HBL-18-003, Annual Radioactive Effluent Release Report for 2017

Annual Radioactive Effluent Release Report for 2017

ML18087A429
Person / Time
Site:	Humboldt Bay
Issue date:	03/27/2018
From:	Franke J Pacific Gas & Electric Co
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
HBL-18-003
Download: ML18087A429 (18)

Text

Ill Pacific Gas and

~~ Electric Company"-'

Jon A. Franke P.O. Box 56 Vice President Avila Beach, CA93424 Power Generation 805.545.4888 E-Mail: Jon.Franke@pge.com March 27, 2018 PG&E Letter HBL-18-003 10 CFR 50, Appendix I 10 CFR 50.36a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-133, OL-DPR-7 Humboldt Bay Power Plant Unit 3 Annual Radioactive Effluent Release Report for 2017

Reference:

1. PG&E Letter HBL-17-005, Annual Radioactive Effluent Release Report for 2016, dated March 30, 2017

Dear Commissioners and Staff:

The Enclosure contains the Humboldt Bay Power Plant Unit 3 "Annual Radioactive Effluent Release Report," covering the period January 1 through December 31, 2017. This report is required by Appendix B, Section 6.3 of the Humboldt Bay Quality Assurance Plan.

Revision 27 to the "SAFSTOR Offsite Dose Calculation Manual" was not changed during the reporting period and was previously submitted in Reference 1.

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

If you have any questions regarding this submittal, please contact Mr. Philippe Soenen at 805-595-6461.

• Enclosure cc: HBPP Humboldt Distribution cc/enc: John B. Hickman, NRC Project Manager Kriss M. Kennedy, NRC Region IV Administrator

Enclosure PG&E Letter HBL-18-003 PACIFIC GAS AND ELECTRIC COMPANY HUMBOLDT BAY POWER PLANT DOCKET NO. 50-133, LICENSE NO. DPR-7 HUMBOLDT BAY POWER PLANT UNIT 3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1 through December 31, 2017

Enclosure PG&E Letter HBL-18-003 TABLE OF CONTENTS INTRODUCTION ....... ................. .... ... ......... ..... ... ................. .... ... ....... ........... ...... ........ ... 1 I. SUPPLEMENTAL INFORMATION......... .......... ....... ... ........ ......... ............ ............ 2 II. GASEOUS AND LIQUID EFFLUENTS .. ............ ......... .......... ..... .. ...... ...... ............ 5 Table 1 -Gaseous Effluents - Summation of All Releases ........... .. ...... ...... ......... . 6 Table 2A- Gaseous Effluents- Elevated Release - Nuclides Released ..... ..... .. ... 7 Table 2B- Gaseous Effluents- Ground-Level Releases- Nuclides Released ...... 7 Table 3- Liquid Effluents- Summation of All Releases ........... ............... .. ............ 8 Table 4- Liquid Effluents - Nuclides Released ... ...... ... .... .......... ..... ..... ..... .... ...... .. 9 Ill. SOLID RADIOACTIVE WASTE...... ..... ..... ..... ... .. ..... ........... ... .... ....... ...... ............ 10 Table 5- Solid Waste and Irradiated Fuel Shipments ... ... ........... ........ ......... ... ... ... 10 IV. RADIOLOGICAL IMPACT ON MAN ... ...... ...... ....... ... .......... .......... ........ ..... ... .. .... 12 Table 6- Radiation Dose for Maximally Exposed Individuals .. ......... ... ... ...... ... .... 14 V. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM).. ... .. .. 15 VI. CHANGES TO THE PROCESS CONTROL PROGRAM (PCP) ..... .................... 15 VII. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS ................... .. 15 VIII. INOPERABLE EFFLUENT MONITORING INSTRUMENTATION .......... ..... ....... 15 IX. ERRATA .... .... ............ ... ... ...... .... ... ...... ...... .... .... .. .... .......... ..... ......................... .. .. 15

Enclosure PG&E Letter HBL-18-003 INTRODUCTION This report summarizes gaseous and liquid radioactive effluent releases from Humboldt Bay Power Plant (HBPP) Unit 3 for the four quarters of 2017. The report includes calculated potential radiation doses and a comparison with the numerical guidelines of 10 CFR 50, Appendix I, as well as a summary of shipments of solid radioactive waste. The concentrations of plant effluent releases during the reporting period were well below Offsite Dose Calculation Manual (ODCM) limits.

The HBPP Main Plant Stack, a ground level release path, and Stack Particulate Airborne Monitoring System (SPAMS), the real time effluent monitor, were shut down on October 14, 2015, and permanently removed from service to facilitate partial demolition of the Reactor Building. Modular HEPA units are available to monitor potential gaseous effluent pathway.

The information is reported as required by Appendix B, Section 6.3 of the Humboldt Bay Quality Assurance Plan and Section 4.2 of the ODCM, and it is presented in the general format of Regulatory Guide 1.21, Appendix B (except for the topics identified below) .

Meteorology The meteorological data logging system was removed from service in 1967 so the information specified by Regulatory Guide 1.21 is not available. Previous HBPP Annual Radioactive Effluent Release Reports summarized the cumulative joint frequency distribution of wind speed, direction, and atmospheric stability for the period April 1962 through June 1967, when the meteorological data logging system was in service.

Short-lived Nuclides, Iodine and Noble Gasses The Unit was last operated on July 2, 1976. Due to the long decay time since operation, short-lived radionuclides are neither expected nor reported. This includes lodines and noble gases other than Kr-85. During 2008, all of the spent nuclear fuel was transferred from the spent fuel pool to the independent spent fuel storage installation (ISFSI), so there is now no source term for Kr-85.

Air Particulate Filter Composites - Sr-90 and Am-241 No modular HEPA ventilation units were used during the reporting period. No weekly sampling was required for monitoring effluents by the ODCM. Airborne radioactivity samplers were established in the vicinity of the Caisson excavation and samples were collected weekly and evaluated for gross alpha and gross beta to identify any adverse trends. No identifiable alpha or beta airborne radioactivity was identified in these weekly samples above effluent concentration limits of 10 CFR 20, Appendix B. Since no gross alpha or beta result identified an adverse trend, no separate analysis for Sr-90 or Am-241 was warranted.

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Enclosure PG&E Letter HBL-18-003 Gaseous Effluents -Tritium Tritium sampling is not required by the HBPP ODCM. No tritium samples were collected during this reporting period.

Liquid Effluents The last batch discharge of radioactive liquid effluent occurred on December 11, 2013.

Subsequent radioactive liquid effluent batches were transported to US Ecology for offsite disposal under the 10CFR 20.2002 exemption. These shipments, volumes, and activity totals are included in Table 5 of this report.

Average Energy Calculations for the average energy of gaseous releases of fission and activation gases are not required for HBPP.

I. SUPPLEMENTAL INFORMATION A. Regulatory Limits

1. Gaseous Effluents

a. Noble Gas Release Rate Limit Noble gases are no longer an issue since the spent nuclear fuel has been relocated to the ISFSI.

b. Iodine Release Rate Limit Due to the long decay time since the Unit was shut down, the license does not define an iodine release rate limit.

c. Particulate Release Rate Limit The radioactive particulate release rate limit is based on concentration limits from 10 CFR 20, divided by an annual average dispersion factor for the sector with the least favorable atmospheric dispersion. If the total release for a period is determined to be a "less than" value, the limits are based on analytical results obtained in November, 2005, for which the mixture was determined to be 84 percent Cs-137, 11 percent Co-60 and 5 percent Sr-90.

The applicable annual average dispersion factor for incidental releases is 6.59E-3 seconds per cubic meter.

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Enclosure PG&E Letter HBL-18-003

2. Liquid Effluents

a. Concentration Limit Concentration limits for liquid effluent radioactivity released to Humboldt Bay are taken from 10 CFR 20 .

B. Effluent Concentration Limits

1. Gaseous Effluents Effluent Concentration Limits for gaseous effluents are taken from 10 CFR 20 ,

Appendix B, Table 2, Column 1.

2. Liquid Effluents Effluent Concentration Limits for liquid effluents are taken from 10 CFR 20, Appendix B, Table 2, Column 2.

C. Measurements and Approximations of Total Radioactivity

1. Gaseous Effluents - Elevated Release Elevated releases did not occur at HBPP during 2017.

2. Gaseous Effluents- Ground-level Release

a. Fission and Activation Gases Fission and activation gases are no longer an issue since the spent fuel has been relocated to the ISFSI.

b. lodines Due to the long decay time since operation (shutdown July 2, 1976), no detectable releases of radioactive Iodine can be expected. Therefore, neither the Technical Specifications nor the ODCM require that these radionuclides be monitored .

c. Particulates Radioactive particulates released from modular HEPA ventilation units are monitored by continuous sample collection on particulate filters when used. No areas involving elevated airborne radioactivity were identified in 2017, so no modular HEPA ventilation units were used in 2017.

3. Liquid Effluents

a. Batch Releases There were no batch liquid effluent releases during this report period.

b. Continuous Releases There were no continuous liquid effluent releases during this report period.

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Enclosure PG&E Letter HBL-18-003 D. Batch Release Statistics

1. Liquid

a. Number of batch releases.... ... ..... ............................... ..... .... 0

b. Total time period for batch releases .................................... N/A

c. Maximum time period for a batch release .......................... N/A

d. Average time period for a batch release ... ......................... N/A

e. Minimum time period for a batch release .... .. ... ............. ... ... N/A

2. Gaseous

a. Number of batch releases.... .. .................. ..... .. ............... .. .. .. 0

b. Total time period for batch releases ........................... ........ N/A

c. Maximum time period for a batch release .. .. .. ..... .............. . N/A

d. Average time period for a batch release .. .. .... .. .................. N/A

e. Minimum time period for a batch release ........ ................... N/A E. Abnormal Release Statistics

1. Liquid

a. Number of abnormal releases... ........................................... 0

b. Total activity released......... ...... .............. ...... .... ... .. ........... N/A

2. Gaseous

a. Number of abnormal releases...................................... ........ 0

b. Total activity released................ ... ... .......... ....................... N/A 4

Enclosure PG&E Letter HBL-18-003 II. GASEOUS AND LIQUID EFFLUENTS A. Gaseous Effluents Table 1 summarizes the total quantities of radioactive gaseous effluents released.

Section A of Table 1, 2A, and 2B have been omitted as Fission & Activation Gases are neither expected or measured.

Table 2A is for reporting the quantities of each of these nuclides determined to be released from an elevated release point (there are none).

Table 2B presents the quantities of each of the nuclides determined to be released by ground level release points (there are none).

There were no "Batch Mode" gaseous releases during this report period.

B. Liquid Effluents Table 3 summarizes the total quantities of radioactive liquid effluents. Table 4 presents the quantities of each of the nuclides determined to be released.

There were no batch liquid effluent releases during this report period .

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Enclosure PG&E Letter HBL-18-003 TABLE 1 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES First Second Third Fourth Est. Total Units Quarter Quarter Quarter Quarter Error,%

B. Particulates

1. Total release Ci N/A N/A N/A N/A N/A I

2. Average release rate )lCi/sec N/A N/A N/A N/A

3. Percent of applicable limit  % N/A N/A N/A N/A

4. Applicable limit )lCi/cc N/A N/A N/A N/A

5. Gross alpha radioactivity Ci N/A N/A N/A N/A Table Notes:

N/A- There were no Gaseous Effluent Releases during the reporting period.

First Second Third Fourth Units Quarter Quarter Quarter Quarter Stack Release Path  % N/A N/A N/A N/A Incidental Release Path  % N/A N/A N/A N/A No operatmg Modular HEPA un1ts after 6/7/16.

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Enclosure PG&E Letter HBL-18-003 TABLE 2A GASEOUS EFFLUENTS- ELEVATED RELEASE- PARTICULATES CONTINUOUS MODE - NUCLIDES RELEASED Continuous Mode First Second Third Fourth Nuclides Released Unit Quarter Quarter Quarter Quarter Particulates Cobalt-60 Ci N/A N/A N/A N/A Strontium-90 Ci N/A N/A N/A N/A Cesium-137 Ci N/A N/A N/A N/A Am-241 Ci N/A N/A N/A N/A Ci N/A N/A N/A N/A Total for period Table Notes:

N/A- There were no elevated gaseous effluents during the report period.

TABLE 2B GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES NUCLIDES RELEASED Continuous Mode First Second Third Fourth Nuclides Released Unit Quarter Quarter , Quarter Quarter

2. Particulates Cobalt-60 Ci N/A N/A N/A N/A Strontium-90 Ci N/A N/A N/A N/A Cesium-137 Ci N/A N/A N/A N/A Americium-241 Ci N/A N/A N/A N/A Total for period Ci N/A N/A N/A N/A Table Notes:

N/A - There were no ground-level gaseous effluents during the report period.

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Enclosure PG&E Letter HBL-18-003

. TABLE 3 LIQUID EFFLUENTS- SUMMATION OF ALL RELEASES First Second Third Fourth Est. Total Units Quarter Quarter Quarter Quarter Error,%

A Fission & Activation Products

1. Total release (not including Ci N/A N/A N/A N/A N/A tritium, gases, alpha)

2. Average diluted concentration ~-tCilml N/A N/A N/A N/A

3. Percent of applicable limit  % N/A N/A N/A N/A

4. Applicable limit ~-tCilml N/A N/A N/A N/A B. Tritium

1. Total release Ci N/A N/A N/A N/A N/A I

2. Average diluted

~-tCilml N/A N/A N/A *N/A concentration

3. Percent of applicable limit  % N/A N/A N/A N/A

4. Applicable limit ~-tCi/ml N/A N/A N/A N/A C. Gross Alpha Radioactivity

11. Total release Ci N/A N/A N/A N/A N/A D. Volume of waste released Liters N/A N/A N/A N/A N/A (prior to dilution)

IE. Volume of dilution water Liters N/A N/A N/A N/A N/A Table Notes:

There were no batch liquid effluent releases during this report period .

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Enclosure PG&E Letter HBL-18-003 TABLE 4 LIQUID EFFLUENTS - NUCLIDES RELEASED Batch Mode First Second Third Fourth Nuclides Released Unit Quarter Quarter Quarter Quarter Strontium-90 Ci N/A N/A N/A N/A Cesium-137 Ci N/A N/A N/A N/A Cobalt-60 Ci N/A N/A N/A N/A Americium-241 Ci N/A N/A N/A N/A Nickel-63 Ci N/A N/A N/A N/A Tritium Ci N/A N/A N/A N/A Total for period Ci N/A N/A N/A N/A Table Notes:

There were no batch liquid effluent releases during this report period.

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Enclosure PG&E Letter HBL-18-003 Ill. SOLID RADIOACTIVE WASTE Table 5 summarizes the disposal of solid radioactive waste during the report period.

Note: Table reflects all waste shipped from HBPP in the reporting period.

TABLE 5 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Offsite For Burial Or Disposal Estimated Total

1. Type of Waste Unit 12 Month Period Error,%

a. Spent resins, filter sludges, There were no spent resins, filter sludges, evaporator evaporator bottoms, etc. bottoms, etc. shipments during this reporting period.

b. Dry compressible waste, soils, Cubic Meter 2.44E+04 1.00E1 contaminated equipment, etc. (1*2l Ci 1.34E+01 5.60E1

c. Irradiated components, There were no irradiated components, control rods, etc.

control rods, etc. shipments during this reporting period.

d. Other (Processed Waste from Cubic Meter 3.64E+OO 1.00E1 HBPP via processor to burial) (SJ Ci 7.93E-03 5.60E1

2. Estimate of major nuclide Unit Nuclide 12 Month Period composition (by type of waste)

a. Spent resins, filter sludges, There were no spent resins, filter sludges, evaporator evaporator bottoms, etc. bottoms, etc. shipments during this reporting period.

% H-3 6.66E+01

b. Dry compressible waste, soils, contaminated equipment, etc. (2 *3)  % C-14 4.4E-01

% Fe-55 3.2E-01

% Co-60 2.85E+OO

% Ni-63 1.40E+01.

% Cs-137 1.23E+01

% Eu-152 2.76E+OO

% U-238 2.30E-01

% Pu-241 1.10E-01

c. Irradiated components, control There were no irradiated components, control rods, etc.

rods, etc. shipments during this reporting period.

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Enclosure PG&E Letter HBL-18-003 TABLE 5- Continued

2. Estimate of major nuclide Unit Nuclide 12 Month Period composition (by type of waste)

d. Other (processed waste- activated  % H-3 2 .54E+01 concrete and instrument check sources)(3, 5)  % Co-60 1.66E+01

% Ni-59 4.13E-01

% Ni-63 5.21E+01

% Cs-137 5.15E+OO

% U-238 1.23E-01 3.a. Solid Waste Disposition from Number of Mode of Destination HBPP Shipments Transportation 391 (4) Truck-US Ecology NCF/MP Truck I Rail -

372 (1)

MP wcs 33 Truck- Hittman Clive 3.b. Solid Waste Disposition via via Toxco to Clive 2 Truck- Hittman processor to disposal (s) orWCS 8 .1 Irradiated Fuel Shipments None N/A N/A Table Notes:

1 Confirmation of the final disposal volume for 29 shipments was not received by year end, but disposal volumes are not expected to change substantially.

2 HBPP no longer performs batch liquid effluent discharges. Volumes and activity totals for liquid shipments are included in Table 5.

3 Radionuclides contributing less than 0.1% to the total activity are not listed in Table 5.2.b and d.

4 391 shipments (including 2 liquid shipments) were made to US Ecology under a 10 CFR 20.2002 exemption.

5 Shipments in 3.b above are primarily activated steel and instrument check sources being prepared by the processor for final disposal. The activity and nuclide distribution is reflected in 1.d. and 2.d.

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Enclosure PG&E Letter HBL-18-003 IV. RADIOLOGICAL IMPACT ON MAN A comparison of calculated doses from various paths has shown that the offsite doses are primarily due to direct radiation. Maximum doses to individuals (for the maximally exposed organs and age groups) are summarized in Table 6. Doses from Noble Gases are not reported, as noble gas releases were neither expected nor measured.

There are no airborne or liquid dose pathways from the adjacent ISFSI, and the direct radiation measurement locations for HBPP include the contribution from the ISFSI.

Therefore, these doses comply with 40 CFR 190 as there are no other uranium fuel cycle facilities within 8 km of the HBPP and ISFSI.

A. Doses to the average individual in the population , based on the guidance of Regulatory Guide 1.1 09, from all receiving-water-related pathways were not calculated for 2017, because there were no batch liquid effluent releases during this report period. The last batch liquid effluent discharge occurred on December 11,2013.

With no batch liquid effluent discharge, doses continue to be well below the 10 CFR 50, Appendix I numerical guidelines for limiting effluents as low as is reasonably achievable (3 mrem/yr to the total body and 10 mrem/yr to any organ).

B. Total body doses to the average individual in the population from gaseous effluents to a distance of 50 miles from the site are not calculated, but this dose is less than the total body dose to an average individual present at the maximally exposed location. For an average individual at the maximally exposed location, the total body dose (determined with the same dispersion and deposition parameters as used to calculate maximum exposure) was not explicitly calculated as there were no releases.

C. Total body doses (to the average individual in unrestricted areas from direct radiation from the facility) are based on thermoluminescent dosimeter (TLD) results of stations at the site boundary, using the shoreline occupancy factors given in Regulatory Guide 1.109 for the highest average potential individual (teenage group). For this group, direct radiation would result in an exposure of 0.1 mrem/yr, calculated as follows :.

Specification 2.10 of the ODCM limits the calendar year dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and radiation, from uranium fuel cycle sources to less than or equal to 25 mrem to the total body or any organ (except the thyroid , which shall be limited to less than or equal to 75 mrem).

Potential direct radiation exposure to an individual at the site boundary is highest at the north boundary of the site. Due to the possibility that an individual at the shoreline (fishing, bird watching , etc.) may use the path along the Coastal Trail, TLD stations T8, T9, and T1 0 along the path are used to estimate an annual radiation exposure. The ODCM calculation model for the direct radiation exposure pathway assumes a maximum occupancy factor of 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> per year, based on regulatory guidance for shoreline recreation for the teenage group.

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Enclosure PG&E Letter HBL-18-003 During 2017, a "haul road" was constructed along the Coastal Trail fence line to allow trucks and transfer equipment access to the two soil management facilities (SMFs) Tents during the Circulating Water line excavation. Direct radiation at T9 has steadily increased during 2017, most likely due to the transportation of radioactive soil and concrete from the caisson to the SMFs, as well as radioactive waste bags and intermodals from the SMFs to the waste management facility for shipment offsite. The increase was noted in the HBPP corrective action program (SAPN 1439150).

Examination of TLD doses for 2017 includes the following :

2017 Average Bkg T8 Average T9 Average T10 Average Quarter (mrem) Dose Dose Dose (mrem) (mrem) (mrem) 2017 01 14.2 14.7 15.1 15.3 2017 02 11.2 11.0 14.6 12.3 2017 03 11.9 11.9 16.1 13.0 2017 04 13.0 13.5 17.8 14.0 Using the maximum quarterly dose as seen on TLDs T8, T9, and T10 from the table:

15.3 + 14.6 + 16.1 + 17.8 =63.8 maximum mrem for the year Total Background dose for the year based on quarterly mean dose from offsite TLDs 1, 2, 14,25 and 17 = 14.2 + 11.2 + 11 .9 + 13.0 = 50.3 mrem Subtracting the yearly background dose from the maximum dose at T8, T9, and T10:

63.8 mrem- 50.3 mrem = 13.5 mrem above background for the year 13.5 mrem corrected to the 67 hour7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> occupancy: 13.5 x 67 hrs I 8760 hrs per yr =

0.1 mrem additional mrem at the fence line.

• This maximum potential dose is well below the 10 CFR 20.1302(b)(2)(ii) limit of 50 mrem/yr from external sources necessary to demonstrate compliance with the 10 CFR 20.1301 dose limit for individual members of the public.

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Enclosure PG&E Letter HBL-18-003 TABLE 6 RADIATION DOSE FOR MAXIMALLY EXPOSED INDIVIDUALS Dose, milli-rem First Second Third Fourth Annual Dose Source Quarter Quarter Quarter Quarter Total Liquid Effluents I Water-related Pathways (1)

Airborne Effluents Particulates (2)

IDirect Radiation (3) <0.01 0.03 0.03 0.04 0.1 Notes

1. Maximum total body and organ doses to individuals in unrestricted areas from receiving-water-related exposure pathways were not calculated as there were no batch liquid effluent releases during this report period. The last batch liquid effluent discharge occurred on December 11, 2013.

2. Maximum total body and organ doses to individuals in unrestricted areas from airborne effluent-related exposure pathways were not calculated as there were no airborne effluent releases during this report period. The plant stack was shut down in October 2015. Modular HEPA ventilation units are available for localized airborne radioactivity control, but were not used during the reporting period because no elevated airborne radioactivity areas were observed.

3. Total body doses (to the maximum individual in the population) are based on TLD results of stations at the site boundary, using the shoreline occupancy factors of Regulatory Guide 1.109 for the maximum potential individual (teenage group).

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Enclosure PG&E Letter HBL-18-003 V. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

As decommissioning proceeds at HBPP, system changes or removal may require changes to the ODCM. No changes were made to the ODCM during the reporting period . ODCM, Revision 27, as previously submitted, remains in effect.

VI. CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

There were no changes to the PCP during the report period.

VI I. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS HBPP no longer performs batch liquid effluent discharges.

VIII. INOPERABLE EFFLUENT MONITORING INSTRUMENTATION Liquid Effluent Monitoring Effective December 23, 2013, HBPP no longer uses outfall canal dilution for liquid effluents. There were no batch liquid effluent releases during this report period.

Airborne Effluent Monitoring Instrumentation No airborne radioactivity areas were identified in 2017. Therefore, no modular HEPA ventilation units were used during the reporting period.

SPAMS was removed from service on October 14, 2015.

IX. ERRATA 2016 Annual Radioactive Effluent Release Report Errata:

None 15