Text

Submittal of Annual Radiological Environmental Monitoring Report for 2016
	ML17117A683
Person / Time
Site:	Humboldt Bay
Issue date:	04/27/2017
From:	Sharp L; Pacific Gas & Electric Co
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
	HBL-17-009
	Download: ML17117A683 (53)
	v • d • e

Pacific Gas and Loren D. Sharp 735 Tank Farm Road EIB'CfTtc Company ~ Senior Director San Luis Obispo, CA 93401 Nuclear Decommissioning Phone: 805.595.6481 Email: LDSL@pge.com April 27, 2017 PG&E Letter HBL-17-009 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 2016

Dear Commissioners and Staff:

Enclosed is the Humboldt Bay Power Plant Unit 3, "Annual Radiological Environmental Monitoring Report" for 2016. 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 8 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. 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 Generic Letter 79-65, "Radiological Environmental Monitoring Program Requirements -

Enclosing Branch Technical Position," Revision 1, dated November 27, 1979.

There are no new or revised regulatory commitments (as defined in NEI 99-04) made in this letter.

Document Control Desk PG&E Letter HBL-17-009 April 27, 2017 Page2 If you have any questions regarding information in the enclosed report, please contact Mr. Philippe Soenen at (805) 595-6461.

Sincerely, D. Sharp Senior Director, Nuclear Decommissioning Enclosure cc: HBPP Humboldt Distribution cc/enc: John B. Hickman, NRC Project Manager Kriss M. Kennedy, NRC Region IV Administrator

Enclosure PG&E Letter HBL-17-009 HUMBOLDT BAY POWER PLANT UNIT 3 ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT JANUARY 1 THROUGH DECEMBER 31,2016

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

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

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

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

b. On site Environmental Monitoring ................................................................... 3

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

3. Interlaboratory Comparison Program .................................................................. 4

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

1. General Comments ............................................................................................. 5

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

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

4. Waterborne Pathway ........................................................................................... 7

a. Surface Water ................................................................................................ 7

b. Groundwater .................................................................................................. 7

5. Ingestion Pathway ............................................................................................... 7

6. Terrestrial Pathway .............................................................................................. 8 C. MONITORING RESULTS ......................................................................................... 8

1. Annual Summary ................................................................................................. 8

2. Direct Radiation Pathway .................................................................................... 8

3. Airborne Pathway ................................................................................................ 9

4. Waterborne Pathway ......................................................................................... 10

a. Surface Water .............................................................................................. 10

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TABLE OF CONTENTS (Continued)

b. Groundwater ................................................................................................ 10

5. Ingestion Pathway ............................................................................................. 12

6. Terrestrial Pathway ............................................................................................ 12

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 ...... ..

DATA ................................................................................................................... 16 A-4 HBPP PARTICIPATION- ECKERT & ZIEGLER INTERLABORATORY CROSS-CHECK PROGRAM DATA .................................................................................. 20 C-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL REPORT

SUMMARY

........................................................................................................... 23 C-2 ON SITE ENVIRONMENTAL TLD STATIONS ..................................................... 25 C-3 OFFSITE (Control) ENVIRONMENTAL TLD STATIONS ..................................... 26 C-4 GROUNDWATER MONITORING WELL RESULTS ............................................ 27 C-5 ODCM REQUIRED AIR SAMPLES ..................................................................... 31 LIST OF FIGURES Figure Page A-1 HBPP ONSITE AIR SAMPLE LOCATIONS ......................................................... 39 A-2 HBPP OFF SITE AIR SAMPLE LOCATION ......................................................... 40 A-3 HBPP ON SITE TLD LOCATIONS ........................................................................ 41 A-4 HBPP OFF SITE TLD LOCATIONS ...................................................................... 42 A-5 HBPP GROUNDWATER SAMPLE POINTS ........................................................ 45 B-1 OFFSITE ENVIRONMENTAL RADIATION LEVEL TRENDS .............................. 46 B-2 ONSITE ENVIRONMENTAL RADIATION LEVEL TRENDS ................................ 47

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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 31,2016 This annual report is required by Section 4.1 of the SAFSTOR Offsite Dose Calculation Manual (ODCM). This report provides information about the SAFSTOR Radiological Environmental Monitoring Program (REMP) for the period of January 1 through December 31, 2016, 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.~. 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-1, "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) offsite environmental air sampling station. The air sampler is run continuously and samples are analyzed weekly for Gross Beta and Gross Alpha activity. Station 3 satisfies this requirement as shown on Figure A-2. Quarterly the com posited 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 AM1 through AM5 as shown on Figure A-1. The air samplers are run continuously and samples are analyzed weekly for Gross Beta and Gross Alpha activity.

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

2. Direct Radiation The SAFSTOR ODCM requires 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 and have been transferred to the Diablo Canyon Power Plant (DCPP) Radiation Protection (RP) Program. This was documented in corrective action SAPN 1414743.

Each quarter the exposures from 16 stations are determined, which results in 64 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 regulated disposal facility. 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 OOCM 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.

A total of twelve (12) 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-11, 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 110ft.

and include RCW-CS-5, RCW-CS-6, RCW-CS-7, RCW-CS-8, RCW-CS-9 and RCW-CS-1 0. Wells are normally 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.

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 four sets of Eckert & Ziegler Analytics samples for 23 parameters that are representative of analyses performed for HBPP during 2016. All results met the acceptance criteria.

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

and gamma in water and tritium in water (3rd quarter). These analyses are representative of those performed by HBPP count room personnel during 2016.

All results met the acceptance criteria with the exception of the third quarter of gamma in water analyses which did not identify 1-131 at 364.5 keV, primarily because 1-131 does not normally appear within cross checks or the HBPP library.

The nuclide has an 8-day half-life and was discarded as an isotope of concern for HBPP several years ago. The problem was documented in corrective action SAPN 1413539.

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.

Based on the current progress of decommissioning at HBPP, plans are underway to phase out groundwater monitoring in 2017. Several stages of required well destruction are being planned to properly close out both active and retired monitoring wells.

B. TRENDS, BASELINE COMPARISONS AND INTERPRETATIONS Section 8 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.8.3, and IV.C.

Section 8 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 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 changes in the location of the unrestricted area 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 8-1, "OFFSITE ENVIRONMENTAL RADIATION LEVEL TRENDS." A plot of the radiation level trends for onsite stations is shown in Figure 8-2, "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.

H8PP changed TLD processing services beginning in January 2014. Data from previous years was based on a Panasonic TLD system. Data in 2014, 2015 and 2016 is based on Mirion Genesis type TLD system. The apparent rise in Figures 8-1 and 8-2 may be a result of the change in monitoring devices in tandem with the increase in decommissioning activities.

Figure 8-2 includes the average dose for two groups of onsite stations, selected by their potential to be affected by radioactive waste handling activities. Figure 8-2 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 in past years assumed an occupancy factor for the portion of the unrestricted area boundary that was closest to the radioactive waste handling area of the plant.

Fence line TLDs T5 through T8 adjacent to the waste handling area, were used to measure the location of the highest potential exposure to the public. In 2016, the radioactive waste handling area was relocated and direct radiation exposure pathway monitoring was provided by TLDs T8, T9 and T1 0. 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.

Using the maximum yearly dose, as seen on TLDs T18-T1 0, 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.

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 Liquid radioactive wastes are shipped for disposal to 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 twelve (12) 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.

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 the exception of one environmental gross beta air sample analysis which had a slightly higher MDA than the required LLD, primarily due to sampler malfunction and reduced run time.

Because alpha and~beta radtoactivity analyses of the saline ground water are less effective than tritium and gamma radioactivity analyses, 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 16 on site 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 on site and offsite monitoring are provided in Tables C-2 and C-3, respectively.

On 4/26/2016, environmental monitoring TLDs T8 and T9 were relocated. The TLDs were originally located on either side of the Discharge Canal. Due to the upcoming planned removal of Discharge Canal outlet piping, the Coastal Trail was repositioned inland to prevent impending work. Former TLD locations would have fallen on the Coastal Trail pathway; therefore, TLDs were relocated in advance of the work. This was documented in corrective action SAPN 1415707.

During excavation activities in the Intake Canal on 8/19/2016, environmental TLD T16 was removed from the railing at the canal headworks. The TLD box and ehvironmental TLD were recovered from a pile of debris and delivered to the Count Room building on 8/23/2016. A temporary holder for the TLD was fabricated and the holder attached to the permanent HBGS fence line around the switchyard. A permanent enclosure for the TLD was installed later. This was documented in corrective action SAPN 1422334.

3. Airborne Pathway Five onsite samples and one offsite sample were collected and analyzed weekly for Gross Beta and Gross Alpha activity.

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-5. The weekly sample results for alpha and beta particulate met the effluent acceptance criteria in the ODCM. All LLD's were met for Gross Beta (required LLD 1.0E-02 pCi/m 3 ), with the exception of the Annex Building sample in 6/2016. Due to air sampler malfunction and shortened run time of 99 hours0.00115 days 0.0275 hours 1.636905e-4 weeks 3.76695e-5 months , the beta MDA for the weekly air sample was <1.02E-02 pCi/m 3 , slightly higher than the required LLD of 1.0E-02 pCi/m 3 . All LLD's were met for Cs-137 activity (required LLD of 6.0E-02 pCi/m 3 ).

On 3/18/2016, a planned site wide 12 kV electrical outage occurred. Air samplers at the Annex Building, East Fence and Building 12 were switched from AC power to generator power to accommodate the outage. At approximately 16:45 hours, the air samplers were disconnected from generator power and reconnected to AC power. The AC power was restored at approximately 23:1 0 hours0 days 0 hours 0 weeks 0 months on the same day. This was documented in corrective action SAPN 1415707.

AC power to the environmental air monitoring station at the Oily Water Separator was shut down from 10:07 hours to 11:10 hours on 4/13/2016 due to an electrical clearance. This was documented in corrective action SAPN 1415707.

The REMP air sampler at the Oily Water Separator was found to be malfunctioning on 6/2/2016. The instrument did not appear to be drawing air through the filter. The air filter removed from the sampler appeared to have normal filter discoloration. Air sample results for gross counts as well as alpha activity, beta activity and total DAC fraction appeared to be within the normal range. Maintenance was performed on the sampler on the same day and the instrument returned to service. This was documented in corrective action SAPN 1419126.

The REMP air sampler at the Annex Building (AM3) was discovered to be not operating on 6/16/2016 and the timer displayed only 99 hours0.00115 days 0.0275 hours 1.636905e-4 weeks 3.76695e-5 months of run time. The REMP air sampler at the Relay Building was also found to be not operating on the same day and displayed only 104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months of run time. The air filters appeared to have been used for a portion of the week, but did not appear discolored enough for a week's normal volume. Alpha and beta analyses of both air filters were based on the volume displayed by the totalizers. The beta MDA for the Annex Building filter was <1.02E-02 pCi/m 3 , slightly higher than the required LLD of 1.0E-02 pCi/m 3 , primarily due to the reduced run time. This was documented in corrective action SAPN 1419889.

The REMP air sampler at the East Fence was found to be not operating on 7/14/2016. Electrical power to the air sampler was disconnected by a Job Supervisor overseeing an excavation in the immediate vicinity. Notice of the sampler shutdown as required by the Information Tag on the instrument was not provided to Count Room techni~ians or Radiation Protection technicians.

The sampler was disconnected from power at 8:30 a.m. and reconnected at 9:54 a.m. on the same date. This was documented in corrective action SAPN 1420708.

The REMP air sampler at Humboldt Hill (Station 3) was discovered to be not operating on 7/14/2016. The pump was warm to the touch and the totalizer was running. The pump did not appear to be drawing air through the filter and the filter appeared lighter in color than normal. RP Instrumentation personnel later determined the Hi-Q samplers were failing due to overheating. Inspection of the instrument exhaust mufflers evidenced carbon clogging of the pump vanes.

New mufflers were obtained and installed and the samplers allowed to operate for a day with no apparent increase in operating temperature. As a result, mufflers on the Hi-Q samplers will be replaced on an annual basis. This was documented in corrective action SAPN 1420706.

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 was performed by sampling twelve (12) monitoring wells located to monitor for leakage from the SFP. Sampling of these monitoring wells was performed quarterly in accordance with plant procedures.

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 demolition and decommissioning activities.

Ground water results will continue to be reported in the annual REMP report for as long as results are available. Current plans include destruction of active monitoring wells beginning in 2017. 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 2016 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 (Spent Fuel Pool) 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.

Due to decommissioning activities, not all required sampling and analysis of the monitoring wells for the waterborne pathway were performed successfully. Monitoring Well RCW-CS-3 (approximately 83 ft. deep and located in the Unit 3 East Yard) was unable to be sampled in 2016 due to ongoing remediation activities within the immediate vicinity. This well was later cut down and capped. This was documented in corrective action SAPN 1415704.

During the first quarter well sampling campaign, RCW-SFP-4 (approximately 70ft. deep and located in the upper yard) was discovered to have a broken well lid. A large amount of sediment was identified in the well, requiring well redevelopment and re-sampling on 3/11/2016. This was documented in corrective action SAPN 1415557.

Remediation activities in the upper yard required removal of soil and fill material surrounding RCW-SFP-1 (approximately 66ft. deep and located adjacent to the roadway to the upper yard). The excavation was performed to slope the terrain in preparation for demolition of remaining Liquid Radwaste Building (LRW) foundation and walls. The well was sampled during the first and second quarterly sampling events. However, due to the well's proximity to the final excavated slope, it could not be safely sampled during the second half of 2016. This was documented in corrective action SAPN 1418277.

MW-11 (approximately 45ft. deep and located southeast of Unit 3) was found to have a cracked surface well cover in August 2016. It is believed the metal cover sustained several cracks due to roadway traffic. A secondary well cover beneath the roadway surface remained intact preventing damage to the well casing. MW-11 was sampled during all four quarterly well monitoring events. This was documented in corrective action SAPN 1421635.

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 practicable to appropriate State/Local officials, with follow up notification to the NRC, as appropriate, regarding significant onsite leaks/spills into groundwater and onsite or offsite water sample results exceeding the criteria in the REMP as described in the ODCMIODAM.

HBPP Response to 2.2:

There were no reports or notifications required to be generated in 2016 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 groundwater that 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 appropriate State agency, and:

HBPP Response to 2.3:

There were no reports or notifications required to be generated in 2016 for groundwater results exceeding reporting/notification levels or significant onsite leaks/spills.

OBJECTIVE 2.4 ANNUAL REPORTING Document all on-site ground water sample results and a description of any significant on-site leaks/spills into groundwater for each calendar year in the AREOR for REMP or the ARERR for the RETS as contained in the appropriate reporting procedure, beginning with Calendar year 2006.

HBPP Response to 2.4:

Onsite groundwater monitoring points are described and reported in this report as follows: MW-11, RCW-SFP-1 (first and second quarter of 2016 only), RCW-SFP-2, RCW-SFP-3, RCW-SFP-4, RCW-SFP-5, RCW-SFP-6, RCW-CS-5, RCW-CS-6, RCW-CS-7, RCW-CS-8, RCW-CS-9, and RCW-CS-1 0. A summary of the sample results are provided in Section C.

There were no significant onsite leaks/spills into groundwater in 2016.

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 lsotopic(a) analysis on quarterly composite (by station).

DIRECT RADIATION 16 onsite stations with TLDs exchanged quarterly Gamma exposure TLDs 5 offsite stations with TLDs exchanged quarterly Gamma exposure TLDs WATERBORNE Groundwater 12 monitoring wells Quarterly Gross alpha and Gross beta radioactivity, Tritium and Gamma lsotopic(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 61 5.8 Drive TABLE A-3 GEL PARTICIPATION -INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2014 Date Value Value (pCi/L) (pCi/L)

Gamma Water 1-131 E11448 1st 5/16/2016 9.92E+01 9.67E+01 1.03 Acceptable Ce-141 E11448 1st 5/16/2016 1.40E+02 1.39E+02 1.01 Acceptable Cr-51 . E11448 1st 5/16/2016 3.95E+02 3.66E+02 1.08 Acceptable Cs-134 E11448 1st 5/16/2016 1.12E+02 1.26E+02 0.89 Acceptable Cs-137 E11448 1st 5/16/2016 1.69E+02 1.67E+02 1.01 Acceptable Co-58 E11448 1st 5/16/2016 1.78E+02 1.80E+02 0.99 Acceptable Mn-54 E11448 1st 5/16/2016 1.66E+02 1.59E+02 1.05 Acceptable Fe-59 E11448 1st 5/16/2016 2.14E+02 1.95E+02 1.01 Acceptable Zn-65 E11448 1st 5/16/2016 3.25E+02 2.99E+02 1.09 Acceptable Co-60 E11448 1st 5/16/2016 3.23E+02 3.28E+02 0.98 Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio- Evaluation Analysis Number 2014 Date Value Value (pCi/L) (pCi/L)

Milk Sr-89 E11446 1st 5/16/2016 8.16E+01 8.67E+01 0.94 Acce_2_table Sr-90 E11446 1st 5/16/2016 1.08E+01 1.14E+01 0.95 Acceptable 1-131 E11447 1st 5/16/2016 9.41 E+01 8.22E+01 1.15 Acceptable Ce-141 E11447 1st 5/16/2016 1.05E+02 9.84E+01 1.07 Acceptable Cr-51 E11447 1st 5/16/2016 2.69E+02 2.43E+02 1.11 Acceptable Cs-134 E11447 1st 5/16/2016 1.13E+02 1.30E+02 0.87 Acceptable Cs-137 E11447 1st 5/16/2016 1.64E+02 1.61 E+02 1.02 Acceptable Co-58 E11447 1st 5/16/2016 1.16E+02 1.17E+02 0.99 Acceptable Mn-54 E11447 1st 5/16/2016 . 1.24E+02 1.17E+02 1.06 Acceptable Fe-59 E11447 1st 5/16/2016 1.47E+02 1.31 E+02 1.12 Acceptable Zn-65 E11447 1st 5/16/2016 1.98E+02 1.79E+02 1.11 Acceptable Co-60 E11447 1st 5/16/2016 2.59E+02 2.44E+02 1.06

Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2014 Date Value Value (pCi) (pCi)

Cartridge 1-131 E11445 1st 5/16/2016 9.39E+01 8.86E+01 1.06 Acceptable TABLE A-3 (Continued)

GEL PARTICIPATION -INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2015 Date Value Value (pCi/L) (pCi/L)

Gamma Water 1-131 E11576 2nd 7/27/2016 1.02E+02 9.67E+01 1.05 Acceptable Ce-141 E11576 2nd 7/27/2016 1.56E+02 1.47E+02 1.06 Acceptable Cr-51 E11576 2nd 7/27/2016 3.33E+02 2.92E+02 1.14 Acceptable Cs-134 E11576 2nd 7/27/2016 1.65E+02 1.85E+02 0.89 Acceptable Cs-137 E11576 2nd 7/27/2016 1.34E+02 1.28E+02 1.05 Acceptable Co-58 E11576 2nd 7/27/2016 1.47E+02 1.51 E+02 0.98 Acceptable Mn-54 E11576 2nd 7/27/2016 1.45E+02 1.33E+02 1.09 Acceptable Fe-59 E11576 2nd 7/27/2016 1.54E+02 1.29E+02 1.19 Acceptable Zn-65 E11576 2nd 7/27/2016 2.72E+02 2.49E+02 1.09 Acceptable Co-60 E11576 2nd 7/27/2016 1.99E+02 1.83E+02 1.09 Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2015 Date Value Value (pCi/L) (pCi/L)

Milk Sr-89 E11574 2nd 7/27/2016 8.51 E+01 9.44E+01 0.90 Acceptable Sr-90 E11574 2nd 7/27/2016 9.49E+01 1.54E+01 0.62 Acceptable 1-131 E11575 2nd 7/27/2016 9.77E+01 9.45E+01 1.03 Acceptable Ce-141 E11575 2nd 7/27/2016 1.46E+02 1.39E+02 1.05 Acceptable Cr-51 E11575 2nd 7/27/2016 2.53E+02 2.76E+02 0.92 Acceptable Cs-134 E11575 2nd 7/27/2016 1.62E+02 1.74E+02 0.93 Acceptable Cs-137 E11575 2nd 7/27/2016 1.20E+02 1.20E+02 1.00 Acceptable Co-58 E11575 2nd 7/27/2016 1.39E+02 1.42E+02 0.98 Acceptable Mn-54 E11575 2nd 7/27/2016 1.26E+02 1.25E+02 1.00 Acceptable Fe-59 E11575 2nd 7/27/2016 1.25E+02 1.22E+02 1.03 Acceptable Zn-65 E11575 2nd 7/27/2016 2.47E+02 2.35E+02 1.05 Acceptable Co-60 E11575 2nd 7/27/2016 1.72E+02 1.73E+02 1.00 Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2015 Date Value Value (pCi) (pCi)

Cartridge 1-131 E11573 2nd 7/27/2016 9.52E+01 8.94E+01 1.07 Acceptable TABLE A-3 (Continued}

GEL PARTICIPATION -INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report Date GEL Reference Ratio Evaluation Analysis Number 2015 Value Value (pCi/L) (pCi/L)

Gamma Water 1-131 E11068 3rd 11/28/2016 5.53E+01 4.90E+01 1.13 Acceptable Ce-141 E11068 3rd 11/28/2016 9.49E+01 8.52E+01 1.11 Acceptable Cr-51 E11068 3rd 11/28/2016 2.03E+02 2.15E+02 0.95 Acceptable Cs-134 E11068 3rd 11/28/2016 1.20E+02 1.24E+02 0.97 Acceptable Cs-137 E11068 3rd 11/28/2016 1.15E+02 1.08E+02 1.06 Acceptable Co-58 E11068 3rd 11/28/2016 9.54E+01 8.90E+01 1.07 Acceptable Mn-54 E11068 3rd 11/28/2016 1.47E+02 1.39E+02 1.06 Acceptable Fe-59 E11068 3rd 11/28/2016 8.73E+01 8.28E+01 1.05 Acceptable Zn-65 E11068 3rd 11/28/2016 1.79E+02 1.63E+02 1.10 Acceptable Co-60 E11068 3rd 11/28/2016 1.26E+02 1.23E+02 1.02 Acceptable Sample/ Radionuclide Sample Quarter Report Date GEL Reference Ratio Evaluation Analysis Number 2015 Value Value (pCi/L) (pCi/L)

Milk Sr-89 E11606 3rd 11/28/2016 7.60E+01 9.09E+01 0.84 Acceptable Sr-90 E11606 3rd 11/28/2016 1.17E+01 1.37E+01 0.85 Acceptable 1-131 E11607 3rd 11/28/2016 7.53E+01 7.19E+01 1.05 Acceptable Ce-141 E11607 3rd 11/28/2016 9.85E+01 9.32E+01 1.06 Acceptable Cr-51 E11607 3rd 11/28/2016 2.63E+02 2.36E+02 1.12 Acceptable Cs-134 E11607 3rd 11/28/2016 1.21 E+02 1.36E+02 0.89 Acceptable Cs-137 E11607 3rd 11/28/2016 1.19E+02 1.19E+02 1.00 Acceptable Co-58 E11607 3rd 11/28/2016 9.56E+01 9.74E+01 0.98 Acceptable Mn-54 E11607 3rd 11/28/2016 1.61 E+02 1.52E+02 1.06 AcceRtable Fe-59 E11607 3rd 11/28/2016 9.00E+01 9.06E+01 0.99 Acceptable Zn-65 E11607 3rd 11/28/2016 2.11 E+02 1.79E+02 1.18 Acceptable Co-60 E11607 3rd 11/28/2016 1.44E+02 1.35E+02 1.07 Acceptable Sample/ Radionuclide Sample Quarter Report Date GEL Reference Ratio Evaluation Analysis Number 2015 Value Value (pCi) (pCi)

Cartridge 1-131 E11605 3rd 11/28/2016 6.33E+01 6.01 E+01 1.05 Acceptable TABLE A-3 (Continued)

GEL PARTICIPATION -INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report Date GEL Reference Ratio Evaluation Analysis Number 2015 Value Value (pCi/L) (pCi/L)

Gamma Water 1-131 E11677 4th 2/21/2017 1.06E+02 9.18E+01 1.15 Acceptable Ce-141 E11677 4th 2/21/2017 1.47E+02 1.38E+02 1.06 Acceptable Cr-51 E11677 4th 2/21/2017 3.03E+02 2.71 E+02 1.12 Acceptable Cs-134 E11677 4th 2/21/2017 1.59E+02 1.73E+02 0.92 Acceptable Cs-137 E11677 4th 2/21/2017 1.38E+02 1.22E+02 1.13 Acceptable Co-58 E11677 4th 2/21/2017 1.49E+02 1.42E+02 1.05 Acceptable Mn-54 E11677 4th 2/21/2017 1.35E+02 1.25E+02 1.08 Acceptable Fe-59 E11677 4th 2/21/2017 1.35E+02 1.21 E+02 1.12 Acceptable Zn-65 E11677 4th 2/21/2017 2.61 E+02 2.36E+02 1.10 Acce_Q_table Co-60 E11677 4th 2/21/2017 1.76E+02 1.72E+02 1.02 Acceptable Sample/ Radionuclide Sample Quarter Report Date GEL Reference Ratio Evaluation Analysis Number 2015 Value Value (pCi/L) (pCi/L)

Milk Sr-89 E11675 4th 2/21/2017 7.86E+01 7.42E+01 1.06 Acceptable Sr-90 E11675 4th 2/21/2017 7.50E+OO 1.00E+01 0.75 Acceptable 1-131 E11676 4th 2/21/2017 1.08E+02 9.74E+01 1.11 Acceptable Ce-141 E11676 4th 2/21/2017 1.55E+02 1.43E+02 1.09 Acceptable Cr-51 E11676 4th 2/21/2017 3.29E+02 2.80E+02 1.18 Acceptable Cs-134 E11676 4th 2/21/2017 1.67E+02 1.78E+02 0.94 Acceptable Cs-137 E11676 4th 2/21/2017 1.43E+02 1.26E+02 1.13 Acceptable Co-58 E11676 4th 2/21/2017 1.54E+02 1.46E+02 1.05 Acceptable Mn-54 E11676 4th 2/21/2017 1.46E+02 1.29E+02 1.13 Acceptable Fe-59 E11676 4th 2/21/2017 1.45E+02 1.25E+02 1.16 Acceptable Zn-65 E11676 4th 2/21/2017 2.68E+02 2.44E+02 1.10 Acceptable Co-60 E11676 4th 2/21/2017 1.87E+02 1.78E+02 1.05 Acceptable Sample/ Radionuclide Sample Quarter Report Date GEL Reference Ratio Evaluation Analysis Number 2015 Value Value (pCi) (pCi)

Cartridge 1-131 E11674 4th 2/21/2017 9.60E+01 9.67E+01 0.99 Acceptable TABLE A-4 HBPP PARTICIPATION- ECKERT & ZIEGLER INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2016 Date Count Value Room (pCi/g)

(pCi/g)

Gamma Soil Ce-141 E11432 1st 3/17/2016 1.82E-01 1.86E-01 0.98 Acceptable Cr-51 E11432 1st 3/17/2016 4.19E-01 4.60E-01 0.91 Acceptable Cs-134 E11432 1st 3/17/2016 2.33E-01 2.46E-01 0.95 Acceptable Cs-137 E11432 1st 3/17/2016 3.60E-01 3.82E-01 0.94 Acceptable Co-58 E11432 1st 3/17/2016 2.05E-01 2.22E-01 0.92 Acceptable Mn-54 E11432 1st 3/17/2016 2.22E-01 2.21 E-01 1.00 Acceptable Fe-59 E11432 1st 3/17/2016 2.42E-01 2.48E-01 0.98 Acceptable Zn-65 E11432 1st 3/17/2016 3.38E-01 3.38E-01 1.00 Acceptable Co-60 E11432 1st 3/17/2016 4.50E-01 4.62E-01 0.98 Acceptable Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2015 Date Count Value (pCi)

Room (pCi)

Gamma Filter Ce-141 E11552 2nd 6/9/2016 1.08E+02 1.04E+02 1.04 Acceptable Cr-51 E11552 2nd 6/9/2016 2.02E+02 2.07E+02 0.98 Acceptable Cs-134 E11552 2nd 6/9/2016 1.19E+02 1.31 E+02 0.91 Acceptable Cs-137 E11552 2nd 6/9/2016 9.71 E+01 9.03E+01 1.08 Acce_Q_table Co-58 E11552 2nd 6/9/2016 1.08E+02 1.07E+02 1.01 Acceptable Mn-54 E11552 2nd 6/9/2016 9.99E+01 9.40E+01 1.06 Accep_table Fe-59 E11552 2nd 6/9/2016 9.90E+01 9.13E+01 1.08 Acceptable Zn-65 E11552 2nd 6/9/2016 1.87E+02 1.76E+02 1.06 Acceptable Co-60 E11552 2nd 6/9/2016 1.39E+02 1.29E+02 1.07 Acceptable Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2015 Date Count Value (pCi)

Room (pCi)

Alpha/Beta Alpha E11551 2nd 6/9/2016 6.15E+01 5.99E+01 1.03 Acceptable 1 Filter Beta E11551 2nd 6/9/2016 2.04E+02 2.00E+02 1.02 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 2015 Date Count Value Room (pCi/L)

(pCi/L)

Gamma Water 1-131 E11603 3rd 9/15/2016 Not 4.90E+01 Note 2 ---

Reported Ce-141 E11603 3rd 9/15/2016 8.62E+01 8.52E+01 1.01 Acceptable Cr-51 E11603 3rd 9/15/2016 2.44E+02 2.15E+02 1.13 Acceptable Cs-134 E11603 3rd 9/15/2016 1.11 E+02 1.24E+02 0.89 Acceptable Cs-137 E11603 3rd 9/15/2016 1.12E+02 1.08E+02 1.03 Acceptable Co-58 E11603 3rd 9/15/2016 8.21 E+01 8.90E+01 0.92 Acceptable Mn-54 E11603 3rd 9/15/2016 1.45E+02 1.39E+02 1.04 Acceptable Fe-59 E11603 3rd 9/15/2016 8.05E+01 8.28E+01 0.97 Acce(Jtable Zn-65 E11603 3rd 9/15/2016 1.75E+02 1.63E+02 1.07 Acceptable Co-60 E11603 3rd 9/15/2016 1.22E+02 1.23E+02 0.99 Acceptable Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2015 Date Count Value Room (pCi/L)

(pCi/L)

Tritium Water H-3 E11602 3rd 9/15/2016 1.70E+03 1.80E+03 0.94 Acceptable Sample/ Radionuclide Sample Quarter Report Date HBPP Reference Ratio Evaluation Analysis Number 2015 Count Value Room (pCi/g)

(pCi/g)

Gamma Soil Ce-141 E11673 4th 12/1/2016 2.42E-01 2.36E-01 1.02 Acceptable Cr-51 E11673 4th 12/1/2016 4.55E-01 4.63E-01 0.98 Acceptable Cs-134 E11673 4th 12/1/2016 2.88E-01 2.95E-01 0.98 Acceptable Cs-137 E11673 4th 12/1/2016 2.83E-01 2.85E-01 0.99 Acceptable Co-58 E11673 4th 12/1/2016 2.40E-01 2.43E-01 0.99 Acceptable Mn-54 E11673 4th 12/1/2016 2.25E-01 2.14E-01 1.05 Acceptable Fe-59 E11673 4th 12/1/2016 2.19E-01 2.07E-01 1.06 Acceptable Zn-65 E11673 4th 12/1/2016 4.12E-01 4.04E-01 1.02 Acceptable Co-60 E11673 4th 12/1/2016 2.95E-01 2.94E-01 1.00 Acceptable Table A-4 Notes:

1 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. Beta filter cross checks normally performed on each Protean gas flow proportional counter at count times of 5 minutes and 10 minutes.

2 HBPP analyses did not identify 1-131 at 364.5 keV, primarily because 1-131 does not normally appear within cross checks or the HBPP library. The nuclide has an 8-day half-life and was discarded as an isotope of concern several years ago. Isotopes of concern for HBPP are Cs-137 at 661.6 keV and Co-60 at 1173.2 and 1332.5 keV. The problem was documented in corrective action SAPN 1413539.

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, 2016 (County, 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] 0 Name Mean, Mean, Measure-(Fraction) (Fraction) ments

& [Ranget & [Range]b (52) samples per

Gross Beta East Fence (AM1) Annex Gross Alpha Humboldt Hill N/A AIRBORNE station 1.00E-02 Gross Alpha (pCi/m3) mean 2.31 E-03, (1 0/52), [1.21 E-03 to 2.89E-03] (pCi/m3) mean (Station 3)

Gross Beta, pCi/m3 Gross Beta (pCi/m3) mean 8.70E-03, (45/52), [3.03E-03 to 2.23E-02] 2.75E-03, (5/52), Gross Alpha Particulates

Gross Alpha Building 12 (AM2) [2.37E-03 to (pCi/m3) mean Gross Alpha (pCi/m3) mean 2.50E-03, (6/52), [2.38E-03 to 3.00E-03] 3.59E-03] 2.09E-03,

[pCi/m3]

Gamma Isotopic

Gamma Gross Beta (pCi/m3) mean 9.26E-03, (45/52), [3.86E-03 to 1.78E-02] (5/52),

Isotopic analysis on analysis on Annex (AM3) [9.19E-04 to quarterly quarterly Gross Alpha (pCi/m3) mean 2.75E-03, (5/52), [2.37E-03 to 3.59E-03] 2.41 E-03]

composite (by composite Gross Beta (pCi/m3) mean 8.46E-03, (40/52), [3.35E-03 to 1.88E-02]

station) (by station) Relay Building (AM4) Relay Gross Beta Gross Beta Gross Alpha (pCi/m3) mean 2.52E-03, (13/52), [1.65E-03 to 3.63E-03] Bldg. (pCi/m3) mean (pCi/m3) mean (5) Onsite Gross Beta (pCi/m3) mean 1.08E-02, (44/52), [3.03E-03 to 2.52E-02] 1.08E-02, 7.26E-03,

Cs-137 Oil Water Separator (OWS - AM5) (44/52), (35/52),

Locations 6.00E-02 Gross Alpha (pCi/m3) mean 2.56E-03, (7/52), [2.37E-03 to 3.03E-03] [3.03E-03 to [4.19E-03 to (1) Offsite pCi/m3 Gross Beta (pCi/m3) mean 8.43E-03, (44/52), [3.35E-03 to 1.44E-02] 2.52E-02] 1.29E-02]

Locations Cs-137 <MDA (64) Fence line 5mRem Fence Line TLDs (T1 to T16) Station T1 (mR/qtr) Stations 1, 2, 0 DIRECT TLD readings 14.6 +/- 0.1, (64/64), [12.7 to 18.4] T-1, mean 14, 25 and T17 RADIATION Figure 15.6 +/- 0.3, (mR/qtr) mean (20) Off-site TLD B-1 (4/4), [14.6 to 14.1 +/- 0.1,

[mR/quarter] Readings 17.0] (20/20),

[12.7 to 16.8]

TABLE C-1 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 Detection a (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-137 Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 0 WATERBORNE (50) Cs-137:18 pCi!L Groundwater <MDA <MDA N/A N/A <MDA <MDA N/A N/A (0/50) (0/50) (0/50) (0/50)

(Monitoring wells)

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

[pCi/L]

Tritium(SO) -------------

ODCM: 2.0E+03 ------------------

<MDA, (0/50), [N/A]

N/A

<MDA, (0/50), [N/A]

N/A 0

pCi/L

-~l~n_t f.~~cy~ ~0.9 __

------------ N/A ------------------

N/A N/A ---------------

N/A ---------------

Not Required N/A

__ (!ciQ~i[lg_\0/.?!~r- __ Not Required Sediment 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 T1 17.0+/-0.7 15.4 +/- 0.7 14.6 +/- 0.5 15.2 +/- 0.4 T2 16.1+/-1.0 14.6 +/- 0.5 14.1 +/- 0.5 14.3 +/- 0.5 T3 15.6 +/- 1.3 14.1 +/- 0.6 13.5 +/- 0.6 14.1 +/- 0.8 T4 16.2 +/- 1.3 14.4 +/- 0.7 14.6 +/- 0.6 14.9 +/- 0.5 T5 16.6 +/- 1.1 13.4 +/- 0.5 13.6 +/- 0.4 14.1+/-0.7 T6 15.5 +/- 0.9 12.9 +/- 0.3 12.7 +/- 0.5 13.2 +/- 0.5 T7 15.9 +/- 1.3 13.1 +/- 0.8 12.9 +/- 0.6 13.4 +/- 0.4 T8 15.3 +/- 1.0 13.0 +/- 0.7 13.9 +/- 0.4 13.8 +/- 0.6 T9 18.4 +/- 0.7 14.4 +/- 0.5 14.4+/-1.1 14.3 +/- 0.5 T10 15.4 +/- 0.4 13.6 +/- 0.9 14.0 +/- 0.3 14.3 +/- 0.4 T11 15.9 +/- 0.7 13.9 +/- 0.6 14.1 +/- 0.5 13.9 +/- 0.3 T12 15.9 +/- 0.9 14.7 +/- 0.9 14.5 +/- 0.4 14.6 +/- 0.5 T13 15.8 +/- 0.4 14.0 +/- 0.5 14.3 +/- 0.4 15.1 +/- 0.6 T14 16.0 +/- 0.8 15.1 +/- 0.8 14.7 +/- 0.6 15.0+/-0.7 T15 16.4+/-1.9 14.2 +/- 0.7 13.3 +/- 0.7 14.2 +/- 0.6 T16 15.2 +/- 0.6 13.9 +/- 0.8 13.7 +/- 0.3 14.7 +/- 0.5 Calculated Parameters (mR)

Parameter First Quarter Second Quarter Third Quarter Fourth Quarter Average 16.1 +/- 0.3 14.0 +/- 0.2 13.9 +/- 0.1 14.3 +/- 0.1 Maximum 18.4 +/- 0.7 15.4 +/- 0.9 14.7 +/- 0.6 15.2 +/- 0.4 Table C-2 Notes:

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

2. The reported exposures do not have an average background subtracted.

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

Number First Quarter Second Quarter Third Quarter Fourth Quarter 1 14.9 +/- 0.4 13.8 +/- 0.4 13.6 +/- 0.3 13.7 +/- 0.4 2 16.8 +/- 0.4 15.3 +/- 0.7 15.3 +/- 0.3 15.7 +/- 0.4 14 14.7+/-1.0 12.8 +/- 0.4 12.7 +/- 0.3 13.2+/-1.0 25 14.4 +/- 0.7 13.7+/-0.9 12.7 +/- 0.4 13.4 +/- 0.5 T17 15.1 +/- 0.8 12.9 +/- 0.6 13.3 +/- 0.3 13.3 +/- 0.3 Calculated Parameters (mR)

Parameter First Quarter Second Quarter Third Quarter Fourth Quarter Average 15.2 +/- 0.3 13.7 +/- 0.3 13.5 +/- 0.1 13.9 +/- 0.3 Maximum 16.8 +/- 0.4 15.3 +/- 0.7 15.3 +/- 0.3 15.7 +/- 0.4 Table C-3 Notes:

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

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* 2/11/2016 < 3.58 6.59 +/- 1.97 < 4.61 < 4.96 < 306 RCW-SFP-1* 2/11/2016 < 21.8 < 12.2 < 4.97 < 5.68 < 302 RCW-SFP-2* 2/11/2016 < 25.9 17.2 +/- 10.9 < 5.12 < 4.01 < 308 RCW-SFP-3* 2/11/2016 <45.6 < 30.8 < 6.17 < 5.11 < 306 RCW-SFP-4* 3/11/2016 < 32.1 < 20.5 < 4.77 < 4.61 < 297 RCW-SFP-5* 2/11/2016 '< 34.3 < 20.5 < 5.83 < 5.74 < 307 RCW-SFP-6* 2/11/2016 < 3.72 < 2.10 < 4.85 <4.82 < 306 RCW-CS-5* 2/11/2016 < 2.61 3.90 +/- 1.35 < 3.81 <4.79 < 308 RCW-CS-6* 2/11/2016 < 112 < 104 < 5.13 < 4.34 < 307 RCW-CS-7* 2/11/2016 < 169 < 102 < 4.42 < 4.67 < 303 RCW-CS-8* 2/11/2016 < 201 < 143 < 4.87 <4.95 < 307 RCW-CS-9* 2/11/2016 < 102 < 71.1 < 5.07 < 5.53 < 301 RCW-CS-10* 2/11/2016 < 36.0 < 23.0 < 4.52 < 4.83 < 299

Indicates thirteen (13) groundwater momtonng wells.

MW-11* 5/10/2016 < 1.95 < 2.15 < 5.87 < 3.53 < 336 RCW-SFP-1* 5/10/2016 < 4.79 < 5.11 < 3.90 < 4.96 < 334 RCW-SFP-2* 5/10/2016 < 22.8 < 23.6 < 4.62 < 5.50 < 339 RCW-SFP-3* 5/10/2016 < 68.7 < 25.2 < 4.35 <4.08 < 335 RCW-SFP-4* 5/10/2016 < 43.9 < 21.7 < 5.71 < 5.16 < 336 RCW-SFP-5* 5/10/2016 < 45.2 < 14.9 < 4.77 < 3.53 < 339 RCW-SFP-6* 5/10/2016 < 3.14 < 1.70 < 4.55 < 4.38 < 336 RCW-CS-5* 5/10/2016 < 3.08 4.46 +/- 2.39 < 3.72 < 4.88 < 338 RCW-CS-6* 5/10/2016 < 123 < 129 < 5.37 < 4.21 < 338 RCW-CS-7* 5/10/2016 < 112 104 +/- 59 < 4.49 <5.47 < 342 RCW-CS-8* 5/10/2016 < 105 < 85.1 < 3.54 < 5.24 < 331 RCW-CS-9* 5/10/2016 < 75.8 < 58.3 < 2.88 < 3.10 < 301 RCW-CS-10* 5/10/2016 < 23.6 < 17.6 < 3.85 <4.37 < 338

Indicates th1rteen (13) groundwater mon1tonng wells.

MW-11* 8/23/2016 < 3.84 3.07 +/- 1.19 < 3.34 < 2.29 < 296 RCW-SFP-2* 8/23/2016 <46.2 < 23.4 < 3.23 <3.49 < 302 RCW-SFP-3* 8/23/2016 <42.0 < 29.0 < 3.99 < 2.33 < 288 RCW-SFP-4* 8/23/2016 < 57.1 < 35.0 < 3.31 < 4.46 < 292 RCW-SFP-5* 8/23/2016 < 43.3 < 13.8 < 5.06 < 3.25 < 294 RCW-SFP-6* 8/23/2016 < 2.27 1.99 +/- 0.98 < 4.04 < 3.97 < 298 RCW-CS-5* 8/23/2016 < 3.28 2.69 +/- 0.91 < 4.15 < 4.00 < 298 RCW-CS-6* 8/23/2016 < 121 < 110 < 5.83 < 6.87 < 289 RCW-CS-7* 8/23/2016 < 255 < 119 < 5.13 <4.68 < 299 RCW-CS-8* 8/23/2016 < 191 < 80.6 < 3.21 < 3.71 < 299 RCW-CS-9* 8/23/2016 < 84.4 < 57.0 < 3.94 < 5.21 < 298 RCW-CS-10* 8/23/2016 < 37.8 < 20.5 < 4.51 < 6.76 < 304

Indicates twelve (12) groundwater mon1tonng 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) (pCi/L) (pCi/L)

Cs-137 Co-60 MW-11* 11/10/2016 < 5.08 3.76 +/- 1.29 < 5.93 < 4.05 < 281 RCW-SFP-2* 11/10/2016 < 46.9 < 16.9 < 5.38 < 6.25 < 284 RCW-SFP-3* 11/10/2016 < 46.3 < 22.9 < 4.69 < 3.92 < 282 RCW-SFP-4* 11/10/2016 < 62.7 < 24.2 < 6.02 < 4.28 < 279 RCW-SFP-5* 11/10/2016 < 25.1 < 12.7 < 3.41 < 3.69 < 274 RCW-SFP-6* 11/10/2016 < 2.90 1.50 +/- 0.86 < 3.80 < 3.98 < 281 RCW-CS-5* 11/10/2016 < 2.94 2.63 +/- 1.05 < 3.91 < 5.64 < 275 RCW-CS-6* 11/10/2016 < 158 < 77.3 < 3.29 < 3.85 < 273 RCW-CS-7* 11/10/2016 < 233 < 87.0 < 4.37 < 3.83 < 273 RCW-CS-8* 11/10/2016 < 210 < 85.4 < 3.68 < 4.02 < 280 RCW-CS-9* 11/10/2016 < 91.2 < 45.7 < 3.87 < 4.30 < 276 RCW-CS-10* 11/10/2016 < 43.4 < 20.6 < 3.95 < 4.39 < 278

~

Indicates twelve (12) groundwater momtonng 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-11 Note 6 4.47 +/- 0.88 Note 6 Note 6 Note 6 Average: RCW-SFP-1* Note 6 Note 6 Note 6 Note 6 Note 6 Average: RCW-SFP-2* Note 6 17.2 +/- 10.9 Note 6 Note 6 Note 6 Average: RCW-SFP-3* Note 6 Note 6 Note 6 Note 6 Note 6 Average: RCW-SFP-4* Note 6 Note 6 Note 6 Note 6 Note 6 Average: RCW-SFP-5* Note 6 Note 6 Note 6 Note 6 Note 6 Average: RCW-SFP-6* Note 6 1.74 +/- 0.65 Note 6 Note 6 Note 6 Average: RCW-CS-5* Note 6 3.42 +/- 0.77 Note 6 Note 6 Note 6 Average: RCW-CS-6* Note 6 Note 6 Note 6 Note 6 Note 6 Average: RCW-CS-7* Note 6 104 +/-59 Note 6 Note 6 Note 6 Average: RCW-CS-8* Note 6 Note 6 Note 6 Note 6 Note 6 Average: RCW-CS-9* Note 6 Note 6 Note 6 Note 6 Note 6 Average: RCW-CS-10* Note 6 Note 6 Note 6 Note 6 Note 6 Maximum: MW-11* Note 6 6.59 +/- 1.97 Note 6 Note 6 Note 6 Maximum: RCW-SFP-1* Note 6 Note 6 Note 6 Note 6 Note 6 Maximum: RCW-SFP-2* Note 6 17.2 +/- 10.9 Note 6 Note 6 Note 6 Maximum: RCW-SFP-3* Note 6 Note 6 Note 6 Note 6 Note 6 Maximum: RCW-SFP-4* Note 6 Note 6 Note 6 Note 6 Note 6 Maximum: RCW-SFP-5* Note 6 Note 6 Note 6 Note 6 Note 6 Maximum: RCW-SFP-6* Note 6 1.99 +/- 0.98 Note 6 Note 6 Note 6 Maximum: RCW-CS-5* Note 6 4.46 +/- 2.39 Note 6 Note 6 Note 6 Maximum: RCW-CS-6* Note 6 Note 6 Note 6 Note 6 Note 6 Maximum: RCW-CS-7* Note 6 104 +/-59 Note 6 Note 6 Note 6 Maximum: RCW-CS-8* Note 6 Note 6 Note 6 Note 6 Note 6 Maximum: RCW-CS-9* Note 6 Note 6 Note 6 Note 6 Note 6 Maximum: RCW-CS-10* Note 6 Note 6 Note 6 Note 6 Note 6

Indicates thirteen (13) groundwater monitoring wells.

Table C-4 Notes:

1. RCW-CS-3 is located in the East Yard of Unit 3. The active well was last sampled on 11/9/2015. The well was unable to be sampled during the 2016 quarterly well monitoring events due to ongoing remediation activities within the immediate vicinity and the weWs proximity to the CSM wall. This action was documented in corrective action SAPN 1415704.

2. Remediation activities in the upper yard required removal of soil and fill material around RCW-SFP-1. This work was performed to slope the terrain in preparation for demolition of the remaining Liquid Radwaste Building (LRW) walls and foundation. RCW-SFP-1 was sampled during the first and second quarterly well monitoring campaigns, but was not sampled again in 2016. Although the well has been protected, it is currently located on an excavated slope and is unable to be sampled safely. This action was documented in corrective action SAPN 1418277.

3. 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".

4. 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-137 are 15 and 18 pCi/L, respectively. The actual MDAs for these analyses were at or below the LLD.

5. 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.

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

Table C-5 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-137 12/30/2015 < 2.92E-03 (MDA) 9.74E-03 +/- 3.51 E-03 1/7/2016 < 3.40E-03 (MDA) 7.09E-03 +/- 3.53E-03 1/14/2016 < 3.38E-03 (MDA) 6.33E-03 +/- 3.42E-03 1/21/2016 < 3.38E-03 (MDA) 3.51 E-03 +/- 3.00E-03 1/28/2016 < 3.32E-03JMDA) 4.83E-03 +/- 3.15E-03 2/4/2016 < 3.41 E-03 (MDA) 1.35E-02 +/- 4.32E-03

<1.45E-03 < 1.27E-03 2/11/2016 < 3.39E-03 (MDA) 7.06E-03 +/- 3.52E-03 (MDA) (MDA) 2/18/2016 < 3.35E-03 (MDA) 6.28E-03 +/- 3.39E-03 2/25/2016 < 3.38E-03 (MDA) 9.15E-03 +/- 3.79E-03 3/3/2016 < 3.33E-03 (MDA) 5.55E-03 +/- 3.27E-03 3/10/2016 < 3.37E-03 (MDA) 8.08E-03 +/- 3.64E-03 1

3/17/2016.1 < 3.45E-03 (MDA) < 6.21 E-03 (MDA) 1 3/24/2016 < 3.49E-03 (MDA) 5.45E-03 +/- 3.37E-03 3/31/2016 2.89E-03 +/- 2.08E-03 1.41 E-02 +/- 4.30E-03 4/7/2016 < 3.34E-03 (MDA) 1.38E-02 +/- 4.30E-03 4/14/2016 < 3.48E-03 (MDA) 1.34E-02 +/- 4.37E-03 4/21/2016 2.36E-03 +/- 1.89E-03 < 6.05E-03 (MDA) 4/28/2016 1.21 E-03 +/- 7.68E-04 6.73E-03 +/- 2.46E-03 5/5/2016 < 3.39E-03 (MDA) < 6.10E-03 (MDA)

< 1.09E-03 < 1.19E-03 5/12/2016 < 3.36E-03 (MDA) 1.09E-02 +/- 3.98E-03 (MDA) (MDA) 5/19/2016 < 3.35E-03 (MDA) 3.48E-03 +/- 2.97E-03 5/26/2016 < 3.40E-03 (MDA) 1.17E-02 +/- 4.11 E-03 6/2/2016 < 3.33E-03 (MDA) 6.58E-03 +/- 3.42E-03 6/9/2016 < 3.38E-03 (MDA) 4.92E-03 +/- 3.21 E-03 6/16/2016 < 3.40E-03 (MDA) 7.43E-03 +/- 3.58E-03 6/23/2016 < 3.37E-03 (MDA) 5.95E-03 +/- 3.36E-03 6/30/2016 < 3.37E-03 (MDA) 3.85E-03 +/- 3.04E-03 7/7/2016;£ < 3.39E-03 (MDA);£ 4.93E-03 +/- 3.21 E-03;l 7/14/2016 2.34E-03 +/- 1.88E-03 8.35E-03 +/- 3.66E-03 7/21/2016 < 3.39E-03 (MDA) 4.94E-03 +/- 3.22E-03 7/28/2016 2.38E-03 +/- 1.90E-03 5.99E-03 +/- 3.37E-03 8/4/2016 < 3.41 E-03 (MDA) 8.35E-03 +/- 3.65E-03

< 1.64E-03 < 1.74E-03 8/11/2016 < 3.38E-03 (MDA) < 5.87E-03 (MDA)

(MDA) (MDA) 8/18/2016 < 3.41 E-03 (MDA) 6.23E-03 +/- 3.37E-03 8/25/2016 < 3.40E-03 _(MDA) 1.04E-02 +/- 3.92E-03 9/1/2016 2.37E-03 +/- 1.87E-03 1.1 OE-02 +/- 3.95E-03 9/8/2016 < 3.42E-03 (MDA) 1.51 E-02 +/- 4.46E-03 9/15/2016 < 3.42E-03 (MDA) 7.65E-03 +/- 3.57E-03 9/22/2016 2.38E-03 +/- 1.88E-03 1.42E-02 +/- 4.33E-03 9/29/2016 < 3.33E-03 (MDA) 1.19E-02 +/- 4.02E-03 10/6/2016 < 3.41 E-03 (MDA) 6.22E-03 +/- 3.36E-03 10/13/2016 2.36E-03 +/- 1.86E-03 7.84E-03 +/- 3.55E-03 10/20/2016 < 3.42E-03 (MDA) 1.01 E-02 +/- 3.89E-03 10/27/2016 2.40E-03 +/- 1.90E-03 < 5.93E-03 (MDA) 11/3/2016 < 3.39E-03 (MDA) 1.35E-02 +/- 4.26E-03

< 1.38E-03 < 1.37E-03 11/10/2016 < 3.42E-03 (MDA) 9.44E-03 +/- 3.81 E-03 (MDA) (MDA) 11/17/2016 < 3.86E-03 (MDA) < 6.71 E-03 (MDA) 11/23/2016 < 3.04E-03 (MDA) 3.03E-03 +/- 2.62E-03 12/1/2016 < 3.40E-03 (MDA) 9.71 E-03 +/- 3.83E-03 12/8/2016 < 3.35E-03 (MDA) < 5.83E-03 (MDA) 12/15/2016 2.43E-03 +/- 1.92E-03 2.23E-02 +/- 5.21 E-03 12/22/2016 < 3.92E-03 (MDA) 1.08E-02 +/- 4.36E-03 Table C-5 (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-137 12/30/2015 < 2.92E-03 (MDA) 1.67E-02 +/- 4.25E-03 1/7/2016 < 3.40E-03 (MDA) 6.01 E-03 +/- 3.39E-03 1/14/2016 < 3.38E-03 (MDA) 4.92E-03 +/- 3.21 E-03 1/21/2016 < 3.39E-031MDA)_ 6.35E-03 +/- 3.43E-03 1/28/2016 < 3.31 E-03 (MDA) 5.16E-03 +/- 3.19E-03 2/4/2016 < 3.41 E-03 (MDA) 1.63E-02 +/- 4.64E-03

<1.24E-03 < 1.15E-03 2/11/2016 < 3.39E-03 (MDA) 1.02E-02 +/- 3.94E-03 (MDA) (MDA) 2/18/2016 < 3.36E-03 (MDA) 1.15E-02 +/- 4.07E-03 2/25/2016 < 3.39E-03 _(MDA) 1.02E-02 +/- 3.94E-03 3/3/2016 < 3.33E-03 (MDA) 7.96E-03 +/- 3.59E-03 3/10/2016 < 3.38E-03 (MDA) 1.09E-02 +/- 4.01 E-03 1 1 1 3/17/2016 < 3.45E-03 _(_MDA) < 6.20E-03 (MDA) 3/24/2016 2.45E-03 +/- 1.96E-03 4.72E-03 +/- 3.26E-03 3/31/2016 < 3.31 E-03 (MDA) 1.21 E-02 +/- 4.09E-03 4/7/2016 < 3.33E-03 (MDA) 1.41 E-02 +/- 4.32E-03 4/14/2016 < 3.48E-03 (MDA) 9.78E-03 +/- 3.96E-03 4/21/2016 < 3.36E-03 (MDA) 1.12E-02 +/- 4.03E-03 4/28/2016 < 1.21 E-03 (MDA) 1.01 E-02 +/- 2.78E-03 5/5/2016 < 3.39E-03 (MDA) 1.09E-02 +/- 4.01 E-03

< 1.28E-03 < 1.10E-03 5/12/2016 < 3.38E-03 (MDA) 1.06E-02 +/- 3.97E-03 (MDA) (MDA) 5/19/2016 < 3.33E-03 (MDA) < 5.99E-03 (MDA) 5/26/2016 < 3.39E-03 (MDA) 6.71 E-03 +/- 3.49E-03 6/2/2016 < 3.33E-03 (MDA) < 5.99E-03 (MDA) 6/9/2016 < 3.38E-03 (MDA) < 6.08E-03 (MDA) 6/16/2016 < 3.40E-03 (MDA) 4.95E-03 +/- 3.23E-03 6/23/2016 < 3.38E-03 (MDA) 3.86E-03 +/- 3.05E-03 6/30/2016 < 3.36E-03 (MDA) < 6.05E-03 (MDA) 7/7/2016 < 3.38E-03 (MDA)_ 7.04E-03 +/- 3.51 E-03 7/14/2016 < 3.32E-03 (MDA) 4.48E-03 +/- 3.1 OE-03 7/21/2016 < 3.39E-03 (MDA) 3.88E-03 +/- 3.06E-03 7/28/2016 < 3.43E-03 _(_MDA) 6.01 E-03 +/- 3.38E-03 8/4/2016 < 3.40E-03 (MDA) < 5.91 E-03 (MDA)

< 2.69E-03 < 3.02E-03 8/11/2016 < 3.38E-03 (MDA) < 5.88E-03 (MDA)

(MDA) (MDA) 8/18/2016 3.00E-03 +/- 2.14E-03 1.19E-02 +/- 4.09E-03 8/25/2016 < 3.40E-03 (MDA) 1.01 E-02 +/- 3.87E-03 9/1/2016 2.38E-03 +/- 1.88E-03 8.27E-03 +/- 3.62E-03 9/8/2016 < 3.41E-03 (MDA)_ 6.58E-03 +/- 3.42E-03 9/15/2016 2.41 E-03 +/- 1. 90 E-03 8.36E-03 +/- 3.66E-03 9/22/2016 2.38E-03 +/- 1.88E-03 1.49E-02 +/- 4.40E-03 9/29/2016 < 3.33E-03 (MDA) 1.19E-02 +/- 4.02E-03 10/6/2016 < 3.42E-03 (MDAl 5.88E-03 +/- 3.32E-03 10/13~16 < 3.34E-03 (MDA) 7.82E-03 +/- 3.54E-03 10/20/201'6 .. < 3.43E-03 (MDA) 8.39E-03 +/- 3.67E-03 10/27/2016 < 3.41 E-03 (MDA) 6.57E-03 +/- 3.42E-03 11/3/2016 < 3.39E-03 (MDA) 1. 78E-02 +/- 4. 71 E-03

< 1.15E-03 < 1.34E-03 11/10/2016 < 3.43E-03 (MDA) 1.09E-02 +/- 3.99E-03 (MDA) (MDA) 11/17/2016 < 3.85E-03 (MDA) 7.83E-03 +/- 3.92E-03 11/23/2016 < 3.04E-03 (MDA) 8.69E-03 +/- 3.42E-03 12/1/2016 2.39E-03 +/- 1.89E-03 9.01 E-03 +/- 3.74E-03 12/8/2016 < 3.35E-03 (MDA) 9.24E-03 +/- 3. 73E-03 12/15/2016 < 3.45E-03 (MDA) 1. 70E-02 +/- 4.69E-03 12/22/2016 < 3.92E-03 (MDA) 8.78E-03 +/- 4.09E-03 Table C-5 (Continued)

ODCM REQUIRED AIR SAMPLES: ANNEX BUILDING (AM3)

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

Co-60 Cs-137 12/30/2015 < 2.92E-03 (MDA) 1.43E-02 +/- 4.01 E-03 1/7/2016 < 3.40E-03 (MDA) < 6.13E-03 (MDA) 1/14/2016 < 3.38E-03 (MDA) 4.21 E-03 +/- 3.1OE-03 1/21/2016 2.37E-03 +/- 1.90E-03 5.62E-03 +/- 3.31 E-03 1/28/2016 < 3.32E-03 (MDA) 6.57E-03 +/- 3.41 E-03 2/4/2016 2.39E-03 +/- 1.91 E-03 1.88E-02 +/- 4.89E-03

<1.51 E-03 < 1.21 E-03 2/11/2016 < 3.39E-03 (MDA) 9.54E-03 +/- 3.86E-03 (MDA) (MDA) 2/18/2016 < 3.35E-03 (MDA) 7.68E-03 +/- 3.59E-03 2/25/2016 < 3.38E-03 (MDA) 6.67E-03 +/- 3.47E-03 3/3/2016 < 3.36E-03 (MDA) 4.89E-03 +/- 3.19E-03 3/10/2016 < 3.35E-03 (MDA) 1.05E-02 +/- 3.93E-03 1 1 3/17/2016 .* < 3.46E-03 (MDA) 7.56E-03 +/- 3.65E-03 3/24/2016 < 3.49E-03 (MDA) 8.00E-03 +/- 3.73E-03 3/31/2016 < 3.29E-03 (MDA) 1.27E-02 +/- 4.14E-03 4/7/2016 < 3.35E-03 (MDA) 1.14E-02 +/- 4.03E-03 4/14/2016 < 3.48E-03 (MDA) 9.78E-03 +/- 3.96E-03 4/21/2016 < 3.36E-03 _{MDA) 6.64E-03 +/- 3.45E-03 4/28/2016 < 1.21 E-03 (MDA) 8.97E-03 +/- 2.66E-03 5/5/2016 < 3.41 E-03 (MDA) 3.89E-03 +/- 3.07E-03

< 1.65E-03 < 1.38E-03 5/12/2016 < 3.37E-03 (MDA) 1.19E-02 +/- 4.11 E-03 (MDA) (MDA) 5/19/2016 < 3.34E-03 (MDA) < 6.02E-03 (MDA) 5/26/2016 < 3.39E-03 (MDA) 8.84E-03 +/- 3. 77E-03 6/2/2016 < 3.33E-03 (MDA) 3.45E-03 +/- 2.95E-03 6/9/2016~ < 5.68E-03 (MOAt < 1.02E-02 (MDAr' 6/16/2016 3.59E-03 +/- 2.36E-03 5.68E-03 +/- 3.35E-03 6/23/2016 < 3.36E-03 (MDA) < 6.05E-03 (MDA) 6/30/2016 < 3.38E-03 (MDA) < 6.08E-03 (MDA) 7/7/2016 < 3.38E-03 (MDA) < 6.08E-03 (MDA) 7/14/2016 < 3.32E-03 (MDA) < 5.97E-03 (MDA) 7/21/2016 < 3.39E-03 (MDA) 8.13E-03 +/- 3.67E-03 7/28/2016 < 3.41 E-03 (MDA) < 5.93E-03 (MDA) 8/4/2016 < 3.41E-03 (MDA) 4.11 E-03 +/- 3.05E-03

< 7.53E-04 < 2.80E-03 8/11/2016 < 3.39E-03 (MDA) < 5.88E-03 (MDA)

(MDA) (MDA) 8/18/2016 < 3.41 E-03 (MDA) < 5.93E-03 (MDA) 8/25/2016 < 3.40E-03 (MDA) 7.61 E-03 +/- 3.55E-03 9/1/2016 < 3.37E-03 (MDA) 1.14E-02 +/- 4.00E-03 9/8/2016 < 3.43E-03 (MDA) 6.97E-03 +/- 3.49E-03 9/15/2016 < 3.42E-03 (MDA) 6.24E-03 +/- 3.38E-03 9/22/2016 < 3.38E-03 (MDA) 7.21 E-03 +/- 3.47E-03 9/29/2016 < 3.33E-03 (MDA) 9.37E-03 +/- 3.72E-03 10/6/2016 < 3.40E-03 (MDA) 1.25E-02 +/- 4.17E-03 10/13/2016 < 3.35E-03 (MDA) < 5.82E-03 (MDA) 10/20/2016 2.40E-03 +/- 1.90E-03 9.74E-03 +/- 3.84E-03 10/27/2016 3.01 E-03 +/- 2.15E-03 8.74E-03 +/- 3.72E-03 11/3/2016 < 3.39E-03 (MDA) 1.25E-02 +/- 4.15E-03

< 1.55E-03 < 1.70E-03 11/10/2016 < 3.42E-03 (MDA) 1.19E-02 +/- 4.11 E-03 (MDA) (MDA) 11/17/2016 < 3.86E-03 (MDAl 7.85E-03 +/- 3.93E-03 11/23/2016 < 3.04E-03 (MDA) 3.35E-03 +/- 2.67E-03 12/1/2016 < 3.40E-03 (MDA) 4.79E-03 +/- 3.14E-03 12/8/2016 < 3.35E-03 _(MDA) 4.04E-03 +/- 3.00E-03 12/15/2016 < 3.45E-03 (MDA) 1.45E-02 +/- 4.42E-03 12/22/2016 < 3.92E-03 (MDA) < 6.81 E-03 (MDA)

Table C-5 (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-137 12/30/2015 2;05E-03 +/- 1.64E-03 1.86E-02 +/- 4.42E-03 1/7/2016 < 3.40E-03 (MOA) 4.60E-03 +/- 3.18E-03 1/14/2016 < 3.38E-03 (MOA) 6.33E-03 +/- 3.42E-03 1/21/2016 < 3.38E-03 (MOA) 6.32E-03 +/- 3.42E-03 1/28/2016 < 3.32E-03 (MOA) 7.95E-03 +/- 3.58E-03 2/4/2016 < 3.41E-03 (MOA) 2.52E-02 +/- 5.48E-03

<1.62E-03 < 1.57E-03 2/11/2016 < 3.39E-03 (MOA) 1.45E-02 +/- 4.42E-03 (MOA) (MOA) 2/18/2016 < 3.35E-03 (MOA) 1.50E-02 +/- 4.44E-03 2/25/2016 < 3.38E-03 (MOA) 1.58E-02 +/- 4.56E-03 3/3/2016 < 3.34E-03 (MOA) < 6.01 E-03 (MOA) 3/10/2016 < 3.37E-03 (MOA) 1.05E-02 +/- 3.96E-03 3/17/2016 < 3.31 E-03 (MOAl 1.35E-02 +/- 4.25E-03 3/24/2016 < 3.49E-03 (MOA) 1.02E-02 +/- 4.01 E-03 3/31/2016 2.31 E-03 +/- 1.85E-03 2.30E-02 +/- 5.17E-03 4/7/2016 2.97E-03 +/- 2.06E-03 2.35E-02 +/- 5.26E-03 4/14/2016 < 3.48E-03 (MOA) 1.99E-02 +/- 5.06E-03 4/21/2016 < 3.36E-03 (MOA) 6.29E-03 +/- 3.40E-03 4/28/2016 1.65E-03 +/- 8.53E-04 1.32E-02 +/- 3.01 E-03 5/5/2016 < 3.41 E-03 (MOAl 1.28E-02 +/- 4.25E-03

< 1.44E-03 < 1.11 E-03 5/12/2016 < 3.36E-03 (MOA) 1.40E-02 +/- 4.35E-03 (MOA) (MOA) 5/19/2016 2.35E-03 +/- 1.88E-03 3.48E-03 +/- 2.97E-03 5/26/2016 < 3.40E-03 (MOA) 1.03E-02 +/- 3.95E-03 6/2/2016 < 3.33E-03 (MOA) 3.80E-03 +/- 3.00E-03 6/9/2016,) < 5.43E-03 (MOAt < 9.77E-03 (MOAt 6/16/2016 < 3.41 E-03 (MOA) < 6.14E-03 (MOA) 6/23/2016 2.36E-03 +/- 1.89E-03 < 6.05E-03 (MOA) 6/30/2016 < 3.38E-03 (MOA) 3.50E-03 +/- 2.99E-03 7/7/2016 < 3.38E-03 _(MOA) < 6.08E-03 (MOA) 7/14/2016 2.33E-03 +/- 1.86E-03 7.94E-03 +/- 3.58E-03 7/21/2016 2.38E-03 +/- 1.91 E-03 7.42E-03 +/- 3.58E-03 7/28/2016 < 3.41 E-03 (MOA) < 5.93E-03 _(MOA) 8/4/2016 2.40E-03 +/- 1.90E-03 < 5.93E-03 (MOA)

< 2.09E-03 < 1.98E-03 8/11/2016 3.56E-03 +/- 2.32E-03 5.12E-03 +/- 3.18E-03 (MOA) (MOA) 8/18/2016 2.41 E-03 +/- 1.90E-03 5.18E-03 +/- 3.21 E-03 8/25/2016 < 3.40E-03 (MOA) 7.26E-03 +/- 3.50E-03 9/1/2016 < 3.37E-03 (MOA) 8.23E-03 +/- 3.60E-03 9/8/2016 < 3.43E-03 (MOA) 1.33E-02 +/- 4.27E-03 9/15/2016 < 3.42E-03 (MOA) 8.71 E-03 +/- 3.71 E-03 9/22/2016 < 3.38E-03 (MOA) 1.31 E-02 +/- 4.21 E-03 9/29/2016 < 3.33E-03 (MOA) 1.47E-02 +/- 4.36E-03 10/6/2016 2.40E-03 +/- 1.89E-03 7.97E-03 +/- 3.61 E-03 10/13/2016 < 3.35E-03 (MOA) 9.59E-03 +/- 3. 78E-03 10/20/2016 < 3.41 E-03 (MOA) 1.26E-02 +/- 4.18E-03 10/27/2016 < 3.43E-03 (MOA) 8.38E-03 +/- 3.67E-03 11/3/2016 < 3.39E-03 (MOA) 9.34E-03 +/- 3.77E-03

< 1.49E-03 < 1.34E-03 11/10/2016 < 3.41 E-03 (MOA) 6.93E-03 +/- 3.47E-03 (MOA) (MOA) 11/17/2016 < 3.88E-03 (MOA) 8.69E-03 +/- 4.05E-03 11/23/2016 < 3.04E-03 (MOA) 3.03E-03 +/- 2.62E-03 12/1/2016 < 3.40E-03 (MOA) 1.01 E-02 +/- 3.86E-03 12/8/2016 < 3.35E-03 (MOA) 6.12E-03 +/- 3.31 E-03 12/15/2016 3.63E-03 +/- 2.37E-03 1.88E-02 +/- 4.87E-03 12/22/2016 < 3.92E-03 (MOA) < 6.81 E-03 (MOA)

Table C-5 (Continued)

ODCM REQUIRED AIR SAMPLES: OIL WATER SEPARATOR (AM5)

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

Co-60 Cs-137 12/30/2015 2.56E-03 +/- 1.85E-03 1.16E-02 +/- 3.70E-03 1/7/2016 < 3.40E-03 (MDA) < 6.13E-03 (MDA) 1/14/2016 < 3.38E-03 (MDA) 5.27E-03 +/- 3.26E-03 1/21/2016 < 3.38E-03 (MDA) 5.97E-03 +/- 3.36E-03 1/28/2016 < 3.32E-03 (MDA) 6.22E-03 +/- 3.36E-03 2/4/2016 < 3.41 E-03 (MDA) 9.23E-03 +/- 3.82E-03

<1 .17E-03 < 1.15E-03 2/11/2016 < 3.39E-03 (MDA) 9.19E-03 +/- 3.81 E-03 (MDA) (MDA) 2/18/2016 < 3.35E-03 (MDA) 9.08E-03 +/- 3.76E-03 2/25/2016 < 3.38E-03 (MDA) 6.67E-03 +/- 3.47E-03 3/3/2016 < 3.34E-03 (MDA) < 6.01 E-03 (MDA) 3/10/2016 < 3.37E-03 (MDA) 1.09E-02 +/- 3.99E-03 3/17/2016 < 3.31 E-03 (MDA) 6.20E-03 +/- 3.35E-03 3/24/2016 < 3.49E-03 (MDA) 6.18E-03 +/- 3.48E-03 3/31/2016 < 3.29E-03 (MDA) 1.34E-02 +/- 4.23E-03 4/7/2016 .. 2.40E-03 +/- 1.83E-03.. 1.00E-02 +/- 3.87E-03..

4/14/2016 < 3.48E-03 (MDA) 1.27E-02 +/- 4.30E-03 4/21/2016 < 3.36E-03 (MDA) 8.40E-03 +/- 3.68E-03 4/28/2016 < 1.21 E-03 (MDA) 1.05E-02 +/- 2.80E-03 5/5/2016 < 3.41 E-03 (MDA) 9.58E-03 +/- 3.87E-03

< 1.56E-03 < 1.28E-03 5/12/2016 < 3.36E-03 (MDA) < 6.05E-03 (MDA)

(MDA) (MDA) 5/19/2016 < 3.35E-03 (MDA) 4.18E-03 +/- 3.08E-03 5/26/2016~ < 3.40E-03 (MOAt 9.91 E-03 +/- 3.90E-03:~

6/2/2016 < 3.37E-03 (MDA) < 6.06E-03 (MDA) 6/9/2016 2.37E-03 +/- 1.90E-03 5.63E-03 +/- 3.32E-03 6/16/2016 < 3.40E-03 (MDA) 4.24E-03 +/- 3.12E-03 6/23/2016 < 3.36E-03 (MDA) 7.70E-03 +/- 3.60E-03 6/30/2016 < 3.38E-03 (MDA) < 6.08E-03 (MDA) 7/7/2016 < 3.38E-03 (MDA) < 6.08E-03 (MDA) 7/14/2016 < 3.32E-03 (MDA) 6.21 E-03 +/- 3.36E-03 7/21/2016 < 3.39E-03 (MDA) 4.23E-03 +/- 3.12E-03 7/28/2016 < 3.41 E-03 (MDA) < 5.93E-03 (MDA) 8/4/2016 < 3.42E-03 (MDA) 5.18E-03 +/- 3.22E-03

< 8.88E-04 < 2.29E-03 8/11/2016 < 3.38E-03 (MDA) < 5.87E-03 _(MDA)_

(M+/-+/-+/-DA) (MDA) 8/18/2016 2.41 E-03 +/- 1.90E-03 6.94E-03 +/- 3.48E-03 8/25/2016 < 3.40E-03 (MDA) 7.97E-03 +/- 3.60E-03 9/1/2016 < 3.37E-03 (MDA) 1.24E-02 +/- 4.12E-03 9/8/2016 < 3.43E-03 (MDA) 1.44E-02 +/- 4.40E-03 9/15/2016 < 3.42E-03 (MDA) 7.30E-03 +/- 3.52E-03 9/22/2016 < 3.38E-03 (MDA) 1.21 E-02 +/- 4.08E-03 9/29/2016 < 3.33E-03 (MDA) 1.19E-02 +/- 4.02E-03 10/6/2016 < 3.40E-03 (MDA) 7.27E-03 +/- 3.50E-03 10/13/2016 < 3.37E-03 (MDA) 7.20E-03 +/- 3.47E-03 10/20/2016 2.40E-03 +/- 1.90E-03 1.33E-02 +/- 4.25E-03 10/27/2016 < 3.42E-03 (MDA) 6.25E-03 +/- 3.38E-03 11/3/2016 < 3.39E-03 (MDA) 1.11 E-02 +/- 3.98E-03

< 1.78E-03 < 1.70E-03 11/10/2016 < 3.41 E-03 (MDA) 1.05E-02 +/- 3.93E-03 (MDA) (MDA) 11/17/2016 2.73E-03 +/- 2.16E-03 9.08E-03 +/- 4.11 E-03 11/23/2016 < 3.04E-03 (MDA) 3.35E-03 +/- 2.67E-03 12/1/2016 < 3.40E-03 (MDA) 4.09E-03 +/- 3.04E-03 12/8/2016 < 3.35E-03 (MDA) 4.73E-03 +/- 3.1 OE-03 12/15/2016 3.03E-03 +/- 2.16E-03 1.38E-02 +/- 4.33E-03 12/22/2016 < 3.92E-03 (MDA) 9.18E-03 +/- 4.15E-03 Table C-5 (Continued)

ODCM REQUIRED AIR SAMPLES: HUMBOLDT HILL (STATION 3)

Sample AI ph a Activity Beta Activity Composite Gamma Date (pCi/m 3 ) (pCi/m 3 ) Activity (pCi/m 3 )

Co-60 Cs-137 12/30/2015 < 2.96E-03 (MDAl 1.05E-02 +/- 3.61 E-03 1/7/2016 < 3.35E-03 (MDA) < 6.04E-03 (MDA) 1/14/2016 < 3.40E-03 (MDA) < 6.11 E-03 (MDA) 1/21/2016 < 3.37E-03 (MDA) < 6.06E-03 (MDA) 1/28/2016 < 3.37E-03 (MDA) 4.90E-03 +/- 3.20E-03 2/4/2016 < 3.39E-03 _{_MDA) 1.20E-02 +/- 4.13E-03

<1.62E-03 < 1.39E-03 2/11/2016 < 3.34E-03 (MDA) 1.08E-02 +/- 3.95E-03 (MDA) (MDA) 2/18/2016 < 3.40E-03 (MDA) 5.30E-03 +/- 3.28E-03 2/25/2016 < 3.37E-03 (MDA) 5.25E-03 +/- 3.25E-03 3/3/2016 < 3.37E-03 (MDA) 4.91 E-03 +/- 3.20E-03 3/10/2016 < 3.36E-03 (MDA) 9.44E-03 +/- 3.82E-03 3/17/2016 < 3.32E-03 (MDA) 5.52E-03 +/- 3.25E-03 3/24/2016 2.41 E-03 +/- 1.93E-03 8.58E-03 +/- 3.76E-03 3/31/2016 < 3.38E-03 (MDA) 7.03E-03 +/- 3.51 E-03 4/7/2016 < 3.38E-03 (MDA) 1.19E-02 +/- 4.1 OE-03 4/14/2016 2.37E-03 +/- 1.90E-03 9.84E-03 +/- 3.87E-03 4/21/2016 < 3.36E-03 (MDA) < 6.05E-03 (MDA) 4/28/2016 9.19E-04 +/- 6.82E-04 5.87E-03 +/- 2.38E-03 5/5/2016 < 3.38E-03 (MDA) 4.92E-03 +/- 3.21 E-03

< 1.29E-03 < 1.30E-03 5/12/2016 < 3.35E-03 (MDA) 5.22E-03 +/- 3.23E-03 (MDA) (MDA) 5/19/2016 < 3.39E-03 (MDA) < 6.11 E-03 (MDA) 5/26/2016 < 3.35E-03 (MDA) 5.23E-03 +/- 3.24E-03 6/2/2016 < 3.37E-03 (MDA) < 6.06E-03 (MDA) 6/9/2016 < 3.39E-03 (MDA) < 6.1 OE-03 (MDA) 6/16/2016 < 3.36E-03 (MDA) 5.60E-03 +/- 3.30E-03 6/23/2016 < 3.38E-03 (MDA) 5.28E-03 +/- 3.27E-03 6/30/2016 < 3.36E-03 (MDA) 4.19E-03 +/- 3.08E-03 7/7/20161j < 3.38E-03 (MDA)c < 6.08E-03 (MDAl 7/14/2016 2.37E-03 +/- 1.90E-03 < 6.09E-03 (MDA) 7/21/2016 < 3.36E-03 (MDA) < 6.05E-03 (MDA) 7/28/2016 < 3.41 E-03 (MDA) < 5.93E-03 (MDA) 8/4/2016 < 3.41 E-03 (MDA) < 5.93E-03 (MDA)

< 2.34E-03 < 3.08E-03 8/11/2016 < 3.39E-03 (MDI\) < 5.89E-03 (MDA)

(MDA) (MDA) 8/18/2016 < 3.39E-03 (MDA) < 5.90E-03 (MDA) 8/25/2016 < 3.40E-03 (MDA) 5.15E-03 +/- 3.20E-03 9/1/2016 < 3.39E-03 (MDA) 8.29E-03 +/- 3.63E-03 9/8/2016 < 3.41 E-03 (MDA) 9.05E-03 +/- 3. 76E-03 9/15/2016 < 3.41 E-03 (MDA) 5.16E-03 +/- 3.21 E-03 9/22/2016 < 3.41 E-03 (MDA) 6.22E-03 +/- 3.37E-03 9/29/2016 < 3.31 E-03 (MDA) 1.14E-02 +/- 3.96E-03 10/6/2016 < 3.39E-03 (MDA) 5.84E-03 +/- 3.30E-03 10/13/2016 < 3.40E-03 (MDA) < 5.91 E-03 (MDA) 10/20/2016 < 3.40E-03 _(MDA) 8.67E-03 +/- 3.69E-03 10/27/2016 < 3.40E-03 (MDA) 4.44E-03 +/- 3.09E-03 11/3/2016 2.40E-03 +/- 1.90E-03 1.29E-02 +/- 4.22E-03

< 1.49E-03 < 1.27E-03 11/10/2016 < 3.39E-03 (MDA) 7.94E-03 +/- 3.59E-03 (MDA) (MDA) 11/17/2016 < 3.97E-03 (MDA) < 6.89E-03 (MDA) 11/23/2016 < 2.95E-03 (MDA) 5.39E-03 +/- 2.91 E-03 12/1/2016 < 3.42E-03 (MDA) < 5.94E-03 _{_MDA) 12/8/2016 < 3.37E-03 (MDA) 6.15E-03 +/- 3.33E-03 12/15/2016 < 3.43E-03 (MDA) 9.46E-03 +/- 3.81 E-03 12/22/2016 < 4.01 E-03 (MDA) 5.66E-03 +/- 3.71 E-03 Table C-5 Notes

1. Environmental air samplers at the Annex Building, Building 12 and the East Fence were affected by a planned site wide electrical outage on 3/18/2016. The air samplers were initially powered by generator and then reconnected to AC power at 16:45 hours. AC power was restored at approximately 23:1 0 hours0 days 0 hours 0 weeks 0 months on the same day. This was documented in corrective action SAPN 1415707.

2. On 7/14/2016, the REMP air sampler at the East Fence was found to be not operating. It was later determined the electrical power to the air sampler was disconnected by a Job Supervisor overseeing an excavation in the immediate vicinity. The sampler was disconnected from power at 8:30 a.m. and reconnected at 9:54a.m. on the same date. This was documented in corrective action SAPN 1420708.

3. The REMP air sampler at the Annex Building (AM3) was discovered to be not operating on 6/16/2016 with the totalizer displaying only 99 hours0.00115 days 0.0275 hours 1.636905e-4 weeks 3.76695e-5 months of run time . The REMP air sampler at the Relay Building was also found to be not operating on the same date with the totalizer displaying only 104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months of run time. Alpha and beta analyses of both air filters were based on the volume displayed by the totalizers. The beta MDA for the Annex Building was <1 .02E-02 pCilm 3 , slightly higher than the required LLD of 1.0E-02 pCi/m 3 , primarily due to the reduced run time. This was documented in corrective action SAPN 1419889.

4. AC power to the REMP air sampler at the Oily Water Separator was shut down from 10:07 hours to 11:10 hours on 4/13/2016 due to an electrical clearance. This was documented in corrective action SAPN 1415707.

5. The REMP air sampler at the Oily Water Separator was discovered to be malfunctioning on 6/2/2016; the pump did not appear to be drawing air through the filter. The air filter removed from the sampler appeared to have normal filter discoloration. Air sample results for gross counts as well as alpha activity, beta activity and total DAC fraction appeared to be within the normal range. This was documented in corrective action SAPN 1419126.

6. The REMP air sampler at Humboldt Hill was found to be malfunctioning on 7/14/2016. The pump did not appear to be drawing air through the filter and the filter appeared lighter than normal. RP Instrumentation personnel later determined the Hi-Q samplers were failing due to overheating.

Inspection of the instrument exhaust mufflers evidenced carbon clogging of the pump vanes. New mufflers were installed and the samplers allowed to operate for a day with no apparent increase in operating temperature.

This was documented in corrective action SAPN 1420706.

7. 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 6.0E-02 pCi/m 3 for Cs-137.

8. All LLD's were met for Gross Beta (required LLD 1.0E-02 Cilm 3 ), with the exception of the Annex Building in 6/2016. Due to the air sampler malfunction and shortened run time of 99 hours0.00115 days 0.0275 hours 1.636905e-4 weeks 3.76695e-5 months , the beta MDA for the weekly air sample was <1.02E-02 pCi/m 3 , slightly higher than the required LLD of 1.0E-02 pCi/m 3 .

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

10. 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 AM1 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.

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

... ., : .. : .~ '*

-. . *~. : : ; ';-

. . . . .. . ~

GPS Coordinates (NAD83/NAVD88 CA. Zone 1) Degree. Decimal / I Easting I Northing I el. Latitude I Longitude 5951260.28 I 2155706.11 I 234.94 40.72676 I -124.20274 FIGURE A-3 HBPP ONSITE TLD LOCATIONS Stations T1 - T16 {excluding T17)

~

T-8 fir T-9 n

T-7

ru:

- T-5

a T -*

Y

e:

- T-3 0~ ll!l:

)7; *-.... T-12 (1/**-.1,/

+150 NOTE:

CA.ZONE 1 / NADB3 NAVDBB HBPP ONSITE TLD LOCATIONS Monitoring Locations T7, T1 0, T11, T13, T16, T2, T3, and T5,generally represent REMP Site Boundary direct exposure monitoring locations in the 8 primary compass points beginning with T7 representing north and moving clockwise.

Location GPS Coordinates Number (NAD83/NAVD88 CA Zone 1)

Easting Northing Elevation T1 5949179 2160815 11 T2 5948805 2160711 12 T3 5948610 2161062 42 T4 5948779 2161270 44 T5 5949003 2161368 38 T6 5949160 2161437 36 T7 5949280 2161495 32 T8 5949417 2161565 25 T9 5949679 2161535 13 T10 5949913 2161634 11 T11 5950012 2161298 14 T12 5950019 2'160858 11 T13 5949842 2160718 10 T14 5949584 2160684 10 T15 5949449 2160601 10 T16 5949328 2160644 11 FIGURE A-4 HBPP OFFSITE TLD LOCATIONS Stations (1, 14 & 25) r

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

HBPP OFFSITE TLD LOCATION FORTUNA (Station 2)

GPS Coordinates (NAD83/NAVD88 CA. Zone 1) Degree. Decimal Easting I Northing I el. Latitude I Longitude 5962583.86 I 2105797.82 I 35.53 40.59057 l. -124.15746 FIGURE A-4 {Continued)

HBPP OFFSITE TLD LOCATION EUREKA {Control Location T17)

~~-~~*.:}£*~.~ ..

~~~i~(,;~:*~~~~~l~*(';. ..

-- -*--* .)i\ Oli>J-GPS Coordinates (NAD83/NAVD88 CA. Zone 1) Degree. Decimal Easting I

Northing I el. Latitude I Longitude 5976549.55 I 2175490.19 I 164.85 40.78276 I -124.11324 FIGURE A-5 HBPP GROUNDWATER SAMPLE POINTS KEY TO MONITORING WELLS RCW-CS-7 ~

INTERMEDIATE MW-11 WELLS RCW-SFP-1 RCW-SFP-2 RCW-SFP-3 RCW-SFP-4 RCW-SFP-5 RCW-SFP-6 DEEP WELLS RCW-CS-5 RCW-CS-6 RCW-CS-7 RCW-CS-8 RCW-CS-9 RCW-CS-10

. s RCW-CS-8 RCW-SFP-2 I' ~*

. * * .. . l?CW-SFPi,-4 EXPLANATION .' . I * * : ~

S GROUNDWATER MONITORING WELL ;

I I, ! , I,"

MW-1 LOCATION AND DESIGNATION . *, I

RCW-SrP2J i I i

- -*** .. s

- *

s*RCW-CS-9 l

1 !

I I

!* ll I . - ~/ *** . .

.11, I* ** ~l?qw~~ML,~:* .'

il

.d J** 'i_.*, , : ! '; *i *'

'I'.

'I!, i REACTOR CAISSON j*

YRm TRUE RCW-CS-10 SMW-11 PLANT

~Rcw.:...sFP-6' 0 NORTH 50' RCW-CS-SS 1 N=60' r:;;-zr--n Pacific Gas & Electric Site Plan e3_fLA_J Hw11boldt l)ay Pmwr Plant with RElvlP Well Locations Consulting Engim*L*rs Em:eka, Califomi,, Sl-IN OOfJ124.10oJ L-------------------------------------------------------------------------------L--&__G_e*_*l~~;~~*is_b_*,_ln_c_.__LJu_ll~'z_o1_6________~_o,__ xn~_-I_Dl_*K_ 'EI_11r_*.f_vi\_\'_-Lr__.,_.,~_2_01_4 __________~--~--

FIGURE B-1 OFFSITE ENVIRONMENTAL RADIATION LEVEL TRENDS 80.0 ~------------------------------------------------------------------------------------,

70.0 ,-,

II ' \

60.0 -~ ,, ... ________ ,,I

, ,- .... _,., .... _.... ~-

~---~' ~~~

~ 50.0 -::::::::===:::::

e<U 0::

E 40.0

<U rn 0

c 30.0

-King Salmon Picnic Area (Station 1)

Fortuna (Station 2) 20.0

South Bay School (Station 14)

--Humboldt Hill (Station 25) 10.0

- Myrtletown Substation (Station T17) 0.0 +-~--~--~-+--+-~--~--~-+--+-~--~--~-+--+-~--~--~-+--+-~--~--~-+--+-~--~

~

~

~

Year The baseline values for each location were obtained by averaging the readings at each location from 1977 through 1983. These values, however, were obtained using ion chambers instead of TLDs. The average annual values from 1977 through 1983 were Station 1 -83.0 mRem, Station 2-79.8 mRem, Station 14- 80.2 mRem, and Station 25-73.7 mRem.

FIGURE B-2 ONSITE ENVIRONMENTAL RADIATION LEVEL TRENDS 80.0 ~---------------------------------------------------------------------------------------,

70.0 60.0

/

~

~50.0 E

Q) 0::

....._' ~

~

E 40.0 Q) t/)

0 -..,._-Stations Near Radwaste Activities (T5-T8), 1989-2015 c 30.0

~Other Onsite Stations (T1-T4, T9-T16), 1989-2015 Radwaste Handling (T8-T10), 2016 20.0

.....,._Other Onsite Stations (T1-T7, T11-T16), 2016 10.0 0.0 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.

HBL-17-009, Submittal of Annual Radiological Environmental Monitoring Report for 2016

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HBL-17-009, Submittal of Annual Radiological Environmental Monitoring Report for 2016

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Dear Commissioners and Staff:

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