 3.32E-03 6/13/2013 < 3.84E-03 (<MDA) 4.10E-03 +/- 3.45E-03 6/20/2013 < 1.19E-02 (<MDA) 4.15E-02 +/- 2.19E-02 6/27/2013 < 3.37E-03 (<MDA) 1.OOE-02 +/- 3.91 E-03 7/05/2013 < 2.94E-03 (<MDA) 9.38E-03 +/- 3.48E-03 _ _._-

7/11/2013 < 3.78E-03 (<MDA) 6.42E-03 +/- 3.75E-03 7/18/2013 < 3.41 E-03 (<MDA) 5.43E-03 +/- 3.33E-03 7/25/2013 < 3.43E-03 (<MDA) 5.48E-03 +/- 3.36E-03 8/01/2013 < 3.37E-03 (<MDA) 6.55E-03 +/- 3.44E-03 8/08/2013 < 3.31 E-03 (<MDA) 8.46E-03 +/- 3.68E-03 8/15/2013 < 3.45E-03 (<MDA) < 6.12E-03 (<MDA) 8/22/2013 < 3.39E-03 (<MDA) 8.02E-03 +/- 3.66E-03 <1.40E-03 <1.34E-03 8/29/2013 2.33E-03 +/- 1.79E-03 7.76E-03 +/- 3.54E-03 >(MDA). DA) 9/05/2013 < 3.50E-03 (<MDA) 9.38E-03 +/- 3.92E-03 9/12/2013 < 3.31 E-03 (<MDA) 1.40E-02 +/- 4.29E-03 9/19/2013 < 3.50E-03 (<MDA) 1.55E-02 +/- 4.61 E-03 9/26/2013 < 3.29E-03 (<MDA) 1.29E-02 +/- 4.17E-03 10/03/2013 2.44E-03 +/- 1.88E-03 6.34E-03 +/- 3.46E-03 10/10/2013 2.36E-03 +/- 1.82E-03 1.79E-02 +/- 4.70E-03 10/17/2013 2.43E-03 +/- 1.97E-03 2.34E-02 +/- 5.41 E-03 10/24/2013 < 3.36E-03 (<MDA) 2.03E-02 +/- 4.98E-03 10/31/2013 < 3.32E-03 (<MDA) 2.84E-02 +/- 5.64E-03 11/07/2013 < 3.42E-03 (<MDA) 1.43E-02 +/- 4.43E-03 11/14/2013 < 3.36E-03 (<MDA) 1.85E-02 +/- 4.80E-03 <1.36E-03 <1.46E-03 11/21/2013 2.89E-03 +/- 2.1OE-03 1.11 E-02 +/- 3.99E-03 (MDA) (MDA) 11/27/2013 < 4.01E-03 (<MDA) 3.38E-02 +/- 6.81E-03 12/05/2013 < 2.90E-03 (<MDA) 3.49E-02 +/- 5.70E-03 12/12/2013 2.35E-03 +/- 1.88E-03 3.39E-02 +/- 6.13E-03 12/19/2013 < 3.38E-03 (<MDA) 2.61 E-02 +/- 5.53E-03 12/26/2013 < 3.43E-03 (<MDA) 1.64E-02 +/- 4.67E-03 1/02/2014 2.32E-03 +/- 1.86E-03 4.OOE-02 +/- 6.53E-03

-40 -

Table C-8 (Continued)

ODCM REQUIRED AIR SAMPLES: HUMBOLDT HILL (STATION,3)

Sample Alpha Activity 3 Beta Activity 3 Composite Gamma 3 Date . (pCi/m ) " (pCi/m ) Activity (pCi/m )

__ ._-_00Co-60 Cs-1 37 1/03/2013 < 444E-03 (<MDA), 7.56E-03,+/- 4.41 E-03.

1/10/2013 < 4.48E-03 (<MDA) 1.OOE-02 +/- 4.78E-03 1/17/2013 < 4.46E-03 (<MDA) 1.47E-02 +/- 5.37E-03 1/24/2013. < 4.40E-03.(<MDA) 1.73E-02 +/- 5.62E-03 1/31/2013 < 4.54E-03 (<MDA) < 8.37E-03 (<MDA) 2/07/2013 < 4.44E-03 (<MDA) 1.04E-02 +/- 4.79E-03 <1.65E-03 <1.72E-03 2/14/2013. < 4.40E-03 (<MDA) < 8.115--03 (<MDA) - 1.5-0 <175-2/21/2013 < 4.60E-03 (<MDA) <8.47E-03 (<MDA) (MDA) (MDA) 2/28/2013 < 4.36E-03 (<MDA)" 6.49E&03 +/- 4.19E-03 3/07/2013 < 4.44E-03 (<MDA) < 8.18E-03 (<MDA) 3/14/2013 < 4.61 E-03 (<MDA) < 8.50E!03 (<MDA) 3/21/2013 < 4.37E-03 (<MDA) 4.67E-03 +/- 3.93E-03 3/28/2013 < 3.41 E-03 (<MDA) 8.33E-03 +/- 3.74E-03 4/04/2013 < 3.39E-03 (<MDA) < 6.26E-03 (<MDA) 4/11/2013 <3.28E-03 (<MDA) 7.43E-03 +/- 3.48E-03 4/18/2013 < 3.38E-03 (<MDA) 4.83E-03 +/- 3.19E-03 4/25/2013 < 3.46E-03 (<MDA) 1.14E-02'+/- 4.17E-03 5/02/2013 < 3.28E-03 (<MDA) 1.08E-02 +/- 3.95E-03' 5/09/2013 < 3.43E-03 (<MDA) 1.09E-02 +/- 4.06E-03 5/16/2013 3.40E-03 +/- 2.26E-03 1.21 E-02 +/- 4.07E-03 < 1.28E-03 < 1.36E-03 5/23/2013 < 3.50E-03 (<MDA) 1.01 E-02 +/- 4.OOE-03 (MDA) (MDA) 5/30/2013 < 3.41 E-03 (<MDA) < 6.05E-03 (<MDA) 6/06/2013 < 3.34E-03 (<MDA) 5.11 E-03 +/- 3.20E-03

.6/13/2013 < 3.42E-03 (<MDA) < 6.31 E-03 (<MDA) 6/20/2013 < 3.20E-03 (<MDA) 9.87E-03 +/- 3.76E-03 6/27/2013 < 3.43E-03 (<MDA) 3.66E-03 +/- 3.08E-03 7/05/2013 < 2.96E-03 (<MDA) < 5.45E-03 (<MDA) 7/11/2013 < 3.85E-03 (<MDA) 5.33E-03 +/- 3.64E-03 7/18/2013 < 3.32E-03 (<MDA) 3.54E-03 +/- 2.98E-03 7/25/2013 < 4.30E-03 (<MDA) < 7.93E-03 (<MDA) 8/01/2013 < 3.44E-03 (<MDA) 3.84E-03 +/- 3.09E-03 8/08/2013 < 3.26E-03 (<MDA) 4.17E-03 +/- 3.03E-03 8/15/2013 < 3.47E-03 (<MDA) < 6.17E-03 (<MDA) <1.73E-03 < 1.46E-03 8/22/2013 < 3.42E-03 (<MDA) < 6.06E-03 (<MDA) (MDA) (MDA) 8/29/2013 < 3.26E-03 (<MDA) < 5.78E-03 (<MDA) 9/05/2013 3.66E-03 +/- 2.35E-03 < 6.19E-03 (<MDA) 9/12/2013 < 3.34E-03 (<MDA) 6.85E-03 +/- 3.45E-03 9/19/2013 < 3.45E-03 (<MDA) 9.96E-03 +/- 3.94E-03 9/26/2013 < 3.39E-03 (<MDA) 3.78E-03 +/- 3.04E-03 10/03/2013 < 3.42E-03 (<MDA) 4.87E-03 +/- 3.23E-03 10/10/2013 2.94E-03 +/- 2.06E-03 9.30E-03 +/- 3.78E-03 10/17/2013 2.36E-03 +/- 1.91 E-03 1.10E-02 +/- 4.05E-03 10/24/2013 2.93E-03 +/- 2.13E-03 1.47E-02 +/- 4.43E-03 10/31/2013 < 3.40E-03 (<MDA) 1.42E-02 +/- 4.40E-03 11/07/2013 < 3.33E-03 (<MDA) 4.13E-03 +/- 3.06E-03 11/14/2013 < 3.38E-03 (<MDA) 1.58E-02 +/- 4.55E-03 11/21/2013 < 3.37E-03 (<MDA) 8.42E-03 +/- 3.69E-03 (MDA) (MDA) 11/27/2013 < 3.97E-03 (<MDA) 1.86E-02 +/- 5.34E-03 12/05/2013 2.61 E-03 +/- 1.81 E-03 1.92E-02 +/- 4.48E-03 12/12/2013 2.37E-03 +/- 1.90E-03 2.05E-02 +/- 5.01 E-03 12/19/2013 < 3.37E-03 (<MDA) 1.58E-02 +/- 4.56E-03 12/26/2013 < 3.40E-03 (<MDA) 8.49E-03 +/- 3.72E-03 1/02/2014 < 3.37E-03 (<MDA) 2.25E-02 +/- 5.20E-03 Table C-8 Notes

1. Composite samples for first, second, third and fourth quarter ODCM Air Samples were analyzed by gamma spectroscopy. Sample analyses were performed by HBPP count room personnel. All samples met the LLD requirements of 6.OE-02 pCi/m 3 for Cs-137.

2. All LLD's were met for Gross Beta (required LLD1.0E-02 pCi/mn3) with the exception of the Oil Water Separator (OWS) air sample- collected on 6/12/2013. The air sample pump- malfunctioned after running approximately 17 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months . As a result, the'beta LLD was 6.05E-02 pCi/m3 instead of the required 1.OE-02 pCiI/m3 due to the low sample volume.

.L . " .. I .. . .

3. All samples reported as <MDA represent results that had no identified gamma peaks.

4. Humboldt Hill (Offsite) is also known as Station 3. East Fence is-also known as AMI1. Building 12 is also known as AM2. Annex is also known as AM3. Relay Building is also known as AM4. Oil Water Separator (OWS) is also known as.AM5.

-42 -

FIGURE A-1 HBPP ONSITE AIR SAMPLE LOCATIONS Location GPS Coordinates (NAD83/NAVD88 CA. Zone 1) HBPP (called north)

Number Easting Northing el. East North AMI 5949518.63 2161208:89 20.68 5383.96 9299.72 AM2 5949091.47 2161143.20 33.05 4989.34 9475.92 AM3 5949177.71 2160817.45 11.29 4885.34 9155.45 AM4 5949441.54 2160838.93 11.36 5118.73 9030.56 AM5 5949576.07 2160969.08 11.94 5302.31 9067.06 Figure A-1 Note:

1. Humboldt Hill (Offsite) is also known as Station 3, East Fence is also known as AM1, Building 12 is also known as AM2, Annex is also known as AM3, Relay Building is also known as AM4, OWS is also known as AM5.

FIGURE A-2 HBPP OFFSITE AIR SAMPLE. LOCATION HUMBOLDT HILL (Station 3)

GPS Coordinates (NAD83/NAVD88 CA. Zone 1) Degree.Decimal Easting I Northing el. Latitude Longitude 5951260.28 2155706.11 234.94 40.72676 -124.20274

-44 -

FIGURE A-3 HBPP ONSITE TLD LOCATIONS Stations T1 - T21 (excluding T17)

Location GPS Coordinates (NAD83/NAVD88 CA. Zone 1) HBPP (called north)

Number Easting Northing el. East I North Ti 5949161.06.2160822.11 10.78 4873.87 9168.63 T2 5948804.52 2160710.72 11.56 4513.84 9268.18 T3 5948609.45 2161061.84 41.77 4540.12 9668.91 T4 5948778.72 2161269.91 43.66 4795.13 9752.07 1"5 5949002.39 2161368.44 38.19 5036.50 9713.721 T6 5949159.22 2161437.55 36.30 5205.77 9686.84 17 5949280.02 2161494.61 32.04 5338.22 9669.36 T8 5949511.99 2161608.36 12.96 5594.82 9639.33 T9 5949651.46 2161588.47 11.79 5701.27 9547.04 T10 5949912.89 2161633.96 11.17 5945.65 9443.64 Tl1 5950011.77 2161297.55 14.18 5846.48 9107.30 T12 5950019.25 2160858.44 11.25 5614.86 8734.19 T13 5949841.53 2160718.03 9.79 5389.40 8712.46 T14 5949583.98 2160684.24 10.46 5154.63 8823.60 T15 5949448.88 2160600.96 10.34 4995.96 8826.81 T16 5949352.82 2160667.18 10.80 4951.10 8934.52 Tie 5948867.24 2161239.36 43.47 485Z98 9678.44 T19 5948796.71 2161242.74 42.84 4795.52 9719.50 T20 5948747.14 2161191.68 44.14 4726.20 9703.44 T21 5948834.52 2161182.89 45.71 4799.39 9644.52 FIGURE A-4 HBPP OFFSITE Stations (1,TLD LOCATIONS 14 & 25)

O GPS Coordinates (NAD83/NAVD88 CA. Zone 1) Degree.Decimal Easting Northing el. Latitude Longitude 1 5948026.52 2161183.79 11.38 40.74156 124.21903 14 5949876.83 2158864.39 18.65 40.73533 -124.20802 25 5950247.30 2154214.18 229.22 40.72260 -124.20626 FIGURE A-4 (Continued)

HBPP OFFSITE TLD LOCATION FORTUNA (Station 2)

GPS Coordinates (NAD83/NAVD88 CA. Zone 1) Degree.Decimal 0 Easting 5962583.86 I Northing 2105797.82 I el.

35.53 Latitude 40.59057 I Longitude

-124.15746 FIGURE A-4 (Continued)

HBPP OFFSITE TLD LOCATION EUREKA (Control Location T17) 0 Easting 5976549.55 Northing 2175490.19 el.

164.85 Latitude 40.78276 Longitude

-124.11324 FIGURE A-5 HBPP EFFLUENT SAMPLING STATION Location GPS Coordinates (NAD83/NAVD88 CA. Zone 1) HBPP (called north)

Easting Northing el. East North SampleStation 5949692.10 2161298.85 11.00 5578.51 9281.57

-49 -

FIGURE A-6 HBPP GROUNDWATER SAMPLE POINTS M~ TO MOMnORING WRllS SM4L Wv ELs RCW-SW--2 RCW--SW-2 ~-'

RCW--SW-4 ) ,

/

MONEE1I!5F AW-1 NEU$ Af#LJ AVW-S$RP-2 - ANIK RC-SP--

Rci-aq 6r :fi VEIP WEIS RCW-CS-4 RCW-.C-3 RCW-,C-9 F3IVrAMA&JTl 0 G~WXWW41ER MTMU~omw NEU Afi- I LOGITG AAV LEWW"M1~ (ONUP; W Ill kq~b(,I Ief.~.

f Z"

ME (I

FIGURE A-7 HBPP OFFSITE DAIRY SAMPLE POINTS GPS Coordinates (NAD83/NAVD88 CA. Zone 1) Degree.Decimal Dairy Address Latitude Longitude Holgerson 5231 Tompkins Hill Rd - Loleta, CA 40.66851 -124.19209 Pedrotti 5396 Elk River Rd - Eureka, CA 40.74869 -124.15746 FIGURE B-1 OFFSITE ENVIRONMENTAL RADIATION LEVEL TRENDS 70.0 60.0

, 50.0 a) 40.0 E

30.0 0

a 20.0 10.0 0.0 Year The baseline values for each location were obtained by averaging the readings at each location from 1977 through 1983. These values, however, were obtained using ion chambers instead of TLDs. The average annual values from 1977 through 1983 were Station 1 - 83.0 mrem, Station 2 -

79.8 mrem, Station 14 - 80.2 mrem, and Station 25 - 73.7 mrem FIGURE B-2 ONSITE ENVIRONMENTAL RADIATION LEVEL TREN DS 70.0 60.0 +

-50.0 E

) 40.0 -

E 30.0 -

0 .020.0 Stations Near Radwaste Activities (T5 through T8) 10.0 t Other Onsite Stations (TI through T4 and T6 through T16)

Stations Surrounding ISFSI (T18 through T21) 0 .0 g I I I I I I I I I I I I I I I I I I I I I h

e The baseline values for the two areas were obtained by averaging the readings for each area from 1977 through 1983. These values, however, were obtained using ion chambers instead of TLDs. The average annual value from 1977 through 1983 for the stations near the radwaste activities was 78.6 mrem and the average annual value for other onsite stations was 79.4 mrem.

HBL-14-011, Annual Radiological Environmental Monitoring Report for 2013

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HBL-14-011, Annual Radiological Environmental Monitoring Report for 2013

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