Text

Annual Radiological Environmental Monitoring Report for 2014
	ML15134A020
Person / Time
Site:	Humboldt Bay
Issue date:	04/29/2015
From:	Sharp L; Pacific Gas & Electric Co
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
	HBL-15-006
	Download: ML15134A020 (54)
	v • d • e

W Pacic Gas and PacificGasanyd Loren D. Sharp Director & Plant Manager Humboldt Bay Power Plant 1000 King Salmon Avenue Electic Company" Humboldt Bay Nuclear Eureka, CA 95503 707.444.0819 Internal: 375.0819 Fax: 707.444.0871 April 29, 2015 PG&E Letter HBL-15-006 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 2014

Dear Commissioners and Staff:

Enclosed is the Humboldt Bay Power Plant Unit 3, "Annual Radiological Environmental Monitoring Report" for 2014. 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-15-006 April 29, 2015 Page 2 If you wish to discuss the information in the enclosed report, please contact Jim Morris at (805) 545-4609.

Loren D. Sharp V 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-15-006 HUMBOLDT BAY POWER PLANT UNIT 3 ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT JANUARY 1 THROUGH DECEMBER 31, 2014

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

1. Program Description ................ I ...................................................................... 1

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

a. Offsite Environm ental Monitoring ............................................................... 2

b. Onsite Environm ental Monitoring ............................................................... 3

c. Other Monitoring ....................................................................................... 4

3. Interlaboratory Com parison Program .................................................................. 4

4. NEI Groundwater Protection Initiative .................................................... 6 B. TRENDS, BASELINE COMPARISONS AND INTERPRETATIONS .................... 6

1. General Com ments ....................................................................................... 6

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

3. Airborne Pathway .............. ;.............................. 7

4. W aterborne Pathway ..................................................................................... 8

a. Surface W ater ........................................................................................... 8

b. Groundwater .............................................................................................. 8

5. Ingestion Pathway .......................................................................................... 8

6. Terrestrial Pathway .......................................................................................... 9 C. MONITO RING RESULTS ..................................................................................... 9

1. Annual Sum m ary ............................................................................................ 9

2. Direct Radiation Pathway ............................................................................... 9

3. Airborne Pathway .......................................................................................... 10

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

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

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TABLE OF CONTENTS (Continued) b . G ro u nd w a te r ................................................................................................ 10 5 . In g e stio n P athw a y ............................................................................................. 11

6. Terrestrial Pathway ........................................................................................ 11

7. NEI Groundwater Protection Initiative Voluntary Reporting 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 DIRECTIONS TO HBPP OFFSITE SAMPLE LOCATIONS ... 15 A-3 GEL PARTICIPATION - INTERLABORATORY CROSS-CHECK PROGRAM DA TA ................................................................................................................... 16 A-4 HBPP PARTICIPATION - ECKERT & ZIEGLER INTERLABORATORY CROSS-C HEC K PRO G RAM DATA .............................................................................. 19 C-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL REPORT S UM M A R Y ................................................................................................... . . 23 C-2 ONSITE ENVIRONMENTAL TLD STATIONS ................................................ 25 C-3 OFFSITE (Control) ENVIRONMENTAL TLD STATIONS ................................. 26 C-4 GROUNDWATER MONITORING WELL RESULTS ....................................... 27 C-5 CAISSON SUMP MONITORING RESULTS .................................................... 31 C-6 FRENCH DRAIN MONITORING RESULTS .................................................... 32 C-7 ODCM REQUIRED AIR SAMPLES ................................................................. 33 LIST OF FIGURES Figure Page A-1 HBPP ONSITE AIR SAMPLE LOCATIONS ..................................................... 40 A-2 HBPP OFFSITE AIR SAMPLE LOCATION ................................................... 41 A-3 HBPP ONSITE TLD LOCATIONS .................................................................... 42 A-4 HBPP OFFSITE TLD LOCATIONS .................................................................. 43 A-5 HBPP GROUNDWATER SAMPLE POINTS ................................................... 46 B-1 OFFSITE ENVIRONMENTAL RADIATION LEVEL TRENDS .......................... 47 B-2 ONSITE ENVIRONMENTAL RADIATION LEVEL TRENDS ............................ 48

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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, 2014 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, 2014, 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. 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 at a nuclear 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 perform sample collection and sample analysis of airborne radioactivity. General Engineering Laboratories (GEL) personnel perform sample analysis of ground water radioactivity. Mirion Technologies personnel perform analysis of thermoluminescent dosimeters (TLDs) used for monitoring direct radiation. A summary of the REMP.is provided as Table A-i, "HBPP RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM".

Sample collection for the REMP is performed at the sampling stations defined by Table A-2, "DISTANCES AND DIRECTIONS TO HBPP OFFSITE 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", and Figure A-5 "HBPP GROUNDWATER SAMPLE POINTS".

2. Monitoring Requirements

a. Offsite Environmental Monitoring

1. Airborne The SAFSTOR ODCM requires one (1) 6ffsite 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.

Offsite environmental stations selected to satisfy this requirement are Stations 1, 2, 14, 25, while T17 is the offsite control station as shown on Figure A-4.. These stations are considered to represent the offsite locations for the direct radiation pathway.

3. Ingestion The requirement to perform milk sampling was removed from the SAFSTOR ODCM Revision 24 based upon no detection of Sr-90 or plant-related gamma emitters in milk since decommissioning began.

b. Onsite Environmental Monitoring

1. Airborne The SAFSTOR ODCM requires five (5) air sampling stations. The stations selected to satisfy this requirement are Stations AMI through AM5 as shown on Figure A-I. 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 a minimum of 8 onsite environmental monitoring stations at or within the site boundary fence line, equipped with TLDs to monitor gamma exposure. TLDs are required to be exchanged quarterly. A total of 16 TLD stations are currently used to satisfy this requirement. Stations T1 through T16 are 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.

The minimum number of TLDs was modified in the ODCM from 16 to 8 stations to allow monitoring locations to be reduced as source term is removed from the site during the final phase of decommissioning.

3. Waterborne Surface Water Effective December 31, 2013, discharge of processed radioactive liquid effluents to Humboldt Bay was terminated. Any remaining or incidental radioactive liquids in concentrations exceeding 10 times 10 CFR 20, Appendix B, Table 2 Column 2 are manifested for disposal at a licensed landfill. Sampling and manifesting requirements are consistent with the requirements of the receiving facility and not subject to ODCM methodology. Sampling of surface water is not required by the current revision of the SAFSTOR ODCM.

Groundwater Revision 23 of the SAFSTOR 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. 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 documented the reassignment of groundwater monitoring from the ODCM to plant procedures.

A total of fourteen (14) intermediate and deep ground water wells are included in the current groundwater monitoring initiative. Intermediate wells range in depth from 45 ft. to 69 ft. and are comprised of MW-1 1, RCW-SFP-1, RCW-SFP-2, RCW-SFP-3, RCW-SFP-4, RCW-SFP-5, and RCW-SFP-6. Deep ground water monitoring wells range in depth from 83 ft. to 110 ft. and include RCW-CS-3, RCW-CS-5, RCW-CS-6, RCW-CS-7, RCW-CS-8, RCW-CS-9 and RCW-CS-10. Each well was sampled on a quarterly basis. Well locations are shown on Figure A-5, "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 count room 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 CROSS-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 three sets of Eckert & Ziegler Analytics samples for 23 parameters that are representative of analyses performed for HBPP during 2014. All results met the acceptance criteria. The fourth quarter Eckert &

Ziegler Analytics sample data had not been reported to GEL as of the time of this report; 2014 fourth quarter results will be included in the HBPP 2015 REMP report. This will be tracked in corrective action SAPN 1401944.

HBPP analyzed four sets of Eckert & Ziegler Analytics samples for gamma in water and gamma in soil, ( 1 st quarter), gamma air filter and alpha/beta air filter (2 nd and 4 th quarters), and gamma in soil and tritium in water (3 rd quarter).

These analyses are representative of those performed by HBPP count room personnel during 2014. All results met the acceptance criteria with the exception of the following:

0 A 5-minute gross alpha count performed on one of the gas flow proportional counters did not meet the acceptance criteria with the analysis results approximately 3% low. Values used for reporting purposes were based on a 10-minute count and were acceptable. This discrepancy is documented in SAPN 1384606. The SAPN was written for tracking and trending purposes and has been closed.

Cr-51 identified in the gamma soil cross check for the third quarter was reported as higher than the E&Z reference value for Detectors 2, 3 and

5. All results for Cs-1 37 and Co-60 were determined as acceptable while the Cr-51 analysis results may be considered "high" but conservative.

This discrepancy is documented in SAPN 1384606. The SAPN was written for tracking and trending purposes and has been closed.

o The 2014 Radiation Protection Audit established HBPP laboratory personnel participated in an interlaboratory environmental cross check program in 2013 as prescribed by Regulatory Guide 4.15 Section 6.3.2.

However, the technical process used to prescribe the contents of the cross check program was not well documented in program procedures.

This discrepancy is documented in SAPN 1394360. A procedure revision was initiated as a result of the SAPN to provide more adequate documentation of cross check criteria and the SAPN status is now closed.

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 established in the Environmental Report.

The results, interpretations, and analysis of 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-1, "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.

HBPP changed TLD processing services beginning in January 2014. Data from previous years was based on a Panasonic TLD system. Data in 2014 is based on Mirion Genesis type TLD system. The apparent rise in Figures B-1 and B-2 may partially be a result of the change in monitoring devices.

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 Spent Fuel Storage Installation (ISFSI) was constructed in 2008, and spent fuel transfer from the spent 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 1.85 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 The original Liquid Radwaste Treatment System has been dismantled and removed. Radioactive water associated with the Spent Fuel Pool is processed using the filtered ion exchange system and liquid radioactive wastes are treated by an offsite waste processor or shipped for disposal at a regulated disposal facility. Discharges of liquid radioactive effluent to Humboldt Bay were eliminated after December 2013.

b. Groundwater None of the samples of the fourteen (14) SAFSTOR REMP monitoring wells indicated 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 on gamma emitting radionuclides and tritium concentrations in the Caisson Sump and gamma emitting 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 direct consumption 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 analysis are summarized in Table C-1 in the format of the BTP Table 3. None 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 Humboldt Hill was found powered off after running approximately 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months and 49 minutes on 4/25/2014. The beta MDA was determined to be 4.28E-02 pCi/m 3 instead of the required 1.OE-02 pCi/m 3 .

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.

TLD station T9 was moved approximately 10 ft. further away from the Discharge Canal on 9/15/2014. The TLD was relocated to prevent impeding future truck/vehicular traffic during demolition activities. Corrective action SAPN 1393975 describes the relocation and new GPS coordinates. Figures A-3 has been updated to reflect the change in location.

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 exception:

Humboldt Hill collected on 4/25/2014. The air sampler was found powered off after running for only 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months and 49 minutes, based on the instrument timer reading. The failure to provide continuous offsite air sample monitoring was described in corrective action SAPN 1388096. SAPN status is now closed.

The required quarterly composited samples were analyzed for Gamma Isotopic by station. All air sample results for alpha and beta activity, and quarterly composite results for Co-60 and Cs-137 are provided in Table C-7.

All LLD's were met for Gross Beta (required LLD 1.OE-02 pCi/m 3 ) and Cs-137 (required LLD of 6.OE-02 pCi/m 3 ). The only exception was the air sample taken from Humboldt Hill. The air sampler was discovered powered off after running only 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months and 49 minutes. The beta MDA was determined to be 4.28E-02 pCi/m 3 instead of the required 1.OE-02 pCi/m 3 .

4. Waterborne Pathway

a. Surface Water Surface water sampling of the waterborne pathway is no longer performed due to the termination of liquid effluent releases in December 2013.

b. Groundwater Groundwater sampling of the waterborne pathway is performed by sampling fourteen (14) monitoring wells located to monitor for leakage from the SFP.

Sampling of these monitoring wells is performed quarterly in accordance with plant procedures.

I The ground water monitoring program requirements were transferred 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-4.

The tritium concentration for all of the wells listed in Table C-4 during 2014 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, plant procedures do 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-4, 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.

During the second quarterly ground water monitoring well event, monitoring wells RCW-SFP-3, RW-CS-5, RCW-CS-6 and RCW-CS-7 were detected as containing sediments that required removal. Well maintenance to remove accumulated sediments in RCW-SFP-3, RCW-SFP-5, RCW-CS-6 and RCW-CS-7 was successfully completed on 9/3/2014. RW-CS-5 was inaccessible at that time due to demolition activities in the close proximity. Flushing of sediments from RW-CS-5 was accomplished on 2/18/2015. These actions have been documented in corrective action SAPN 1388694.

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-5, 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 in Table C-6, but are not considered part of the SAFSTOR REMP.

5. Ingestion Pathway Ingestion pathway monitoring is not required by the ODCM.

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 practicableto 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 criteriain the REMP as described in the ODCM/ODAM.

HBPP Response to 2.2:

There were no reports or notifications required to be generated in 2014 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 criteria in the licensee's existing REMP for 30-day reporting of offsite water sample results. Copies of 30-day reports for 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 2014 for groundwater results exceeding reporting/notification levels or significant onsite leaks/spills.

OBJECTIVE 2.4 ANNUAL REPORTING Document all on-site ground watersample results and a description of any significant on-site leaks/spills into groundwaterfor each calendaryear in the AREOR for REMP or the ARERR for the RETS as contained in the appropriatereportingprocedure, beginning with Calendaryear 2006.

HBPP Response to 2.4:

Onsite groundwater monitoring points are described and reported in this report as follows: MW-1 1, RCW-SFP-'1, RCW-SFP-2, RCW-SFP-3, RCW-SFP-4, RCW-SFP-5, RCW-SFP-6, RCW-CS-3, RCW-CS-5, RCW-CS-6, RCW-CS-7, RCW-CS-8, RCW-CS-9, RCW-CS-10, 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 2014.

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

8. Errata for Previous Years' Reports None.

TABLE A-1 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 location operation with 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 Groundwater 14 monitoring wells Quarterly Gross alpha and Gross beta radioactivity, Tritium and 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 Humboldt .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 Pollution 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 6.0 Drive

TABLE A-3 GEL PARTICIPATION - INTERLABORATORY CROSS-CHECK PROGRAM I Sample/ Radionuclide Sample Quarter Report GEL Reference Analysis Number 2014 Date Value Value (pCi/L) (pCi/L)

Gamma Water 1-131 E10849 1st 5/16/2014 9.24E+01 8.99E+01 Ce-141 E10849 1st 5/16/2014 8.19E+01 7.71E+01 Cr-51 E10849 1st 5/16/2014 3.32E+02 3.19E+02 Cs-134 E10849 1st 5/16/2014 1.27E+02 1.36E+02 Cs-137 E10849 1st 5/16/2014 1.69E+02 1.64E+02 Co-58 E10849 1st 5/16/2014 1.75E+02 1.74E+02 Mn-54 E10849 1st 5/16/2014 2.08E+02 1.93E+02 Fe-59 E10849 1st 5/16/2014 1.68E+02 1.42E+02 Zn-65 E10849 1st 5/16/2014 2.25E+02 2.10E+02 Co-60' E10849 1st 5/16/2014 2.31E+02 2.19E+02 Sample/ Radionuclide Sample Quarter Report GEL Reference Analysis Number 2014 Date Value Value (pCi/L) (pCi/L)

Milk Sr-89 E10847 1st 5/16/2014 9.14E+01 9.17E+01 Sr-90 E10847 1st 5/16/2014 1.27E+01 1.51E+01 1-131 210848 1st 5/16/2014 9.84E+01 9.85E+01 Ce-141 E10848 1st 5/16/2014 1.21E+02 1.19E+02 Cr-51 E10848 1st 5/16/2014 5.19E+02 4.91E+02 Cs-134 E10848 1st 5/16/2014 1.79E+02 2.1OE+02 Cs-137 E10848 1st 5/16/2014 2.55E+02 2.53E+02 Co-58 E10848 1st 5/16/2014 2.58E+02 2.68E+02 Mn-54 E10848 1st 5/16/2014 3.01E+02 2.97E+02 Fe-59 E10848 1st 5/16/2014 2.24E+02 2.19E+02 Zn-65 E10848 1st 5/16/2014 3.45E+02 3.23E+02 Co-60 E10848 1st 5/16/2014 3.39E+02 3.37E+02 Sample/ Radionuclide Sample Quarter Report GEL Reference Analysis Number 2014 Date Value Value

_ I (pCi) (pCi)

Cartridge 1-131 E10846 1st 5/16/2014 7.83E+01 7.52E+01 TABLE A-3 (Continued) r1=I DAITIrPIDATI'II - INTI=II ARnrAT()V rCP. n__. .C.wi 0 PA(-PAM IIATA Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2014 Date Value Value (pCi/L) (pCiIL)

Gamma Water 1-131 E10900 2nd 8/8/2014 1.13E+02 9.83E+01 1.15 Acceptable Ce-141 E10900 2nd 8/8/2014 1.52E+02 1.43E+02 1.06 Acceptable Cr-51 E10900 2nd 8/8/2014 3.62E+02 2.94E+02 1.23 Acceptable Cs-134 E10900 2nd 8/8/2014 1.69E+02 1.88E+02 0.90 Acceptable Cs-137 E10900 2nd 8/8/2014 1.48E+02 1.39E+02 1.06 Acceptable Co-58 E10900 2nd 8/8/2014 1.34E+02 1.30E+02 1.03 Acceptable Mn-54 E10900 2nd 8/8/2014 1.88E+02 1.80E+02 1.04 Acceptable Fe-59 E10900 2nd 8/8/2014 1.29E+02 1.19E+02 1.09 Acceptable Zn-65 E10900 2nd 8/8/2014 3.29E+02 2.93E+02 1.12 Acceptable Co-60 E10900 2nd 8/8/2014 2.74E+02 2.60E+02 1.05 Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2014 Date Value Value (pCilL) (pCilL)

Milk Sr-89 E10898 2nd 8/8/2014 9.84E+01 9.13E+01 1.08 Acceptable Sr-90 E10898 2nd 8/8/2014 1.44E+01 1.45E+01 0.99 Acceptable 1-131 E10899 2nd 8/8/2014 9.89E+01 9.09E+01 1.09 Acceptable Ce-141 E10899 2nd 8/8/2014 1.38E+02 1.24E+02 1.12 Acceptable Cr-51 E10899 2nd 8/8/2014 2.68E+02 2.53E+02 1.06 Acceptable Cs-134 E10899 2nd 8/8/2014 1.58E+02 1.62E+02 0.97 Acceptable Cs-137 E10899 2nd 8/8/2014 1.27E+02 1.20E+02 1.06 Acceptable Co-58 E10899 2nd 8/8/2014 1.20E+02 1.12E+02 1.07 Acceptable Mn-54 E10899 2nd 8/8/2014 1.67E+02 1.56E+02 1.07 Acceptable Fe-59 E10899 2nd 8/8/2014 1.02E+02 1.02E+02 1.00 Acceptable Zn-65 E10899 2nd 8/8/2014 2.68E+02 2.52E+02 1.06 Acceptable Co-60 E10899 2nd 8/8/2014 2.42E+02 2.24E+02 1.08 Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2014 Date Value Value I I I (pCi) (pCi)

Cartridge 1-131 E10897 2nd 8/8/2014 8.73E+01 8.54E+01 1.02 Acceptable TABLE A-3 (Continued)

£E=L PARTICIPATION - INTERLARORATORY CROSS-CHECK PRO(GRAM flATA Sample/ Radionuclide Sample Quarter Report Date GEL Reference Ratio Evaluation Analysis Number 2014 Value Value I (pCilL) (pCilL)

Gamma Water 1-131 E10996 3rd 11/22/2014 1.02E+02 9.88E+01 1.03 Acceptable Ce-141 E10996 3rd 11/22/2014 1.30E+02 1.25E+02 1.04 Acceptable Cr-51 E10996 3rd 11/22/2014 2.75E+02 2.86E+02 0.96 Acceptable Cs-134 E10996 3rd 11/22/2014 1.45E+02 1.56E+02 0.93 Acceptable Cs-137 E10996 3rd 11/22/2014 1.94E+02 1.92E+02 1.01 Acceptable Co-58 E10996 3rd 11/22/2014 1.43E+02 1.42E+02 1.01 Acceptable Mn-54 E10996 3rd 11/22/2014 1.46E+02 1.41 E+02 1.04 Acceptable Fe-59 E10996 3rd 11/22/2014 1.66E+02 1.57E+02 1.06 Acceptable Zn-65 E10996 3rd 11/22/2014 7.55E+01 7.24E+01 1.04 Acceptable Co-60 E10996 3rd 11/22/2014 3.09E+02 2.95E+02 1.05 Acceptable Sample/ Radionuclide Sample Quarter Report Date GEL Reference Ratio Evaluation Analysis Number 2014 Value Value (pCi/L) (pCiIL)

Milk Sr-89 E10994 3rd 11/22/2014 9.73E+01 9.69E+01 1 Acceptable Sr-90 E10994 3rd 11/22/2014 1.31E+01 1.64E+01 0.80 Acceptable 1-131 E10995 3rd 11/22/2014 1.04E+02 9.76E+01 1.07 Acceptable Ce-141 E10995 3rd 11/22/2014 1.28E+02 1.26E+02 1.01 Acceptable Cr-51 E10995 3rd 11/22/2014 3.12E+02 2.88E+02 1.08 Acceptable Cs-134 E10995 3rd 11/22/2014 1.51E+02 1.58E+02 0.96 Acceptable Cs-137 E10995 3rd 11/22/2014 2.03E+02 1.93E+02 1.05 Acceptable Co-58 E10995 3rd 11/22/2014 1.44E+02 1.43E+02 1.01 Acceptable Mn-54 E10995 3rd 11/22/2014 1.49E+02 1.42E+02 1.05 Acceptable Fe-59 E10995 3rd 11/22/2014 1.82E+02 1.58E+02 1.15 Acceptable Zn-65 E10995 3rd 11/22/2014 7.41E+01 7.30E+01 1.01 Acceptable Co-60 E10995 3rd 11/22/2014 3.14E+02 2.94E+02 1.06 Acceptable Sample/ Radionuclide Sample Quarter Report Date GEL Reference Ratio Evaluation Analysis Number 2014 Value Value L (pCi) (pCi)

Cartridge 1-131 E10993 3rd 11/22/2014 9.47E+01 8.99E+01 1.05 Acceptable NOTE: 2014 fourth quarter interlaboratory cross-check program data between GEL and Eckert & Ziegler had not been received by GEL as of the date of this report. 2014 fourth quarter data will be included in the 2015 REMP report.

TABLE A-4 HBPP PARTICIPATION - ECKERT & ZIEGLER INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2014 Date Count Value Room (pCi/L)

(pCi/L)

Gamma Water Ce-141 E10805 1st 4/2/2014 8.02E+01 7.71E+01 1.04 Acceptable Cr-51 E10805 1st 4/2/2014 3.33E+02 3.19E+02 1.05 Acceptable Cs-134 E10805 1st 4/2/2014 1.23E+02 1.36E+02 0.90 Acceptable Cs-137 E10805 1st 4/2/2014 1.67E+02 1.64E+02 1.02 Acceptable Co-58 E10805 1st 4/2/2014 1.66E+02 1.74E+02 0.96 Acceptable Mn-54 E10805 1st 4/2/2014 1.94E+02 1.93E+02 1.01 Acceptable Fe-59 E10805 1st 4/2/2014 1.29E+02 1.42E+02 0.91 Acceptable Zn-65 E10805 1st 4/2/2014 2.OOE+02 2.1OE+02 0.95 Acceptable Co-60 E10805 1st 4/2/2014 2.17E+02 2.19E+02 0.99 Acceptable Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2014 Date Count Value Room (pCi/g)

(pCi/g)

Gamma Soil Ce-141 E10806 1st 4/2/2014 1.84E-01 1.74E-01 1.06 Acceptable Cr-51 E10806 1st 4/2/2014 7.29E-01 7.18E-01 1.02 Acceptable Cs-134 E10806 1st 4/2/2014 3.09E-01 3.07E-01 1.01 Acceptable Cs-137 E10806 1st 4/2/2014 4.31E-01 4.51E-01 0.95 Acceptable Co-58 E10806 1st 4/2/2014 4.15E-01 3.92E-01 1.06 Acceptable Mn-54 E10806 1st 4/2/2014 4.48E-01 4.35E-01 1.03 Acceptable Fe-59 E10806 1st 4/2/2014 3.35E-01 3.20E-01 1.05 Acceptable.

Zn-65 E10806 1st 4/2/2014 4.96E-01 4.72E-01 1.05 Acceptable Co-60 E10806 1st 4/2/2014 4.84E-01 4.93E-01 0.98 Acceptable TABLE A-4 (Continued)

HBPP PARTICIPATION - ECKERT & ZIEGLER INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2014 Date Count Value (pCi)

Room (pCi)

Gamma Filter Ce-141 El 0933 2nd 7/11/2014 9.43E+01 8.70E+01 1.08 Acceptable Cr-51 E10933 2nd 7/11/2014 1.69E+02 1.78E+02 0.95 Acceptable Cs-134 E10933 2nd 7/11/2014 1.03E+02 1.14E+02 0.90 Acceptable Cs-137 E10933 2nd 7/11/2014 9.04E+01 8.43E+01 1.07 Acceptable Co-58 E10933 2nd 7/11/2014 8.18E+01 7.89E+01 1.04 Acceptable Mn-54 E10933 2nd 7/11/2014 1.23E+02 1.09E+02 1.12 Acceptable Fe-59 E10933 2nd 7/11/2014 7.87E+01 7.20E+01 1.09 Acceptable Zn-65 E10933 2nd 7/11/2014 1.83E+02 1.77E+02 1.03 Acceptable Co-60 E10933 2nd 7/11/2014 1.62E+02 1.58E+02 1.03 Acceptable Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2014 Date Count Value (pCi)

Room (pCi)

Alpha/Beta Alpha E10934 2nd 7/11/2014 3.28E+01 3.74E+01 0.88 Acceptable 1 Filter Beta E10934 2_ 7/11/2014 2.03E+02 2.01E+02 1.01 Acceptable Table A-4 Notes:

'Analysis results based on 10 minute count times for alpha and beta analysis on Protean SN 7109. Alpha filter cross checks normally performed on each Protean gas flow proportional counter at count times of 5 minutes, 10 minutes and 20 minutes for gross alpha. Beta filter cross checks normally performed on each Protean gas flow proportional counter at count times of 5 minutes and 10 minutes. The 5-minute gross alpha count performed on Protean SN 7109 did not meet the acceptance criteria as the analysis results appeared to be approximately 3% low. This discrepancy is documented in SAPN 1384606.

- 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 2014 Date Count Value Room (pCi/g)

(pCi/g)

Gamma Soil Ce-141 El1008 3rd 10/21/2014 2.OOE-01 1.86E-01 1.08 Acceptable Cr-51 El1008 3rd 10/21/2014 5.11E-01 4.25E-01 1.20 Not 2 Acceptable Cs-134 E11008 3rd 10/21/2014 2.35E-01 2.33E-01 1.01 Acceptable Cs-137 E11008 3rd 10/21/2014 3.86E-01 3.65E-01 1.06 Acceptable Co-58 E11008 3rd 10/21/2014 2.05E-01 2.11E-01 0.97 Acceptable Mn-54 E11008 3rd 10/21/2014 2.34E-01 2.09E-01 1.12 Acceptable Fe-59 E11008 3rd 10/21/2014 2.48E-01 2.33E-01 1.07 Acceptable Zn-65 E11008 3rd 10/21/2014 1.02E-01 1.08E-01 0.95 Acceptable Co-60 E11008 3rd 10/21/2014 4.479-01 4.38E-01 1.02 Acceptable Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2014 Date Count Value Room (pCi/L)

(pCi/L)

Tritium Water H-3 El1009 3rd 10/21/2014 9.97E+03 9.85E+03 1.01 Acceptable Table A-4 Notes:

2Cross checks for the third quarter were received on 9/10/2014 but not analyzed until 9/25/2014 due to work load constraints. Cr-51 has a 27.7 day half-life. Detectors 2, 3 and 5 displayed higher activities for Cr-51 than the E&Z reference value. Cr has one gamma line at 320.1 keV and at 0.425 pCi/g in soil; the Cr-51 nuclide in the cross check sample is only slightly above the system MDA. Cr-51 results for Detectors 2, 3 and 5 were reported as higher than the reference value, making the analysis decision conservative. Primary gamma radionuclides of concern for HBPP are Cs-1 37 at 661.66 keV (30.07 year half-life), Am-241 at 59.3 keV (432.2 year half-life) and Co-60 at 1173.2 and 1332.5 keV (5.27 year half-life). Short-lived radionuclides are no longer present following the plant's shutdown in 1976. Cr-51's one gamma line falls at a location on the efficiency curve where identification of expected HBPP radionuclides is not anticipated. All results for Cs-1 37 and Co-60 were determined as acceptable while the Cr-51 analysis results may be considered "high" but conservative. This discrepancy is documented in SAPN 1384606.

TABLE A-4 (Continued)

HBPP PARTICIPATION - ECKERT & ZIEGLER INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report Date HBPP Reference Ratio Evaluation Analysis Number 2014 Count Value (pCi)

Room (pCi)

Gamma Filter Ce-141 E11076 4th 12/18/2014 1.08E+02 1.07E+02 1.01 Acceptable Cr-51 E11076 4th 12/18/2014 1.94E+02 1.98E+02 0.98 Acceptable Cs-134 El1076 4th 12/18/2014 7.13E+01 8.02E+01 0.89 Acceptable Cs-137 E11076 4th 12/18/2014 9.50E+01 9.65E+01 0.98 Acceptable Co-58 E11076 4th 12/18/2014 6.08E+01 6.34E+01 0.96 Acceptable Mn-54 E11076 4th 12/18/2014 1.14E+02 1.1OE+02 1.04 Acceptable Fe-59 E11076 4th 12/18/2014 8.70E+01 8.51E+01 1.02 Acceptable Zn-65 E11076 4th 12/18/2014 1.60E+02 1.45E+02 1.11 Acceptable Co-60 El1076 4th 12/18/2014 1.14E+02 1.15E+02 1.00 Acceptable Sample/ Radionuclide Sample Quarter Report Date HBPP Reference Ratio Evaluation Analysis Number 2014 Count Value (pCi)

Room (pCi)

Alpha/Beta Alpha E11077 4th 12/18/2014 7.64E+01 7.13E+01 1.07 Acceptable Filter Beta E11077 4th 12/18/2014 2.47E+02 2.37E+02 1.04 Acceptable

- 22-

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, 2014

_Co _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]" Name Mean, Mean, Measure-(Fraction) (Fraction) ments

_ [Rangeib & [Range]b (52) samples per

Gross Beta East Fence (AMI) Annex Gross Alpha Humboldt Hill N/A AIRBORNE station 1.OOE-02 Gross Alpha (pCi/m3) mean 2.79E-03, (9/52), [2.02E-03 to 3.56E-03] (pCi/m3) mean (Station 3)

" Gross Beta, pCi/m3 Gross Beta (pCi/m3) mean 1.22E-02, (46/52), [3.51 E-03 to 3.76E-02] 3.1 OE-03, (4/52), Gross Alpha Particulates o Gross Alpha Building 12 (AM2) [2.38E-03 to (pCi/m3) mean

" Gamma

Gamma Gross Alpha (pCi/m3) mean 2.93E-03, (10/52), [2.38E-03 to 4.28E-03] 4.15E-03] 2.38E-03,

[pCi/m3] Isotopic Isotopic Gross Beta (pCi/m3) mean 1.19E-02, (48/52), [3.55E-03 to 3.87E-02] (3/52),

analysis on analysis on Annex (AM3) East Gross Beta [2.36E-03 to quarterly quarterly Gross Alpha (pCi/m3) mean 3.10E-03, (4/52), [2.38E-03 to 4.15E-03] Fence (pCi/m3) mean 2.43E-03]

composite (by composite Gross Beta (pCi/m3) mean 1.04E-02, (44/52), [3.47E-03 to 3.39E-02] 1.22E-02, station) (by station) Relay Building (AM4) (46/52), Gross Beta Gross Alpha (pCi/m3) mean 2.97E-03, (6/52), [2.36E-03 to 4.76E-03] [3.51 E-03 to (pCi/m3) mean (5) Onsite Cs-137 Gross Beta (pCi/m3) mean 1.13E-02, (40/52), [4.24E-03 to 3.28E-02] 3.76E-02] 1.04E-02, Locations

Cs-13 Oil Water Separator (OWS - AM5) (34/52),

(1) Offsite 6.E-02 Gross Alpha (pCi/m3) mean 2.71 E-03, (7/52), [2.34E-03 to 3.04E-03] Cs-1 37 <MDA [3.47E-03 to Locations pCi/m3 Gross Beta (pCi/m3) mean 1.13E-02, (47/52), [4.14E-03 to 3.73E-02] 2.77E-02]

(80) Fence line 5 mRem Fence Line TLDs (T1 to TI6 and T18 to T21) Station T19 (mR/qtr) Stations 1, 2, 0 DIRECT TLD readings 14.4 +/- 0.1, (80/80), [12.3 to 16.4] T-19, mean 14, 25 and T17 RADIATION Figure 15.7 +/- 0.4, (mR/qtr) mean

[mR/quarter] (20) Off-site TLD B-1 (1/4), [15.2 to 13.9 +/- 0.1,

[ aReadings 16.4] (20/20),

[13.0-16.1]

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, b & [Range] b Measurements Gamma isotopic Co-60:15 pCi/L Co-60 Cs-1 37 Co-60 Cs-1 37 Co-60 Cs-1 37 Co-60 Cs-137 0 WATERBORNE (56) Cs-1 37:18 pCi/L Groundwater <MDA <MDA N/A N/A <MDA <MDA N/A N/A (Monitoring wells) (0/56) (0/56) (0/56) (0/56)

(N/A] [N/A] [N/A] [N/A]

[pCi/L]

Tritium(56) ODCM: 2.0E+03 <MDA, (0/56), [N/A] N/A <MDA, (0/56), [N/A] N/A 0 pCi/L

Plant Policy-400 SedimentWater Drinking Not Required N/A N/A N/A N/A Not Required N/A Not Required N/A 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 Not Required N/A N/A N/A N/A Not Required N/A 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 priori (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 values for the radionuclide specific analyses were 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 to 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 Plan (now identified as the Post Shutdown Decommissioning Activities Report and Defueled Safety Analysis Report).

N/A - Not applicable TABLE C-2 ONSITE ENVIRONMENTAL TLD STATIONS Station TLD Exposure Measurements (mR)

Number First Quarter Second Quarter Third Quarter Fourth Quarter TI 16.0 +/- 0.3 14.7 +/- 0.3 14.8 +/- 0.2 15.8 +/- 0.2 T2 15.1 +/- 0.4 14.6 +/- 0.3 13.6 +/- 0.2 14.2 +/- 0.2 T3 14.6 +/- 0.3 13.7 +/- 0.3 13.8 +/- 0.2 14.2 +/- 0.3 T4 15.2 +/- 0.3 14.2 +/- 0.2 14.2 +/- 0.2 14.9 +/- 0.3 T5 14.5 +/- 0.4 13.8 +/- 0.2 13.7 +/- 0.2 14.3 +/- 0.2 T6 13.9 +/- 0.5 12.9 +/- 0.2 12.3 +/- 0.2 13.4 +/- 0.2 T7 15.1 +/- 0.4 13.5 +/- 0.1 13.1 +/- 0.2 14.0 +/- 0.4 T8 14.2 +/- 0.2 13.0 +/- 0.2 12.6 +/- 0.2 13.2 +/- 0.3 T9 14.9 +/- 0.4 14.1 +/- 0.2 13.9 +/- 0.2 15.0 +/- 0.2 TIO 13.8 +/- 0.3 13.5+/- 0.3 13.3 +/- 0.1 13.8 +/- 0.2 T11 14.2 +/- 0.3 13.9 +/- 0.3 13.7 +/- 0.2 14.5 +/- 0.2 T12 14.7 +/- 0.3 14.3 +/- 0.3 14.2 +/- 0.2 14.7 +/- 0.3 T13 14.6 +/- 0.3 14.2 +/- 0.3 14.2 +/- 0.1 14.6 +/- 0.2 T14 15.4 +/- 0.3 14.5 +/- 0.1 14.7 +/- 0.2 15.1 +/- 0.4 T15 14.0 +/- 0.1 13.8 +/- 0.3 13.8 +/- 0.2 14.1 +/- 0.3 T16 13.2 +/- 0.3 13.4 +/- 0.3 12.9 +/- 0.2 13.5 +/- 0.3 T18 16.0 +/- 0.4 15.2 +/- 0.1 15.0 +/- 0.2 15.0 +/- 0.4 T19 15.8 +/- 0.2 15.2 +/- 0.4 15.2 +/- 0.2 16.4 +/- 0.3 T20 15.7 +/- 0.4 14.8 +/- 0.1 14.8 +/- 0.3 15.8 +/- 0.3 T21 14.8 +/- 0.3 14.7 +/- 0.2 15.1 +/- 1.1 15.0 +/- 0.2 Calculated Parameters (mR)

Parameter First Quarter Second Quarter Third Quarter Fourth Quarter Average 14.8 +/- 0.1 14.1 +/- 0.1 13.9 +/- 0.1 14.6

+ 0.1 Maximum 16.0 +/- 0.4 15.2 +/- 0.4 15.2 +/- 0.2 16.4 +/- 0.3 Table C-2 Notes:

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

- 25 -

TABLE C-3 OFFSITE (Control) ENVIRONMENTAL TLD STATIONS Station TLD Exposure Measurements (mR)

Number First Quarter Second Quarter Third Quarter Fourth Quarter 1 14.4 +/- 0.4 13.5 +/- 0.3 13.5 +/- 0.2 14.1 +/- 0.3 2 15.7 +/- 0.4 15.1 +/- 0.3 14.8 +/- 0.3 16.1 +/- 0.2 14 13.6 +/- 0.5 12.7 +/- 0.2 12.8 +/- 0.1 13.0 +/- 0.2 25 14.0 +/- 0.4 13.3 +/- 0.2 12.7 +/- 0.2 13.3 +/- 0.1 T17 13.4 +/- 0.6 13.0 +/- 0.2 12.9 +/- 0.2 13.2 +/- 0.3 Calculated Parameters (mR)

Parameter First Quarter Second Quarter Third Quarter Fourth Quarter Average 14.2 +/- 0.2 13.5 +/- 0.1 13.3 +/- 0.1 13.9 +/- 0.1 Maximum 15.7 +/- 0.4 15.1 +/- 0.3 14.8 +/- 0.3 16.1 +/- 0.2 Table C-3 Notes:

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

-26 -

TABLE C-4 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-137 Co-60 MW-11* 2/12/2014 < 14.7 (MDA) < 6.58 (MDA) < 4.63 (MDA) < 5.60 (MDA) < 328 (MDA)

RCW-SFP-I* 2/12/2014 < 2.45 (MDA) < 1.32 (MDA) < 4.52 (MDA) < 3.90 (MDA) < 341 (MDA)

RCW-SFP-2* 2/12/2014 < 5.07 (MDA) 12.3 +/- 3.88 < 4.05 (MDA) < 4.41 (MDA) <.328 (MDA)

RCW-SFP-3* 2/12/2014 < 4.78 (MDA) 6.04 +/- 2.01 < 6.28 (MDA) < 4.99 (MDA) < 342 (MDA)

RCW-SFP-4* 2/12/2014 < 4.54 (MDA) 4.16 +/- 1.43 < 6.75 (MDA) < 6.14 (MDA) < 336 (MDA)

RCW-SFP-5* 2/12/2014 < 4.04 (MDA) < 4.90 (MDA) < 4.58 (MDA) < 4.40 (MDA) < 335 (MDA)

RCW-SFP-6* 2/12/2014 < 15.3 (MDA) < 8.37 (MDA)' < 3.99 (MDA) < 4.29 (MDA) < 332 (MDA)

RCW-CS-3* 2/12/2014 < 2.58 (MDA) 1.74 +/- 0.96 < 4.87 (MDA) < 5.78 (MDA) < 332 (MDA)

RCW-CS-5* 2/12/2014 < 2.27 (MDA) 3.04 +/- 1.09 < 4.86 (MDA) < 2.91 (MDA) < 333 (MDA)

RCW-CS-6* 2/12/2014 < 71.8 (MDA) < 71.2 (MDA) < 3.82 (MDA) < 3.90 (MDA) < 334 (MDA)

RCW-CS-7* 2/12/2014 < 95.0 (MDA) < 82.5 (MDA) < 4.67 (MDA) < 4.99 (MDA) < 342 (MDA)

RCW-CS-8* 2/12/2014 < 93.7 (MDA) < 93.3 (MDA) < 5.71 (MDA) < 7.00 (MDA) < 344 (MDA)

RCW-CS-9* 2/12/2014 < 23.3 (MDA) < 19.6 (MDA) < 4.42 (MDA) < 3.69 (MDA) < 346 (MDA)

RCW-CS-10* 2/12/2014 < 15.1 (MDA) < 12.2 (MDA) < 3.72 (MDA) < 4.14 (MDA) < 339 (MDA)

MW-11* 5/15/2014 < 18.7 (MDA) < 13.2 (MDA) < 5.58 (MDA) < 4.72 (MDA) < 245 (MDA)

RCW-SFP-I* 5/15/2014 < 3.46 (MDA) < 3.28 (MDA) < 4.63 (MDA) < 4.29 (MDA) < 243 (MDA)

RCW-SFP-2* 5/15/2014 < 10.8 (MDA) < 6.99 (MDA) < 4.17 (MDA) < 2.57 (MDA) < 243 (MDA)

RCW-SFP-3* 5/15/2014 < 6.22 (MDA) < 5.40 (MDA) < 3.94 (MDA) < 4.25 (MDA) < 247 (MDA)

RCW-SFP-4* 5/15/2014 < 4.16 (MDA) 3.75 +/- 1.50 < 3.72 (MDA) < 3.77 (MDA) < 253 (MDA)

RCW-SFP-5* 5/15/2014 < 6.45 (MDA) < 3.44 (MDA) < 4.93 (MDA) < 6.08 (MDA) < 242 (MDA)

RCW-SFP-6* 5/15/2014 < 14.2 (MDA) < 6.47 (MDA) < 4.38 (MDA) < 4.83 (MDA) < 244 (MDA)

RCW-CS-3* 5/1"5/2014 < 3.23 (MDA) < 2.80 (MDA) < 4.38 (MDA) < 4.21 (MDA) < 253 (MDA)

RCW-CS-5* 5/15/2014 < 3.08 (MDA) < 2.25 (MDA) < 4.04 (MDA) < 3.48 (MDA) <251 (MDA)

RCW-CS-6* 5/15/2014 < 60.3 (MDA) < 41.7 (MDA) < 4.34 (MDA) < 3.94 (MDA) < 244 (MDA)

RCW-CS-7* 5/15/2014 < 83.5 (MDA) < 57.5 (MDA) < 4.41 (MDA) < 4.69 (MDA) < 249 (MDA)

RCW-CS-8* 5/15/2014 < 105 (MDA) < 93.8 (MDA) < 5.35 (MDA) < 4.19 (MDA) < 264 (MDA)

RCW-CS-9* 5/15/2014 < 16.0 (MDA) < 19.3 (MDA) < 6.82 (MDA) <4.75 (MDA) < 242 (MDA)

RCW-CS-10* 5/15/2014 < 9.47 (MDA) < 14.3 (MDA) < 3.66 (MDA) < 4.53 (MDA) < 249 (MDA)

MW-11* 8/13/2014 < 15.2 (MDA) < 13.6 (MDA) < 3.82 (MDA) < 5.39 (MDA) < 309 (MDA)

RCW-SFP-I* 8/13/2014 < 3.43 (MDA) < 2.84 (MDA) < 5.19 (MDA) < 3.66 (MDA) < 315 (MDA)

RCW-SFP-2* 8/13/2014 < 21.2 (MDA) < 10.7 (MDA) < 3.31 (MDA) < 4.12 (MDA) < 324 (MDA)

RCW-SFP-3* 8/13/2014 < 10.3 (MDA) < 6.51 (MDA) < 5.38 (MDA) < 3.14 (MDA) < 314 (MDA)

RCW-SFP-4* 8/13/2014 < 4.66 (MDA) 4.53 +/- 2.07 < 4.41 (MDA) < 4.58 (MDA) < 302 (MDA)

RCW-SFP-5* 8/13/2014 < 5.62 (MDA) < 4.97 (MDA) < 5.40 (MDA) < 5.78 (MDA) < 313 (MDA)

RCW-SFP-6* 8/13/2014 < 16.8 (MDA) < 12.3 (MDA) < 5.20 (MDA) < 4.60 (MDA) < 321 (MDA)

RCW-CS-3* 8/13/2014 < 3.18 (MDA) < 3.33 (MDA) < 5.10 (MDA) < 5.80 (MDA) < 318 (MDA)

RCW-CS-5* 8/13/2014 < 2.76 (MDA) < 2.33 (MDA) < 4.32 (MDA) < 4.66 (MDA) < 323 (MDA)

RCW-CS-6* 8/13/2014 < 96.0 (MDA) < 58.5 (MDA) < 3.58 (MDA) < 3.62 (MDA) < 316 (MDA)

RCW-CS-7* 8/13/2014 < 129 (MDA) < 78.1 (MDA) < 5.39 (MDA) < 6.68 (MDA) < 324 (MDA)

RCW-CS-8* 8/13/2014 < 171 (MDA) < 111 (MDA) < 4.36 (MDA) < 2.46 (MDA) < 288 (MDA)

RCW-CS-9* 8/13/2014 < 32.5 (MDA) < 25.7 (MDA) < 5.18 (MDA) < 3.60 (MDA) < 318 (MDA)

RCW-CS-10* 8/13/2014 < 37.7 (MDA) < 23.1 (MDA) < 5.01 (MDA) < 5.27 (MDA) < 318 (MDA)

Indicates fourteen (14) groundwater monitoring wells.

TABLE C-4 (Continued)

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

Cs-1 37 Co-60 aW-11* 8/13/2014 < 20.1 (MDA) < 10.4 (MDA) < 4.84 (MDA) < 5.09 (MDA) < 324 (MDA)

RCW-SFP-I* 8/13/2014 < 2.55 (MDA) 1.89,+ 0.92 < 4.08 (MDA) < 4.20 (MDA) <322 MDA)

RCW-SFP-2* 8/13/2014 < 15.4 (MDA) < 13.2 (MDA) < 4.99 (MDA) < 5.58 (MDA) < 319 (MDA)

RCW-SFP-3* 8/13/2014 < 10.9 (MDA) < 6.60 (MDA) < 4.93 (MDA) < 5.52 (MDA) < 311 (MDA)

RCW-SFP-4* 8/13/2014 < 6.14 (MDA) 4.84 +/- 2.08 < 5.88 (MDA) < 7.85 (MDA) < 320 (MDA)

RCW-SFP-5* 8/13/2014 < 5.33 (MDA < 4.47 (MDA) < 4.31 (MDA) < 5.64 (MDA) < 321 (MDA)

RCW-SFP-6* 8/13/2014 < 17.8 (MDA) < 11.2 (MDA) < 5.05 (MDA) < 6.86 (MDA) < 315 (MDA)

RCW-CS-3* 8/13/2014 < 2.29 (MDA) < 1.97 (MDA) < 8.93 (MDA) < 7.41 (MDA) < 310 (MDA)

RCW-CS-5* 8/13/2014 < 2.12 (MDA) 3.19 +/- 1.29 < 6.69 (MDA) < 8.40 (MDA) < 318 (MDA)

RCW-CS-6* 8113/2014 < 144 (MDA) < 98.3 (MDA) < 7.08 (MDA) < 9.33 (MDA) < 313 (MDA)

RCW-CS-7* 8/13/2014 < 140 (MDA) < 70.3 (MDA) < 7.65 (MDA) < 4.89 (MDA) < 321 (MDA)

RCW-CS-8* 8/13/2014 < 218 (MDA) < 129 (MDA) < 6.65 (MDA) < 8.23 (MDA) < 320 (MDA)

RCW-CS-9* 8/13/2014 < 34.3 (MDA) < 26.4 (MDA) < 6.95 (MDA) < 4.70 (MDA) < 324 (MDA)

RCW-CS-10* 8/13/2014 < 25.4 (MDA) < 18.0 (MDA) < 7.88 (MDA) < 6.49 (MDA) < 319 (MDA)

Indicates (14) groundwater monitoring wells.

TABLE C-4 (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-137 Co-60 Average: MW-1I Note 4 Note 4 Note 4 Note 4 Note 4 Average: RCW-SFP-l* Note 4 1.89 +/- 0.92 Note 4 Note 4 Note 4 Average: RCW-SFP-2* Note 4 12.3 +/- 3.88 Note 4 Note 4 Note 4 Average: RCW-SFP-3* Note 4 6.04 +/- 2.01 Note 4 Note 4 Note 4 Average: RCW-SFP-4* Note 4 4.32 +/- 0.90 Note 4 Note 4 Note 4 Average: RCW-SFP-5* Note 4 Note 4 Note 4 Note 4 Note 4 Average: RCW-SFP-6* Note 4 Note 4 Note 4 Note 4 Note 4 Average: RCW-CS-3* Note 4 1.74 +/- 0.96 Note 4 Note 4 Note 4 Average: RCW-CS-5* Note 4 3.12 +/- 0.84 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-CS-10* Note 4 Note 4 Note 4 Note 4 Note 4 Maximum: MW-1I Note 4 Note 4 Note 4 Note 4 Note 4 Maximum: RCW-SFP-I*. Note 4 1.89 +/- 0.92 Note 4 Note 4 Note 4 Maximum: RCW-SFP-2* Note 4 12.3 +/- 3.88 Note 4 Note 4 Note 4 Maximum: RCW-SFP-3* Note 4 6.04 +/- 2.01 Note 4 Note 4 Note 4 Maximum: RCW-SFP-4* Note 4 4.84 +/- 2.08 Note 4 Note 4 Note 4 Maximum: RCW-SFP-5* Note 4 Note 4 Note 4 Note 4 Note 4 Maximum: RCW-SFP-6* Note 4 Note 4 Note 4 Note 4 Note 4 Maximum: RCW-CS-3* Note 4 1.74 +/- 0.96 Note 4 Note 4 Note 4 Maximum: RCW-CS-5* Note 4 3.19 +/- 1.29 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-CS-10* Note 4 Note 4 Note 4 Note 4 Note 4

Indicates (14) groundwater monitoring wells.

Table C-4 Notes:

1. Reported values are net measurements (above instrument background). The normal minimum detectable activities (MDAs) for the analyses for gross alpha, gross 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 maximum lower 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 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.

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

TABLE C-5 CAISSON SUMP MONITORING RESULTS Sample Cs-1 37 Activity Co-60 Activity Tritium Activity Date (pCi/L) (pCi/L) (pCi/L) 1/29/2014 <MDA 42.0 +/- 7.1 1030 400 2/25/2014 <MDA <MDA 650 + 380 3/19/2014 <MDA <MDA < 630 (MDA) 4/1412014 <MDA <MDA 690 +/- 380 5/23/2014 <MDA <MDA < 630 (MDA) 6/20/2014 <MDA <MDA < 630 (MDA) 7/18/2014 <MDA <MDA < 620 (MDA) 8/15/2014 <MDA <MDA < 620 (MDA) 9/12/2014 <MDA <MDA < 620 (MDA) 10/24/2014 <MDA <MDA < 630 (MDA) 11/13/2014 <MDA <MDA < 630 (MDA) 12/10/2014 <MDA <MDA < 660 (MDA)

Table C-5 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-6 FRENCH DRAIN MONITORING RESULTS Sample Cs-137 Activity Co-60 Activity Tritium Activity Date (pCi/L) (pCi/L) (pCi/L) 11812014 217 +/- 23 <MDA < 640 (MDA) 2/5/2014 228 +/- 24 <MDA 1050 +/- 400 3/19/2014 275 +/- 26 <MDA < 630 (MDA) 411412014 269 +/- 26 <MDA < 630 (MDA) 512312014 285 +/- 28 <MDA < 630 (MDA) 6120/2014 309 +/- 28 <MDA < 630 (MDA) 7/18/2014 294 +/- 29 <MDA 810 +/- 380 8/15/2014 326 +/- 31 <MDA < 620 (MDA) 9/12/2014 306 +/- 30 <MDA 780 +/- 380 10/24/2014 300 +/- 29 <MDA 2,500 +/- 430 11/7/2014 278 +/- 27 <MDA 5,890 +/- 440 11/13/2014 272 +/- 26 <MDA 5,040 +/- 470 11/20/2014 250 +/- 24 <MDA 5,810 +/- 480 11/25/2014 264 +/- 27 <MDA 5,140 +/- 490 1214/2014 247 +/-25 <MDA 6,320 +/- 480 12/10/2014 251 +/- 26 <MDA 5,700 +/- 490 12/18/2014 245 +/- 26 <MDA 6,590 +/- 490 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".

Table C-7 ODCM REQUIRED AIR SAMPLES: EAST FENCE (AM1)

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

_ __ ___ __ ___ __ ___ ___ __ Co-60 Cs-I137

< 3.47E-03 (MDA) 1.26E-02 +/- 4.29E-03 1/2/2014 1/9/2014 < 3.38E-03 (MDA) 1.23E-02 +/- 4.18E-03 1/16/2014 2.91 E-03 +/- 2.09E-03 2.21 E-02 +/- 5.11E-03 1/23/2014 3.56E-03 +/- 2.34E-03 3.35E-02 +/- 6.14E-03 1/30/2014 < 3.43E-03 (MDA) 9.29E-03 +/- 3.85E-03 2/6/2014 < 3.32E-03 (MDA) 5.52E-03 +/- 3.25E-03 <6.71 E-04 <6.57E-04 2/13/2014 < 3.36E-03 (MDA) < 6.05E-03 (MDA) (MDA) (MDA) 2/20/2014 < 3.42E-03 (MDA) 1.10E-02 +/- 4.05E-03 2/27/2014 < 3.39E-03 (MDA) 3.52E-03 +/- 3.01 E-03 3/6/2014 < 3.32E-03 (MDA) 8.30E-03 +/- 3.64E-03 3/13/2014 < 3.40E-03 (MDA) 6.02E-03 +/- 3.39E-03 3/20/2014 < 3.33E-03 (MDA) 8.33E-03 +/-3.65E-03 3/27/2014 < 3.41 E-03 (MDA) 7.45E-03 +/- 3.59E-03 4/3/2014 2.35E-03 +/- 1.88E-03 6.97E-03 +/- 3.47E-03 4/10/2014 2.39E-03 +/- 1.91 E-03 1.38E-02 +/- 4.37E-03 4/17/2014 < 3.32E-03 (MDA) 8.64E-03 +/- 3.69E-03 4/24/2014 < 3.41 E-03 (MDA) 8.52E-03 +/- 3.74E-03 5/1/2014 < 3.33E-03 (MDA) 1.07E-02 +/- 3.94E-03 5/8/2014 < 3.44E-03 (MDA) 3.76E-02 +/- 6.51 E-03 <7.22E-04 <6.37E-04 5/15/2014 < 3.26E-03 (MDA) 1.12E-02 +/- 3.95E-03 (MDA) (MDA) 5/22/2014 < 3.48E-03 (MDA) 3.26E-02 +/- 6.16E-03 M 5/29/2014 < 3.35E-03 (MDA) 7.31 E-03 +/- 3.53E-03 6/5/2014 < 3.38E-03 (MDA) 3.51 E-03 +/- 3.OOE-03 6/12/2014 < 3.33E-03 (MDA) < 5.99E-03 (MDA) 6/19/2014 < 3.41 E-03 (MDA) 2.49E-02 +/- 5.44E-03 6/26/2014 < 3.31 E-03 (MDA) < 5.96E-03 (MDA) 7/3/2014 < 3.43E-03 (MDA) < 6.17E-03 (MDA) 7/10/2014 < 3.38E-03 (MDA) 5.27E-03 +/- 3.26E-03 7/17/2014 < 3.37E-03 (MDA) < 6.07E-03 (MDA) 7/24/2014 < 3.32E-03 (MDA) 5.52E-03 +/- 3.25E-03 7/31/2014 < 3.37E-03 (MDA) 5.26E-03 +/- 3.26E-03 8/7/2014 < 3.38E-03 (MDA) 7.74E-03 +/- 3.61 E-03 <9.38E-04 <6.52E-04 8114/2014 < 3.42E-03 (MDA) 8.18E-03 +/- 3.69E-03 (MDA) (MDA) 8/21/2014 < 3.33E-03 (MDA) 4.49E-03 +/- 3.11E-03 8/28/2014 < 3.40E-03 (MDA) 1.31 E-02 +/- 4.28E-03 9/4/2014 < 3.26E-03 (MDA) 1.43E-02 +/- 4.29E-03 9/11/2014 2.96E-03 +/- 2.13E-03 1.48E-02 +/- 4.43E-03 9/18/2014 < 3.34E-03 (MDA) 1.39E-02 +/- 4.32E-03 9/25/2014 < 3.48E-03 (MDA) 1.49E-02 +/- 4.54E-03 10/2/2014 2.98E-03 +/- 2.06E-03 2.71E-02 +/- 5.57E-03 10/9/2014 3.04E-03 +/- 2.19E-03 5.76E-03 +/- 3.39E-03 10/16/2014 < 3.22E-03 (MDA) 5.69E-03 +/- 3.21E-03 10/23/2014 < 3.53E-03 (MDA) 9.55E-03 +/- 3.96E-03 10/30/2014 < 3.37E-03 (MDA) 1.48E-02 +/- 4.43E-03 11/6/2014 < 3.36E-03 (MDA) 1.92E-02 +/- 4.88E-03 <8.55E-04 <9.13E-04 11/13/2014 2.89E-03 +/- 2.08E-03 1.62E-02 +/- 4.53E-03 11/20/2014 < 4.07E-03 (MDA) 4.65E-03 +/- 3.67E-03 (MDA) (MDA) 11/26/2014 2.02E-03 +/- 1.62E-03 1.29E-02 +/- 3.82E-03 12/4/2014 < 3.42E-03 (MDA) 1.32E-02 +/- 4.30E-03 12/11/2014 < 3.36E-03 (MDA) < 6.05E-03 (MDA) 12/18/2014 < 4.01 E-03 (MDA) 9.61 E-03 +/- 4.33E-03 12/24/2014 < 3.93E-03 (MDA) 7.35E-03 +/- 3.97E-03 Table C-7 (Continued)

ODCM REQUIRED AIR SAMPLES: BUILDING 12 (AM2)

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

Co-60 Cs-1 37 1/2/2014 2.43E-03 +/- 1.95E-03 2.78E-02 +/- 5.77E-03 1/9/2014 < 3.40E-03 (MDA) 1.81 E-02 +/- 4.81 E-03 1/16/2014 < 3.30E-03 (MDA) 3.51 E-02 +/- 6.18E-03 1/23/2014 < 3.14E-03 (MDA) 3.87E-02 +/- 6.27E-03 113012014 3.01 E-03 +/- 2.17E-03 7.14E-03 +/- 3.56E-03 2/6/2014 < 3.31 E-03 (MDA) < 5.96E-03 (MDA) < 8.90E-04 < 4.43E-04 2/13/2014 < 3.36E-03 (MDA) < 6.05E-03 (MDA) (MDA) (MDA) 2/20/2014 2.40E-03 +/- 1.92E-03 1.78E-02 +/- 4.79E-03 2/27/2014 < 3.39E-03 (MDA) 3.88E-03 +/- 3.06E-03 3/6/2014 < 3.32E-03 (MDA) 7.61 E-03 +/- 3.55E-03 3/13/2014 2.38E-03 +/- 1.91 E-03 8.84E-03 +/- 3.78E-03 3/20/2014 < 3.35E-03 (MDA) 1.57E-02 +/- 4.52E-03 3/27/2014 < 3.41 E-03 (MDA) 7.10E-03 +/- 3.54E-03 4/3/2014 < 3.34E-03 (MDA) 8.69E-03 +/- 3.71 E-03 4/10/2014 < 3.41 E-03 (MDA) 6.04E-03 +/- 3.40E-03 4/17/2014 < 3.31 E-03 (MDA) 1.21 E-02 +/- 4.1OE-03 4/24/2014 < 3.42E-03 (MDA) 1.10E-02 +/- 4.05E-03 5/1/2014 < 3.32E-03 (MDA) 1.21 E-02 +/- 4.1 OE-03 5/8/2014 < 3.44E-03 (MDA) 1.44E-02 +/- 4.46E-03 5/15/2014 < 3.26E-03 (MDA) 1.22E-02 +/- 4.06E-03 (MDA) (MDA) 5/22/2014 4.28E-03 +/- 2.60E-03 1.02E-02 +/- 4.OOE-03 (

5/29/2014 2.93E-03 +/- 2.11 E-03 1.25E-02 +/- 4.16E-03 6/5/2014 < 3.39E-03 (MDA) 2.76E-02 +/- 5.67E-03 6/12/2014 < 3.33E-03 (MDA) 5.19E-03 +/- 3.21 E-03 6/19/2014 < 3.43E-03 (MDA) 6.77E-03 +/- 3.52E-03 6/26/2014 < 3.30E-03 (MDA) < 5.94E-03 (MDA) 7/3/2014 < 3.42E-03 (MDA) 7.84E-03 +/- 3.66E-03 7/10/2014 < 3.38E-03 (MDA) 5.63E-03 +/- 3.32E-03 7/17/2014 < 3.37E-03 (MDA) 9.47E-03 +/- 3.83E-03 7/24/2014 < 3.32E-03 (MDA) 5.18E-03 +/- 3.20E-03 7/31/2014 < 3.40E-03 (MDA) 5.65E-03 +/- 3.33E-03 8/7/2014 .< 3.36E-03 (MDA) 9.09E-03 +/- 3.77E-03 8/14/2014 < 3.42E-03 (MDA) 3.55E-03 +/- 3.04E-03 <1.02E-03 <8.58E-04 8/21/2014 < 3.33E-03 (MDA) 5.88E-03 +/- 3.32E-03 (MDA) (MDA) 8/28/2014 < 3.39E-03 (MDA) 5.65E-03 +/- 3.33E-03 9/4/2014 < 3.26E-03 (MDA) 1.50E-02 +/- 4.36E-03 9/11/2014 < 3.37E-03 (MDA) 1.72E-02 +/- 4.70E-03 9/18/2014 < 3.34E-03 (MDA) 1.29E-02 +/- 4.19E-03 9/25/2014 3.05E-03 +/- 2.19E-03 1.34E-02 +/- 4.37E-03 10/2/2014 2.98E-03 +/- 2.07E-03 2.19E-02 +/- 5.12E-03 10/9/2014 < 3.46E-03 (MDA) 1.30E-02 +/- 4.32E-03 10/16/2014 < 3.22E-03 (MDA) 4.68E-03 +/- 3.05E-03 10/23/2014 < 3.56E-03 (MDA) 5.55E-03 +/- 3.43E-03 10/30/2014 < 3.35E-03 (MDA) 1.01 E-02 +/- 3.89E-03 11/6/2014 2.95E-03 +/- 2.12E-03 1.23E-02 +/- 4.16E-03 11/13/2014 2.89E-03 +/- 2.08E-03 1.71 E-02 +/- 4.62E-03 (84E0 <71E0 11/20/2014 < 4.10E-03 (MDA) 7.25E-03 +/- 4.09E-03 (MDA) (MDA) 11/26/2014 < 2.87E-03 (MDA) 1.23E-02 +/- 3.75E-03 12/4/2014 < 3.44E-03 (MDA) 7.15E-03 +/- 3.57E-03 12/11/2014 < 3.35E-03 (MDA) 5.92E-03 +/- 3.34E-03 12/18/2014 < 4.03E-03 (MDA) < 7.25E-03 (MDA) 12/24/2014 < 3.88E-03 (MDA) 1.01 E-02 +/- 4.31 E-03 Table C-7 (Continued)

ODCM REQUIRED AIR SAMPLES: ANNEX BUILDING (AM31 Sample Alpha Activity Beta Activity Composite Gamma Date (pCi/m 3) (pCi/m 3) Activity (pCi/m 3)

Co-60 Cs-I 37 1/2/2014 < 3.47E-03 (MDA) 1.95E-02 +/- 5.01 E-03 1/9/2014 < 3.38E-03 (MDA) 1.23E-02 +/- 4.18E-03 1/16/2014 < 3.30E-03 (MDA) 2.79E-02 +/- 5.60E-03 1/23/2014 4.15E-03 +/- 2.52E-03 3.39E-02 +/- 6.16E-03 1/30/2014 < 3.41 E-03 (MDA) 7.1OE-03 +/- 3.54E-03 2/6/2014 < 3.34E-03 (MDA) 3.47E-03 +/- 2.96E-03 <5.47E-04 <5.77E-04 2/13/2014 < 3.36E-03 (MDA) < 6.05E-03 (MDA) (MDA) (MDA) 2/20/2014 < 3.40E-03 (MDA) 1.38E-02 +/- 4.37E-03 2/27/2014 < 3.40E-03 (MDA) < 6.12E-03 (MDA) 3/6/2014 < 3.31 E-03 (MDA) 6.20E-03 +/- 3.35E-03 3/13/2014 2.38E-03 +/- 1.90E-03 9.54E-03 +/- 3.86E-03 3/20/2014 < 3.34E-03 (MDA) 1.11 E-02 +/- 4.01 E-03 3/27/2014 < 3.41 E-03 (MDA) 6.39E-03 +/- 3.45E-03 4/3/2014 < 3.35E-03 (MDA) 4.52E-03 +/- 3.13E-03 4/10/2014 < 3.40E-03 (MDA) 8.86E-03 +/- 3.78E-03 4/17/2014 < 3.33E-03 (MDA) 8.32E-03 +/- 3.65E-03 4/24/2014 < 3.41 E-03 (MDA) 9.94E-03 +/- 3.91 E-03 5/1/2014 2.93E-03 +/- 2.11 E-03 1.18E-02 +/- 4.07E-03 5/8/2014 < 3.42E-03 (MDA) 1.18E-02 +/- 4.14E-03 <7.44E-04 <7.34E-04 5/15/2014 < 3.27E-03 (MDA) 1.36E-02 +/- 4.22E-03 (MDA) (MDA) 5/22/2014 < 3.47E-03 (MDA) 6.87E-03 +/- 3.57E-03 5/29/2014 < 3.36E-03 (MDA) 1.15E-02 +/- 4.06E-03 6/5/2014 < 3.39E-03 (MDA) 3.52E-03 +/- 3.OOE-03 6/12/2014 < 3.33E-03 (MDA) 7.63E-03 +/- 3.56E-03 6/19/2014 < 3.41 E-03 (MDA) 5.67E-03 +/- 3.34E-03 6/26/2014 < 3.32E-03 (MDA) 4.83E-03 +/- 3.15E-03 7/3/2014 < 3.40E-03 (MDA) < 6.13E-03 (MDA) 7/10/2014 < 3.39E-03 (MDA) 4.59E-03 +/- 3.17E-03 7/17/2014 < 3.37E703 (MDA) < 6.06E-03 (MDA) 7/24/2014 < 3.35E-03 (MDA) 3.83E-03 +/- 3.02E-03 7/31/2014 < 3.33E-03 (MDA) < 5.99E-03 (MDA) 8/7/2014 < 3.40E-03 (MDA) 1.42E-02 +/- 4.39E-03 <6.52E-04 <1.10E-03 8/14/2014 < 3.41 E-03 (MDA) 3.54E-03 +/- 3.02E-03 (MDA) (MDA) 8/21/2014 2.92E-03 +/- 2.10E-03 6.23E-03 +/- 3.37E-03 8/28/2014 < 3.39E-03 (MDA) 1.10E-02 +/- 4.02E-03 9/4/2014 < 3.28E-03 (MDA) 1.26E-02 +/- 4.12E-03 9/11/2014 < 3.37E-03 (MDA) 1.76E-02 +/- 4.73E-03 9/18/2014 < 3.34E-03 (MDA) 1.36E-02 +/- 4.29E-03 9/25/2014 < 3.48E-03 (MDA) 9.06E-03 +/- 3.87E-03 10/2/2014 < 3.26E-03 (MDA) 2.04E-02 +/- 4.96E-03 10/9/2014 < 3.34E-03 (MDA) 9.02E-03 +/- 3.85E-03 10/16/2014 < 3.21 E-03 (MDA) 7.01 E-03 +/- 3.38E-03 10/23/2014 < 3.56E-03 (MDA) 1.15E-02 +/- 4.21E-03 10/30/2014 < 3.35E-03 (MDA) 5.92E-03 +/- 3.33E-03 11/6/2014 < 3.36E-03 (MDA) 1.30E-02 +/- 4.23E-03 <9.45E-04 <9.95E-04 11/13/2014 < 3.31 E-03 (MDA) 1.17E-02 +/- 4.03E-03 (MDA) (MDA) 11/20/2014 < 4.08E-03 (MDA) < 7.34E-03 (MDA) 11/26/2014 < 2.87E-03 (MDA) 1.01 E-02 +/- 3.50E-03 12/4/2014 < 3.43E-03 (MDA) 4.64E-03 +/- 3.20E-03 12/11/2014 < 3.37E-03 (MDA) < 6.06E-03 (MDA) 12/18/2014 < 4.OOE-03 (MDA) < 7.20E-03 (MDA) 12/24/2014 < 3.90E-03 (MDA) 8.52E-03 +/- 4.11 E-03 Table C-7 (Continued)

ODCM REQUIRED AIR SAMPLES: RELAY BUILDING (AM4)

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

Co-60 Cs-1 37 1/2/2014 < 3.47E-03 (MDA) 1.84E-02 +/- 4.90E-03 1/9/2014 < 3.38E-03 (MDA) 1.16E-02 +/- 4.09E-03 1/16/2014 < 3.30E-03 (MDA) 2.41 E-02 +/- 5.27E-03 1/23/2014 < 3.38E-03 (MDA) 3.28E-02 +/- 6.09E-03 1/30/2014 < 3.41 E-03 (MDA) < 6.14E-03 (MDA) 2/6/2014 < 3.34E-03 (MDA) < 6.01 E-03 (MDA) < 8.33E-04 < 6.90E-04 2/13/2014 < 3.36E-03 (MDA) < 6.05E-03 (MDA) (MDA) (MDA) 2/20/2014 < 3.40E-03 (MDA) 1.17E-02 +/- 4.12E-03 2/27/2014 < 3.40E-03 (MDA) 4.24E-03 +/- 3.12E-03 3/6/2014 < 3.31 E-03 (MDA) 7.58E-03 +/- 3.54E-03 3/13/2014 < 3.40E-03 (MDA) 6.36E-03 +/- 3.44E-03 3/20/2014 < 3.34E-03 (MDA) 9.05E-03 +/- 3.75E-03 3/27/2014 < 3.41E-03 (MDA) < 6.13E-03 (MDA) 4/3/2014 < 3.35E-03 (MDA) 6.27E-03 +/- 3.39E-03 4/10/2014 < 3.40E-03 (MDA) 9.57E-03 +/- 3.87E-03 4/17/2014 < 3.33E-03 (MDA) 9.70E-03 +/- 3.82E-03 4/24/2014 < 3.41 E-03 (MDA) 1.46E-02 +/- 4.44E-03 5/1/2014 < 3.34E-03 (MDA) 1.15E-02 +/- 4.04E-03 5/8/2014 2.40E-03 +/-.1.92E-03 7.48E-03 +/- 3.60E-03 < 6.51 E-04 < 6.26E-04 5/15/2014 < 3.27E-03 (MDA) 8.85E-03 +/- 3.67E-03 (MDA) (MDA) 5/22/2014 < 3.47E-03 (MDA) 1.26E-02 +/- 4.29E-03 5/29/2014 2.36E-03 +/- 1.89E-03 6.99E-03 +/- 3.49E-03 6/5/2014 < 3.39E-03 (MDA) 4.57E-03 +/- 3.16E-03 6/12/2014 < 3.33E-03 (MDA) < 6.OOE-03 (MDA) 6/19/2014 < 3.41 E-03 (MDA) < 6.14E-03 (MDA) 6/26/2014 < 3.32E-03 (MDA) < 5.97E-03 (MDA) 7/3/2014 < 3.41 E-03 (MDA) 6.03E-03 +/- 3.40E-03 7/10/2014 < 3.39E-03 (MDA) < 6.10E-03 (MDA) 7/17/2014 < 3.37E-03 (MDA) < 6.06E-03 (MDA) 7/24/2014 < 3.33E-03 (MDA) 4.50E-03 +/- 3.11 E-03 7/31/2014 < 3.36E-03 (MDA) 6.98E-03 +/- 3.48E-03 8/7/2014 < 3.39E-03 (MDA) 4.58E-03 +/- 3.17E-03 8/14/2014 < 3.41 E-03 (MDA) < 6.14E-03 (MDA) (MDA) (MDA) 8/21/2014 < 3.33E-03 (MDA) 7.62E-03 +/- 3.56E-03 8/28/2014 4.76E-03 +/- 2.74E-03 9.19E-03 +/- 3.81 E-03 9/4/2014 < 3.28E-03 (MDA) 1.13E-02 +/- 3.97E-03 9/11/2014 2.96E-03 +/- 2.13E-03 1.90E-02 +/- 4.87E-03 9/18/2014 < 3.34E-03 (MDA) 1.71 E-02 +/- 4.65E-03 9/25/2014 < 3.48E-03 (MDA) 1.27E-02 +/- 4.30E-03 10/2/2014 2.40E-03 +/- 1.83E-03. 2.32E-02 +/- 5.22E-03 10/9/2014 < 3.46E-03 (MDA) 1.01 E-02 +/- 3.97E-03 10/16/2014 < 3.21 E-03 (MDA) < 5.78E-03 (MDA) 10/23/2014 < 3.55E-03 (MDA) 1.30E-02 +/- 4.39E-03 10/30/2014 < 3.35E-03 (MDA) 9.06E-03 +/- 3.75E-03 11/6/2014 2.95E-03 +/- 2.12E-03 1.23E-02 +/- 4.16E-03 11/13/2014 < 3.31 E-03 (MDA) 1.48E-02 +/- 4.38E-03 (MDA) (MDA) 11/20/2014 < 4.08E-03 (MDA) 1.66E-02 +/- 5.23E-03 11/26/2014 < 2.86E-03 (MDA) 1.16E-02 +/- 3.67E-03 12/4/2014 < 3.43E-03 (MDA) 7.14E-03 +/- 3.56E-03 12/11/2014 < 3.37E-03 (MDA) < 6.06E-03 (MDA) 12/18/2014 < 4.OOE-03 (MDA) 7.91 E-03 +/- 4.11 E-03 12/24/2014 < 3.90E-03 (MDA) 1.14E-02 +/- 4.47E-03 Table C-7 (Continued)

ODCM REQUIRED AIR SAMPLES: OIL WATER SEPARATOR IAMSI Sample Alpha Activity Beta Activity Composite Gamma Date (pCi/m 3) (pCiIm 3) Activity (pCi/m 3)

Co-60 Cs-1 37 1/2/2014 3.04E-03 +/- 2.19E-03 2.71 E-02 +/- 5.70E-03 1/9/2014 2.97E-03 +/- 2.14E-03 1.62E-02 +/- 4.60E-03 1/16/2014 2.91 E-03 +/- 2.09E-03 3.73E-02 +/- 6.34E-03 1/23/2014 < 3.38E-03 (MDA) 3.60E-02 +/- 6.33E-03 1/30/2014 < 3.43E-03 (MDA) 6.07E-03 +/- 3.42E-03 2/6/2014 < 3.34E-03 (MDA) < 6.OOE-03 (MDA) < 7.58E-04 < 6.86E-04 2/13/2014 < 3.36E-03 (MDA) 7.70E-03 +/- 3.60E-03 (MDA) (MDA) 2/2012014 < 3.40E-03 (MDA) 1.45E-02 +/- 4.44E-03 2/27/2014 < 3.40E-03 (MDA) < 6.12E-03 (MDA) 3/6/2014 < 3.31 E-03 (MDA) 5.86E-03 +/- 3.30E-03 3/13/2014 < 3.40E-03 (MDA) 5.66E-03 +/- 3.33E-03 3/20/2014 < 3.12E-03 (MDA) 7.79E-03 +/- 3.41 E-03 3/27/2014 < 3.39E-03 (MDA) 4.58E-03 +/- 3.16E-03 4/3/2014 < 3.37E-03 (MDA) 7.37E-03 +/- 3.55E-03 4/10/2014 < 3.40E-03 (MDA) 1.06E-02 +/- 4.OOE-03 4/17/2014 < 3.33E-03 (MDA) 7.27E-03 +/- 3.51 E-03 4/24/2014 2.40E-03 +/- 1.92E-03 9.61 E-03 +/- 3.89E-03 5/1/2014 2.93E-03 +/- 2.11 E-03 1.78E-02 +/- 4.72E-03 5/8/2014 < 3.42E-03 (MDA) 1.14E-02 +/- 4.10E-03 5/15/2014 < 3.27E-03 (MDA) 1.46E-02 +/- 4.33E-03 -0(MDA) (MDA) 5/22/2014 < 3.47E-03 (MDA) 7.94E-03 +/- 3.71 E-03 5/29/2014 < 3.36E-03 (MDA) 6.99E-03 +/- 3.49E-03 6/5/2014 < 3.39E-03 (MDA) 5.28E-03 +/- 3.27E-03 6/12/2014 < 3.33E-03 (MDA) 5.89E-03 +/- 3.32E-03 6/19/2014 < 3.41 E-03 (MDA) 7.45E-03 +/- 3.59E-03 6/26/2014 < 3.32E-03 (MDA) 4.14E-03 +/- 3.05E-03 7/3/2014 < 3.41 E-03 (MDA) 8.52E-03 +/- 3.74E-03 7/10/2014 < 3.39E-03 (MDA) < 6.10E-03 (MDA) 7/17/2014 < 3.37E-03 (MDA) 6.30E-03 +/- 3.41 E-03 7/24/2014 < 3.33E-03 (MDA) < 5.99E-03 (MDA) 7/31/2014 2.36E-03 +/- 1.89E-03 8.74E-03 +/- 3.73E-03 8/7/2014 < 3.42E-03 (MDA) 7.82E-03 +/- 3.65E-03 8/14/2014 < 3.38E-03 (MDA) < 6.09E-03 (MDA) <8.23E-04 <7.57E-04 8/21/2014 < 3.33E-03 (MDA) 4.50E-03 +/- 3.11 E-03 (MDA) (MDA) 8/28/2014 < 3.39E-03 (MDA) 9.18E-03 +/- 3.80E-03 9/4/2014 < 3.28E-03 (MDA) 1.47E-02 +/- 4.34E-03 9/11/2014 < 3.37E-03 (MDA) 1.41 E-02 +/- 4.36E-03 9/18/2014 2.34E-03 +/- 1.87E-03 1.08E-02 +/- 3.95E-03 9/25/2014 < 3.48E-03 (MDA) 1.09E-02 +/- 4.08E-03 10/2/2014 < 3.34E-03 (MDA) 2.14E-02 +/- 5.06E-03 10/9/2014 < 3.46E-03 (MDA) 1.23E-02 +/- 4.23E-03 10/16/2014 < 3.22E-03 (MDA) 1.01 E-02 +/- 3.78E-03 10/23/2014 < 3.55E-03 (MDA) 9.60E-03 +/- 3.98E-03 10/30/2014 < 3.35E-03 (MDA) 4.52E-03 +/- 3.13E-03 11/6/2014 < 3.36E-03 (MDA) 1.61 E-02 +/- 4.58E-03 <8.44E-04 <1.10E-03 11/13/2014 < 3.31E-03 (MDA) 2.OOE-02 +/- 4.90E-03 (MDA) (MDA) 11/20/2014 < 4.08E-03 (MDA) 1.02E-02 +/- 4.47E-03 11/26/2014 < 2.86E-03 (MDA) 9.25E-03 +/- 3.39E-03 12/4/2014 < 3.43E-03 (MDA) 1.21 E-02 +/- 4.18E-03 12/11/2014 < 3.37E-03 (MDA) 6.31 E-03 +/- 3.41 E-03 12/18/2014 < 4.OOE-03 (MDA) 6.66E-03 +/- 3.92E-03 12/24/2014 < 3.90E-03 (MDA) 1.18E-02 +/- 4.54E-03 Table C-7 (Continued)

ODCM REQUIRED AIR SAMPLES: HUMBOLDT HILL (STATION 3)

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

_____ __ ___ __ __ ___ ___ __ ___ __ Co-60 Cs-I137

< 3.35E-03 (MDA) 1.71 E-02 +/- 4.66E-03 1/2/2014 1/9/2014 < 3.36E-03 (MDA) 9.81 E-03 +/- 3.86E-03 1/16/2014 < 3.38E-03 (MDA) 1.90E-02 +/- 4.89E-03 1/23/2014 2.36E-03 +/- 1.89E-03 2.77E-02 +/- 5.65E-03 1/30/2014 < 3.35E-03 (MDA) 3.47E-03 +/- 2.97E-03 2/6/2014 < 3.42E-03 (MDA) < 6.15E-03 (MDA) < 5.28E-04 < 7.75E-04 2/13/2014 < 3.39E-03 (MDA) < 6.10E-03 (MDA) (MDA) (MDA) 2/20/2014 < 3.36E-03 (MDA) 1.05E-02 +/- 3.95E-03 2/27/2014 < 3.33E-03 (MDA) 5.19E-03 +/- 3.21E-03 3/6/2014 < 3.41 E-03 (MDA) 7.45E-03 +/- 3.59E-03 3/13/2014 < 3.35E-03 (MDA) < 6.03E-03 (MDA) 3/20/2014 < 3.18E-03 (MDA) 6.95E-03 +/- 3.35E-03 3/27/2014 < 3.39E-03 (MDA) < 6.1OE-03 (MDA) 4/3/2014 < 3.34E-03 (MDA) 7.65E-03 +/- 3.57E-03 4/10/2014 < 3.40E-03 (MDA) < 6.12E-03 (MDA) 4/17/2014 < 3.29E-03 (MDA) 9.94E-03 +/- 3.83E-03 4/24/2014 < 2.38E-02 (MDA) < 4.28E-02 (MDA) 5/1/2014 < 3.28E-03 (MDA) 7.84E-03 +/- 3.54E-03 5/8/2014 < 3.49E-03 (MDA) 6.17E-03 +/- 3.48E-03 <6.48E-04 <6.52E-04 5/15/2014 < 3.25E-03 (MDA) 8.79E-03 +/- 3.64E-03 (MDA) (MDA) 5/22/2014 < 3.49E-03 (MDA) 6.54E-03 +/- 3.54E-03 5/29/2014 < 3.31 E-03 (MDA) 6.55E-03 +/- 3.40E-03 6/5/2014 < 3.45E-03 (MDA) < 6.21 E-03 (MDA) 6/12/2014 < 3.23E-03 (MDA) 2.09E-02 +/- 4.92E-03 6/19/2014 < 3.47E-03 (MDA) 5.41 E-03 +/- 3.35E-03 6/26/2014 < 3.40E-03 (MDA) 1.59E-02 +/- 4.59E-03 7/3/2014 < 3.40E-03 (MDA) < 6.11 E-03 (MDA) 7/10/2014 < 3.30E-03 (MDA) < 5.94E-03 (MDA) 7/17/2014 < 3.43E-03 (MDA) < 6.17E-03 (MDA) 7/24/2014 < 3.37E-03 (MDA) < 6.07E-03 (MDA) 7/31/2014 < 3.37E-03 (MDA) 4.20E-03 +/- 3.09E-03 8/7/2014 2.36E-03 +/- 1.89E-03 8.05E-03 +/- 3.63E-03 8/14/2014 < 3.38E-03 (MDA) <<6.08E-03 (MDA) 2< 6.13E-04 8/21/2014 < 3.36E-03 (MDA) < 6.04E-03 (MDA) (MDA) (MDA) 8/28/2014 < 3.40E-03 (MDA) < 6.12E-03 (MDA) 9/24/2014 < 3.22E-03 (MDA) 1.51 E-02 +/- 4.35E-03 9/11/2014 < 3.38E-03 (MDA) 1.16E-02 +/- 4.08E-03 9/18/2014 < 3.47E-03 (MDA) 6.85E-03 +/- 3.56E-03 9/25/2014 < 3.40E-03 (MDA) 7.08E-03 +/- 3.53E-03 10/2/2014 < 3.39E-03 (MDA) 1.30E-02 +/- 4.24E-03 10/9/2014 < 3.38E-03 (MDA) 1.13E-02 +/- 4.06E-03 10/16/2014 < 3.33E-03 (MDA) 6.92E-03 +/- 3.45E-03 10/23/2014 < 3.44E-03 (MDA) 1.22E-02 +/- 4.20E-03 10/30/2014 < 3.34E-03 (MDA) 1.18E-02 +/- 4.08E-03 11/6/2014 < 3.25E-03 (MDA) 1.42E-02 +/- 4.28E-03 <9.78E-04 <9.13E-04 11/13/2014 2.43E-03 +/- 1.94E-03 1.15E-02 +/- 4.15E-03 (MDA) (MDA) 11/20/2014 < 4.02E-03 (MDA) < 7.24E-03 (MDA) 11/26/2014 < 2.91 E-03 (MDA) 9.41 E-03 +/- 3.45E-03 12/4/2014 < 3.37E-03 (MDA) < 6.07E-03 (MDA) 12/11/2014 < 3.47E-03 (MDA) < 6.25E-03 (MDA) 12/18/2014 < 3.96E-03 (MOA) < 7.12E-03 (MDA) 12/24/2014 <3.84E-03 (MDA) 7.59E-03 +/- 3.94E-03 Table C-7 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-1 37.

2. All LLD's were met for Gross Beta (required LLD 1.OE-02 Ci/m 3) with the exception of the Humboldt Hill air sample collected on 4/25/2014. The air sample pump malfunctioned after running approximately 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months and 49 minutes. The beta MDA was determined to be 4.28E-02 pCi/m 3 instead of the required 1.OE-02 pCi/m 3 due to the low sample volume.

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 AM1. Building 12 is also known as AM2. Annex Building is also known as AM3. Relay Building is also known as AM4. Oil Water Separator (O.W.S.) is also known as AM5.

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, O.W.S. is also known as AM5.

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

GPS Coordinates (NAD83/NAVD88 CA. Zone 1)1 Degree.Decimal I F Easting 5951260.28 Northing 2155706.11 el.

234.94 Latitude 40.72676 Longitude

-124.20274 I FIGURE A-3 HBPP ONSITE TLD LOCATIONS Stations T1 - T21 (excluding T17)

LowAcM n GPS cQmadnek, A NVD[ CA AUM. 1) HPP (ceedaruth)

Number Eesft d. East Nth TI 5945161.06 2101822.11 1l078 4873.87 918.63 T2 5948804.62 21D710.72 11.50 4513.84 92MB.

"M3 9461]9.45 216111.84 41.77 454M.12 9006.91 14 5948778.72 216120D.91 43.L0 4705.13 975207 11 594901.39 2161308.44 38.19 6036.5 071372 "T 594915M22 2161437.55 36.30 ,&M05.77 9000.84 17 50402R=02 21614M4.61 32.04 5338.22 9600.36 78 54014.l199 2161008.30 1290 5M4.82 903g.33 "1 5094M ) 215152.00 11.19 56M1.27 9547.04 110 9M4012.89 2161&33.96 11.17 5945.05 9443.4 "11 5900-11.77 21615127.5 14.18 5846 g9107.30 912 5951019.25 2103M58.44 11.25 5814.80 57341 113 5940I0.53 2160718103 9.L9 5389.40 871240 314 5949003.8 2160094.24 11140 5154.63 882n(

M15 5944418.88 21000M).90 10.34 4995.90 8626.81

-1n 594 -2 2160007.18 11180 4951.10 8934.52 no 594B887.24 2161239.36 43.47 486Z90 9878.44 "10 5948"96.71 216124274 42.84 4795.52 9719.50 T20 5946747.14 2161191.08 44.14 4720.20 97M344 121 5948834.52 2161162.89 45.71 47W939 904452

-42 -

FIGURE A-4 HBPP OFFSITE TLD LOCATIONS Stations (1, 14 & 25)

GPS Coordinates (NAD83/NAVD88 CA. Zone 1) Degree.Decimal 0 Easting Northing el. Latitude Longitude 1 5948026.52 2161183.79 11.38 40.74156 -124.21903 U 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)1 Degree.Decimal 0 I Easting 5962583.86 I Northing 2105797.82 I el.

35.53 I Latitude.

40.59057 Longitude

-124.15746

-44 -

FIGURE A-4 (Continued)

HBPP OFFSITE TLD LOCATION EUREKA (Control Location T17)

I GPS Coordinates (NAD83/NAVD88 CA. Zone 1)1 Degree. Decimal

(Ž9 Easting 5976549.55

- Northing 2175490.19 el.

164.85 Latitude 40.78276 Longitude

-124.11324

-45 -

FIGURE A-5 HBPP GROUNDWATER SAMPLE POINTS

- -:~a> '- - I KEY T"o MoNrr'oRINGOI ff7FmBmim~

NIez.5 ffCW-SfP- I RCW-SFP-2 RCW-SFP-3 RCW-$fP-4 Asr-W-&P-5

"-cs-s Ti. -'

YCW-CS-o * *.~I, RC~W-CS-9 iRCW-CS- 10 EXPLANATION IS GOUADWWTR &0"M'R1A KU AOW- I LOCA MW AMV XWVG4 MWA

' OR

-Ti r.l-,

- R5WLTdR-CAliSON4:

J

~~1 PlAN 7I7 P~LAW y =gO Cr Ii~ir~ SI Xiooltild y ~crIAi 5irc-N a:I Iin i

P- . - -- "' - A ý- FIT *T,,' "*

Fig*.)TC "

-46 -

FIGURE B-1 OFFSITE ENVIRONMENTAL RADIATION LEVEL TRENDS 70.0 60.0 50.0 E

4) 40.0 E

30.0 U) 0 20.0 10.0 0.0-i 1

Year The baseline values s 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

-47 -

FIGURE B-2 ONSITE ENVIRONMENTAL RADIATION LEVEL TRENDS 70.0 60.0 -

50.0 -

E 40.0 -

E 30.0 -

0 20.0 -

. - - Stations Near Radwaste Activities (T5 through T8) 10.0 - -Other Onsite Stations (TI through T4 and T9 through T16)

-Stations Surrounding ISFSI (T18 through T21) 0.0

'1 Year 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.

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HBL-15-006, Annual Radiological Environmental Monitoring Report for 2014

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HBL-15-006, Annual Radiological Environmental Monitoring Report for 2014

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Dear Commissioners and Staff:

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