Text

Annual Radiological Environmental Monitoring Report for 2017
	ML18123A361
Person / Time
Site:	Humboldt Bay
Issue date:	04/26/2018
From:	Sharp L; Pacific Gas & Electric Co
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
	HBL-18-007
	Download: ML18123A361 (56)
	v • d • e

Pacific Gss and Loren D. Sharp 4111 Broad Street Electric Company* Senior Director Suite 120 Nuclear Decommissioning San Luis Obispo, CA 93401 Phone: 805.595.6481 Email: Loren.Sharp@pge.com April 26, 2018 PG&E Letter HBL-18-007 U.S. Nuclear Regulatory Commission ATIN: 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 2017

Dear Commissioners and Staff:

Enclosed is the Humboldt Bay Power Plant Unit 3, "Annual Radiological Environmental Monitoring Report" for 2017. This report provides the information required by Section 4.1 of the SAFSTOR/Decommissioning Offsite Dose Calculation Manual (ODCM).

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

Section B provides summaries, interpretations, and analyses of trends of the results of the REMP for the reporting period. The material provided is consistent with the objectives outlined in the ODCM, and in 10 CFR 50, Appendix I, Sections IV.8.2, 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.

m Document Control Desk PG&E Letter HBL-18-007 April 26, 2018 Page2 If you have any questions regarding information in the enclosed report, please contact Mr. Philippe Soenen at (805) 595-6461.

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

Enclosure PG&E Letter HBL-18-007 HUMBOLDT BAY POWER PLANT UNIT 3 ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT JANUARY 1 THROUGH DECEMBER 31, 2017

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

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

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

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

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

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

3. lnterlaboratory 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 .......... .... ........................ .. ...... ........ ....... ... .. ..... .... ... .. .... ........... 8

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

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

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

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

4. Waterborne Pathway ... ....... .. .......... .......... .... .. .. ..... ..... .. ........... .... .... ..... ............ . 11

a. Surface Water ...... ... ... .............. .. ..... .. ..... ... ........ ......... .... .. .. .... ... ....... .. .... ..... . 11

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TABLE OF CONTENTS (Continued)

b. Groundwater .... .. .................. ... ...... ...... .... ....... .......... ..... .. ....... .. .... ....... .... .. 11

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

.. .... ... .. .. ... ..... ..... ......... ........ .... ...... .. .... .... ...... ..... ..... .... .... .... 26 C-2 ONSITE ENVIRONMENTAL TLD STATIONS .. ...... ........... .... ..... .... .. ... .... ..... .... ... 28 C-3 OFFSITE (Control) ENVIRONMENTAL TLD STATIONS ...... ...... ... .... ... ..... .... .. .. .. 29 C-4 GROUNDWATER MONITORING WELL RESULTS ....... ..... .. ...... ..... ... ... .. ..... ...... 30 C-5 ODCM REQUIRED AIR SAMPLES ... ... .. ....... .......... ....... ..... .... .... .... .. .... ... .... ....... 33 LIST OF FIGURES Figure Page A-1 HBPP ONSITE AIR SAMPLE LOCATIONS .. ....... ....... .... .. .... .. ...... ... .... .... .. .......... 42 A-2 HBPP OFFSITE AIR SAMPLE LOCATION ... .......... ........... ... .... .......... .... .. .... ..... . 43 A-3 HBPP ONSITE TLD LOCATIONS .. .... ... ......... ....... .. ... ...... ...... ... ...... .... .. .... ....... .. . 44 A-4 HBPP OFFSITE TLD LOCATIONS ..... ... .... ... ........... .... ..... ..... .... ...... .. ....... ... ..... ... 45 A-5 HBPP GROUNDWATER SAMPLE POINTS ...... ............... .... ........ .... .... ...... ........ . 48 B-1 OFFSITE ENVIRONMENTAL RADIATION LEVEL TRENDS .... ..... ..... ..... .. ... .. ... . 49 B-2 ONSITE ENVIRONMENTAL RADIATION LEVEL TRENDS .. ........ ..... ... ... ... .. .... .. 50

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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, 2017 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, 2017, 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 lnterlaboratory Comparison Program.

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

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

A. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

1. Program Description The NRC Radiological Assessment Branch issued a 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 Humboldt Bay Power Plant (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. Mirian 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 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 . The composited samples are analyzed for gamma isotopic quarterly.

2. Direct Radiation The SAFSTOR ODCM requires 4 offsite environmental monitoring stations and 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, and 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 5 onsite 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. The composited samples are analyzed for gamma isotopic quarterly 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 additional TLDs were added around the independent spent fuel storage installation (ISFSI) in 2010 and have been transferred to the Diablo Canyon Power Plant Radiation Protection 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 3 TLDs, each containing a number of phosphors (normally 3) . The phosphor exposures for each TLD are averaged and then the 3 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 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 . Th is 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 12 intermediate and deep ground water wells were included in the 2017 groundwater monitoring initiative. Intermediate wells ranged in depth from 45 ft. to 69 ft. and were 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 ranged in depth from 83 ft. to 110 ft. and included RCW-CS-5, RCW-CS-6 , RCW-CS-7 , RCW-CS-8 , RCW-CS-9 and RCW-CS-10 . Wells were sampled during the first two quarters of 2017 . After May 2017 , formal closure of the ground water monitoring program was initiated. Well locations sampled in the first two quarters of 2017 are shown on Figure A-5, "HBPP GROUNDWATER SAMPLE POINTS ."

c. Other Monitoring Offsite 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 NRG-approved SAFSTOR Decommissioning Plan , (now identified as the PSDAR and DSAR) , these baseline conditions will only need to be reestablished prior to final decommi~sion ing if a sign ificant release occurs during SAFSTOR. The Environmental Report also contains a description of the demography and human activities within the environs surrounding the site.

3. lnterlaboratory 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 lnterlaboratory Cross-Check Program. HBPP count room personnel also participated in the Eckert & Ziegler lnterlaboratory 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 Mon itoring Program and Radioactive Material Control Program ."

GEL's Th ird-Party Cross-Check Program provides environmental matrices representative of HBPP analyses performed during 2017 and is intended to meet or exceed the inter-laboratory comparison program requirements of NRC Regulatory Guide 4.15. GEL analyzed 92 Eckert & Ziegler individual environmental sample analyses. All results met GEL's acceptance criteria (100 percent within acceptance) .

HBPP analyzed four sets of Eckert & Ziegler Analytics samples for gamma in soil , (first and fourth quarters), gamma air filter and alpha/beta air filter (second quarter) , and gamma in water and tritium in water (third quarter). These analyses are representative of those performed by HBPP count room personnel during 2017 . All results met the acceptance criteria with the exception of the fourth quarter gamma in soil analyzed on Detector 6 (Gamma Analyst) . Ce-141 with one gamma at 145.44 keV and a half-life of 32.5 days was reported conservatively high by Detector 6. The problem was documented in corrective action SAPN 1426132.

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 state of decommissioning at HBPP, isolation of the caisson and removal of the source term from plant support structures, there remains little potential for ground water to become contaminated during the final stages of decommissioning . Formal closure of the ground water monitoring wells was initiated in 2017, and will continue through 2018 . Ground water monitoring wells are being closed in accordance with local water authority guidance and permits under Work Package 99-28, "Well Abandonment. " Sampling of ground water monitoring wells was discontinued after the second quarter of 2017 .

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

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

1. General Comments The Environmental Report, subm itted 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 B-1 , "OFFSITE ENVIRONMENTAL RADIATION LEVEL TRENDS. " A plot of the radiation level trends for onsite stations is shown in Figu re B-2 ,

"ONSITE ENVIRONMENTAL RADIATION LEVEL TRENDS." The plots show that the offsite annual doses continue to be within the ranges that have been observed over the last ten years.

HBPP changed TLD processing services in January 2014. Data from previous years was based on a Panasonic TLD system . Data in 2014 to the present is based on the Mirian Genesis type TLD system. The apparent rise in Figures B-1 and B-2 after 2014 may be a result of the change in monitoring devices in tandem with the increase in decommissioning activities.

Figure B-2 includes the average dose for two groups of onsite stations, selected by their potential to be affected by radioactive waste handling activities.

Figure B-2 also shows that dose measurement variations can be attributed to in-plant sources and low-level waste packaging and sh ipping 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 20 16, the radioactive waste handling area was relocated and direct radiation exposure pathway monitoring was provided by TLDs T8 , T9, and T10. 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 T8 throughT10 , 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 5 offsite TLDs, the dose to the maximum exposed individual from this source was approximately 0.1 millirem (mrem) above background. The slight increase in dose is documented in corrective action SAPN 1439150.

The Humboldt Bay ISFSI is licensed under 10 CFR 72 , but is contained within the licensed boundary of the HBPP site, so no other dose contributions to the public are considered. The HBPP site had no measurable liquid or gaseous radioactive effluents that would challenge the limitations of 40 CFR 190. The direct dose is the only contributor to public dose and is within the 25 mrem limit to the whole body.

3. Airborne Pathway Offsite 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 NRG-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 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 ODGM. The Environmental Report, submitted to the NRG as Attachment 6 to SAFSTOR License Amendment Request 84-01, established baseline conditions for the ingestion pathway. In accordance with the NRG-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 ODGM 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 ODGM. The Environmental Report, submitted to the NRG as Attachment 6 to SAFSTOR License Amendment Request 84-01, established baseline conditions for the terrestrial pathway. In accordance with the NRG-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 ODGM 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 G-1 in the format of the BTP Table 3.

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 G-1 of this report, with the exception of three environmental gross beta air sample analysis results which could not meet the required LLD of 1.0E-02 pGi/m 3 , primarily due to an air sample pump malfunction and reduced run time.

Because alpha and beta radioactivity analyses of the saline ground water are less effective than tritium and gamma radioactivity analyses , the ODGM 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 onsite locations near the OCA fence line, and at 4 offsite environmental monitoring stations and 1 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 TLD sets are exchanged quarterly. The reported result and its standard error are calculated from the measurements of multiple elements in the TLD triplet. Resu lts of the onsite and offsite monitoring are provided in Tables C-2 and C-3, respectively.

At the end of the first quarter of 2017, environmental TLDs T2 and T9 were relocated due to decommissioning activities within the respective areas . The relocations were performed during the quarterly TLD changeout and new global positioning system (GPS) coordinates were obtained . This was documented in corrective action SAPN 1428502.

Corrective action SAPN 1439150 documents the increase in dose rate on TLD T9 at the site fence line. T9 displayed the maximum dose of all fence line TLDs for the second , third , and fourth quarters of 2017. The increase in dose rate is most likely due to the transportation of radioactive soil and concrete from the caisson to the soil management facilities (SMFs) along the "haul road "

which runs adjacent to the Coastal Trail, as well as the transfer of radwaste bags and intermodals from the SMFs to the waste management facility for shipment offsite. Using the maximum quarterly dose as seen on TLDs T8 , T9 ,

and T10 which lie along the waste transportation route and subtracting the average dose from offsite TLDs 1, 2, 14, 25, and T17 results in an additional 0.10 mrem at the fence line based on the 67-hour occupancy.

3. Airborne Pathway Five onsite samples and one offsite sample were collected and analyzed weekly for gross beta and gross alpha activity.

The requi red 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 LLDs were met for gross beta (required LLD 1.0E-02 pCi/m3), with the exception of the following :

Humboldt Hill air sampler suffered a mechanical malfunction after approximately 41 minutes of run time in June 2017. Although extended count times were employed , the required LLD for gross beta of 1.0E-02 pCi/m 3 could not be obtained . This deficiency was noted in corrective action SAPN 1430964.

On July 13, 2017, the REMP air sampler outside Building 12 (AM2) was found to be running but not drawing air through the filter. Internal vanes within the sampler were discovered to be severely broken. Because an accurate totalizer reading could not be obtained , the air filter was marked as "Information Only. " Th is deficiency was noted in corrective action SAPN 1432351 .

On 11/17/2017, the REMP air sampler at Humboldt Hill was found to be not operating after approximately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of run time . Although extended count times were employed , the required LLD for gross beta of 1.0E-02 pCi/m 3 could .not be obtained . This deficiency was noted in corrective action SAPN 1436695.

Additional interruptions of continuous REMP air sampler operations occurred on the following dates due to ongoing decomm issioning activities :

Date SAPN Description 5/10/2017 1430423 Oily water separator (OWS) air sampler (AM5) was taken out of service for less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months due to remediation/demolition activities within the near vicinity and relocation of the air sampler.

5/25/2017 1430972 Humboldt Hill air sampler suffered a blown fuse .

6/8/2017 1431460 OWS air sampler (AM5) lost electrical power after de-energizing Lift Station 3. Drawings failed to identify Lift Station 3 as the source of electrical power for the REMP sampler.

9/1/2017 1434019 Planned electrical power outage affected REMP samplers at the Annex (AM3) and Building 12 (AM2).

Annex sampler was powered by generator but Building 12 sampler lost power.

9/28/2017 1434996 Planned electrical power outage affected REMP sampler at the Annex (AM3) . Sampler lost electrical power for approximately 2 to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

10/20/2017 1436302 Building 12 (AM2) air sampler lost electrical power while removing utilities from the 12-series trailers.

Power was temporarily restored until a permanent source of power could be supplied.

11/13/2017 1436694 At approximately 4 a.m. , the Annex Building lost electrical power due to weather conditions. This affected the REMP air sampler located at the Annex (AM3) .

12/19/2017 1437846 OWS air sampler (AM5) was taken out of service for approximately 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months due to de-energizing Lift Station 3 for performance of maintenance activities.

On May 4, 2017 , the gas flow proportional counter gross beta source check fell below the lower warning limit on the quality control (QC) chart and was not investigated. REMP air filters were analyzed on the same date. The error was discovered on June 4, 2017, and the routine air filters were reanalyzed. A review of the revised air sample results indicated the required LLD was achieved and that there were no appreciable differences in the gross alpha or gross beta air sample results. This was documented in corrective action SAPN 1431432.

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 12 monitoring wells located to monitor for leakage from the spent fuel pool (SFP). Sampling of these monitoring wells was performed during the first and second quarters of 2017 in accordance with plant procedures.

Detailed results of groundwater monitoring during the first and second quarters of 2017 are provided in Table C-4.

Tritium concentrations for all wells listed in Table C-4 during 2017 were less than the MDA of approximately 300 pCi/liter. All of the monitoring wells are inside the OCA boundary, and the groundwater is saline and is not used now nor likely to be used in the future for either direct consumption or for agricultural purposes. Therefore, there is no groundwater waterborne pathway for a member of the public. None of the other ODCM required REMP samples indicated detectable levels of tritium or gamma radioactivity.

Because alpha and beta radioactivity analyses of the saline groundwater are less effective than tritium and gamma radioactivity analyses for monitoring potential SFP leakage, plant procedures do not currently require alpha and beta radioactivity analyses to be part of the SAFSTOR REMP .

Nevertheless, alpha and beta radioactivity analyses are performed as a matter of plant policy, in order to maintain a historical record of this parameter for the remainder of SAFSTOR. These results are included in Table C-4 , but are not considered part of the SAFSTOR REMP.

During the first quarter of 2017, monitoring wells RCW-CS-8 and RCW-SFP-4, located in the final site survey (FSS) area of the upper yard ,

exhibited higher than normal turbidity measurements during the well sampling event. The wells were located adjacent to each other in a small depression and at the time of sampling , dirt and gravel were noted to be covering the well lids. Sediment due to surface influence likely contributed to the higher than normal turbidity measurements rather than significant disturbance of the water column or excessive stress placed on the formation .

GEL analytical results for these two sample sets appear to be in agreement with values previously reported for these wells. This was documented in corrective action SAPN 1428500.

The tritium sample collected from RCW-CS-5 during the first quarter monitoring well campaign sustained damage during shipment to GEL. In its place, GEL agreed to take water from the nitric acid !)reserved RCW-CS-5 sample and analyze it for tritium. Activity value reported appeared normal and less than the required LLD . This was documented in corrective action SAPN 1428501 .

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 NRG, 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 OOCMIODAM.

HBPP Response to 2.2:

There were no reports or notifications required to be generated in 2017 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 NRG 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 2017 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-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-10. A summary of the sample results are provided in Section C.

There were no significant onsite leaks/spills into groundwater in 2017.

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 Parkinq 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 2017 Date Value Value (pCi/L) (pCi/L)

Gamma Water 1-131 E11821 1st 7/07/2017 9.68E+01 8.79E+01 1.10 Acceptable Ce-141 E11821 1st 7/07/2017 1.24E+02 1.19E+02 1.05 Acceptable Cr-51 E11821 1st 7/07/2017 2.43E+02 2.11E+02 1.15 Acceptable Cs-134 E11821 1st 7/07/2017 1.84E+02 1.88E+02 0.98 Acceptable Cs-137 E11821 1st 7/07/2017 2.49E+02 2.26E+02 1.10 Acceptable Co-58 E11821 1st 7/07/2017 1.88E+02 1.77E+02 1.06 Acceptable Mn-54 E11821 1st 7/07/2017 2.79E+02 2.48E+02 1.13 Acceptable Fe-59 E11821 1st 7/07/2017 1.46E+02 1.27E+02 1.15 Acceptable Zn-65 E11821 1st 7/07/2017 3.36E+02 2.95E+02 1.14 Acceptable Co-60 E11821 1st 7/07/2017 3.07E+02 2.92E+02 1.05 Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2017 Date Value Value (pCi/L) (pCi/L)

Milk Sr-89 E11819 1st 7/07/2017 8.86E+01 9.96E+01 0.89 Acceptable Sr-90 E11819 1st 7/07/2017 1.97E+01 2.55E+01 0.77 Acceptable 1-131 E11820 1st 7/07/2017 9.57E+01 9.68E+01 0.99 Acceptable Ce-141 E11820 1st 7/07/2017 1.21 E+02 1.19E+02 1.02 Acceptable Cr-51 E11820 1st 7/07/2017 1.76E+02 2.12E+02 0.83 Acceptable Cs-134 E11820 1st 7/07/2017 1.71E+02 1.89E+02 0.90 Acceptable Cs-137 E11820 1st 7/07/2017 2.31 E+02 2.27E+02 1.02 Acceptable Co-58 E11820 1st 7/07/2017 1.89E+02 1.78E+02 1.06 Acceptable Mn-54 E11820 1st 7/07/2017 2.74E+02 2.49E+02 1.10 Acceptable Fe-59 E11820 1st 7/07/2017 1.35E+02 1.27E+02 1.06 Acceptable Zn-65 E11820 1st 7/07/2017 3.22E+02 2.96E+02 1.09 Acceptable Co-60 E11820 1st 7/07/2017 2.85E+02 2.93E+02 0.97 Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2017 Date Value Value (pCi) (pCi)

Cartridge 1-131 E11818 1st 7/07/2017 9.93E+01 9.46E+01 1.05 Acceptable TABLE A-3 (Continued)

GEL PARTICIPATION - INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2017 Date Value Value (pCi/L) (pCi/L)

Gamma Water 1-131 E11876 2nd 8/2/2017 8.69E+01 8.12E+01 1.07 Acceptable Ce-141 E11876 2nd 8/2/2017 2.09E+02 1.99E+02 1.05 Acceptable Cr-51 E11876 2nd 8/2/2017 4.41 E+02 4 .13E+02 1.07 Acceptable Cs-134 E11876 2nd 8/2/2017 2.38E+02 2.47E+02 0.96 Acceptable Cs-137 E11876 2nd 8/2/2017 2.20E+02 1.97E+02 1.12 Acceptable Co-58 E11876 2nd 8/2/2017 2.11 E+02 2.04E+02 1.04 Acceptable Mn-54 E11876 2nd 8/2/2017 2.43E+02 2.25E+02 1.08 Acceptable Fe-59 E11876 2nd 8/2/2017 1.64E+02 1.51 E+02 1.09 Acceptable Zn-65 E11876 2nd 8/2/2017 2.95E+02 2.67E+02 1.10 Acceptable Co-60 E11876 2nd 8/2/2017 2.57E+02 2.50E+02 1.03 Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2017 Date Value Value (pCi/L) (pCi/L)

Milk Sr-89 E11874 2nd 8/2/2017 8.88E+01 9.26E+01 0.96 Acceptable Sr-90 E11874 2nd 8/2/2017 9.50E+OO 1.35E+01 0.71 Acceptable 1-131 E11875 2nd 8/2/2017 9.93E+0 1 9.36E+01 1.06 Acceptable Ce-141 E11875 2nd 8/2/2017 1.62E+02 1.51 E+02 1.07 Acceptable Cr-51 E11875 2nd 8/2/2017 3.65E+02 3.15E+02 1.16 Acceptable Cs-134 E11875 2nd 8/2/2017 1.74E+02 1.88E+02 0.92 Acceptable Cs-137 E11875 2nd 8/2/2017 1.57E+02 1.50E+02 1.05 Acceptable Co-58 E11875 2nd 8/2/2017 1.53E+02 1.55E+02 0.98 Acceptable Mn-54 E11875 2nd 8/2/2017 1.95E+02 1.72E+02 1.14 Acceptable Fe-59 E11875 2nd 8/2/2017 1.28E+02 1.15E+02 1.11 Acceptable Zn-65 E11875 2nd 8/2/2017 2.18E+02 2.04E+02 1.07 Acceptable Co-60 E11875 2nd 8/2/2017 2.07E+02 1.91 E+02 1.08 Acceptable Sample/ Radionuclide Sample Quarter Report GEL Reference Ratio Evaluation Analysis Number 2017 Date Value Value (pCi) (pCi)

Cartridge 1-131 E11873 2nd 8/2/2017 8.65E+01 8.46E+01 1.02 Acceptable TABLE A-3 (Continued)

GEL PARTICIPATION-INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report Date GEL Reference Ratio Evaluation Analysis Number 2017 Value Value (pCi/L) (pCi/L)

Gamma Water 1-131 E11929 3rd 11/10/2017 8.08E+01 7.92E+01 1.02 Acceptable Ce-141 E11929 3rd 11/10/2017 1.09E+02 9.95E+01 1.10 Acceptable Cr-51 E11929 3rd 11/10/2017 2.47E+02 2.48E+02 1.00 Acceptable Cs-134 E11929 3rd 11/10/2017 2.06E+02 2.29E+02 0.90 Acceptable Cs-137 E11929 3rd 11/10/2017 2.00E+02 1.96E+02 1.02 Acceptable Co-58 E11929 3rd 11/10/2017 1.41 E+02 1.34E+02 . 1.05 Acceptable Mn-54 E11929 3rd 11/10/2017 1.50E+02 1.40E+02 1.07 Acceptable Fe-59 E11929 3rd 11/10/2017 1.58E+02 1.43E+02 1.10 Acceptable Zn-65 E11929 3rd 11/10/2017 2.37E+02 2.10E+02 1.13 Acceptable Co-60 E11929 3rd 11/10/2017 3.18E+02 2.99E+02 1.06 Acceptable Sample/ Radionuclide Sample Quarter Report Date GEL Reference Ratio Evaluation Analysis Number 2017 Value Value (pCi/L) (pCi/L)

Milk Sr-89 E11927 3rd 11/10/2017 7.50E+01 8.27E+01 0.91 Acceptable Sr-90 E11927 3rd 11/10/2017 1.01 E+01 1.21E+01 0.84 Acceptable 1-131 E11928 3rd 11/10/2017 7.35E+01 7.10E+01 1.04 Acceptable Ce-141 E11928 3rd 11/10/2017 8.31 E+01 8.70E+01 0.95 Acceptable Cr-51 E11928 3rd 11/10/2017 2.37E+02 2.17E+02 0.92 Acceptable Cs-134 E11928 3rd 11/10/2017 1.85E+02 2.01 E+02 0.92 Acceptable Cs-137 E11928 3rd 11/10/2017 1.67E+02 1.72E+02 0.97 Acceptable Co-58 E11928 3rd 11/10/2017 1.21 E+02 1.17E+02 1.03 Acceptable Mn-54 E11928 3rd 11/10/2017 1.28E+02 1.23E+02 1.04 Acceptable Fe-59 E11928 3rd 11/10/2017 1.56E+02 1.25E+02 1.24 Acceptable Zn-65 E11928 3rd 11/10/2017 1.97E+02 1.84E+02 1.07 Acceptable Co-60 E11928 3rd 11/10/2017 2.59E+02 2.62E+02 0.99 Acceptable Sample/ Radionuclide Sample Quarter Report Date GEL Reference Ratio Evaluation Analysis Number 2017 Value Value (pCi) (pCi)

Cartridge 1-131 E11926 3rd 11/10/2017 6.30E+01 6.48E+01 0.97 Acceptable TABLE A-3 (Continued)

GEL PARTICIPATION-INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample/ Radionuclide Sample Quarter Report Date GEL Reference Ratio Evaluation Analysis Number 2017 Value Value (pCi/L) (pCi/L)

Gamma Water 1-131 E12070 4th 2/02/2018 5.36E+01 4.95E+01 1.08 Acceptable Ce-141 E12070 4th 2/02/2018 6.60E+01 6.24E+01 1.06 Acceptable Cr-51 E12070 4th 2/02/2018 1.68E+02 1.54E+02 1.09 Acceptable Cs-134 E12070 4th 2/02/2018 7.47E+01 7.92E+01 0.94 Acceptable Cs-137 E12070 4th 2/02/2018 9.31 E+01 8.97E+01 1.04 Acceptable Co-58 E12070 4th 2/02/2018 5.95E+01 5.70E+01 1.04 Acceptable Mn-54 E12070 4th 2/02/2018 1.14E+02 1.02E+02 1.12 Acceptable Fe-59 E12070 4th 2/02/2018 8.74E+01 7.19E+01 1.22 Acceptable Zn-65 E12070 4th 2/02/2018 1.57E+02 1.34E+02 1.17 Acceptable Co-60 E12070 4th 2/02/2018 1.15E+02 1.10E+02 1.05 Acceptable Sample/ Radionuclide Sample Quarter Report Date GEL Reference Ratio Evaluation Analysis Number 2017 Value Value (pCi/L) (pCi/L)

Milk Sr-89 E12068 4th 2/02/2018 9.54E+01 9.23E+01 1.03 Acceptable Sr-90 E12068 4th 2/02/2018 1.34E+01 1.69E+01 0.79 Acceptable 1-131 E12069 4th 2/02/2018 6.59E+01 5.78E+01 1.14 Acceptable Ce-141 E12069 4th 2/02/2018 1.07E+02 9.83E+01 1.09 Acceptable Cr-51 E12069 4th 2/02/2018 2.69E+02 2.42E+02 1.11 Acceptable Cs-134 E12069 4th 2/02/2018 1.20E+02 1.25E+02 0.96 Acceptable Cs-137 E12069 4th 2/02/2018 1.63E+02 1.41 E+02 1.15 Acceptable Co-58 E12069 4th 2/02/2018 9.29E+01 8.99E+01 1.03 Acceptable Mn-54 E12069 4th 2/02/2018 1.79E+02 1.61 E+02 1.11 Acceptable Fe-59 E12069 4th 2/02/2018 1.27E+02 1.13E+02 1.12 Acceptable Zn-65 E12069 4th 2/02/2018 2.34E+02 2.11 E+02 1.11 Acceptable Co-60 E12069 4th 2/02/2018 1.95E+02 1.73E+02 1.13 Acceptable Sample/ Rad ion ucl ide Sample Quarter Report Date GEL Reference Ratio Evaluation Analysis Number 2017 Value Value (pCi) (pCi)

Cartridge 1-131 E12067 4th 2/02/2018 4.84E+01 4.81 E+01 1.01 Acceptable TABLE A-4 HBPP PARTICIPATION-ECKERT & ZIEGLER INTERLABORATORY CROSS-CHECK PROGRAM DATA Sample Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2017 Date (pCi/g) (pCi/g)

Gamma Soil Ce-141 E11788 1st 4/18/2017 2.75E-01 2.50E-01 1.10 Acceptable Detector 1 Cr-51 E11788 1st 4/18/2017 4.76E-01 5.00E-01 0.95 Acceptable Cs-134 E11788 1st 4/18/2017 2.05E-01 2.07E-01 0.99 Acceptable Cs-137 E11788 1st 4/18/2017 3.03E-01 3.17E-01 0.96 Acceptable Co-58 E11788 1st 4/18/2017 2.65E-01 2.58E-01 1.03 Acceptable Mn-54 E11788 1st 4/18/2017 3.06E-01 2.83E-01 1.08 Acceptable Fe-59 E11788 1st 4/18/2017 2.32E-01 2.22E-01 1.04 Acceptable Zn-65 E11788 1st 4/18/2017 3.57E-01 3.44E-01 1.04 Acceptable Co-60 E11788 1st 4/18/2017 3.15E-01 3.15E-01 1.00 Acceptable Sample Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2017 Date (pCi/a) (pCi/g)

Gamma Soil Ce-141 E11788 1st 4/18/2017 2.64E-01 2.50E-01 1.06 Acceptable Detector 3 Cr-51 E11788 1st 4/18/2017 4.71 E-01 5.00E-01 0.94 Acceptable Cs-134 E11788 1st 4/18/2017 2.00E-01 2.07E-01 0.97 Acceptable Cs-137 E11788 1st 4/18/2017 3.16E-01 3.17E-01 1.00 Acceptable Co-58 E11788 1st 4/18/2017 2.48E-01 2.58E-01 0.96 Acceptable Mn-54 E11788 1st 4/18/2017 3.02E-01 2.83E-01 1.07 Acceptable Fe-59 E11788 1st 4/18/2017 2.24E-01 2.22E-01 1.01 Acceptable Zn-65 E11788 1st 4/18/2017 3.52E-01 3.44E-01 1.02 Acceptable Co-60 E11788 1st 4/18/2017 3.11 E-01 3.15E-01 0.99 Acceptable Sample Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2017 Date (pCi/g) (pCi/g)

Gamma Soil Ce-141 E11788 1st 4/18/2017 2.56E-01 2.50E-01 1.02 Acceptable Detector 5 Cr-51 E11788 1st 4/18/2017 4.77E-01 5.00E-01 0.95 Acceptable Cs-134 E11788 1st 4/18/2017 1.97E-01 2.07E-01 0.95 Acceptable Cs-137 E11788 1st 4/18/2017 3.14E-01 3.17E-01 0.99 Acceptable Co-58 E11788 1st 4/18/2017 2.50E-01 2.58E-01 0.97 Acceptable Mn-54 E11788 1st 4/18/2017 2.99E-01 2.83E-01 1.06 Acceptable Fe-59 E11788 1st 4/18/2017 2.29E-01 2.22E-01 1.03 Acceptable Zn-65 E11788 1st 4/18/2017 3.46E-01 3.44E-01 1.01 Acceptable Co-60 E11788 1st 4/18/2017 3.12E-01 3.15E-01 0.99 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 2017 Date (pCi/L) (pCi/L)

Gamma Soil Ce-141 E11788 1st 4/18/2017 2.55E-01 2.SOE-01 1.02 Acceptable Detector 6 Cr-51 E11788 1st 4/18/2017 4.82E-01 5.00E-01 0.96 Acceptable Cs-134 E11788 1st 4/18/2017 1.91 E-01 2.07E-01 0.92 Acceptable Cs-137 E11788 1st 4/18/2017 3.08E-01 3.17E-01 0.97 Acceptable Co-58 E11788 1st 4/18/2017 2.55E-01 2.58E-01 0.99 Acceptable Mn-54 E11788 1st 4/18/20 17 2.89E-01 2.83E-01 1.02 Acceptable Fe-59 E11788 1st 4/18/2017 2.28E-01 2.22E-01 1.03 Acceptable Zn-65 E11788 1st 4/18/2017 3.60E-01 3.44E-01 1.05 Acceptable Co-60 E11788 1st 4/18/2017 3.18E-01 3.1SE-01 1.01 Acceptable Sample Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2017 Date (pCi) (pCi)

Air Filter Gross Alpha E11855 2nd 6/27/2017 4.46E+01 1 3.99E+01 1.12 Acceptable Protean 7108 Gross Beta E11855 2nd 6/27/2017 2.09E+02 1 2.11E+02 0.99 Acceptable Sample Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2017 Date (pCi) (pCi)

Air Filter Gross Alpha E11855 2nd 6/27/2017 4.61 E+01 1 3.99E+01 1.16 Acceptable Protean 7109 Gross Beta E11855 2nd 6/27/2017 2.07E+02 1 2.11 E+02 0.98 Acceptable Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2017 Date (pCi) (pCi)

Gamma Air Ce-141 E11856 2nd 6/27/2017 1.24E+02 1.17E+02 1.06 Acceptable Filter Cr-51 E11856 2nd 6/27/2017 2.34E+02 2.44E+02 0.96 Acceptable Detector 1 Cs-134 E11856 2nd 6/27/2017 1.34E+02 1.46E+02 0.92 Acceptable Cs-137 E11856 2nd 6/27/2017 1.22E+02 1.16E+02 1.05 Acceptable Co-58 E11856 2nd 6/27/2017 1.24E+02 1.21 E+02 1.03 Acceptable Mn-54 E11856 2nd 6/27/2017 1.39E+02 1.33E+02 1.04 Acceptable Fe-59 E11856 2nd 6/27/2017 9.85E+01 8.94E+01 1.10 Acceptable Zn-65 E11856 2nd 6/27/2017 1.71E+02 1.58E+02 1.08 Acceptable Co-60 E11856 2nd 6/27/2017 1.53E+02 1.48E+02 1.03 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 2017 Date (pCi/L) (pCi/L)

Gamma Air Ce-141 E11856 2nd 6/27/2017 1.15E+02 1.17E+02 0.98 Acceptable Filter Cr-51 E11856 2nd 6/27/2017 2.45E+02 2.44E+02 1.00 Acceptable Detector 3 Cs-134 E11856 2nd 6/27/2017 1.29E+02 1.46E+02 0.88 Acceptable Cs-137 E11856 2nd 6/27/2017 1.21 E+02 1.16E+02 1.04 Acceptable Co-58 E11856 2nd 6/27/2017 1.21 E+02 1.21 E+02 1.00 Acceptable Mn-54 E11856 2nd 6/27/2017 1.43E+02 1.33E+02 1.07 Acceptable Fe-59 E11856 2nd 6/27/2017 9.86E+01 8.94E+01 1.10 Acceptable Zn-65 E11856 2nd 6/27/2017 1.63E+01 1.58E+02 1.03 Acceptable Co-60 E11856 2nd 6/27/2017 1.51 E+02 1.48E+02 1.02 Acceptable Sample Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2017 Date (pCi) (pCi)

Gamma Air Ce-141 E11856 2nd 6/27/2017 1.23E+02 1.17E+02 1.05 Acceptable Filter Cr-51 E11856 2nd 6/27/2017 2.57E+02 2.44E+02 1.05 Acceptable Detector 5 Cs-134 E11856 2nd 6/27/2017 1.33E+02 1.46E+02 0.91 Acceptable Cs-137 E11856 2nd 6/27/2017 1.20E+02 1.16E+02 1.03 Acceptable Co-58 E11856 2nd 6/27/2017 1.22E+02 1.21 E+02 1.01 Acceptable Mn-54 E11856 2nd 6/27/2017 1.40E+02 1.33E+02 1.05 Acceptable Fe-59 E11856 2nd 6/27/2017 1.00E+02 8.94E+01 1.12 Acceptable Zn-65 E11856 2nd 6/27/2017 1.72E+02 1.58E+02 1.09 Acceptable Co-60 E11856 2nd 6/27/2017 1.57E+02 1.48E+02 1.06 Acceptable Sample Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2017 Date (pCi) (pCi) 3 TriCarb Tritium (H ) E11912 3rd 10/5/2017 2.91E+03 2.82E+03 1.03 Acceptable Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2017 Date (pCi) (pCi)

Gamma Water Ce-141 E11913 3rd 10/5/2017 1.04E+02 9.95E+01 1.05 Acceptable Detector 1 Cr-51 E11913 3rd 10/5/2017 2.60E+02 2.48E+02 1.05 Acceptable Cs-134 E11913 3rd 10/5/2017 2.04E+02 2.29E+02 0.89 Acceptable Cs-137 E11913 3rd 10/5/2017 1.96E+02 1.96E+02 1.00 Acceptable Co-58 E11913 3rd 10/5/2017 1.30E+02 1.34E+02 0.97 Acceptable Mn-54 E11913 3rd 10/5/2017 1.45E+02 1.40E+02 1.03 Acceptable Fe-59 E11913 3rd 10/5/2017 1.49E+02 1.43E+02 1.04 Acceptable 1-131 E11913 3rd 10/5/2017 8.44E+01 7.92E+01 1.07 Acceptable Zn-65 E11913 3rd 10/5/2017 2.22E+02 2.10E+02 1.05 Acceptable Co-60 E11913 3rd 10/5/2017 2.91 E+02 2.99E+02 0.97 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 2017 Date (pCi/L) (pCi/L)

Gamma Water Ce-141 E11913 3rd 10/5/201 7 1.01 E+02 9.95E+01 1. 02 Acceptable Detector 3 Cr-51 E11913 3rd 10/5/2017 2.70E+02 2.48E+02 1.09 Acceptable Cs-134 E11913 3rd 10/5/2017 2.05E+02 2.29E+02 0.89 Acceptable Cs-137 E11913 3rd 10/5/2017 2.03E+02 1.96E+02 1.03 Acceptable Co-58 E11913 3rd 10/5/201 7 1.36E+02 1.34E+02 1.02 Acceptable Mn-54 E11913 3rd 10/5/2017 1.44E+02 1.40E+02 1.03 Acceptable Fe-59 E11913 3rd 10/5/2017 1.50E+02 1.43E+02 1.05 Acceptable 1-131 E11913 3rd 10/5/2017 7.73E+01 7.92E+01 0.98 Acceptable Zn-65 E11913 3rd 10/5/2017 2.28E+02 2.10E+02 1.08 Acceptable Co-60 E11913 3rd 10/5/201 7 2.95E+02 2.99E+02 0.98 Acceptable Sample Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2017 Date (pCi) (pCi)

Gamma Water Ce- 141 E11913 3rd 10/5/2017 1.01 E+02 9.95E+01 1.02 Acceptable Detector 5 Cr-51 E11913 3rd 10/5/2017 2.63E+02 2.48E+02 1.06 Acceptable Cs-134 E11913 3rd 10/5/2017 2.10E+02 2.29E+02 0.92 Acceptable Cs-137 E11913 3rd 10/5/2017 2.01 E+02 1.96E+02 1.02 Acceptable Co-58 E11913 3rd 10/5/2017 1.31 E+02 1.34E+02 0.98 Acceptable Mn-54 E11913 3rd 10/5/2017 1.46E+02 1.40E+02 1.04 Acceptable Fe-59 E11913 3rd 10/5/2017 1.49E+02 1.43E+02 1.04 Acceptable 1-131 E11913 3rd 10/5/2017 7.82E+01 7.92E+01 0.99 Acceptable Zn-65 E11913 3rd 10/5/2017 2.26E+02 2.1OE+02 1.07 Acceptable Co-60 E11913 3rd 10/5/2017 2.87E+02 2.99E+02 0.96 Acceptable Sample/ Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2017 Date (pCi) (pCi)

Gamma Soi l Ce-141 E12075 4th 1/10/2018 1.69E-0 1 1.39E-01 1.21 Acceptable Detector 1 Cr-51 E12075 4th 1/ 10/2018 3.55E-01 3.43E-01 1.04 Acceptable Cs-134 E12075 4th 1/10/2018 1.80E-01 1.77E-01 1.02 Acceptable Cs-137 E12075 4th 1/10/2018 2.87E-01 2.75E-01 1.04 Acceptable Co-58 E12075 4th 1/10/2018 1.35E-01 1.27E-01 1.06 Acceptable Mn-54 E12075 4th 1/10/2018 2.45E-01 2.27E-01 1.08 Acceptable Fe-59 E12075 4th 1/10/2018 1.63E-01 1.60E-01 1.02 Acceptable Zn-65 E12075 4th 1/10/2018 3.04E-01 2.99E-01 1.02 Acceptable Co-60 E12075 4th 1/10/2018 2.51 E-01 2.45E-01 1.03 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 2017 Date (pCi/L) (pCi/L)

Gamma Soil Ce-141 E12075 4th 1/10/2018 1.48E-01 1.39E-01 1.06 Acceptable Detector 3 Cr-51 E12075 4th 1/10/2018 3.43E-01 3.43E-01 1.00 Acceptable Cs-134 E12075 4th 1/10/2018 1.82E-01 1.77E-01 1.03 Acceptable Cs-137 E12075 4th 1/10/2018 2.94E-01 2.75E-01 1.07 Acceptable Co-58 E12075 4th 1/10/2018 1.25E-01 1.27E-01 0.98 Acceptable Mn-54 E12075 4th 1/10/2018 2.54E-01 2.27E-01 1.12 Acceptable Fe-59 E12075 4th 1/10/2018 1.71E-01 1.60E-01 1.07 Acceptable Zn-65 E12075 4th 1/10/2018 3.13E-01 2.99E-01 1.05 Acceptable Co-60 E12075 4th 1/10/2018 2.SOE-01 2.45E-01 1.02 Acceptable Sample Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2017 Date (pCi/L) (pCi/L)

Gamma Soil Ce-141 E12075 4th 1/10/2018 1.49E-01 1.39E-01 1.07 Acceptable Detector 5 Cr-51 E12075 4th 1/10/2018 3.24E-01 3.43E-01 0.95 Acceptable Cs-134 E12075 4th 1/10/2018 1.78E-01 1.77E-01 1.01 Acceptable Cs-137 E12075 4th 1/10/2018 2.87E-01 2.75E-01 1.04 Acceptable Co-58 E12075 4th 1/10/2018 1.35E-01 1.27E-01 1.06 Acceptable Mn-54 E12075 4th 1/10/2018 2.51 E-01 2.27E-01 1.10 Acceptable Fe-59 E12075 4th 1/10/2018 1.64E-01 1.60E-01 1.02 Acceptable Zn-65 E12075 4th 1/10/2018 3.1OE-01 2.99E-01 1.04 Acceptable Co-60 E12075 4th 1/10/2018 2.47E-01 2.45E-01 1.01 Acceptable Sample Radionuclide Sample Quarter Report HBPP Reference Ratio Evaluation Analysis Number 2017 Date (pCi/L) (pCi/L)

Gamma Soil Ce-141 E12075 4th 1/10/2018 1.76E-Ofl 1.39E-01 1.27 Not Detector 6 Acceptable Cr-51 E12075 4th 1/10/2018 3.88E-01 3.43E-01 1.13 Acceptable Cs-134 E12075 4th 1/10/2018 1.80E-01 1.77E-01 1.02 Acceptable Cs-137 E12075 4th 1/10/2018 2.81 E-01 2.75E-01 1.02 Acceptable Co-58 E12075 4th 1/10/2018 1.42E-01 1.27E-01 1.12 Acceptable Mn-54 E12075 4th 1/10/2018 2.SSE-01 2.27E-01 1.12 Acceptable Fe-59 E12075 4th 1/10/2018 1.64E-01 1.60E-01 1.02 Acceptable Zn-65 E12075 4th 1/10/2018 3.33E-01 2.99E-01 1.12 Acceptable Co-60 E12075 4th 1/10/2018 2.53E-01 2.45E-01 1.03 Acceptable Table A-4 Notes:

1. Analysis results based on 10 minute count times for alpha and beta analysis on Proteans SN 7108 and 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. Ce-141 with one gamma at 145.44 keV and a half-life of 32.5 days was reported conservatively high by Detector 6.

Detector 6 is housed in the Gamma Analyst, which has an automatic sample changer. Mechanical problems with the sample changer occurred in December 2017 and the instrument was out of service until January 9, 2018. Cross checks were received on December 7, 2017. Due to the length of time the instrument was out of service, at least one half-life of Ce-141 had transpired . Primary radionuclides of concern at HBPP are Cs-137 and Co-60, with energies of 661 .6 keV, 1173.2 keV, and 1332.5 keV respectively. The conservative value observed for Ce-141 should not be a concern . This notation was reported in corrective action SAPN 1426132.

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 , 2017 (County, State)

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

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

& [Ranget & [Ranget (52) samples per

Gross Beta East Fence (AM1) Bldg. Gross Alpha Humboldt Hill NIA AIRBORNE station 1.00E-02 Gross Alpha (pCi/m3) mean 2.73E-03 , (9/52), [1 .34E-03 to 4.19E-03] 12 (pCi/m3) mean (Station 3)

Gross Beta , pCi/m3 Gross Beta (pCi/m3) mean 1.04E-02, (48/52), [3.38E-03 to 2.45E-02] (AM2) 2.90E-03 , (7/52), Gross Alpha Particulates

Gross Alpha Building 12 (AM2) [2 .39E-03 to (pCi/m3) mean Gross Alpha (pCi/m3) mean 2.90E-03, (7/52), [2 .39E-03 to 3.56E-03] 3.56E-03] 2.90E-03,

[pCi/m3]

Gamma Isotopic

Gamma Gross Beta (pCi/m3) mean 9.97E-03, (43/52) , [3.42E-03 to 1.88E-02] (9/52),

Isotopic analysis on analysis on Annex (AM3) [1.34E-03 to quarterly quarterly Gross Alpha (pCi/m3) mean 2.60E-03 , (8/52), [2 .34E-03 to 3.51 E-03] 4.97E-03]

composite (by composite Gross Beta (pCi/m3) mean 8.87E-03, (43/52), [3.41 E-03 to 1.84E-02]

station) (by station) Relay Building (AM4) East Gross Beta Gross Beta Gross Alpha (pCi/m3) mean 2.68E-03 , (6/52) , [2.37E-03 to 3.59E-03] Fence (pCi/m3) mean (pCi/m3) mean (5) Onsite Gross Beta (pC i/m3) mean 9.74E-03; (40/52), [3.35E-03 to 3.04E-02] (AM1) 1.04E-02 , 9.35E-03,

Cs-137 Oil Water Separator (OWS - AMS) (48/52), (32/52),

Locations 6.00E-02 Gross Alpha (pCi/m3) mean 2.75E-03 , (4/52) , [2.40E-03 to 3.72E-03] [3 .38E-03 to [3.39E-03 to (1) Offsite pCi/m3 Gross Beta (pC i/m3) mean 9.00E-03, (47/52), [3.71 E-03 to 2.60E-02] 2.45E-02] 2.13E-02]

Locations Cs-137 <MDA (64) Fence line 5mRem Fence Line TLDs (T1 to T16) Station T9 (mR/qtr) Stations 1, 2, 0 DIRECT TLD readings 13.3 +/- 0.1, (64/64), [10.2 to 17.8] T-9, mean 14, 25 and T17 RADIATION Figure 15.9 +/- 0.4, (mR/qtr) mean (20) Off-site TLD B-1 (4/4), [14.6 to 12.6+/-0.1,

[mR/quarter] Readings 17.8] (20/20),

[9.8 to 16.3]

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) & rRanqel b Direction & [Range] b & [Range] b Measurements Gamma isotopic Co-60: 15 pCilL Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 0 WATERBORNE (24) Cs-137:18 pCilL Groundwater <MDA <MDA NIA NIA <MDA <MDA NIA NIA (0124) (0124) (0124) (0124)

(Monitoring wells) [NIA] [NIA]

[NIA] [NIA]

[pCi/L]

Tritium(50) ODCM:-------

2. 0E+03 - ----

<MDA, --(0124), [NIA] ---- --

NIA <MDA, (0124), ---- -----

--- --[NIA] NIA ---- ------ --- ----0----- --

pCilL

_Plant Policy: 400 __

------------ NIA

__ Drinking Water __ Not Required NIA ---------------

NIA ---------------

NIA

-Not -- - --------- --------------

-- Required NIA Sediment Not Required NIA NIA --------------- ------

NIA NIA ---------------

Not Required NIA

--Alqae

--- --- -------- ---- NIA ---- --- ----- ------ ---- ----- ---

NIA ---- -- -----

-- -- -NIA Not Required NIA-- --- ---- -- --- - NIA

- - - - - -------- -- --- Not Required INGESTION Not Required NIA NIA NIA NIA Not Required NIA TERRESTRIAL Soil Not Required NIA NIA NIA NIA Not Required NIA 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 probabi lity with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

LLD is defin ed as the a pri ori (before the fact) LLD (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 ran ge 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 resu lts is indicated in brackets; e.g .,

[23 to 34] .

Not Required : Not required by the HBPP Unit 3 Technical Specifications or the SAFSTOR ODCM. Baseline environmental conditions for this parameter were established in the Environmental Report as referenced by the SAFSTOR Decommissioning Plan (now identified as the PS DAR and DSAR) .

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 15.5 +/- 0.6 12.6 +/- 0.1 13.1 +/- 0.3 14.4 +/- 0.1 T2 14.1 +/- 0.5 12.3+/-0.1 12.9 +/- 0.3 14.0 +/- 0.3 T3 14.3 +/- 0.4 11 .7+/-0.1 12.3 +/- 0.2 13.4 +/- 0.1 T4 15.0+/-0.1 12.4+/-0.2 12.4+/-0.2 13.7 +/- 0.3 TS 13.7 +/- 0.1 11.4 +/- 0.1 11.9 +/- 0.2 13.6 +/- 0.1 TS 13.0 +/- 0.3 10.2 +/- 1.0 11 .2 +/- 0.2 12.3 +/- 0.1 T7 13.9 +/- 0.3 11 .1 +/- 0.2 11.4+/-0.9 12.3 +/- 0.8 T8 14.7 +/- 0.2 11 .0 +/- 1.2 11.9+/-0.5 13.5 +/- 0.4 T9 15.1 +/- 0.2 14.6+/-1.1 16.1 +/-0.9 17.8 +/- 0.4 1 T10 15.3+/-1.8 12.3 +/- 0.2 13.0 +/- 0.5 14.0 +/- 0.3 T11 14.6 +/- 0.1 11.5 +/- 0.6 12.2 +/- 0.0 13.8 +/- 0.2 T12 14.5 +/- 0.6 12.0 +/- 0.1 12.7+/-0.4 13.8 +/- 0.2 T13 14.6 +/- 0.4 12.3 +/- 0.2 13.1 +/- 0.1 14.0 +/- 0.2 T14 15.4 +/- 0.4 12.5 +/- 0.1 13.2 +/- 0.4 14.5 +/- 0.3 T15 14.6 +/- 0.3 11 .7 +/- 0.3 12.1 +/- 0.1 13.3 +/- 0.2 T16 15.1 +/- 0.1 12.1+/-0.3 12.4+/-0.5 13.6 +/- 0.2 Calculated Parameters (mR)

Parameter First Quarter Second Quarter Third Quarter Fourth Quarter Average 14.6 +/- 0.1 12.0 +/- 0.1 12.6 +/- 0.1 13.9+/-0.1 Maximum 15.5 +/- 0.6 14.6 +/- 1.1 16.1 +/- 0.9 17.8 +/- 0.4 Table C-2 Notes:

1. Corrective action SAPN 1439150 documents the radiation dose at T9 for the fourth quarter was 4.8 mrem above the average background .

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

3. 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 14.4 +/- 0.3 11.4 +/- 0.4 11 .8 +/- 0.2 13.0 +/- 0.3 2 16.3 +/- 0.3 13.1 +/- 0.3 13.6 +/- 0.4 14.9 +/- 0.4 14 13.2 +/- 0.5 9.8 +/- 0.7 11 .5+/-0.4 11.9+/-0.4 25 , 12.9 +/- 0.3 10.7 +/- 0.2 11 .3+/-0.3 13.0 +/- 0.3 T17 14.3 +/- 0.1 11 .0+/-0.4 11 .2+/-0.1 12.3+/-0.4 Calculated Parameters (mR)

Parameter First Quarter Second Quarter Third Quarter Fourth Quarter Average 14.2 +/- 0.1 11 .2 +/- 0.2 11 .9 +/- 0.1 13.0 +/- 0.2 Maximum 16.3 +/- 0.3 13.1 +/- 0.3 13.6 +/- 0.4 14.9 +/- 0.4 Table C-3 Notes:

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

l I 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* 2/15/2017 < 4.39 (MDA) 2.53 +/- 1.13 < 4.01 (MDA) < 1.83 (MDA) < 312 (MDA)

RCW-SFP-2* 2/15/2017 < 35 .6 (MDA) < 13.7 (MDA) < 4.17 (MDA) < 4.56 (MDA) < 312 (MDA)

RCW-SFP-3* 2/15/2017 < 58.6 (MDA) < 17.9 (MDA) < 5.06 (MDA) < 5.44 (MDA) < 297 (MDA)

RCW-SFP-4* 2/15/2017' < 16.5 (MDA) 15.1 +/- 5.01 < 3.66 (MDA) < 4.25 (MDA) < 311 (MDA)

RCW-SFP-5* 2/15/2017 < 21.7(MDA) < 10.8 (MDA) < 5.16 (MDA) < 4.4 1 (MDA) < 306 (MDA)

RCW-SFP-6* 2/15/2017 < 2.85 (MDA) 0.897 +/- 0.576 < 4.03 (MDA) < 4.38 (MDA) < 309 (MDA)

RCW-CS-5* 2/15/2017 < 2.93 (MDA) 2.3 +/- 0.783 < 3.03 (MDA) < 3.51 (MDA) < 295 (MDA)'

RCW-CS-6* 2/15/2017 < 198 (MDA) < 72 .2 (MDA) < 4.06 (MDA) < 3.07 (MDA) < 311 (MDA)

RCW-CS-7* 2/15/2017 < 207 (MDA) 97.7 + 50 < 3.50 (MDA) < 4.05 (MDA) < 299 (MDA) 1 RCW-CS-8* 2/15/2017 < 144 (MDA) < 90 .7 (MDA) < 3.43 (MDA) < 3.05 (MDA) < 307 (MDA)

RCW-CS-9* 2/15/2017 < 104 (MDA) < 40.8 (MDA) < 6.19(MDA) < 5.53 (MDA) < 307 (MDA)

RCW-CS-10* 2/15/2017 < 35.9 (MDA) < 12.3 (MDA) < 4.05 (MDA) < 3.98 (MDA) < 313(MDA)

I ndicates 12 groundwater monitoring wells.

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* 5/5/2017 < 5.42 (MDA) < 3.02 (MDA) < 5.68 (MDA) < 4.91 (MDA) < 305 (MDA)

RCW-SFP-2* 5/5/2017 < 87.2 (MDA) < 16.8 (MDA) < 3.18 (MDA) < 3.05 (MDA) < 308 (MDA)

RCW-SFP-3* 5/5/2017 < 38.3 (MDA) 27.3 +/- 8.17 < 3.00 (MDA) <4.15(MDA) < 305 (MDA)

RCW-SFP-4* 5/5/2017 < 22 .6 (MDA) 10.9 +/- 4.19 < 3.36 (MDA) < 3.83 (MDA) < 304 (MDA)

RCW-SFP-5* 5/5/2017 < 24 .1 (MDA) < 16.6 (MDA) < 4.94 (MDA) < 4.05 (MDA) < 296 (MDA)

RCW-SFP-6* 5/5/2017 < 2.92 (MDA) 2.01 +/- 0.964 < 3.48 (MDA) < 3.20 (MDA) < 296 (MDA)

RCW-CS-5* 5/5/2017 < 2.77 (MDA) 3.02 +/- 1.07 < 3.03 (MDA) <4 .19 (MDA) < 290 (MDA)

RCW-CS-6* 5/5/2017 < 138 (MDA) < 92 .8 (MDA) < 4.69 (MDA) < 2.69 (MDA) < 310 (MDA)

RCW-CS-7* 5/5/2017 < 260 (MDA) < 153 (MDA) < 4.44 (MDA) < 3.96 (MDA) < 325 (MDA)

RCW-CS-8* 5/5/2017 < 143 (MDA) < 108 (MDA) < 4.64 (MDA) < 3.62 (MDA) < 320 (MDA)

RCW-CS-9* 5/5/2017 < 63 (MDA) < 47.6 (MDA) < 4.08 (MDA) < 4.21 (MDA) < 322 (MDA)

RCW-CS-10* 5/5/2017 < 33.5 (MDA) 17.3 +/- 9.45 < 3.59 (MDA) < 3.37 (MDA) < 308 (MDA)

Indicates 12 groundwater monitoring wells.

TABLE C-4 (Continued)

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

Number) Cs-137 Co-60 Average: MW-11 Note 6 2.53 +/- 1.13 Note 6 Note 6 Note 6 Average: RCW-SFP-2* Note 6 Note 6 Note 6 Note 6 Note 6 Average: RCW-SFP-3* Note 6 27 .3 +/- 8.17 Note 6 Note 6 Note 6 Average: RCW-SFP-4* Note 6 13.0 +/- 3.27 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 1.45 +/- 0.56 Note 6 Note 6 Note 6 Average: RCW-CS-5* Note 6 2.66 +/- 0.66 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 97.7 +/- 50 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 17.3 +/- 9.45 Note 6 Note 6 Note 6 Maximum: MW-11

Note 6 2.53 +/- 1.13 Note 6 Note 6 Note 6 Maximum: RCW-SFP-2* Note 6 Note 6 Note 6 Note 6 Note 6 Maximum: RCW-SFP-3* Note 6 27.3 +/- 8.17 Note 6 Note 6 Note 6 Maximum: RCW-SFP-4* Note 6 15.1 +/- 5.01 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 2.01 +/- 0.964 Note 6 Note 6 Note 6 Maximum: RCW-CS-5* Note 6 3.02 +/- 1.07 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 97 .7 +/- 50 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 17.3 +/- 9.45 Note 6 Note 6 Note 6

I ndicates 12 groundwater monitoring wells.

Table C-4 Notes:

1. Monitoring wells RCW-SFP-4 and RCW-CS-8 were located adjacent to each other in a small depression in the FSS area of the upper yard . During the first quarter well sampling event of 2017, some dirt and gravel were found to be covering the well lids. As a result, turbidity measurements for both wells were elevated . The increased sediment in the water was most likely due to surface influence rather than a significant disturbance in the water column or excessive stress placed on the formation . GEL Labs was advised of the higher than normal turbidity measurements and was requested to allow any sediment in the samples to settle before analyses were performed . The GEL data report for monitoring wells RCW-SFP-4 and RCW-CS-8 appeared to be in line with values seen previously. This action was documented in corrective action SAPN 1428500.

2. On February 27 , 2017, GEL Labs advised via email that the H-3 sample for monitoring well RCW-CS-5 was damaged during shipment and the sample was lost. GEL collected a H-3 sample from the nitric acid preserved sample. GEL reported H-3 activity for RCW-CS-5 as less than 295 pCi/L, which is a normal value for H-3 activity in HBPP monitoring wells and less than the required LLD of 400 pCi/L. This action was documented in corrective action SAPN 1428501 .

3. Reported values are net measurements (above instrument background). The normal MDAs for the analyses for gross alpha, gross beta, and tritium are approximately 5, 4, and 2,000 pCi/L, respectively . Gross alpha and gross beta are analyzed for trending purposes only. 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 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 th is report, LLD is defined as the a priori (before the fact) LLD, 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 12/28/2016 < 3.00E-03 (MDA) 8.27E-03 +/- 3.34E-03 1/5/2017 < 3.30E-03 (MDA) 1.05E-02 +/- 3.84E-03 1/12/2017 < 3.52E-03 (MDA) 1.92E-02 +/- 4.97E-03 1/19/2017 < 3.40E-03 (MDA) < 5.90E-03 (MDA) 1/26/2017 < 3.41 E-03 (MDA) 2.45E-02 +/- 5.37E-03 2/2/2017 < 3.37E-03 (MDA) 8.25E-03 +/- 3.61 E-03

<1.48E-03 < 1.67E-03 2/9/2017 1.34E-03 +/- 1.07E-03 1.55E-02 +/- 4.50E-03 (MDA) (MDA) 2/16/2017 < 3.36E-03 (MDA) < 5.84E-03 (MDA) 2/23/2017 < 3.44E-03 (MDA) 1.05E-02 +/- 3.97E-03 3/2/2017 < 3.36E-03 (MDA) 8.91 E-03 +/- 3.70E-03 3/9/2017 < 3.43E-03 (MDA) 5.20E-03 +/- 3.23E-03 3/16/2017 < 3.41 E-03 (MDA) 5.51 E-03 +/- 3.26E-03 3/23/2017 < 3.37E-03 (MDA) 5.1OE-03 +/- 3.17E-03 3/30/2017 < 3.41 E-03 (MDA) 8.69E-03 +/- 3. 70E-03 4/6/2017 < 3.43E-03 (MDA) 5.55E-03 +/- 3.28E-03 4/13/2017 < 3.41E-03 (MDA) 7.98E-03 +/- 3.61 E-03 4/20/2017 2.37E-03 +/- 1.87E-03 1 9.28E-03 +/- 3.74E-03 1 4/27/2017 < 3.43E-03 (MDA) 6.61 E-03 +/- 3.44E-03 5/4/2017 < 3.41 E-03 (MDA) 9.40E-03 +/- 3.79E-03

< 1.29E-03 < 1.27E-03 5/11/2017 < 3.38E-03 (MDA) 3.38E-03 +/- 2.92E-03 (MDA) (MDA) 5/18/2017 2.34E-03 +/- 1.85E-03 7.42E-03 +/- 3.46E-03 5/25/2017 < 3.41E-03 (MDA) 7.98E-03 +/- 3.61 E-03 6/1/2017 < 3.44E-03 (MDA) 6.63E-03 +/- 3.45E-03 6/8/201 7 < 3.44E-03 (MDA) 4.14E-03 +/- 3.08E-03 6/15/2017 3.56E-03 +/- 2.32E-03 4.77E-03 +/- 3.13E-03 6/22/2017 < 3.44E-03 (MDA) 5.21 E-03 +/- 3.24E-03 6/29/2017 < 3.39E-03 (MDA) 1.07E-02 +/- 3.94E-03 7/6/2017 < 3.40E-03 (MDA) 1.08E-02 +/- 3.96E-03 7/13/2017 2.42E-03 +/- 1.91 E-03 9.48E-03 +/- 3.82E-03 7/20/2017 < 3.36E-03 (MDA) < 5.84E-03 (MDA) 7/27/2017 < 3.41 E-03 (MDA) 5.51 E-03 +/- 3.26E-03 8/3/2017 < 3.43E-03 (MDA) 5.19E-03 +/- 3.22E-03

< 1.29E-03 < 1.10E-03 8/10/2017 < 3.35E-03 (MDA) 8.53E-03 +/- 3.63E-03 (MDA) (MDA) 8/17/2017 < 3.43E-03 (MDA) < 5.96E-03 (MDA) 8/24/201 7 2.39E-03 +/- 1.89E-03 1.11 E-02 +/- 3.99E-03 8/31/2017 4.19E-03 +/- 2.53E-03 1.58E-02 +/- 4.53E-03 9/7/2017 < 3.38E-03 (MDA) 1.35E-02 +/- 4.25E-03 9/14/2017 < 3.38E-03 (MDA) 1.21 E-02 +/- 4.09E-03 9/21/2017 < 3.32E-03 (MDA) 1.84E-02 +/- 4.73E-03 9/28/2017 < 3.41 E-03 (MDA) 1.83E-02 +/- 4.82E-03 10/5/2017 2.38E-03 +/- 1.88E-03 1.87E-02 +/- 4.80E-03 10/12/2017 < 3.43E-03 (MDA) 1.90E-02 +/- 4.88E-03 10/19/2017 < 3.39E-03 (MDA) 7.59E-03 +/- 3.54E-03 10/26/2017 3.55E-03 +/- 2.32E-03 2.05E-02 +/- 4.95E-03 11/2/2017 < 3.43E-03 (MDA) 9.1 OE-03 +/- 3.78E-03

< 1.29E-03 < 1.02E-03 11/9/2017 < 3.39E-03 (MDA) 5.14E-03 +/- 3.19E-03 (MDA) (MDA) 11/16/201 7 < 4.00E-03 (MDA) 1.14E-02 +/- 4.51 E-03 11/22/2017 < 2.87E-03 (MDA) 5.34E-03 +/- 2.83E-03 11/30/2017 < 3.40E-03 (MDA) 1.39E-02 +/- 4.32E-03 12/7/2017 < 3.32E-03 (MDA) 2.01 E-02 +/- 4.88E-03 12/14/2017 < 3.47E-03 (MDA) 1.50E-02 +/- 4.49E-03 12/21/2017 < 3.38E-03 (MDA) 7.23E-03 +/- 3.48E-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 12/28/2016 < 3.00E-03 (MDA) 1.08E-02 +/- 3.63E-03 1/5/2017 < 3.30E-03 (MDA) 8.41 E-03 +/- 3.58E-03 1/12/2017 < 3.52E-03 (MDA) 1.77E-02 +/- 4.82E-03 1/19/2017 2.39E-03 +/- 1.89E-03 < 5.90E-03 (MDA) 1/26/2017 < 3.41 E-03 (MDA) 1.47E-02 +/- 4.40E-03 2/2/2017 < 3.37E-03 (MDA) 7.90E-03 +/- 3.57E-03

<1 .26E-03 <1 .14E-03 2/9/2017 < 1.97E-03 (MDA) 1.69E-02 +/- 4.66E-03 (MDA) (MDA) 2/16/2017 < 3.36E-03 (MDA) 6.83E-03 +/- 3.42E-03 2/23/2017 < 3.44E-03 (MDA) 4.14E-03 +/- 3.08E-03 3/2/2017 < 3.36E-03 (MDA) 7.52E-03 +/- 3.51 E-03 3/9/2017 < 3.43E-03 (MDA) 4.49E-03 +/- 3.12E-03 3/16/2017 < 3.40E-03 (MDA) < 5.91 E-03 (MDA) 3/23/2017 < 3.37E-03 (MDA) 1.07E-02 +/- 3.92E-03 3/30/2017 < 3.41 E-03 (MDA) 1.08E-02 +/- 3.97E-03 4/6/2017 < 3.43E-03 (MDA) 9.45E-03 +/- 3.81 E-03 4/13/2017 < 3.41 E-03 (MDA) 9.39E-03 +/- 3.79E-03

< 3.37E-03 (MDA) 1 1

4/20/2017 5.45E-03 +/- 3.22E-03 4/27/2017 < 3.43E-03 (MDA) 3.42E-03 +/- 2.96E-03 5/4/2017 < 3.41 E-03 (MDA) 3. 76E-03 +/- 3.00E-03

< 1.48E-03 < 1.13E-03 5/11/2017 < 3.39E-03 (MDA) < 5.88E-03 (MDA)

(MDA) (MDA) 5/18/2017 < 3.32E-03 (MDA) < 5.76E-03 (MDA) 5/25/2017 < 3.41 E-03 (MDA) 3.75E-03 +/- 3.00E-03 6/1/2017 < 3.44E-03 (MDA) 4.85E-03 +/- 3.18E-03 6/8/2017 < 3.44E-03 (MDA) 6.63E-03 +/- 3.45E-03 6/15/2017 < 3.38E-03 (MDA) < 5.88E-03 (MDA) 6/22/2017 < 3.44E-03 (MDA) < 5.97E-03 (MDA) 6/29/2017 3.56E-03 +/- 2.32E-03 8.98E-03 +/- 3.73E-03 7/6/2017 Note 6 Note 6 7/13/2017 < 3.46E-03 (MDA) < 6.00E-03 (MDA) 7/20/2017 < 3.36E-03 (MDA) < 5.84E-03 (MDA) 7/27/2017 < 3.41E-03 (MDA) 6.23E-03 +/- 3.37E-03 8/3/2017 < 3.42E-03 (MDA) 6.96E-03 +/- 3.49E-03

< 1.35E-03 < 1.38E-03 8/10/2017 < 3.35E-03 (MDA) 6.11 E-03 +/- 3.31 E-03 (MDA) (MDA) 8/17/2017 < 3.43E-03 (MDA) 4.84E-03 +/- 3.17E-03 8/24/2017 < 3.39E-03 (MDA) 1.42E-02 +/- 4.35E-03 8/31/2017 3.13E-03 +/- 2.23E-03' 1.50E-02 +/- 4.57E-03' 9/7/2017 < 3.38E-03 (MDA) 9.32E-03 +/- 3.76E-03 9/14/2017 < 3.38E-03 (MDA) 9.33E-03 +/- 3.76E-03 9/21/2017 2.91 E-03 +/- 2.07E-03 1.39E-02 +/- 4.25E-03 9/28/2017 < 3.41 E-03 (MDA) 1.40E-02 +/- 4.34E-03 10/5/2017 < 3.38E-03 (MDA) 1.46E-02 +/- 4.37E-03 10/12/2017 < 3.43E-03 (MDA) 1.76E-02 +/- 4.74E-03 10/19/2017 < 3.45E-03 (MDA)~ 7.72E-03 +/- 3.60E-03~

10/26/2017 < 3.38E-03 (MDA) 1.73E-02 +/- 4.66E-03 11/2/2017 < 3.43E-03 (MDA) 1.16E-02 +/- 4.08E-03

< 1.32E-03 < 1.38E-03 11/9/2017 < 3.40E-03 (MDA) 7.27E-03 +/- 3.50E-03 (MDA) (MDA) 11/16/2017 < 3.98E-03 (MDA) 5.21 E-03 +/- 3.63E-03 11/22/2017 < 2.87E-03 (MDA) 1.12E-02 +/- 3.58E-03 11/30/2017 2.39E-03 +/- 1.89E-03 1.39E-02 +/- 4.32E-03 12/7/2017 3.50E-03 +/- 2.28E-03 1.88E-02 +/- 4.76E-03 12/14/2017 2.44E-03 +/- 1.93E-03 1.38E-02 +/- 4.35E-03 12/21/2017 < 3.40E-03 (MDA) 1.32E-02 +/- 4.23E-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 (pCi/m 3 )

Co-60 Cs-137 12/28/2016 < 3.00E-03 (MDA) 5.48E-03 +/- 2.96E-03 1/5/2017 < 3.30E-03 (MDA) 9.44E-03 +/- 3.72E-03 1/12/2017 < 3.52E-03 (MDA) 1.23E-02 +/- 4.22E-03 1/19/2017 < 3.40E-03 (MDA) 3.74E-03 +/- 2.99E-03 1/26/2017 < 3.41 E-03 (MDA) 1.54E-02 +/- 4.47E-03 2/2/2017 < 3.37E-03 (MDA) 5.11 E-03 +/- 3.17E-03

<9.75E-04 < 1.21 E-03 2/9/2017 < 1.97E-03 (MDA) 7.67E-03 +/- 3.58E-03 (MDA) (MDA) 2/16/2017 < 3.36E-03 (MDA) < 5.84E-03 (MDA) 2/23/2017 < 3.44E-03 (MDA) < 5.98E-03 (MDA) 3/2/2017 < 3.36E-03 (MDA) < 5.84E-03 (MDA) 3/9/2017 < 3.43E-03 (MDA) 5.55E-03 +/- 3.28E-03 3/16/2017 < 3.40E-03 (MDA) 6.21 E-03 +/- 3.36E-03 3/23/2017 < 3.37E-03 (MDA) 8.24E-03 +/- 3.60E-03 3/30/2017 < 3.41E-03 (MDA) 7.28E-03 +/- 3.51 E-03 4/6/2017 < 3.43E-03 (MDA) 6.97E-03 +/- 3.49E-03 4/13/2017 < 3.41 E-03 (MDA) 6.57E-03 +/- 3.42E-03 4/20/2017 < 3.37E-03 (MDA)' < 5.85E-03 (MDA) 1 4/27/2017 < 3.43E-03 (MDA) 7.32E-03 +/- 3.53E-03 5/4/2017 < 3.41 E-03 (MDA) < 5.93E-03 (MDA)

< 1.28E-03 < 1.13E-03 5/11/2017 2.39E-03 +/- 1.89E-03 4.78E-03 +/- 3.14E-03 (MDA) (MDA) 5/18/2017 < 3.32E-03 (MDA) 4.68E-03 +/- 3.07E-03 5/25/2017 2.40E-03 +/- 1.90E-03 7.63E-03 +/- 3.56E-03 6/1/2017 < 3.44E-03 (MDA) < 5.97E-03 (MDA) 6/8/2017 < 3.44E-03 (MDA) 6.28E-03 +/- 3.40E-03 6/15/2017 < 3.37E-03 (MDA) 5.11 E-03 +/- 3.18E-03 6/22/2017 < 3.44E-03 (MDA) 5.56E-03 +/- 3.29E-03 6/29/2017 < 3.39E-03 (MDA) < 5.89E-03 (MDA) 7/6/2017 < 3.41 E-03 (MDA) < 5.92E-03 (MDA) 7/13/2017 < 3.42E-03 (MDA) 3.41 E-03 +/- 2.95E-03 7/20/2017 < 3.37E-03 (MDA) 5.11 E-03 +/- 3.17E-03 7/27/2017 < 3.41 E-03 (MDA) < 5.92E-03 (MDA) 8/3/2017 < 3.41 E-03 (MDA) 6.22E-03 +/- 3.37E-03

< 1.16E-03 < 1.44E-03 8/10/2017 < 3.35E-03 (MDA) 7.86E-03 +/- 3.56E-03 (MDA) (MDA) 8/17/2017 2.42E-03 +/- 1.91 E-03 4.13E-03 +/- 3.07E-03 8/24/2017 < 3.41E-03 (MDA) 5.87E-03 +/- 3.31 E-03 8/31/2017 < 3.41 E-03 (M DA)' 1.61 E-02 +/- 4.57E-03' 9/7/2017 < 3.39E-03 (MDA) 1.18E-02 +/- 4.07E-03 9/14/2017 < 3.38E-03 (MDA) 9.33E-03 +/- 3.76E-Q3 9/21/2017 2.34E-03 +/- 1.85E-03 1.40E-02 +/- 4.26E-03 11 9/28/2017 < 3.43E-03 (MDAt 1.33E-02 +/- 4.28E-03 10/5/2017 < 3.36E-03 (MDA) 1.38E-02 +/- 4.27E-03 10/12/2017 < 3.44E-03 (MDA) 1.41 E-02 +/- 4.38E-03 10/19/2017 2.39E-03 +/- 1.89E-03 5.84E-03 +/- 3.30E-03 10/26/2017 < 3.37E-03 (MDA) 1.45E-02 +/- 4.36E-03 11/2/2017 < 3.43E-03 (MDA) 1.41 E-02 +/- 4.36 E-03

< 1.37E-03 < 9.26E-04 11/9/2017 < 3.48E-03 (MDA)1u 5.64E-03 +/- 3.33E-03 1 u (MDA) (MDA) 11/16/2017 3.51 E-03 +/- 2.50E-03 1.02E-02 +/- 4.34E-03 11/22/2017 < 2.88E-03 (MDA) 8.42E-03 +/- 3.27E-03 11/30/2017 < 3.39E-03 (MDA) 1.14E-02 +/- 4.03E-03 12/7/2017 2.34E-03 +/- 1.85E-03 1.84E-02 +/- 4.72E-03 12/14/2017 3.05E-03 +/- 2.18E-03 1.53E-02 +/- 4.53E-03 12/21/2017 < 3.38E-03 (MDA) 1.11 E-02 +/- 3.97E-03 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 12/28/2016 < 3.00E-03 (MDA) 1.23E-02 +/- 3.82E-03 1/5/2017 < 3.30E-03 (MDA) 1.05E-02 +/- 3.84E-03 1/12/2017 < 3.52E-03 (MDA) 1.41 E-02 +/- 4.42E-03 1/19/2017 < 3.40E-03 (MDA) < 5.90E-03 (MDA) 1/26/2017 < 3.41 E-03 (MDA) 1.54E-02 +/- 4.47E-03 2/2/2017 < 3.37E-03 (MDA) < 5.86E-03 (MDA)

<1.67E-03 < 1.10E-03 2/9/2017 < 1.97E-03 (MDA) 1.44E-02 +/- 4.40E-03 (MDA) (MDA) 2/16/2017 < 3.36E-03 (MDA) < 5.84E-03 (MDA) 2/23/2017 < 3.44E-03 (MDA) 3.43E-03 +/- 2.97E-03 3/2/2017 2.37E-03 +/- 1.87E-03 3.35E-03 +/- 2.90E-03 3/9/2017 < 3.43E-03 (MDA) 4.13E-03 +/- 3.07E-03 3/16/2017 < 3.40E-03 (MDA) 6.57E-03 +/- 3.41 E-03 3/23/2017 < 3.37E-03 (MDA) 5.80E-03 + 3.27E-03 3/30/2017 < 3.41 E-03 (MDA) 1.26E-02 +/- 4.18E-03 4/6/2017 < 3.43E-03 (MDA) 6.26E-03 +/- 3.39E-03 4/13/2017 < 3.41 E-03 (M DA) 5.16E-03 +/- 3.21 E-03 4/20/2017 < 3.37E-03 (MDA)' 4.06E-03 +/- 3.01 E-03' 4/27/2017 < 3.43E-03 (MDA) 7.67E-03 +/- 3.58E-03 5/4/2017 < 3.41 E-03 (MDA) < 5.93E-03 (MDA)

< 1.20E-03 < 1.30E-03 5/11/2017 < 3.39E-03 (MDA) < 5.88E-03 (MDA)

(MDA) (MDA) 5/18/2017 < 3.32E-03 (MDA) < 5.76E-03 (MDA) 5/25/2017 < 3.41 E-03 (MDA) 4.46E-03 +/- 3.1 OE-03 6/1/2017 < 3.44E-03 (MDA) 5.21 E-03 +/- 3.24E-03 6/8/2017 < 3.44E-03 (MDA) < 5.98E-03 (MDA) 6/15/2017 < 3.37E-03 (MDA) 5.79E-03 +/- 3.27E-03 6/22/2017 < 3.44E-03 (MDA) 7.34E-03 +/- 3.54E-03 6/29/2017 < 3.40E-03 (MDA) < 5.91 E-03 (MDA) 7/6/2017 < 3.40E-03 (MDA) 7.62E-03 +/- 3.55E-03 7/13/2017 < 3.43E-03 (MDA) 3.78E-03 +/- 3.01 E-03 7/20/2017 < 3.36E-03 (MDA) < 5.84E-03 (MDA) 7/27/2017 < 3.42E-03 (MDA) < 5.93E-03 (MDA) 8/3/2017 < 3.41 E-03 (MDA) 6.23E-03 +/- 3.37E-03

< 1.46E-03 < 1.40E-03 8/10/2017 < 3.35E-03 (MDA) 7.86E-03 +/- 3.56E-03 (MDA) (MDA) 8/17/2017 < 3.43E-03 (MDA) < 5.96E-03 (MDA) 8/24/2017 2.40E-03 +/- 1.90E-03 5.51 E-03 +/- 3.26E-03 8/31/2017 3.59E-03 +/- 2.35E-03 2.00E-02 +/- 4.96E-03 9/7/2017 < 3.39E-03 (MDA) 8.98E-03 +/- 3.73E-03 9/14/2017 < 3.38E-03 (MDA) 7.92E-03 +/- 3.59E-03 9/21/2017 < 3.32E-03 (MDA) 1.53E-02 +/- 4.40E-03 9/28/2017 < 3.41 E-03 (MDA) 1.4 7E-02 +/- 4.42E-03 10/5/2017 < 3.37E-03 (MDA) 1.24E-02 +/- 4.12E-03 10/12/2017 < 3.44E-03 (MDA) 1.16E-02 +/- 4.09E-03 10/19/2017 < 3.39E-03 (MDA) 5.84E-03 +/- 3.30E-03 10/26/2017 < 3.37E-03 (MDA) 1.1 OE-02 +/- 3.96E-03 11/2/201 7 2.42E-03 +/- 1.91 E-03 1.19E-02 +/- 4.12E-03

< 1.28E-03 < 1.22E-03 11/9/2017 < 3.39E-03 (MDA) < 5.88E-03 (MDA)

(MDA) (MDA) 11/16/2017 < 4.00E-03 (MDA) 1.35E-02 +/- 4.76E-03 11/22/2017 < 2.87E-03 (MDA) 5.03E-03 +/- 2.79E-03 11/30/2017 < 3.40E-03 (MDA) 1.22E-02 +/- 4.11 E-03 12/7/2017 2.92E-03 +/- 2.08E-03 3.04E-02 +/- 5.79E-03 12/14/2017 < 3.47E-03 (MDA) 1.21 E-02 +/- 4.17E-03 12/21/2017 2.38E-03 +/- 1.88E-03 1.70E-02 +/- 4.64E-03 Table C-5 (Continued)

ODCM REQUIRED AIR SAMPLES: OIL WATER SEPARATOR (AMS)

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

Co-60 Cs-137 12/28/2016 < 3.00E-03 (MDA) 6.1OE-03 +/- 3.06E-03 1/5/2017 < 3.30E-03 (MDA) 1.08E-02 +/- 3.87E-03 1/12/2017 < 3.52E-03 (MDA) 1.55E-02 +/- 4.59E-03 1/19/2017 < 3.40E-03 (MDA) 5.15E-03 +/- 3.20E-03 1/26/2017 < 3.41 E-03 (MDA) 1.43E-02 +/- 4.37E-03 2/2/2017 < 3.37E-03 (MDA) 3.71 E-03 +/- 2.96E-03

<1.30E-03 < 1.38E-03 2/9/2017 < 1.97E-03 (MDA) 1.09E-02 +/- 3.99E-03 (MDA) (MDA) 2/16/2017 < 3.36E-03 (MDA) < 5.84E-03 (MDA) 2/23/2017 < 3.44E-03 (MDA) 7.35E-03 +/- 3.54E-03 3/2/2017 < 3.36E-03 (MDA) 4.05E-03 +/- 3.00E-03 3/9/2017 < 3.43E-03 (MDA) 5.55E-03 +/- 3.28E-03 3/16/2017 < 3.40E-03 (MDA) 7.97E-03 +/- 3.61 E-03 3/23/2017 < 3.37E-03 (MDA) 6.15E-03 +/- 3.33E-03 3/30/2017 < 3.41 E-03 (MDA) 1.22E-02 +/- 4.12E-03 4/6/20 17 < 3.43E-03 (MDA) 4.84E-03 +/- 3.17E-03 4/13/2017 < 3.41 E-03 (MDA) 7.63E-03 +/- 3.56E-03 4/20/2017 < 3.37E-03 (MDA) 1 < 5.85E-03 (MDA) 1 4/27/2017 < 3.43E-03 (MDA) < 5.95E-03 (MDA) 5/4/2017 < 4.02E-03 (MDAt 7.34E-03 +/- 3.97E-03_.

< 1.36E-03 < 1.23E-03 5/11/2017 3.72E-03 +/- 2.43E-03 9.74E-03 +/- 3.93E-03 (MDA) (MDA) 5/18/2017 < 3.32E-03 (MDA) 6.39E-03 +/- 3.33E-03 5/25/2017 < 3.41 E-03 (MDA) 4.81 E-03 +/- 3.15E-03 6/1/2017 < 3.48E-03 (MDA)" 5.99E-03 +/- 3.38E-03" 6/8/2017 < 3.49E-03 (MDA) 5.64E-03 +/- 3.34E-03 6/15/2017 < 3.37E-03 (MDA) 5.45E-03 +/- 3.22E-03 6/22/2017 < 3.44E-03 (MDA) 7.34E-03 +/- 3.54E-03 6/29/2017 < 3.40E-03 (MDA) < 5.90E-03 (MDA) 7/6/2017 2.40E-03 +/- 1.89E-03 5.15E-03 +/- 3.20E-03 7/13/2017 < 3.43E-03 (MDA) 4.49E-03 +/- 3.12E-03 7/20/2017 < 3.36E-03 (MDA) 4.74E-03 +/- 3.11 E-03 7/27/20 17 < 3.42E-03 (MDA) < 5.93E-03 (MDA) 8/3/2017 < 3.41 E-03 (MDA) 6.58E-03 +/- 3.42E-03

< 1.24E-03 < 1.36E-03 8/10/2017 < 3.35E-03 (MDA) 4.39E-03 +/- 3.05E-03 (MDA) (MDA) 8/17/20 17 < 3.43E-03 (MDA) 6.61 E-03 +/- 3.44E-03 8/24/2017 2.40E-03 +/- 1.89E-03 8.67E-03 +/- 3.69E-03 8/31/2017 < 3.42E-03 (MDA) 1.40E-02 +/- 4.35E-03 9/7/2017 < 3.38E-03 (MDA) 1.07E-02 +/- 3.94E-03 9/14/20 17 < 3.38E-03 (MDA) 8.27E-03 +/- 3.62E-03 9/21/2017 < 3.32E-03 (MDA) 1.29E-02 +/- 4.14E-03 9/28/2017 < 3.42E-03 (MDA) 1.51 E-02 +/- 4.47E-03 10/5/2017 < 3.37E-03 (MDA) 1.31E-02 +/- 4.19E-03 10/12/2017 < 3.43E-03 (MDA) 1.41 E-02 +/- 4.37E-03 10/19/2017 < 3.39E-03 (MDA) 6.19E-03 +/- 3.35E-03 10/26/2017 < 3.37E-03 (MDA) 1.52E-02 +/- 4.43E-03 11/2/2017 < 3.43E-03 (MDA) 1.66E-02 +/- 4.63E-03

< 1.13E-03 < 1.23E-03 11/9/2017 < 3.39E-03 (MDA) 7.94E-03 +/- 3.59E-03 (MDA) (MDA) 11/16/2017 < 4.00E-03 (MDA) 6.47E-03 +/- 3.83E-03 11/22/2017 < 2.87E-03 (MDA) 5.95E-03 +/- 2.92E-03 11/30/2017 < 3.39E-03 (MDA) 1.07E-02 +/- 3.94E-03 12/7/2017 < 3.32E-03 (MDA) 2.60E-02 +/- 5.41 E-03 12/14/2017 2.47E-03 +/- 1.95E-03'" 1.29E-02 +/- 4.30E-03"'

12/21/2017 < 3.38E-03 (MDA) 1.11 E-02 +/- 3.97E-03 Table C-5 (Continued)

ODCM REQUIRED AIR SAMPLES: HUMBOLDT HILL (STATION 3)

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

Co-60 Cs-137 12/28/2016 < 2.95E-03 (MDA) 6.30E-03 +/- 3.04E-03 1/5/2017 < 3.31 E-03 (MDA) 5.70E-03 +/- 3.22E-03 1/12/2017 < 3.51 E-03 (MDA) 8.23E-03 +/- 3.72E-03 1/19/2017 < 3.40E-03 (MDA) 3.39E-03 +/- 2.94E-03 1/26/2017 3.58E-03 +/- 2.34E-03 2.13E-02 +/- 5.06E-03 2/2/2017 < 3.38E-03 (MDA) < 5.88E-03 (MDA)

<1.90E-03 < 1.37E-03 2/9/2017 1.34E-03 +/- 1.07E-03 7.66E-03 +/- 3.57E-03 (MDA) (MDA) 2/16/2017 < 3.40E-03 (MDA) < 5.91 E-03 (MDA) 2/23/2017 < 3.40E-03 (MDA) < 5.91 E-03 (MDA) 3/2/2017 < 3.39E-03 (MDA) < 5.89E-03 (MDA) 3/9/2017 < 3.41 E-03 (MDA) < 5.93E-03 (MDA) 3/16/2017 < 3.40E-03 (MDA) 5.50E-03 +/- 3.25E-03 3/23/2017 < 3.41 E-03 (MDA) 6.58E-03 +/- 3.42E-03 3/30/2017 2.39E-03 +/- 1.89E-03 1.11E-02 +/- 3.98E-03 4/6/2017 < 3.40E-03 (MDA) < 5.91 E-03 (MDA) 4/13/2017 < 3.38E-03 (MDA) 7.22E-03 +/- 3.48E-03 4/20/2017 < 3.42E-03 (MDA)' 3.76E-03 +/- 3.00E-03' 4/27/2017 < 3.41 E-03 (MDA) 7.28E-03 +/- 3.51 E-03 5/4/2017 < 3.40E-03 (MDA) < 5.91 E-03 (MDA)

< 1.48E-03 < 1.37E-03 5/11 /2017 < 3.39E-03 (MDA) < 5.89E-03 (MDA)

(MDA) (MDA) 5/18/2017 < 4.73E-03 (MDA)" < 8.21E-03 (MDA)"

5/25/2017 Note 4 Note 4 6/1/2017 < 3.42E-03 (MDA) 3.77E-03 +/- 3.01 E-03 6/8/2017 < 3.40E-03 (MDA) < 5.91 E-03 (MDA) 6/15/2017 < 3.38E-03 (MDA) < 5.87E-03 (MDA) 6/22/2017 < 3.42E-03 (MDA) 4.82E-03 +/- 3.16E-03 6/29/2017 < 3.39E-03 (MDA) 5.84E-03 +/- 3.30E-03 7/6/2017 < 3.41E-03 (MDA) < 5.92E-03 (MDA) 7/13/2017 < 3.41 E-03 (MDA) < 5.92E-03 (MDA) 7/20/2017 < 3.32E-03 (MDA) < 5.76E-03 (MDA) 7/27/2017 < 3.49E-03 (MDA) < 6.07E-03 (M DA) 8/3/2017 < 3.38E-03 (MDA) 3.72E-03 +/- 2.97E-03

< 1.36E-03 < 1.21 E-03 8/10/2017 2.40E-03 +/- 1.89E-03 < 5.91 E-03 (MDA)

(MDA) (MDA) 8/17/2017 < 3.41E-03 (MDA) < 5.92E-03 (M DA) 8/24/2017 < 3.36E-03 (MDA) 9.95E-03 +/- 3.82E-03 8/31/20 17 4.21 E-03 +/- 2.54E-03 1.62E-02 +/- 4.60E-03 9/7/2017 2.43E-03 +/- 1.92E-03 1.34E-02 +/- 4.30E-03 9/14/2017 < 3.36E-03 (MDA) < 5.84E-03 (MDA) 9/21/2017 < 3.28E-03 (MDA) 9.04E-03 +/- 3.65E-03 9/28/2017 < 3.47E-03 (MDA) 1.46E-02 +/- 4.45E-03 10/5/2017 < 3.41 E-03 (MDA) 8.68E-03 +/- 3.70E-03 10/12/2017 < 3.40E-03 (MDA) 1.71 E-02 +/- 4.66E-03 10/19/2017 < 3.40E-03 (MDA) 5.51 E-03 +/- 3.26E-03 10/26/2017 < 3.35E-03 (MDA) 1.75E-02 +/- 4.66E-03 11/2/2017 < 3.45E-03 (MDA) 7.01 E-03 +/- 3.51 E-03 11 11 < 1.23E-03 < 1.32E-03 11/9/2017 4.97E-03 +/- 3.73E-03 < 2.29E-02 (MDA)

(MDA) (MDA) 11/16/2017 < 4.04E-03 (MDA) 9.87E-03 +/- 4.32E-03 11/22/2017 < 2.90E-03 (MDA) 6.31 E-03 +/- 2.99E-03 11/30/2017 < 3.39E-03 (MDA) 1.15E-02 +/- 4.04E-03 12/7/2017 2.40E-03 +/- 1.89E-03 1.78E-02 +/- 4.73E-03 12/14/2017 2.40E-03 +/- 1.89E-03 1.43E-02 +/- 4.36E-03 12/21/2017 < 3.35E-03 (MDA) 8.18E-03 +/- 3.58E-03 Table C-5 Notes

1. On May 4, 2017 , the beta source efficiency check was performed on Protean 7109. The calculated efficiency fell below the lower warning limit, but the source check was not repeated . The error was discovered while assembling the monthly QC documents for the records management system. All routine air samples, including REMP air samples , analyzed on May 4, 2017, were pulled and reanalyzed on June 7, 2017. A review of the sample recounts indicated required LLDs were achieved and there were no appreciable differences in the alpha or beta air sample results.

Air sample analyses performed on June 7, 2017, were used as the correct documentation . This was recorded in corrective action SAPN 1431432.

2. On May 10, 2017, the REMP air sampler at the OWS (AM5) was removed from service to allow relocation of the sample station due to remediation activities occurring within the immediate vicinity. This was documented in corrective action SAPN 1430423.

3. The REMP air sampler at Humboldt Hill was found to be not operating on May 25, 2017 (for the time period of May 18, 2017, to May 25, 2017). It was determined the sample pump experienced a blown fuse . The fuse was replaced and the air sampler determined to be operable . This was documented in corrective action SAPN 1430972.

4. The REMP air sampler at Humboldt Hill was found to be not operating on June 1, 2017. The sampler totalizer reading showed only 41 minutes of run time since May 25, 2017. The air filter was counted "For Information Only" and the required beta LLD of 1.0E-02 pCi/m 3 could not be achieved due to the small sample volume of 82 cubic feet. An evaluation was made based on analysis results from two onsite REMP air samplers (Relay Building and OWS) for the 7-day time frame that a radiological release did not occur during the time in question. This was documented in corrective action SAPN 1430964.

5. AC power to the REMP air sampler at the OWS (AM5) was discovered to be off on June 8, 2017. It was later determined the sampler receives power from Lift Station 3, which had been powered down for maintenance activities. Drawings failed to show the electrical connection between the lift station and the air sampler. Temporary generator power was used to power the air sampler until line power could be restored . This was documented in corrective action SAPN 1431460.

6. On July 13, 2017, the REMP air sampler at Building 12 was found to be running , but not drawing air through the air filter. The sample pump suffered broken internal vanes , causing air flow through the sample filter head to stop. The sample filter was analyzed for gross alpha and gross beta, but results were considered "For Information Only." Because the length of air flow time could not be determined with any accuracy, the sample results are not included in this REMP report.

Table C-5 Notes, continued Routine job coverage air samplers located at the U-3 West Caisson Demo and the U-3 North Caisson Demo were used as an evaluation tool to estimate results for the Building 12 air sampler. The gross alpha and gross beta analysis results fo r the 2 air samplers are in the normal range of REMP samplers and meet the detection requirements of the ODCM ,

thus indicating there was no radiological concern due to the inoperability of the Building 12 air sampler. This was documented in corrective action SAPN 1432351 .

7. An electrical outage was planned for September 1, 2017, which was not a regular work day. The outage affected the REMP sampler at both the Annex and Building 12. The Annex sampler was powered by a small generator, but the Building 12 air sampler lost power for the duration of the outage. No other outside work was planned , thereby avoiding the risk of a rad iological release . Totalizer readings from the sample pumps were used to determine sample volumes . This was documented in corrective action SAPN 1434019.

8. A planned power outage on September 28, 2017 , affected the REMP air sampler at the Annex (AM3) . No airborne generating work was scheduled concurrent with the electrical outage (4:30 p.m. on the day before a 4-day weekend) and the outage duration was short lived (2 to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ) . The incident was documented in corrective action SAPN 1434996.

9. The Building 12 REMP air sampler (AM2) lost power for approximately 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months on October 20, 2017. The sampler received electrical power from the 12-series trailers . With the demobilization of the trailers , the source of electricity was also removed from the sample pump. Power to the REMP sampler was temporarily rerouted . The incident was documented in corrective action SAPN 1436302.

10. At approximately 4 a.m. on November 13, 2017, Building 6 (Annex -AM3) suffered an electrical power outage which was assumed to be weather related . The power outage also affected the REMP air sampler outside the Annex. There were no active excavations that could generate airborne radioactivity at the time of the power outage. The incident was documented in corrective action SAPN 1436694.

11 . On November 17, 2017, the Humboldt Hill REMP air sampler was found to be not operating and required a reset of the ground fault circuit interrupter.

A totalizer reading of only 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months was noted. Due to the short run time ,

extended count times were performed for both gross alpha and gross beta activity. The gross beta MDA of 1.0E-02 pCi/L could not be achieved.

This was documented in corrective action SAPN 1436695.

Table C-5 Notes, continued

12. On December 19, 2017, the OWS REMP air sampler (AM5) was turned off for approximately 90 minutes. The sampler receives electrical power from the same feed as Lift Station 3, which was powered down briefly for maintenance activities. The Relay Building REMP air sampler is in close proximity to the OWS air sampler. If a radiological airborne event had occurred within the vicinity of the OWS air sampler, the Relay Building sampler should have captured the activity. The incident was documented in corrective action SAPN 1437846.

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

14. All LLDs were met for gross beta (required LLD 1.0E-02 pCi/m 3) except for three gross beta air sample analyses. The required LLD could not be met due to pump malfunction and short run times.

15. All samples reported as less than MDA represent results that had no identified gamma peaks .

16. 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 . OWS is also known as AM5 .

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

Number Easting* Northing* el.* East* North*

East Fence 5949519 2161209 20.68 5384 9300 AM1 Bldg 12 5949091 2161143 33.05 4989 9476 AM2 Annex Bldg 5949178 2160817 11 .29 4885 9155 AM3 Relay Bldg 5949456 2160858 11.18 5141 9039 AM4 ows 5949576 2160969 11 .94 5302 9067 AM5 Figure A-1 Note:

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

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

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

- - -= = - -. ~ --=- -=--=- -~ :-

- ;:- :s: -- - =--~ T-1 0 -

T-8 ~ -=- .*

- T-9 =._- -

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. - - -*--- - - ...:..:: 150 NOTE:

CA.ZONE 1 / NAD83 NAVD88 HBPP ONSITE TLD LOCATIONS Monitoring Locations T7 , T10 , 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 represenfinq no rth an d movinq

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

Easting Northing Elevation T1 5949179 2160815 11 T2 5948753 2160690 11 T3 5948610 2161062 42 T4 5948779 2161270 44 T5 5949003 2161368 38 T6 5949160 2161437 36 T7 5949280 2161495 32 T8 5949147 2161564 21 T9 5949678 2161626 14 T10 5949913 2161634 11 T11 5950012 2161298 14 T12 5950019 2160858 11 T13 5949842 2160718 10 T14 5949584 2160684 10 T15 5949473 2160590, 11 T16 5949327 2160643 11 FIGURE A-4 HBPP OFFSITE TLD LOCATIONS Stations (1, 14 & 25)

GP S Coordinates (NAD83/NAV 088 CA. Zone 1) Degree. Decimal 0 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)

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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 I -124.15746 FIGURE A-4 (Continued)

HBPP OFFSITE TLD LOCATION EUREKA (Control Location T17)

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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 ICET JQ NCIIBIIPG PJ 1!

y-IM/llf' 1IIIJE

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FIGURE 8-1 OFFSITE ENVIRONMENTAL RADIATION LEVEL TRENDS 80.0 ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~

70.0 60 .0 50 .0 e

~

E 40 .0 Q)

II) 0 Cl 30 .0

- - King Salmon Pi cnic Area (Station 1)

* Fortuna (Station 2) 20 .0

* South Bay School (Station 14)

- - Humboldt Hill (Station 25) 10.0

- - Myrtletown Substation (St ation T17) 0 .0 -+-----+--+--+----+--+----+---+----+---+-----<>---+--+--+---+----+----+-----<--+--+--+---+----+----+-----<--+--+---+------<

~~~~R~~~~~~~~fe~~~~A~~~~~~~~~~

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

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 8-2 ONSITE ENVIRONMENTAL RADIATION LEVEL TRENDS 70 60 fl 50

,..._ __ ..+,---+---..... ,_.,'

E Q)

~

E 40 Q)

Ill 0

C 30

--* -* Stations Near Radwaste Activities (T5-T8), 1989-2015 20

- Othe r Onsite Stations (Tl-T4, T9-T16). 1989-2015 Radwaste Handling(T8-T10). 2016-201 7 10

~ Other Onsite Stations (Tl-T7 , Tll -Tl6), 2016-2017 0 +------!--+--t--+-----+---+--+-----+---+--+----+--+--+----+--+--+---+-----+---+------!-----+---+------<--+--t--+-----+---+-~

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.